BEGIN:VCALENDAR VERSION:2.0 PRODID:-//CERN//INDICO//EN BEGIN:VEVENT SUMMARY:(WITHDRAWN) Isomeric yield ratio measurements from $^{232}$Th($\\a lpha$\,f) for investigation of the mechanism for angular momentum generati on in fission DTSTART:20220727T144500Z DTEND:20220727T150900Z DTSTAMP:20260420T153400Z UID:indico-contribution-629@indico.frib.msu.edu DESCRIPTION:Speakers: Andreas Solders\, Simone Cannarozzo\, Zhihao Gao\, A li Al-Adili\, Mattias Lantz\, Stephan Pomp (Uppsala University)\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/629/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/629/ END:VEVENT BEGIN:VEVENT SUMMARY:Basics of Nuclear Fission DTSTART:20220722T202000Z DTEND:20220722T212000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1214@indico.frib.msu.edu DESCRIPTION:Speakers: Ramona Vogt (LLNL\, UC Davis)\n\nChair: Marc Verrier e\n\nhttps://indico.frib.msu.edu/event/52/contributions/1214/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1214/ END:VEVENT BEGIN:VEVENT SUMMARY:Machine Learning for Nuclear Data DTSTART:20220722T213000Z DTEND:20220722T223000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1215@indico.frib.msu.edu DESCRIPTION:Speakers: Denise Neudecker\n\nChair: Robert Casperson\n\nhttps ://indico.frib.msu.edu/event/52/contributions/1215/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1215/ END:VEVENT BEGIN:VEVENT SUMMARY:Open discussion DTSTART:20220722T223000Z DTEND:20220722T230000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1216@indico.frib.msu.edu DESCRIPTION:https://indico.frib.msu.edu/event/52/contributions/1216/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1216/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Use of a Kubernetes Cluster of Docker Containers in Au tomating Nuclear Data Quality Assurance DTSTART:20220728T141200Z DTEND:20220728T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-883@indico.frib.msu.edu DESCRIPTION:Speakers: David Brown\, Benjamin Shu (National Nuclear Data Ce nter)\, Rebecca Coles\, Ramon Arcilla (NNDC-BNL)\n\nThe benefits of contai nerized software in the deployment of applications are already well recogn ized and understood in the nuclear data community. In this regard\, this paper describes how we migrated ADVANCE\, NNDC’s continuous nuclear data quality assurance (QA) system\, from the Buildbot CI/CD environment to an on-premise Kubernetes cluster of Docker containers which also serves as o ur new platform for automating the nuclear data pipeline. The new platfor m enabled the integration of NNDC’s GitLab server\, ADVANCE server\, app lications development server and high-performance Linux cluster to provide a powerful environment for ENDF/B library verification and validation. F urther\, the new platform has provided the new ADVANCE system the reliabil ity\, scalability\, security and rapid development and deployment of new f unctionalities essential to the QA process. Future plans on migrating oth er NNDC applications to the new ADVANCE system will also be discussed.\n\n https://indico.frib.msu.edu/event/52/contributions/883/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/883/ END:VEVENT BEGIN:VEVENT SUMMARY:The Neutron Scattering Cross Section and Angular Distribution Meas urement Program at LANL DTSTART:20220728T145000Z DTEND:20220728T151400Z DTSTAMP:20260420T153400Z UID:indico-contribution-827@indico.frib.msu.edu DESCRIPTION:Speakers: J. M. O'Donnell\, Mark Paris\, Eames Bennett\, M. De vlin\, Keegan Kelly (Los Alamos National Laboratory)\n\nhttps://indico.fri b.msu.edu/event/52/contributions/827/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/827/ END:VEVENT BEGIN:VEVENT SUMMARY:Prioritization of nuclear data needs DTSTART:20220729T163000Z DTEND:20220729T170000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1241@indico.frib.msu.edu DESCRIPTION:Speakers: Tim Hallman (DOE)\n\nhttps://indico.frib.msu.edu/eve nt/52/contributions/1241/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1241/ END:VEVENT BEGIN:VEVENT SUMMARY:Improved calculations of Maxwellian-averaged \\textit{n}-capture c ross sections using machine learning for intentional forensics and astroph ysics DTSTART:20220725T170600Z DTEND:20220725T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-768@indico.frib.msu.edu DESCRIPTION:Speakers: Amber Lauer-Coles\n\nThe National Nuclear Data Cente r (NNDC) maintains a repository of physical and theoretical quantities in the Evaluated Nuclear Data Format/B library (ENDF/B)\, currently on the 8t h release (ENDF/B-VIII.0). Many fields rely on the accuracy of these quant ities and their uncertainties\, from real world applications (such as nucl ear power) to more theoretical ones. This work is part of a larger effort by the NNDC to supply nuclear data for Intentional Forensics (IF) applicat ions. The aim of IF is to develop a system for tagging commercially produc ed reactor fuel to alleviate a great security concern to the United States and other nation states and organizations. Apparently unrelated questions concerning the nature of the \\textit{r}-process\, including abundances\, reaction rates\, and astrophysical sites\, remain enigmatic and an extrem ely active field of study. Both of these pursuits rely heavily on neutron capture in stable (but understudied) and unstable nuclei. The NNDC is anal yzing and expanding the available data for these efforts\, based on the EN DF/B-VIII.0 neutron sublibrary\, containing 557 species of long lived isot opes and isomers relevant to neutron applications. \n\nFor both IF and man y astrophysical applications the most relevant nuclear quantities are unme asured (or under measured!)\, and will remain so for some time. Theoretica l estimates are employed with varying levels of success due to assumptions that\, while necessary\, might not be supported by the physics. Current m ethods attempt to connect the cross section to physical quantities such as mass\, level density\, and neutron separation energy in order to identify patterns. These often focus on a single nuclear quantity or bulk property (such as mass model)\, which heavily weights that quantity's importance b y default. As such\, new methods are always of interest. This work is to f irst produce a catalogue of Maxwellian Averaged Cross Sections (MACS) for neutron-capture for the isotopes in the neutron sublibrary and spanning fr om thermal energies to the neutron activation range. From this library we will attempt to improve estimates of neutron capture Maxwellian Averaged C ross Sections\, especially off-stability where few or no measurements exis t. As the neutron fluence in many applications can be treated as a weighte d sum of Maxwellian spectra\, inverse problem theory allows us develop a r egression model for the temperature dependence of the MACS. By applying th e predictive capability of machine learning (ML) we can couple these estim ates to additional physical quantities where known\, to highlight or empha size previously unknown relationships. These results will be provided to t he IF group to inform their efforts. The results will also be implemented in new \\textit{r}-process simulations\, implementing the most up-to-date astrophysical models and nuclear network methods.\n\nhttps://indico.frib.m su.edu/event/52/contributions/768/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/768/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutrons propagation in Lead: a feasibility study for experiments in the RSV TAPIRO fast research reactor DTSTART:20220726T171800Z DTEND:20220726T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-709@indico.frib.msu.edu DESCRIPTION:Speakers: Valentina Fabrizio\, Nunzio Burgio (ENEA)\, Luca Fal coni (ENEA)\n\nThe increasing interest worldwide in Lead-cooled Fast React ors (LFRs) substantiates the need to validate the analytical codes and met hods used to support their design. For neutronic analyses\, this is chiefl y reflected in assessing the impact of nuclear data uncertainties on the i ntegral and local parameters resulting from such analyses. Besides this dr iving interest\, the aim of refining nuclear data moves continuous efforts for more accurate measurements\, be them differential or integral\, for w hich adequate facilities are required.\nA preliminary attempt at adjusting the ENDF/B-VIII.0 neutron data libraries for application to ALFRED – th e demonstration reactor of future European LFRs – provided clear indicat ions on the need to refine the cross-sections of Lead isotopes\, and parti cularly of the elastic and inelastic ones at high energies. However\, expe riments dealing specifically with Lead's neutronics are not frequent in li terature and even scarce in international databases establishing benchmark cases for the validation of neutronic codes or the adjustment of nuclear data libraries. Therefore\, the availability at the ENEA's Casaccia resear ch center of a fast source reactor – RSV TAPIRO – provides a unique op portunity to perform new integral experiments in support of fast reactors\ , including LFRs\, owing to the well-characterized neutron spectrum of the thermal column\, a spacious experimental slot within the biological shie ld of the reactor in the proximity of the RSV TAPIRO's external copper ref lector.\nAccordingly\, a series of experiments has been envisaged\, dealin g with the use of Lead in a reactor\, with the possibility for some of tho se experiments to become benchmark cases of international relevance. The e xperiments concern the propagation of neutrons through blocks of materials representing relevant elements of a reactor core\, and ranging from pure Lead to mixtures reproducing portions of the reflector and shield in LFRs. The paper will be focused on the feasibility study of some of these experi ments\, where Leadand mixture blockswill be inserted in the so-called ther mal column of the RSV TAPIRO reactor and irradiated by the neutron flux em erging from the copper reflector surrounding the reactor core. Despite the name of the experimental opening\, the spectrum of the incident flux is r elative hard\, owing to the almost-pure core fission spectrum.\nThe scope of the feasibility study will include the conceptual design of the blocks\ , moving from representative studies with target LFRs. An in-depth investi gation will be also performed concerning the required instrumentation: app ropriate Neutron detectors and threshold activation foilswill be selecteda iming at characterizing the assembly's neutron flux intensity and energy s pectrum\, so thatthe measured reaction rates and spectral indexes could be used to assess the impact of nuclear data on these parameters\, retrievin g information for ad-hoc adjustments applied to LFRs.\n\nhttps://indico.fr ib.msu.edu/event/52/contributions/709/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/709/ END:VEVENT BEGIN:VEVENT SUMMARY:Am-241 thermal neutron capture cross section and neutron capture r esonance integral from reactor activation and oscillation measurements DTSTART:20220728T133600Z DTEND:20220728T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-816@indico.frib.msu.edu DESCRIPTION:Speakers: Gilles Noguère\, Vladimir Radulović\, Ljudmila Ben edik\, Gašper Žerovnik\n\nIn spent nuclear fuel\, $^{241}$Am is an impor tant contributor to the decay heat and radiotoxicity for cooling times bet ween several decades and a few centuries. Inherent $\\gamma$-ray emission from $^{241}$Am aggravate time-of-flight (TOF) measurements of $^{241}$Am capture cross section. Alternatively\, $^{241}$Am thermal neutron capture cross section and resonance integral may be estimated by analysis of activ ation or pile oscillation measurements. Potentially\, the former may be mo re accurate than the one obtained from TOF measurements. It may thus serve for normalisation of the energy dependent capture yields measured by TOF. \n\nStudies within the framework of the OECD/NEA WPEC SG-41 have shown th at there are significant biases in the derivation of the thermal $^{241}$A m capture cross section from activation measurements with cadmium transmis sion filters using the conventional Westcott method. It was shown that thi s problem can be overcome either by a higher order correction to the Westc ott method or by Monte Carlo calculated correction factors.\n\nNeutron act ivation analysis of $^{241}$Am is comparatively complex. First\, $^{241}$A m cross section contains two resonances below and around the cadmium trans mission filter cut-off energy ($\\sim$ 0.55 eV). Second\, the activation p roduct is produced in both ground and metastable state\, and the latter ha s a much longer half-life (141 a for $^{242m}$Am vs. $\\sim$ 16 h for $^{2 42g}$Am). And finally\, the decay scheme of activation products is relativ ely complicated. $\\gamma$-ray spectrometry of activation products is diff icult due to low $\\gamma$-ray energies and increased $\\gamma$-ray backgr ound from $^{241}$Am fission products and $^{241}$Am itself. Therefore\, t he only realistic option is $\\alpha$-particle spectrometry. $\\alpha$-par ticles originating from $^{242}$Cm\, which is a decay product of $^{242g\, m}$Am\, are measured relative to $\\alpha$-particles originating from $^{2 41}$Am. Due to the much longer half-life of $^{242m}$Am and a relatively s mall branching fraction for its production by neutron capture ($\\sim$ 0.0 9)\, its contribution to the $^{242}$Cm activity is negligible compared to the contribution from $^{242g}$Am for a few years after irradiation. \n\n In contrast\, pile oscillations are performed by introducing a sample cont aining $^{241}$Am into the reactor during operation\, and the resulting de crease in system reactivity is assumed proportional to the neutron capture rate in $^{241}$Am. Compared to activation measurements\, the required am ount of $^{241}$Am in the samples is several orders of magnitudes higher.\ n\nTwo $^{241}$Am samples\, one with and one without cadmium cover\, were irradiated Central Channel (CC) of the TRIGA reactor at Jožef Stefan Inst itute (JSI). The neutron fluence was monitored by reactions $^{59}$Co(n\,$ \\gamma$)\, $^{197}$Au(n\,$\\gamma$) and $^{58}$Ni(n\,p). In addition\, os cillation measurements of two $^{241}$Am samples were performed in the MIN ERVE reactor of CEA Cadarache in the frame of the OSMOSE program.\n\nThe f irst step is to determine the specific reaction rates starting from the me asured detector count rates. In the case of JSI measurements\, the reactio n rates were deduced from $\\alpha$-particle spectrometry ($^{241}$Am) and $\\gamma$-ray spectrometry (other materials). On the other hand\, a C/E c omparison was performed for the oscillation measurements at CEA Cadarache. \n\nPreliminary trends on the $^{241}$Am neutron capture cross section hav e been obtained from the simultaneous analysis of the OSMOSE and JSI resul ts by using a simple approach. The optimization process results in obtaini ng final C/E values close to unity. In the case of the JSI results\, the C d areal density was deduced from the measurements with the monitor sample containing gold. After optimisation\, the discrepancies in the $^{241}$Am cross section are low. Using the corrected cross sections\, the resulting thermal capture cross section and resonance integral are estimated as $\\s igma(E_{th}) = 745$ b and $I_0 = 1560$ b\, respectively. This confirms tha t the $^{241}$Am neutron capture resonance integral in JEFF-3.3 ($I_0 = 18 26$ b) is overestimated.\n\n[1] G. Žerovnik et al.\, ''Systematic effects on cross section data derived from reaction rates in reactor spectra and a re-analysis of $^{241}$Am reactor activation measurements\,'' Nucl. Inst r. Meth. A 877 (2018) 300-313.\n\n[2] G. Žerovnik et al.\, ''Method for A nalysis of Neutron Activation Measurements of Am-241 with Uncertainty Prop agation\,'' Proc. Int. Conf. NENE 2021\, Sept. 6-9\, 2021\, Bled\, Sloveni a\, pp. 1006.1-1006.8.\n\nhttps://indico.frib.msu.edu/event/52/contributio ns/816/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/816/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Data Needs for Space Radiation Transport Calculations DTSTART:20220726T130000Z DTEND:20220726T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-678@indico.frib.msu.edu DESCRIPTION:Speakers: Lawrence Heilbronn (University of Tennessee)\n\nhttp s://indico.frib.msu.edu/event/52/contributions/678/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/678/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurements of fission product masses and isotopic yields from $^ {252}$Cf spontaneous fission at the FRS Ion Catcher DTSTART:20220726T181500Z DTEND:20220726T183900Z DTSTAMP:20260420T153400Z UID:indico-contribution-620@indico.frib.msu.edu DESCRIPTION:Speakers: Yuval Waschitz\, Israel Mardor\, Samuel Ayet San And res\, Daler Amanbayev\, Soenke Beck\, J. Bergmann\, Hans Geissel\, Lizzy G roef\, Timo Dickel\, D. Nichita\, Dimiter Balabanski\, Wolfgang Plass\, N. Kalantar-Nayestanaki\, A. Solders\, Pual Constantin\, Z. Brencic\, Anamar ia Spataru\, S. Pomp\, Ivan Miskun\, G. Stanic\, M. Dehghan\, Christine Ho rnung\, Christoph Scheidenberger\, M. Vencelj\, Erez O. Cohen\, Ali Mollae brahimi\, Jianwei Zhao\, Gabriella Kripko-Koncz\, M. Wasserhess\n\nMeasure ments of independent isotopic fission yields (IIFYs) provide access to the underlying probability distribution of products resulting from fission. T he knowledge of IIFY distributions contributes to our understanding of the nuclear fission process in more depth with respect to mass yield distribu tions. A better understating of the fission process has wide implications\ , including the abundance of elements through nucleosynthesis\, nuclear st ructure and reactions\, and nuclear waste management and safety [1].\n\nWe will present the first results of a novel method for measuring IIFYs of 2 52Cf spontaneous fission (SF) via direct mass measurements [2]\, at the FR S Ion Catcher (FRS-IC) at GSI\, Germany [3]. Fission products were generat ed from a 252Cf source that was installed inside the cryogenic stopping ce ll (CSC) [4]\, and were identified and counted with the multiple-reflectio n time-of-flight mass spectrometer (MR-TOF-MS) [5] of the FRS-IC\, utilizi ng well-established measurement and data analysis methods [6]. The high pe rformance of the MR-TOF-MS can resolve isobars unambiguously\, even with l imited statistics. The non-scanning nature of the MR-TOF-MS ensures minima l relative systematic uncertainties in IIFY amongst fission products.\n\nO ur high-accuracy mass results constitute by themselves new important data\ , as they include first (or first direct) mass measurements at the N≈90 and Z=56-62 region. We compare our results to existing data of indirect me asurements and to the Atomic Mass Evaluation 2020 (AME2020) [7].\nThe anal ysis for extracting IIFYs includes isotope-dependent efficiency correction s for all components of the FRS-IC. In particular\, we applied a self-cons istent technique that takes into account the element- dependent survival e fficiencies in the CSC\, due to chemical reactions with the buffer gas.\n \nOur IFY results\, which cover several tens of fission products in the le ss-accessible high-mass peak down to fission yields at the level of 10-5\, are generally similar to those of the NuDat 2 database [8]. Nevertheless\ , they reveal some structures that are not observed in the database smooth trends.\nThese are the first results of a planned campaign to investigate IIFY distributions of spontaneous fission at the FRS-IC. Upcoming experim ents will extend our results to wider Z and N ranges\, lower fission yield s\, and other spontaneously-fissioning actinides.\n\nReferences:\n[1] Dimi triou\, P.\, Hambsch\, F.-J.\, & Pomp\, S. (2016). Fission Product Yields Data: Current status and perspectives Summary Report of an IAEA Technical Meeting (INDC(NDS)--0713). International Atomic Energy Agency (IAEA)\n[2] Mardor et al.\, EPJ Web of Conferences 239\, 02004 (2020)\n[3] W. R. Plass et al.\, Nucl. Inst. Meth. B 317\, 457 (2013)\n[4] M. Ranjan et al.\, Nuc l. Inst. Meth. A 770\, 87 (2015)\n[5] T. Dickel et al.\, Nucl. Inst. Meth. A 777\, 172 (2015)\n[6] S. Ayet San Andres et al.\, Phys. Rev. C 99\, 064 313 (2019)\n[7] M. Wang et al.\, Chinese Phys. C 45 030003 (2021)\n[8] Nat ional Nuclear Data Center\, information extracted from the NuDat 2 databas e\, https://www.nndc.bnl.gov/nudat2/\n\nhttps://indico.frib.msu.edu/event/ 52/contributions/620/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/620/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the 176Yb(n\,γ) cross-section and its application to nuclear medicine DTSTART:20220725T171800Z DTEND:20220725T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-658@indico.frib.msu.edu DESCRIPTION:Speakers: Francisco García-Infantes (Universidad de Granada\, Granada\, Spain\; European Organization for Nuclear Research (CERN)\, Gen eva\, Switzerland)\, Fernando Arias de Saavedra Alías\, Mario Mastromarco \, Javier Praena Rodríguez\, Ignacio Parras\, Vasilis Vlachoudis\n\nNucle ar medicine has proven to be a much needed medical specialty in order to d iagnose and treat several diseases\, among them\, cardiovascular diseases and cancer\, the first and the second causes of mortality worldwide\, resp ectively [1]. Several international agencies recommend to study of new rou tes and new facilities for producing radioisotopes with application to nuc lear medicine as a complementary option to the conventional ones based on nuclear reactors or dedicated cyclotrons [2\,3\,4]. This has been speciall y pushed in the last years with the development and the availability of hi gh-intensity accelerators and new installations because they allow the pro duction of emergent or new radioisotopes. In addition\, these new installa tions can provide quantities of various radioisotopes at regional level. C ERN’s MEDICIS ISOLDE facility is an excellent example [5].\n\n177Lu is a versatile radioisotope used for therapy and diagnosis (theranostics) of c ancer with good success in gastroenteropancreatic neuroendocrine tumours [ 6]. Currently\, the use of 177Lu is under study for several other tumours with good results [7]. 177Lu is produced in a few nuclear reactors mainly by the neutron capture on 176Lu (direct route). However\, it could be prod uced at high-intensity accelerator-based neutron facilities as IFMIF-DONES by means of the route 176Yb(n\,γ) (indirect route) [8]. In fact\, the pr oduced 177Yb beta-decays to the 177Lu with a half-life of 1.9 h. Although the cross-section of the direct route is higher\, several advantages in th e indirect route have been pointed out:\n\ni) The specific activity is fou r times higher. About 100% of the theoretical specific activity can be ach ieved [9\,10].\nii) The contaminants that remain in the final quantity of the material are much lower.\niii) The undesirable 177mLu (t1/2≈160 d) i s produced in the direct route\, 0.05%\, whereas in the indirect route is less than 10-5 % [11].\n\nThese properties have a direct impact on the qua lity of the diagnosis and the therapy. The higher specific activity allows a much better tumour uptake\; thus\, the dose delivered to the tumour for the same activity is much higher in case of the indirect route\, and in a ddition\, the quality of imaging of the tumour is much better [9\,10].\n\n The energy of the neutrons in accelerator-based neutron facilities is high er than in thermal reactors. Consequently\, experimental data on the 176Yb (n\,γ) cross-section in the eV and keV region are mandatory to accurately calculate the production of 177Lu. At present\, there is no available ex perimental 176Yb(n\,γ) cross-section data for thermal neutron energies up to 3 keV. In addition\, the resonances have not been resolved in the rang e from 3 to 50 keV. \nAn experimental campaign at the n_TOF facility provi des data from the thermal to the resolved resonance region for the first t ime\, resolving the largest resonances in the 176Yb(n\,γ) cross-section. The γ-rays cascade\, with a total energy of 5.24 MeV emitted after each capture reaction in 176Yb\, have been detected using a set of four C6D6 de tectors [12]. The Monte Carlo-based pulse height weighting technique (PWHT ) have been in the analysis [13]. These data will be ready to be used in future evaluations of the 176Yb(n\,γ) cross-section and for the calculati on of 177Lu production in accelerator-based neutron sources as IFMIF-DONES .\nResults of the analysis will be shown with particular attention to the possible confirmation of the 1/v behaviour of between thermal resonance re gion\, where there are not experimental data. Furthermore\, this measureme nt will potentially clarify the existence of resonances which have been ob served in transmission experiments but were not measured in previous captu re measurements.\n\nReferences:\n[1] https://www.euro.who.int/en/health-to pics/noncommunicable-diseases/cancer.\n[2] Nuclear Physics European Collab oration Committee: nuclear physics for medicine. ISBN: 978-2-36873-008-9. http://www.nupecc.org/pub/npmed2014.pdf.\n[3] European Nuclear Society\, T he Medical Isotope Crisis. http://www.euronuclear.org/1-information/news/m edical-isotope-crisis.htm.\n[4] NuPEcc. Long Range Plan 2017 Perspectives in Nuclear Physics. \nhttps://www.esf.org/fileadmin/user_upload/esf/Nupecc -LRP2017.pdf.\n[5] https://medicis.cern/\n[6] K. Kim et al.\, Lu-177-Based Peptide Receptor Radionuclide Therapy for Advanced Neuroendocrine Tumors\ , Nucl Med Mol Imag.\, 2018 Jun\; 52(3): 208–215. https://doi.org/10.10 07/s13139-017-0505-6.\n[7] J. Zhang et al.\, Clin. Nucl. Med.\, January 20 20\, Volume 45\, Issue 1\, p e48-e50. \nhttps://doi.org/10.1097/RLU.000000 0000002655.\n[8] A. Dash et al.\, Production of 177Lu for targeted radionu clide therapy: available options. Nuc. Med. and mol. 1Ima.\, 49(2):85–10 7\, 2015. https://pubmed.ncbi.nlm.nih.gov/26085854/.\n[9] R. Henkelmann\, Thursday\, 28 February 2013\, Lu-177 production with a focus on radiation in the KBA at FRM II\, SAAGAS 24\, TUM Garching https://indico.frm2.tum.de /event/0/attachments/4/14/Henkelmann_177Lu_gek.pdf.\n[10] E. A. M. Ruigrok et al.\, Extensive preclinical evaluation of lutetium-177-labeledPSMA-spe cific tracers for prostate cancer radionuclide therapy\, Eur. J. Nucl. Med . Mol. Imaging\, 2020 Oct 23. 10.1007/s00259-020-05057-6.\n[11] K. M. Ferr eira et al.\, Half-life measurement of the medical radioisotope 177Lu prod uced from the 176Yb(n\,γ) reaction. EPJ Web of Conferences Vol 146\, pag 08002\, EDP Sciences\, 2017. https://doi.org/10.1051/epjconf/201714608002. \n[12] P. F. Mastinu et al.\; New C6D6 detectors: reduced neutron sensitiv ity and improved safety\, (The n_TOF Collaboration)\, CERN-n TOF-PUB-2013- 002 (2013).\n[13] U. Abbondanno\, G. Aerts et al.\, New experimental valid ation of the pulse height weighting technique for capture cross-section me asurements\, https://doi.org/10.1016/j.nima.2003.09.066.\n\nhttps://indico .frib.msu.edu/event/52/contributions/658/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/658/ END:VEVENT BEGIN:VEVENT SUMMARY:Reaction cross sections of prompt-gamma and PET radioisotopes for range verification in proton therapy DTSTART:20220725T192100Z DTEND:20220725T193300Z DTSTAMP:20260420T153400Z UID:indico-contribution-650@indico.frib.msu.edu DESCRIPTION:Speakers: Victor Valladolid Onecha (Universidad Complutense de Madrid)\n\nAlthough protontherapy is advantageous over more traditional r adiotherapy from the point of view of dose delivery and sparing of organs at risk\, its full potential has not been reached yet [1]. A lot of effort is focused on proton range verification techniques to improve dose locali zation. Several of these techniques profit from the secondary emission ind uced by protons to identify the proton range and to estimate the dose depo sited in patients [2]. They include the generation and detection of PET ra dioisotopes\, and the production of prompt gammas (PG) by proton-induced r eactions. It is nonetheless crucial to have reliable cross section values of the more interesting reaction channels. The radiation induced on natura l tissues is not always the most suitable to perform proton range verifica tion. Thus the use of contrast agents that provide an increased induced ra dioactivity near the Bragg peak region has been suggested to improve the r ange verification capabilities [3\,4]. Our studies show several promising candidates. \nWater-18 (H218O) has a great potential as a contrast agent b oth in PET and in PG thanks to the oxygen 18O isotope. As a PET contrast a gent the most interesting reaction channel is the (p\,n) one\, which produ ces 18F\, which is a β⁺ emissor with a halflife of 109 min. The cross s ection values up to 10 MeV are well known because of its medical use as ra diotracer. On the contrary\, the relevant energies in protontherapy amount up to 220 MeV and therefore it is necessary to know the cross section val ues up to this energy. We will report on measurements performed using the 220 MeV cyclotron at the Quirónsalud protontherapy center in Madrid. Samp les were irradiated in the beam at several energies and measured offline u sing a setup based on fast LaBr3(Ce) scintillator detectors coupled to a d igital acquisition system. The results are illustrated in Fig. 1 (left)\, where measurements of an irradiated 100 μl water-18 sample was irradiated at 150 MeV. We will report on the cross section results and on the benchm arking measurements carried out at the 5-MV tandetron accelerator of the C enter for Micro Analysis of Materials (CMAM) [5] in Madrid (Spain). \nPro mpt gamma emission from water-18 also is promising for proton range verifi cation due to the presence of intense\, discrete γ-rays. We have performe d measurements of PG production at low energies at CMAM in the energy rang e 1–10 MeV using a set-up consisting of two pairs of collinear opposed LaBr3(Ce) detectors and a fully digital acquisition system with high-rate capabilities. We will report on results\, shown in Fig. 1 (right)\, which highlight the presence of prompt γ-rays from 18O visible above backgroun d for the irradiation of an admixture of distilled water (93)% and water-1 8 (7%). \n\n\n\n \n\n\n\n\n\n\n\nFigure 1: (Lef) PET activity as a functi on of time for a water-18 sample irradiated at Quirónsalud at 150 MeV. (R ight) PG spectrum at 8.8 MeV measured at CMAM.\n\n Another promising candi date for proton range verification using contrasts is Iodine. It is routin ely used as a contrast agent in several other medical applications. Proto n-induced reactions produce 127mXe with 69-s halflife\, via the (p\,n) cha nnel\, which can be used for online range verification [6]. Since the reac tion cross sections were not known down to the low energies relevant for t he Bragg peak we have performed irradiations in the 4–10 MeV range in th e external microbeam line at CMAM. The measurements made use of the on-lin e setup based on LaBr3(Ce) detectors mentioned above. We will report on th e results and the comparison to model calculations\, which support the via bility of 127I as a contrast agent for proton radiotherapy. Concerning the production of prompt gammas we will report on the measurements carried ou t at CMAM at low energies\, and at the Quirónsalud cyclotron up to 220 Me V proton energies. \n\n[1] Knopf\, A.\, Lomax\, A.\, Phys. Med. Biol. 58 ( 15)\, R131\, 2013.\n[2] H. Paganetti\, Phys. Med. Biol. 57 (11)\, R99\, 20 12.\n[3] L.M. Fraile et al.\, Nucl. Instrum. Methods A 814\, 110–116\, 2 016.\n[4] PRONTO-CM\, 2020. Protontherapy and Nuclear Techniques for Oncol ogy. \n[5] A. Redondo-Cubero et al.\, Eur. Phys. J. Plus\, 136:175\, 2021. \n[6] A. Espinosa Rodriguez et al.\, Radiation Physics and Chemistry 185\, 109485\, 2021.\n\nhttps://indico.frib.msu.edu/event/52/contributions/650/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/650/ END:VEVENT BEGIN:VEVENT SUMMARY:miniBELEN: a modular neutron long counter for (α\,n) reactions DTSTART:20220726T191500Z DTEND:20220726T192700Z DTSTAMP:20260420T153400Z UID:indico-contribution-736@indico.frib.msu.edu DESCRIPTION:Speakers: Jose Manuel Quesada Molina\, Alejandro Algora\, Alva ro Tolosa-Delgado\, Nil Mont i Geli (Universitat Politècnica de Catalunya )\, Jorge Lerendegui\, Emilio Mendoza Cembranos\, Daniel Cano-Ott\, Victor Alcayne\, Max Pallas Solis\, César Domingo-Pardo\, Roberto Santorelli\, J. R. Murias\, Ariel Tarifeño-Saldivia\, Trinitario Martinez\, M. Llanos\ , David Villamarin\, J. Briz\, Alberto Perez de Rada\, Adrian Sanchez\, En rique Nacher\, Javier Balibrea\, A. De Blas\, Joaquin Gomez-Camacho\, Carl os Guerrero\, Sonia Orrigo\, Vicente Pesudo\, Angel Perea\, Olof Tengblad\ , María José García Borge\, Gastón Garcia\, Francisco Calviño\, Silvi a Viñals\, Guillem Cortés\, J. Benito\, Luis Mario Fraile\, Jose Luis Ta in\, Julio Plaza\, Enrique Miguel Gonzalez-Romero\, Roger Garcia\, V. Sán chez-Tembleque\, B. Fernández\n\n**Abstract**\nNeutron production through α-induced nuclear reactions is a key issue in several fields. Specifical ly\, (α\,n) reactions are interesting in nuclear astrophysics as a source of neutrons for the slow neutron capture nucleosynthesis (the s-process) [TAI16] and in the α-particles capture process (the α-process) [WOO92\, BLI17]. Other fields of interest include the neutron-induced background in underground laboratories [BET10]\, which is a crucial issue in low counti ng rate experiments\, and in nuclear facilities such as nuclear reactors a nd particle accelerators [MUR02]. Currently\, evaluated data is available only for a limited number of isotopes and the databases present large disc repancies in some cases.\n\nIn this work we present the miniBELEN detector \, a new modular and transportable neutron counter for (α\,n) reactions. This detector has been developed in the context of a Spanish effort for t he Measurement of Alpha Neutron Yields and spectra (MANY collaboration). T he miniBELEN detector is based on the use of several long 3He-filled propo rtional neutron counters embedded in a modular high density polyethylene m oderator. In order to provide the detector with a response independent of the neutron energy\, namely a flat response\, an innovative design methodo logy has been applied. The method is based on the optimization of the cont ribution of each counter to the total efficiency by using thermal neutron absorbers. This allows to obtain flat responses up to 10 MeV. The experime ntal characterization of miniBELEN using 252Cf neutron sources and results of the commissioning with the measurement of the 27Al(α\,n)30P reaction at Spanish research facilities will be presented. \n\n**Acknowledgments**\ nThis work has been supported by the Spanish Ministerio de Economía y Com petitividad under grants FPA2017-83946-C2-1 & C2-2 and PID2019-104714GB-C2 1 & C22.\n\n**Bibliography**\n[BET10] A. Bettini\, Nucl. Instrum. Methods A 626 - 627 (2010) S64 - S68.\n[BLI17] J. Bliss et al. J. Phys. G.: Nucl. Part. Phys. 44 (2017) 054003\n[MUR02] T. Murata and K. Shibata\, J. Nucl. Sci. Technol. 39 (2002) 76 - 79\n[TAI16] J.L. Tain et al.\, J. Phys.: Conf . Ser. 665 (2016) 012031.\n[WOO92] S.E. Woosley and R.D. Hoffmann\, Astrop hys. J. 395 (1992) 202 - 239\n\nhttps://indico.frib.msu.edu/event/52/contr ibutions/736/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/736/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Combining DICER and DANCE to Obtain Improved Neutron C ross Sections and Resonance Parameters for Very Small Samples DTSTART:20220726T163000Z DTEND:20220726T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-711@indico.frib.msu.edu DESCRIPTION:Speakers: Paul Koehler (LANL)\n\nP. E. Koehler1\, A. Stamatopo ulos1\, E. Bond2\, T. A. Bredeweg2\, A. Couture1\, B. DiGiovine1\, M. E. F assbender2\, A. C. Hayes-Sterbenz3\, G. Keksis2\, A. Matyskin2\, K. Parson s4\, G. Rusev2\, J. Ullmann1\, C. Vermeulen2\n\n1. Physics division\, Los Alamos National Laboratory\, 87545\, NM\, USA\n2. Chemistry division\, Los Alamos National Laboratory\, 87545\, NM\, USA\n3. Theory Division\, Los A lamos National Laboratory\, 87545\, NM\, USA\n4. X-Computational Physics d ivision\, Los Alamos National Laboratory\, 87545\, NM\, USA\n\nCombined me asurement and analysis of neutron total and capture cross sections results in more accurate cross sections and resonance parameters for applications and for testing and improving theory. The results are even more valuable when the apparatus is capable of enhanced resonance spin and parity determ ination. Furthermore\, the ability to make these measurements on very smal l samples extends the capability to a wider range of nuclides. The new Dev ice for Indirect Capture Experiments on Radionuclides (DICER) [1] at the L os Alamos Neutron Science Center (LANSCE) is being developed to make neutr on transmission measurements on very samples. The current 1-mm-diameter co llimation system typically requires samples in the mg range although sampl es as small as about 1 g are possible in exceptional circumstances. Typ ical neutron transmission measurements requires samples in the grams to te ns of grams or more range. DICER will soon be upgraded to a 0.1-mm-diamete r collimation system\, allowing routine measurements on samples in the 100 g range. DICER features a unique\, innovative binocular collimator sys tem which enables simultaneous sample-in and sample-out measurements\, the reby minimizing both the sample size and measurement time. The Detector fo r Advanced Neutron Capture Experiments (DANCE) at LANSCE has for years mea sured neutron capture cross sections for samples in the mg range. DANCE al so has been shown to be an excellent neutron resonance “spin meter” [3 \, 4]. In addition to spin and parity\, each neutron resonance has both a neutron and a gamma width\; hence\, both neutron capture and total cross s ections are needed to fully determine all the parameters for as many reson ances as possible. Because they have a wider range of resonance spins as w ell as typically large cross sections\, odd-A nuclides in particular repre sent a fertile testing ground [3\, 5] for theory as well as a challenge fo r applications [6\, 7]. The combined power of DICER and DANCE will be demo nstrated via new data and combined resonance analysis on 147\,149Sm and 19 1\,193Ir.\n[1] A. Stamatopoulos et al.\, submitted to Nucl. Instrum. Meth. A (2021).\n[2[ A. Stamatopoulos et al.\, submitted to this conference.\n[ 3] P. E. Koehler et al.\, Phys. Rev. Lett. 108\, 142502 (2012).\n[4] S. A. Sheets et al.\, Phys. Rev. C 76\, 064317 (2007).\n[5] P. E. Koehler et al .\, in Compound-Nuclear Reactions\, CNR*18\, editedby J. Escher\, Y. Alhas sid\, L. A. Bernstein\, D. Brown\, C. Frohlich\, P. Talou\, and W. Younes (Springer 2021) p. 187.\n[5] L. C. Leal\, H. Derrien\, M. E. Dunn\, and D. E. Mueller\, “Assessment of Fission Product Cross-Section Data for Burn up Credit Applications”\, ORNL/TM-2005/65.\n[6] N. Leclaire\, I. Duhamel \, and M. Monestier\, in Criticality safety – Pushing Boundaries by mode rnizing and Integration Data\, Methods\, and Regulations\, edited by C. As sociates (American Nuclear Society\, 2017)\, p. 15.\n\nhttps://indico.frib .msu.edu/event/52/contributions/711/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/711/ END:VEVENT BEGIN:VEVENT SUMMARY:Regression analysis of experimental reaction cross-section data of 241Am(n\, 2n)240Am DTSTART:20220727T171200Z DTEND:20220727T171400Z DTSTAMP:20260420T153400Z UID:indico-contribution-1135@indico.frib.msu.edu DESCRIPTION:Speakers: Tejashree Phatak (Vivekanand Education Society's Ins titute Of Technology)\n\n\\documentclass[12pt]{paper}\n%\\usepackage{simpl emargins}\n\n%\\usepackage[square]{natbib}\n\\usepackage{amsmath}\n\\usepa ckage{amsfonts}\n\\usepackage{amssymb}\n\\usepackage{graphicx}\n%\\setleng th\\parindent{0pt}\n\\begin{document}\n\\pagenumbering{gobble}\n\n \\begin {center}\n\\textbf{\\large Regression analysis of experimental reaction\nc ross-section data of $^{241}$\\emph{Am}(n\, 2n)$^{240}$\\emph{Am}}\\\\ \n\ n\\hspace{10pt}\n\n% Author names and affiliations\nTejashree S. Phatak$^1 $\, Jayalekshmi Nair$^2$\, Sangeetha Prasanna Ram$^2$\, Bidyut Roy$^3$ and G Mohanto$^4$ \\\\\n\n\\hspace{10pt}\n\\vspace{-5pt}\n\\renewcommand{\\th efootnote}{\\fnsymbol{footnote}}\n$^1$ Junior Research fellow (BRNS)\\foot note{ Department of atomic Energy and Board of Research in Nuclear Science s (DAE-BRNS)\, Government of India\, through major research project (Sanct ion No. 51/14/07/2019-BRNS/36083)}\,\nV E S Institute of Technology\,\nMum bai 400 074\, India\\\\\n$^2$ Department of Instrumentation\,\nV E S Insti tute of Technology\,\nMumbai 400 074\, India\\\\\n$^3$ Nuclear Physics Div ision\, Bhabha Atomic Research Centre\, Mumbai – 400085\, India \\\\\n \ n\\end{center}\n\\vspace{-15pt}\n\\begin{abstract}\n Pre-processing of experimental nuclear data is very essential in the nuclear data evaluatio n. Nuclear data evaluation is very vital in nuclear science and technology because nuclear data are necessary constituents in numerous applications including the nuclear power plants design\, management of nuclear waste\, radioisotopes production\, research of fusion energy\, materials inspectio ns\, nuclear safeguards\, materials inspections\, nuclear safeguards and m any more. Since the quality and accuracy of these nuclear data sets can af fect the efficiency of their applications\, evaluation of nuclear data is mandatory.\n \\par In the evaluation process \\cite{1}\, experimentally measured data are analyzed and skilfully combined with the predictions of nuclear model calculations\, to obtain the true values of nuclear data. T he excellence of evaluated data depends on the correctness of experimental data and theoretical data. Therefore both these data should not have erro r or uncertainty which is practically not possible. It is certain that unc ertainties can be encountered in the measured quantity of nuclear experime nts because nuclear reactions are a random activity\, and measurements bas ed on detection of the emitted particles from the nuclear reactions are af fected by some statistical fluctuations which are unavoidable. Therefore\, in the evaluation process\, the pre-processing of the experimental data b efore combining it with the theoretical data is essential (Fig \\ref{fig:m y_label}). \\begin{figure}\n \\centering\n \\includegraphics[scale=0 .55]{1.png}\n \\vspace{-10pt}\n \\caption{Block diagram for evaluati on of nuclear data}\n \\label{fig:my_label}\n\\end{figure}\n%\\vspace{- 10pt}\n\\par In this paper\, a pre-processing on nuclear cross-section dat a for nuclear reaction $^{241}$\\emph{Am}(n\, 2n)$^{240}$\\emph{Am} has be en considered. Required experimental data has been acquired from EXFOR \\c ite{2}. As per Fig\\ref{fig:my_label}\, Pre-processing of experimental nuc lear data involves two steps\, one is removal of outlier from data and sec ond one is regression on clean experimental data. Presence of outlier in t he available nuclear data set may affect the analysis of data or the accur acy of the result\, in this paper\, Studentized residual and Standardized residual have been adopted for detection of outliers. After cleaning or re moval of outlier from data\, regression method has been applied on clean e xperimental data.\n\\par Regression is important in pre-processing of expe rimental data\, in nuclear science\, as more than one person performs the same experiment in different parts of different countries\, they may get d ifferent cross section values for the same energy because each experimente r uses different methods or equipment\, such situation may create ambiguit y in the selection of data for future applications. In such cases\, it is essential to make a single cross-section value for same energies. Also exp erimental data usually do not cover the whole range of incident energies t hat are of interest. Therefore\, the predictions of nuclear models are req uired to fill the gaps. Regression analysis is the best tool to overcome a ll these problems. Regression analysis is the most effective method for pr edicting the value based on available evidence. In this paper\, polynomial regression and Gaussian Process Regression (GPR) \\cite{3} have been appl ied to regress the nuclear cross-section data of reaction $^{241}$\\emph{A m}(n\, 2n)$^{240}$\\emph{Am} and also covariance matrix and uncertainty ha ve been calculated using GPR. Among them GPR is found to be giving better result for reaction $^{241}$\\emph{Am}(n\, 2n)$^{240}$\\emph{Am}.\n\\end{a bstract}\n%\\vspace{0.11pt}\n\\vspace{-20pt}\n{\\normalsize\n\\begin{thebi bliography}{}\n\\vspace{-10pt}\n\\bibitem{1}R. Capote\, D. L. Smith and A. Trkov\, \\emph{Nuclear data evaluation methodology including estimates of covariances}\, EPJ Web of Conferences 8 04001 (2010)\,DOI: 10.1051/epjcon f/20100804001.\n\\vspace{-10pt}\n\\bibitem{2}https://www-nds.iaea.org/exfo r/\n\\vspace{-10pt}\n\\bibitem{3}Eric Schulz\, Maarten Speekenbrink\, Andr eas Krause\,\n\\emph{"A tutorial on Gaussian process regression: Modelling \, exploring\, and exploiting functions"}\, Journal of Mathematical Psycho logy\, Volume 85\, 2018\, Pages 1-16\, ISSN 0022-2496.\n\n\\end{thebibliog raphy}\n}\n\\end{document}\n\nhttps://indico.frib.msu.edu/event/52/contrib utions/1135/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1135/ END:VEVENT BEGIN:VEVENT SUMMARY:Multi-Feature Treatment Verification in Particle Therapy DTSTART:20220725T193300Z DTEND:20220725T194500Z DTSTAMP:20260420T153400Z UID:indico-contribution-651@indico.frib.msu.edu DESCRIPTION:Speakers: Toni Kögler (OncoRay – National Center for Radiat ion Research in Oncology)\n\nParticle therapy is a promising and rapidly d eveloping methodology of modern tumor treatment. In order to reach its ful l potential\, however\, it requires detailed verification that the clinica l target volume receives the planned dose while sparing surrounding health y tissues.\n\nAlthough the applicability of in-beam positron emission tomo graphy and prompt gamma rays has already been demonstrated in patients\, r ange verification is not yet part of the clinical routine in particle ther apy. This is due both to the methodological limitations of previous system s\, but also to commercial\, clinical and physical boundary conditions.\n\ nIn pencil beam scanning\, the most advanced particle therapy treatment me thod\, the number of secondary particles available per spot ($\\Delta t =$ 10 to 100 ms) is limited. In order to develop a clinically usable treatme nt verification system\, as much information as possible must be extracted from the secondary radiation field. On the other hand\, the instantaneous fluence rate of secondary particles is high ($5\\cdot10^6$ to $1\\cdot10^ 8$ cm$^{-1}$ s$^{-1}$)\, which challenges modern digital data acquisition systems connected to monolithic inorganic scintillators with typical sizes used in prompt gamma ray verification systems. In order to reduce the loa d on the detectors\, and also with regard to the ever increasing current i ntensities of next generation medical accelerators\, future systems have t o be granular. Multi-Feature Treatment Verification (MFTV) combines and ex tends established methods (prompt gamma-ray imaging\, spectroscopy\, timin g\, etc.) in order to achieve higher reliability and performance. \n\nThis idea was taken up by the NOVO project and expanded by a multi-particle ap proach. The NOVO (A **no**vel and holistic approach to real-time dose **v* *erificati**o**n enabling a new era of radiotherapy for cancer treatment) consortium is a collaboration of medical\, nuclear and detector physicists \, nuclear engineers\, and mathematicians\, and aims at developing a holis tic real-time treatment verification system in particle therapy. In additi on to the development of the multi-particle detector\, the NOVO consortium focuses on the development of crucial elements of a clinical system inclu ding image reconstruction methods\, deterministic predictors\, dose estima tors\, decision making schemes and the determination of neutron and photon production cross-sections of therapy-relevant isotopes in the proton ener gy range of 70 to 230 MeV.\n\nElements of a potential multi-channel MFTV s ystem were characterized in a double time-of-flight experiment at the puls ed photo-neutron source *n*ELBE. The essential properties (time resolution \, light yield\, detection efficiency and pulse shape discrimination) of E J-276 plastic scintillators and novel organic glass scintillators from San dia National Laboratories were determined. Organic glasses are reported to have higher light yield\, improved pulse shape discrimination (PSD) prope rties and faster fall times compared to commercially available plastic sci ntillator materials such as the EJ-276. Therefore\, organic glasses repres ent an interesting alternative to materials currently available in the mar ket. \n\nThe first experimental results show that the time resolution of a $10\\times10\\times200$ mm$^3$ organic glass scintillator read-out at both ends will reach the high demands of such a proposed range verificati on system. Preliminary results show a time resolution of $\\approx$390 ps\ , an energy resolution of $\\approx$ 22 % / 17 % at 340 keV / 1061 keV and a pulse-shape discrimination figure-of-merit greater than 1.03 for separa ting neutrons and $\\gamma$-rays over the entire usable kinetic energy ran ge of *n*ELBE. These properties make organic glasses a promising candidate for an MFTV system.\n\nhttps://indico.frib.msu.edu/event/52/contributions /651/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/651/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Nuclear data needs for the new era of Boron Neutron Ca pture Therapy DTSTART:20220725T195700Z DTEND:20220725T200900Z DTSTAMP:20260420T153400Z UID:indico-contribution-652@indico.frib.msu.edu DESCRIPTION:Speakers: Ignacio Porras (Universidad de Granada (ES))\n\nBoro n Neutron Capture Therapy (BNCT) is facing a renaissance with the developm ent of accelerator-based neutron sources in different countries [1\,2]. Th ese facilities can be placed in hospitals\, overcoming the main barrier in the expansion of this promising therapy\, which up to now has been only p erformed at research reactors. BNCT is the only external radiotherapy opti on which is selective at the cellular level and is delivered in just one d ay\, without any fractioning.\n\nThese new facilities are based on the pro duction of neutrons by means of proton collisions on lithium or berillium targets\, then\, the produced neutron beam is moderated and collimated by a beam shaping assembly (BSA) providing an adequate neutron beam for the p atient treatment. Each BSA must be specifically designed for each combinat ion of proton energy and neutron production target (example in Ref. [3]). This allows to adjust the neutron spectrum in the optimal epithermal energ y region. The spectrum is key in the dose delivered to the patient\, both at the tumor and at the organs at risk. \n\nThere are different nuclear da ta needs for the improvement of the different elements involved in the the rapy. First\, there are different neutron interactions with the most commo n materials of the BSA (especially inelastic scattering processes) that ar e key for optimizing the final spectrum by means of Monte Carlo simulation s. In addition\, the cross sections of other neutron induced reactions of interest for the dosimetry and experimental spectrometry via multiactivati on in the epithermal range are also not well known. Finally\, the dose cal culation at tumor and normal tissues requires accurate (with less than 5% uncertainty) data of the most important reactions leading to energy releas es. In this sense\, the n_TOF collaboration has recently measured the cros s sections of the reactions 14N(n\,p)\, 35Cl(n\,p) and 35Cl(n\,g) of inter est for the determination of the normal tissue absorbed dose\, especially at skin and brain.\n\nIn this contribution other cross sections correspond ing to reactions of interest for BNCT will be mentioned and the current kn owledge on them will be analysed.\n\n[1] A.J. Kreiner et al.\, Present sta tus of Accelerator-Based BNCT\, Rep. Pract. Oncol. Radiother. 21\, 95-101 (2016).\n[2] I. Porras et al.\, Perspectives on Neutron Capture Therapy of Cancer\, in Proceedings of the 15th International Conference on Nuclear R eaction Mechanisms\, edited by F. Cerutti\, A. Ferrari\, T. Kawano\, F. Sa lvat-Pujol\, and P. Talou\, CERN-Proceedings-2019-001 (CERN\, Geneva\, 201 9)\, pp. 295-304.\n[3] P. Torres-Sánchez\, I. Porras\, N. Ramos-Chernenko \, F. Arias de Saavedra and J. Praena\, Optimized beam shaping assembly fo r a 2.1-MeV proton-accelerator-based neutron source for boron neutron capt ure therapy. Sci Rep. 11:7576 (2021) https://doi.org/10.1038/s41598-021-87 305-9\n\nhttps://indico.frib.msu.edu/event/52/contributions/652/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/652/ END:VEVENT BEGIN:VEVENT SUMMARY:New perspectives for neutron capture measurements in the upgraded CERN-n_TOF Facility DTSTART:20220725T170600Z DTEND:20220725T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-758@indico.frib.msu.edu DESCRIPTION:Speakers: Michael Bacak\, Cristian Massimi\, Frank Gunsing\, J avier Balibrea-Correa\, Emilio Mendoza Cembranos\, Alberto Mengoni\, Adria Casanovas\, Carlos Guerrero\, Daniel Cano-Ott\, Jose Antonio Lopez Pavon\ , Victor Alcayne\, Vasilis Vlachoudis\, Elizabeth Musacchio González\, M arta Sabate-Gilarte\, César Domingo Pardo\, Francisco Garcia Infantes\, V ictor Babiano-Suárez\, The n_TOF Collaboration\, Jorge Lerendegui\n\nNeut ron capture cross-section measurements are of great interest for various n uclear data applications\, such as the slow neutron capture (s-) process o f nucleosynthesis in stars\, innovative nuclear technology or medical appl ications. The neutron energy range of interest varies depending on the app lication and\, hence\, pulsed white neutron sources combined with the time -of-flight (TOF) technique are the best suited facilities for these measur ements.\n\nSince 2001\, the high resolution neutron time-of-flight facilit y CERN-n_TOF-EAR1 [1] has provided neutron capture cross sections with an excellent energy resolution and broad energy range up to 1 MeV [2]. In 20 14\, the n_TOF Collaboration built a new vertical beam line\, so-called n_ TOF-EAR2 [3]\, with a flight path of only 20 m\, approximately ten times s horter than the 185 m of n_TOF-EAR1. Given its high instantaneous flux [4] \, this new neutron beam line opened the door to challenging measurements of samples with high activity\, available only in small quantities or with small cross sections [5\, 6\, 7]. \n\nThe n_TOF facility has just underg one in 2021 a major upgrade with the installation of its third generation spallation target that has been designed to optimize the performance of th e two n_TOF time-of-flight lines. This contribution will present the first results of reference capture measurements in the two beam lines of the up graded n_TOF facility. \n\nThe performance and new possibilities for (n\, Ɣ) measurements at n_TOF will be presented and compared with the currentl y most competitive time-of-flight facilities worldwide featuring white neu tron beams. Several key aspects for capture measurements will be discussed \, focusing on the maximum neutron energy limit\, of relevance for astroph ysics and fast reactor applications\, the instantaneous neutron fluence\, which determines the signal to background ratio in the case of radioactive samples\, and the energy resolution. The latter is a key factor for both increasing the signal-to-background ratio and obtaining accurate Resonance Parameters [8]. In particular\, the energy resolution has been clearly im proved for the 20 m long vertical beam line with the new target design\, a ccording to our very preliminary results (see [Fig. 1]) while keeping the remarkably high resolution of the long beamline n_TOF-EAR1 [1]. \n\n**FIGU RE ATTACHED** \n [Fig. 1]: https://drive.google.com/file/d/1G59l4MV5SGlM0Z ARozIr24Tx29qHvEKU/view?usp=sharing\n\n[Fig. 1].- Time-of-flight spectrum of 197Au(n\,Ɣ) measured with C6D6 detectors at n_TOF-EAR2 (measuring pos ition at 19.5 m) with the previous (2015) and the upgraded (2021) spallat ion target. The neutron energy between 200 and 300 eV is displayed.\n\nLas t\, current experimental limitations for capture measurements at CERN n_TO F will be discussed together with some of the on-going detector R&D projec ts that will try to tackle them in the upcoming years [9].\n\n[1] C. Guerr ero et al.\, Performance of the neutron time-of-flight facility n_TOF at C ERN\, Eur. Phys. J. A 49\, 27 (2013).\n[2] G. Aerts et al.\, Neutron capt ure cross section of 232Th measured at the n_TOF facility at CERN in the u nresolved resonance region up to 1 MeV\, Phys. Rev. C 73\, 054610 (2006).\ n[3] C. Weiss et al.\, The new vertical neutron beam line at the CERN n_TO F facility design and outlook on the performance\, Nucl. Inst. and Methods A\, 799\, 90-98 (2015).\n[4] M. Sabaté-Gilarte et al\, High-accuracy det ermination of the neutron flux in the new\nexperimental area n_TOF-EAR2 at CERN\, Eur. Phys. J. A 53\, 10 (2017).\n[5] M. Barbagallo et al.\, 7Be(n\ ,α)4He Reaction and the Cosmological Lithium Problem: Measurement of the Cross Section in a Wide Energy Range at n_TOF at CERN\, Phys. Rev. Lett. 1 17\, 152701 (2016).\n[6] V. Alcayne et al.\, Measurement of the 244Cm capt ure cross sections at both CERN n_TOF experimental areas\, EPJ Web Conf.\, 239\, 01034 (2020).\n[7] Sabaté-Gilarte M. et al\, The 33S(n\,α)30Si cr oss section measurement at n_TOF-EAR2 (CERN): From 0.01 eV to the resonanc e region\, EPJ Web Conf. 146\, 08004 (2017).\n[8] P. Koehler\, Comparison of white neutron sources for nuclear astrophysics experiments using very s mall samples\, Nucl. Inst. and Methods A 460\, 352-361 (2001).\n[9] V. Ba biano-Suárez\, J. Lerendegui-Marco\, et al. Imaging neutron capture cross sections: i-TED proof-of-concept and future prospects based on Machine-Le arning techniques. Eur. Phys. J. A 57\, 197 (2021).\n\nhttps://indico.frib .msu.edu/event/52/contributions/758/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/758/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the $^{35}$Cl radiative neutron capture cross secti on at the n_TOF facility\, CERN DTSTART:20220725T165400Z DTEND:20220725T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-595@indico.frib.msu.edu DESCRIPTION:Speakers: Ignacio Porras\, Tobias Wright\, The n_TOF Collabora tion\, Sam Bennett\n\nThe $^{35}$Cl radiative capture rate is important in a number of applications. The long-lived radionuclide $^{36}$Cl is a by-p roduct of the activation of $^{35}$Cl present in graphite moderated reacto rs both in the fuel cladding and as an impurity in nuclear graphite (< 2 p pm by mass). Reliable predictions of the amount of $^{36}$Cl present in th e large volume of irradiated nuclear graphite waste relies on accurate rea ction cross section data\, essential for its safe disposal [1]. Moreover\, in Boron Neutron Capture Therapy (BNCT)\, currently being considered more widely as a cancer therapy [2]\, accurate knowledge of the dose rate deli vered both to tumours and the surrounding healthy tissue is imperative\; c hlorine has an important role in the dose rate\, especially in brain tissu e [3] where it represents 0.3% by mass. Simulations have indicated that ar ound 11% of the total dose rate relevant to the neutron energy ranges used in BNCT (100 eV - 10 keV) comes from neutron capture on 35Cl. Finally\, $ ^{35}$Cl is one of several ‘minor neutron poisons’ in the astrophysica l s-process\, reducing the efficiency of neutron recycling and is furtherm ore involved in the as yet unknown origin of $^{36}$S [4\, 5]\; accurate c apture cross section data are important in determining the significance of $^{35}$Cl in the s-process and its impact on stellar reaction networks.\n The reaction cross section has been measured twice via the time-of-flight method in the past [6\, 7]\, for which the results of resonance analyses a re discrepant by around 15%\, and evaluations (ENDF/B-VIII.0\, JEFF-3.3\, JENDL-4.0) differ with respect to one another by around 10% in the resonan ce region. The recent AMS measurement of the 30 keV Maxwellian averaged cr oss section is inconsistent with the existing time-of-flight measurements [8].\nWork has been performed to accurately measure the $^{35}$Cl$(n\,\\ga mma$)$^{36}$Cl reaction cross section at the 185m beam-line at the neutron time-of-flight facility (n_TOF) at CERN\, using a C6D6 total energy detec tion setup. We measured thirteen resonances up to a maximum energy of arou nd 50 keV\, limited to the strongest resonances by a prohibitive backgroun d. Preliminary results are in agreement with the results of Reference [6]\ , and the Maxwellian averaged cross section extracted from the data is con sistent with the recent AMS measurement [8]. Our results indicate that the ENDF/BVIII.0 and JEFF-3.3 evaluations (both based on the R-Matrix analysi s of Sayer et al. [9]) underestimate the cross section by around 15%. The experimental procedure\, analysis and results of this measurement shall be presented.\n[1] R. Mills\, Z. Riaz\, A. Banford\, Nuclear Data issues in the calculation of 14C and 36Cl in irradiated graphite\, ENC 2012 Confere nce proceedings.\n[2] International Atomic Energy Agency (IAEA)\, press re lease: https://www.iaea.org/newscenter/news/boron-neutron-capture-therapy- back-in-limelight-after-successful-trials\n[3] R. F. Barth\, M. G. H. Vice nte\, O. K. Harling et al.\, Current status of boron neutron capture thera py of high grade gliomas and recurrent head and neck cancer\, Radiation On cology 7\, 146 (2012).\n[4] H. Schatz\, S. Jaag\, G. Linker\, R. Steininge r\, F. Käppeler\, P. E. Koehler\, S. M. Graff\, and M. Wiescher\, Phys. R ev. C 51\, 379 (1995). 
[5] R. Reifarth\, K. Schwarz\, and F. Käppeler\ , Astrophys. J. 528\, 573 (2000). 
[6] R. L. Macklin\, Phys. Rev. C 29\, 1996 (1984). 
[7] K. H. Guber\, R. O. Sayer\, T. E. Valentine\, L. C. L eal\, R. R. Spencer\, J. A. Harvey\, P. E. Koehler\, and T. Rauscher\, Phy s. Rev. C 65\, 058801 (2002). 
[8] S. Pavetich\, A. Wallner\, M. Martsch ini et al.\, Accelerator mass spectrometry measurement of the reaction $^{ 35}$Cl$(n\,\\gamma$)$^{36}$Cl at keV energies\, Phys. Rev. C 99\, 015801 ( 2019).\n[9] R. O. Sayer\, K. H. Guber\, L. C. Leal et al.\, R-matrix analy sis of Cl neutron cross sections up to 1.2 MeV\, Physical Review C 73\, 04 4603 (2006)\n\nhttps://indico.frib.msu.edu/event/52/contributions/595/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/595/ END:VEVENT BEGIN:VEVENT SUMMARY:Dead-Time correction method with pulse pile-up rejection for neutr on TOF experiments DTSTART:20220727T134800Z DTEND:20220727T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-741@indico.frib.msu.edu DESCRIPTION:Speakers: Atsushi Kimura (Japan Atomic Energy Agency (JP))\n\n In the field of radiation detection using Ge detectors\, pulse pile-up rej ection processing (PUR) is widely used. PUR reduces the distortion of the spectrum shape but it causes further increase of dead time. Many papers ha ve been written on the dead time losses with PUR and methods to correct th e influence [1]\,[2]. The proposed correction methods presuppose that the timing of pulses is random. However\, in neutron time-of-flight (TOF) expe riments\, event rates dramatically change depending on TOF and the presupp osed randomness is not satisfied. Then a new dead time correction method a pplicable for neutron TOF experiments is required.\n\nThe dead-time influe nce in TOF is simulated by using a CAEN v1724 digitizer\, a BNC DB-2 rando m pulse generator\, a BNC PB-5 pulse generator and a clock generator. 1 kH z triggers were produced by the clock generator and fed into the digitizer as a reset signal of a clock counter (dummy of triggers from an accelerat or). With the rate of 70% of the reset signals\, trigger signals delayed b y 12 $\\mu$s were fed into the external trigger input of PB-5 to produce i nput signals. The random pulse generator was used to produce dummy constan t background signals. The produced input and background signals were fed t ogether into the digitizer. The time interval from the reset signal and th e pulse height of the signal for each event were recorded as a list-format ted data. \n\nAn example of the obtained time dependence spectrum is shown in Figure. The constant background rate decreases not only after the even t\, but also before it as well. In the time range from 11.5 $\\mu$s to 12. 25 $\\mu$s\, the constant background rate is recovered. This is because th e digitizer is incapable of discriminating two events in this range and re ports as a single event. The reported signal height indicates the sum of t he deposited energy in the detector of the two events. In the present work \, we refer the time range from 9.5 $\\mu$s to 11.5 $\\mu$s and 12.25 $\\m u$s to 15.2 $\\mu$s as “dead state” and that from 11.5 $\\mu$s to 12.2 5 $\\mu$s as “accidental sum state”.\n\nThe dead time of the digitizer can be calculated in offline data analysis using the list format data. In a normal gamma-ray spectroscopy\, the accidental sum state is not accepta ble\, because single gamma-ray energy is needed. In this case\, the rate o f the dead time\, $P_{dt}(i)$\, is calculated at each TOF channel as follo ws:\n$P_{dt} (i)=(T_{ds} (i)+T_{as} (i))/(N_{shot} \\delta_t )$\nwhere $T_ {ds}(i)$ is the time length of the digitizer being in the dead state\, $T_ {as}(i)$ is that being in the accidental sum state\, $N_{shot}$ is the num ber of the reset signals and $\\delta_t$ is the TOF bin width. On the othe r hand\, in neutron TOF experiments with the pulse height weighting techni que\, the accidental sum state is acceptable if a weighting function of a detector is close to be a linear. (Of course\, its uncertainty should be e stimated.) In this case\, the rate of the dead time is calculated by follo wing equation.\n$P_{dt}(i)=(T_{ds}(i))/(N_{shot} \\delta_t )$\n\nThis dead time correction has been applied to the analysis of the data measured wit h CAEN V1724 digitizers in Beam Line #04 (ANNRI) at J-PARC to deduce neutr on capture cross section.\n\nhttps://indico.frib.msu.edu/event/52/contribu tions/741/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/741/ END:VEVENT BEGIN:VEVENT SUMMARY:A Python-Based Nuclear Data Visualization Package DTSTART:20220727T191200Z DTEND:20220727T192400Z DTSTAMP:20260420T153400Z UID:indico-contribution-878@indico.frib.msu.edu DESCRIPTION:Speakers: Nathan Gibson (Los Alamos National Laboratory)\n\nAc ross the nuclear data pipeline\, it is important to drive improvements in validation and verification. One powerful tool in this process\, for eval uation through applications\, is simply visualizing the data. The ability to visualize nuclear data exists in many forms already\, ranging from the legacy but robust tools in NJOY [1] (PLOTR and VIEWR) to the NEA’s Java -based Nuclear Information System (JANIS) [2] to transport-code-provided v isualization like the MCNP© plotter [3]. While every one of these tools is still useful\, a more modern approach that enables consistent visualiza tion from evaluated data and experimental data sets all the way through ap plication data is warranted.\n \nThe NJOY21 project [4] has prioritized th e development of open source and robust tools to read and write nuclear da ta in a wide number of formats. ENDFtk provides an interface to ENDF form atted data\, ACEtk to ACE data\, and GNDStk to GNDS data. With ENDFtk nea ring completion and ACEtk and GNDStk undergoing rapid development\, each p rovides a Python interface to extract data. With a Python interface to th e data\, a plotting tool simply needs hooks to the widely used plotting pa ckage Matplotlib [5] to create flexible and professional-quality visualiza tions.\n \nA new nuclear data visualization package is thus underway at th e Los Alamos National Laboratory\, with the capability to plot evaluated d ata from ENDF and GNDS files\, interface files such as GENDF and PENDF\, a nd application files including ACE and NDI. This tool also has the flexib ility to plot user-provided data in a variety of simple formats\, used to display\, for instance\, a new proposed evaluation not yet formatted or ex perimental datasets. There is functionality to plot integrated cross sect ions\, angular distributions\, and energy spectra. There is also a conven ient interface for creating comparisons between two curves\, displaying bo th the curves themselves and the difference between them. This visualizat ion package has both a Python API and a YML input file\, allowing flexibil ity for differing workflows and environments. Simply plotting a variety o f datasets from a variety of data sources\, such as shown in Figure 1\, ha s proven to be a very useful tool for nuclear data creators and users at L ANL.\n\n*Figure 1*\nFigure 1. Plot of integrated cross sections from the ENDF/B-VIII.0 evaluation of U-235 taken directly from a variety of file ty pes.\n\nReferences\n1. Macfarlane\, Robert\, Muir\, Douglas W.\, Boicourt\ , R. M.\, Kahler\, III\, Albert Comstock\, & Conlin\, Jeremy Lloyd\, The N JOY Nuclear Data Processing System\, Version 2016. https://doi.org/10.2172 /1338791 \n2. N. Soppera\, M. Bossant\, E. Dupont\, JANIS 4: An Improved V ersion of the NEA Java-based Nuclear Data Information System\, Nuclear Dat a Sheets\, 120\, 294-296\, (2014).\n3. T. Goorley\, M. James\, T. Booth\, F. Brown\, J. Bull\, L. J. Cox\, J. Durkee\, J. Elson\, M. Fensin\, R. A. Forster\, J. Hendricks\, H. G. Hughes\, R. Johns\, B. Kiedrowski\, R. Mart z\, S. Mashnik\, G. McKinney\, D. Pelowitz\, R. Prael\, J. Sweezy\, L. Wat ers\, T. Wilcox & T. Zukaitis\, Initial MCNP6 Release Overview\, Nuclear T echnology\, 180:3\, 298-315\, (2012).\n4. Jeremy Lloyd Conlin\, A.C. Kahle r\, Austin P. McCartney and Daniel A. Rehn\, NJOY21: Next generation nucle ar data processing capabilities\, EPJ Web Conf.\, 146\, 09040\, (2017).\n5 . J. D. Hunter\, Matplotlib: A 2D Graphics Environment\, Computing in Scie nce & Engineering\, vol. 9\, no. 3\, pp. 90-95\, (2007).\n\nLA-UR-21-29494 \n\nhttps://indico.frib.msu.edu/event/52/contributions/878/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/878/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of $^6$Li(n\,t) and $^{235}$(n\,f) with cold neutrons DTSTART:20220727T132400Z DTEND:20220727T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-627@indico.frib.msu.edu DESCRIPTION:Speakers: Elizabeth Mae Scott\, Christopher Haddock\, Elisa Pi rovano\, Jimmy Caylor\, Evan Adamek\, Maynard Dewey\, Pieter Mumm\n\nThe A lpha-Gamma device at the National Institute of Standards and Technology (N IST) utilizes neutron capture on a totally absorbing $^{10}$B deposit to m easure the absolute flux of a monochromatic cold neutron beam to better th an 0.1% precision. Gammas produced by the boron capture are counted using high purity germanium detectors\, which are calibrated using a precisely c haracterized alpha source and the alpha-to-gamma ratio from neutron captur e on a thin $^{10}$B target. This device has been successfully operated an d used to calibrate the neutron flux monitor for a beam-based neutron life time experiment at NIST. Here we will discuss work underway to provide sys temically-distinct measurements of the $^6$Li(n\,t)$^4$He and $^{235}$U(n\ ,f) cross sections with competitive precision.\n\nhttps://indico.frib.msu. edu/event/52/contributions/627/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/627/ END:VEVENT BEGIN:VEVENT SUMMARY:Data Assimilation using Non-invasive Monte Carlo Sensitivity Analy sis of Reactor Kinetics Parameters DTSTART:20220727T134800Z DTEND:20220727T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-990@indico.frib.msu.edu DESCRIPTION:Speakers: Noah Kleedtke (LANL)\n\nLA-UR-21-29561\n\nAbstract\n \n High-fidelity simulation of nuclear systems are paramount to the operat ional success and safety of many nuclear applications. Simulations rely on quality nuclear data. The nuclear data input for these simulations is con tinuously being reassessed by nuclear data evaluators. One way to support this ongoing evaluation is to present the evaluators with detailed analysi s from data assimilation techniques. These techniques examine major source s of nuclear data-induced uncertainties in important nuclear parameters\, such as measures of criticality. In this work\, a data assimilation techni que called the bias factor method will be utilized to improve the predicte d accuracy and precision of the effective neutron multiplication factor do cumented for multiple International Criticality Safety Benchmark Experimen t Project (ICSBEP) benchmarks [1]. This data assimilation technique has be en shown to be successful in reducing nuclear data-induced uncertainty in the effective neutron multiplication factor by researchers at Nagoya Unive rsity [2]. To perform calculations of the bias factor\, one must calculate sensitivity coefficient matrices of a parameter of interest. The paramete rs to be examined in this work include the effective delayed neutron fract ion\, reactivity coefficient\, and prompt neutron decay constant. Monte Ca rlo N-Particle® Code Version 6.21 (MCNP®6.2) will be used in a non-invas ive manner (i.e.\, source code will not be modified) to calculate these se nsitivity coefficients. The calculation of these sensitivity coefficients follows work performed by researchers at TerraPower LLC [3] and Jožef Ste fan Institute [4]. The data will be subsequently used to assist with the o ptimization of an integral experiment for the Experiments Underpinned by C omputational Learning for Improvements in Nuclear Data (EUCLID) project at Los Alamos National Laboratory. By examining the results of the bias fact or method with the three aforementioned parameters\, more certainty can be attributed to the optimal integral experiment providing results that can improve/adjust uncertain or inaccurate nuclear data.\n\n1 MCNP® and Monte Carlo N-Particle® are registered trademarks owned by Triad National Secu rity\, LLC\, manager and operator of Los Alamos National Laboratory. Any t hird party use of such registered marks should be properly attributed to T riad National Security\, LLC\, including the use of the designation as app ropriate. For the purposes of visual clarity\, the registered trademark sy mbol is assumed for all references to MCNP within the remainder of this pa per.\n\nAcknowledgements\n\n Research reported in this publication was sup ported by the U.S. Department of Energy Laboratory Directed Research and D evelopment (LDRD) program at Los Alamos National Laboratory. Los Alamos Na tional Laboratory is operated by Triad National Security\, LLC\, for the N ational Nuclear Security Administration of the US Department of Energy und er Contract No.89233218CNA000001.\n\nReferences\n\n[1] J. D. Bess\, T. I vanova\, L. Scott\, I. Hill\, “The 2019 Edition of the ICSBEP Handbook\, ” Transactions of the American Nuclear Society\, 121\, 901-904 (2019).\n \n[2] T. Endo\, A. Yamamoto\, “Data Assimilation Using Subcritical Measu rement of Prompt Neutron Decay Constant\,” Nuclear Science and Engineeri ng\, 194\, 1089-1104 (2020).\n\n[3] N. Touran\, J. Yang\, “Sensitivities and Uncertainties Due to Nuclear Data in a Traveling Wave Reactor\,” PH YSOR\, Sun Valley\, Idaho\, May 1 – 5 (2016). \n\n[4] I. Kodeli\, “Sen sitivity and uncertainty in the effective delayed neutron fraction (β_eff )\,” Nuclear Instruments and Methods in Physics Research A\, 715\, 70-78 (2013)\n\nhttps://indico.frib.msu.edu/event/52/contributions/990/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/990/ END:VEVENT BEGIN:VEVENT SUMMARY:Langevin approach to fission dynamics with Cassini shape parameter ization DTSTART:20220725T171800Z DTEND:20220725T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-599@indico.frib.msu.edu DESCRIPTION:Speakers: Nicolae Carjan\, Takahiro Wada\, Kazuki Okada\n\nFis sion plays an important role in the study of nuclear data in the actinide region. The dynamical approach to fission using the multi-dimensional Lang evin equation has been widely accepted as a practical method. In this appr oach\, nuclear shapes are expressed with a few shape parameters and the fi ssion process is described as their time evolution by the Langevin equatio n. The shape parameters determine the model space and the calculation resu lts depend critically on them. \n\nThe two-center shell model (TSCM) is a widely used model\, which has five deformation degrees of freedom: elongat ion\, asymmetry of fragment mass\, neck radius\, and deformation of right and left fragments [1]. In many cases\, the neck degree of freedom is not treated as a dynamical variable. TSCM has been successfully applied in the four-dimensional Langevin calculation and provides good agreement with th e experimental data such as fragment mass and kinetic energy distributions [2]. One drawback of TSCM is that only quadrupole deformations of the fra gments are taken into account. On the other hand\, Cassini shape parameter ization can describe the various shapes of deformed nuclei by modifying th e original Cassini oval with the Legendre expansion [3]. The coefficients $\\alpha_i$ of the Legendre polynomial are the shape parameters. It has be en applied in the static approach using the microscopic-macroscopic method to calculate the potential energy of deformation and provided the fragmen t mass and kinetic energy distributions in the actinide and super-heavy nu clear regions [4\, 5]. These studies show that we can select five paramete rs $\\alpha$\, $\\alpha_1$\, $\\alpha_3$\, $\\alpha_4$\, and $\\alpha_6$ a mong many Cassini parameters\, corresponding to elongation\, asymmetry of fragment mass\, asymmetry of fragment shape\, quadrupole deformation of fr agments\, and octupole deformation of fragments\, respectively. However\, its application to the dynamical treatment of fission was not realized. \n \nIn this study\, we apply the Cassini shape parameterization to the dynam ical calculation of fission using the multi-dimensional Langevin equation. We use the three- and the four-dimensional model space to calculate the f ragment mass and kinetic energy distributions. As an example\, we show the results for 14 MeV neutron-induced fission $^{235}$U($n$\, $f$) with thre e- and four-dimensional calculation. As it is well known\, the fragment ma ss distribution is asymmetric with the mass number of the heavy fragment a t the peak position being 136 [6]. It is considered to reflect the magic n umbers ($Z$\, $N$) = (50\, 82). Figure 1 shows the calculated fragment mas s distributions for two cases: three-dimensional case with $\\{\\alpha\,\\ \, \\alpha_1\,\\\, \\alpha_4\\}$ and four-dimensional case with $\\{\\alph a\,\\\, \\alpha_1\,\\\, \\alpha_3\,\\\, \\alpha_4\\}$. By including the sh ape asymmetric degree of freedom $\\alpha_3$\, the peak position moves fro m 95+141 to 100+136\, which gives a better reproduction to the experimenta l data. The corresponding shapes at scission are shown at the top of Fig. 1. In the three-dimensional calculation\, the shape is given by $\\{\\alph a\,\\\, \\alpha_1\,\\\, \\alpha_4\\} =\\{1.0\,\\\,0.076\,\\\,-0.036\\}$\, and in the four-dimensional calculation\, it is given by $\\{\\alpha\,\\\, \\alpha_1\,\\\, \\alpha_3\,\\\, \\alpha_4\\} =\\{1.0\,\\\,0.015\,\\\,-0.0 91\,\\\,-0.013\\}$. It should be noted that the mass asymmetry is determin ed by the combination of $\\alpha_1$ and $\\alpha_3$. In the former case\, two fragments have the same deformation with a slightly prolate shape. In the latter case\, the heavy fragment is almost a sphere and the light one is elongated. It is important to consider not only the mass asymmetry but also the shape asymmetry to study the asymmetric fission as $^{236}$U. We examined the fission of Fm isotope as another example of actinide nuclei. For this element\, it is known that the mass distribution in spontaneous fission changes drastically when we change the number of neutrons\, i.e.\, it is asymmetric for $N$ = 156 and is symmetric for $N$ = 158 [7]. In th e Langevin approach\, we chose $\\alpha_6$ as the fourth degree of freedom \, by which we can describe the super-long and the super-short configurati ons in the symmetric fission. We performed the Langevin calculation at ver y low excitation energy to simulate the spontaneous fission. It has been c onfirmed that the transition from the asymmetric to the symmetric fission occurs at the correct neutron number when we include $\\alpha_6$. \n\nAs a next step\, we plan to extend the Langevin calculation to include five Ca ssini parameters $\\{\\alpha\,\\\, \\alpha_1\,\\\, \\alpha_3\,\\\, \\alpha _4\,\\\, \\alpha_6\\}$. We will apply the five-dimensional calculation in the actinide region and compare the result with that of four-dimensional c ases. Moreover\, we will extend the system to super-heavy nuclei. It is su ggested from the static approach that five Cassini parameters are necessar y to describe the strongly deformed fragment that may appear in the fissio n of super-heavy nuclei [5]. It is important to confirm the mass and the s hape of the fragment by the dynamical calculation using the Langevin equat ion with five Cassini parameters.\n\n**Reference**\n[1] J. Maruhn and W. G reiner\, Z. Phys. **251**\, 431 (1972).\n[2] M. D. Usang *et al*.\, Phys. Rev C **96**\, 064617 (2017).\n[3] V. V. Pashkevich\, Nucl. Phys. A **169* *\, 275 (1971).\n[4] N. Carjan *et al*.\, Nucl. Phys. A **942**\, 97 (2015 ).\n[5] N. Carjan\, F. A. Ivanyuk and Yu. Ts. Oganessian\, Phys. Rev. C ** 99**\, 064606 (2019).\n[6] K. Shibata *et al*.\, J. Nucl. Sci. Technol. ** 48**(1)\, 1-30 (2011).\n[7] D. C. Hoffman *et al*.\, Phys. Rev. C **21**\, 972 (1980).\n\nhttps://indico.frib.msu.edu/event/52/contributions/599/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/599/ END:VEVENT BEGIN:VEVENT SUMMARY:The $^{41}$Ar($n\,\\gamma)^{42}$Ar reaction DTSTART:20220727T144500Z DTEND:20220727T145700Z DTSTAMP:20260420T153400Z UID:indico-contribution-805@indico.frib.msu.edu DESCRIPTION:Speakers: Moshe Tessler\, Rudra N. Sahoo (The Hebrew Universit y of Jerusalem)\, Alex Zylstra\, Ulli Koester\, Michael Paul (The Hebrew U niversity of Jerusalem)\n\nhttps://indico.frib.msu.edu/event/52/contributi ons/805/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/805/ END:VEVENT BEGIN:VEVENT SUMMARY:Excitation functions of $^3$He- induced nuclear reactions on natur al copper up to 55 MeV DTSTART:20220727T190000Z DTEND:20220727T191200Z DTSTAMP:20260420T153400Z UID:indico-contribution-813@indico.frib.msu.edu DESCRIPTION:Speakers: Kotaro Nagatsu\, Samer Ali\, Katsuyuki Minegishi\, M ing-Rong Zhang\, Naohiko Otsuka\, Mayeen Khandaker\n\nhttps://indico.frib. msu.edu/event/52/contributions/813/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/813/ END:VEVENT BEGIN:VEVENT SUMMARY:Studying the impact of updated isomeric yield ratios on reactor an tineutrino spectra DTSTART:20220727T150900Z DTEND:20220727T152100Z DTSTAMP:20260420T153400Z UID:indico-contribution-631@indico.frib.msu.edu DESCRIPTION:Speakers: Caroline Sears\, Alejandro Sonzogni\, Elizabeth A. M cCutchan\, Chris Morse\, Cassandra Billings\, Andrea Mattera\n\nIsomeric s tates have been observed in about 150 of the hundreds of isotopes that can be produced in the fission of major actinides. These isomers can be popul ated directly through fission\, and the isomeric yield ratio (IYR) represe nts the relative population of the excited state(s) and the ground state ( GS) independent yield. \n\nDue to the underlying nuclear structure\, the i someric state often undergoes β decay and populates very different states in the daughter nucleus compared to the GS decay. This has important impl ications for decay heat calculations\, as well as for the determination of the reactor antineutrino flux. \n\nThe yields of certain fission products have been shown to play a particularly important role in the calculation of reactor antineutrino spectra with the summation method [1\,2]. However \, an exhaustive study of the impact of IYRs was never reported. Improved IYR determinations could be instrumental in addressing the discrepancy be tween the shape of the predicted and observed antineutrino spectra\, which appears as an excess of experimentally measured antineutrinos between 4 a nd 6 MeV - colloquially known as “the bump” [3]. \n\nA compilation and evaluation of experimental isomeric yields was recently published [4]\, t hat also provided new recommended IYRs for 42 nuclides produced in low-ene rgy neutron-induced fission. In this work\, we present a comprehensive stu dy of the extent to which IYRs affect the antineutrino flux predictions wi th the summation method using two different approaches. First\, we estima ted how the newly published recommended IYRs change the antineutrino spect ra of all major actinides of interest for reactor antineutrino spectra ($^ {235\,238}$U\, $^{239\,241}$Pu). Then we individually looked at the contri bution of each fission product with a known isomer\, and studied how a dif ferent IYR value would affect the calculated antineutrino spectra.\n\nA re sult from the first study is shown in Figure 1\, where we present the anti neutrino spectrum with the newly evaluated IYRs shown as the ratio to the one obtained with the unmodified JEFF-3.3 yields [5\,6]. While essentially no effect on the antineutrino spectrum is observed below 5 MeV\, changes on the order of 1%-2% for each fuel type become evident between 5 and 7 Me V. These grow to as much as 30% above 7 MeV. The changes show consistently an increase in the antineutrino yield when the newly evaluated isomeric y ields are used\, compared to the original JEFF-3.3 values.\nIn the second phase of this work\, we performed a sensitivity analysis to identify which IYRs the antineutrino spectrum is most dependent on. This looked beyond t he experimentally determined values from Ref. [4]\, and allowed us to iden tify a number of fission products whose IYR might considerably affect the antineutrino spectrum in proximity to the *bump* region\, and for which no direct yield measurement has been reported to date.\n\nThis work was spon sored by the Office of Nuclear Physics\, Office of Science of the U.S. DOE \, under Contract No. DE-SC0012704\, and supported by the Office of Defens e Nuclear Nonproliferation Research & Development (DNN R&D)\, National Nuc lear Security Administration\, U.S. DOE.\n\nReferences\n\n 1. Sonzogni\, A .A.\, et al. "Effects of Fission Yield Data in the Calculation of Antineut rino Spectra for U-235(n\, fission) at Thermal and Fast Neutron Energies." Phys Rev Lett 116.13 (2016): 132502.\n 2. Sonzogni\, A. A.\, T. D. Johnso n\, and E. A. McCutchan. "Nuclear structure insights into reactor antineut rino spectra." Phys Rev C 91.1 (2015): 011301.\n 3. An\, Feng Peng\, et al . "Measurement of the reactor antineutrino flux\n and spectrum at Daya Bay." Phys Review Lett 116.6 (2016): 061801.\n 4. C.J. Sears\, et al. “C ompilation and Evaluation of Isomeric Fission\n Yield Ratios.” Nucl D ata Sheets 173 (2021): 118.\n 5. Mills\, R.W. "A new UK fission yield eval uation UKFY3.7." EPJ Web of\n Conf Vol. 146 (2017).\n 6. Plompen\, A.J. \, et al. "The joint evaluated fission and fusion\n nuclear data librar y\, JEFF-3.3." Eur Phys Jour A 56.7 (2020): 1.\n\nhttps://indico.frib.msu. edu/event/52/contributions/631/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/631/ END:VEVENT BEGIN:VEVENT SUMMARY:How can a diverse set of integral and semi-integral measurements i nform identification of discrepant nuclear data? DTSTART:20220727T184800Z DTEND:20220727T190000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1003@indico.frib.msu.edu DESCRIPTION:Speakers: Alexander Clark (LANL)\n\n\\noindent Los Alamos Nati onal Laboratory\\\\\nP.O. Box 1663\, MS A143\\\\\nLos Alamos\, New Mexico 87545\\\\\nEmail: \\url{arclark@lanl.gov}\\\\\nLA-UR-21-29584\\\\ \\\\\nNu clear data are widely used by the international community for a variety of applications\, including criticality safety\, reactor performance\, and m aterial safeguards. Despite the breadth of use-cases\, critical benchmarks are primarily used for nuclear data validation\, which are sensitive to s pecific energy regions and nuclides and are unable to uniquely constrain\, for instance\, neutron fission parameters (\\ie the average fission multi plicity\, fission cross section\, and fission spectrum). As a consequence\ , general-purpose nuclear data libraries\, such as \\eviii~\\cite{Brown201 8}\, may have deficiencies that\, while not apparent in criticality applic ations\, negatively impact other applications\, such as non-destructive an alysis of special nuclear material \\cite{Miller2014\, Evans2014}.\n\nRece nt work by the \\underline{E}xperiments \\underline{U}nderpinned by \\unde rline{C}omputational \\underline{L}earning for \\underline{I}mprovements i n Nuclear \\underline{D}ata (EUCLID) project demonstrated \\cite{Neudecker 2020} that machine learning (ML) can effectively augment expert judgment i n identifying discrepant nuclear data. The ML algorithm used random forest s and the SHAP metric to determine which nuclear data contribute most to b ias between measured and simulated \\keffns -eigenvalues. Specifically\, t he authors were able to identify issues\, both known (\\eg ${}^{239}$Pu th ermal and resonance parameters in \\evii) and unknown (\\eg ${}^{19}$F neu tron inelastic scatter cross section from 0.4-0.9 MeV). EUCLID further app lied \\cite{Neudecker2021} the ML algorithm to studying the impact of comb ining critical benchmarks with the LLNL pulsed sphere measurements \\cite{ Wong1972}. Because the pulsed sphere time-of-flight neutron leakage spectr a were sensitive to nuclear data in a different energy regime than compare d to critical benchmarks\, nuclear data for several nuclides could be iden tified as reliable (${}^{1\,2}$H\, ${}^{7}$Li\, ${}^{9}$Be\, ${}^{14}$N\, ${}^{235\, 238}$U\, and ${}^{239}$Pu) or having potential shortcomings (${ }^{6}$Li\, ${}^{12}$C\, ${}^{16}$O\, ${}^{24-26}$Mg\, ${}^{27}$Al\, ${}^{4 8}$Ti\, ${}^{56}$Fe\, and ${}^{208}$Pb).\n\nThis work explores how the div erse set of integral and semi-integral responses\,\n\n\\begin{enumerate}\n \\item Critical benchmarks\,\n\\item pulsed spheres measurements\,\n\\item Beta-effective measurements\,\n\\item Reactivity coefficient measurements \,\n\\item Reaction rate ratio measurements\, and\n\\item Neutron multipli city counting benchmarks\,\n\n\\end{enumerate} \n\n\\noindent are differen tly (or similarly) sensitive to the same nuclear data and discusses how th at adds to understanding shortcomings in nuclear data libraries. The focus will be on how changes between the response sensitivities can potentially inform the ML-based identification of discrepancies in plutonium fission parameters. Future work will extend this analysis to a larger nuclear data set and discuss the impact on nuclear data validation.\n\n\\section*{Ackn owledgments}\n\nResearch reported in this publication was supported by the U.S. Department of Energy LDRD program at Los Alamos National Laboratory. This work was supported by the US Department of Energy through the Los Al amos National Laboratory. Los Alamos National Laboratory is operated by Tr iad National Security\, LLC\, for the National Nuclear Security Administra tion of the US Department of Energy under Contract No. 89233218CNA000001.\ n\nhttps://indico.frib.msu.edu/event/52/contributions/1003/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/1003/ END:VEVENT BEGIN:VEVENT SUMMARY:Decay Data for Radionuclide Monitoring Applications DTSTART:20220728T164000Z DTEND:20220728T170400Z DTSTAMP:20260420T153400Z UID:indico-contribution-660@indico.frib.msu.edu DESCRIPTION:Speakers: Paraskevi Dimitriou (International Atomic Energy Age ncy)\n\nRadionuclide monitoring involves measurements of the concentration s of radioactive particles and noble gases in air\, soil\, and liquid samp les. After collection and appropriate treatment of the samples\, γ and β emissions are measured by means of Ge detectors and β counters\, respect ively. Quantification of such spectra relies heavily on up-to-date evaluat ions of the nuclear structure and decay data of all potential candidate ra dionuclides. R&D work and Monte-Carlo simulations for identification and quantification of radionuclides also depend on a sound knowledge of the in tensities of the γ and β-\, ec/β+ emissions\, along with their equivale nt atomic radiations. \nWe report on an international project coordinated by the International Atomic Energy Agency [1] to improve and update the de cay data for 27 selected long-lived fission products considered to be of h igh priority for worldwide radionuclide monitoring efforts. Half-lives\, a nd emission energies and intensities of the selected radionuclides have be en evaluated and recommended on the basis of a common set of guidelines to produce an adopted decay data set. Both β- and ec/β+ properties were c alculated by means of the BetaShape code [2\,3]\, while atomic radiation d ata have been determined from the BrIccEmis code [4]. A final set of reco mmended data files have been produced in ENSDF format and will be publishe d and made available to laboratories and international bodies such as the Comprehensive Test-Ban Treaty Organisation (CTBTO) involved in the monitor ing of such radionuclides.\n\n[1] Jun Chen\, F. Kondev\, P. Dimitriou\, Im proved Decay Data for Monitoring Applications\, Summary report of the IAEA Technical Meeting\, 24-26 March 2021\, IAEA report INDC(NDS)-0828\, July 2021.\n[2] X. Mougeot\, Reliability of Usual Assumptions in the Calculatio n of β and ν Spectra\, Phys. Rev. C91 (2015) 055504\, 1-12\; DOI: https: //doi.org/10.1103/PhysRevC.91.055504\nErratum\, Phys. Rev. C92 (2015) 0599 02\, 1\; DOI:https://doi.org/10.1103/PhysRevC.92.059902\n[3] X. Mougeot\, Towards High-precision Calculation of Electron Capture Decays\, Appl. Radi at. Isot. 154 (2019) 108884\, 1-8\; DOI: https://doi.org/10.1016/j.apradis o.2019.108884 \n[4] B.P.E. Tee\, T. Kibédi\, B.Q. Lee\, M. Vos\, R. du Ri etz\, A.E. Stuchbery\, Development of a New Database for Auger-electron an d X-ray Spectra\, Proc. Heavy Ion Accelerator Symposium (HIAS2019)\, 9-13 September 2019\, Canberra\, Australia\, editors: A.J. Mitchell\, S. Paveti ch\, D. Koll\, EPJ Web Conf. 232 (2020) 01006\, 1-4\; DOI: https://doi.org /10.1051/epjconf/202023201006\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/660/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/660/ END:VEVENT BEGIN:VEVENT SUMMARY:Validation of the ELECTR module in NJOY DTSTART:20220728T171600Z DTEND:20220728T172800Z DTSTAMP:20260420T153400Z UID:indico-contribution-661@indico.frib.msu.edu DESCRIPTION:Speakers: Ahmed Naceur (École Polytechnique de Montréal)\n\n The NJOY nuclear data processing system is widely used for pointwise and m ultigroup neutronic and photonic cross sections production from Evaluated Nuclear Data Files (ENDF). Current restriction to neutral particles-induce d evaluations limits the scope of the system's mission to applications rel ated to fission and fusion reactor design\, licensing and safety analysis\ , stockpile stewardship modelling\, criticality safety benchmarking\, radi ation shielding and nuclear waste management [1].\nThis paper proposes an extension and demonstration of the system capabilities for electron and po sitron-inducted evaluations in a radiation oncology context. We are propos ing the implementation [2] and the validation of a new ELECTR module in NJ OY with the production of 80-\, 174- and 364-group ENDF/B-VIII.0 [3] libra ries $-$ containing multigroup electroatomic cross sections\, relaxation cascade production\, anisotropic Legendre components of within-group elast ic and group-to-group inelastic scattering matrices\, radiative and collis ional stopping powers\, multigroup momentum transfer coefficients\, energy and charge deposition cross sections\, covering the [100 eV\, 20 MeV] med ical range for elements $Z=1$ (hydrogen) to $Z=100$ (fermium). Total\, lar ge angle elastic ($e\,e$)\, catastrophic inelastic scattering ($e\,2e$) an d bremsstrahlung ($e\,\\gamma e$) cross sections feed the Boltzmann operat ors\, while excitations are labelled soft\, handled by the stopping powers and feed the 1st-order Fokker-Planck operator [4\, 5]. Highly forward-pea ked elastic scattering Legendre expansion is bypassed by the extended tran sport δ correction [6].\nA first implementation of the ELECTR module\, ba sed on the CEPXS feed functions [7]\, was made. Our strategy is *i*) to re place the CEPXS feed functions with those described in the ENDF-102 specif ication report [8\, 9]\; and *ii*) to use EPICS-2017 data [10]. The final version of the ELECTR module with its validation will be presented at the meeting. The upgraded MATXSR post-processing module in NJOY formats each l ibrary in a single stand-alone multigroup dataset that can be accessed by a variety of legacy discrete ordinates and lattice codes including DRAGON- 5 [11]. The produced MATXS file is then recovered by the DRAGON-5 Boltzman n-Fokker-Planck (BFP) discrete ordinate solver [12\, 13]\, where a high-or der diamond differencing (HODD) scheme is used for spatial discretization\ , with a $P_{l\\geq 8}$ Legendre expansion for scattering anisotropy and $ S_{n\\geq 42}$ angular quadrature. Results are compared with the GEANT-4 M onte Carlo (MC) code [14\, 15].\nElectron beam dose distributions and char ge depositions are compared for homogeneous tissue phantoms (water\, corti cal bone\, male soft tissue\, mean adipose\, lung parenchyma\, blood eryth rocytes and skeletal muscle)\, homogeneous slab materials ($_{4}$Be\, $_{6 }$C\, $_{13}$Al\, $_{26}$Fe\, $_{29}$Cu\, $_{32}$Ge\, $_{47}$Ag\, $_{79}$A u\, $_{82}$Pb and $_{92}$U)\, and an upgraded Ahnesjo's tissues stack benc hmark [16]. Ionization\, excitation and bremsstrahlung reaction rates obta ined by DRAGON-5 are compared to GEANT-4 corresponding tallies. Electron c ontamination\, bremsstrahlung spectrums\, angular distributions and yields are produced and compared in a simplified medical LINAC head benchmark. A n optimization of an Intraoperative Electron Radiation Therapy (IOERT) tre atment planning [17] is demonstrated using the same NJOY-DRAGON chain. All computational schemes are uncoupled\, based on the latest EEDL- and EADL (Rev.1)-2017 data [18\, 19] and limited to semi-infinite slabs. Preliminar y results\, based on CEPXS feed functions\, show that\, on average\, in $9 3.6\\%$ of voxels\, discrepancies from MC calculations are lower than the $2\\%$ AAPM (American Association of Physicists in Medicine) Task Group to lerance criteria (Fig.1). \nThe feasibility of a deterministic Boltzmann-F okker-Planck solver for electron beams treatment planning is demonstrated. We therefore anticipate an important role of the new module in systematic quality assurance for particle transport applications supporting nuclear medicine\, brachytherapy\, external radiotherapy and radiosurgery.\n\n\n** References**\n[1] R. MacFarlane\, A. Kahler\, Methods for processing ENDF/ B-VII with NJOY\, Nuclear Data Sheets 111 (12) (2010) 2739–2890.\n[2] A. Hébert\, A. Naceur\, Implementation of the ELECTR in NJOY. 15th Int. Con f. on Nuclear Data for Science and Technology\, Sacramento\,\nCA\, July 24 – 29\, 2022.\n[3] D. A. Brown\, et al.\, ENDF/B-VIII. 0: The 8th major release of the nuclear reaction data library with CIELO-project cross sect ions\, new\nstandards and thermal scattering data\, Nuclear Data Sheets 14 8 (2018) 1–142.\n[4] J. Morel\, Fokker-Planck calculations using standar d discrete ordinates transport codes\, Nuclear Science and Eng. 79 (4) (19 81) 340–356.\n[5] C. Leakeas\, A Generalized Fokker-Planck Theory for El ectron Transport Problems\, PhD dissertation\, The University of Michigan (1999).\n[6] J. Morel\, On the validity of the extended transport cross-se ction correction for low-energy electron transport\, Nuclear Science and E ngineering\n71 (1) (1979) 64–71.\n[7] L. Lorence\, J. Morel\, G. Valdez\ , Physics guide to CEPXS: A multigroup coupled electron-photon cross secti on generating code\, Tech. rep.\, Sandia National Laboratory\, SAND89-1685 (1989).\n[8] V. McLane\, ENDF-102 data formats and procedures for the eva luated nuclear data file ENDF-6\, Tech. rep.\, Brookhaven National Lab. BN L-NCS–44945-01/04-REV. (2001)\n[9] A. Tikov\, M. Herman\, D. Brown\, END F-6 Formats Manual: Data Formats and Procedures for the Evaluated Nuclear Data Files ENDF/B-VI\,\nENDF/B-VII and ENDF/B-VIII\, Tech. rep.\, Brookhav en National Lab\, CSEWG\, BNL-203218-2018-INRE\, Rev.215 (2018).\n[10] D. Cullen\, EPICS-2017: April 2019 Status Report\, Tech. rep.\, Nuclear Data Services\, IAEA-NDS-228 (2019).\n[11] G. Marleau\, A. Hébert\, R. Roy\, A User Guide for DRAGON Version 5\, Institut de génie nucléaire\, Départ ement de génie physique\, École\nPolytechnique de Montréal. Montréal\, QC\, Canada\, Tech. Rep. IGE-335.\n[12] A. Hébert\, C. Bienvenue\, High- order diamond differencing schemes for the Boltzmann Fokker-Planck equatio n in 1D and 2D Cartesian\ngeometries. Submitted to Ann. Nuclear Energy.\n[ 13] C. Bienvenue\, A. Hébert\, High-Order Diamond Differencing Schemes fo r the Boltzmann Fokker-Planck Equation in 3D Cartesian Geometries.\nPHYSOR 2022 – Int. Conf. on Physics of Reactors 2022\, May 15 – 20\, Pittsbu rgh\, PA\, 2022.\n[14] S. Agostinelli\, et al.\, GEANT4—a simulation too lkit\, Nuclear instruments and methods in physics research section A: Acce lerators\, Spectrometers\,\nDetectors and Associated Equipment 506 (3) (20 03) 250–303.\n[15] J. Allison\, K. Amako\, J. Apostolakis\, P. Arce\, M. Asai\, T. Aso\, E. Bagli\, A. Bagulya\, S. Banerjee\, G. Barrand\, et al. \, Recent developments in\nGeant4\, Nuclear Instruments and Methods in Phy sics Research Section A: Accelerators\, Spectrometers\, Detectors and Asso ciated Equipment\n835 (2016) 186–225.\n[16] A. Ahnesjo\, M. M. Aspradaki s\, Dose calculations for external photon beams in radiotherapy\, Physics in Medicine & Biology 44 (11) (1999)\nR99.\n[17] P. Guerra\, J. M. Ud´ıa s\, E. Herranz\, J. A. Santos-Miranda\, J. L. Herraiz\, M. F. Valdivieso\, R. Rodrıguez\, J. A. Calama\, J. Pascau\, F. A. Calvo\,\net al.\, Feasib ility assessment of the interactive use of a Monte Carlo algorithm in trea tment planning for intraoperative electron radiation\ntherapy\, Physics in Medicine & Biology 59 (23) (2014) 7159.\n[18] D. Cullen\, A Survey of Ele ctron Cross Section Data for use in EPICS2017\, Tech. rep.\, Nuclear Data Services\, IAEA-NDS-226 (December\n2017) (2017).\n[19] D. Cullen\, A Surve y of Atomic Binding Energies for use in EPICS2017\, Tech. rep.\, Nuclear D ata Services\, IAEA-NDS-224 (Rev.1\, April\n2018) (2018).\n\nhttps://indic o.frib.msu.edu/event/52/contributions/661/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/661/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron capture cross-section measurements of Mn-53 DTSTART:20220726T165400Z DTEND:20220726T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-691@indico.frib.msu.edu DESCRIPTION:Speakers: Rugard Dressler (Paul Scherrer Institute)\n\nShort-l ived radionuclides\, i.e.\, radioactive isotopes with half-lives less than 100 Ma\, were present in the proto-solar cloud and during the early phase s of the formation of our Solar system. The origin of individual short-liv ed radionuclides is still under debate. Due to the comparatively short hal f-lives\, these isotopes are nowadays not present in cosmic samples\, but are recognizable as enhancements of their decay products e.g. in samples o f meteorites. \nA remarkable case is $^{53}$Mn\, which is expected to be o ne of the most abundant short-lived radioisotopes present in our Galaxy. S ahijpal modelled the general galactic chemical evolution of the stellar cl uster surrounding our Solar system within galactic timescales [1]. It can be efficiently produced and released into the interstellar medium during s upernovae explosions and thus be able to reach our Solar system. The analy sis of deep sea manganese crust samples reveal the presence of layers with enhanced $^{53}$Mn concentrations pointing to the precipitation after clo se-by supernovae explosions [2]. In addition\, it was shown that $^{53}$Mn is continuously deposited on Earth by analyzing 500 kg snow sample from A ntarctica [3] \nDifferent to other short lived isotopes\, $^{53}$Mn can al so be formed in dust that originates from asteroid collisions and comets v ia spallogenic reactions. The estimation of the amounts arriving on Earth and its relation to the originally produced quantity in the supernovae eve nt are still the subject of intensive discussions. Secondary particle reac tions are one of the essential components in this debate. However\, the do minating nuclear reactions in the dust leading to $^{53}$Mn are proton and neutron induced reactions on iron. In such an environment\, one has to co nsider also the follow-up reactions of $^{53}$Mn with these particles\, wh ich could be one of the sources for the observed reduced $^{53}$Mn content . In any case\, the synthesized $^{53}$Mn must pass through regions of hig h neutron densities and therefore undergoes further nuclear reactions that modulate the total content of expelled $^{53}$Mn. One of the possible rea ctions causing such an effect could be neutron capture. \nDue to the rarit y of $^{53}$Mn on Earth – it only occurs in usable quantities in meteori tes – the measurement of nuclear properties is challenging. Therefore\, only the thermal neutron capture cross-section was determined so far using samples containing about 10$^{13}$ atoms of $^{53}$Mn. In the course of t he ERAWAST (Exotic Radionuclides from Accelerator Waste for Science and Te chnology) initiative it was possible to gain a stock of about 10$^{19}$ at oms $^{53}$Mn from proton activated materials at the ring cyclotron at PSI . Parts of this stock were used to fabricate samples to measure neutron ca pture cross-sections of $^{53}$Mn at different neutron facilities. These s amples were used to measure the neutron capture cross-section in a wide ra nge of neutron energies starting from very cold neutron till stellar neutr ons utilizing different neutron facilities [4]. Figure 1 shows an overall plot of all obtained results together with an adopted TALYS calculation an d the normalized used neutron spectra.\nIn the case of using cold and ther mal neutrons\, the results are in good agreement with each other as well a s with reported values of the thermal capture cross-section obtained 50 ye ars ago\, but with an order of magnitude reduced uncertainties. In additio n\, due to the direct determination of the number of atoms in the samples\ , these values do not depend of the half-life of $^{53}$Mn. The resonance integrals and the capture cross-section at very cold and stellar neutron e nergies were measured for the first time.\n\n![Neutron capture cross-secti on measurements of $^{53}$Mn presented in this work. The top panel display s the capture cross-sections (colored points) measured at various faciliti es\, together with the energy interval covering 99% of applied neutrons fl ux indicated as error bars of the energy axis. The gray line represents TA LYS cross-section predictions. The position of the resonances was tuned to reproduce the experimental data\, especially the resonance integral and M ACS. The uncertainty of all measured cross-sections is below 3% (95% confi dence interval) about the size of the gray line. The lower panel shows the normalized neutron spectra of the indicated experimental facilities. The colors correspond to the facilities in booth of the panels.][5]\n\nAcknowl edgment:\nWe would like to thank T. Jenke\, St. Roccia and U. Köster at t he Institut Laue-Langevin (France) for the support conducting experiments at the very cold neutron beam line PF2\; N. Kneip\, D. Studer\, T. Kieck\, and K. Wendt of the Johannes Gutenberg-Universität Mainz (Germany) for p reparing samples using the RISIKO off-line laser mass separation facility for the experiments at the PF2 beam line\; L. Viererbl \,M. Vinš\, H. Ass mann-Vratislavská of the Research Centre Řež (Czech Republic) for condu ction the thermal and epithermal neutron activations at the research react or LRV-15\; O. Aviv\, A. Barak\, Y. Buzaglo\, H. Dafna\, B. Kaizer\, D. Ki jel\, A. Kreisel\, M. Tessler\, L. Weissman\, Z. Yungrais of the Soreq Nat ional Research Center (Israel) for providing the proton beam at the LiLiT Neutron Source at SARAF and support and participating in the experiment at stellar neutron energy\; M. Paul and E. Peretz of Racah Institute of Phys ics at the Hebrew University Jerusalem (Israel) for participating and co-a nalysing the experiment at stellar neutron energy\; as well as the followi ng colleagues of the Paul Scherrer Institut: M. Ayranov and T. Wieseler fo r elaborating the chemical extraction methods and performing the purificat ion to create the stock of $^{53}$Mn\; P. Sprung for determining the total $^{53}$Mn quantities of the used samples via ICP-MS measurements and A. K aestner for support to perform experiments at the cold neutron beam line I CON at the neutron source SINQ at PSI.\n\n[1] S. Sahijpal\, J. Astrophys. Astron. 35 (2014) 121\n[2] G.Korschinek\, et al.: Phys. Rev. Lett.125 (202 0) 031101\n[3] D. Koll\, et al.: Phys. Rev. Lett. 123 (2019) 072701\n[4] J . Ulrich\, PhD thesis 2020\, High precision nuclear data of $^{53}$Mn for astrophysics and geosciences\, University of Berne\, Switzerland\n[5]: htt ps://indico.frib.msu.edu/event/52/contributions/691/attachments/230/1491/1 74_Fig1.png\n\nhttps://indico.frib.msu.edu/event/52/contributions/691/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/691/ END:VEVENT BEGIN:VEVENT SUMMARY:Implementation of the ELECTR module in NJOY DTSTART:20220728T170400Z DTEND:20220728T171600Z DTSTAMP:20260420T153400Z UID:indico-contribution-662@indico.frib.msu.edu DESCRIPTION:Speakers: Alain Hébert (Polytechnique Montréal)\n\n**Abstrac t**\n\nThe ELECTR module of NJOY is designed to produce complete and accur ate multigroup electroatomic cross sections from ENDF/B-IV\, -V -VI or -VI I data[1]. It will also work with the newer formats developed for ENDF/B-V II. ELECTR produces restricted cross sections consistent with a solution o f the multigroup Boltzmann-Fokker-Planck (BFP) equation. Total\, elastic\, inelastic (collision and bremsstrahlung) cross sections can be averaged u sing a variety of group structures and weighting functions. The Legendre c omponents of the within-group elastic and group-to-group inelastic collisi on cross sections are calculated using tabulated data in energy and analyt ic expressions of the angular deviation recovered from the CEPXS code[2]. Here\, we propose an Open-Source implementation of this module\, named ELE CTR in NJOY-2012 and NJOY-2016.[3] ELECTR also computes partial energy dep osition and charge deposition cross sections for each reaction and sum the se partial contributions. The resulting multigroup constants are written o n an intermediate GENDF file for later conversion to any desired format.\n \n**Introduction**\n\nELECTR processes the following electroatomic reactio ns and collision laws from ENDF-102 evaluations:\n\n - the impact electroi onization is a correlated process including the (e\,2e) inelastic collisio n differential cross section and relaxation production. Electrons scatter inelastically from the atomic electrons ejecting them from the $i-$th atom ic shell with considerable kinetic energy. If $i\\le 5$ ($K$\, $L$ or $M$ shells)\, and if the atom is heavy\, there is a production of additional r elaxation radiation consisting of *Auger electrons* and *fluorescence phot ons*. These are produced in a cascade of shell transitions induced by the initial electron vacancy.\n - the bremsstrahlung differential cross sectio n. The bremsstrahlung process takes place when initial electron pass near atomic nuclei and inelastic radiative interaction occurs.\n - the elastic collision differential cross section where the energy of the incident elec tron is conserved by the interaction. We consider the *large angle elastic cross section* (MT=525) corresponding to a deviation cosine with $-1 \\le \\mu \\le 0.999999$. Forward peaked elastic scattering is further removed from the multigroup BFP equation using a *transport correction*.\n - the *microscopic stopping power* $s(E)$ is the average rate at which the elect rons lose energy at any point along their tracks\, according to\n \\begin {equation}\n s(E)= -{1\\over N}{dE \\over dx}\n \\end{equation}\nwher e $N$ is the number of atoms per unit volume.\n\nThe stopping power repres ents components of atomic excitation\, inelastic collision and bremsstrahl ung processes. The stopping power is evaluated data\, in units of Mev-barn \, formally defined by the relation\n \\begin{equation}\n s(E)=\\int_ {0^+}^E dE' \\\, (E-E')\\\, \\sigma(E\\rightarrow E')\n \\end{equation}\n keeping in mind that $\\sigma(E\\rightarrow 0)$ or $\\sigma(E\\rightarrow E)$ may diverge. According to Ref [2]\, the lower energy limit must be set to $E/2$ for the collisional stopping power:\n \\begin{equation}\n s ^{\\rm col}(E)=\\int_{E/2}^E dE' \\\, (E-E')\\\,\n \\sigma_{\\rm col}( E\\rightarrow E') \\ .\n \\end{equation}\n\n - the energy and charge depo sition cross sections are generated.\n\nThe electroatomic reactions are re presented in ENDF-102 format with the MT numbers of Table 1. All reactions except 525 are written in restricted multigroup form on the GENDF tape. R eaction 525 is written in transport-corrected multigroup form. Restricted stopping powers are used to represent soft collisions in the Fokker-Planck operator. The excitation cross section representing a slowing down proces s through the electronic field of an atom (MT=528) is assumed to be soft. Other catastrophic reactions are used in the usual way. The soft componen t of the collisional and radiative stopping powers at group boundaries are written on the GENDF tape as MT=507 and MT=508.\n\nScattering laws of typ e LAW $=1$ for collision/ionization inelastic and bremsstrahlung reactions are stored in TAB2 records similar to those used for neutron-induced reac tions in module GROUPR where tab1io data structures are replaced by listio data structures. The subroutine eetsed returns the secondary-energy distr ibution for electrons for all groups simultaneously\, using an implementat ion similar to subroutines getsed of module GROUPR.\n\n**Table 1: Types of electroatomic material numbers**\nMT number: Class of data \\\\\n507: C ollisional stopping power\n508: Radiative (bremsstrahlung) stopping power \n501: Total\n525: Large angle elastic collision\n527: Bremsstrahlung\n 534-572: Impact electroionization and relaxation production\n530: Energy deposition by electrons\n531: Charge deposition by electrons\n\n**Referen ces**\n\n[1] R. W. Roussin\, J. R. Knight\, J. H. Hubbell\, and R. J. Howe rton\, ``Description of the DLC-99/HUGO Package of Photon Interaction Data in ENDF/B-V Format\,'' Oak Ridge National Laboratory report ORNL/RSIC-46 (ENDF-335) (December 1983).\n\n[2] L. J. Lorence\, Jr.\, J. E. Morel and G . D. Valdez\, ``Physics Guide to CEPXS: A Multigroup Coupled Electron-Phot on Cross-Section Generating Code\, Version 1.0\,'' Sandia report SAND89-16 85 (October 1989).\n\n[3] R. E. MacFarlane and A. C. Kahler\, ``Methods fo r Processing ENDF/B-VII with NJOY\," *Nuclear Data Sheets*\, **111**\, 273 9 (2010).\n\nhttps://indico.frib.msu.edu/event/52/contributions/662/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/662/ END:VEVENT BEGIN:VEVENT SUMMARY:Decay Data Evaluation Project: Updating the evaluations of nuclear decay data and their importance in radionuclide metrology DTSTART:20220728T172800Z DTEND:20220728T174000Z DTSTAMP:20260420T153400Z UID:indico-contribution-664@indico.frib.msu.edu DESCRIPTION:Speakers: Xavier Mougeot (CEA)\, Aurelian Luca (IFIN-HH)\n\nRe liable and precise nuclear decay data are essential in many applications. In radionuclide metrology\, decay data are input parameters in calculation s related to radioactivity measurements\, when absolute or relative standa rdisation methods are used. This is why the metrology community\, especial ly in Europe\, has carefully evaluated decay schemes and atomic and nuclea r data for the last 50 years.\nThis paper presents the results obtained re cently concerning the update of the nuclear decay data evaluations of a nu mber of radionuclides of interest for nuclear medicine: ${^{52}}Mn$\, ${^{ 52m}}Mn$\, ${^{226}}Th$ and ${^{230}}U$. The initial evaluations were prod uced in the framework of the IAEA CRP F41029 “Nuclear Data for Charged-p article Monitor Reactions and Medical Isotope Production” (2012-2018) $^ {1\,2\,3\,4}$. The work was undertaken using the procedures and tools of t he Decay Data Evaluation Project (DDEP)\, an international co-operation of ficially founded 25 years ago $^{5}$. New developments in this field have recently become available. For example\, the new Atomic Mass Evaluation (A ME 2020) $^6$ has enabled updated decay energies (*Q*-values) to be includ ed\, which influence the beta endpoint energies in the decay schemes\, hav ing a particular importance for these evaluations. Furthermore\, a new ver sion (2.2/2021) of the BetaShape code $^{7\,8}$ for $\\beta$ transitions a nd electron captures (EC) has been released and provides improved calculat ions for single transition and total $\\beta$ spectra\, EC probabilities a nd their ratios for all subshells\, mean energies\, log ft values\, EC/$\\ beta_+$ ratios and branch splitting. The new *Q* values from AME 2020 are included in this new version of the code as an external file\, and a simpl e option allows for an automatic update of this parameter. These developme nts can lead to important improvements in the recommended data resulting f rom the evaluation procedure\, beyond possible new published measurements. The nuclear decay data update for the two manganese radionuclides ${^{52} }Mn$ and ${^{52m}}Mn$\, decaying by EC/$\\beta_+$ transitions\, is a good example of what improved theoretical predictions can provide. The updates to the two alpha-particle emitters\, ${^{226}}Th$ and ${^{230}}U$\, will a lso be discussed. The authors have also considered the question “How oft en should nuclear decay data evaluations be updated?”. Several criteria to support the decision of undertaking data evaluation updates are propose d and discussed\, along with recent examples relevant for radionuclide met rology. \n\nAcknowledgement: This work was funded through the research pro gramme Program Nucleu\, carried out with the support of the Romanian Minis try of Research\, Innovation and Digitization (MCID)\, project no. PN 19 0 6 02 04 /2021.\n\nReferences:\n$^1$ A. Luca\, Appl. Radiat. Isot. 155 (202 0) 108941\n$^2$ A. Luca\, M.-R. Ioan\, Appl. Radiat. Isot. 134 (2018) 426- 428\n$^3$ R. Capote et al.\, EPJ Web of Conferences 146\, 08007 (2017)\n$^ 4$ A. Luca\, EPJ Web of Conferences 146\, 08003 (2017)\n$^5$ M.A. Kellett\ , O. Bersillon\, EPJ Web of Conferences 146\, 02009 (2017)\n$^6$ Meng Wang et al.\, Chinese Phys. C 45 (2021) 030003\n$^7$ X. Mougeot\, Physical Rev iew C 91\, 055504 (2015)\; Erratum Phys. Rev. C 92\, 059902 (2015)\n$^8$ X . Mougeot\, Appl. Radiat. Isot. 154 (2019) 108884\n\nhttps://indico.frib.m su.edu/event/52/contributions/664/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/664/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement and analysis of the neutron total cross sections of $^ {209}$Bi on the Back-n beam line at CSNS DTSTART:20220728T141200Z DTEND:20220728T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-819@indico.frib.msu.edu DESCRIPTION:Speakers: Song Feng\n\nhttps://indico.frib.msu.edu/event/52/co ntributions/819/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/819/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the fission yield of $^{136}$Cs in the $^{239}$Pu(n $_{\\text{th}}$\,f) reaction and its impact on the total dose rate calcula tion DTSTART:20220725T165400Z DTEND:20220725T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-666@indico.frib.msu.edu DESCRIPTION:Speakers: Abdelaziz Chebboubi (CEA)\n\nA. Chebboubi1\, D. Bern ard1\, V. Vallet1\, G. Kessedjian1\, O. Méplan2\, Y.H. Kim3\, U. Köster3 \, Ch.E. Düllmann4\,5\,6\, F. Géhin1\, M. Houdouin-Quenault1\,2\, O. Lit aize1\, C. Mokry4\,6\, M. Ramdhane2\, J. Runke4\,5 \,C. Sage3\, O. Serot1 \n \n1`CEA\, DES\, IRESNE\, DER\, SPRC\, Cadarache\, Physics Studies Labor atory\, 13108 Saint-Paul-lès-Durance\, France\n2 LPSC\, Université Greno ble-Alpes\, CNRS/IN2P3\, 38026 Grenoble\, France\n3 Institut Laue-Langevin (ILL)\, 38042 Grenoble\, France\n4 Department of Chemistry - TRIGA site\, Johannes Gutenberg University Mainz\, 55128 Mainz\, Germany\n5 GSI Helmho ltzzentrum für Schwerionenforschung GmbH\, 64291 Darmstadt\, Germany\n6 H elmholtz Institute Mainz\, 55128 Mainz\, Germany\n\n\nA recent experimenta l campaign performed at the LOHENGRIN spectrometer at ILL aimed at measuri ng the independent fission yield of $^{136}$Cs in the $^{239}$Pu(n$_{\\tex t{th}}$\,f) reaction. Indeed\, recent works from CEA/LEPh have shown that this nuclide can have an important contribution to the total dose rate com ing from the decay of radioactive nuclides. Moreover\, its impact is of f irst-order on the uncertainty of the total dose rate calculated in specifi c areas of Nuclear Power Plants within accidental conditions. The producti on paths of this nuclide in a nuclear reactor are complex. A sensitivity a nalysis performed with the DARWIN package [1] has shown that one of the mo st important production paths was directly from the fission process. There fore\, a new measurement of its independent yield along with a rigorous un certainty analysis would allow handling its impact on the total dose rate. \nThe experimental campaign has been performed in June 2021 with a 129 µg /cm$^{2}$ $^{239}$Pu target (99.5% enrichment) produced by molecular plat ing [2] at the TRIGA Site of the Department of Chemistry at Johannes Guten berg University Mainz. The experimental setup consisted of a vacuum chambe r placed in the focal plane of the LOHENGRIN spectrometer and surrounded b y two HPGe clover detectors. Due to its low independent yield\, the signal from $^{136}$Cs decays is very low in comparison to the γ–ray backgrou nd at the measurement position. Therefore\, the ions were collected by imp lantation of the mass-separated beam into Al foil placed inside the vacuum chamber. This foil was then removed and transfer to a low γ-ray backgrou nd setup located at LPSC. The procedure is then repeated for different LOH ENGRIN settings. The low γ-ray background setup features a considerably i mproved signal-to-background ratio compared to more conventional measureme nts in the on-line regime [3].\nThis talk will present the results of this experiment and the improvement on the total dose rate calculation uncerta inty.\n\n\n[1] A. Tsilanizara\, T. D. Huynh\, Annals of Nuclear Energy 164 \, 108579 (2021)\n[2] J. Runke et al.\, J Radioanal Nucl Chem 299\, 1081 ( 2014)\n[3] S. Julien-Laferrière et al.\, Phys. Rev. C 102\, 034602 (2020) \n\nhttps://indico.frib.msu.edu/event/52/contributions/666/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/666/ END:VEVENT BEGIN:VEVENT SUMMARY:Hydrogen isotopes emissions from the nuclear muon capture reaction in silicon DTSTART:20220726T140000Z DTEND:20220726T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-782@indico.frib.msu.edu DESCRIPTION:Speakers: Yukinobu Watanabe\, Magumi Nikura\, Dai Tomono\, Tak eshi Saito\, Kawashima Yoshitake\, Keita Nakano\, Daisuke Suzuki\, Akira S ato\, Seiya Manabe\n\nThe main threat to electronics at the ground level i s well-known as the secondary-cosmic-ray-induced soft error. The soft erro r is caused by an upset of the memory information due to an energy deposit ion by an energetic ionizing radiation. Among the cosmic-ray species\, the muon has recently drawn attention as a new cause of the soft error due to the reduction of the critical charge of the static random-access memory. Our previous works [1] reported that the negative muon has much more serio us effect on the occurrence of soft errors compared to the positive one be cause of the emission of light ions (hydrogen and helium) from the nuclear muon capture reaction in the silicon nuclei. In this work\, we performed the experiment to accumulate the basic data of the fundamental physical pr ocess of muon-induced soft error\, i.e.\, the light ion from the nuclear m uon capture reaction\, to improve the accuracy of the simulation of the mu on-induced soft error. In addition to the experiment\, a validation of the model calculation implemented in Particle and Heavy Ions Transport code S ystem (PHITS) [2] was made by comparing the experimental data and the simu lation.\n\nThe experiment was performed at the M1 muon beam line of Muon S cience Innovative muon beam Channel [3] in Research Center for Nuclear Phy sics\, Osaka University\, Japan. The pions\, which is a source of muons\, were generated through the nuclear reaction between a 392-MeV proton beam and a graphite target. The produced pions almost decayed into muons in a s uperconducting solenoid magnet. The polarity and the momentum of the muon were selected by the solenoid magnet and the selected muons were transport ed to a vacuum chamber which was connected to the beam exit of the M1 beam line. The momentum of 36 MeV/c was chosen to maximize the number of stopp ing muons. A 100 µm thick silicon target was mounted at the center of the chamber at a tilt angle of 45° to the beam direction. The size of the ta rget is 10 cm × 5 cm. Two forward plastic scintillators with the size of 5 cm × 7 cm × 0.5 cmt were set to count the number of incident muons and make the triggers for the data acquisition. Two telescopes were mounted p arallelly to the target at both the upstream and downstream of the target to detect the secondary ions and measure their kinetic energies. The energ ies of the ions were determined by a ΔE-E method by using a 325 µm silic on detector (ΔE) and 25 mm thick CsI detector (E).\n\nThe energy spectra of proton\, deuteron and triton were successfully measured in the energy r ange from 8 MeV to 35 MeV. The proton and deuteron spectra in the energy r ange of 8-15 MeV and the triton spectrum were first measured in this work. The measured proton and deuteron spectra were compared to those of the pa st work [4]. The comparison demonstrated the consistency between the prese nt and past data. Next\, a benchmark test of the PHITS calculation was per formed. The nuclear muon capture reaction is described with the quantum mo lecular dynamics (QMD) [5] or modified QMD (MQMD) [6] for the dynamic proc ess plus the generalized evaporation model (GEM) for statistical decay pro cess [7]. The test indicated that the MQMD plus GEM has larger yields of d euteron and triton than the QMD plus GEM. However\, both models still sign ificantly underestimated the measured spectra in the high emission energy region.\n\n[1] S. Manabe et al.\, IEEE Trans. Nucl. Sci.\, 65:8\, 1742-174 9 (2018).\n[2] T. Sato et al.\, J. Nucl. Sci. and Technol.\, 55:5-6\, 684- 690 (2018).\n[3] Y. Matsumoto et al.\, Proc. of 6th International Particle Accelerator Conference (IPAC)\, 2537-2540 (2015).\n[4] S. E. Sobottka and E. L. Wills\, Phys. Rev. Lett.\, 20:12\, 596-598 (1968).\n[5] K. Niita et al.\, Phys. Rev. C\, 52:26\, 2620-2635 (1995)\n[6] Y. Watanabe and D. Kad rev\, in Proc. of International Conference on Nuclear Data for Science and Technology 2007 (2008)\n[7] S. Furihata et al.\, Japan Atomic Energy Rese arch Institute\; 2001. (JAERI-Data/Code 2001-015).\n\nhttps://indico.frib. msu.edu/event/52/contributions/782/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/782/ END:VEVENT BEGIN:VEVENT SUMMARY:Complete Fission-Fragment Identification with the FALSTAFF Spectro meter DTSTART:20220727T180000Z DTEND:20220727T182400Z DTSTAMP:20260420T153400Z UID:indico-contribution-635@indico.frib.msu.edu DESCRIPTION:Speakers: D. Doré\, E. Berthoumieux\, P. Legou\, M. Rejmund\, X. Ledoux\, A. Letourneau\, J. Pancin\, J. E. Ducret\, A. Lemasson\, Dieg o Ramos\n\nThe fission process has intrigued physicists for a long time fr om both\, experimental and theoretical points of view~\\cite{Bohr\,wil76\, bro90}. The large deformations achieved in the process and the interplay b etween intrinsic and collective degrees of freedom prevent\, so far\, from a complete microscopic description of the phenomenon~\\cite{sorting\,scam ps18\,kh18}. The role of the nuclear structure in fission is of particular interest: Only the microscopic structure of the nuclei can explain the as ymmetric distribution of fission fragments produced from neutron-rich acti nides. Nuclear structure depends on the number of protons and neutrons sep arately. This strengthens the need of an experimental complete identificat ion of fission fragments.\n\nIn addition\, the concept and development of future IV-generation nuclear reactors require a complete nuclear data base for incoming neutron energies up to several of MeV~\\cite{NEA\,Pro\,ENDF} . Therefore\, from the application point of view\, there is also a need of data concerning the fission production from actinides induced by fast neu trons.\n\nA new setup based on two position-sensitive Secondary Electrons Detectors and an Axial Ionization Chamber\, the FALSTAFF spectrometer\, ha s been built in order to measure both\, the mass and the nuclear charge of the full distribution of fission products from fast-neutron induced fissi on in actinides~\\cite{fal1\,fal2}. \n\nThe FALSTAFF spectrometer will be used in combination with the VAMOS++ magnetic spectrometer early in 2022 at GANIL (France)\, in order to measure both fragments at the same time fr om fusion-fission reactions in inverse kinematics. This will allow to bett er understand the response of FALSTAFF. Later\, it will benefit from the h igh neutron flux from the new Neutrons For Science Facility at GANIL-SPIRA L2 to perform fast neutron-induced fission studies. Preliminary results fr om the first measurement will be presented as well as the prospectives of the following experiments. The strength of the FALSTAFF setup for complete fission-fragment identification will be discussed. \n\n\n\n\n\\begin{theb ibliography}{00}\n\\bibitem{Bohr} N. Bohr and J.A. Wheeler\, Phys. Rev. 56 \, 426 (1939).\n\\bibitem{wil76} B.D. Wilkins\, E.P. Steinberg\, and R.R. Chasman\, Phys. Rev. C 14\, 1832 (1976).\n\\bibitem{bro90} U. Brosa\, S. G rossman\, and A. M\\"{u}ller\, Phys. Reports 197\, 167 (1990).\n\n\\bibite m{sorting} K.-H. Schmidt and B. Jurado\, Phys. Rev. Lett. 104\, 212501 (20 10).\n\\bibitem{scamps18} G. Scamps and C. Simenel\, Nature 564\, 382 (201 8).\n\\bibitem{kh18} K.-H. Schmidt and B. Jurado\, Rep. Prog. Phys. 81\, 1 06301 (2018).\n\n\\bibitem{NEA} Accelerator-driven systems (ADS) and fast reactors (FR) in advanced nuclear fuel cycles\, OECD Nuclear Energy Agency Report No. 3109 (2002).\n\\bibitem{Pro} Proceedings of the International Workshop\, Antwerpen\, Belgium\, April 2005\, https://doi.org/10.1142/6130 \n\\bibitem{ENDF} D. Brown\, et al.\, ENDF/B-VIII\, Nucl. Data Sheets 148\ , 1 (2018).\n\n\\bibitem{fal1} D. Doré\, et al.\, Nuclear Data Sheets 119 \, 346 (2014)\n\\bibitem{fal2} D. Doré\, et al.\, EPJ Web Of Conf. 211\, 04002 (2019).\n\nhttps://indico.frib.msu.edu/event/52/contributions/635/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/635/ END:VEVENT BEGIN:VEVENT SUMMARY:Improvement of targetry methods for nuclear data measurements DTSTART:20220726T181500Z DTEND:20220726T183900Z DTSTAMP:20260420T153400Z UID:indico-contribution-721@indico.frib.msu.edu DESCRIPTION:Speakers: Emilio Andrea Maugeri (Paul Scherrer Institut)\n\nAc cording to the Nuclear Data High Priority Request List published by the Nu clear Energy Agency (http://www.oecd-nea.org/dbdata/hprl/)\, values of cro ss sections used in nuclear technology should be known with uncertainties between 1% and 5%\, while cross sections of key isotopes involved in s- an d r-processes must be known with uncertainties of about 1%. \nThe uncertai nty associated with the measured cross sections has two sources\, data eva luation and experimental procedure. Experimental uncertainties are mainly generated by time resolution of experimental configurations (duration and speed of neutron burst\, etc.)\, detectors and electronics [1]\, and by th e targetry (defined as discipline of design\, manufacture and characteriza tion of targets) [2]. On the other end several measurements of important c ross sections have been hindered by the lack of adequate amount of the rel ative target nuclide with the requested high chemically and isotopically p urity. \nThe first part of this contribution focuses on the production and purification of some exotic radionuclides at the Paul Scherrer Institut\, Switzerland. Some examples\, to illustrate the importance of the target c hemical purity for obtaining the envisaged measurement\, are presented. \ nThe main part of the talk centers on recent developments of novel methods for the production of homogeneous and uniform solid targets allowing obta ining cross sections with lower uncertainty. In fact\, only if the target material is homogeneous and has uniform thickness\, the incident particles will have the same probability of interaction with the target nuclei and the energy loss of all the detected particles\, especially if charged\, wi ll be similar. This will allow measurements that are more precise.\nNew fi ndings on the role of the solvent on Molecular Plating\, one of the most u sed techniques for solid target production [3]\, are presented. These resu lts show that less volatile solvent allow obtaining more uniform and thinn er targets. Figure 1 illustrates three scanning electron microscopy imagin es (x 600 magnification) of three different targets of holmium obtained wi th identical conditions in term of temperature and concentration\, but usi ng solvent with different vapor pressure\, i.e. isopropanol (5.78 kPa)\, I sobutanol (1.53 kPa) and N\,N-Dimethylformamide (0.44 kPa). It is possible to see that the material deposited from solvents with higher vapor pressu re are characterized by a less homogeneous and island-like structure\, wit h presence of cracks and peeling off the deposited material.\nA still uns olved problem related with the Molecular Plating is the inevitable co-prec ipitation of organic compounds\, which causes thickening and introduction of impurities into the deposited layer\, enhancing the background during t he cross section measurement. \nThe development of a new method\, based on electrodeposition of exotic radionuclides from ionic liquid\, is under de velopment in our laboratories to deposit chemically pure elements avoiding any co-precipitation. Some preliminary results of this project are presen ted too.\nReference\n[1] H. Postma\, P. Schillebeeckx\, Neutron Resonance Capture and Transmission Analysis\, Encyclopedia of Analytical Chemistry\, John Wiley & Sons\, Ltd\, 2006.\n[2] P. Schillebeeckx\, A. Borella\, J.C. Drohe\, R. Eykens\, S. Kopecky\, C. Massimi\, L.C. Mihailescu\, A. Moens\ , M. Moxon\, R. Wynants\, Target requirements for neutron-induced cross-se ction measurements in the resonance region\, Nucl. Instr. Meth. Phys. Res. A\, 613 (2010) 378.\n[3] W. Parker\, R. Falk\, Molecular plating: A metho d for the electrolytic formation of thin inorganic films\, Nucl. Instr. Me th.\, 16 (1962) 355.\n\nhttps://indico.frib.msu.edu/event/52/contributions /721/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/721/ END:VEVENT BEGIN:VEVENT SUMMARY:Update of the CIELO $^{238}$U resonance evaluation to improve LWR performance with burnup DTSTART:20220726T134800Z DTEND:20220726T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-695@indico.frib.msu.edu DESCRIPTION:Speakers: Peter Schillebeeckx\, Stefan Kopecky\, Andrej Trkov (Jozef Stefan Institute)\, Roberto Capote (IAEA NDS)\n\nNew U-235 and U-23 8 evaluations [1-3] were undertaken within the OECD/NEA Data Bank CIELO Pr oject [4] and were adopted for the ENDF/B-VIII.0 library [5]\, which was r eleased in 2018. Since then\, several reports and publications were releas ed that showed serious discrepancies with the light water reactor (LWR) pe rformance of the previous ENDF/B-VII.1 library [6] in criticality studies as the function of the burnup\, e.g.\, see Ref. [7]. A slight increase of the LWR reactivity was observed at the Beginning of Cycle (BOC) with a sev ere loss of reactivity at large burnup observed for the ENDF/B-VIII.0 libr ary. Sensitivity studies showed some compensation effects at the BOC\, but uniquely identified the U-238 evaluation as the responsible for the react ivity loss [7].\n\nRecent changes in the U-235 resonance evaluation [8] sl ightly reduced the U-235 capture cross section below 20eV\, but these chan ges are not expected to have an impact on reactivity trends with burnup. H owever\, slight positive criticality bias may be expected due to U-235 cha nges. \n\nIn this work we focused on studying changes in resonance cross sections of U-238 that may explain the observed trend as a function of bur nup. It was found that capture cross section from 0.1eV up to 10eV was red uced in ENDF/B-VIII.0 evaluation by about 2% [\,4\,5\,9] compared to the E NDF/B-VII.1 evaluation [6\,10] as shown in Figure 1.\n \n(see attached PDF )\nFigure 1. ENDF/B-VII.1 to ENDF/B-VIII.0 capture cross-section ratio in the resonance region.\n\nThe observed changes may explain the observed bur nup trend as lower capture cross sections in U-238 around 1eV lead to incr eased criticality at the BOC\, but results in lower criticality at higher burnup due to the reduced production of Pu-239 due to the lower capture cr oss section. This hypothesis was tested in deterministic calculations and confirmed in our preliminary studies. \n.\nAdditional changes in ENDF/B-VI II.0 evaluation in the resonance region [9] are on-going to try to preserv e the capture cross section below 10eV reproducing at the same time the ex isting transmission experiments. \n\n[1] R. Capote\, A. Trkov\, M. Sin\, M . Herman\, A. Daskalakis\, Y. Danon\, Physics of neutron interactions with 238U: new developments and challenges\, Nucl. Data Sheets 118\, 26(2014)\ n[2] R. Capote\, A. Trkov\, M. Sin et al.\, IAEA CIELO evaluation of neutr on-induced reactions on 235U and 238U targets\, Nucl. Data Sheets 148\, 25 4 (2018)\n[3] R. Capote\, A. Trkov (coordinators)\, IAEA CIELO Data Develo pment Project within the International Pilot Project of the OECD/NEA [1]\, 235U and 238U files released December 1st\, 2017\, https://www-nds.iaea.o rg/CIELO/\n[4] M.B. Chadwick et al.: “CIELO Collaboration Summary Result s: International Evaluations of Neutron Reactions on Uranium\, Plutonium\, Iron\, Oxygen and Hydrogen”\, Nuclear Data Sheets 148 (2018) 189–213. \n[5] D.A. Brown et al.: “ENDF/B-VIII.0: The 8th Major Release of the Nu clear Reaction Data Library with CIELO-project Cross Sections\, New Standa rds and Thermal Scattering Data”\, Nuclear Data Sheets 148 (2018) 1–14 2.\n[6] M.B. Chadwick\, M.W. Herman\, P. Oblozinsky et al.\, ENDF/B-VII.1 nuclear data for science and technology: cross sections\, covariances\, fi ssion product yields and decay data\, Nucl. Data Sheets 112\, 2887 (2012)\ n[7] Kang-Seog Kim and William A. Wieselquist\, “Neutronic Characteristi cs of ENDF/B-VIII.0 Compared to ENDF/B-VII.1 for Light-Water Reactor Analy sis”\, J. Nucl. Eng. 2 (2021) 318–335. https://doi.org/10.3390/jne2040 026 \n[8] M.T. Pigni\, R. Capote\, A. Trkov\, Y. Danon. “Updates of the U-235 resonance parameters below 20 eV”\, INDEN collaboration\, IAEA 202 0. See U-235 tab at https://www-nds.iaea.org/INDEN/. \n[9] H.I. Kim\, C. P aradela\, I. Sirakov et al.\, Neutron capture cross section measurements f or 238U in the resonance region at GELINA\, Eur. Phys. J. A 52\, 170 (2016 )\n[10] H. Derrien\, L.C. Leal\, N.M. Larson\, and A. Courcelle\, Report O RNL/TM-2005/241 (2005). “Neutron Resonance Parameters of 238U and the Ca lculated Cross Sections from the Reich-Moore Analysis of Experimental Data in the Neutron Energy Range from 0 keV to 20 keV”.\n\nhttps://indico.fr ib.msu.edu/event/52/contributions/695/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/695/ END:VEVENT BEGIN:VEVENT SUMMARY:ACEMAKER: A processing system for producing ACE-formatted files fo r Monte Carlo calculations DTSTART:20220725T165400Z DTEND:20220725T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-853@indico.frib.msu.edu DESCRIPTION:Speakers: Daniel Lopez Aldama (IAEA/Consultant)\n\nSince 2016 the Nuclear Data Section of the International Atomic Energy Agency (NDS/I AEA) has encouraged the development of new codes for processing evaluated nuclear data for applications. The main motivation has been the need for i mproving processing methods and avoiding common failure modes. In the fram e of this effort\, the NDS/IAEA has supported the development of the proce ssing system ACEMAKER\, which takes advantage of the system of codes PREPR O and complements it with new modules for producing ACE-formatted files fo r Monte Carlo calculations. The new modules can process any correlated ene rgy-angle distributions\, gamma-production data\, gamma-uncorrelated energ y-angle distributions\, thermal scattering laws and dosimetry files for pr oducing the appropriated ACE-formatted file for Monte Carlo simulations. T his paper describes the main features of the processing system ACEMAKER\, its verification and validation process\, and discuss planned developments .\n\n 1. List item\n\nhttps://indico.frib.msu.edu/event/52/contributions/8 53/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/853/ END:VEVENT BEGIN:VEVENT SUMMARY:ENSDF Modernization and Expansion with Machine Learning Tools for Data Ingestion DTSTART:20220727T180000Z DTEND:20220727T182400Z DTSTAMP:20260420T153400Z UID:indico-contribution-872@indico.frib.msu.edu DESCRIPTION:Speakers: Andrea Mattera (Brookhaven National Laboratory - NND C)\, Donnie Mason\, Shinjae Yoo\, Edwin Gomez\, Sean McCorkle\, Alejandro Sonzogni\, Shaofei Zhu\, Caleb M Mattoon\, Benjamin Shu (National Nuclear Data Center)\, Cassandra Billings\, Carlos Soto\, Filip Kondev\, Chris Mo rse\, Elizabeth A. McCutchan (Brookhaven National Laboratory)\n\nThe Evalu ated Nuclear Structure Data File (ENSDF) database is the comprehensive\nnu clear structure and decay database\, containing all published experimental \nnuclear structure and decay data for the 3300 observed nuclides\, along with\ncarefully evaluated recommended values and uncertainties. ENSDF is t he leading\nsource of nuclear structure and decay data worldwide for both basic and applied\nsciences\, exceeding 3.2M lookups per year via the NNDC website.\n\nThe complete modernization of the ENSDF database is underway- -an ambitious\nproject that is transforming the restrictive 80-column ASCI I format in use\nsince its inception into an expansible Object-Oriented Da tabase and API. In\naddition to the existing ENSDF data\, this upgrade wi ll allow for the addition\nof a wide variety of content (such as continuou s spectra)\, efficiently deliver\ncomplex search results\, and provide str aightforward data access to modern\ncomputational tools. The modernized d atabase will be amenable to the addition\nof arbitrary types of open data\ , as well as supplemental information from\nevaluators to speed subsequent evaluations.\n\nOne of the bottlenecks in curating nuclear data from the scientific literature\nis extracting table contents from PDF (Portable Doc ument Format) documents for\nevaluation\, particularly because standard PD F table extraction tools produce\nmany artifacts which are laborious to co rrect. New machine learning (ML) tools\nand techniques are being develope d in parallel to automate the insertion of\nnewly-published data into the companion database for pre-evaluation published\nresults (XUNDL)\, which w ill significantly reduce the labor required of the\ncompiler. Our approac h is to develop machine learning models to 1) isolate\ntables in documents \, 2) visually detect individual cells\, 3) predict table\nstructure\, and 4) recognize the text contents. These machine learning models\nare develo ped using a combination of convolutional and recurrent neural\nnetworks.\n \nThe ENSDF data format and storage are being migrated to JSON and the Cou chDB\ndatabase. This has a number of benefits. Using a standard format a nd database\nmanagement system will greatly reduce the time required to un derstand the data\nstructure and encourage community contributions to API development. The new\nformat will allow ENSDF to exploit existing tools i n modern databases and\nsupport rigorous accuracy testing. The data struc ture will be easily\ncomprehensible and human-readable for current and fut ure developers\, as well as\nmachine-readable for AI/ML and other applicat ions. The hierarchical key-value\nstructure of JSON will enable unambiguo us direct references to any data in the\nupgraded ENSDF\, with an intuitiv e syntax.\n\nEfficient search methods for physical properties such as leve l half-lives\,\n$\\gamma$-decay energies\, *etc.* are being developed\, in parallel with a\nPython API. The API will include high-level functions a nd tools to utilize\nthe search capabilities. Users will be able to write their own Python scripts\nand applications\, using the API to access data directly from the new ENSDF\nserver. The database server will be able to export the majority of the data\ncurrently available in ENSDF to the orig inal 80-column format for legacy codes.\n\nENSDF is intended to support th e research community. As such\, user input is\nbeing solicited\, and a nu mber of outreach workshops will be held throughout the\nduration of the pr oject. New interfaces will be designed for the evaluator and\nthe user co mmunity\, and a visualization tool to clarify the data structure is\nunder development.\n\nThis Research is sponsored by Office of Nuclear Physics\, Office of Science\, US\nDepartment of Energy\, under contracts DE-AC02-98 CH10946 (BNL) and\nDE-AC-06CH11357 (ANL).\n\nhttps://indico.frib.msu.edu/e vent/52/contributions/872/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/872/ END:VEVENT BEGIN:VEVENT SUMMARY:GRAPhEME: performances\, achievements (@EC-JRC/GELINA facility) an d future (@ GANIL/SPIRAL2/NFS facility) DTSTART:20220726T163000Z DTEND:20220726T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-784@indico.frib.msu.edu DESCRIPTION:Speakers: Greg Henning\, Alexandru Nagret\, François Claeys\, Marian Boromiza\, Markus Nyman\, Roberto Capote\, Toshihiko Kawano\, Step hane Hilaire\, Adina Olacel\, Marc Dupuis\, Carlos Paradela Dobarro\, Jean -Claude Drohé\, Arjan Plompen\, Nicolas Dari Bako\, Cyrille de Saint Jean \, Catalin Borcea\, Ruud Wynants\, Philippe Dessagne\, Maelle Kerveno\n\nG RAPhEME is a $\\gamma$ spectrometer developed by CNRS/IPHC Strasbourg (Fra nce)\, in collaboration with EC-JRC/Geel (Belgium) and IFIN-HH Bucharest ( Romania). With its 6 High Purity Planar Germanium detectors\, GRAPhEME\, i nstalled at the EC-JRC GELINA facility\, was optimized for measurements of accurate (n\,xn $\\gamma$) cross sections on actinides. The experimental methodology is based on prompt $\\gamma$-ray spectroscopy coupled to time of flight measurements. In a first configuration\, involving 4 HPGe\, seve ral measurement campaigns have produced numerous sets of data for $^{235}$ U [1]\, $^{238}$U [2] \, $^{232}$Th [3] and $^{183\,182\,184\,186\,nat}$W isotopes [4]. An update of the setup in 2016\, with a segmented (6x6 pix els) HPGe has opened the way for measurements with very active targets. A first campaign on $^{233}$U has been performed and a second one\, on $^{23 9}$Pu is planned in the coming months. Beyond the experimental work\, a st rong collaboration with theoreticians has emerged allowing the use of the data produced with GRAPhEME to test and constraint nuclear reaction codes [5] like TALYS\, CoH and EMPIRE.\n\nIn this paper\, we would like to pres ent an overview of fifteen years of experiments with GRAPhEME and to highl ight the performances and achievements done at EC-JRC GELINA facility. The limitations of our apparatus and methodology will be also described with the solutions we implement continuously to improve GRAPhEME and the associ ated data analysis methodology. The next challenge tackled with GRAPhEME i s to perform (n\,2n) and (n\,3n) cross sections measurements at the new GA NIL/SPIRAL2/NFS facility in Caen\, France. A status of this new project wi ll be discussed. This overview paper\, if accepted\, will be completed by five other submitted papers\, which will present more focused items relate d to GRAPhEME (new inelastic cross section data on $^{233}$U and $^{183}$W \, improvement of data analysis methodology\, inferring total cross sectio n from measured partial ones\, problematic of nuclear structure uncertaint ies\, evaluation). \n- On the need for precise nuclear structure data for high quality (n\, n'$\\gamma$) cross section measurements. G.Henning et a l.\n- (poster) Using Monte-Carlo method to analyze experimental data and p roduce uncertainties and covariances. G.Henning et al.\n- Experimental mea surement of $^{183}$W(n\, n'$\\gamma$) and (n\, 2n$\\gamma$) cross section s (preliminary). G.Henning et al.\n- Measurement and evaluation of partial and total (n\,xn) reaction cross-sections on highly radioactive nuclei of interest for energy production application. F. Claeys et al.\n- (poster) From $^{232}$Th(n\,n' $\\gamma$) cross sections to level production and to tal inelastic scattering cross section. N. Dari Bako et al.\n[1] M.Kerveno et al.\, Physical Review C 87\, 24609 (2013)\n[2] M.Kerveno et al.\, Phys ical Review C\, accepted for publication (2021)\n[3] E. Party\, Thesis Uni versity of Strasbourg\, paper in preparation\n[4] G. Henning et al.\, Proc eedings of PHYSOR 2020 conference: https://hal.archives-ouvertes.fr/hal-02 956052\n[5] M.Kerveno et al.\, Eur. Phys. J Web of Conferences 239\, 01023 (2020)\n\nhttps://indico.frib.msu.edu/event/52/contributions/784/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/784/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement and evaluation of partial and total (n\,xn) reaction c ross-sections on highly radioactive nuclei of interest for energy producti on application. DTSTART:20220728T151400Z DTEND:20220728T152600Z DTSTAMP:20260420T153400Z UID:indico-contribution-828@indico.frib.msu.edu DESCRIPTION:Speakers: Markus Nyman\, Marian Boromiza\, Maëlle Kerveno\, A . Olacel\, Arjan Plompen\, Marc Dupuis\, Stephane Hilaire\, Nicolas Dan-Ba ko\, Cyrille de Saint Jean\, Alexandru Negret\, Philippe Dessagne\, Gilles Noguerre\, Catalin Borcea\, Greg Henning\, Francois Claeys\n\nIn the cont ext of the development of Gen. IV nuclear reactors\, the GIF (Generation I V. International Forum) has selected six innovative technologies. Among th em\, one can highlight the concept of breeding for $^{232}$Th/$^{233}$U an d $^{238}$U/$^{239}$Pu fuel cycles. But those nuclei\, crucial for such cy cles\, suffer from a lack of precise knowledge (nuclear structure\, reacti on cross sections). In particular\, it has been demonstrated that neutron inelastic scattering reaction cross sections are not precise enough for th e isotope $^{238}$U and $^{239}$Pu\, and not known at all experimentally f or the nucleus of $^{233}$U. In order to perform simulations of reactor co res for the development of those technologies\, new measurements have to b e done. The GRAPhEME (GeRmanium array for Actinides PrEcise Measurements) experimental setup\, developed by the IPHC from the CNRS\, installed at th e GELINA facility is a powerful tool to answer this need [1\,2]. Combining the prompt $\\gamma$-ray spectroscopy and the time-of-flight methods\, it measures partial (n\,xn$\\gamma$) reaction cross sections. This paper pre sents on one hand main challenges which represent experiments on high acti vity actinides\, especially on $^{233}$U and $^{239}$Pu and on the other h and results obtained so far for the measurements of partial (n\,xn$\\gamma $) reaction cross section for the nucleus $^{233}$U. \n \n Exploring a more theoretical aspect of nuclear data\, the LEPh and the SPN from the CEA work\, among other nuclear fields\, on the evaluation of nuclear data. Using nuclear calculation codes such as TALYS [3] and experimental data\, they aim to provide new evaluated data. In particular\, a new evaluation of the neutron inelastic scattering on $^{238}$U is in progress. It is bas ed on a recent set of experimental data\, namely results on $^{238}$U part ial (n\,xn$\\gamma$) reaction cross sections obtained with GRAPhEME and a updated version of TALYS\, with new models recently added into this code.\ n\n**References**\n\n[1] : M. Kerveno\, G. Henning\, C. Borcea\, P. Dessag ne\, M. Dupuis\, S.Hilaire\, A. Negret\, M. Nyman\, A. Olacel\, E. Party and A. Plompen\; *How to produce accurate inelastic cross sections from an indirect measurement method ?*\; EPJ N - Nuclear Sciences & Technologies\ , Vol. 4\; 2018\; https://hal.archives-ouvertes.fr/hal-02109918.\n\n[2] : M. Kerveno\, M. Dupuis\, C. Borcea\, M. Boromiza\, R. Capote}\, P. Dessagn e\, G. Henning\, S. Hilaire\, T. Kawano\, A. Negret\, M. Nyman\, A. Olacel \, E. Party\, A. Plompen\, P. Romain and M. Sin\; *What can we learn from (n\,xn$\\gamma$) cross sections about reaction mechanism and nuclear struc ture ?*\; ND 2019 : International Conference on Nuclear Data for Science a nd Technology\; 2019\; https://hal.archives-ouvertes.fr/hal-02957494.\n\n[ 3] : A.J. Koning\, D. Rochman\, J. Sublet\, N. Dzysiuk\, M. Fleming and S. van der Marck\; *TENDL: Complete Nuclear Data Library for Innovative Nucl ear Science and Technology*\; Nucl. Data Sheets\; Vol.155\; 2019.\n\nhttps ://indico.frib.msu.edu/event/52/contributions/828/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/828/ END:VEVENT BEGIN:VEVENT SUMMARY:Modernization efforts for the R-Matrix code SAMMY DTSTART:20220726T170600Z DTEND:20220726T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-890@indico.frib.msu.edu DESCRIPTION:Speakers: Dorothea Wiarda (ORNL)\n\nThe R-Matrix code SAMMY \\ cite{SAMMY} is a widely used nuclear data evaluation code focused on the r esolved range\,\nwhich includes corections for experimental effects. The code is still mostly written in Fortran 77\, and uses\na memory managment system suitable for the time of its initial writing (1984). A modernizatio n effort is under way\nto bring the code in-line with modern software deve lopment practices. A continuous-integration testing\nframework was added\, automating the large exisiting set of test cases. It is run on every com mit.\nThe memory management was updated to current standard practices suit able for modern software analysis tools.\nThe code can be optained from \ \href{https://code.ornl.gov/RNSD/SAMMY}{https://code.ornl.gov/RNSD/SAMMY}. \n\nThe resonance parameters and covariance information are now stored in C++ objects shared by SAMMY and AMPX \\cite{AMPX}\,\nthe processing code t hat generates nuclear data libraries for SCALE \\cite{SCALE}. This\nallow s for easier maintainance and access to the resonance parameters inside an d outside of SAMMY.\nThis feature is already used by accessing and changin g parameters in memory in the\nBayesian Monte Carlo Evaluation Framework f or Cross Sections Nuclear Data and Integral Benchmark Experiments project \\cite{ND10}\,\n\nFurther plans include the switch to the ENDF reading and writing routines in AMPX\, as these routines\nare more robust\, easier to maintain\, and support more features. Of note here is support for the new GNDS format \\cite{GNDS}.\nPreviously it wasn't easy to share the full c ovariance matrix for evaluations containing more than one isotope due to \ nlimitations on the ENDF format\; this is now supported in GNDS. The data are currently available in a binary SAMMY format and can be exported \nto GNDS to make them more widely available and sharable.\n\nThe next step wil l be to use the same resonance processing code at 0K in AMPX and SAMMY as one of the available\nReich-Moore R-Matrix formalism.\nThe first step tow ard this goal is to isolate the reconstruction into a module that takes r esonance parameters as its input and\ndoes not depend on SAMMY gobal param eters. This goal has been achieved and it should now be possible to more easily\nchange the resonance formalism\nand add enhancements as the Phen omenological $R$-Matrix parameterization of direct\, doorway\, and compoun d nuclear reactions discussed\nelsewhere on this conference.\nThis concert ed modernization and enhancement effort provides multiple advantages to th e nuclear data community.\nIt will allow parameter optimization using enha nced formalisms\, including experimental effects\, that better match compl ex experimental data. \nThen those evaluated parameters can immediately be passed off to AMPX to be reconstructed with the exact same cross section model and\nbe put into a data library for subsequent testing using SCALE a nd the Valid Benchmark suite \\cite{VALID} or other suitable benchmark sui tes. \n\n{\\bf Acknowledgments:} This work was supported by the U.S. Depar tment of Energy (DOE) Nuclear Criticality Safety Program\, which is funded and managed by the National Nuclear Security Administration for DOE.\n\n\ n\\thispagestyle{empty}\n\\begin{thebibliography}{1}\n\\bibitem{SAMMY} N.M . Larson\, {\\em ``Updated Users' Guide for SAMMY: Multilevel R-matrix Fit s to Neutron Data Using Bayes' Equations"}\, ORNL/TM-9179/R8 (2008)\n\n \ n\\bibitem{AMPX} D. Wiarda\, M. L. Williams\, C. Celik\, and M. E. Dunn\,\ n {\\em AMPX-2000: A Cross-Section Processing System for Generating Nucle ar Data for Criticality Safety Applications}\,\n International Conference on Nuclear Criticality Safety (ICNC 2015).\n\n\\bibitem{SCALE} W. A. Wies elquist\, R. A. Lefebvre\, and M. A. Jessee\, Eds.\, {\\em SCALE Code Syst em}\,\n ORNL/TM-2005/39\, Version 6.2.4\, Oak Ridge National Laboratory\, Oak Ridge\, TN (2020).\n \n \n\\bibitem{ND10} G. Arbanas\, J.M. Brown\, A.M. Holcomb\, and D. Wiarda\,\n {\\em Bayesian Monte Carlo Evaluation Fr amework for Cross Sections Nuclear Data and\n Integral Benchmark Experi ments}\, in the proceedings of the ANS Winter Meeting\, NCSP Session (2020 )\n\n\\bibitem{GNDS} Specifications for the Generalised Nuclear Database S tructure (GNDS)\n \\href{https://www.oecd-nea.org/science/wpec/documents/7 519-GNDS.pdf}{https://www.oecd-nea.org/science/wpec/documents/7519-GNDS.pd f}\,\n(accessed September 15\, 2021).\n\n\n \n\\bibitem{VALID} W. J. Mars hall and B. T. Rearden\,\n {\\em The SCALE Verified\, Archived Library of Inputs and Data – VALID}\,\n ANS NCSD 2013 - Criticality Safety in the Modern Era: Raising the Bar\, Wilmington\, NC\, September 29 –October 3 \, 2013\, on CD-ROM\, American Nuclear Society\, LaGrange Park\, IL (2013) .\n\n\n\\end{thebibliography}\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/890/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/890/ END:VEVENT BEGIN:VEVENT SUMMARY:International criticality benchmark comparison exercise in suppor t of nuclear data validation DTSTART:20220727T150900Z DTEND:20220727T152100Z DTSTAMP:20260420T153400Z UID:indico-contribution-994@indico.frib.msu.edu DESCRIPTION:Speakers: Nicolas Leclaire\n\nThe development of bias estimati on methodologies has been a great tool for data uncertainty assessments. I n particular\, keff data and their uncertainties are becoming paramount fo r criticality-safety and reactor physics assessment. Moreover\, the adjust ment of cross sections implemented to match experimental keff within their uncertainty margins is important to produce the requested bias and associ ated uncertainty. A computation error on keff can strongly influence the c alculated bias and its associated uncertainty. Therefore\, it is highly re commended to have a high confidence level on the calculated keff values. M any Monte Carlo and deterministic codes and various nuclear data libraries are available for assessing keff. Since the bias due to the Monte Carlo s imulation is relatively small\, the biases in a calculation are mostly in connection to the nuclear data libraries. \n\nThere had been initially in 2018 a motivation under the US/DOE NCSP1 for promoting inter-comparison ex ercise. The focus was mainly on keff values produced by various Monte Carl o codes for a three year period. \n\nThe aim of the keff inter-comparison exercise was:\n• To check the consistency between results from different codes using the same nuclear data libraries and therefore test the “ind ependent modelling effect”\; this task allowed providing a rigorous basi s for quality experiments with a view to validate nuclear data\,\n• If l ack of agreement exists\, to find out the source of the discrepancy betwee n the Monte Carlo model\, interpretation of benchmark (detailed/simplified )\, revision number differing\, processing of nuclear data libraries and c orrect the input decks so that all validation databases involve input deck s describing the same benchmark model\,\n• To provide feedback on the nu clear data libraries (cross sections and thermal scattering) through the c omparison of results using different nuclear data libraries and through tr ending analyses.\nA progressive analysis was done from 2019 dealing with t he keff comparison of critical benchmarks involving Pu\, HEU (2019)\, LEU\ , IEU (2020)\, MIX\, U233 (2021) fissile media. Quite a few mistakes were highlighted on input decks explaining some calculated discrepancies. Issue s on nuclear data processing were also outlined\, such as the processing b y AMPX2 of the incoherent elastic scattering of hydrogen cross sections be ing a good example. \n\nThe main conclusions of this inter-comparison exer cise will be presented in the final paper along with some analysis on keff sensitivity values. It should also be noted that this work is complementa ry to the work done in the framework of the VaNDaL3 whose aim is to ensure that existing validation databases are under quality assurance and will a lso help improve the quality of the ICSBEP/DICE4 database.\n\nFinally\, qu ite recently the need for comparison on reactor physics kinetics parameter s and shielding benchmarks values has arisen and it was proposed and accep ted to extend the exercise until FY 2024.\n\n[1] https://ncsp.llnl.gov\n\n [2] Alex Lang\, Alex Shaw\, Chris Chapman\, and William Marshall\, “Disc overy of AMPX Thermal Scattering Law Processing Issue for Solid Moderators ”\, ANS transactions\, Volume 124\, Number 1\, June 2021\, pages 368-371 .\n\n[3] https://www.oecd-nea.org/jcms/pl_23388/wpec-subgroup-45-sg45-vali dation-of-nuclear-data-libraries-vandal-project\n\n[4] International Handb ook of Evaluated Criticality Safety Benchmark Experiments\, NEA/NSC/DOC(95 )03/I\, Volume I\, 2020 edition\n\nhttps://indico.frib.msu.edu/event/52/co ntributions/994/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/994/ END:VEVENT BEGIN:VEVENT SUMMARY:On the need for precise nuclear structure data for high quality (n \, n’ γ) cross section measurements DTSTART:20220728T152600Z DTEND:20220728T153800Z DTSTAMP:20260420T153400Z UID:indico-contribution-829@indico.frib.msu.edu DESCRIPTION:Speakers: Markus Nyman\, Cyrille de Saint Jean\, Philippe Dess agne\, François Claeys\, Pascal Romain\, M. Boromiza\, Roberto Capote\, A rjan Plompen\, Nicolas Dari Bako\, Maëlle Kerveno\, Catalin Borcea\, Ruud Wynants\, Marc Dupuis\, Carlos Paradela Dobarro\, Stephane Hilaire\, Jean -Claude Drohé\, Alexandru Negret\, A. Olacel\, Greg Henning\n\nThe necess ary improvement of evaluated nuclear data for nuclear applications develop ment is possible through new and high-quality experimental measurements\, often combined with appropriate nuclear-reaction modelling. In particular\ , improving inelastic cross-section evaluations requires new and high-qual ity data. \n\nOur group at CNRS-IPHC developed an experimental program to measure (n\, n’ gamma) cross-sections using prompt gamma-ray spectroscop y and neutron energy determination by time-of-flight [1-3]. To extract\, f rom these partial data\, the total inelastic cross-section\, we rely on th eoretical model as well as nuclear structure data such as gamma ray emissi on probabilities.\n\n\nThis structure information\, tabulated in databases such as ENSDF\, comes with uncertainty (although\, in some cases\, the un certainty may not even be known or quoted in the tables). This directly af fects the precision of our results\, regardless of how good the measuremen t is.\n\n\nTo reach the extra precision needed for evaluation\, we want to lower the uncertainties on nuclear structure data\, so that it reflects d irectly on the precision of experimentally derived cross-sections.\n\n\nIn the talk\, we will present the issue of limited precision structure data and its impact on nuclear reaction data quality in the case of neutron ine lastic scattering measurements. We will discuss how to foresee and mitigat e the issue. Finally\, we will list key nuclear structure data that are ne eded to directly improve experimentally extracted cross-section data.\n\n\ n- [1] “What can we learn from (n\, x n γ) cross sections about reactio n mechanism and nuclear structure ?”\, by Kerveno\, Maëlle and Dupuis\, Marc and Borcea\, Catalin and Boromiza\, Marian and Capote\, Roberto and Dessagne\, Philippe and Henning\, Greg andHilaire\, Stéphane and Kawano\, Toshihiko and Negret\, Alexandra and Nyman\, Markus and Olacel\, Adina an d Party\, Eliot and Plompen\, Arjan and Romain\, Pascal and Sin\, Mihaela. ND 2019 : International Conference on Nuclear Data for Science and Techno logy (2019). 10.1051/epjconf/202023901023 https://hal.archives-ouvertes.fr /hal-02957494 \n- [2] “How to produce accurate inelastic cross sections from an indirect measurement method ?”\, by Kerveno\, Maëlle and Hennin g\, Greg and Borcea\, Catalin and Dessagne\, Philippe and Dupuis\, Marc an d Hilaire\, Stéphane and Negret\, Alexandru and Nyman\, Markus and Olacel \, Adina and Party\, Eliot and Plompen\, Arjan in EPJ N - Nuclear Sciences & Technologies 4\, (2018). 10.1051/epjn/2018020 https://hal.archives-ouve rtes.fr/hal-02109918 \n- [3] “From γ emissions to (n\,xn) cross section s of interest : The role of GAINS and GRAPhEME in nuclear reaction modelin g”\, by Kerveno\, M. and Bacquias\, A. and Borcea\, C. and Dessagne\, Ph . and Henning\, G. and Mihailescu\, C. and Negret\, A. and Nyman\, M. and Olacel\, A. and Plompen\, M. and Rouki\, C. and Rudolf\, G. and Thiry\, C. in European Physical Journal A 51\, 12 (2015). 10.1140/epja/i2015-15167-y https://hal.archives-ouvertes.fr/hal-02154831\n\nhttps://indico.frib.msu. edu/event/52/contributions/829/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/829/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Reactor Antineutrino Energy Spectra and Associated Unc ertainties Using the GEF Model DTSTART:20220727T130000Z DTEND:20220727T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-723@indico.frib.msu.edu DESCRIPTION:Speakers: Magali Estienne (Subatech)\, Karl-Heinz Schmidt\, Mu riel Fallot\n\nReactor antineutrino energy spectra are the subject of acti ve experimental researches nowadays\, either through large reactor neutrin o experiments\, short baseline neutrino experiments at research reactors o r through dedicated nuclear physics measurements of the properties of the fission products. The summation method relies on the use of nuclear data t o build the reactor antineutrino energy spectrum emitted by a reactor\, or after the fission of each actinide at the origin of the thermal power in- core[1\,2]. It is a unique alternative to converted spectra[3]\, which rel y on measurements of integral beta spectra and a subsequent conversion app roach. The summation method presents in addition the advantage of being pr edictive \; it can be used for the computation of reactor antineutrino spe ctra associated to innovative fuels\, of interest for non-proliferation pu rposes\, or to predict the antineutrino spectrum in wider energy ranges (l ower/larger energies) than accessible with the conversion method\, of inte rest for the fundamental study of neutrino properties. \nDuring the last d ecade\, the precision achieved by the summation method to predict reactor antineutrino spectra has been greatly improved by nuclear data measurement s using the Total Absorption Gamma-ray Spectroscopy technique (TAGS)[4]\, reaching a level comparable to the conversion method[1\,3]. The main drawb ack of the summation predictions is the difficulty to propagate the uncert ainties of nuclear data on the antineutrino observable\, which require cov ariance matrices for fission yields and for beta decay data. Covariance ma trices for fission yields could be obtained consistently with predictions for fission yields from a model such as the GEF model[5].\nRecently\, we h ave used the reactor antineutrino observable to improve the GEF model [6]\ , making it a useful tool to predict fission yields for antineutrino spect ra calculations\, along with their uncertainties. The level of prediction achieved by the antineutrino flux obtained with the GEF fission yields is now close to the one obtained in[4]\, it is thus possible to use GEF to co mpute the associated uncertainties. \nAt this conference\, we will present new summation method antineutrino predictions based on fission yields com puted with the new version of the GEF code\, updated with the latest Total Absorption Gamma-ray Spectroscopy (TAGS) results [6] and\, for the first time\, with their associated computed uncertainties. Spectra will be displ ayed for the main uranium and plutonium isotopes contributing to the fissi ons in a Pressurized Water Reactor\, but also for various fuels to be used in innovative reactor designs. The results will be compared with recent m easurements of reactor antineutrino flux and energy spectra.\n\n[1] Th. A. Mueller et al.\, Phys.Rev. C 83 \, 054615 (2011)\n[2] M. Fallot et al.\, Phys. Rev. Lett. 109 \, 202504 (2012)\n[3] P. Huber\, Phys. Rev. C 84\, 0 24617 (2011). Also presented in ND2013.\n[4] M. Estienne et al.\, Phys. Re v. Lett. 123\, 022502 (2019).\n[5] K.-H. Schmidt\, B. Jurado\, C. Amouroux \, C. Schmitt\, Nucl. Data Sheets 131 (2016) 107\n[6] K.-H. Schmidt\, M. E stienne\, M. Fallot et al.\, Nuclear Data Sheets Volume 173\, (2021)\n\nht tps://indico.frib.msu.edu/event/52/contributions/723/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/723/ END:VEVENT BEGIN:VEVENT SUMMARY:Spallation reaction study for long-lived fission products in nucle ar waste: Cross-section measurements for 107Pd on proton and deuteron at d ifferent reaction energy DTSTART:20220728T183000Z DTEND:20220728T185400Z DTSTAMP:20260420T153400Z UID:indico-contribution-667@indico.frib.msu.edu DESCRIPTION:Speakers: He Wang (RIKEN)\n\nReduction in the quantity of high -level radioactive waste in the spent fuel is one of the major issues for the use of a nuclear power plant. In recent years\, substantial research a nd development activity has been devoted to the partitioning and transmuta tion technology for the reduction and recycling of radioactive waste. The transmutation on the long-lived fission products (LLFPs) in the spent fuel has attracted much attention because the LLFP nuclei have large radiotoxi cities and long lifetimes\, and they can be produced continuously even in the accelerator driven systems and next-generation nuclear reactors. It is essential to find effective reactions for the LLFP transmutation. However \, experimental reaction data are currently lacking.\n\nAiming at bringing an invention to the nuclear transmutation on LLFP\, we have performed sys tematics studies on the proton- and deuteron-induced spallation reactions for the long-lived fission products ($^{137}$Cs\, $^{90}$Sr\, $^{107}$Pd\, $^{93}$Zr\, $^{126}$Sn and $^{79}$Se) at the RIKEN RI beam factory. To ov ercome the difficulty in handling LLFP targets\, we introduce the inverse kinematics technique. Namely\, the LLFP nuclides are made as beams by in-f light fission of a $^{238}$U primary beam at 345 MeV/nucleon in the BigRIP S separator. The beams of LLFP nuclei impinge on hydrogen and deuteron tar gets. The reaction residues are analyzed by the ZeroDegree spectrometer. B oth the LLFP beams and reaction residues are unambiguously identified even t-by-event.\n\nThe present work focuses on $^{107}$Pd\, which is a typical LLFP nuclide with a half-life of 6.5 $\\times$ 10$^6$ years. Cross sectio ns on both proton and deuteron were successfully obtained. To find out the optimal energy for nuclear transmutation\, cross sections were obtained a t different incident energies ranging from 50 to 200 MeV/nucleon. The new data were compared with theoretical calculations with intra-nuclear cascad e and evaporation processes by using the PHITS framework as well as the DE URACS including the breakup process of deuteron. In the presentation\, the detailed results on the LLFP nuclide $^{107}$Pd as well as the potential of spallation reaction on the LLFP transmutation will be discussed. \n\nTh is work was supported and funded by ImPACT Program of Council for Science\ , Technology and Innovation (Cabinet Office\, Government of Japan).\n\nhtt ps://indico.frib.msu.edu/event/52/contributions/667/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/667/ END:VEVENT BEGIN:VEVENT SUMMARY:Sensitivity analysis of JEFF-3.3 and ENDF/B-VIII.0 for a light wat er reactor DTSTART:20220728T160200Z DTEND:20220728T161400Z DTSTAMP:20260420T153400Z UID:indico-contribution-898@indico.frib.msu.edu DESCRIPTION:Speakers: Francisco Alvarez-Velarde (CIEMAT)\n\nThe safe manag ement of the spent nuclear waste (SNF) requires a special effort of charac terization\, since its isotopic composition is the key to its transport\, handling and storage by means of the decay heat\, gamma emission and neutr on emission it produces due to radioactive decay.\nThe effort is being don e in the frame of the EU EURAD project (European Joint Programme on Radioa ctive Waste Management) project\, funded under H2020-Euratom-1.2 programme \, where its Work Package 8 (Spent Fuel Characterization and Evolution Unt il Disposal) is in charge of producing procedures to determine the nuclide content of SNF\, including uncertainties (in particular\, in Task 2.1: Th eoretical study of SNF source terms).\nAmong the work to be done in the me ntioned task\, sensitivity studies have been proposed to define confidence limits on the current nuclear data libraries and identify nuclear data re quiring improvement. The goal of these sensitivity calculations is to esti mate the uncertainties in the isotopic composition after the irradiation d ue to some parameters. Differences between the reference calculation and t he sensitivity one are then evaluated to obtain which parameter provides a larger impact and has to be hence better quantified.\nIn this work\, a se nsitivity study involving the most recent versions of two nuclear database s\, JEFF-3.3 and ENDF/B-VIII.0\, has been done. A simulation of the Takaha ma-3 reactor\, a Japanese light water reactor (LWR) operated by Kansai Ele ctric Power Company (KEPCO) whose experimental information was available a t the NEA SFCOMPO\, has been done with these two libraries. In particular\ , the fifth pellet of the SF95 rod has been chosen for this task. This pel let had an initial $^{235}$U enrichment of 4.1% and was irradiated for a t otal of 30.4 GWd/tU.\nThe reference code used in this task has been EVOLCO DE 2.0\, successfully validated against LWR experimental data in previous studies. EVOLCODE 2.0 is a combined neutronics and depletion evolution sim ulation code developed at CIEMAT to describe the burnup evolution of nucle ar reactors. The neutron transport is currently being solved by the genera l MC transport code MCNP/X while the depletion of the materials is carried out by the activation code ACAB.\nResults of this sensitivity calculation have been calculated for a list of isotopes due to their relevance in dif ferent parameters of interest. This list includes actinides relevant for o peration or transmutation causes\, fission products for criticality safety reasons\, for radioprotection\, for post irradiation examination comparis on and impurities in the fuel. For the actinides\, a small impact can be f ound\, because only $^{242M}$Am presents a significant discrepancy (of aro und 22%)\, while the other actinides show differences smaller than 6%. The discrepancy of $^{242M}$Am comes as a consequence of having different val ues of the $^{241}$Am capture cross sections in both libraries. In particu lar\, since EVOLCODE requires the calculation of one-group cross sections to perform the irradiation\, this difference could be quantified. A system atic ~37% larger value of the $^{241}$Am capture cross sections along burn -up was found for JEFF-3.3 regarding ENDF/B-VIII.0.\nMost of the studied f ission products show similar results for both libraries\, with differences smaller than 5%. However\, some of them show a significant discrepancy. T his is the case of $^{14}$C\, $^{109}$Ag\, $^{110M}$Ag\, $^{129}$I\, $^{14 2}$Nd\, $^{151}$Eu\, $^{157}$Gd and $^{158}$Gd. An exhaustive analysis has been done for each of these fission products to understand the origin of the discrepancies.\nAs an example\, $^{157}$Gd shows a discrepancy between libraries of around 50%. This isotope appears due to several processes. F irst\, it can be generated as an independent fission yield. Second\, it ca n be created by decay from other direct fission yields having A=157. Third \, it can be generated by captures in $^{156}$Gd. Finally\, it can appear from a successive capture and decay starting in $^{156}$Eu. $^{156}$Eu is a β$^{-}$ emitter with a half-life of 15.2 d that is created by its own c hain of fission yields. However\, having this long enough half-life togeth er with a large enough capture cross section\, makes that its capture rate competes with its decay\, leading to $^{157}$Eu\, parent of $^{157}$Gd. T his is the cause of the discrepancy of 50% between libraries. This cross s ection has a long energy range up to around 1 eV where there is a discrepa ncy of two orders of magnitude. This creates a one-group cross section of 342 b in JEFF-3.3 and 52 b in ENDF/B-VIII.0. None of these libraries provi des the uncertainty in the $^{156}$Eu capture cross section. Besides\, the larger $^{156}$Eu capture in JEFF-3.3 also causes a smaller amount in $^{ 156}$Eu and hence a smaller $^{156}$Gd amount of ~11.3% at the end of the irradiation in this library\, with respect to ENDF/B-VIII.0.\nRecommendati ons to improve the JEFF and ENDF/B libraries will be provided as a result of the sensitivity analysis performed as part of this work.\n\nhttps://ind ico.frib.msu.edu/event/52/contributions/898/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/898/ END:VEVENT BEGIN:VEVENT SUMMARY:Surrogate Modeling for Fission Cross Sections\, Criticality Studie s\, and Uncertainty Quantification DTSTART:20220727T133600Z DTEND:20220727T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-725@indico.frib.msu.edu DESCRIPTION:Speakers: Christian Brazell (Texas A&M University)\n\nChristia n Brazell\n10/15/21\nTAMU-LLNL\nLLNL-ABS-827556\nND2022\n\nSurrogate Model ing for Fission Cross Sections\, Criticality Studies\, and Uncertainty Qua ntification\nABSTRACT\n\nComputational methods have advanced to the point where\, in many cases\, the main source of uncertainty in neutronics calcu lations comes from the underlying Nuclear Data (ND). Assessing the impact of the underlying uncertainties can be a challenging and computationally e xpensive task. Yet\, it is critical to understand how ND affect the predic ted behavior of nuclear systems. This is the goal of Uncertainty Quantific ation (UQ) and Sensitivity Analysis (SA)\, research areas of great interes t to nuclear engineering researchers and practitioners alike. The present study considers the sensitivities of the effective neutron multiplication factor (keff) to multi-group fission cross sections (XS). Machine Learning (ML) techniques are employed to enable and accelerate UQ research beyond the capabilities of current methods. \nAdjoint methods are used to examine the sensitivity of a Quantity of Interest (QoI) to perturbations in a mod el parameter\, such as ND. As in the case of this study\, computing the se nsitivity of keff to uncertainty in multigroup XS using the adjoint requir es only two neutronics calculations. While the adjoint methods are computa tionally inexpensive\, assumptions are made along the way which do not nec essarily hold outside of small XS perturbations. Such classical adjoint se nsitivities are based on first-order approximations\, and cannot capture t he true non-linearity of keff’s response to uncertain XS values. This le ads to inaccuracies when evaluating the uncertainty of keff over the entir e uncertain region of the XS.\nThis study explores a new approach to UQ an d SA using data-driven methods. Advances in ML have shown that regression models are able to capture complex non-linear behavior in systems\, exhibi ting high accuracy and precision in their predictions. Here\, we use ML to train surrogate models that map a realization of a XS to the correspondin g keff for a given criticality problem. Once trained\, these models can ac curately compute keff across the full uncertain distribution of the XS. \n Realizations of the uncertainty in the XS are constructed by sampling fro m the cross section’s multi-group covariance matrix. These samples form a set of inputs which are representative of the uncertainty in the evaluat ed data. The keff corresponding to each sample is then computed using a n eutron transport code. This set of (XS\, keff) pairs is then used to train \, validate\, and test the ML models. Performing this analysis using vario us critical benchmark experiments\, multiple nuclides’ fission cross se ctions\, and several ML models\, the present study then compares the perfo rmance of the ML models to each other and to the adjoint solution as a bas eline. \nInitial results showing the performance of the ML methods on a te st set can be seen in Figure 1. Here\, Gaussian Process (GP) regression\, Support Vector Machine (SVM) regression\, Multivariate Adaptive Regression Splines (MARS)\, and Artificial Neural Networks (ANNs) are used as surrog ates to map the U-235 fission XS to keff in the Godiva benchmark. The dist ribution of predicted keff values is compared to the true distribution in the test set\, with the difference (residual) between the two being plotte d below. Each method shows strong performance in capturing the full relati onship between the multigroup XS and the system criticality\, with some sh owing a mean absolute error in keff as low as 2 pcm.\n\n \n\nFigure 1. The performance of each regression method for the Godiva problem is shown in the histogram/residual plots above. The models map realizations of the U-235 fission XS to keff.\n\nThis study demonstrates the usefulness of ML in nuclear data applications. Computational costs are often prohibitive in UQ/SA tasks\, and perturbation methods designed to avoid these costs invo lve assumptions which do not always hold true. By building surrogate model s which capture the nonlinear relationship between nuclear data and applic ations such as criticality\, UQ and other such studies can be enabled with negligible cost. This study also opens the door to a broad range of futur e work. Directions for further research include exploring the data require ments for good model performance and implementation of the UQ for more com plex QoIs\, such as reaction rates\, multiphysics effects\, and transient system behaviors.\n\nhttps://indico.frib.msu.edu/event/52/contributions/72 5/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/725/ END:VEVENT BEGIN:VEVENT SUMMARY:GIDI+: a GNDS 2.0 suite of C++ APIs to access nuclear and atomic d ata for use in neutronic transport codes. DTSTART:20220725T170600Z DTEND:20220725T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-854@indico.frib.msu.edu DESCRIPTION:Speakers: Caleb M Mattoon\, Godfree Gert\, Bret Beck (LLNL)\n \nTransport codes used to simulate reactors\, critical assemblies\, medica l diagnostics\, etc. need access to nuclear and atomic data (e.g.\, data f rom ENDF/B-VIII.0 and EPICS2017). The Generalized Nuclear Data Structure ( GNDS) supports storing evaluated and processed nuclear and atomic data - p rocessed data are data in a form more suitable for transport codes (e.g.\, cross sections reconstructed from resonance parameters\, heated cross sec tions\, multi-grouped data). The specification for version 2.0 of the GNDS standard has recently been finalized. In this talk we will describe GIDI+ which is a suite of C++ APIs for reading GNDS 2.0 data\, performing multi -group operations and sampling the data for Monte Carlo transport.\n\nGIDI + is comprised of the following C++ APIs:\n\n* PoPI: Properties of Particl es Interface\n1. Supports reading and accessing GNDS PoPs data. PoPs data describe properties of particles including a particle’s mass\, spin\, ha lflife and decay particles.\n\n* GIDI: General Interaction Data Interface\ n1. Supports reading and accessing data in a GNDS reactionSuite. A reactio nSuite describes the nuclear or atomic reactions for a projectile hitting a target (e.g.\, “n + O16”).\n2. Supports reading GNDS map files. A ma p file links many reactionSuites together to form a nuclear and atomic dat a library.\n3. Provides functions for finding and reading in a reactionSui te for a specified projectile and target (e.g.\, “n + Th232”) found in a map file.\n4. Provides functions for accessing multi-group data in a re actionSuite which includes performing operations on the multi-group data ( e.g.\, summing\, collapsing and transport correcting with the Pendlebury/U nderhill formalism).\n5. Allows one to mark some reactions as disabled in a reactionSuite instance. Disables reactions are skipped by multi-group ro utines and MCGIDI. For example\, one can disable the (n\,3n) reaction. Wit h this reaction disabled\, a subsequent call to the total multi-group cros s section will not include the (n\,3n) cross section.\n5. Support specifyi ng modifications to reaction cross sections to perform sensitivity studies .\n\n* MCGIDI: Monte Carlo GIDI\n1. Loads data from GIDI classes into clas ses that are better suited for Monte Carlo lookup\, sampling and require l ess memory.\n2. Provides functions to evaluate the total cross section or the cross section for a reaction.\n3. Provides functions for sampling a re action from the reactions in a reactionSuite.\n4. Provides functions for s ampling outgoing particle data for a reaction.\n5. Supports continuous ene rgy and multi-group cross section data.\n6. Supports unresolved region pro bability tables.\n7. Provides serializing a reactionSuite’s data which c an then be broadcasted to MPI processes and GPUs.\n8. Supports shared memo ry to reduce footprint.\n\nCurrently\, GIDI+ supports transporting n\, p\, d\, t\, h\, $\\alpha$ and $\\gamma$. For $\\gamma$ both photo-atomic and photo-nuclear data are supported. For neutrons\, Thermal Neutron Scatterin g Law data are supported. We are currently adding support for electron tra nsport and will describe its status at the meeting.\n\nGIDI+ is freely ava ilable under the open-source MIT license and can be downloaded from https: //github.com/LLNL/gidiplus.\n\nPrepared by LLNL under Contract DE-AC52-07N A27344.\n\nLLNL-ABS-827368\n\nhttps://indico.frib.msu.edu/event/52/contrib utions/854/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/854/ END:VEVENT BEGIN:VEVENT SUMMARY:High precision re-determination of the half-lives of $^{146}$Sm\, $^{148}$Gd\, and $^{154}$Dy. DTSTART:20220726T163000Z DTEND:20220726T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-698@indico.frib.msu.edu DESCRIPTION:Speakers: Nadine Mariel Chiera\n\nRadioisotopes with half-live s (t$_{1/2}$) in the order of millions of years play an essential role in the description of galactic events\, as well as in the nuclear dating of e xtraterrestrial samples. Among the different benchmark radionuclides for a strophysics and geophysics studies\, the radio-lanthanides $^{146}$Sm\, $^ {148}$Gd and $^{154}$Dy are of especial interest. In fact\, through the pu re α-decay sequence $^{154}$Dy → $^{150}$Gd → $^{146}$Sm → $^{142}$ Nd\, these radionuclides directly influence both the abundance of $^{146}$ Sm\, as well as the natural isotopic composition of stable Nd\, thus contr ibuting to the Sm/Nd chronometer. The latter is one of the most powerful t ools to date silicate differentiation and primitive crust formation events occurred during the first hundreds of million years (My) of the Solar Sys tem [1\, 2]. Furthermore\, photodisintegration processes on $^{148}$Gd\, t he rate of the $^{144}$Sm(α\,γ)$^{148}$Gd reaction\, and competing nucle ar reactions like $^{154}$Dy(α\, γ)$^{158}$Er\, $^{154}$Dy(γ\, α)$^{15 0}$Gd\, and $^{154}$Dy(γ\, n)$^{152}$Dy [3-5]\, just to mention a few\, are essential for a better understanding of the nucleosynthetic processes that led to the present isotopic abundances in the lanthanide region. It i s apparent that an accurate knowledge on the nuclear properties of the abo ve-mentioned radionuclides is crucial. However\, the currently available d ata for the half-life of $^{146}$Sm\, $^{148}$Gd\, and $^{154}$Dy are inco nsistent\, or affected by uncertainties even up to 50% [6-8]. Recently\, t he re-evaluated half-life data of a considerable number of radionuclides s howed a significant disagreement with previous values\, as in the case of $^{146}$Sm [9]. The shorter measured half-life for this radio-lanthanide i mplies a higher abundance of $^{146}$Sm in the early Solar System\, and th us\, planetary events dated with the $^{146}$Sm-$^{142}$Nd chronometer con verge now to a shorter time span than previously estimated. Reasons for th ese imprecise nuclear data lie in the difficulty of obtaining samples of t he isotopes of interest in sufficient amounts and purity\, together with i nherent problematics in performing such demanding measurements. In this wo rk\, which belongs to the initiative “ERAWAST - Exotic Radionuclides fro m Accelerator Waste for Science and Technology” [10]\, we could obtain s ufficient amounts of $^{146}$Sm\, $^{148}$Gd\, and $^{154}$Dy by reprocess ing irradiated Ta materials available at the PSI accelerator-facilities. T he re-determination of the half-lives of the above-mentioned radio-lanthan ides proceeded by successively applying the “direct” or the “decay ” method\, depending on the order of magnitude of the expected t$_{1/2}$ . A scheme for both methods is presented in the Figure.\nHere\, in the fra mework of the ERAWAST project\, preliminary results on the measured half-l ives of $^{148}$Gd and $^{154}$Dy\, together with the first steps towards determining the decay constant of $^{146}$Sm\, will be presented.\n\n![Fig ure][1]\n*Figure:* Process followed for the determination of half-lives be low 150 years (a) and the determination of half-lives above 150 years (b). \n\n**Acknowledgement**\nThis project is funded by the Swiss National Scie nce Foundation (SNF grant no 200021-159738).\n\n**References**\n[1] Bouvie r\, A.\, and M. Boyet. Nature 537\, no. 7620 (2016): 399-402 [2] Harper\, C. L.\, and Stein B. Jacobsen. Nature 360\, no. 6406 (1992): 728-732 [3] S cholz\, P.\, H. Wilsenach\, H. W. Becker\, A. Blazhev\, F. Heim\, V. Fotei nou\, U. Giesen et al. Physical Review C 102\, no. 4 (2020): 045811. [4] R auscher\, T. Physical Review C 73\, no. 1 (2006): 015804. [5] Woosley\, S. E.\, and W. M. Howard. The Astrophysical Journal 354 (1990): L21-L24. [6] Khazov\, Yu\, A. Rodionov\, and G. Shulyak. Nuclear Data Sheets 136 (2016 ): 163-452. [7] Nica\, N. Nuclear Data Sheets 117 (2014): 1-229. [8] Reich \, C. W. Nuclear Data Sheets 110\, no. 10 (2009): 2257-2532. [9] Kinoshita \, N.\, M. Paul\, Y. Kashiv\, P. Collon\, C. M. Deibel\, B. DiGiovine\, J. P. Greene et al. Science 335\, no. 6076 (2012): 1614-1617. [10] Schumann\ , D.\, and J. Neuhausen. Journal of Physics G: Nuclear and Particle Physic s 35\, no. 1 (2007): 014046.\n\n\n [1]: https://indico.frib.msu.edu/event /52/contributions/698/attachments/225/1484/206_Figure.tiff\n\nhttps://indi co.frib.msu.edu/event/52/contributions/698/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/698/ END:VEVENT BEGIN:VEVENT SUMMARY:Towards the experimental validation of a small Time-Projection-Cha mber for the quasi-absolute measurement of the fission cross section DTSTART:20220725T193300Z DTEND:20220725T194500Z DTSTAMP:20260420T153400Z UID:indico-contribution-762@indico.frib.msu.edu DESCRIPTION:Speakers: Ludovic Mathieu\, Olivier Bouland\, Maria Diakaki\, Gilles Noguere\, Mourad Aiche\, Carole Chatel\n\nImprovement in neutronics codes jointly with the advent of high performance computing systems made the calculations more sensitive to the nuclear data. The latter are used b oth for solving the neutron transport equation together and for nuclear in strumentation validation and operation. Hence\, it becomes relevant to imp rove the knowledge of the fission cross section of fertile secondary actin ides as the 242Pu one\, which is fissile in a fast neutron flux. This isot ope has been chosen as a deposit for the fission chamber for the online mo nitoring of the fast flux in the experimental irradiation reactor Jules Ho rowitz (RJH) at CEA Cadarache. As any nuclear thermal or fast neutron reac tor\, it has a high neutron flux around 1 MeV. This motivates the improvem ent of the fission cross section for the fertile 242Pu isotope\, for which the various experimental data show a dispersion of 10 to 15% around 1 MeV .\nThe standard measuring technique of a fission cross section is based on simultaneous comparison between the target nucleus and another one so-cal led reference nucleus. Usually secondary standards are used as reference r eactions\, known within a few percent\, and calibrated to a primary standa rd of very high precision. The classical isotope chosen as reference for f ission cross sections is the 235U whose fission cross section is known wit h an accuracy of 0.5 to 5%. The use of the same reaction as reference lead s to correlations between the different measurements. Our approach aims to produce an independent measurement and to bypass the secondary standard b y performing the measurement directly with the primary standard. Thereby\, the obtained measurements are completely uncorrelated to any other. The r eaction cross section 1H(n\,n)p was chosen to achieve our goal since the l atter is known from 0.2 to 0.5% over the energy range 0-20 MeV\, allowing very accurate measurements. Quantifying the neutron flux with the 1H(n\,n) p reaction requires a precise count of the number of recoil protons emitte d by a hydrogenated sample of chosen thickness irradiated by this neutron flux. It is therefore essential to use a recoil proton detector having a p erfectly known intrinsic efficiency in all operating regimes and a linear response with respect to the input signal. Above 1 MeV\, the use of a sili con junction is fully adequate. However\, this device is unsuitable at low er energies when a large number of gamma and electrons generate a cripplin g background noise. This presentation will therefore focus on the recent d evelopment and validation of the Gaseous Proton Recoil Telescope (GPRT)\, insensitive to gamma/electrons noise. This detector uses the Micromegas te chnology for the detection plane\, contains a small time-projection chambe r and will be used for the 242Pu fission cross section measurement from 20 0 keV to a few MeV. During this work\, the optimal conditions and the intr insic efficiency of this detector have been investigated and will be prese nted. The track reconstruction and the background rejection will also be s hown.\n\nhttps://indico.frib.msu.edu/event/52/contributions/762/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/762/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron production double differential cross section from Carbon\, Niobium and Bismuth targets bombarded by 290 MeV/u $^136$Xe ions DTSTART:20220728T153800Z DTEND:20220728T155000Z DTSTAMP:20260420T153400Z UID:indico-contribution-830@indico.frib.msu.edu DESCRIPTION:Speakers: Cheolmin Ham\, Eunjin In\, Seung-Woo Hong\, Heekyun Baek\, Shogo Izumitani\, Jeongho Kim\, Tae-Su Park\, Nobuhiro Shigyo\, Da l-Ho Moon\n\nThe neutron production double-differential cross sections (DD X) from thin $^{nat}$C\, $^{93}$Nb and $^{209}$Bi targets bombarded by 290 MeV/u $^{136}$Xe ions were measured by using the Heavy Ion Medical Accele rator in Chiba (HIMAC) facility of National Institute of Radiological Scie nces (NIRS)\, Japan. The NE213 liquid organic scintillators were placed at the angles of 15°\, 30°\, 45°\, 60°\, 75° and 90° to measure DDX. W e used the inverse time-of-flight method to obtain energy distribution of neutrons. By integrating the DDX over the incident neutron energies\, the differential cross sections were measured. The background neutron events g enerated by projectiles which collide with air after passing through the t arget were estimated by Monte-Carlo simulation. The contribution to the DD X due to the background events was removed by using Monte-Carlo simulation codes\, GEANT4\, MCNP and PHITS. The experimental double differential cro ss sections are compared with the simulation results with or without the r emoval of the background events due to the collision of heavy ions with th e air.\n\nhttps://indico.frib.msu.edu/event/52/contributions/830/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/830/ END:VEVENT BEGIN:VEVENT SUMMARY:A Study of the Covariance Data in ENDF/B VIII.0 for Low Z Isotopes DTSTART:20220725T192100Z DTEND:20220725T193300Z DTSTAMP:20260420T153400Z UID:indico-contribution-774@indico.frib.msu.edu DESCRIPTION:Speakers: Kent Parsons (Los Alamos National Laboratory)\n\nhtt ps://indico.frib.msu.edu/event/52/contributions/774/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/774/ END:VEVENT BEGIN:VEVENT SUMMARY:Theoretical Calculations and Evaluations for n+28\,29\,30Si Reacti ons DTSTART:20220726T132400Z DTEND:20220726T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-680@indico.frib.msu.edu DESCRIPTION:Speakers: Yinlu Han (中国原子能科学研究院)\, Yue Zha ng (中国原子能科学研究院)\n\nSilicon is of great applied interes t in the semiconductor industry and in detectors for physics experiments. An increased understanding of neutron induced charged particle producing r eactions on silicon is particularly significant not only for basic physics but also for applications. \nIn the present work\, an optimal set of opti cal model potential parameters is obtained for the n+28\,29\,30Si reaction s up to 200 MeV\, all the cross sections\, the angle integrated spectra an d the double differential cross sections of neutron\, proton\, deuteron\, triton\, helium and alpha-particle emission for n+28\,29\,30Si reactions a re consistently calculated.\nThe optical model\, the unifed Hauser-Feshbac h and exciton model which includes the improved Iwamoto-Harada model\, the distorted wave Born approximation\, the intra-nuclear cascade model and r ecent experimental data are including in the theoretical calculations. \nT he results are analyzed and compared with existing experimental data and e valuations in ENDF/B-VIII.0 and JENDL-4.0.\n\nhttps://indico.frib.msu.edu/ event/52/contributions/680/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/680/ END:VEVENT BEGIN:VEVENT SUMMARY:Limited confidence and overall consistency concepts in nuclear dat a evaluation DTSTART:20220726T185100Z DTEND:20220726T190300Z DTSTAMP:20260420T153400Z UID:indico-contribution-899@indico.frib.msu.edu DESCRIPTION:Speakers: Toshihiko Kawano (Los Alamos National Laboratory)\, Mike Herman (LANL)\n\nLA-UR-21-29369\n\nWe use an example of Ta181 evaluat ion to illustrate modern evaluation methodology which\, while based on the classic three pillars of the evaluation (differential experimental data\, nuclear reaction modeling\, and validation with integral experiments)\, m akes predominant use of the "limited confidence" and "overall consistency" concepts. The limited confidence applies to all three pillars. Differenti al data have limited precision and in some cases might be misleading. Reac tion modeling might use inappropriate models\, be affected by model defect s\, and leaves pretty wide leeway to parameter adjustment. The integral ex periments\, because of the fact of being "integral"\, may lead to the comp ensation of errors and\, similarly to the differential measurements\, migh t be misleading. We will show how in this confusing realm requiring the ov erall consistency\, and obeying physics laws leads to ignoring a number of differential experiments and results in a clean\, model based evaluation reproducing wide range of differential observables and improving performan ce in integral testing.\n\nTantalum is nearly mono-isotopic metal with Ta1 81 being 99.988% of the\nnatural mixture. Therefore\, there is an exceptio nal wealth of experimental data\, including cross sections (also to isomer ic states)\, angular distributions\, as well as spectra and double-differe ntial cross sections. This abundance allows\, in several cases\, to elimin ate datasets that are not consistent with the remaining bulk of experiment al data. We will show that this elimination goes beyond simple rejection o f outliers.\n\nThe modeling was performed with EMPIRE-3.2.3 reaction model code. In view of multiple choices for selecting models available in EMPIR E various combinations of those were first explored in attempt to reprodu ce vast set of existing experimental data\, while refraining from adjusti ng individual model parameters. This way the following models were adopt ed:\n\n- Coupled-Channels with dispersive Optical Model potential.\n- Quan tum-mechanical TUL Multistep Direct (MSD) model for pre-equilibrium emiss ion of neutrons.\n- Heidelberg formulation of the Multistep Compound (MSC) model for pre-equilibrium neutron\, proton and gamma emission.\n- Exciton model with Iwamoto-Harada extension for pre-equilibrium cluster emission. \n- Hauser-Feshbach with width-fluctuations correction\, full gamma-cascad e\, and Gilbert-Cameron level densities.\n\nCombination of MSD and MSC mod els provides very good description of the neutron spectra\, which is also essential for correct description of channels such as (n\,2n) and (n\,p). Gilbert-Cameron level densities were chosen over EGSM and microscopic Har tree-Fock-Bogoliubov because the former produce better capture cross sect ions between 1-3 MeV\, and slightly better gamma spectra.\n\nhttps://indic o.frib.msu.edu/event/52/contributions/899/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/899/ END:VEVENT BEGIN:VEVENT SUMMARY:WPEC/SG46 Exercise on Target Accuracy Requirement DTSTART:20220728T134800Z DTEND:20220728T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-882@indico.frib.msu.edu DESCRIPTION:Speakers: Oscar Cabellos (Universidad Politécnica de Madrid ( UPM))\n\nRecently\, a second Target Accuracy Requirements (TAR) exercise h as been launched in the framework of the WPEC/S46 on “Efficient and Effe ctive Use of Integral Experiments for Nuclear Data Validation”. The TAR exercise aims at quantifying nuclear data needs (in terms of uncertainty r eduction) to meet target accuracies on specific integral parameters. These target accuracies are driven by reactor and fuel cycle design needs.\n\nT he first TAR exercise was performed at NEA in the period 2005-2008 within the framework of WPEC/SG26 on “Uncertainty and target accuracy assessmen t for innovative systems using recent covariance data evaluations”. The WPEC/SG26 exercise did provided both crucial entries to the NEA High Prior ity Request List (HPRL) and guidance for new experiments and data evaluati ons via the NEA/HPRL. Moreover\, it was the triggering factor for a worldw ide revival of covariance data evaluations in all major cross section data evaluation projects. A large expert participation contributed to WPEC/SG2 6 (2005-2008). As a main outcome of this project\, a first list of 14 data priorities (i. e. uncertainty reductions) for GEN-IV reactors was establi shed and implemented in the HPRL at NEA.\n\nThus\, the aim of second TAR e xercise is intended mainly for updating and enlarging the scope of the pre vious WPEC/SG26 exercise\, and for providing updated target accuracies for nuclear data uncertainty reduction. This updated TAR exercise will take a dvantage of:\n\n - The progress of covariance data assessment in different international projects (e. g. WPEC/SG44 on “Investigation of Covariance Data in General Purpose Nuclear Data Libraries”) and evaluation project s of nuclear data (e. g. JEFF\, ENDF\, etc…)\n - The potential nuclear d ata issues and requirements for systems (reactor and associated fuel cycle s) recently emerging as new and innovative concepts of interest for the in ternational community\n - The expansion of Sensitivity/Uncertainty methodo logies\n - The assessment of “correlations” between reactions in the “inverse method” optimization. Neglecting of the correlations in WPEC /SG26 may be one of the major concerns. Current studies have shown that ta king into account correlations may require tighter uncertainties on the co nsidered nuclear data.\n - The credit of the uncertainty reduction of nucl ear data for design optimization\, margins reduction\, optimized reactor o peration and innovative fuel cycles feasibility assessment\n\nTarget Accur acy Requirements (TAR) represent typical industrial targets to be met. For nuclear reactors and nuclear fuel facilities these targets may represent safety acceptance limits on different integral parameters for a safe opera tion both in normal (e. g. nominal operation\, manoeuvres\, …) and accid ental transients (e .g. Loss-Of-Coolant Accident (LOCA) …). Different sa fety design limits may be defined to assess: i) the source term with limit s in radiotoxicity\, dose\, etc… ii) the criticality with safety limits in keff\, iii) the damage of fuel in accidents with safety limits peak pow er distributions. However\, the target accuracies are difficult to specify and are often hidden behind/included in an engineering margin. The values of TAR should include only the impact of nuclear data uncertainty\, assum ing and recognizing that this is only one component of the total uncertain ty. These TARs should result as far as possible from reactor and associate fuel cycle designers\, reactor physicists involved in data validation usi ng integral experiments\, and nuclear data physicists. Consequently\, desi gn code system developers should also be included in this work. It is also recognized that for this second TAR exercise it will be essential to upda te and verify the status of WPEC/SG26 design target accuracies and their p otential evolution (reactor operation and fuel cycle parameters) since the n.\n\nThe updated TAR exercise will be applied for nuclear systems (reacto r and associated fuel cycles) including: i) WPEC/SG26 (2005-2008) systems: Gen IV\, MA burners\, and ADS systems\, ii) WPEC/SG33 (2014-2018) systems : ABR type and JOYO\, iii) new reactors concepts (SMR\, MSR\, HTFR\,…)\, sodium-cooled fast reactors and lead-cooled fast reactors\, ADS systems ( e.g. MYRRHA)\, back-end facilities and concepts\, iv) review of SG26 syste ms: LWRs.\n\nThe specifications for the updated TAR exercise were delivere d in May 2021. It is worth noting that a new energy structure for sensitiv ities and uncertainties for the exercise\, consists of only seven energy g roups. \n\nThis exercise will be also useful to test different methodologi es with the “traditional” methodology used in WPEC/SG26 via sensitivit y analysis. Particularly\, this work will assess the importance of cross-c orrelations of covariance data.\n\nThe results of this TAR exercise will b e presented in this paper. These results will serve to assess the effect o f nuclear data uncertainty reduction on output relevant for reactor design and operation\; with the goal to provide the NEA/HPRL with new requiremen ts of “nuclear data uncertainty reduction”. This work will motivate an d focus new experiments needed for meeting the new requirements.\n\nhttps: //indico.frib.msu.edu/event/52/contributions/882/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/882/ END:VEVENT BEGIN:VEVENT SUMMARY:Results and interpretations of isomeric yield ratios measured at t he IGISOL facility DTSTART:20220728T132400Z DTEND:20220728T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-906@indico.frib.msu.edu DESCRIPTION:Speakers: Zhihao Gao (Uppsala University)\n\nIn nuclear physic s the term meta-stable state refers to an excited state with an unusually long half-life\, which can sometimes be even longer than that of the corresponding ground state. As a result\, these states are often c onsidered to be nuclei in their own right and\, together with th e corresponding ground state nuclei\, they are referred to as isomers. The yields of such isomers in fission significantly impact the yield evolu tion of the fission products\, and hence also the criticality and decay he at calculations in nuclear reactors.\nIn fission\, the Isomeric Yield Rati o (IYR) is the amount of fission products populating a certain nucleus\, r elative to the population all isomers of set nucleus. In the formation of isomers\, a combination of shape\, spin and spin projection of a nucleus \, inhibits the decay\, and results in excited states with long half-lives [1\, 2\, 3]. Consequently\, the IYR of fission prod ucts are connected to the angular momentum and energy distributions of the initial fission fragments\,before neutron and gamma emission. He nce\, the reaction code TALYS\, that describes this de-excitation pro cedure\, provides an indirect way [4] to explore the angular momentum dist ribution of fission fragments.\nWith this in mind\, a measurement of IYRs was conducted at the IGISOL facility. In the measurement\, a 25 MeV proton beam was used to induce fission of $^{238}$U and produce fission products . A Penning trap utilizing the Phase-Imaging Ion-Cyclotron-Resonance (PI- ICR) technique was then used as a high resolution mass filter in order to separate the fission products. With this technique isomers down to a f ew tens of keV can be separated by mass and their yields measure d through direct ion counting.\nIn total\, 19 IYRs were measured: $^{102}$ Nb\,$^{126\,128\,129}$In\, $^{129\,131}$Sn\, $^{129\,132\,134}$Sb\, $^{129 \,131\,133}$Te\, $^{132\,133\,134\,136}$I\, $^{133\,135}$Xe and $^{138}$Cs . A strong odd-even effect is ob-served in the IYRs of several of the iso topes. Further more\, the proton numbers of isotones N = 77\, 79 and 81 c ross the magic proton number Z = 50\; and the neutron numbers of isotopes Z = 51 and 53 cross the magic neutron number 82. In this way possible shel l effects in population of isomers can be studied.\nReferences:\n[1] Phil ip Walker and George Dracoulis. Energy traps in atomic nuclei.Nature(Londo n)\,399:35–40\, 1999.\n[2] G.D. Dracoulis. Isomers\, nuclear struc ture and spectroscopy.Phys. Scr\,2013:014015\, 2013.\n[3] G.D. Dracoul iset al. Review of meta-stable states in heavy nuclei.Rep.Prog. Phys .\,79:076301\, 2016.\n[4] V. Rakopoulos et al.First isomeric yield ratio measurements by direct ion counting and implications for the angular momen tum of the primary fission fragments.Phys. Rev. C\,98:024612\, 2018.\n\nht tps://indico.frib.msu.edu/event/52/contributions/906/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/906/ END:VEVENT BEGIN:VEVENT SUMMARY:Proton-neutron interaction studies via accurate mass measurements at the outskirts of the nuclear chart DTSTART:20220728T133600Z DTEND:20220728T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-907@indico.frib.msu.edu DESCRIPTION:Speakers: Israel Mardor (Tel Aviv University)\n\nNuclear mass measurements give access to nuclear binding energies\, which reflect the s um of interactions among its constituent nucleons. Certain double differen ces of neighboring nuclei binding energies provide $\\delta$V$_{pn}$\, the average interaction strength of the last one or two protons with the last one or two neutrons [1].\nWe will present highly-accurate mass measuremen ts of the nuclides $^{69}$As\, $^{70\,71}$Se\, and $^{71}$Br\, produced vi a fragmentation of a $^{124}$Xe primary beam at the Fragment Separator (FR S) at GSI. These measurements were performed with the multiple-reflection time-of-flight mass spectrometer (MR-TOF-MS) of the FRS Ion Catcher with a n unprecedented mass resolving power of almost 1\,000\,000 [2]. Such high resolving power is the only way to achieve accurate results and resolve ov erlapping peaks of short-lived exotic nuclei\, whose total number of accum ulated events is always limited.\nWe obtained relative mass uncertainties at the level of 10$^{-7}$ with only up to 20 events for $^{69}$As (first d irect mass measurement)\, $^{71}$Se and $^{71}$Br\, and at the level of 10 $^{-8}$ with less than 500 events for $^{70}$Se. All our results are in go od agreement with the 2020 Atomic Mass Evaluation. We measured also the ma ss of the stable molecule $^{14}$N$^{15}$N$^{40}$Ar with a relative mass a ccuracy of $\\delta$m/m = 1.7 $\\times$ 10$^{−8}$\, the best yet achieve d with an MR-TOF-MS. \nOur results show that the measured re-strengthening of the proton-neutron interaction ($\\delta$V$_{pn}$) for odd-odd nuclei along the N = Z line above Z = 29 (recently extended to Z = 37) is hardly evident at the N − Z = 2 line\, and not evident at the N − Z = 4 line. Nevertheless\, detailed structure of $\\delta$V$_{pn}$ along the N − Z = 2 and N − Z = 4 lines\, confirmed by our mass measurements\, may provi de a hint regarding the ongoing $\\approx$ 500 keV discrepancy in the mass value of the nuclide $^{70}$Br\, which prevents including it in the world average of Ft value for super-allowed 0$^{+}$ $\\rightarrow$ 0$^{+}$ $\\b eta$-decays. The reported work sets the stage for mass measurements with t he FRS Ion Catcher of nuclei at and beyond the N = Z line in the same regi on of the nuclear chart\, including the nuclide $^{70}$Br.\nWe will furthe r present results of a systematic search for deviations from the expected $\\delta$V$_{pn}$ trends throughout the nuclear chart\, which may indicate that some mass evaluations in the Atomic Mass Evaluation are not correct and even some mass measurements are questionable.\nWe will also present an analysis of mass measurements via higher-order mass-difference indicators \, which may disentangle the Wigner term (p-n correlations) from the Symme try term (mean-field) [3]. This analysis is performed for both N $\\approx $ Z nuclei and neutron-rich N$_{val}$ $\\approx$ Z$_{val}$ (equal proton a nd neutron numbers above doubly-magic cores) nuclei\, for which $\\delta$V $_{pn}$ is apparently enhanced\, perhaps hinting emergent symmetries in th ese nuclei that are similar to those of N $\\approx$ Z nuclei [4].\nWe pla n to apply these analyses to our upcoming mass measurements of neutron-ric h nuclei around N$_{val}$ $\\approx$ Z$_{val}$\, which are planned and pro posed via spontaneous fission at the FRS Ion Catcher at GSI\, and via mult i-neutron-transfer reactions at JYFLTRAP at the University of Jyväskylä. \n\n\nReferences:\n[1] P. Van Isacker et al.\, Phys. Rev. Lett. 74\, 4607 (1995)\n[2] I. Mardor et al.\, Phys. Rev. C 103\, 034319 (2021)\n[3] W. Sa tula et al.\, Phys. Lett. B 407\, 103 (1997)\n[4] R. B. Cakirli et al.\, P hys. Rev. C 82\, 061304(R) (2010)\n\nhttps://indico.frib.msu.edu/event/52/ contributions/907/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/907/ END:VEVENT BEGIN:VEVENT SUMMARY:Isomer discovery and studies in the vicinity of $^{100}\\text{Sn}$ by the means of high-resolution mass spectrometry at the FRS Ion Catcher DTSTART:20220728T140000Z DTEND:20220728T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-910@indico.frib.msu.edu DESCRIPTION:Speakers: Daler Amanbayev (Justus-Liebig-Universität Gießen\ , II. Physikalisches Institut)\n\nThe N=Z=50 isotope $^{100}\\text{Sn}$ ha s long been of interest from theoretical and experimental perspectives bec ause it is the heaviest self-conjugate doubly-magic nucleus. Despite the s ignificant progress in the last decade\, the challenge of reaching it in e xperimental facilities remains to date. Systematic measurements of ground state masses and isomer excitation energies in its vicinity provide import ant information for understanding the evolution of single-particle states in the N≈Z region and the structure of $^{100}\\text{Sn}$ itself.\n\nThe FRS Ion Catcher setup (FRS-IC) [1] located at GSI Helmholtz Centre for He avy Ion Research (Darmstadt\, Germany) is specialized in high-resolution d irect mass measurements of slowed down and thermalized exotic nuclei produ ced at relativistic energies. It consists of a cryogenic gas-filled stoppi ng cell (CSC)\, an RFQ beamline\, and a multiple-reflection time-of-flight mass-spectrometer (MR-TOF-MS). Fast ion extraction from the CSC of down t o $25 \\text{ ms}$ [2] combined with an unprecedented MR-TOF-MS mass resol ving power (FWHM) of almost $1\,000\,000$ provides an exceptional opportun ity to measure masses of short-lived exotic nuclei with uncertainties down to $4.0 \\cdot 10^{-8}$ [3] and to resolve long-lived nuclear isomeric st ates\, that are challenging to measure with traditional gamma spectroscopy methods. Furthermore\, the MR-TOF-MS is broadband *i.e.\,* it covers a la rge mass region of interest which makes it a powerful tool for discovering previously unknown states.\n\nWe will discuss the results of direct measu rements of ground state masses and isomer excitation energies of $^{97}\\t ext{Ag}$ and odd indium isotopes $^{101-109}\\text{In}$. A $(1/2^-)$ isome ric state was discovered in $^{97}\\text{Ag}$ with excitation energy of $6 18(38) \\text{ keV}$. Remarkably\, this is the first time a nuclear isomer was discovered using an MR-TOF-MS. This discovery was supported by large- scale shell-model and advanced mean-field calculations. The comparison of measured excitation energies with large-scale shell-model calculations\, and deduced extrapolations towards $^{99}\\text{In}$ – one-proton hole o f $^{100}\\text{Sn}$ – showed the importance of including core excitatio ns in that region [4]. In addition\, other results from this region of the nuclide chart will be presented.\n\nReferences:\n[1] W.R. Plaß et al.\, Nucl. Instr. Meth. B 317 (2013) 457\n[2] S. Purushothaman et al.\, EPL\, 1 04 (2013) 42001\n[3] I. Mardor et al.\, PRC 103 (2021) 034319\n[4] C. Horn ung\, D. Amanbayev et al.\, Phys. Lett. B 802 (2020) 135200\n\nhttps://ind ico.frib.msu.edu/event/52/contributions/910/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/910/ END:VEVENT BEGIN:VEVENT SUMMARY:Radiative capture cross section measurements of $^{54}$Fe at the R PI LINAC DTSTART:20220726T185100Z DTEND:20220726T190300Z DTSTAMP:20260420T153400Z UID:indico-contribution-822@indico.frib.msu.edu DESCRIPTION:Speakers: Yaron Danon\, Peter Brain\, Michael Rapp\, Adam Dask alakis\, Benjamin Wang\, Katelyn Cook\, Dominik Fritz\, Adam Ney\, Sukhjin der Singh\n\n$^{54}$Fe capture cross section measurements were conducted a t the Rensselaer Polytechnic Institute (RPI) Gaerttner Linear Accelerator (LINAC) Center using an enriched $^{54}$Fe sample in the keV energy region . $^{54}$Fe is a constituent of natural iron\, which is present in a large variety of nuclear grade materials.Therefore\, it is important to have an accurate understanding of the cross section of $^{54}$Fe\, which can be m easured experimentally. In the time-of-flight measurements previously cond ucted at the LINAC\, an array of four C$_{6}$D$_{6}$ detectors surrounded the sample and data were collected using a digital data acquisition system . In this work\, the experimental apparatus was upgraded with additional C $_{6}$D$_{6}$ detectors\, allowing for more accurate measurements from 1 k eV – 2 MeV while preserving the low neutron sensitivity of the system. T he capture yield of the $^{54}$Fe measurements was normalized using the sa turated resonances in Au and Ta. The capture yield was subsequently compar ed to evaluations and prior experimental data. Results were found to have good agreement in certain energy regions. The improved experimental appara tus used in these measurements will greatly enhance RPI’s ability to mea sure neutron capture cross sections in the keV region.\n\nhttps://indico.f rib.msu.edu/event/52/contributions/822/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/822/ END:VEVENT BEGIN:VEVENT SUMMARY:Evaluation of charged-particle reactions in the resolved resonance region DTSTART:20220726T181500Z DTEND:20220726T183900Z DTSTAMP:20260420T153400Z UID:indico-contribution-902@indico.frib.msu.edu DESCRIPTION:Speakers: Ian Thompson\, Paraskevi Dimitriou (International At omic Energy Agency)\n\nCharged-particle-induced reactions at low energies in the resolved resonance region are important for a range of applications in basic and applied sciences. Ion Beam Analysis of materials for cultura l heritage\, environment and climate control\, and forensics\, depends on the knowledge of proton-\, deuteron- and alpha-induced reactions at energi es of a few MeV. Management of fuel in nuclear reactors involves the contr ol of neutrons produced after the reactor operation is shutdown. For the m ost widely used fuel materials\, UO2\, UF6\, PuF4 and PuO2\, the dominant neutron producing reactions are (α\,xn) reactions on isotopes of O and F\ , at incident energies above the neutron emission threshold. In nuclear as trophysics\, main stellar processes producing the energy of the stars and leading to the synthesis of the light and medium-mass elements up to the i ron nuclei\, are fuelled by thermonuclear reactions at temperatures of ten s of millions of degrees Kelvin. These conditions simulated in the earth l aboratories translate into charged-particle induced reactions on light and medium-mass nuclei at energies of a few hundreds of keV. Alpha-nucleus re actions up to 10 MeV are also a potential source of low-energy neutron bac kground for rare event research in astroparticle physics (dark matter sear ch\, neutrino\, etc.).\nSignificant effort has been made over the past dec ades to measure some of these cross sections. The Ion Beam Analysis Data L ibrary (IBANDL) maintained by the IAEA contains over 6000 datasets of diff erential and total experimental cross sections for charged-particle-induce d reactions in the energy region below several MeV. In nuclear astrophysic s\, several dedicated compilations (NACRE-I and II) and theoretical reacti on rate databases (REACLIB\, BRUSLIB\, KADONIS\, NUCASTRODATA.ORG) have be en made available to meet the needs of the stellar nucleosynthesis calcula tions.\nOn the other hand\, the evaluated nuclear data libraries maintaine d by national or international coordinated efforts (ENDF\, JEFF\, JENDL\, CENDL) are to date\, incomplete as far as charged-particle- induced reacti ons in the resolved resonance region are concerned.\nIn response to the ab ove-mentioned gap in the evaluated libraries\, the IAEA Nuclear Data Secti on is coordinating an international effort to (i) verify that the existing R-matrix codes are consistent\, (ii) evaluate charged-particle cross sect ions in the resolved resonance region\, (iii) produce evaluated nuclear da ta files for further processing and finally (iv) disseminate the evaluated data through general purpose evaluated nuclear data libraries.\nIn this p aper we present the results of the effort made thus far on 1) verification of the available R-matrix codes\, minimization methods and calculation of covariances\, 2) the evaluation of the compound system 7Be*\, and 3) impr oving (alpha\,n) reaction data for the applications.\nWe also discuss the open issues in R-matrix calculations as we extend to higher energies\, suc h as dealing with the rapidly growing number of open channels and merging with the regime of smooth cross sections described by the statistical mode l. Finally\, we summarize the main conclusions of the IAEA Technical meeti ng on ‘(alpha\,n) reaction evaluation and data needs’.\n\nThe work of I.J. Thompson was performed under the auspices of the U.S. Department of E nergy by Lawrence Livermore National Laboratory under Contract DE-AC52-07N A27344. \nThe work of G. Hale and M. Paris was supported by the U.S. Depar tment of Energy through the Los Alamos National Laboratory. Los Alamos Nat ional Laboratory is operated by Triad National Security\, LLC\, for the Na tional Nuclear Security Administration of U.S. Department of Energy (Contr act No. 89233218CNA000001). [LA-UR-21-29650]\n\nhttps://indico.frib.msu.ed u/event/52/contributions/902/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/902/ END:VEVENT BEGIN:VEVENT SUMMARY:Experimental study of high-energy fission and quasi-fission dynami cs with fusion-induced fission reactions at VAMOS++ DTSTART:20220727T190000Z DTEND:20220727T191200Z DTSTAMP:20260420T153400Z UID:indico-contribution-639@indico.frib.msu.edu DESCRIPTION:Speakers: Daniel Fernandez\, Y. H. Kim\, M. Rejmund\, D. Galav iz\, B. Fernandez-Dominguez\, D. Acknermann\, A. Lemasson\, F. Farget\, D. Ralet\, B. Jurado\, Manuel Caamaño\, Diego Ramos\, D. Durand\, B. Jacquo t\, T. Roger\, P. Teubig\, J. D. Frankland\, P. Morfouace\, Hector Alvarez \, I. Tsekhanovich\, A. Heinz\, S. Biswas\, M. O. Fregeau\, E. Galiana-Bal do \, C. Schmitt\, A. Henriques\, J. Piot\, L. Audouin\, E. Clement\n\nDur ing the last ten years\, the use of inverse kinematics in the experimental study of fission is bringing a wealth of new observables obtained in sing le measurements\, which allows their analysis and\, also importantly\, of their correlations [1\, 2]. An ongoing application of this technique the b asis of a series of experiments performed with the variable-mode\, large-a cceptance VAMOS++ spectrometer at GANIL (France) [3\, 4]. In these experim ents\, fission reactions are induced by fusion and transfer reactions betw een a $^{238}$U beam and a set of different light targets. The kinematics of the transfer and fusion reactions allows us to identify the fissioning system and determine its initial excitation energy [5]\, while the data fr om the VAMOS spectrometer gives us the isotopic identification for the ful l fragments distribution\, and their velocity vectors. These measurements result in an accurate determination of the fragments mass before and after post-scission neutron evaporation\, their neutron multiplicity\, the tota l kinetic and excitation energy\, and their emission angle in the centre o f mass [1\, 6\, 7]. In addition\, these characteristics can be studied as a function of the initial excitation energy of the fissioning system [9]. The correlation between these magnitudes also permits to determine\, for i nstance\, the scission configuration and the sharing of excitation energy between the fragments [8\, 9]\, and even to obtain information about the b alance between intrinsic and collective excitation energy [10].\n\nIn a re cent experiment\, we have focused on the survival of nuclear structure eff ects in high excitation energy and the frontier between fission and quasi- fission. The main objective is to build and to study observables that woul d allow us to estimate the fission and quasi-fission components of the pro duction and to identify relevant shells\, such as newly highlighted octupo lar-deformed closed shells [11]\, and their role on the fission dynamics a t high energy.\n\nThe results of our analysis show that the ratio between neutrons and protons at scission as a function of the fragment split\, tog ether with the total kinetic and excitation energies\, and the isotopic yi elds\, reveal the presence of structure effects related at high energy\, e ven if pre-scission evaporation is taken into account.\n\nConcerning the q uasi-fission component\, the classical mass-angular distribution is comple ted in our case with the fragment identification\, the ratio between neutr ons and protons\, and more importantly\, the ratio between the production of fragments with an even and odd number of protons\, the so-called even-o dd effect [12\, 13]. The latter shows a clear different mechanism for fiss ion and quasi-fission that can be used to address\, not only the separatio n between fission and quasi-fission\, but also to study the energy dissipa ted in each of these processes.\n\n[1] M. Caamano et al.\, Phys. Rev. C 88 \, 024605 (2013)\n[2] E. Pellereau et al.\, Phys. Rev. C 95\, 054603 (2017 )\n[3] S. Pullanhiotan\, et al.\, Nucl. Instr. and Meth. A 593\, 343 (200 8)\n[4] M. Rejmund et al.\, Nucl. Instr. and Meth. A 646\, 184 (2008)\n[5 ] C. Rodriguez-Tajes et al.\, Phys. Rev. C 89\, 024614 (2014)\n[6] D. Ramo s et al.\, Phys. Rev. C 99\, 024615 (2019)\n[7] D. Ramos et al.\, Phys. Re v. Lett. 123\, 092503 (2019)\n[8] M. Caamano et al.\, Phys. Rev. C 92\, 03 4606 (2015)\n[9] D. Ramos et al.\, Phys. Rev. C 101\, 034609 (2020)\n[10] M. Caamano and F. Farget\, Phys. Lett. B 770\, 72 (2017)\n[11] G. Scamps and C. Simenel\, Nature 564\, 382 (2018)\n[12] B. Jurado and K.-H. Schmidt \, J. Phys. G 42\, 055101 (2015)\n[13] D. Ramos et al.\, to be published\n \nhttps://indico.frib.msu.edu/event/52/contributions/639/ URL:https://indico.frib.msu.edu/event/52/contributions/639/ END:VEVENT BEGIN:VEVENT SUMMARY:Characterisation of the n_TOF/CERN 185m beam-line after the facili ty’s major upgrades DTSTART:20220726T134800Z DTEND:20220726T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-704@indico.frib.msu.edu DESCRIPTION:Speakers: Michael Bacak\, Maria-Elisso Stamati (European Organ ization for Nuclear Research (CERN)\, Geneva\, Switzerland and Department of Physics\, University of Ioannina\, Ioannina\, Greece)\n\nThe n_TOF faci lity at CERN is a pulsed neutron source for time-of-flight measurements\, first conceptualised by Carlo Rubbia in 1998 [1]. It is designed to study neutron induced reactions bearing importance for fundamental research\, nu clear astrophysics [2\,3]\, nuclear technology applications [4] as well as nuclear medicine [5]. During its first two operation phases\, n_TOF consi sted of a single beam-line of 185 m length\, while for its third phase in 2014\, a vertical 20 m beam-line was constructed.\n\nThe facility’s 185 m flight path provides an excellent energy resolution\, reaching as low as ΔE/E ~ 10-4 for the eV region [6]\, enabling high precision measurements that can significantly contribute to standard neutron cross section evalu ations [7]. The energy range it covers stretches from a few meV up to the GeV region\, allowing for significant extension of cross section data\, es pecially for fission measurements. Furthermore\, the high instantaneous ne utron flux\, provided by a high intensity 20 GeV/c proton beam impinging o n a lead spallation target allows to measure highly radioactive samples. \n\nThroughout CERN’s Long Shutdown 2\, the n_TOF facility has been larg ely upgraded. The biggest change was the replacement of the water-cooled\, single block lead spallation target\, with a new nitrogen-cooled target c onsisting of several slabs of lead and optimised also for n_TOF’s vertic al beam-line. After this major change\, it must be ensured that the perfor mance of the horizontal beam-line still fulfills its high standards and ha s not significantly changed. Additionally\, the performance of the new tar get must be inspected thoroughly.\n\nDuring the Commissioning in 2021\, se veral detection systems\, such as a fission and charged particles setup fo r the measurement of the neutron flux and beam profile. The energy resolut ion of the beam-line was investigated with neutron capture detectors compl imented by extensive Monte Carlo simulations.\n\nIn this work\, the charac terisation of the horizontal beam-line after the facility’s spallation t arget replacement will be summarised. The preliminary results on the neutr on flux will be presented along with a comparison with simulations as well as with the flux of the previous spallation target. Characteristics such as the energy resolution and the background conditions will also be discus sed and compared to the beam-line’s previous performance. \n\n**Referenc es**\n[1] C. Rubbia et al.\, A high resolution spallation driven facility at the CERN-PS to measure neutron cross sections in the interval from 1 eV to 250 MeV\, CERN/LHC/98-02 (EET)\, 1998\n[2] U. Abbondanno et al.\, Neut ron Capture Cross Section Measurement of 151Sm at the CERN Neutron Time of Flight Facility (n_TOF)\, Phys. Rev. Lett. 93\, 161103 (2004)\n[3] C. Led erer et al.\, Neutron Capture Cross Section of Unstable 63Ni: Implications for Stellar Nucleosynthesis\, Phys. Rev. Lett. 110\, 022501 (2013)\n[4] N . Colonna\, A. Tsinganis\, R. Vlastou\, et al. The fission experimental pr ogramme at the CERN n_TOF facility: status and perspectives. Eur. Phys. J. A 56\, 48 (2020)\n[5] J. Praena et al.\, Measurement and resonance analys is of the 33S(n\,α)30Si cross section at the CERN n_TOF facility in the e nergy region from 10 to 300 keV\, Phys. Rev. C 97\, 064603 (2018)\n[6] Gue rrero\, C.\, Tsinganis\, A.\, Berthoumieux\, E. et al. Performance of the neutron time-of-flight facility n_TOF at CERN. Eur. Phys. J. A 49\, 27 (20 13)\n[7] S. Amaducci\, L. Cosentino\, M. Barbagallo\, et al. Measurement o f the 235U(n\, f) cross section relative to the 6Li(n\, t) and 10B(n\,a) s tandards from thermal to 170 keV neutron energy range at n_TOF. Eur. Phys. J. A 55\, 120 (2019)\n\nhttps://indico.frib.msu.edu/event/52/contribution s/704/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/704/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Experimental analysis and comparison to simulation of high-resolution $\\gamma$-spectroscopy measurements of irradiated metallic foils in a 14 MeV fusion-neutron environment DTSTART:20220728T153800Z DTEND:20220728T155000Z DTSTAMP:20260420T153400Z UID:indico-contribution-849@indico.frib.msu.edu DESCRIPTION:Speakers: Mark Gilbert\n\nDesign engineering of future fusion experimental devices and near-commercial power plants are considering a va riety of materials for the construction – some known and applied in the wider nuclear industry and some under development. When used in the extrem e neutron environments predicted for the in-vessel components of future co mmercial and near-commercial magnetic-confinement fusion power plants\, nu clei of these materials will undergo frequent nuclear reactions with the n eutrons\, resulting in transmutation and activation. The production of sho rt- and medium-lived radionuclides (half-lives of the order of minutes to months) will create radiological issues to solve relating to the operation and maintenance of fusion reactor components\, for example due to on-load and post-operation decay heat requiring additional cooling capacity. Mean while\, the creation of longer-lived nuclides (half-lives from decades to centuries or more) will potentially create challenges when decommissioning fusion reactors because the nuclear waste may be too severe (to highly ac tivated) for near surface repositories. Whilst such fusion wastes are less radiotoxic than those generated in fission at long timescales\, the radio activity-based criteria for licencing storage facilities could present con ditions for similar long-lived waste problems as those faced with fission. \n\nAccurate and reliable predictions of the nuclear response of materials using evaluated nuclear data libraries are a critical part of the design activities. Computational validation activities\, comparing experimental d ecay heat measurements to simulations with different nuclear libraries [1\ ,2]\, demonstrate that modern nuclear data libraries generally perform wel l. However\, there are still areas for improvement\, particularly for some of the more exotic materials being considered in the novel concepts being explored for fusion – for example\, decay-heat predictions for iridium and osmium do not match well with experimental measurements after fusion-n eutron exposure. Such discrepancies and the need to reduce uncertainties\, which would otherwise result in engineering design including unacceptably large and costly safety margins\, prompted an effort to perform new measu rements.\n\nIn this paper we discuss the experimental set-up for a campaig n of irradiations and $\\gamma$-spectroscopy measurements at the UK-based 14 MeV ASP-accelerator. Previously [3]\, comparison of simulations with th e analysed results from measurements on Mo – a candidate fusion armour m aterial – have demonstrated how the database of experimental measurement s\, covering ~20 different metallic elements in more than 300 separate exp eriments\, can be used to benchmark inventory code predictions with FISPAC T-II [4] – the transmutation and activation simulation platform develope d at UKAEA. The analysis and interpretation has been revised and improved in the present work. Results for fusion relevant materials\, including W a nd Cr\, are discussed.\n\nUsing this experimental experience\, particularl y an appreciation of the analysis and interpretation difficulties\, we mak e recommendations for how future experiments should be conducted\, such as targeted irradiation times and optimized measurement approaches.\n.\nThis work is part funded by the RCUK Energy Programme [grant number EP/T012250 /1].\n.\n[1] M.R. Gilbert\, J.-Ch. Sublet\, “Experimental decay-heat sim ulation-benchmark for 14 MeV neutrons & complex inventory analysis with FI SPACT-II” *Nuclear Fusion* **59** (2019) 086045\n[2] M.R. Gilbert\, O.V. Vilkhivskaya\, J.-Ch. Sublet\, “Fusion decay heat validation\, FISPACT- II & TENDL-2019\, ENDF/B-VIII.0\, JEFF-3.3\, EAF2010\, and IRDFF-II nuclea r data libraries” UKAEA report UKAEA-CCFE-RE(20)04. Available from fispa ct.ukaea.uk\n[3] M.R. Gilbert\, L.W. Packer\, T. Stainer\, “Experimental validation of inventory simulations on molybdenum and its isotopes for fu sion applications” *Nuclear Fusion* **60** (2020) 106022\n[4] J.-Ch. Sub let\, J.W. Eastwood\, J.G. Morgan\, M.R Gilbert\, M. Fleming\, W. Arter\, “FISPACT-II: An Advanced Simulation System for Activation\, Transmutatio n and Material Modelling“ *Nuclear Data Sheets* **139** (2017) 77–137. See fispact.ukaea.uk\n\nhttps://indico.frib.msu.edu/event/52/contribution s/849/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/849/ END:VEVENT BEGIN:VEVENT SUMMARY:Getting NJOY ready for ENDF/B-VIII.1 DTSTART:20220725T173000Z DTEND:20220725T174200Z DTSTAMP:20260420T153400Z UID:indico-contribution-856@indico.frib.msu.edu DESCRIPTION:Speakers: Wim Haeck (LANL)\n\nEach release of the ENDF/B nucle ar data library [1] pushes the limits of the processing codes through the introduction of new data and new data formats. Processing codes must be ad apted to ensure that they are capable of using these new formats\, or at t he very least understand them. NJOY [2]\, the nuclear data processing code developed at Los Alamos National Laboratory is no exception to this. Sinc e NJOY2016 is still the main production code for nuclear data libraries at LANL\, we will continue to make the necessary changes in this version of NJOY to ensure full compatibility with the ENDF/B-VIII.1 nuclear data libr ary. Where relevant\, the modern NJOY21 components will also be updated.\n \nThe addition of the mixed elastic scattering option (LTHR = 2) for elast ic thermal scattering (found in MF7 MT2) is one of the most anticipated ch anges for the ENDF/B-VIII.1 nuclear data library since it lifts the limita tion of using either coherent or incoherent elastic scattering for moderat ors. For NJOY2016\, this new format has required changes in various module s\, the most important ones being THERMR (which processes the thermal scat tering data) and ACER (which formats the data into an ACE file for use in application codes like the MCNP® code [3]). Figure 1 gives an example of what this mixed mode data looks like for D in 7LiD after processing throug h ACER in NJOY2016.65 which provides this new capability.\n\nBecause the c oherent and incoherent data needs to be treated separately by MCNP6\, the mixed mode scattering also necessitated an update to the ACE format itself by adding an additional elastic scattering data block [4]\, and a subsequ ent modification to MCNP so that the mixed mode elastic data can be used d uring a Monte Carlo simulation. Experimental support for this new format i s available in MCNP\, version 6.3.0 [5].\n\nA second ENDF format change th at will impact processing is the addition of R-matrix background elements for resonance channels in the R-matrix limited format (LRF = 7). Contrary to the mixed mode elastic scattering\, the required changes to NJOY will b e mainly limited to RECONR and NJOY21’s resonance reconstruction compone nt.\n\nIn addition to these format changes\, some processing limitations t hat were identified in the past will also have to be lifted to process END F/B-VIII.1 evaluations. Examples here would be MF34 covariance processing with multiple subsections in ERRORR or photonuclear data processing (in th is case allowing for ACELAW=61 in the secondary photons).\n\nIn this paper we will give an overview of the most important changes that were made to NJOY2016 for processing ENDF/B-VIII.1 nuclear data\, and where possible we will provide validation results that illustrate the impact that these cha nges will have for nuclear data users.\n\nReferences\n[1] D. Brown et al.\ , “ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Lib rary with CIELO-project Cross Sections\, New Standards and Thermal Scatter ing Data\,” Nuclear Data Sheets\, 148\, 2018\, p. 1-142\n[2] R. E. MacFa rlane et al.\, “The NJOY Nuclear Data Processing System\, Version 2016\, ” Los Alamos National Laboratory\, LANL Technical Report LA-UR-20093\n[3 ] J. A. Kulesza et al.\, “MCNP Code Version 6.3.0 Theory & User Manual\, ” Los Alamos National Laboratory\, LANL Technical Report\, to be publish ed (2021)\n[4] J. L. Conlin\, P. Romano\, W. Haeck\, “A Compact ENDF (AC E) Format Specification\,” Los Alamos National Laboratory\, LANL Technic al Report LA-UR-19-29016\n[5] J. A. Kulesza\, C. J. Josey\, S. R. Bolding\ , J. C. Armstrong\, J. E. Sweezy\, J. S. Bull\, M. E. Rising\, E. J. Pears on\, “MCNP® Code Version 6.3.0 Release Notes\,” Los Alamos National L aboratory\, LANL Technical Report\, to be published (2021)\n\nhttps://indi co.frib.msu.edu/event/52/contributions/856/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/856/ END:VEVENT BEGIN:VEVENT SUMMARY:Additional reaction mechanisms to statistical $\\alpha$-emission a nd the related optical-potential validation DTSTART:20220728T150200Z DTEND:20220728T151400Z DTSTAMP:20260420T153400Z UID:indico-contribution-847@indico.frib.msu.edu DESCRIPTION:Speakers: Marilena Avrigeanu (Horia Hulubei National Institute for Physics and Nuclear Engineering (IFIN-HH))\, Vlad Avrigeanu (Horia Hu lubei National Institute for Physics and Nuclear Engineering (IFIN-HH))\n\ n\\documentclass[aps\,prc\,groupedaddress\,amsmath\,amssymb\,12pt\,tighten lines]{revtex4}\n\\usepackage{graphics}\n\\usepackage{longtable}\n\n\\begi n{document}\n\n\\title{Additional reaction mechanisms to statistical $\\al pha$-emission and the related optical-potential validation}\n\n\\author{V. ~Avrigeanu} \\email{vlad.avrigeanu@nipne.ro}\n\\author{M.~Avrigeanu}\n\n\\ affiliation{Horia Hulubei National Institute for Physics and Nuclear Engin eering\, 077125 Bucharest-Magurele\, Romania}\n\n\\maketitle \n\n%\\begin{ abstract}\n{\\bf Abstract} \n\nAn $\\alpha$-particle optical model potenti al (OMP) previously established by analysis of $\\alpha$-particle elastic scattering and induced reactions on $A$$\\approx$45--209 nuclei\, at ener gies $\\leq$50 MeV [1] has lately been proved able to describe also the $\ \alpha$-emission from excited nuclei in nucleon-induced reactions within t he $A$$\\sim$60 mass-number range [2]. This description in terms of the co mpound nucleus (CN) and pre-equilibrium emission (PE) models was possible firstly using CN+PE consistent parameter sets already validated by analysi s of other independent data that are distinct from $\\alpha$-induced react ion or $\\alpha$-emission cross sections. Thus\, it has also been provided an alternate solution of so-called $\\alpha$-potential mystery [3] to des cribe at once both absorption and emission of $\\alpha$-particles\, of equ al interest for nuclear astrophysics and fusion technology.\n\nOn the othe r hand\, it has been shown that further consideration should be given to t he pickup direct interaction (DI) leading to increase of the $\\alpha$-emi ssion beyond the CN+PE predictions. A suitable account of the measured $\\ alpha$-emission cross sections at the Giant Quadrupole Resonance (GQR) ene rgies of $^{55\,57\,58}$Fe excited nuclei\, in addition to the CN componen t\, has also been attributed to a {\\it like}-GQR component. Lastly\, a co mparison with results of an earlier OMP [4] that was set up to describe on ly the $\\alpha$-particle emission in neutron-induced reactions\, with dis tinct predictions from potentials for incident $\\alpha$ particles [5]\, s eems to answer the question of different OMPs for incident and emitted $\\ alpha$ particles [6-8].\n \nWhile the previous $\\alpha$-emission analysis [2] took the advantage of quite useful recent data of low-lying states fe eding in neutron-induced reactions on Fe\, Co\, Cu\, and Zn nuclei\, a sim ilar one for the stable Ni isotopes [9] provides its confident completion in the present work. Moreover\, the most-recent data around the GQR energi es of the excited nuclei in the $(n\,\\alpha)$ reaction on $^{58\,60\,61}$ Ni are additionally quite useful. Finally\, the issue of additional reacti on channels able to increase of the $\\alpha$-emission cross sections\, be yond the statistical predictions\, proved similar to that pointed out form erly [2]. Moreover\, a comparable contribution at the GQR energy of Ni exc ited nuclei has been needed in order to provide a suitable account of the measured $\\alpha$-emission cross sections at the lowest energies. This is sue is proved especially for $^{64}$Ni target nucleus due to the isotopic effect of the $(n\,\\alpha)$ reaction cross sections. On the other hand\, because the corresponding Gaussian distributions added in this respect ha ve widths which are much lower than the systematic 'best' values [10]\, we still may call these components only {\\it like}-GQR components. More sim ilar cases to be concerned particularly for heavier nuclei could help also concerning the physics behind the actual empirical addition.\n\n%\\end{ab stract}\n\n\\bigskip\n\n[1] V. Avrigeanu\, M. Avrigeanu\, and C. M\\u an\\ u ailescu\, Phys. Rev. C {\\bf 90}\, 044612 (2014)\n\n[2] V. Avrigeanu and M. Avrigeanu\, Eur. Phys. J. A {\\bf 57}\, 54 (2021)\n\n[3] T. Rauscher\, Phys. Rev. Lett. {\\bf 111}\, 061104 (2013).\n\n[4] V. Avrigeanu\, P.E. H odgson\, and M. Avrigeanu\, Phys. Rev. C {\\bf 49}\, 2136 (1994).\n\n[5] L . McFadden and G.R. Satchler\, Nucl. Phys. {\\bf 84}\, 177 (1966).\n\n[6] M. Avrigeanu\, W. von Oertzen\, and V. Avrigeanu\, Nucl. Phys. A {\\bf 764 }\, 246 (2006).\n\n[7] V. Avrigeanu and M. Avrigeanu\, Phys. Rev. C {\\bf 91}\, 064611 (2015).\n\n[8] V. Avrigeanu and M. Avrigeanu\, Phys. Rev. C { \\bf 96}\, 044610 (2017).\n\n[9] H. Jiang {\\it et al.}\, Chin. Phys. C {\ \bf 44}\, 114102 (2020).\n\n[10] J. Speth and A. van der Woude\, Rep. Prog . Phys. {\\bf 44}\, 719 (1981).\n\n\\vspace{1in}\n\\noindent\n{\\it This w ork has been partly supported by Autoritatea Nationala pentru Cercetare St iintifica (Project PN-19060102) and carried out within the framework of th e EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 and 2019-2020 under grant agreement No 6 33053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.}\n\n\\end{document}\n\nhttps://indico.fr ib.msu.edu/event/52/contributions/847/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/847/ END:VEVENT BEGIN:VEVENT SUMMARY:Assimilation of integral experiments on high-energy nuclear parame ters DTSTART:20220728T140000Z DTEND:20220728T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-884@indico.frib.msu.edu DESCRIPTION:Speakers: Elias Vandermeersch (CEA)\n\nNuclear data evaluation principally relies on adjustments of nuclear parameters on differential e xperiment data. To add another source of information\, one may use integra l experiments data. Usually\, this process is applied on multi-group cross sections\, with the help of deterministic transport code. However\, nucle ar data obtained are often biased toward the integral experiment studied\, or the calculation scheme used. To obtain the best adjustment\, and not d eteriorate nuclear data physical correlations\, one has to work directly w ith nuclear parameters. Such an assimilation needs to account for paramete rs influence not only on cross sections\, but also angular (AD) and energy (ED) distributions. Most of all\, to exclude all bias from multi-group di scretization\, continuous energy data has to be used.\n\nPrevious works [a ] managed to extend the assimilation process to nuclear parameters\, and e ven by using continuous energy [b]. However\, these were restricted to cro ss-sections influence\, and continuous energy calculations limited to spec ific nuclear parameters (resonance parameters). A recent coupling [c] betw een the nuclear reaction code CONRAD [d] and the stochastic code TRIPOLI-4 \\textregistered \\ [e] allows calculating full sensitivities of integral experiment reactivity to nuclear parameters\, with contributions from all nuclear data\, without energy and models restrictions. The CONRAD code is used to compute sensitivities of nuclear data to nuclear parameters\, and TRIPOLI-4 \\textregistered \\ computes reactivity sensitivities to nuclea r data. This second part uses perturbation theory\, implemented here with the Iterated Fission Probability method. All these contributions are used to compute full sensitivity $S$ of reactivity $\\rho$ to nuclear parameter $\\Gamma$:\n$S^\\rho_\\Gamma = \\int_E \\left[\\frac{\\partial \\rho}{\\p artial \\sigma(E)} \\frac{\\partial \\sigma(E)}{\\partial \\Gamma} + \\fra c{\\partial \\rho}{\\partial AD(E)} \\frac{\\partial AD(E)}{\\partial \\Ga mma} + \\frac{\\partial \\rho}{\\partial ED(E)} \\frac{\\partial ED(E)}{\\ partial \\Gamma}\\right]\\text{d}E.$\nThese sensitivities calculations are a main component of the assimilation process\, and this work seeks to stu dy the impact of a complete assimilation\, where sensitivities are calcula ted by taking account of all the nuclear data\, compared to a more classic multi-group cross section adjustment. For this work\, the assimilation is achieved with Bayesian inference\, solved by a Newton method (iterative G eneralized Least Square (GLS)). Such a method needs information about para meters values $\\vec{x}$\, correlations between nuclear parameters ${M}_{x }^{\\text{prior}}$\, the expected integral experiments data $\\vec{y}$\, sensitivities $S$ of this data to nuclear parameters\, correlations betwee n the integral experiments ${M}_{y}$\, and data estimation $\\vec{t}$ obta ined with the values of the studied parameters\, so that\, for each iterat ion $n$:\n$M_{x}^{n} = [{M_{x}^{\\text{prior}}}^{-1} + S_{n-1}^\\text{T} M _{y}^{-1} S_{n-1}]^{-1}\,$\nand:\n$\\vec{x}_n = \\vec{x}_{n-1} + M_x^n [S^ \\text{T}_{n-1} M_y^{-1}(\\vec{y}-\\vec{t}_{n-1}) + M_x^{\\text{prior}^{-1 }} (\\vec{x}_{n-1}-\\vec{x}^\\text{prior})]\,$\nwith $x^{\\text{prior}}$ t he initial nuclear parameters.\n\nThis work focus on the ICSPBEP benchmark Jezebel [f]: We used its reactivity to adjust the plutonium-239 Optical M odel Potential (OMP) parameters from Morillon-Romain [g] parametrization\, and fission-related parameters. From an initial plutonium-239 nuclear par ameter evaluation\, obtained after adjusting total and fission cross secti on over two sets of differential data\, we realized two assimilations of J ezebel's reactivity: The first one uses the complete assimilation\, with c omplete sensitivities\, and all the nuclear data are updated at each itera tion. The second assimilation is achieved by only working with cross secti on\, to be the closest to the classic adjustment. \n\nThe expected multipl ication factor ($k_\\text{eff}$) expected from Jezebel is 1.00000 $\\pm$ 2 00 pcm. The $k_\\text{eff}$ obtained after a Monte-Carlo transport simulat ion\, using the initial plutonium-239 evaluation\, was 0.97634 $\\pm$ 1 pc m. For the complete assimilation\, the fitted parameters give a $k_\\text{ eff}$ of 0.99833 $\\pm$ 1 pcm\, and $k_\\text{eff}$ = 0.99882 $\\pm$ 1 pcm for the cross-section only adjustment. Both methods manage to fit Jezebel expected reactivity. Thus\, the difference of 49 pcm highlights the impor tance of fitting nuclear parameters with full sensitivities. Regarding par ameters correlations\, presented in the figure below\, we see an initial a nticorrelation between OMP and fission parameters. Correlations matrix aft er assimilations are similar (small numerical differences)\, with a trend to decorrelate OMP parameters.\n\n![Nuclear parameters correlations matrix ][1]\n[Correlation matrix available here in case of indico error: https:// imagizer.imageshack.com/v2/xq90/922/m5slFm.png][2]\nWe are now attempting to compare the complete assimilation method to a determinist multi-group c ross section adjustment\, and to include neutron spectrum parameters in th e adjustment\, to fully characterize the impact of complete assimilation. The results\, to be presented in the full paper\, will be based on a more realistic initial plutonium-239 evaluation (the preliminary differential a djustment realized here was intentionally coarse\, to accelerate computati on time).\n\n[a] C. De Saint Jean et al. “Evaluation of Cross Section Un certainties Using Physical Constraints: Focus on Integral Experiments.” Nuclear Data Sheets\, Volume 123\, 2015\, Pages 178-184\, ISSN 0090-3752.\ n[b] V. Sobes et al. “Resonance Parameter Adjustment Basedon Integ ral Experiments.” Nuclear Science and Engineering\,volume 183(3)\, pp. 3 47–355(2016).\n[c] Elias Vandermeersch et al. “Two examples of recent advances in sensitivity calculations.” EPJ Nuclear Sci. Technol.\, 7 (20 21) 13.\n[d] P. Archier et al. “CONRAD Evaluation Code: Development St atus and Perspectives.” Nuclear Data Sheets\,volume 118\, pp. 488–490 (2014)\\newline\n[e] E. Brun et al. “TRIPOLI-4® \, CEA\, EDF and AREVA reference Monte Carlo code.”Annals of Nuclear Energy\,volume 82\, pp. 15 1–160 (2015). Joint International Conference onSupercomputing in Nuclea r Applications and Monte Carlo 2013\, SNA + MC 2013.\n[f] OECD-NEA. “Int ernational Handbook of Evaluated Criticality Safety Benchmark Experi-ments .“ Springer\, City and Country (2018).\n[g] B. Morillon and P. Romai n. “Dispersive and global spherical optical model with a localen ergy approximation for the scattering of neutrons by nuclei from1 keV to 2 00 MeV.” PhysRev C\,volume 70\, p. 014601 (2004).\n\n\n [1]: https://im agizer.imageshack.com/v2/xq90/922/m5slFm.png\n [2]: https://imagizer.imag eshack.com/v2/xq90/922/m5slFm.png\n\nhttps://indico.frib.msu.edu/event/52/ contributions/884/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/884/ END:VEVENT BEGIN:VEVENT SUMMARY:Total Absorption Spectroscopy of fission fragments relevant for re actor antineutrino spectra and nuclear structure and astrophysics DTSTART:20220728T130000Z DTEND:20220728T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-905@indico.frib.msu.edu DESCRIPTION:Speakers: Magali Estienne\, Muriel Fallot (Subatech)\n\nThe ac curate determination of reactor antineutrino spectra remains a very actual research topic for which new interrogations have emerged in the latest ye ars. Indeed\, after the “reactor anomaly”[1] – a deficit of measured antineutrinos at short baseline reactor experiments with respect to spect ral predictions – the three international reactor neutrino experiments D ouble Chooz\, Daya Bay and Reno have evidenced spectral distortions in the ir measurements w.r.t the same spectral predictions[2]. This puzzle is cal led the “shape anomaly”. The latter predictions were obtained through the conversion of integral beta energy spectra obtained at the ILL researc h reactor[3]. Several studies have shown that the underlying nuclear physi cs required for the conversion of these spectra into antineutrino spectra is not totally under control[4]. The unique alternative to converted spect ra is a complementary approach consisting in determining the antineutrino spectrum through nuclear data[5\,6]. It was shown that beta properties of some key fission products suffer from the pandemonium effect[7] which can be circumvented through the use of the Total Absorption Gamma-ray Spectros copy technique (TAGS). The main contributors to the PWR (Pressurized Water Reactor) antineutrino spectrum in the region where the spectral distortio n has been observed have been measured at the radioactive beam facility of the university of Jyväskylä in two TAGS experiments[8\,9\,10]. The anal ysis of these experiments is now complete and new yet unpublished results will be shown at this conference. We will then display an update of the cu mulative impact on the predictions of reactor antineutrino spectra of the final results of these TAGS campaigns and compare with the results of reac tor antineutrino experiments. Besides\, comparisons of measured experiment al beta strengths with predictions from theoretical models will be present ed\, of interest for nuclear structure and astrophysics. \n\n[1] G. Mentio n et al. \, Phys. Rev. D 83 \, 073006 (2011)\n[2] Double Chooz and Reno Co llaborations in Proceedings of the Neutrino 2014 Conference\, http://neutr ino2014.bu.edu/\; Daya Bay Collaboration in Proceedings of the ICHEP 2014 Conference\, http://ichep2014.es/.\n[3] P. Huber\, Phys. Rev. C 84\, 02461 7 (2011). \n[4] A. C. Hayes et al.\, Phys. Rev. Lett. 112\, 202501 (2014). \n[5] M. Fallot et al.\, Phys. Rev. Lett. 109 \, 202504 (2012). \n[6] A A . Sonzogni et al. \, Phys. Rev. C 91 \, 011301 (R) (2015). \n[7] J.C. Hard y et al. \, Phys. Lett. B 71 \, 307 (1977).\n[8] A.-A. Zakari-Issoufou\, P hys. Rev. Lett. 115 \, 102503 (2015).\n[9] V. Guadilla et al.\, Nuclear In struments and Methods in Physics Research B 376 (2016) 334. \n[10] A. Algo ra\, B. Rubio\, J.-L. Tain\, M. Fallot\, W. Gelletly Review Paper Eur. Phy s. J. A 57\, 85 (2021).\n\nhttps://indico.frib.msu.edu/event/52/contributi ons/905/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/905/ END:VEVENT BEGIN:VEVENT SUMMARY:Solid $^3$He target for nuclear reactions: H+$^3$He differential elasticscattering cross-section from 1.5 to 4.5 MeV DTSTART:20220728T191800Z DTEND:20220728T193000Z DTSTAMP:20260420T153400Z UID:indico-contribution-844@indico.frib.msu.edu DESCRIPTION:Speakers: Begoña Fernández-Martínez\, Juan Pablo Fernández -García\, Asunción Fernández\, Dirk Hufschmidt\, Francisco Javier Ferre r Fernandez\n\nDue to the introduction of several novel applications of He implantation\, e.g. in materials of future fusion reactors [1 and in opti cal waveguides [2\, 3]\, the need for elemental analysis of helium has rec ently increased dramatically. Depth profiling of helium can be realized by several ion beam analysis methods. Proton elastic backscattering spectrom etry (p-EBS) is a basic method for such analyses [4\, 5]. Ion beam analys is methods strongly rely on the available cross-section data\, and the acc uracy of IBA methods cannot exceed that of the available cross-sections. C onsequently\, precise cross-section curves are required in order to obtain reliable results with IBA. A large number of excitation functions for nuc lear reactions relevant to IBA have been measured and are compiled in IBAN DL at www.nds.iaea.org/ibandl/. This database reveals a lack of data for t he 3He(p\,p)3He cross section. Only one serie of data appears at one angle (159.2°) in a limited range of energies (1520-2860 keV).\nIn this work w e have measured the elastic scattering cross section using Si-3He targets developed by the NanoMatMicro group from the Institute of Materials Scienc e. [7]. With these data we have propose completed the resonance of the ela stic cross section in a range of energy from 1500 to 4500 keV at different angles (159\, 165 and 150°) and we have compared with the scarce data in the literature.\n\n[1] F. Paszti\, Nucl. Instr. and Meth. B 66 (1992) 83. \n[2] Y. Avrahami\, E. Zolotoyabko\, Nucl. Instr. and Meth. B 120 (1996) 8 4.\n[3] P. Bindner\, A. Boudrioua\, J.C. Loulergue\, P. Moretti\, Nucl. In str. and Meth. B 120\n(1996) 88.\n[4] J.S. Blewer\, Ion Beam Surface Layer Analysis\, Plenum\, New York\, 1976. p. 185.\n[5] F.J. Ferrer\, M. Alcair e\, J. Caballero-Hernández\, F.J. Garcia-Garcia\, J. Gil-Rostra\, A. Terr iza\, V. Godinho\, J. García-López\, A. Barranco\, A. Fernández-Camacho \, Nucl. Instr. and Meth. B 332 (2014) 449–453\n[6] Langley\, R.A. (1976 ) in Proc. Int. Conf. on Radiation Effect and Tritium Technology for Fusio n Reactors\, vol IV\, (J.S. Walson and F.W. Wiffen\, eds.)\, p.158. Conf. 750989\, US Dept. of Commerce\, Springfield\, VA\, USA\n[7] Asunción Fern ández\, Dirk Hufschmidt\, Julien L. Colaux\, Jose Javier Valiente-Dobón\ , Vanda Godinho\, Maria C. Jiménez de Haro\, David Feria\, Andrés Gadea\ , Stéphane Lucas\, Low gas consumption fabrication of 3He solid targets f or nuclear reactions\, Materials & Design\, 186 (2020) 108337 (1-10)\n\nht tps://indico.frib.msu.edu/event/52/contributions/844/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/844/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron production in the interaction of 200-MeV deuterons with Li \, Be\, C\, Al\, Cu\, Nb\, In\, Ta\, and Au DTSTART:20220728T193000Z DTEND:20220728T194200Z DTSTAMP:20260420T153400Z UID:indico-contribution-846@indico.frib.msu.edu DESCRIPTION:Speakers: Hiroki Sadamatsu\, Daiki Satoh\, Shiochiro Kawase\, Shinsuke Nakayama\, Tatsushi Shima\, Shouhei Araki\, Keita Nakano\, Yosuke Iwamoto\, Tadahiro Kin\, Masayuki Hagiwara\, Hiroshi Yashima\, Yukinobu W atanabe\n\nIntensive fast neutron sources using deuteron accelerators have been proposed for the study of medical RI production\, radiation damage f or fusion reactor materials\, nuclear transmutation of radioactive waste\, and so on. Neutron production data from various materials bombarded by de uterons are required for the design of such neutron sources. However\, the experimental data\, e.g. double-differential neutron production cross sec tions (DDXs)\, are not sufficient. In the present work\, therefore\, we ha ve conducted a systematic measurement of DDXs for a wide atomic number ran ge of targets (Li\, Be\, C\, Al\, Cu\, Nb\, In\, Ta\, and Au) at an incide nt energy of 200 MeV in the Research Center for Nuclear Physics (RCNP)\, O saka University.\n\nThe experiment was carried out at the N0 course in RCN P. A deuteron beam accelerated to 200 MeV was transported to the neutron e xperimental hall and focused on a thin target foil placed in the beam swin ger magnet. Emitted neutrons from the target were detected by two differen t-size EJ301 liquid organic scintillators (2” in dia. x 2” thick and 5 ” in dia. x 5” thick) located at two distances of 7 m and 20 m\, respe ctively. The neutron DDXs were measured at six forward angles (0$^\\circ$\ , 5$^\\circ$\, 10$^\\circ$\, 15$^\\circ$\, 20$^\\circ$\, and 25$^\\circ$) by moving the target along the beam trajectory in the swinger magnet. The two-gate integration method was adopted to eliminate gamma-ray background. The neutron energy was determined by a conventional time-of-flight (TOF) method.\n\nEach measured neutron spectrum showed a characteristic broad pe ak around half the incident deuteron energy\, which is formed via the brea kup of incident deuterons. The peak yield was found to increase monotonica lly with an increase in target mass number. The measured DDXs were compare d with theoretical model calculations by the DEUteron-induced Reaction Ana lysis Code System (DEURACS) [1\,2] and PHITS [3]. The result indicated tha t the DEURACS calculation provides better agreement with the measured DDXs than the PHITS calculation. In addition\, two deuteron nuclear libraries\ , JENDL Deuteron Reaction Data File 2020 (JENDL/DEU-2020) [4] and TENDL-20 17 [5]\, were benchmarked using the experimental DDX data of Li\, Be\, and C. \n\n[1] S. Nakayama\, H. Kouno\, Y. Watanabe\, Phys. Rev. C **94**\, 0 14618 (2016). \n[2] S. Nakayama\, O. Iwamoto\, Y. Watanabe\, Phys. Rev. C **100**\, 044603 (2019).\n[3] T. Sato\, et al.\, J. Nucl. Sci. Technol. ** 55**\, 684-690 (2018).\n[4] S. Nakayama\, et al.\, J. Nucl. Sci. Technol. **58**\, 805-821 (2021).\n[5] A. J. Koning\, and D. Rochman\, Nucl. Data S heets\, **113**\, 2841(2012).\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/846/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/846/ END:VEVENT BEGIN:VEVENT SUMMARY:Dependence of TKE of fission fragments in neutron-induced fission on excitation energy by 4D Langevin mode DTSTART:20220726T130000Z DTEND:20220726T131200Z DTSTAMP:20260420T153400Z UID:indico-contribution-603@indico.frib.msu.edu DESCRIPTION:Speakers: Fedir Ivanyuk\, Chikako Ishizuka\, Satoshi Chiba\, K azuya Shimada\n\nThe total kinetic energy (TKE) of fission fragments is ac counting for about 80 to 90 % of the Q-value in nuclear fission. Therefore \, it is important to understand the characteristics of TKE from the persp ective of nuclear energy utilization and basic research\, e.g.\, number of fission in reactor power or local heating of the r-process site including fission recycling. Naively thinking\, the TKE is expected to increase\, w hen the excitation energy of the fissioning system increases. In the reali ty\, however\, the TKE decreases as the excitation energy increases as is shown by many data on neutron-induced nuclear fission. Our 4-dimensional L angevin model has elucidated this mystery. TKE and the fission fragment de formation are related\, the excitation energy dependence of TKE decreasing is discussed.\n\nhttps://indico.frib.msu.edu/event/52/contributions/603/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/603/ END:VEVENT BEGIN:VEVENT SUMMARY:Comprehensive investigation of fission yields by using (p\,2p)- in duced fission in inverse kinematics. DTSTART:20220727T191200Z DTEND:20220727T192400Z DTSTAMP:20260420T153400Z UID:indico-contribution-640@indico.frib.msu.edu DESCRIPTION:Speakers: José Luis Rodríguez Sánchez (Universidad de Santi ago de Compostela)\, Jose Benlliure\n\nFission reactions investigated in i nverse kinematic at relativistic energies have proven\nto be a powerful te chnique to get access to a large variety of non stable heavy nuclei\n[1] b ut also to fully identify\, for the first time\, in atomic and mass number both fission\nfragments [2]. These systematic investigations made possibl e to establish the role of\nproton shells in the asymmetric fission modes present in actinides and pre-actinides [3]\nbut also to identify a new com pact symmetric fission mode from the fission yields\nevolution in thorium isotopes [4].\nUntil now\, inverse kinematic fission was mostly induced by the excitation of the giant-\ndipole resonance (GDR) in electromagnetic i nteractions using targets with large atomic\nnumber. The advantage of Coul ex is the large fission cross sections\, being the only\ndrawback that the range in excitation energy covered is limited to the GDR width and\nno en ergy selection possibility. To go a step further\, we propose now to induc e fission\nusing quasi-free scattering (QFS) of protons (p\,2p).\nQFS of p rotons on heavy nuclei induces fission through particle-hole excitations t hat\ncan range from few to ten’s of MeV. Moreover\, the measurement of t he momenta of the\ntwo scattered protons made it possible to determine the missing energy in the reaction\nand then\, the excitation energy of the f issioning compound nucleus.\nThe realization of such an experiment require s a complex setup providing the full\nisotopic identification of both fiss ion fragments\, and at the same time a precise\nmeasurement of the momenta of the two outgoing protons. This was realized at the\nR3B experiment at GSI/FAIR (see Fig.1).\nAt R3B\, a liquid hydrogen target is used to induce d (p\,2p) QFS on the incoming heavy\nprojectiles accelerated at relativist ic energies (~ 500A MeV). Fission fragments\nproduced in those reactions f ly forward and are identified in atomic number by\nmeasuring their energy loss in a twin ionization chamber and their time-of-flight\nbetween a star t plastic scintillator and a stop large-area wall of plastic scintillators . The\nmass numbers of the fragments is obtained by tracking their traject ories in the large-\nacceptance super-conducting magnet GLAD. In order to achieve a resolution in charge\nof around 0.4 units (FWHM) (see Fig. 2) an d in mass of around 0.6 units\, the energy\nloss was measured with an accu racy of 1%\, time-of-flight with a resolution of 40 ps\n(FWHM) and the tra jectories with a resolution of around 200 m (FWHM).\nThe missing energy in the reaction is determined using a silicon tracker and the\nCALIFA calori meter surrounding the target to measure the momenta of the two\nprotons. T he measurement of these momenta with a resolution around 1% allows us to\n reconstruct the excitation energy of the fissioning compound nucleus with a resolution\nof around 3 MeV.\n\nIn this work we will present the first r esults of an experiment we run last April 2021 to\ninvestigate the dumping of shell effects in the fission yields. We will also outline the\nfuture program at R3B to investigate fission at the new FAIR facility.\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/640/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/640/ END:VEVENT BEGIN:VEVENT SUMMARY:Bayesian Monte Carlo Evaluation Framework for Imperfect Data and M odels DTSTART:20220726T190300Z DTEND:20220726T191500Z DTSTAMP:20260420T153400Z UID:indico-contribution-900@indico.frib.msu.edu DESCRIPTION:Speakers: Jesse Brown (ORNL)\n\nhttps://indico.frib.msu.edu/ev ent/52/contributions/900/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/900/ END:VEVENT BEGIN:VEVENT SUMMARY:Deep Learning applied to Capture Cross Section Data Analyisis DTSTART:20220725T163000Z DTEND:20220725T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-765@indico.frib.msu.edu DESCRIPTION:Speakers: Adrian Sanchez Caballero\n\nThe data analysis of neu tron cross section measurements is a critical step for generating high qua lity and reliable nuclear databases [1-4] to be used in the fields of nucl ear technologies\, radioprotection\, nuclear medicine or astrophysics\, am ong others. Artificial intelligence techniques\, and in particular deep le arning\, have proven to be a very useful tool for data recognition and ana lysis. We have investigated the suitability of deep learning and neural ne twork techniques as a complementary tool for the analysis of neutron captu re cross section measurements. \n\nSome of the neutron capture cross secti on measurements performed at the n_TOF facility at CERN [5] use the so-cal led Total Absorption Calorimeter (TAC) [6]. This device is made of 40 BaF$ _2$ crystals capable of detecting in coincidence the γ-rays emitted after the capture reactions. In a standard analysis\, conditions (cuts) on the total energy deposition in the TAC and on the event multiplicity (number o f crystals with signals in coincidence) serve to discriminate capture from background events. \n\nWe have trained a neural network with the list of energies deposited in the different crystals with Monte Carlo simulated ca pture and background events (due to scattered neutrons and competing fissi on reactions) and evaluated its capability of selecting the γ-ray cascade s in a virtual capture experiment. We have compared different strategies a nd combinations of the neural network topologies and standard analysis met hods in order to obtain at the same time large signal-to-background ratios and large capture detection efficiencies. The use of a neural network wit h 5 hidden fully connected layers and some conditions on the total energy and multiplicity of the crystals has achieved up to 5 times better signal- to-background ratio and ~15% more remaining capture events in the resultin g dataset than with the standard analysis method. \n\nIn this conference\ , we will present these results and describe the deep learning methods use d. \n \n\nReferences\n----------\n[1] OTUKA\, N.\, et al.\, Towards a more complete and accurate experimental nuclear reaction data library (EXFOR) : international collaboration between nuclear reaction data centres (NRDC) \, Nucl. Data Sheets 120\, 272 (2014).\n[2] BROWN\, D.A.\, The 8th major r elease of the nuclear reaction data library with CIELO-project cross secti ons\, new standards and thermal scattering data\, Nucl. Data Sheets\, 148 (2028) 1-142. \n[3] CABELLOS\, O.\, et al.\, Benchmarking and validation a ctivities within JEFF project\, EPJ Web Conf.\, 146 (2017)\, Article 06004 .\n[4] SHIBATA\, K.\, et al.\, JENDL-4.0: A new library for nuclear scienc e and engineering\, J. Nucl. Sci. Technol.\, 48 1 (2011) 1.\n[5] GUERRERO\ , C.\, et al. Performance of the neutron time-of-flight facility n_TOF at CERN. Eur. Phys. J. A 49\, 27 (2013). \n[6] GUERRERO\, C.\, et al.\, The n _TOF total absorption calorimeter for neutron capture measurements at CERN \, Nucl. Instrum. Methods A\, 608 3 (2009) 424-433.\n[7] GARSONS\, G.D.\, Interpreting neural networks connection weights\, AI Expert 6 (1991) 47-51 .\n\nhttps://indico.frib.msu.edu/event/52/contributions/765/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/765/ END:VEVENT BEGIN:VEVENT SUMMARY:Impact of adjustment with criticality and reaction rate data DTSTART:20220728T133600Z DTEND:20220728T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-881@indico.frib.msu.edu DESCRIPTION:Speakers: Robert Casperson (LLNL)\n\nAdjustment is a useful to ol for optimizing a nuclear data library for particular applications\, but can also highlight deficiencies and suggest changes when employed with va lidation data that disagrees with an evaluation. Spectral indices validat ion data for ENDF/B-VIII.0 appear systematically higher than calculated va lues made using the evaluation. Adjustment with this data would lead to c hanges in criticality significantly beyond experimental keff uncertainties \, while adjustment with these reaction rates along with criticality data leads to an evaluation that is consistent with both.\n\nThe adjusted evalu ation suggests changes in major actinide fission cross sections\, particul arly a 1% decrease in U-235(n\,f). Additionally\, uncertainties in fissio n and inelastic scattering cross sections are significantly reduced\, a re sult that is not observed with criticality adjustment alone. The implicat ions and limitations of these results are discussed.\n\nThis work was perf ormed under the auspices of the U.S. Department of Energy by Lawrence Live rmore National Laboratory under contract DE-AC52-07NA27344.\n\nhttps://ind ico.frib.msu.edu/event/52/contributions/881/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/881/ END:VEVENT BEGIN:VEVENT SUMMARY:Determination of the Plasma Delay Time in PIPS detectors for fissi on fragments with the LOHENGRIN spectrometer DTSTART:20220726T132400Z DTEND:20220726T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-605@indico.frib.msu.edu DESCRIPTION:Speakers: A. Soklers\, A. Oberstedt\, A. G. Smith\, N. V. Sosn in\, S. Oberstedt\, Z. Gao\, S. Bennett\, S. Pomp\, D. Tarrio\, A. Al-Adil i\, Y. H. Kim\, A. Göök\, U. Köster\, Ana Maria Gomez\n\nThe particle s pectrometer VERDI (VElocity foR Direct particle Identification) allows hig h-precision measurements of fission fragment (FF) mass distributions by us ing the 2E-2v technique. VERDI consists of two arms with 16 Silicon PIPS ( Passivated Implanted Planar Silicon) detectors and a Micro Channel Plate ( MCP) each. The MCPs provide the pick-off signal used to trigger the time-o f-flight (ToF) measurement\, and the Si detectors are used both for energy detection and as a stop signal. In silicon detectors\, the signal amplitu de and shape get affected by the formation of a plasma from the interactio n between the heavy ions and the detector material. In PIPS detectors this plasma causes a signal delay\, the Plasma Delay Time (PDT)\, with typical delays up to 5 ns for FFs\, resulting in a smearing of the mass distribut ion as well as increasing the systematic errors [1]. Moreover\, it can ren der faulty fission-neutron correlations\, if not properly corrected. Exist ing studies [2-4] propose different parameterizations to calculate the PDT contribution. These studies are not in agreement with each other and are limited to certain ion species and regions of energy. Moreover\, the PDT e ffect is believed to be detector-specific\, which necessitates a dedicated investigation. \n\nA characterization of the PDT in the silicon detectors used in VERDI was performed at the LOHENGRIN recoil separator of the Ins titut Laue Langevin\, for a wide range of energies and masses\, $E$ $\\sim $ 40-110 MeV and $A$ $\\sim$ 80-160 u\, respectively. With LOHENGRIN\, cha racteristic FFs from $^{239}$Pu(n\,f) were selected based on their A/q and E/q ratios. A unique collaboration allowed the utilization of a MCP detec tor from the STEFF spectrometer [5] and 6 silicon detectors from VERDI. Th e measured ToF\, between the MCP and silicon\, was compared to the true To F derived from LOHENGRIN. The signals were recorded in a digital acquisiti on system to completely exploit the offline analysis capabilities. All the PIPS detectors were fully characterized to study their individual respons e to the PDT effect. The data will provide a calibration procedure in whic h the PDT contribution is calculated relative to alpha particles and proto ns. The achieved combined timing and energy resolutions of our experimenta l setup are around 160 ps and 0.1 MeV (FWHM)\, respectively.\n\nDuring the presentation\, we will discuss the PDT trend as a function of both mass a nd energy of the FF\, and we will relate them to the protons and alpha par ticles. In addition\, we will discuss the impact of the PDT correction on the fission fragment data measured with the 2E-2v method. \n\n[1] Jansson\ , K.\, Al-Adili\, A.\, Andersson Sundén\, E. *et al.* The impact of neutr on emission on correlated fission data from the 2E-2v method. *Eur. Phys. J. A* **54**\, 114 (2018). https://doi.org/10.1140/epja/i2018-12544-0\n\n[ 2] J. Velkovska and R.L. McGrath. Fission fragment mass reconstruction fro m Si surface barrier detector measurement. *Nucl. Instrum. Methods Phys. R es. A.* **430\, 2-3** 507-511 (1999). https://doi.org/10.1016/S0168-9002(9 9)00225-9\n\n[3] W. Seibt\, K.E. Sundström\, P.A. Tove. Charge collection in silicon detectors for strongly ionizing particles *Nucl. Instrum. Meth ods Phys. Res. A.* **113\, 3** 317-324 (1973). https://doi.org/10.1016/002 9-554X(73)90496-5\n\n\n[4] H-O. Neidel\, H. Henschel\, H. Geissel\, Y. Lai chter. Plasma delay of $^{238}$U ions in surface barrier detectors *Nucl. Instrum. Methods Phys.* **212\, 1-3** 299-300 (1983). https://doi.org/10.1 016/0167-5087(83)90705-6\n\n[5] I. Tsekhanovich\, J.A. Dare\, A. G. Smith\ , *et. al.* A novel 2v2e spectrometer in Manchester: new development in id entification of Fission Fragments *Seminar on Fission* *pp 189-196* (2008 ). https://doi.org/10.1142/9789812791061_0018\n\nhttps://indico.frib.msu.e du/event/52/contributions/605/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/605/ END:VEVENT BEGIN:VEVENT SUMMARY:Results of the $^{244}$Cm\, $^{246}$Cm and $^{248}$Cm neutron-indu ced capture cross sections measurements at EAR1 and EAR2 of the n_TOF f acility DTSTART:20220726T191500Z DTEND:20220726T192700Z DTSTAMP:20260420T153400Z UID:indico-contribution-824@indico.frib.msu.edu DESCRIPTION:Speakers: Trinitario Martinez\, Enrique Miguel Gonzalez-Romero \, Daniel Cano-Ott\, Atsushi Kimura\, Alberto Pérez de Rada Fiol\, Emilio Mendoza Cembranos\, the n_TOF Collaboration\, Victor Alcayne\n\nV. Alcayn e a)\, A. Kimura b)\, E. Mendoza a)\, D. Cano-Ott a)\, T. Martinez a)\, E. González-Romero a)\, A. Pérez de Rada a)\, and the n_TOF collaboration c)\n\na) Centro de Investigaciones Energéticas\, Medioambientales y Tecno lógicas (CIEMAT)\, E-28040 Madrid\, Spain\nb) Japan Atomic Energy Agency (JAEA)\, Tokai-mura\, Japan\nc) Conseil Européen pour la Recherche Nuclé aire\, CERN\, Switzerland\n\nThe safe and efficient management of the high level waste produced in the operation of nuclear reactors requires more a ccurate nuclear data. In particular\, inventory calculations of the spent nuclear fuel (SNF) and the derived magnitudes such as the decay heat\, rad io toxicity or neutron and gamma dose\, among others\, rely on the accurac y of neutron induced reaction cross sections ruling the burn-up in the rea ctor. The Cm isotopes require a special attention due to their various imp lications along the fuel cycle. For instance\, $^{244}$Cm is responsible of ∼10% of the radio-toxicity and the decay heat in the spent nuclear fu el in a Light Water Reactor (LWR) during the first fifteen years after unl oading the SNF from the reactor. Furthermore\, the neutron emission in the spent fuel is dominated by the $^{244}$Cm and $^{246}$Cm spontaneous fiss ion during the first 10$^4$ years of disposal. From the point of view of r eactor (LWR) and fuel cycle parameters\, the sensitivity analyses performe d in [1] indicate that uncertainties in the $^{244}$Cm capture cross secti on need to be reduced to 4.1% between 4 and 22.6 eV and to 14.4% between 2 2.6 and 454 eV. Last\, but not least\, a more accurate knowledge of the ca pture cross sections of $^{244}$Cm\, $^{246}$Cm and $^{248}$Cm is required for improving the calculations on the formation of heavier isotopes such as Bk\, Cf and other Cm isotopes.\n\nIn this work\, we will present the fi nal results of the capture cross section measurement on $^{244}$Cm\, $^{24 6}$Cm and $^{248}$Cm performed at the CERN n\\_TOF facility [2]. It is imp ortant to notice that\, the Cm samples used in the experiment at n\\_TOF h ave been used previously in an experiment at J-PARC [3]. At n\\_TOF\, the capture cross section measurements of $^{244}$Cm\, $^{246}$Cm and $^{248}$ Cm were performed at the 20 m vertical flight path (EAR2) with three C$_6$ D$_6$ total energy detectors [4]. In addition\, the cross section of $^{24 4}$Cm was measured at the 185 m flight path (EAR1) with a Total Absorption Calorimeter (TAC) [5]. The combination of measurements in EAR1 and EAR2 a nd the use of two complementary experimental techniques\, the total absorp tion calorimetry and the pulse height weighting technique\, has contribute d to control and reduce the systematic uncertainties in the results.\nWe w ill present the radiative kernels of the resonances of $^{244}$Cm\, $^{246 }$Cm and $^{248}$Cm obtained in the energy ranges from 7 to 300 eV\, 4 to 400 eV\, and 7 to 100 eV\, respectively\, and compare the results of the m easurement with previous capture and transmission data and evaluated cross sections.\n\nReferences\n[1] G. Aliberti et. al.\, \, Ann. Nucl. Ener. 33 \, 700 (2006)\n[2] C. Guerrero et al. Eur. Phys. J. A 49\, 27 (2013)\n[3] A. Kimura et. al.\, Jour. Nucl. Sc. Tech. 49\, 708 (2012)\n[4] U. Abbondan noet al.\, Nuc. Inst. Meth. A. 521\, 454-467\, (2004)\n[5] C.Guerrero et a l.\, Nucl. Instrum. Meth. A 608\, 424 (2009)\n\nhttps://indico.frib.msu.ed u/event/52/contributions/824/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/824/ END:VEVENT BEGIN:VEVENT SUMMARY:EUCLID: A New Approach to Improve Nuclear Data Coupling Optimized Experiments with Validation using Machine Learning DTSTART:20220727T132400Z DTEND:20220727T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-777@indico.frib.msu.edu DESCRIPTION:Speakers: Jesson Hutchinson (LANL)\n\n\\documentclass{style/ns eJournal}\n\n\\usepackage{enumitem}\n\\usepackage{xcolor}\n\\usepackage{hy perref}\n\\usepackage{cleveref}\n\\usepackage{graphicx}\n\\usepackage{rota ting}\n\\usepackage{ulem}\n\n\\newcommand{\\beff}{$\\beta_\\mathrm{eff} $} \n\\newcommand{\\keff}{$k_\\mathrm{eff}$}\n\n\\begin{document}\n\n\\title{ EUCLID: A New Approach to Improve Nuclear Data Coupling Optimized Experime nts with Validation using Machine Learning}\n\n\\addAuthor{\\corresponding Author{Jesson Hutchinson}}{a}\n\\correspondingEmail{jesson@lanl.gov}\n\\ad dAuthor{Jennifer Alwin}{a}\n\\addAuthor{Alex{and}er Clark}{a}\n\\addAuthor {Theresa Cutler}{a}\n\\addAuthor{Michael Grosskopf}{a}\n\\addAuthor{Wim Ha eck}{a}\n\\addAuthor{Michal Herman}{a}\n\\addAuthor{Noah Kleedtke}{a}\n\\a ddAuthor{Juliann Lamproe}{a}\n\\addAuthor{Robert Little}{a}\n\\addAuthor{I saac Michaud}{a}\n\\addAuthor{Denise Neudecker}{a}\n\\addAuthor{Michael Ri sing}{a}\n\\addAuthor{Travis Smith}{a}\n\\addAuthor{Nicholas Thompson}{a}\ n\\addAuthor{Scott Vander Wiel}{a}\n\n\\addAffiliation{a}{Los Alamos Natio nal Laboratory\\\\ P.O. Box 1663\, MS B228\, Los Alamos\, New Mexico 87545 }\n\n%\\addKeyword{None}\n\n\\titlePage\n\n\n\\section{Abstract}\n\\label{ sec:Intro}\nUnconstrained physics spaces arise between nuclear data due to imprecise knowledge or missing differential experimental data and theory combined with the fact that validation with integral experiments cannot un iquely identify one nuclear-data value as driving the difference between s imulated and experimental values of these experiments. Compensating errors of nuclear data can easily hide within these unconstrained physics spaces . This can potentially have large impacts on application calculations that do not closely resemble validation experiments we validate our nuclear da ta against.\n\nThe EUCLID project (Experiments Underpinned by Computationa l Learning for Improvements in Nuclear Data) aims to resolve part of these compensating errors by performing an integral experiment optimized to bet ter constrain nuclear data. In addition to that\, the project will adjust ENDF/B-VIII.0 nuclear data with respect to this new experiment to better c onstrain nuclear data. \n\nEUCLID includes four major components: (1) simu lations\, (2) experiments\, (3) machine learning\, and (4) nuclear data va lidation/adjustment. One major component of EUCLID is the evaluation of se veral integral measurement methods (criticality\, reaction rate ratios\, n eutron noise\, etc.). Regarding simulations\, new capabilities are being d eveloped to estimate sensitivity coefficients for all of these methods. Re garding experiments\, the National Criticality Experiments Research Center (NCERC) will be utilized to perform measurements. These experiments will be optimized using Bayesian optimization. The measured responses (along wi th the simulated responses and sensitivities) will be utilized via Random Forest to perform nuclear data adjustment. This will include requirements to obey physics constraints and will result in adjusted nuclear data. \n\n \\begin{figure}[htb!]\n %\\vspace{-20pt}\n \\centering\\includegraphics[wi dth=6in]{figures/EUCLIDimage.pdf}\n %\\vspace{-5pt}\n \\caption{Unconstrai ned physics spaces within nuclear data can adversely impact application si mulations\, but cannot be resolved using current techniques. EUCLID aims t o provide a capability to help understand such unconstrained spaces. In or der to achieve this\, we utilize machine learning with simulated sensitivi ties in MCNP of experiments and measured results to augment expert identif ication of areas where compensating errors may be resolved. The design of new experiments will then be optimized using machine learning. After the n ew experiments are completed\, the new data will be used to produce adjust ed libraries.} \n \\label{Fig_EUCLID}\n %\\vspace{-25pt}\n\\end{figure}\n\ n\\newpage\n\n\\section*{Acknowledgments}\n\\label{sec:acknowledgements}\n \\textcolor{black}{Research reported in this publication was supported by the U.S. Department of Energy LDRD program at Los Alamos National Laborato ry. The National Criticality Experiments Research Center (NCERC) is suppor ted by the DOE Nuclear Criticality Safety Program\, funded and managed by the National Nuclear Security Administration for the Department of Energy. This work was supported by the US Department of Energy through the Los Al amos National Laboratory. Los Alamos National Laboratory is operated by Tr iad National Security\, LLC\, for the National Nuclear Security Administra tion of the US Department of Energy under Contract No. 89233218CNA000001.} \n\n\\end{document}\n\nhttps://indico.frib.msu.edu/event/52/contributions/ 777/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/777/ END:VEVENT BEGIN:VEVENT SUMMARY:Comparison of URR Implementations in GNDS Format DTSTART:20220727T153300Z DTEND:20220727T154500Z DTSTAMP:20260420T153400Z UID:indico-contribution-996@indico.frib.msu.edu DESCRIPTION:Speakers: Caleb Mattoon (Lawrence Livermore National Laborator y)\, Bret Beck\, Matteo Vorabbi (Brookhaven National Laboratory)\, Pavlos Vranas (Lawrence Livermore National Laboratory)\, Godfree Gert\, Marie-Ann e Descalle (LLNL)\n\nThe Generalized Nuclear Database Structure (GNDS) is an international nuclear data format meant to replace the half-century-old Evaluated Nuclear Data Format (ENDF-6). The current version of the specif ications as defined by the Working Party on Evaluation Co-operation (OECD/ NEA/WPEC) Expert group on GNDS (EGGNDS)\, includes specifications for the treatment of the unresolved resonances region (URR) and of thermal neutron scattering laws. However\, the URR specifications in the current and upco ming GNDS specifications do not fully support the data format and construc ts for the URR probability tables required by ACE files and the Monte Carl o transport codes that use them.\n\nLawrence Livermore National Laboratory has developed a suite of codes to handle GNDS formatted data\, a processi ng code named FUDGE (For Updating Data and Generating Evaluations)\, and G IDI+. FUDGE supports translation of ENDF-6 formatted data to and from GNDS . It processes GNDS data for use in Monte Carlo and deterministic transpor t codes\, including reconstructing cross sections and angular distribution s from resonance parameters. Finally\, FUDGE can also translate data from GNDS into the ACE format\, for use in Monte Carlo transport codes that use ACE formatted data (e.g.\, MCNP6). GIDI+ consists of two C++ libraries na med GIDI (General Interaction Data Interface) and MCGIDI (Monte Carlo GIDI ) for accessing nuclear data from the Generalized Nuclear Database Structu re. GIDI directly accesses the GNDS data and is implemented in LLNL’s Mo nte Carlo and deterministic particle transport codes named Mercury and Ard ra\, respectively. The MCGIDI library extracts data from a GIDI instance a nd puts the data into a form better suited for Monte Carlo transport. MCGI DI also provides routines to look up and sample from the data. MCGIDI is i mplemented in Mercury.\n\nThe implementation of URR has implications in te rms of data format specifications\, processing codes and processed data fi les\, and transport codes. FUDGE has recently been updated to support two different methods of computing and sampling cross sections in the URR. One option is to produce a cross section probability density function (pdf) f or each open reaction. Another option\, similar to the PURR module in NJOY \, is to produce a probability table for the total cross section at each i ncident energy along with conditional probabilities for each open reaction . Both options condense the variability of URR cross sections into a form that can be easily integrated in Monte Carlo transport\, but the two optio ns must be stored and sampled differently.\n\nWe previously demonstrated t he first implementation of the processing and simulations capabilities for the URR probability tables in GNDS/GIDI/MCGIDI\, and we observed discrepa ncies between the MCNP and Mercury Monte Carlo codes for some of the criti cality benchmarks that are sensitive to the URR cross sections. Here\, we present results from criticality benchmark simulations using ENDF/B-VIII. 0 evaluated nuclear data to test and compare the original implementation o f the Unresolved Resonance Region probability tables in NJOY to FUDGE and GIDI/MCGIDI results using both options outlined above. We also compare k-e ffective values obtained with the Mercury code (with cross section data in the GNDS format) to those calculated using MCNP6 (with cross section data in the ACE format). For the MCNP cases comparisons are made with ACE file s that were generated with both NJOY and FUDGE.\n\nPrepared by LLNL under Contract DE-AC52-07NA27344.\n\nhttps://indico.frib.msu.edu/event/52/contri butions/996/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/996/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Programme for the measurement of ($\\alpha$\,xn) react ion yields and neutron spectra in Spain: the MANY collaboration DTSTART:20220727T153300Z DTEND:20220727T155700Z DTSTAMP:20260420T153400Z UID:indico-contribution-802@indico.frib.msu.edu DESCRIPTION:Speakers: Daniel Cano-Ott\, Roberto Santorelli\, J. R. Murias\ , Beatriz Fernández\, Ariel Tarifeño-Saldivia\, Trinitario Martinez\, M. Llanos\, Emilio Mendoza\, David Villamarin\, César Domingo\, J. Briz\, A lvaro Tolosa-Delgado\, Alberto Perez de Rada\, Jose Manuel Quesada\, Adria n Sanchez\, Enrique Nacher\, Javier Balibrea\, A. De Blas\, Joaquin Gomez- Camacho\, Carlos Guerrero\, Victor Sanchez Tembleque\, Sonia Orrigo\, Vice nte Pesudo\, Angel Perea\, Olof Tengblad\, María José García Borge\, Ga stón Garcia\, R. Garcia\, Jorge Lerendegui-Marco\, Nil Mont i Geli\, Fran cisco Calviño\, Silvia Viñals\, Guillem Cortés\, M. Pallas\, J. Benito\ , Victor Alcayne\, Luis Mario Fraile\, Jose Manuel Udias\, Alejandro Algor a\, Jose Luis Tain\, Julio Plaza\, Enrique Miguel Gonzalez-Romero\n\nNeutr on yields and energy spectra from ($\\alpha$\,xn) reactions are relevant d ata for several fields such as nuclear astrophysics\, underground physics (low background measurements)\, nuclear technologies and applications like nuclear safeguards. The existing experimental data have been obtained wit h thin and thick targets often via activation measurements or in direct ne utron measurements using proportional counters based on BF$_{3}$ and $^{3} $He as well as with organic scintillators. The data available in the EXFOR database [1] show large discrepancies with respect to the reported uncert ainties. On the other hand\, the only existing evaluated nuclear data libr ary JENDL/AN-2005 [2] contains information for just 17 isotopes. The gener al purpose and computer driven TENDL [3] library provides data for a much larger set of isotopes\, but in relevant cases it differs significantly fr om the JENDL/AN-2005 evaluation and from the experimental data. Therefore\ , the conclusion is that it is highly desirable to perform new measurement s with the aim to improve our knowledge on ($\\alpha$\,xn) cross sections. \n\nA collaboration for the Measurement of Alpha Neutron Yields and spectr a (MANY) formed by Spanish research groups has been established with the a im to carry out measurements of ($\\alpha$\,xn) reactions on isotopes of i nterest. Two different detector types are being used: one based on $^{3}$H e proportional counters moderated in a high-density polyethylene matrix\, miniBELENA [4]\, and a second detector based on BC501/EJ301 liquid scintil lator modules\, MONSTER [5\, 6]\, which can operate as a time of flight sp ectrometer. Both instruments are coupled to high performance digital elect ronics and have been commissioned at the two accelerator facilities CMAM [ 7] and CNA HISPANOS [8] studying the response to well-known nuclear reacti ons. The measurements are complemented by $\\gamma$ spectroscopy measureme nts for ($\\alpha$\,xn$\\gamma$) reactions using an array of fast scintill ators. \n\nThe experimental program of the MANY collaboration and first re sults with pulsed and continuous $\\alpha$ beams will be reported. A compa rison with simulations carried out with the SaG4n code [9] for ($\\alpha$\ ,xn) yield calculations will also be provided.\n\n**References**\n[1] http s://www-nds.iaea.org/exfor/endf.htm\n[2] T. Murata\, H. Matsunobu\, K. Shi bata\, Technical Report\, JAEA-Research 2006-052\, 2006.\n[3] A. Koning an d D. Rochman\, Nucl. Data Sheets\, 113 (12) (2012)\, pp. 2841-2934\n[4] N. Mont i Geli\, A novel modular neutron detector for ($\\alpha$\,n) reactio ns: design and experimental validation\, Master thesis. U. de Sevilla\, 20 20.\n[5] A.R. Garcia et al.\, JINST 7 C05012 (2012).\n[6] T. Martinez et a l.\, Nuclear Data Sheets\, 120 (2014)\, pp. 78\n[7] A. Redondo-Cubero et a l.\, Eur. Phys. J. Plus (2021) pp. 136-175\nhttps://doi.org/10.1140/epjp/s 13360-021-01085-9\n[8] Gomez-Camacho\, J.\, Garcia Lopez\, J.\, Guerrero\, C. et al. Research facilities and highlights at the Centro Nacional de Ac eleradores (CNA). Eur. Phys. J. Plus 136\, 273 (2021)\n[9] E. Mendoza et a l.\, Nucl. Instr. and Meth. A 960\, (2020) 163659.\n\nhttps://indico.frib .msu.edu/event/52/contributions/802/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/802/ END:VEVENT BEGIN:VEVENT SUMMARY:Fast neutron-induced fission cross section of $^{242}$Pu measured at nELBE and PIAF DTSTART:20220728T164000Z DTEND:20220728T170400Z DTSTAMP:20260420T153400Z UID:indico-contribution-833@indico.frib.msu.edu DESCRIPTION:Speakers: Ralf Nolte\, Andreas Wagner\, Arnd R. Junghans\, Han s F. R. Hoffmann\, Roland Beyer\, Toni Kogler\n\nPrecise neutron-induced fission cross-sections of actinides such as the plutonium isotopes are of relevance for the development of future transmutation technologies and 4$^ \\text{th}$ generation of nuclear reactors. In contrast to thermal reactor s\, these future technologies employ the fast-neutron spectrum. \n\nFor $^ {242}$Pu current uncertainties of the fission cross section in the energy region between 500 keV and 2.23 MeV are of about 19 %. Sensitivity studies [1\,2] show that the total uncertainty has to be reduced below 5 %\, to a llow for reliable neutron physics simulations. \n\nThis challenging task w as tackled at the neutron time-of-flight facility *n*ELBE of the Center f or High Power Radiation Sources at HZDR\, Dresden. A parallel-plate fissio n ionization chamber with novel\, homogeneous\, large-area $^{242}$Pu depo sits on Si-wafer backings was used to determine the $^{242}$Pu(n\,f) cross section relative to the IAEA neutron cross-section standard $^{235}$U(n\, f) in the energy range of 0.5 to 10.0 MeV. A systematic uncertainty below 2.7 % and an average statistical uncertainty of 4.9 % was reached [3]. The results show an agreement of better than 1 % as compared to recently publ ished data (e.g. [4] & [5]) and a good accordance to current evaluated dat a sets.\n\nIn the course of characterizing the actinide targets at the PIA F facility of PTB Braunschweig with 15 MeV DT-neutrons\, not only the area l density of the $^{235}$U fission chamber used as reference detector coul d be precisely determined\, but also a further data point for the $^{242}$ Pu(n\,f) cross section could be obtained. In contrast to the experiment at *n*ELBE\, PIAF provides an open neutron field where the whole housing of the chamber was irradiated by neutrons. Thus\, the scattering corrections at PIAF were of considerable importance. The effects on the incident neutr on fluence were corrected using Geant4-based particle transport calculatio ns.\n\nThis work was supported by the EURATOM FP7 project CHANDA and by th e German Federal Ministry of Education and Research (03NUK13A). \n\n[1] W orking Party on International Evaluation Co-Operation\, OECD / NEA\, The H igh Priority Request List for Nuclear Data (HPRL) (2011).\n[2] WPEC\, Unc ertainty and Target Accuracy Assessment for Innovative Systems Using Recen t Covariance Data Evaluations\, Tech. Rep. (Working Party on International Evaluation Co-Operation\, OECD / NEA\, 2008).\n[3] T. Kögler *et al*.\, Fast-neutron-induced fission cross section of $^{242}$Pu measured at the neutron time-of-flight facility *n*ELBE\, Phys. Rev. C **99**\, 02460 4 (2019).\n[4] F. Tovesson *et al.*\, Neutron induced fission of $^{240\, 242}$Pu from 1 eV to 200 MeV\, Phys. Rev. C **79**\, 014613 (2009).\n[5] P. Salvador-Castineira *et al*.\, Neutron-induced fission cross sections o f $^{242}$Pu from 0.3 MeV to 3 MeV\, Phys. Rev. C **92**\, 044606 (2015)\n \nhttps://indico.frib.msu.edu/event/52/contributions/833/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/833/ END:VEVENT BEGIN:VEVENT SUMMARY:Towards implementing new isotopes for environmental research: The half-life of $^{32}$Si DTSTART:20220725T184500Z DTEND:20220725T190900Z DTSTAMP:20260420T153400Z UID:indico-contribution-858@indico.frib.msu.edu DESCRIPTION:Speakers: Mario Veicht (Paul Scherrer Institut (PSI)\; École polytechnique fédérale de Lausanne (EPFL))\n\n$^{32}$Si is an extremely rare\, naturally occurring radioactive isotope. With its half-life ($\\tex tit{T}$$_{1/2}$) of approximately 150 years $^{32}$Si would be one of the suitable candidates for radiometric dating in the range of 100–1000 year s\, where an appropriate dating nuclide is still missing (Fig. 1a).\nThe f act that the application of this nuclide for dating has been very limited so far is due to the imprecise and contradictory data for its half-life (F ig. 1b). With the current best estimate of 153(19) years\, a more precise and more accurate determination is absolutely necessary.\n\n![Fig. 1: (a) Dating gap between 100 and 1000 years\, and (b) compilation of previous $^ {32}$Si half-life determinations (modified from (2))][1]\n\nThe SNSF-funde d project SINCHRON ($\\textbf{Si}$ – a $\\textbf{n}$ew $\\textbf{chro}$n ometer for $\\textbf{n}$uclear dating) aims for an accurate half-life rede termination of $^{32}$Si with a relative standard uncertainty of less than 5% on the basis of several independent measurements. MBq quantities of $^ {32}$Si have been successfully produced at the Paul Scherrer Institut (PSI \, Switzerland) by exposing metallic vanadium discs to high-energy protons . In order to obtain radiochemically pure $^{32}$Si solutions\, a robust c hemical separation procedure has been developed (2). Several partners are involved in the SINCHRON-Project covering different tasks of the half-life determination.\nGenerally\, two approaches are employed\, while all measu rements will be performed using aliquots of the same source material. The first approach is to follow the decay over a given time interval. For such measurements\, the long-term stability of both the sample and the measure ment device (e.g.\, ionization chamber (IC)) is essential. The second appr oach is the so-called direct method\, where the $\\textit{T}$$_{1/2}$ can be determined from the relationship $\\textit{T}$$_{1/2}$ = $\\mathit{N}$ $\\mathit{ln(2)}$/$\\mathit{A}$. Here\, inductively coupled plasma mass sp ectrometry (ICP-MS)\, and accelerator mass spectrometry (AMS) are utilized for the determination of the number of atoms ($\\mathit{N}$). The activit y ($\\mathit{A}$) is measured using liquid scintillation counting (LSC) wi th two techniques that are well established in radionuclide metrology: the triple-to-double coincidence ratio (TDCR) method and CIEMAT/NIST efficien cy tracing. In addition\, a coincidence setup with a plastic scintillation detector and a gamma-ray detector is used to apply another independent ef ficiency tracing technique. Finally\, enough sample material that meets th e quality requirements has been produced and the individual measurements a re currently ongoing - first\, preliminary results of the half-life determ ination will be presented.\n\n$\\textbf{References}$:\n(1) Ouellet\, C.\, and Balraj\, S. "Nuclear data sheets for A = 32" $\\textit{Nuclear Data Sh eets}$ 112.9 (2011): 2199-2355.\n\n(2) Veicht\, M.\, Mihalcea\, I.\, Cvjet inovic\, Đ.\, & Schumann\, D. (2021). "Radiochemical separation and purif ication of non-carrier-added silicon-32". Radiochimica Acta.$\\textit{Radi ochimica Acta}$ (2021\, pre-published online).\n\n\n$\\textbf{Acknowledgem ents}$:\nThe authors acknowledge the funding through the Swiss National Sc ience Foundation (Grant No. 177229) and additionally from the Marie Skłod owska-Curie Grant (No. 701647).\n\n[1]: https://indico.bnl.gov/event/9462/ abstracts/2554/attachments/219/Compilation%2BDatingGap_ND2022.pdf\n\nhttps ://indico.frib.msu.edu/event/52/contributions/858/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/858/ END:VEVENT BEGIN:VEVENT SUMMARY:Impact of uncertainties on non-LWR reactivity analysis with ENDF/B -VII.0\, ENDF/B-VII.1 and ENDF/B-VIII.0 DTSTART:20220727T144500Z DTEND:20220727T150900Z DTSTAMP:20260420T153400Z UID:indico-contribution-729@indico.frib.msu.edu DESCRIPTION:Speakers: Celik Cihangir (Oak Ridge National Laboratory)\, And rew Holcomb\, William Wieselquist (Oak Ridge National Laboratory)\, Friede rike Bostelmann (Oak Ridge National Laboratory)\n\nNon-light water reactor (non-LWR) concepts under development throughout the industry are signific antly different from traditional LWR designs with respect to geometry\, ma terials\, and operating conditions. These differences result in significan t differences with respect to the reactor physics behavior of non-LWRs as compared to LWRs. Given the limited operating experience with non-LWRs\, t he accurate simulation of reactor physics and the quantification of associ ated uncertainties are important for ensuring that the nuclear design for advanced reactor concepts include appropriate margins. Nuclear data are a major source of input uncertainties in reactor physics analysis. \n\nAs pa rt of a project sponsored by the US Nuclear Regulatory Commission\, the im pact of nuclear data uncertainties for reactor physics analysis was quanti fied based on sensitivity and uncertainty analyses performed for six selec ted benchmarks: a graphite moderated high temperature gas-cooled reactor ( HTGR)\, a fluoride salt-cooled high temperature reactor (FHR)\, a graphite -moderated molten salt reactor (MSR)\, a fast-spectrum heat pipe reactor ( HPR)\, and a sodium-cooled fast reactor (SFR). For these benchmarks\, comp arisons of uncertainties were performed for several safety-relevant reacti vity effects using the latest three Evaluated Nuclear Data File (ENDF)/B l ibrary releases: ENDF/B-VII.0\, ENDF/B-VII.1\, and ENDF/B-VIII.0. The anal ysis of the top contributing nuclide reactions to the observed uncertainti es was used to identify the causes of the different magnitudes of observed output uncertainties. \n\nIn addition to nuclear data uncertainties that are often found relevant in LWR uncertainty analysis (e.g.\, $^{235}$U neu tron multiplicity\, $^{235}$U and $^{238}$U neutron capture)\, several la rge cross section uncertainties that are not commonly found to be relevant in LWR studies were found to be significant for several non-LWR systems. In particular\, three nuclide reactions stood out: (1) The uncertainty of $^{238}$U inelastic scattering in the fast energy range contributes signif icantly to large reactivity uncertainties of the control rod worth in reac tor designs with fast neutron spectrum. For the studied HPR and the SFR\, large uncertainties of the multiplication factor\, control rod worth\, rea ctivity changes from grid expansion and fuel temperature increase are caus ed by this reaction. (2) The uncertainty of $^{235}$U (n\,$\\gamma$) in th e fast energy range causes significant reactivity uncertainties in fast ne utron spectrum systems that use $^{235}$U-enriched fuel. In the studied $^ {235}$U-enriched HPR and SFR\, this reaction causes large uncertainties of the multiplication factor\, the control rod worth\, and the reactivity ch anges from fuel temperature and coolant density increase\, grid radial exp ansion\, and fuel axial expansion. (3) The uncertainty of $^7$Li (n\,$\\ga mma$) causes a large fraction of uncertainty in the reactivities investiga ted for MSR systems in which lithium is part of the salt. In the studied M SR and the FHR\, this reaction causes large uncertainties of the multiplic ation factor and reactivity changes from fuel temperature and salt density increase.\n\nSpecial attention should be paid to differences in cross sec tion and uncertainties of different evaluated nuclear data library release s. Significant differences were found in nuclear data that can lead to maj or differences in reactivity calculations\, even for well-known nuclides. In particular\, differences in $^{235}$U\, $^{238}$U\, and $^{239}$Pu nomi nal and uncertainty data between the ENDF/B-VII.1 and ENDF/B-VIII.0 nuclea r data releases are the major causes of differences in calculations when u sing these libraries.\n\nA significant gap for the performed uncertainty a nalyses of the selected moderated systems was identified in terms of the u navailability of uncertainty for graphite and FLiBe thermal scattering dat a. For the analysis of fast spectrum systems\, the unavailability of angul ar scattering data uncertainties was noted. \n\nThe presentation will cove r an overview of the major outcome of the performed uncertainty analyses. Major differences between analyses with the different ENDF/B nuclear data libraries will be highlighted\, and the magnitude of reactivity uncertaint ies including their major contributors will be discussed. Uncertainty anal yses as presented in this work\, in particular the ranking of contribution s to the output uncertainties\, can guide future measurement and evaluatio n efforts to reduce the identified large uncertainties. Reduced nuclear da ta uncertainties will contribute to the improved prediction of key figures of merit for reactor safety.\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/729/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/729/ END:VEVENT BEGIN:VEVENT SUMMARY:The Calculation and Comparing of Benchmark Models with ENDF/B-VIII .0 and CENDL-3.2 Fe-56 Nuclear Data DTSTART:20220727T172300Z DTEND:20220727T172400Z DTSTAMP:20260420T153400Z UID:indico-contribution-1145@indico.frib.msu.edu DESCRIPTION:Speakers: 晓波 刘 (核物理与化学研究所)\, 博 史 ( 中国工程物理研究院研究生院)\n\nIn order to compare the ENDF/B -VIII.0 and CENDL-3.2 Fe-56 nuclear data\, 28 iron sensitive models were s elected from the International Criticality Safety Benchmarking Experiments Evaluation Program. There are 21 highly enriched models and 7 plutonium m ental models. The benchmark models were modeled in MC program and k_{eff} calculated with ENDF/B-VIII.0\, with a hybrid ENDF/B-VIII.0 with CENDL-3.2 substituted for Fe-56. The calculated result with complete ENBF/B-VIII.0 and hybrid ENDF/B-VIII.0 shows that the ENDF/B-VIII.0 Fe-56 nuclear data i s better in highly enriched models and the CENDL-3.2 Fe-56 nuclear data is better in plutonium mental models.\n\nhttps://indico.frib.msu.edu/event/5 2/contributions/1145/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1145/ END:VEVENT BEGIN:VEVENT SUMMARY:First high-resolution $^{80}$Se(n\,$\\gamma$) cross section measur ement between 1 eV and 100 keV and its astrophysical implications for the $s$-process DTSTART:20220726T130000Z DTEND:20220726T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-778@indico.frib.msu.edu DESCRIPTION:Speakers: César Domingo Pardo\, Javier Balibrea-Correa\, Jorg e Lerendegui-Marco\, Ion Ladarescu\, Luis Caballero\, n_TOF collaboration\ , Victor Babiano-Suarez\n\nThe slow neutron capture ($s$-) process is resp onsible for the formation of half of the elements heavier than iron in the Universe. Despite the long time scale of this process\, the long half-lif e of some isotopes throughout the $s$-process reaction flow creates branch ing points that lead to the division of the nucleosynthesis path. ${79}$Se ($t_{1/2} = 3.27 \\times 10^5$ y [1]) represents one of the most relevant and debated s-branching nuclei [2] for two main reasons. On the one hand\ , the existence of quantum states in ${79}$Se\, whose population varies wi th temperature\, makes the s-process path sensitive to temperature. On the other hand\, the observed abundances of the s-only isotopes of krypton ($ {80\,82}$Kr) are very well-known from meteoric data. Thus\, by comparing t hese abundances with those predicted by stellar models\, information about the thermal conditions of the stellar media in which the $s$-process occu rs can be obtained. To this aim hydrodynamic stellar models need experimen tal data on the neutron capture cross section of all isotopes involved in the branching.\nIn this context\, we have measured the neutron capture cro ss section of ${80}$Se at CERN n_TOF\, with very high energy resolution fo r the first time [3]. Although there is a previous measurement on of ${80} $Se(n\,$\\gamma$) [4]\, it suffers from a very limited energy resolution a nd a short neutron-energy range\, as it can be appreciated in Fig. 1. Thes e drawbacks have been remarkably improved in this time-of-flight measureme nt that covers the entire energy range of astrophysical interest between 1 eV and 100 keV. One hundred and thirteen resonances have been characteriz ed\, ninety-eight of them for the first time. The impact is sizable\, bein g the MACS at kT = 8 keV 36\\% smaller than the recommended value in KADoN iS [5]. In this work we present final results together with a discussion o f their astrophysical implications.\n\n[1] G. Jörg et al.\, Applied Radia tion and Isotopes\, 68(12):2339–2351\, 2010.\n[2] F. Kappeler et al.\, R eports on Progress in Physics\, 52(8):945–1013\, August 1989.\n[3] V. Ba biano-Suárez et al.\, CERN-INTC-2018-005\, INTC-P-536\, 2018.\n[4] G. Wal ter et al.\, Astron. Astrophysic\, 167:186-199\, 1986.\n[5] I. Dillmann et al.\, Nuclear Data Sheets\, 120:171–174\, 2014.\n\nhttps://indico.frib. msu.edu/event/52/contributions/778/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/778/ END:VEVENT BEGIN:VEVENT SUMMARY:The $^{35}$Cl(n\,p)$^{35}$S cross section measured at n_TOF-CERN f acility DTSTART:20220727T183600Z DTEND:20220727T184800Z DTSTAMP:20260420T153400Z UID:indico-contribution-811@indico.frib.msu.edu DESCRIPTION:Speakers: Javier Praena\, Ignacio Porras\, Hamza Amar\n\nWe pr esent the results of the $^{35}$Cl(n\,p)$^{35}$S cross section measurement using $^{10}$B(n\,α)$^{7}$Li as reference at the n_TOF Experimental Area 2 (EAR-2) facility at CERN\, providing data below 100 keV. On the one han d\, this reaction is of interest in astrophysics as it is involved in the production of $^{36}$S\, whose astrophysical origin remains unresolved [1] \, as well as the observed deviation from the solar $^{35}$Cl/$^{37}$Cl ra tio in observations in carbon-rich AGB stars is matter of debate [2]. On t he other hand\, $^{35}$Cl is being also studied in medical physics. In Bor on Neutron Capture Therapy (BNCT)\, $^{35}$Cl(n\,p)$^{35}$S reaction is qu ite important because of their crucial contribution to the dose in healthy brain tissue [3\,4]\, where the concentration of Cl is higher than in the rest of the body.\n\nhttps://indico.frib.msu.edu/event/52/contributions/8 11/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/811/ END:VEVENT BEGIN:VEVENT SUMMARY:Zr Nuclear Data Campaign: Measurement of (n\,$\\gamma$) cross sect ion of Zr-90 DTSTART:20220728T171600Z DTEND:20220728T172800Z DTSTAMP:20260420T153400Z UID:indico-contribution-835@indico.frib.msu.edu DESCRIPTION:Speakers: Klaus Guber\, Jesse Brown (ORNL)\, Peter Schillebeec kx\, Stefan Kopecky\, Carlos Paradela Dobarro\n\nhttps://indico.frib.msu.e du/event/52/contributions/835/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/835/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of double-differential neutron yields for iron\, lead\ , and bismuth induced by 107-MeV protons for research and development of a ccelerator-driven systems DTSTART:20220728T194200Z DTEND:20220728T195400Z DTSTAMP:20260420T153400Z UID:indico-contribution-848@indico.frib.msu.edu DESCRIPTION:Speakers: Kazuaki Tsukada\, Yasutoshi Kuriyama\, Yoshihiro Ish i\, Kota Okabe\, Riccardo Orlandi\, Heita Nakano\, Yoshiharu Mori\, Fumi S uzaki\, Yosuke Iwamoto\, Katsuhisa Nishio\, Akito Oizumi\, Kentaro Hirose\ , Daiki Satoh\, Tomonori Uesugi\, Hiroshi Yashima\, Fujio Maekawa\, Shin-i chiro Meigo\, Yiroyuki Makii\, Hiroki Iwamoto\n\nFor accurate prediction o f neutronic characteristics for accelerator-driven systems (ADS) and a sou rce term of spallation neutrons for reactor physics experiments for the AD S at Kyoto University Critical Assembly (KUCA) [1]\, we have launched an e xperimental program to measure nuclear data on ADS using the Fixed Field A lternating Gradient (FFAG) accelerator at Kyoto University. As part of thi s program\, the proton-induced double-differential thick-target neutron-yi elds (TTNYs) and cross-sections (DDXs) for iron\, lead\, and bismuth have been measured with the time-of-flight (TOF) method.\n\nFor each measuremen t\, the target was installed in a vacuum chamber on the beamline and bomba rded with 107-MeV proton beams accelerated from the FFAG accelerator. Neut rons produced from the targets were detected with stacked\, small-sized ne utron detectors composed of the NE213 liquid organic scintillators and pho tomultiplier tubes\, which were connected to a multi-channel digitizer mou nted with a field-programmable gate array (FPGA)\, for several angles from the incident beam direction. The TOF spectra were obtained from the detec ted signals and the FFAG kicker magnet’s logic signals\, where gamma-ray events were eliminated by pulse shape discrimination applying the gate in tegration method to the FPGA. Finally\, the TTNYs and DDXs were obtained f rom the TOF spectra by relativistic kinematics.\n\nThe measured TTNYs and DDXs were compared with calculations by the Monte Carlo transport code PHI TS [2] with its default physics model of INCL version 4.6 [3] combined wit h GEM [4] (INCL4.6/GEM) and those with the JENDL-4.0/HE nuclear data libra ry [5]. Details of the TTNY and DDX measurements for the iron\, lead and b ismuth targets and their experimental results will be presented.\n\n**Refe rences**\n[1] C.H. Pyeon\, et al.\, Ann Nucl Energy. 2020\; 144: 107498.\n [2] T. Sato\, et al.\, J Nucl Sci Technol. 2018\; 55: 529–533.\n[3] A. B oudard\, et al.\, Phys Rev C. 2013\; 87: 014606.\n[4] S. Furihata\, Nucl I nstrum Meth B. 2000\; 171: 251–258.\n[5] S. Kunieda\, et al.\, In Procee dings of the 2015 symposium on Nuclear Data\; 2015 Nov 19–20\; Tokai (Ja pan): Ibaraki Quantum Beam Research Center\; 2016.\n\n**Acknowledgement**\ nThis work was supported by MEXT Innovative Nuclear Research and Developme nt Program Grant Number JPMXD0219214562.\n\nhttps://indico.frib.msu.edu/ev ent/52/contributions/848/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/848/ END:VEVENT BEGIN:VEVENT SUMMARY:FLUKAVAL - A validation framework for the FLUKA radiation transpor t Monte Carlo Code DTSTART:20220727T163600Z DTEND:20220727T163900Z DTSTAMP:20260420T153400Z UID:indico-contribution-1120@indico.frib.msu.edu DESCRIPTION:Speakers: Markus Widorski\n\nThe [FLUKA](https://fluka.cern) g eneral purpose radiation transport Monte Carlo code being developed and ma intained by CERN has adopted modern software development standards includi ng a formal quality assurance process. This includes the FLUKAVAL testing framework that takes into account the specific needs of testing a Monte Ca rlo radiation transport simulation code.\n\nFLUKAVAL is a Python-based com mand line application that enables semi-automatic batch submission\, proce ssing\, validation and reporting of test cases. Any FLUKA input and any de dicated tests having access to the FLUKA code at the model level can be ad apted and integrated in a few steps into the test framework. FLUKAVAL make s extensive use of the git version control system to store simulation and reference data sets on the CERN GitLab instance. In its current version\, FLUKAVAL is optimised for the submission of a large number of test cases t o the CERN Batch Service (LXBATCH)\, which provides distributed computing power with over 220'000 CPU cores.\n\nFLUKA output data are stored in the standardised JSON format\, which is compatible with the Geant Validation P ortal\, to simplify future direct comparisons of identical test cases with Geant4.\n\nThe results are processed\, validated and compiled in a compre hensive evaluated report\, which allows the direct comparison of results f rom the FLUKA version under validation with results obtained with previous FLUKA versions\, other radiation transport codes and/or experimental data . A quantitative analysis is performed in addition to a qualitative compar ison whenever possible. \n\nWe will demonstrate on real examples how refer ence benchmark data and output from simulation calculations are analysed a nd compiled\, and how this can be extended to a large amount of test cases . The focus will be on the capabilities of the FLUKAVAL framework with res pect to cross-section data for nuclear reactions.\n\nhttps://indico.frib.m su.edu/event/52/contributions/1120/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1120/ END:VEVENT BEGIN:VEVENT SUMMARY:Towards an ENDF/B-VIII.0-Based Processed Covariance Library at LAN L DTSTART:20220727T150900Z DTEND:20220727T152100Z DTSTAMP:20260420T153400Z UID:indico-contribution-730@indico.frib.msu.edu DESCRIPTION:Speakers: Kent Parsons\, Alexander Clark (LANL)\, Denise Neude cker\, Nathan Gibson\n\nIn the last few decades\, the field of nuclear dat a has been increasingly more diligent in the generation and use of uncerta inty information related to nuclear data. This increased interest is fuele d by the more wide-spread request for characterization of uncertainties\, perhaps for quantifying performance margins or for identifying the best us e of experimental resources. Use cases range\, for instance\, from setting criticality safety limits [1]\, to nuclear data validation [2]\, to estim ating uncertainties on performance of reactor systems [3]. However\, desp ite these needs\, processed covariances are not readily available for use in LANL’s application codes such as MCNP. As the covariance user commun ity continues to expand\, we must deliver a general purpose processed cova riance data library in a similar manner to the widely available continuous energy ACE libraries or internally available multigroup libraries\, rathe r than continuing to rely on ad-hoc processing on an as-needed basis. Thu s\, an effort is now underway to create such a covariance library or serie s of libraries based on ENDF/B-VIII.0 covariances.\n \nThe creation of thi s library is not as simple as executing the processing code NJOY [4]. The re are known deficiencies in evaluated covariance data\, undesirable effec ts of processing\, and difficulties in interpretation of the data. Furthe rmore\, there are challenges in validation and verification\, as there is no internal library to use as a baseline (although external libraries do e xist) and there is no widely accepted validation test suite. Finally\, th e very concept of a general-purpose covariance library is difficult\, due to the limited set of experimental data used in covariance evaluation.\n \ nThese challenges have motivated the development of covariance testing too ls to be integrated into a formal testing suite. The tests include mathem atical checks (e.g.\, positive definiteness)\, physics checks (e.g.\, comp aring to experimental uncertainty templates [5])\, and “gut-check” val idation results on critical benchmarks. Both via this test suite and thro ughout the processing workflow\, deficiencies in both evaluated covariance s and the processing tools have been identified\, and an approach to corre cting these deficiencies is suggested. Lastly\, this work includes consid erations regarding the delivery of the data\, including a usable and moder n format and documentation/communication.\n\nReferences\n1. Brian C. Kiedr owski\, Forrest B. Brown\, Jeremy L. Conlin\, Jeffrey A. Favorite\, Albert C. Kahler\, Alyssa R. Kersting\, D. Kent Parsons & Jessie L. Walker\, Whi sper: Sensitivity/Uncertainty-Based Computational Methods and Software for Determining Baseline Upper Subcritical Limits\, Nuclear Science and Engin eering\, 181:1\, 17-47\, (2015). \n2. D. Neudecker\, M. Grosskopf\, M. Her man\, W. Haeck\, P. Grechanuk\, S. Vander Wiel\, M.E. Rising\, A.C. Kahler \, N. Sly\, P. Talou\, Enhancing nuclear data validation analysis by using machine learning\, Nuclear Data Sheets\, 167\, 36-60\, (2020).\n3. Alexan der Aures\, Wolfgang Bernnat\, Friederike Bostelmann\, Jérémy Bousquet\, Bernard Krzykacz-Hausmann\, Andreas Pautz\, Kiril Velkov\, Winfried Zwerm ann\, Reactor simulations with nuclear data uncertainties\, Nuclear Engine ering and Design\, 355\, 110313\, (2019).\n4. Macfarlane\, Robert\, Muir\, Douglas W.\, Boicourt\, R. M.\, Kahler\, III\, Albert Comstock\, & Conlin \, Jeremy Lloyd\, The NJOY Nuclear Data Processing System\, Version 2016. https://doi.org/10.2172/1338791 \n5. Neudecker\, Denise\, Hejnal\, Brooke Ellen\, Tovesson\, Fredrik\, White\, Morgan Curtis\, Smith\, Donald L.\, V aughan\, Diane Elizabeth\, & Capote\, R.\, Template for estimating uncerta inties of measured neutron-induced fission cross-sections\, EPJ Nuclear Sc iences and Technologies\, 4\, 21\, (2018).\n\nLA-UR-21-29495\n\nhttps://in dico.frib.msu.edu/event/52/contributions/730/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/730/ END:VEVENT BEGIN:VEVENT SUMMARY:Uncertainty Considerations that Impact the Use of Dosimetry Metric s in Modern Semiconductors DTSTART:20220727T153300Z DTEND:20220727T154500Z DTSTAMP:20260420T153400Z UID:indico-contribution-752@indico.frib.msu.edu DESCRIPTION:Speakers: Patrick Griffin\n\nSilicon provides a good exemplar for a consideration of the critical parameters that affect the uncertainty for neutron dosimetry metrics\, e.g.\, total kerma\, ionizing kerma\, dis placement damage energy. In addition to the energy-dependent cross section uncertainty found in the ENDF-6 formatted nuclear data files\, one must a lso address uncertainty due to: a) models used\, e.g.\, modeling of the re coil ion energy from the capture gamma reaction\; b) the damage partition function that is used to divide the deposited energy into ionization and d isplacement components\, e.g.\, the Robinson partition function\; c) recoi l ion stopping power\; d) treatment of the displacement threshold region f or some damage metrics\, e.g.\, the Kinchin-Pease dpa [1]\; e) treatment o f the angle-dependence of the lattice atom displacement when examining the creation of Frenkel pairs. Work with silicon [2] clearly established the critical importance of considering cross-reaction correlations. Analysis [ 3] has also addressed the effect of correlations between nuclear data eval uations for different isotopes in the naturally occurring elements. When w e go from Si to other modern semiconductor materials\, like GaAs\, GaN\, a nd SiGe\, we also need to address the uncertainty due to: a) the treatment of the polyatomic lattice atoms within the damage partition function [4]\ ; b) use of damage metrics that show an additional dependence upon the ene rgy of the recoil atom [5]\, e.g.\, the arcdpa efficiency [6] which exhibi ts an energy-dependent uncertainty that has uncertainty contributions from the model-based functional form uncertainty as well as from the model- or experiment-based data calibration\; c) the correlation between the calcul ated damage metric and the useful experimental metrics\, e.g.\, use of dpa or the number of Frenkel pairs created as a metric for the minority carri er recombination lifetime [7]. In some cases the use of modified damage me trics\, e.g.\, 1-MeV(Si)-Eqv. Fluence\, can reduce the overall uncertainty by looking at damage ratios and removing some of systematic uncertainty t erms. \nThis paper starts with a summary of the status of our uncertaint y quantification in silicon semiconductors and then extends the discussion to ongoing work with GaAs and GaN semiconductors. We then address emergin g issues that are associated with SiGe and small feature-sizes (<5 nm) sem iconductors found in FinFET and gate-all-around (GAA) devices. \n[1] M. Robinson\, O. Oen\, “On the Use of Thresholds in Damage Energy Calculati ons\,” Journal of Nuclear Materials\, Vol. 110\, pp. 147-149\, 1982. \n[ 2] P. Griffin\, “Uncertainty Characterization of Silicon Damage Metrics\ ,” IEEE Trans. On Nuclear Science\, Vol. 66\, No. 1\, pp. 327-336\, Jan. 2019. http://dx.doi.org/10.1109/TNS.2018.2876058\n[3] J.-Ch. Sublet\, et al.\, “Neutron-induced damage simulations: Beyond defect production cros s-section\, displacement per atom and iron-based metrics\,” Eur. Phys. J . Plus\, Vol. 134\, 350 (2019). https://doi.org/10.1140/epjp/i2019-12758-y \n[4] C. Coulter\, D.M. Parkin\, “Damage Energy Functions in Polyatomic materials\, Journal of Nuclear Materials\, Vol.88\, pp. 249-260\, 1980.\n[ 5] P. Griffin\, et al.\, “Neutron Damage Equivalence in GaAs”\, IEEE T rans. On Nuclear Science\, Vol. 38\, No. 6\, pp. 1216-1224\, December 1991 . \n[6] K. Nordlund\, et al.\, “Improving atomic displacement and replac ement calculations with physically realistic damage models\,” Nature Com munications\,9\, 1084 (2018). https://doi.org/10.1038/s41467-018-03415-5\n [7] G. C. Messenger\, M. A. Ash\, The Effects of Radiation on Electronic S ystems\, Van Nostrand Reinhold Company\, 1986. \n*This work was supported in part by the U.S. Department of Energy under contract DE-NA0003525. Sand ia National Laboratories is a multi-mission laboratory managed and operate d by National Technology and Engineering Solutions of Sandia\, LLC\, a who lly owned subsidiary of Honeywell International\, Inc.\, for the U.S. Depa rtment of Energy's National Nuclear Security Administration under contract DE-NA0003525.\n\nThe views expressed in the paper do not necessarily repr esent the views of the U.S. Department of Energy or the United States Gove rnment.\n\nhttps://indico.frib.msu.edu/event/52/contributions/752/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/752/ END:VEVENT BEGIN:VEVENT SUMMARY:A Graph Theory Approach to the GNDS Schema Definition DTSTART:20220727T190000Z DTEND:20220727T191200Z DTSTAMP:20260420T153400Z UID:indico-contribution-877@indico.frib.msu.edu DESCRIPTION:Speakers: David Brown\, Bret Beck\, Caleb Mattoon (Lawrence Li vermore National Laboratory)\, Godfree Gert\n\nThe Generalized Nuclear Dat a Structure (GNDS) is the new international standard for the dissemination of nuclear reaction data. The GNDS structure is defined in a set of JSON files which allow for its implementation as follows:\n- a written report ( illustrated in Figure 1) which supplements the GNDS description with examp les\; and\n- post-processing of the JSON files to alternate formats\, e.g. \no to XSD to validate the GNDS output generated with the FUDGE processing code\;\no mapping to object-oriented programming language data types to s treamline the implementation of GNDS in processing codes or APIs that prov ide the interface to nuclear reaction data in GNDS format. \n\n\nFigure 1: GNDS Build System\nThis talk focusses on the modernization of the current GNDS build system (see Figure 1) that consists of an infrastructure that converts the JSON files to latex files which are combined with static late x input for the report wording and GNDS examples\, to generate the GNDS Sp ecification report in PDF format.\n\nThe existing GNDS build system uses P ython scripts to populate a custom-made object-oriented computational mode l of the GNDS specification. This model is both flexible (since its hierar chical structure is defined by the JSON input) and rigid (since it is hard coded to JSON input that adhere to a specific convention and its output i s restricted to the GNDS Specification Report in PDF format). The JSON use r community is however converging on a JSON specification that does not ne cessarily conform to the convention expected in the GNDS build system and there is an increasing need to expand the build-system output beyond the P DF format.\n\nA graph theory based directed acyclic graph (DAG) approach t o the GNDS schema definition is consequently being evaluated. The hierarch ical nature of the GNDS schema makes this representation a natural choice with a one-to-one mapping between the GNDS and DAG nodes. This approach is independent to the file format used for the GNDS schema definition and pr ovides a standardized internal computational representation that can easil y be converted to an output format for use in downstream applications.\n\n The DAG implementation in the NetworkX Python Package is used in this eval uation with the individual namespaces in the GNDS schema modeled as separa te DAGs. Methods are being developed to \n- read the current JSON implemen tation of the GNDS schema definition\;\n- convert the individual GNDS name spaces to separate DAGs\; and\n- generate XSD output for validating the GN DS 2.0 implementation in the FUDGE processing code.\n \nThis approach will replace the current GNDS schema definition processing (not the JSON input ) and opens new opportunities such as the automatic validation of new GNDS schema proposals\, and the generation of interactive visual representatio n of the GNDS schema definition. Examples in this approach that leans itse lf to automatic validation of the GNDS schema definition include NetworkX methods to find cycles in the tree representation\, identifying isolated n odes (i.e.\, nodes with degree 0)\, inconsistent naming of the same node ( e.g.\, due to typographical errors)\, multiple definition of nodes\, etc. \n\nThe initial implementation showed promising results for the documentat ion namespace and the planned future work include:\n- expanding the graph theory representation to the remaining GNDS namespaces\;\n- a collapsible tree representation in HTML\;\n- generating a GNDS specification report in both PDF and HTML\; and\n- generating a description of the GNDS schema in a JSON format that conforms to the new JSON schema.\n\nIt is further anti cipated that it will be easier to map object-oriented programming datatype s to the graph theory model of the GNDS schema than mapping to JSON files. \n\n\nThis work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-0 7NA27344.\nLLNL-ABS-827367\n\nhttps://indico.frib.msu.edu/event/52/contrib utions/877/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/877/ END:VEVENT BEGIN:VEVENT SUMMARY:Overview of NNDC Web Services 2020-21 DTSTART:20220726T141200Z DTEND:20220726T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-870@indico.frib.msu.edu DESCRIPTION:Speakers: Benjamin Shu\n\nThe National Nuclear Data Center (NN DC) provides access to physics research data through a collection of 40 we bsites. Each is dedicated to a topic\, a database\, or to a previous confe rence. Many also have long histories\, with the oldest websites having bee n deployed in 1998. Collectively\, these websites receive millions of requ ests for data\, with an estimated 5.2 million retrievals in 2020 alone. Th e popularity of the NNDC’s most prominent websites can attest to both it s reach and its impact.\n\nThe Evaluated Nuclear Structure Data File (ENSD F) format has its own dedicated database and a website of the same name. T he ENSDF website provides evaluated research data on excitation states for all known nuclides\, in addition to data on nuclear reactions and decay. In 2020\, the ENSDF website received its own chart interface to enable vis ual exploration of the ENSDF database.\n\nENSDF is the second most-visited website after NuDat\, which maintains the original Chart of Nuclides. Thi s interface visualizes patterns in half-lives\, decay energies\, fission y ields\, and more by mapping each nuclide onto a coordinate grid. In additi on to the Chart of Nuclides\, NuDat provides several plotting tools\, all of which received updates in 2019. Of particular note is the Advanced Cros s-Variable Plot\, which graphs relationships between observable nuclear pr operties. In 2021\, the NuDat 3.0 beta was released as a preview of a fast er\, smoother Chart of Nuclides.\n\nTo address the needs of specific users \, the NNDC website also provides tools which query and visualize subsets of the main libraries for specific applications. The Medical Isotope Radia tion Dose (MIRD) format is designed for isotopes used in nuclear medicine\ , and has its own dedicated website. The process of thermal neutron captur e decay is also recorded in the CapGam website. In 2020\, the MIRD website was updated to improve response times and add nuclear decay diagrams. Sho rtly afterwards\, CapGam was redesigned with responsive user interfaces an d a streamlined update process to keep up with new evaluations.\n\nMore re cently\, the NNDC has turned its attention towards modernizing its web ser vices. Over time\, the differences in each website’s creation and purpos e have complicated updating code and correcting programming errors. The NN DC’s most recent web development project was started to create a standar dized development process for present and future NNDC websites. It started with using Git version control for organizing and managing changes to cod e. It then progressed to using the Gradle build tool to make updates simpl er and faster. The final (and still ongoing) step in this project is to re -deploy each website as a portable Web Archive (WAR) file. Each of these s teps was taken with the intent of streamlining NNDC web development\, whic h in turn will hopefully improve existing websites and guide the creation of new ones.\n\nWork sponsored by the Office of Nuclear Physics\, Office o f Science of the U.S. Department of Energy\, under Contract No. DE-AC02-98 CH10886.\n\nhttps://indico.frib.msu.edu/event/52/contributions/870/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/870/ END:VEVENT BEGIN:VEVENT SUMMARY:Updates to the evaluation of neutron induced reactions on $^{56}$F e target DTSTART:20220726T181500Z DTEND:20220726T183900Z DTSTAMP:20260420T153400Z UID:indico-contribution-895@indico.frib.msu.edu DESCRIPTION:Speakers: Caleb M Mattoon\, Roberto Capote\, Andrej Trkov (Jo zef Stefan Institute)\n\nIron is an important structural and shielding mat erial that appears in many applications. Nuclear reaction data of iron hav e been addressed within the Subgroup-40 (CIELO) of the OECD/NEA Data Bank [1]. The resulting evaluated data files from the BNL/IAEA collaboration fo r the iron isotopes [2] were included in the ENDF/B-VIII.0 library [3] and performed well in criticality benchmarks. Unfortunately\, inadequate perf ormance of the $^{56}$Fe evaluation was discovered for shielding benchmark s just before the release of the ENDF/B-VIII.0 library: the leakage spectr a from very thick iron shells with a $^{252}$Cf source in the centre were significantly under-predicted in the energy range 1-8 MeV.\nAdditional ana lysis was performed which showed that the root cause of the problem was th e non-elastic cross section\, which seemed to be too high. This hypothesis was in contradiction with the new measurement of the inelastic cross sect ion by Beyer et al [4] but was partially confirmed by a new measurement of the elastic cross section [5]. A compromise between the measured elastic and the inelastic cross section was sought such that unitarity with the to tal cross section was preserved. In addition\, the elastic cross section w as increased in the resonance interference minima (being the largest incre ase around 300 keV). The increase was guided by the measured leakage spect ra from thick iron shells with a $^{252}$Cf source in the centre to elimin ate the observed overestimation by 30% of the measured neutron leakage aro und 300 keV. Some of the improvements were already presented orally at var ious meetings\, but no formal report or publication has been released.\nTh ere was also a question of the thermal capture cross section. R. Firestone [6] published the results from prompt-gamma activation analysis\, which s uggested lowering of the thermal capture cross section by 7%. Validation m easurements at CEA within the MAESTRO project [7] did not support such a d ecrease [8]. The same validation showed that JEFF evaluation was essential ly correct\, so the recommended value of the thermal capture cross section for $^{56}$Fe of 2.577 barns was adopted. This value is also in agreement with latest Firestone evaluation [8].\nThe resulting evaluated data files were extensively tested. The previously observed deficiency of under-pred icting the fast-neutron leakage spectra from thick iron shells with a $^{2 52}$Cf source was avoided. The 30% overestimation of the neutron leakage a round 300 keV was also eliminated. Similar benchmark experiments with a D- T source also showed an improvement. In a benchmark involving 40 MeV neutr ons the new evaluation performed much better than the ENDF/B-VII.1 library . At the same time\, performance in criticality benchmarks was not comprom ised.\nThe benchmarking exercise illustrates how integral benchmarks can b e used to discriminate between discrepant differential data to produce eva luated data files that perform well in situations that are critical for th e safe operation of nuclear installations. Details of the changes to the d ifferential data will be given and selected representative benchmark resul ts will be presented.\n\nReferences\n[1] M.B. Chadwick et al.: “CIELO C ollaboration Summary Results: International Evaluations of Neutron Reactio ns on Uranium\, Plutonium\, Iron\, Oxygen and Hydrogen”\, Nuclear Data S heets 148 (2018) 189–213.\n[2] M.W. Herman et al: “Evaluation of Neut ron Reactions on Iron Isotopes for CIELO and ENDF/B-VIII.0”\, Nuclear Da ta Sheets 148 (2018) 214–253.\n[3] D.A. Brown et al.: “ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-proj ect Cross Sections\, New Standards and Thermal Scattering Data”\, Nuclea r Data Sheets 148 (2018) 1–142.\n[4] R. Beyer et al.: “Inelastic scatt ering of fast neutrons from 56Fe”\, EPJ Web of Conferences 146\, 02017 ( 2017).\n[5] E. Pirovano et al.: “Cross section and neutron angular distr ibution measurements of neutron scattering on natural iron”\, Physical R eview C 99\, 024601 (2019)\n[6] R.B. Firestone et al.: “Thermal neutron capture cross section for 56Fe(n\,γ )”\, Physical Review C 95\, 014328 (2017).\n[7] P. Leconte\, “Nuclear data feedback on structural\, moderat ing and absorbing materials through the MAESTRO experimental programme in MINERVE\,” Tech. Rep. JEF/DOC-1849\, Nuclear Energy Agency\, OECD\, Pari s\, France (2017).\n[8] R.B. Firestone\, private communication\, to be pub lished (2020).\n\nhttps://indico.frib.msu.edu/event/52/contributions/895/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/895/ END:VEVENT BEGIN:VEVENT SUMMARY:Response of nuclear physics detectors to laser-driven neutrons at the PW DRACO laser facility DTSTART:20220726T185100Z DTEND:20220726T190300Z DTSTAMP:20260420T153400Z UID:indico-contribution-734@indico.frib.msu.edu DESCRIPTION:Speakers: María de los Ángeles Millán Callado (Centro Nacio nal de Aceleradores (CNA\, US - Junta de Andalucía - CSIC) - Universidad de Sevilla (US)\, Dpt. Física Atómica\, Molecular y Nuclear (FAMN))\n\nP ulsed neutron beams are a valuable tool in nuclear physics\, but their app lications are strongly restricted by the limited number of neutron sources available worldwide [1]. These neutron beams\, suitable for "time of flig ht" (TOF) experiments\, can be characterized by their time resolution\, th e intensity per pulse\, and the frequency or repetition rate.\n\nIn terms of neutron production\, laser-driven ion sources are garnering the interes t of the nuclear physics community due to the fast development of ultra-sh ort (fs) and ultra-high power (> $10^{19}$ W/cm$^2$) lasers and their use as compact particle accelerators [2]. Neutrons produced using this alterna tive method can reach higher instantaneous neutron fluxes than conventiona l neutron sources [3-4]. Nevertheless\, the potential use of these neutron s in nuclear physics applications relies on the behavior of nuclear physic s detectors\, which is still not characterized for the peculiarities of th e harsh environment produced in a laser facility. \n\nThis work presents t he results of a multiple detectors’ experimental campaign performed at t he PW-class DRACO laser system at HZDR [5] during fall 2021. During this c ampaign\, different detectors employed in conventional nuclear physics exp eriments were tested under a laser-driven neutron source. This set include d lithium detectors for thermal and epithermal neutron detection\, organic liquid and solid detectors for fast neutrons\, diamond and silicon detect ors for charged particles\, and a neutron camera to study the possibilitie s of neutron imaging. \n\nThe experiment was performed under different neu tron production configurations and also with and without moderation of the neutron flux. This systematic analysis based on the response of the diffe rent diagnostics allowed us to set an optimized setup to perform a dedicat ed time-of-flight measurement. The purpose of this experiment is to establ ish the viability of carrying out nuclear physics experiments in this type of neutron sources and to identify the advantages and disadvantages of th is production method as opposed to conventional systems.\n\n[1] INTERNATIO NAL ATOMIC ENERGY AGENCY\, Development Opportunities for Small and Medium Scale Accelerator Driven Neutron Sources – Report of a technical meeting held in Vienna\, 18–21 May 2004\, IAEA-TECDOC-1439\, IAEA\, Vienna (200 5).\n[2] Alejo A.\, Ahmed H.\, Green A. et al. Recent advances in laser-dr iven neutron sources. Il nuovo cimento 38 C\, 188 (2015). 10.1393/ncc/i201 5-15188-8\n[3] Roth M.\, Jung D.\, Falk K. et al. Bright Laser-Driven Neut ron Source Based on the Relativistic Transparency of Solids. Phys. Rev. Le tt. 110\, 044802 (2013). 10.1103/PhysRevLett.110.044802\n[4] Guerrero C.\, Domingo-Pardo C.\, Käppeler F. et al. Prospects for direct neutron captu re measurements on s-process branching point isotopes. Eur. Phys. J. A 53\ , 87 (2017). 10.1140/epja/i2017-12261-2\n[5] Schramm U.\, Bussmann M.\, Ir man A. et al. First results with the novel petawatt laser acceleration fac ility in Dresden. J. Phys.: Conf. Ser. 874\, 012028 (2017). 10.1088/1742-6 596/874/1/012028\n\nhttps://indico.frib.msu.edu/event/52/contributions/734 / LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/734/ END:VEVENT BEGIN:VEVENT SUMMARY:Study of nuclear data measurement with covariances and uncertainty quantification DTSTART:20220727T154500Z DTEND:20220727T155700Z DTSTAMP:20260420T153400Z UID:indico-contribution-754@indico.frib.msu.edu DESCRIPTION:Speakers: Aman Gandhi (Department of Physics\, Banaras Hindu U niversity\, Varanasi-221005\, India)\, Aman Sharma\, Rebecca Pachuau (Depa rtment of Physics\, Banaras Hindu University\, Varanasi-221005\, India)\, A. Kumar (Department of Physics\, Banaras Hindu University\, Varanasi-2210 05\, India)\n\nhttps://indico.frib.msu.edu/event/52/contributions/754/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/754/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Data and Neutronics Study for Long-Lived Radionuclides Pro duced during Fusion Reactor Operation DTSTART:20220728T151400Z DTEND:20220728T152600Z DTSTAMP:20260420T153400Z UID:indico-contribution-850@indico.frib.msu.edu DESCRIPTION:Speakers: Jyoti Pandey (ITER-India\, Institute For Plasma Rese arch\, Gandhinagar\, Gujarat)\n\nNeutronics study is the backbone for the reactor Physics design. In both\, fission and fusion reactor neutrons play an important role to the generation of electricity\, by the conversion of their kinetic energy to heat energy. Fission neutrons have a maximum ener gy 2-3 MeV\, while fusion neutrons coming from D-T plasma have a maximum e nergy of ~ 14.6 MeV. The Dynamics of fusion reactor neutrons is going to p lay a crucial role for the upcoming fusion reactor\; International thermon uclear experimental reactor (ITER)\, DEMO\, IFMIF and others. Out of the m any neutrons induced reactions that take place inside a fusion reactor\, t he ones that produce gaseous elements like hydrogen and helium are of utmo st importance for the study of structural integrity of reactor materials. The production of hydrogen and helium gases takes place mainly through (n\ , xp) and (n\, xα) reactions. These reactions are induced on the first wa ll\, structural and blanket materials of the fusion reactor. In addition t o the production of hydrogen and helium\, the other processes such as atom ic displacements and transmutations can produce microstructural defects an d modify physical properties of the materials. The materials suitable for the reactor structures are stainless steel with Cr\, Fe\, and Ni as main c onstituents (in SS316(LN)-IG content of Fe ≈ 65%\, Ni ≈ 12%\, Cr ≈ 1 7%). As the neutrons continuously coming from plasma interact with the var ious wall of the reactor made up of SS. There will be generation of variou s long-lived radionuclides like 55Fe (t1/2= 2.737 years)\, 59Ni (t1/2= 7.6 ×104years)\, 59Fe(t1/2 = 44.5 days)\, 60Co (t1/2 = 5.27years)\, 60Fe (t1/ 2= 2.6×106 years)\, 53Mn (t1/2=3.74×106 y)\, 54Mn (t1/2 = 312.16 days) i nside reactor environment. The neutrons coming from plasma interacts with various long-lived radionuclides already generated in reactor environment during its operation\, such types of reaction are called second generation reaction. These radionuclides play crucial role in damage of the reactor material\, because of their long time presence inside reactor. As there is no experimental and theoretical study on the neutron induced reactions of various radionuclides produced inside the reactor environment during the reactor operation. As they are radionuclides\, their properties such as d ecay heat\, activity\, dose rate\, ingestion dose\, inhalation dose\, will effect normal lattice sites. The cross sections of the neutron induced re action of various radionuclides are not measured and studied till now. So\ , there is a large gap in the nuclear data library . \nThe determination o f reaction cross-section for long-lived radionuclide and short lived nucle i is a very challenging task . For the very first time\, I have studied an d experimentally verified the use of surrogate ratio method for the determ ination of (n\,xp) reaction cross-sections. The cross-sections of 59Ni(n\, xp) (t1/2 = 7.6 × 104 year) has been measured for the very first time us ing surrogate ratio method. Also\, there exist no experimental data for th e neutron induced charged particle reaction on 60Co. Excitation function o f 60Co(n\,p)60Fe and 60Co(n\,α) have been obtained from threshold to 20 M eV using Hauser Feshbach model calculations with pre-equilibrium contribut ion using TALYS code. Major pathways (nuclear reaction channels) and their production cross-section for the formation of long-lived radionuclides 55 Fe\, 60Co\, 63Ni\, 59Ni have been calculated using activation code-ACTYS a nd nuclear reaction modular codes TALYS-1.8 code. During the present study \, it has been recognized that the 59Ni(n\,α)56Fe and 55Fe(n\,α)52Cr rea ctions may also generate significant displacement damage as the recoil ene rgy of 56Fe and 52Cr are 2.476 MeV and 2.497 MeV (for fast neutrons)\, res pectively. A two step neutron reaction sequence 58Ni(n\,g)59Ni(n\,α)56Fe and 56Fe(n\,2n)55Fe(n\,α) result in an important contribution to the heli um production in reactor environment.\n\nThe detail explanation of the met hods used and results obtained during the present research work\, will be presented during conference.\n\nhttps://indico.frib.msu.edu/event/52/contr ibutions/850/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/850/ END:VEVENT BEGIN:VEVENT SUMMARY:Validating Gamma-rays Produced in Nuclear Reactions DTSTART:20220725T190900Z DTEND:20220725T192100Z DTSTAMP:20260420T153400Z UID:indico-contribution-859@indico.frib.msu.edu DESCRIPTION:Speakers: Isabel Hernandez\n\nAuthors: \nIsabel Hernandez\, Je nnifer Jo Ressler\, Bonnie Canion \n\nUnderstanding gamma-ray production i n a neutron environment is vital in many scientific concentrations. Emerge ncy response\, planetary exploration\, safety and shielding designs – am ong many other applications – depend on analyzing neutron induced gamma- ray spectra from measurements. These research areas often require simulati on capabilities to extend analysis and substitute as a low-cost and fast s olution option to physical measurements. Due to the wide availability and applicability of neutron transport codes\, many users depend on the status of current nuclear data libraries in order to produce accurate simulated results. \n\nDiscrepancies observed between simulations and measurements m ay be due to the availability of the nuclear data needed to model an inter action\, the accuracy and precision of the nuclear data available\, or the manner in which the simulation tool is incorporating the nuclear data to model an interaction. Therefore\, it is of current interest to determine t he condition of current nuclear data libraries and compare them to gamma-r ay data. We focus on the ENDF/B VIII evaluation\, due to the high volume o f users. Proposed benchmark datasets\, such as published IAEA compiled sta ndards\, will be used in its comparison. In this work\, we developed a pro cess for extracting neutron induced gamma-ray production data from the GND S data libraries for discrete gamma-ray energies\, as well as exploring be st methods for including the continuum spectrum contribution. \n\nWe then compared these gamma-ray production cross sections in the GNDS library to experimental benchmarks. We saw that non-graphical library extraction meth ods provided a more accurate cross section compared to experimental result s\, though the continuum contribution that led to a comparable cross secti on was often non-trivial compared to its discrete counterpart\, and the ap propriate integration energy window size varied greatly. This is notable\, since the importance of the non-discrete contribution to the total cross section is prevalent in all analyzed isotopes and may lead to interpretati on issues in simulation codes. Lastly\, we used popular neutron transport codes\, MCNP\, Mercury\, and GEANT4 to extract the interpreted ENDF/B VIII data and provide comparisons to measurements. We found that isotopes with library storage issues found in the previous step had greatly misinterpre ted cross sections across the board compared to the raw library data. Thes e isotopes include 12C and 14N\, two prominent isotopes relevant for appli cations such as non-destructive cargo screening techniques. Future work wi ll include investigating why these Monte Carlo codes are accessing nuclear data differently and extending this process to other isotopes and interac tions. Recommendations to the U.S. Nuclear Data Team have and will be made for further improvements where data are incorrect or missing. \n\nPrepare d by LLNL under Contract DE-AC52-07NA27344.\nLLNL-ABS-827870\n\nhttps://in dico.frib.msu.edu/event/52/contributions/859/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/859/ END:VEVENT BEGIN:VEVENT SUMMARY:Cross section measurements of ${}^{7}$Li(d\,x) tritium and berylli um production\, ${}^{39}$K(n\,p)${}^{39}$Ar for HPRL DTSTART:20220727T145700Z DTEND:20220727T150900Z DTSTAMP:20260420T153400Z UID:indico-contribution-804@indico.frib.msu.edu DESCRIPTION:Speakers: Jaromír Mrázek\, Mitja Majerle\, Klix Axel\, Marti n Ansorge\, Eva Šimečková\, Jan Novak\, Daniil Koliadko\n\nThe Nuclear Energy Agency's High Priority Nuclear Data Request List (HPRL) is a compil ation of the highest priority nuclear data requirements. The U-120M cyclot ron of the Nuclear Physics Institute of the Czech Academy of Sciences is a suitable tool for studies of several reactions from this list. In this pa per\, we present the measurements of the ${}^{7}$Be and tritium production in the lithium after irradiation with deuterons (ID: 116H and 117H) and t he validation measurement for the ${}^{39}$Ar production in ${}^{39}$K aft er irradiation with neutrons (ID: 45H).\n\nThe U-120M cyclotron is used to accelerate deuterons up to 20 MeV. The deuterons are directed to Li$_{2}$ CO$_{3}$ pellets with 100% enriched ${}^{7}$Li. After the irradiation\, th e ${}^{7}$Be production is measured by gamma spectrometry\, and tritium pr oduction is measured by dissolving the pellet in the liquid scintillator a nd with the aid of scintillation equipment.\n\nFor the measurement of the ${}^{39}$Ar production in the reaction ${}^{39}$K(n\,p)${}^{39}$Ar\, the m uscovite mica foil is irradiated using well known continuous neutron spect rum from the p+Be neutron generator. The beta spectra from the decay of ${ }^{40}$K\, ${}^{39}$Ar\, and other beta emitters in the mica foil are reco rded using the PIN diode before and after the irradiation. The amount of p roduced ${}^{39}$Ar is deduced from the differences between the recorded s pectra.\n\nhttps://indico.frib.msu.edu/event/52/contributions/804/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/804/ END:VEVENT BEGIN:VEVENT SUMMARY:Half-life determination of long-lived hard-to-measure isotopes: ex amples 53-Mn and 93-Mo DTSTART:20220728T170400Z DTEND:20220728T171600Z DTSTAMP:20260420T153400Z UID:indico-contribution-923@indico.frib.msu.edu DESCRIPTION:Speakers: Dorothea Schumann (Paul Scherrer Institut Villigen\, Switzerland)\n\nKnowing the half-life of a radioactive isotope as precise ly as possible is crucial for many research areas\, for example nuclear as trophysics\, nuclear energy technology or environmental research. Radionuc lides with half-lives of hundreds to millions of years are particularly im portant\, not only because of their significance in the relevant scientifi c field but also because of their potential impact on humans and the envir onment. Their half-lives cannot be determined by following the decay but h ave to be measured by the direct method\, requiring the determination of t he specific activity and the corresponding number of atoms. The half-lives of a many of these long-lived nuclides are poorly known\, with data only based on a small number of measurements that can be very old. Some of thes e half-lives have large uncertainties\, or the results of various studies are discrepant. This situation is largely caused by the low quantity and p oor quality of the available samples. Especially for radionuclides that de cay via electron capture only (so-called “hard-to-measure-isotopes”)\, the exact determination of the activity is a big challenge\, since a radi ochemically pure sample is required. The required level of radiochemical p urity can be achieved either by a dedicated production route or by isolati on of the wanted isotope using preparative mass separation.\nIn our presen t contribution\, we focus on two such isotopes\, 53Mn and 93Mo. 53Mn is a radionuclide that is mainly produced in freeze-out phases of nuclear stati stical equilibria of explosive burning in both thermonuclear and core-coll apse supernovae explosions. Although the primordial 53Mn is now extinct\, its former presence can be observed by enhancements of its daughter 53Cr i n meteorites from asteroids formed in the Early Solar System. The 53Mn/53C r chronometer could be used for precise dating of events in the Early Sola r System on the timescale of 20 Ma [1]\, given that the half-life is known with low uncertainty.\n93Mo is produced by neutron activation of stable 9 2Mo\, and\, since molybdenum is a component of the construction materials in nuclear power plants (e.g. in steel\, Inconel alloys and cables)\, it b ecomes the dominant dose contributor in low and intermediate level radioac tive waste after the shorter-lived radionuclides have decayed. It is one o f the few long-lived isotopes where no direct experimental determination o f half-life existed so far.\nThe present work reports the determination of the half-lives of 53Mn and 93Mo using a combination of isotope dilution m ass spectrometry for the measurement of the numbers of atoms\, and liquid scintillation counting for measurement of activity. Low mass resolution mu lticollector inductively coupled plasma mass spectrometry (MC-ICP-MS) was used for 93Mo\, and a combination of high mass resolution MC-ICP-MS and th ermal ionization mass spectrometry were used for 53Mn. \nA radiochemically pure sample of 93Mo was directly produced by proton irradiation of niobiu m and followed by a chemical separation of molybdenum with a decontaminati on factor larger than 1.6×1014. The 53Mn sample\, chemically separated fr om irradiated steel samples\, underwent a mass separation using the RISIKO laser mass separator facility at the University of Mainz to get rid of 54 Mn that would interfere with the activity measurements. \nThe determinatio n of the activity is particularly challenging in the case of 93Mo since th e decay partly leads to the isomer 93mNb. With the help of long-term liqui d scintillation counting measurements and a very complicated evaluation me thod\, the decay probability of 93Mo to 93mNb could be determined with unp recedented accuracy in addition to the activity and the half-life value [2 ].\nWe will present details on the sample preparation as well as the corre sponding activity and mass spectrometry measurements and report on the res ults [2\,3].\n[1] Birck\, JL.\, Allègre\, C. Manganese—chromium isotope systematics and the development of the early Solar System. Nature 331\, 5 79–584 (1988). https://doi.org/10.1038/331579a0\n[2] [2] Kajan\, I.\, He initz\, S.\, Kossert\, K. et al. First direct determination of the 93Mo ha lf-life. Sci Rep 11\, 19788 (2021).\n[3] J. Ulrich\, PhD thesis 2020\, Hig h precision nuclear data of 53Mn for astrophysics and geosciences\, Univer sity of Berne\, Switzerland\n\nhttps://indico.frib.msu.edu/event/52/contri butions/923/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/923/ END:VEVENT BEGIN:VEVENT SUMMARY:$\\beta$-delayed neutron spectroscopy of $^{85}$As with MONSTER DTSTART:20220728T145000Z DTEND:20220728T150200Z DTSTAMP:20260420T153400Z UID:indico-contribution-916@indico.frib.msu.edu DESCRIPTION:Speakers: Alberto Pérez de Rada Fiol (CIEMAT)\n\nA better qua ntitative understanding of $\\beta$-delayed neutron emission rates and spe ctra is relevant for nuclear structure\, astrophysics\, and reactor applic ations: $\\beta$-delayed neutrons provide valuable information on the $\\b eta$-decay process\, are needed in network calculations for understanding the stellar nucleosynthesis process\, and can improve the understanding of the kinematics and safety of new reactor concepts loaded with new types o f fuels. The field has experienced an increased activity during the last d ecades [1] thanks to the advances in nuclear experimental techniques and t he radioactive ion beam facilities. More accurate measurements of $\\beta$ -delayed neutron emission properties like the emission probability\, $\\be ta$-feeding\, and energy spectrum from individual precursors are being mad e with advanced neutron detectors [2\, 3\, 4]\, digital data acquisition s ystems [5]\, and high intensity ion beams [6\, 7\, 8\, 9].\n\nThe $\\beta$ -delayed neutron emission in the $^{85}$As decay has been measured at the Ion Guide Isotope Separator On-Line (IGISOL) facility [9] of the JYFL Acce lerator Laboratory of the University of Jyväskylä. The $^{85}$As isotope s were produced by proton-induced fission reactions in $^{238}$U\, separat ed from the rest of the fission fragments with IGISOL\, and implanted onto a tape. The complete decay has been studied with the help of a complex se tup which consists of a plastic scintillator detector for the emitted $\\b eta$-particles\, a HPGe Clover and four LaBr$_3$ detectors for the emitted $\\gamma$-rays\, and the \\textbf{MO}dular \\textbf{N}eutron \\textbf{S}p ectrome\\textbf{TER} (MONSTER) [4\, 10] for the detection of the emitted n eutrons. MONSTER consists of an array of 48 cylindrical cells of 200 mm di ameter and 50 mm height\, filled with BC501A or EJ301 scintillating liquid . Each cell is coupled through a light guide of 31 mm thickness to a R4144 or R11833 PMT. The neutron energy is determined by the time-of-flight tec hnique\, using the signals from the plastic detector and MONSTER as the st art and stop signals\, respectively.\n\nIn this conference\, we report the results obtained from the measurement at JYFL. The $\\beta$-delayed neutr on energy distribution of the $^{85}$As $\\beta$-decay has been determined by unfolding the time-of-flight spectrum with the iterative Bayesian unfo lding method [11]\, and their partial branching ratios to the excited stat es in the final nucleus by applying $\\beta$-n-$\\gamma$ coincidences. We also compare the results of this work to existing data [12\, 13].\n\n----- -----\n\n[1] P. Dimitriou *et al.*\, Nuclear Data Sheets\, **173**\, (2021 ) 144-238\n[2] A. Buţă *et al.*\, Nucl. Instrum. and Methods A\, **455** \, (2000) 412-423\n[3] C. Matei *et al.*\, Proceedings of the 10$^{th}$ In ternational Symposium on\nNuclei in the Cosmos\, 138\, Proceedings of Scie nce\, (2008) 1–5\n[4] A.R. Garcia *et al.*\, JINST\, **7**\, (2012) C050 12\n[5] D. Villamarin *et al.*\, In preparation\n[6] W.F. Henning *et al.* \, GSI publication\, (2001) https://fair-center.eu/\n[7] H. Okuno\, *et al .*\, Prog. Theor. Exp. Phys.\, (2012) 03C002\n[8] R. Catherall *et al.*\, Nucl. Instrum. and Methods B\, **317**\, (2013) 204–207\n[9] I.D. Moore *et al.*\, Nucl. Instrum. and Methods B\, **317**\, (2013) 208\n[10] T. Ma rtinez *et al.*\, Nuclear Data Sheets\, **120**\, (2014) 78\n[11] G. D'Ago stini\, Nucl. Instrum. and Methods A\, **362**\, (1995) 487-498\n[12] K.-L . Kratz *et al.*\, Nucl. Phys. A\, **317**\, (1979) 335\n[13] D. Rudstam * et al.*\, At. Data and Nucl. Data Tables\, **53**\, (1993) 1\n\nhttps://in dico.frib.msu.edu/event/52/contributions/916/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/916/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) First-forbidden $\\beta$-decay study in the pnQRPA app roach DTSTART:20220727T154500Z DTEND:20220727T155700Z DTSTAMP:20260420T153400Z UID:indico-contribution-935@indico.frib.msu.edu DESCRIPTION:Speakers: Arthur Beloeuvre (Subatech)\n\nFirst-forbidden beta decays play an important role in several domains of physics. First\, in as trophysics\, where nuclear data such as the half-life govern stellar evolu tion and nucleosynthesis [1]. Second\, they are of interest for nuclear r eactors physics as first highlighted in 2014 [2]. In first-forbidden $\\be ta$-decays\, the form factor of the leptonic spectra are not equal to one as for allowed decays. It has been shown that it could have a non negligea ble impact on the shape of the antineutrino energy spectra. Among the mode ls developed since then\, which do not all tend to agree [3\, 4\, 5\, 6]\, some even state that it could solve the reactor antineutrino shape anomal y. \nNew theoretical calculations of the first-forbidden form factors asso ciated to summation calculations [7] and dedicated experimental measuremen ts would be useful to corroborate or negate already existing predictions.\ n\nCharge-exchange excitations corresponding to beta-decay first forbidden transitions in nuclei have been studied in the self-consistent *proton-ne utron quasiparticle random-phase approximation* (pnQRPA) using the finite- range Gogny interaction [8]. No parameters beyond those included in the ef fective nuclear force are included. Axial deformations are taken into acco unt for both the ground state and charge-exchange excitations.\nWith this formalism\, nuclear matrix elements have been computed for operators deriv ed from the multipole expansion of the weak current [9]: spin-dipole\, ant i-analog dipole and pseudoscalar-axial vector and tensor-polar vector oper ators. Those operators come to complete the already existing Fermi and Gam ow-Teller operators already considered in Ref. [8] in order to have a simu ltaneous description of the allowed and first-forbidden $\\beta$-decays.\n \nAt this conference\, first results of the corresponding leptonic form f actors of first-forbidden beta-decays will be presented\, as well as the a ssociated leptonic spectra. A comparison with experimental beta spectra fr om fission products will be shown.\n\n**References**:\n\n[1] M. Arnould\, S. Goriely\, and K. Takahashi. The r-process of stellar nucleosynthesis: A stro- physics and nuclear physics achievements and mysteries. Phys. Rept.\ , 450:97–213\, 2007.\n\n\n[2] A. C. Hayes\, J. L. Friar\, G. T. Garvey\, Gerard Jungman\, and Guy Jonkmans. Systematic Uncertainties in the Analys is of the Reactor Neutrino Anomaly. Phys. Rev. Lett.\, 112:202501\, 2014.\ n\n[3] Dong-Liang Fang and B. Alex Brown. Effect of first forbidden decays on the shape of neutrino spectra. Phys. Rev. C\, 91(2):025503\, 2015. [Er ratum: Phys.Rev.C 93\, 049903 (2016)].\n \n[4] X. B. Wang and A. C. Hayes. Weak magnetism correction to allowed β decay for reactor antineutrino sp ectra. Phys. Rev. C\, 95(6):064313\, 2017.\n\n[5] X. B. Wang\, J. L. Friar \, and A. C. Hayes. Nuclear Zemach moments and finite-size corrections to allowed β decay. Phys. Rev. C\, 94(3):034314\, 2016.\n\n[6] J. Petkovic\, T. Marketin\, G. Martinez-Pinedo\, and N. Paar. Self-consistent calculati on of the reactor antineutrino spectra including forbidden transitions. J. Phys. G\, 46(8):085103\, 2019.\n\n[7] M. Estienne et al. Updated Summatio n Model: An Improved Agreement with the Daya Bay Antineutrino Fluxes. Phys . Rev. Lett.\, 123(2):022502\, 2019.\n\n[8] M. Martini\, S. Peru\, and S. Goriely. Gamow-Teller strength in deformed nuclei within the self- consist ent charge-exchange quasiparticle random-phase approximation with the Gogn y force. Phys. Rev. C\, 89(4):044306\, 2014.\n\n[9] Aage Bohr and Ben R Mo ttelson. Nuclear Structure. World Scientific Publishing Company\, 1998.\n\ nhttps://indico.frib.msu.edu/event/52/contributions/935/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/935/ END:VEVENT BEGIN:VEVENT SUMMARY:A new R-matrix module for multi-channel calculations with GECCCOS DTSTART:20220727T134800Z DTEND:20220727T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-922@indico.frib.msu.edu DESCRIPTION:Speakers: Helmut Leeb\, Thomas Srdinko\n\nA versatile R-matrix module for multi-channel reaction calculations was developed which allows not only phenomenological R-matrix analyses\, but also extensions to new and non-standard formulations of R-matrix theory such as the Reduced R-mat rix formulation and the hybrid R-matrix concept. An important feature of t he module is the capability to combine standard R-matrix analysis with the result of calculable R-matrix calculations an important aspect for the re alisation of the hybrid R-matrix approach [1]. The calculable R-matrix all ows the solution of potential-based coupled-channel problems in terms of R -matrix parameters using the Lagrange-mesh technique [2]. The R-matrix mod ule can be coupled with parameter optimization frameworks like the DAKOTA- package [3] and allows the analysis of experimental data in terms of R-mat rix parameters. The flexible code structure enabled the development of sev eral approaches such as the hybrid R-matrix using pseudo-potentials instea d of background poles or the reduced R-matrix method which inherently acco unts for threshold energies of channels not explicitly included in the ana lysis. \n\nThe new R-matrix module provides the collision matrix and can e asily be included into the multi-channel code GECCCOS (GEneral Coupled-Cha nnel COde System) which has been developed by the nuclear data group at TU -Wien to perform nuclear reaction calculations especially for light nuclea r systems. Aiming at maximum flexibility regarding the inclusion of new or enhanced modules a clear structure regarding the calculation flow and the data transfer between modules was an important design goal. This ensured easy development and inclusion of new reaction modules as well as compatib ility with existing codes for ENDF file generation. Furthermore the output of observables follows the scheme of the TALYS [4] code thus simplifying the combined use in nuclear data evaluation. \n\nA successful run of the c ode yields the complete S-matrix (collision matrix) as well as observables for unpolarised beams\, angle-differential cross sections\, excitation fu nctions\, and angle-integrated cross sections (if existing). Recently an e xtension for obtaining the analysing power of spin 1/2 particles was succe ssfully implemented and tested. The inclusion of polarisation observables for higher spin values is in progress. For phenomenological R-matrix analy ses a separate module automatically assembles calculated and available exp erimental values\, automatically performs reference frame transformations if necessary and calculates chi-square values as feedback for the paramete r fitting process. In the presentation an overview of the design concept\, implemented functionality and current status of development will be given together with an outlook on envisaged future developments. \n\n**Acknowle dgement:** The work has been carried out within the framework of the EUROf usion Consortium and has received funding from the Euratom research and tr aining programme 2014-2018 and 2019-2020 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those o f the European Commission.\n\nReferences\n[1] Th. Srdinko\, H. Leeb\, EPJ Web of Conferences 146\, 12030 (2017).\n[2] P. Descouvemont\, D. Baye\, Re p. Prog. Phys. 73\, 036301 (2010).\n[3] B.M. Adams\, W.J. Bohnhoff\, et al .\, Dakota\, A Multilevel Parallel Object-Oriented Framework for Design Op timization\, Parameter Estimation\, Uncertainty Quantification\, and Sens itivity Analysis (Version 6.12\, User’s Manual\, Sandia Technical Report SAND2020-12495\, Nov. 2020).\n[4] A.J. Koning\, S. Hilaire and M.C. Duijv estijn\, “TALYS-1.0”\, Proc. of the Int. Conf. on Nuclear Data for Sci ence and Technology\, April 22-27\, 2007\, Nice\, France\, Eds.: O.Bersill on\, F.Gunsing\, E.Bauge\, R.Jacqmin\, and S.Leray\, EDP Sciences\, 2008\, p. 211-214.\n\nhttps://indico.frib.msu.edu/event/52/contributions/922/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/922/ END:VEVENT BEGIN:VEVENT SUMMARY:Improved current measurements for ionization chambers using the UL CA: A benchmark experiment to determine the 18F half-life DTSTART:20220728T152600Z DTEND:20220728T153800Z DTSTAMP:20260420T153400Z UID:indico-contribution-929@indico.frib.msu.edu DESCRIPTION:Speakers: Ole Jens Nähle (Physikalisch-Technische Bundesansta lt)\n\nImproved current measurements for ionization chambers using the ULC A: A benchmark experiment to determine the F-18 half-life\n\nOle Nähle1)\ , Dietmar Drung 1)\, Karsten Kossert 1)\, Hansjörg Scherer1)\, Marcell P éter Takács 1)\n\n1) Physikalisch-Technische Bundesanstalt (PTB)\, Bunde sallee 100\, 38116 Braunschweig\, Germany\nCorresponding author’s e-mail : ole.j.naehle@ptb.de\n\nIonization chambers play an important role in rad ionuclide metrology and are used for secondary activity standardization as well as for half-life determinations of a number of radionuclides. In bot h cases\, the actual measurand is the ionization current which is often de termined by means of electrometers with insufficient accuracy. In particul ar when considering a wide current range over several orders of magnitude (typically about 5 nA down to a few 10 fA) most electrometers suffer from range switches and/or significant non-linearities that may even be influen ced by the preceding measurements. Thus\, when using such devices\, correc tions must be applied\, and additional uncertainty components must be take n into account when determining activities or half-lives. These effects ca n only be studied by measuring short half-lives and will harm the determin ation of long half-lives in an unpredictable way.\nIn this paper we presen t results of a benchmark experiment using a modified experimental setup th at makes use of the ultrastable low-noise current amplifier (ULCA) [1\, 2] . The voltage readout of this device was measured by means of a Keysight 3 548A voltmeter. During the installation\, great emphasis was placed on exc ellent shielding of the cables and connectors and a dedicated data acquisi tion software was developed. All test measurements so far underline a sign ificant improvement in linearity of the instrument readings. Moreover\, th e readings do not show any disturbing unsteadiness that was previously fou nd as a consequence of range switches.\nAs an important benchmark experime nt\, we present here the determination of the half-life of 18F. To this en d\, a 18F sample was measured for 25 half-lives with unchanged sample posi tion until background current was reached. The analysis yields a half-life (preliminary result: 109.711 min) that is shorter than current values fro m nuclear data evaluations. This somewhat shorter half-life is confirmed b y independent measurements using liquid scintillation counting systems to apply the triple-to-double coincidence ratio (TDCR) method. In this case\, valuable information on the sample/counter stability can be derived from triple and double coincidence counting rates.\nDetails on the analyses and uncertainty assessments will be presented.\n\nReferences\n[1] Drung\, D.\ , Götz\, M.\, Pesel\, E.\, Scherer\, H.\, 2015a. Improving the Traceable Measurement and Generation of Small Direct Currents. IEEE Trans. Instrum. Meas. 64\, 3021–3030.\n[2] Drung\, D.\, Krause\, C.\, Becker\, U.\, Sche rer\, H.\, Ahlers\, F.J.\, 2015b. Ultrastable low-noise current amplifier: a novel device for measuring small electric currents with high accuracy. Rev. Sci. Instrum. 86\, 024703.\n\nhttps://indico.frib.msu.edu/event/52/co ntributions/929/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/929/ END:VEVENT BEGIN:VEVENT SUMMARY:Liquid scintillation counting: A valuable tool to determine half-l ives DTSTART:20220728T164000Z DTEND:20220728T170400Z DTSTAMP:20260420T153400Z UID:indico-contribution-921@indico.frib.msu.edu DESCRIPTION:Speakers: Karsten Kossert (Physikalisch-Technische Bundesansta lt)\n\nhttps://indico.frib.msu.edu/event/52/contributions/921/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/921/ END:VEVENT BEGIN:VEVENT SUMMARY:Ab initio theory applied to the evaluation of the 6Li(n\,t)4He re action DTSTART:20220727T180000Z DTEND:20220727T182400Z DTSTAMP:20260420T153400Z UID:indico-contribution-944@indico.frib.msu.edu DESCRIPTION:Speakers: Konstantinos Kravvaris\n\nFirst-principles calculati ons have made great strides during the past years in bridging the gap from fundamental nuclear interactions derived from chiral effective field theo ry to the description of nuclear structure and dynamics. Due to their pred ictive capability\, large-scale calculations can form the basis on which n uclear data evaluations can be performed. In this talk\, I will outline a new approach that combines such first-principles calculations with Gaussia n process emulators and nuclear data in order to arrive at an evaluated cr oss section for the 6Li(n\,t)4He reaction with quantified uncertainties.\n \nhttps://indico.frib.msu.edu/event/52/contributions/944/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/944/ END:VEVENT BEGIN:VEVENT SUMMARY:Generation of thermal scattering laws with the CINEL code DTSTART:20220728T130000Z DTEND:20220728T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-932@indico.frib.msu.edu DESCRIPTION:Speakers: Gilles Noguere (CEA\, DES\, IRESNE Cadarache)\n\nThe thermal scattering laws (TSLs) take into account the crystalline structur e and atomic motions of isotopes bound in materials. This paper presents t he CINEL code\, which was developed to generate temperature-dependent TSLs for solid\, liquid and free gas materials of interest for nuclear reactor s. \n\nCINEL is able to calculate TSLs from the phonon density of states ( PDOS) of materials under the Gaussian-Incoherent approximations. The PDOS can be obtained by using theoretical approaches (e.g.\, ab initio density functional theory and molecular dynamics) or experimental results. In this work\, the PDOS presented in the ENDF/B-VIII.0 database [1] and the NJOY- NCrystal library [2] were used for numerical validation purposes. The CINE L results are in good agreement with those reported in these databases\, e ven in the specific cases of TSLs with the newly mixed elastic format.\n\n The coding flexibility offered by Python using the JupyterLab interface al lowed to investigate limits of physical models reported in the literature\ , such as a four-site model for UO2\, anharmonic behaviors of oxygen atoms bound in a Fm3m structure\, texture in Zry-4 samples and jump corrections in a roto-translational diffusion model for liquid water. The use of grap hic processing units (GPU) is a necessity to perform calculations in a few minutes. \n\nThe performances of the CINEL code will be illustrated with the results obtained on actinide oxides having a Fm3m structure (UO2\, ThO 2\, NpO2 PuO2 and AmO2)\, low enriched fuel (U3Si2\, UMo\, UZrH) and moder ators (H2O with a specific emphasis on ice).\n\nReferences\n[1] D.A. Brown et al. “ENDF/B‐VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO‐project Cross Sections\, New Standards and Therm al Scattering Data”. In: Nuclear Data Sheets 148 (2018). \n[2] Kemal Ram ic et al. NJOY+NCrystal: an open‐source tool for creating thermal neutro n scattering libraries. 2021. https://arxiv.org/pdf/2108.11737.pdf\n\nhttp s://indico.frib.msu.edu/event/52/contributions/932/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/932/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Study of Breakup Reactions of Weakly Bound nuclei $^{6 \,7}$Li DTSTART:20220727T184800Z DTEND:20220727T190000Z DTSTAMP:20260420T153400Z UID:indico-contribution-948@indico.frib.msu.edu DESCRIPTION:Speakers: Wendi Chen (Beihang University)\n\nIt is an open que stion in the fields of nuclear reactions to study the mechanism of reactio ns induced by the weakly bound nuclei at different incident energies with various target nuclei and calculate the reaction cross sections. The struc ture of weakly bound nuclei\, which is easily broken up\, plays an importa nt role in their induced reaction and is thought to be the main reasons fo r their reaction characteristics. We apply the Lagrange mesh method to dis cretize continuum states of weakly bound nuclei for continuum-discretized coupled-channels (CDCC) calculations of $^{6\,7}$Li induced reactions and study their breakup effect on elastic scattering\, inelastic scattering\, fusion reaction and total reaction cross sections. Furthermore\, the break up effect on transfer reaction is studied with coupled-channels born-appro ximation (CCBA) method. Energy and target dependences of breakup effect ar e discussed.\n\nhttps://indico.frib.msu.edu/event/52/contributions/948/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/948/ END:VEVENT BEGIN:VEVENT SUMMARY:Advanced Modeling and Simulation Methods for Evaluation of Thermal Neutron Scattering Materials DTSTART:20220728T155000Z DTEND:20220728T160200Z DTSTAMP:20260420T153400Z UID:indico-contribution-950@indico.frib.msu.edu DESCRIPTION:Speakers: Chris Chapman (Oak Ridge National Laboratory)\n\nWit h the rise of interest in thermal neutron scattering data for advanced rea ctor\, criticality safety\, and shielding applications\, new experimental data is required both for evaluations of new materials or for re-evaluatio ns (or validations) of previously evaluated materials. New experimental da ta is evaluated in a 3-step process: 1) computing the phonon characteristi cs (e.g. eigenvalues/vectors of the material’s dynamical matrix\, molecu lar dynamics trajectories\, etc.)\, 2) computing the dynamic structure fac tor (DSF) from it\, and\, 3) using the experimental setup to simulate the experimental data. All three steps have challenges\, from needing a suffic iently general material simulation code\, a processing code that can compu te the corresponding DSF\, to having a detailed layout of the instrument/b eamline/facility where the data were measured. Whereas phonon characterist ics of materials can be computed using various methods (molecular dynamics \, density functional theory\, etc.)\, a high-fidelity computation of the DSF and the simulation of the experiment based on the DSF is vital to the accuracy of evaluation. The latter 2 steps can be achieved by using the tw o corresponding code systems developed by instrument scientists at the Spa llation Neutron Source (SNS) at Oak Ridge National Laboratory: 1) OCLIMAX (a program that calculates the dynamic structure factor from DFT and MD si mulation results)\, and 2) MCViNE (a Monte Carlo neutron ray-tracing progr am designed to simulate neutron scattering experiments). Recently\, polyet hylene and yttrium hydride were measured at the ARCS\, SEQUOIA\, and VISIO N instrument stations of the SNS. These experiments are simulated using th e density functional theory code CASTEP to compute its phonon characterist ics (eigenvalues/vectors and PDOS)\, which is then processed using OCLIMAX to yield the DSF\, and finally the data at each instrument station is sim ulated by the MCViNE for comparison to the measured for evaluation. For co mparison to conventional evaluation methods\, results processed from OCLIM AX are compared against those processed from the LEAPR module of NJOY\, an d the results from MCViNE simulations are compared against previously used simplified beamline models implemented in MCNP. \n\nAcknowledgments\n\nTh is work was supported by the U.S. Department of Energy (DOE) Nuclear Criti cality Safety Program\, which is funded and managed by the National Nuclea r Security Administration for DOE and the Transformational Challenge React or Program of the US Department of Energy Office of Nuclear Energy.\n\n* T his manuscript has been authored by UT-Battelle\, LLC\, under contract DE- AC05-00OR22725 with the US Department of Energy (DOE). The US government r etains and the publisher\, by accepting the article for publication\, ackn owledges that the US government retains a nonexclusive\, paid-up\, irrevoc able\, worldwide license to publish or reproduce the published form of thi s manuscript\, or allow others to do so\, for US government purposes. DOE will provide public access to these results of federally sponsored researc h in accordance with the DOE Public Access Plan (http://energy.gov/downloa ds/doe-public-access-plan).}\n\nhttps://indico.frib.msu.edu/event/52/contr ibutions/950/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/950/ END:VEVENT BEGIN:VEVENT SUMMARY:Thermal scattering law for ice based on neutron time-of-flight exp eriments carried out at the SEQUOIA spectrometer at the Oak Ridge National Laboratory DTSTART:20220728T152600Z DTEND:20220728T153800Z DTSTAMP:20260420T153400Z UID:indico-contribution-947@indico.frib.msu.edu DESCRIPTION:Speakers: Vaibhav Jaiswal (Institut de Radioprotection et de S ûreté Nucléaire (IRSN))\n\n**Thermal scattering law for ice based on ne utron time-of-flight experiments carried out at the SEQUOIA spectrometer a t the Oak Ridge National Laboratory**\n\nVaibhav Jaiswal$^{1\,*}$\, Luiz L eal$^1$\, and Alexander I. Kolesnikov$^2$\n\n$^1$Insititut de Radioprotect ion et de Sûreté Nucléaire (IRSN)\, Fontenay-aux-Roses\, France\n$^2$Ne utron Scattering Sciences Division\, Oak Ridge National Laboratory\, Oak R idge\, TN 37831-6473\, USA\n$*$ Corresponding author: vaibhav.jaiswal@irsn .fr\n\nNeutrons generated in the fission process are in the MeV energy ran ge that are slowed down to thermal energies (eV) by the scattering process with moderator materials. During the scattering process\, when the neutro n energy is comparable to the bound energies of the scattering atom/molecu le\, a special treatment must be performed to characterize this effect cor rectly\, which is described by the thermal scattering law (TSL).\n\nThe In stitut de Radioprotection et de Sûreté Nucléaire (IRSN) is working on t he development of improved TSL for light water ice to support research on advanced nuclear systems using ice as a neutron moderator (operating aroun d 80 K) [1]. International recommendation from institutes like IAEA and UK AEA highlights the need to design packages to be transported at low temper ature (up to -40°c) [2\,3]. This recommendation emphasizes the need for i ce neutron scattering data in the temperature range around 253-293 K. Many polymorphic phases of water ice exist depending on the thermodynamic cond itions. The most common type of ice at normal pressure and near water free zing point temperature (273.15 K) is ice-Ih [4]. Following the importance and the need for accurate modeling of neutron scattering distributions in energy and angle for light-water ice-Ih\, TSLs for ice-Ih were recently de veloped for the ENDF/B-VIII.0 and JEFF-3.3 nuclear data libraries. Total c ross-section and inelastic neutron scattering experimental data were used in the evaluation. However\, the detailed structure of the TSL was develop ed independently of neutron scattering measurements carried out at require d temperatures. Also\, the integral performance of the ENDF/BVIII.0 ice-Ih TSL has been validated with an experimental pulsed-neutron die-away (PNDA ) diffusion benchmark [5]\, which does not necessarily validate the TSL ph ysics model or guarantee that the TSL will perform acceptably in condition s similar to those of practical applications.\n\nExisting experimental dou ble-differential scattering data for ice-Ih are extremely sparse and of li mited quality. New high-quality double-differential measurements for ice-I h over multiple temperatures and incident energies would directly support the validation and improvement of TSL models for criticality safety applic ations. Following this\, IRSN carried out a series of double-differential neutron scattering and transmission experiments for light-water ice-Ih at low temperatures (starting at 273 K and down to 5 K) at the SEQUOIA spectr ometer at the Spallation Neutron Source (SNS) at the Oak Ridge National La boratory (ORNL)\, the United States. \n\nA commonly used tool by the react or physics community for generating thermal scattering cross-section data is the LEAPR module of the NJOY code. The process of energy exchange betwe en the neutron and the scattering atom leads to the excitation/deexcitatio n of vibrational and rotational modes of the moderator material\, represen ted by the phonon spectrum. LEAPR calculates the thermal scattering cross- section data using the phonon spectrum of moderator materials as an input. This paper will present the TSL for ice-Ih based on the phonon spectrum m easured at SEQUOIA at different temperatures using the LEAPR module of NJO Y. The outcome of this study will lead to a next-generation TSL evaluation for ice-Ih based on significantly improved material and physics models.\n \n[1] IAEA website\, “Advanced Moderators for Intense Cold Neutron Beams in Materials Research\,” https://www.iaea.org/projects/crp/f12026.\n[2] Technical report\, “IAEA Safety Standards for protecting people and the environment: Regulations for the Safe Transport of Radioactive Material\, ” Specific Safety Requirements\, No. SSR-6.\n[3] SG-3: Criticality Bench mark: A proposal for a benchmark examining the effect of temperature on th e neutron multiplication factor for PWR fuel assemblies.\n[4] M. K. Gupta\ , R. Mittal\, Baltej Singh\, S. K. Mishra\, D. T. Adroja\, A. D. Fortes\, and S. L. Chaplot\, “Phonons and anomalous thermal expansion behavior of H2O and D2O ice Ih\,” PHYSICAL REVIEW B 98\, 104301 (2018).\n[5] J. Hol mes\, M. Zerkle and David Heinrichs\, “Benchmarking a first-principles t hermal neutron scattering law for water ice with a diffusion experiment\, ” EPJ Web of Conferences 146\, 13004 (2017).\n\nhttps://indico.frib.msu. edu/event/52/contributions/947/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/947/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron thermal cross section of organic polymers within the Avera ge Functional Group Approximation DTSTART:20220728T132400Z DTEND:20220728T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-934@indico.frib.msu.edu DESCRIPTION:Speakers: Giovanni Romanelli (Università degli Studi di Roma Tor Vergata and ISIS Neutron and Muon Source)\n\n**Abstract**\nThermal neu tron cross sections of hydrogenous materials are a fundamental ingredient for the simulation and design of\, amongst other things\, neutron moderato rs at research centres and nuclear reactors. However\, experimental therma l cross sections are available for just a handful of materials (see\, e.g. \, Ref. 1]). In order to match the level of detail in modern Monte Carlo n uclear transport\ncodes\, the possibility to calculate thermal cross secti ons from simplified models\, molecular dynamics\, and ab initio calculatio ns has been a topic of recent development (see\, e.g.\, Refs. [1\, 2]).\n\ nWe present new applications of the recently developed Average Functional Group\nApproximation (AFGA) for the determination of total neutron scatter ing cross sections at thermal neutron energies [3]. While using only a lim ited number of effective vibrational densities of states\, representing th e hydrogen dynamics of functional groups within organic molecules\, the mo del allows an accurate reproduction\, within the incoherent approximation\ , of the total cross sections from a vast series of polymers\, including m aterials for neutron moderation or phantoms for calculations related to ra diation protection.\n\nThe model was developed based on neutron transmissi on measurements at the VESUVIO\nspectrometer of the ISIS Neutron and Muon Source [4] to determine the total neutron cross section of all proteinogen ic amino acids. Each molecular system was then simulated using phonon calc ulations\, and the hydrogen-projected vibrational density of states within different functional groups in the molecule was isolated. For each functi onal group\, the vibrational density of states was averaged over all amino acids containing it. This procedure effectively corrected each function\n (representing a perfect single crystal) for the disorder and correlation p henomena that the same functional group experiences in a macromolecule or an organic polymer. Such large systems\, whose modelling with atomistic si mulations is prohibitively challenging\, can be simply rationalised in the AFGA as a combination of contribution from our average functional groups. \n\nFigure 1 reports the total cross section of hydrogen within several fu nctional groups from the AFGA\, showing the importance of taking into acco unt the chemistry of the material at thermal neutron energies. In order to facilitate its use\, the AFGA is now avail able within the NCrystal envir onment [2].\n\n**References**\n[1] Macfarlane\, R.\, Muir\, D. W.\, Boicou rt\, R. M.\, Kahler\, III\, A. C.\, and Conlin\, J. L. The njoy nuclear da ta processing system\, version 2016. Los Alamos National Laboratory report LAUR-17-20093 (2017).\n[2] Cai\, X.-X.\, and Kittelmann\, T. Ncrystal: A library for thermal neutron\ntransport. Computer Physics Communications 24 6 (2020)\, 106851.\n[3] Romanelli\, G.\, Onorati\, D.\, Ulpiani\, P.\, Can celli\, S.\, PerelliCippo\, E.\, Damián\, J. I. M.\, Capelli\, S. C.\, Cr oci\, G.\, Muraro\, A.\, Tardocchi\, M.\, Gorini\, G.\, Andreani\, C.\, an d Senesi\, R. Thermal neutron cross sections of amino acids\nfrom average contributions of functional groups. Journal of Physics: Condensed\nMatter 33\, 28 (may 2021)\, 285901.\n[4] Robledo\, J.\, Dawidowski\, J.\, Damián \, J. M.\, Skoro\, G.\, Bovo\, C.\, and Romanelli\, G. Measurement of neut ron total cross sections at the vesuvio spectrometer. Nucl. Instrum. Metho ds Phys. Res.\, Sect. A 969 (2020)\, 164096.\n\nhttps://indico.frib.msu.ed u/event/52/contributions/934/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/934/ END:VEVENT BEGIN:VEVENT SUMMARY:Development of thermal scattering kernels for sodium hydroxide DTSTART:20220728T133600Z DTEND:20220728T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-936@indico.frib.msu.edu DESCRIPTION:Speakers: Esben Klinkby (Seaborg Technologies)\n\nIn recent ye ars\, molten salt reactor (MSR) concepts have seen renewed interest both w ithin academia and emerging industry. Several widespread reactor concepts are developed\, sharing the feature that the fissile fuel is dissolved in a molten fluoride or chloride salt which remains liquid over a wide temper ature range at atmospheric pressure. One of the attractive features of MSR s is precisely that high pressure is avoided\, thereby eliminating a rang e of possible accident scenarios. Combining this with the fuel salt fissio n product retention properties and the ability to do online fission produc t processing\, paves the way for a completely different safety case for MS R concepts with respect to conventional reactors\, allowing significant sa vings on construction costs.\nThe MSR concept is not new. Two reactors wer e built and operated at ORNL in the 50’ies and 60’ies\, but the techno logy never matured into commercial reactors. Though generally successful a ccording to assessment reports\, the operation of these reactors did ident ify several challenges [1]. Among the more concerning were (irradiation as sisted) corrosion issues of the structural material\, while another relate s to the mechanical and moderation properties of the graphite moderator un der irradiation [2].\nAlthough significant efforts have been made\, the is sues relating to the graphite behaviour under irradiation have not been re solved during the half century that has passed. At present\, some MSR deve lopers are focusing their research on solving this issue [3]\, while other s plan frequent replacements of the core\, to limit irradiation damage [4] .\nAt Seaborg Technologies\, a Danish based MSR developer\, a different pa th is chosen\, namely to replace the graphite moderator with sodium hydrox ide (NaOH) [5].\nWhile this introduces several complications relating to c orrosion and chemistry control\, it does also promise several benefits. Du ring operation of the reactor\, the NaOH would be liquid\, thus eliminatin g issues relating to radiation damage. Additionally\, due to the presence of hydrogen\, the moderation power is significant allowing for a compact c ore design\, which is essential for the assembly line based deployment and central to Seaborg’s business case.\nAnother challenge following the us e of sodium hydroxide relates to the fact that only limited past experienc e is available in the literature [6]. Although the interactions of neutron s with materials can be reliably predicted using Monte-Carlo techniques fo r energetic neutrons using nuclear data per nuclide\, in the thermalizatio n regime\, where the neutron kinetic energy approaches the energy levels o f the molecules of the moderator\, molecular levels need to be considered. \n To facilitate the usage of NaOH as a moderator\, the modelling must be supplemented with thermal scattering kernels describing interactions betwe en neutrons and NaOH in the thermal regime. The development of such scatte ring kernels relies on experiments as well as modeling and will be describ ed in detail in this conference contribution. The outline is as follows:\n Using the pulsed neutron beam available at the ISIS Pulsed Neutron and Muo n Source\, at the Rutherford Appleton Laboratory (UK)\, it is possible to determine total cross sections as a function of the energy using the time- of-flight (TOF) technique and over a wide range of energies. For the prese nt work\, we carried out experiments in May 2020 using the VESUVIO beamlin e - see figure below\, a neutron spectrometer optimized for the routine me asurement of the total cross sections over a broad energy range [7\,8]. \n A sample of 8.47g of NaOH at room temperature was prepared [9]\, and place d centrally in the neutron beam. To limit multiple scattering and undesire d scattering on the sample container\, the sample was pressed to 1.5 mm th ickness inside a polyethylene bag. \n![enter image description here][1]\n VESUVIO instrument at ISIS [8].\n \nThe incident as well as transmitted be ams were monitored\, allowing the TOF spectrum to be converted into a neut ron energy spectrum\, ranging over several orders of magnitude and coverin g the energy region of interest for thermal scattering kernel development (roughly: 1meV-0.1eV).\nIn the post-processing\, the measured data was nor malized to the well-known epithermal cross-section. The measured results h ave been compared with calculations using NJOY [10] and NCrystal [11]\, be fore making them available for use in modern Monte-Carlo codes\, such as S erpent\, MCNP and OpenMC.\nThe results for the total cross-section of neut rons on solid NaOH at ambient temperatures will be presented along with ex amples of usage in Monte-Carlo reactor modeling.\nIn addition\, the proces s forward for measurements on liquid NaOH at elevated temperatures\, more relevant to reactor operation\, will be described.\n\nReferences:\n[1] P. N. Haubenreich J. R. Engel\, ”Experience with the Molten-Salt Reactor Ex periment”\, Nucl. App. and Tech. Vol 8\, 1970 - Issue 2\, pp 118-136\n[2 ] P. R.Kasten et al\, “Graphite behavior and its effects on MSBR perform ance”\, Nucl. Eng. and Design\, Vol 9\, Issue 2\, (1969)\, pp157-195\n[3 ] G.\, Zhu et al\, “Neutronic effect of graphite dimensional change in a small modular molten salt reactor”\,Int.J of Energy Research — 2020\ , Vol 45\, Issue 8\, pp. 11976-11991\n[4] https://thorconpower.com/ and ht tps://www.terrestrialenergy.com/ are examples. \n[5] Patent WO 2018/229265 Al - “Molten Salt Reactors”\n[6] C.E. Teeter\, et al.. Catalog Of Nuc lear Reactor Concepts. Part I. Homogeneous and Quasi-Homogenous Reactors. Section III. Reactors Fueled With Molten-Salt Solutions. No. ANL-7092. Arg onne National Lab.\, Ill.\, 1965.\n[7] J.I. Robledo\, et al\, “Measureme nt of neutron total cross section at the VESUVIO spectrometer”\, Nucl. I nst. Meth. A\, A 971 (2020) 164096\n[8] https://www.isis.stfc.ac.uk/Pages /Vesuvio.aspx\n[9] Sodium hydroxide white powder 757527 – 25g ultra dry from Sigma Aldrich. https://www.sigmaaldrich.com/GB/en/product/aldrich/75 7527\n[10] R. Macfarlane\, et al. “The NJOY nuclear data processing syst em”\, version 2016. No. LA-UR-17-20093. Los Alamos National Lab.(LANL)\, Los Alamos\, NM (United States)\, 2017.\n[11] XX. Cai\, and T. Kittelmann . "NCrystal: A library for thermal neutron transport." Computer Physics Co mmunications 246 (2020): 106851.\n\n\n [1]: https://www.isis.stfc.ac.uk/G allery/detectors3.png\n\nhttps://indico.frib.msu.edu/event/52/contribution s/936/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/936/ END:VEVENT BEGIN:VEVENT SUMMARY:NCrystal : an open source library for thermal neutron transport DTSTART:20220728T170400Z DTEND:20220728T171600Z DTSTAMP:20260420T153400Z UID:indico-contribution-954@indico.frib.msu.edu DESCRIPTION:Speakers: Thomas Kittelmann (European Spallation Source ERIC)\ n\nInitially born out of the needs of the ESS Detector Group to enhance th e realism of thermal neutron scattering in Geant4-based detector design st udies\, the NCrystal project has grown into a generic backend for such mod elling -- which is both flexible\, efficient\, and available under a liber al open source license. In this contribution we present the project\, incl uding both design philosophy\, an overview of the physics modelling capabi lities of the software\, the material database\, and the current and plann ed possibilities for using it.\n\nFrom the beginning\, the aim has been to provide a common physics modelling engine\, which can then be used either as a standalone toolkit (which includes command-line tools and Python/C++ /C APIs)\, to enable neutron physics in custom domain-specific simulation applications (like ANTS2)\, or as a backend to an existing Monte Carlo cod e like Geant4\, McStas\, or OpenMC. This approach enables collaborators fr om a range of communities to pool their efforts in terms of code developme nt (possibly taking advantage of NCrystal's plugin mechanism)\, physics va lidation\, and material database maintenance. Not only is such a project a n obvious advantage for users of a code like Geant4 where thermal neutron scattering has not traditionally been a strong focus\, but also more neutr on-focused codes like McStas\, OpenMC\, or even MCNP\, are able to benefit from the physics models and material database of NCrystal. In addition t o discussing the physics capabilities\, we will accordingly also provide a n overview of the various options for deploying and accessing NCrystal. As part of this overview\, we will discuss efforts to expand these options f urther\, in particular to traditional nuclear radiation codes via direct h ooks or through conversions to existing formats (e.g. ENDF) via the NJOY-N Crystal project.\n\nThe physics capacity of the software currently include s modelling of both elastic (Bragg diffraction and incoherent-elastic) and inelastic scattering components\, and supports materials which are crysta lline solids (isotropic or single-crystal including HOPG)\, amorphous soli ds\, or even liquids. Multiphase materials and related effects (SANS) are also supported. We will discuss how materials are mostly defined in terms of crystal structure and/or phonon density distributions\, and how the eve r growing NCrystal Data Library provides an unusually large number (>130) of relevant and validated material definitions for users to access out of the box. Notably\, the focus on computational efficiency in all code\, mea ns that this large amount of material definitions is provided without the need for pre-processing of data\, and the associated hassle of large stora ge requirements normally associated with thermal scattering libraries. Ins tead\, derived data such as inelastic scattering kernels or lists of Bragg reflection planes\, are calculated automatically on-the-fly at initialisa tion time with highly optimised algorithms (~100ms/material)\, from the pr ovided phonon density of state curves and crystal structures. Finally\, we will also discuss the universal configuration mechanism of NCrystal\, whi ch aims to enable users to reliably configure a material in a consistent f ashion across the different codes and APIs.\n\nNCrystal is currently heavi ly used at the European Spallation Source ESS\, in particular when it come s to the design of moderators\, beam extraction\, and detector systems\, a nd the development has been supported by the European Union’s Horizon 20 20 research and innovation programme under grant agreement No 676548 (the BrightnESS project) and 951782 (the HighNESS project).\n\nhttps://indico.f rib.msu.edu/event/52/contributions/954/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/954/ END:VEVENT BEGIN:VEVENT SUMMARY:Evaluation of Uranium Carbide Thermal Scattering Law and Cross Sec tions DTSTART:20220728T140000Z DTEND:20220728T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-938@indico.frib.msu.edu DESCRIPTION:Speakers: Jonathan P. W. Crozier (North Carolina State Univers ity)\, Ayman I. Hawari (North Carolina State University)\n\nUranium Carbid e (UC) is a nuclear fuel material\, whose crystal binding may affect doppl er broadening of epithermal neutron absorption resonances and scattering b ehavior of thermal neutrons. Currently\, there is no Thermal Scattering La w (TSL) evaluation for UC in the ENDF/B-VIII.0 database. Ab-initio lattice dynamics (AILD) techniques are used to calculate the phonon spectrum usin g spin-orbit-coupling density functional theory (DFT). The present evaluat ion details TSL production for Uranium and Carbon in UC\, and generates th e thermal neutron scattering cross sections. \n\nThe thermal neutron de-Br oglie wavelength is on the order of magnitude of inter-atomic spacing and its energy is on the order of magnitude of lattice vibrations. The thermal scattering interactions in a crystalline material are therefore a functio n of its structure and vibrational state availability. In inelastic scatte ring\, energy can be exchanged between a neutron and the atomic lattice th rough the absorption and emission of elementary excitations (phonons)\, an d elastic scattering occurs at Bragg edges. The incoherent inelastic cross section is therefore calculated with a phonon expansion in the harmonic a pproximation and the coherent elastic double differential cross section is calculated as a function of the atomic structure factor in the cubic appr oximation. Bose-Einstein statistics determine availability of lattice vibr ations.\n\nUC has a rock-salt crystal structure with Fm-3m symmetry (space group 225)\, and paramagnetic structure at room temperature. At low tempe ratures\, both semi-itinerant bonding and AFM-I ordering of 5$f$ electrons exists. Capturing the magnetic orientation of adjacent Uranium atoms redu ces unit cell structure to tetragonal P4mmm symmetry (space group 123). El ectronic structure minimizations in the AFM ground state were conducted us ing VASP DFT code. These spin-orbit-coupling (SOC) calculations used PAW p seudo-potentials with the GGA-PBE-sol exchange-correlation functional edit ed for bulk materials\, a plane wave-cutoff of 500 eV and 8x8x8 Monkhorst- Pack k-mesh. 1${}^{st}$ order Methfessel-Paxton smearing with a width 0.2 eV was used\, and a moderate effective Hubbard value (U - J) of 1.9 eV con trolled the degree of itineracy of the 5$f$ Uranium electrons. These param eters ensured that the ground state energy and volume were converged to be low 5 meV/atom and 0.1%\, respectively. These 2x2x2 cubic supercell calcul ations (4x4x4 k-mesh\, 64 atom) displaced non-equivalent U and C atom site s 0.02 angstrom in $\\mathrm{\\pm}$ X-direction. The isotropic PM phase is approximated by averaging Hellman-Feynman forces for AFM magnetic orienta tion in planes perpendicular (001) and parallel (100) to the direction of atomic displacement with (2/3) and (1/3) weights\, respectively.\n\nPhonon dispersion relations and phonon DOS were generated in the PHONON code\, a s a function of the generated Hellman-Feynman Forces. The partial DOS for Carbon and Uranium were processed in $FLASSH$ to generate their TSL\, inco herent inelastic\, and coherent elastic cross section data. The generalize d DOS is constructed by neutron-weighting partial DOS. These calculations assume isotropic compositions of U and C. The free atom cross section and mass are those which correspond to current ENDF evaluations. The total sc attering cross section is composed of inelastic and elastic scattering fro m both U and C. The total cross section for UC is compares favorably to ex perimental transmission data after accounting for the absorption cross sec tion of Carbon\, U-235 and U-238.\n\nhttps://indico.frib.msu.edu/event/52/ contributions/938/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/938/ END:VEVENT BEGIN:VEVENT SUMMARY:Effects of Hydrogen Bonding on Nuclear Data Development of Liquid Anhydrous HF DTSTART:20220728T141200Z DTEND:20220728T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-940@indico.frib.msu.edu DESCRIPTION:Speakers: Ayman Hawari\, Tanvir Ahmed (Department of Nuclear E ngineering\, North Carolina State University)\, N. Colby Fleming (Departme nt of Nuclear Engineering\, North Carolina State University)\n\nHydrogen f luoride (HF) is a material commonly used in nuclear fuel processing and ma nufacturing. As HF is commonly used directly in conjunction with various f orms of uranium\, an accurate representation of the thermal cross sections is vital to criticality safety. To generate the thermal scattering cross sections for HF\, a classical molecular dynamics (MD) simulation of the fl exible HF system was developed. The first\, two-site model was developed u sing the LAMMPS simulation package. LAMMPS however is unable to capture th e HF-HF interactions that result from intermolecular hydrogen bonding. The refore\, a second\, three-site model was developed in GROMACS (GROningen M Achine for Chemical Simulations) to accurately capture the intermolecular effects. The hydrogen bonds were treated in MD by attaching a massless cha rge to a dummy site within the molecule. Liquid anhydrous HF was then simu lated across typical temperatures and pressures.\n\nIn LAMMPS\, a traditio nal two-site model with 4096 molecules was developed using a newly reparam etrized potential with the addition of 12-6 Lennard Jones (LJ)\, Coulombic \, and bond potential term between the hydrogen and fluorine atoms. The sy stem was equilibrated for 200\,000 timesteps (0.1 fs timesteps) using NPT. After equilibration\, an additional 2000 loops of 5000 fs were calculated to generate the diffusional coefficient and normalized velocity autocorre lation function (VACF). \n\nIn order to capture the HF-HF intermolecular b onding\, a three-site model of liquid anhydrous HF was developed for high temperature and pressure and implemented in the GROMACS simulation. For th is model\, the initial structure of 1000 molecules was produced using ffto ol and PACMOL. Both the Nose-Hoover thermostat and the Parrinello-Rahman b arostat were applied. At 0.90 nm\, the Lennard-Jones interactions were ter minated\, and the long-range electrostatic forces were calculated using th e particle mesh Ewald technique. Initially\, the system was equilibrated f or 1000 ps using a 0.01 fs timestep. After the equilibration\, the liquid HF system was simulated for a total of 2500 ps. The 2500 ps was split into 500 loops (5 ps each) to find the exact time-averaged normalized VACF. \n \nFrom these two models\, key parameters were compared against experimenta l data to validate the methodology and models. The bond length of hydrogen and fluorine atoms\, potential energy\, diffusion coefficient\, and densi ty were used to benchmark the model before producing the normalized VACF. \n\nThe phonon DOSs for both cases were then calculated as the Fourier tra nsform of the normalized VACF. These DOSs were then used as the primary in put for the evaluation of two thermal scattering laws (TSL\, i.e. S($\\alp ha$\,$\\beta$)) and associated neutron thermal scattering cross sections f or hydrogen in HF. The TSLs were analyzed using the Full Law Analysis Scat tering System Hub (*FLASSH*) using the Schofield diffusional model. The in clusion of the hydrogen bonding results in significant change to the diffu sional contributions of the TSL. This is reflected in the low energy cross section where the inclusions of the HF-HF intermolecular binding effects significantly shifts the scattering cross section.\n\nhttps://indico.frib. msu.edu/event/52/contributions/940/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/940/ END:VEVENT BEGIN:VEVENT SUMMARY:Where Could Compensating Errors Hide in ENDF/B-VIII.0? DTSTART:20220725T184500Z DTEND:20220725T190900Z DTSTAMP:20260420T153400Z UID:indico-contribution-771@indico.frib.msu.edu DESCRIPTION:Speakers: Denise Neudecker\n\n**LA-UR-21-29134**\n\n\nIt is a well-known fact that our current nuclear data libraries\, among them ENDF/ B-VIII.0 [1] in the US\, are home to compensating errors that lurk in unco nstrained physics spaces [2]. Unconstrained physics spaces arise\, on the one hand\, due to differential information (from theory and experiments) t hat is too imprecise to fully describe nuclear data. One the other\, this is combined with validating combinations of nuclear data with integral exp eriments cannot uniquely identify one nuclear data value as driving the di fference between simulated and experimental values of these experiments. I f we knew where these unconstrained physics spaces occur in nuclear data l ibraries\, we could either build targeted experiments or propose theory de velopments that help to shine a light on them and\, thus\, reduce the poss ibility of compensating errors.\n\nThe EUCLID project (Experiments Underpi nned by Computational Learning for Improvements in Nuclear Data) developed a work-flow [3] that identifies these unconstrained physics spaces by bri nging together various experimental values of integral responses (critical ity\, $\\beta_\\mathrm{eff}$\, reaction rates in critical assemblies\, LLN L pulsed spheres neutron-leakage spectra\, reactivity coefficients and sub -critical assembly observables) with their simulated counter-parts as well as differential information. This wealth of information is processed by m achine learning tools supported by the random forest algorithms and analyz ed by human experts [4]. Here\, we will show how this work-flow is execute d and a few representative examples of where compensating errors could pot entially hide in ENDF/B-VIII.0. \n\n**Acknowledgments**\nResearch reported in this publication was supported by the U.S. Department of Energy LDRD p rogram at Los Alamos National Laboratory. This work was supported by the US Department of Energy through the Los Alamos National Laboratory. Los Al amos National Laboratory is operated by Triad National Security\, LLC\, fo r the National Nuclear Security Administration of the US Department of Ene rgy under Contract No. 89233218CNA000001.\n\n\n[1] D.A. Brown\, M.B. Chadw ick\, R. Capote et al.\,ENDF/B-VIII.0: The 8th Major Release of the Nuclea r Reaction Data Library with CIELO-project Cross Sections\, New Standards and Thermal Scattering Data\,Nucl. Data Sheets 148\, 1 (2018).\n[2] E. Bau ge\, G. Belier\, J. Cartier et al.\, Coherent Investigation of Nuclear Dat a at CEA DAM: Theoretical Models\, Experiments and Evaluated Data\, The Eu ropean Physical Journal A 48\, 113 (2012).\n[3] D. Neudecker\, O. Cabellos \, A.R. Clark et al.\, Informing Nuclear Physics via Machine Learning Meth ods with Differential and Integral Experiments\, Phys. Rev. C 104\, 034611 (2021).\n[4] D. Neudecker\, M. Grosskopf\, M. Herman et al.\, Enhancing N uclear Data Validation Analysis by Using Machine Learning\, Nucl. Data She et 167\, 36 (2021).\n\nhttps://indico.frib.msu.edu/event/52/contributions/ 771/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/771/ END:VEVENT BEGIN:VEVENT SUMMARY:140\,142Ce Neutron Cross Section Resolved Resonance Region Evaluat ion DTSTART:20220725T193300Z DTEND:20220725T194500Z DTSTAMP:20260420T153400Z UID:indico-contribution-684@indico.frib.msu.edu DESCRIPTION:Speakers: Chris Chapman (Oak Ridge National Laboratory)\n\nA r esolved resonance region evaluation of 140\,142Ce has been carried out by Oak Ridge National Laboratory. Requested by the US Nuclear Criticality Saf ety Program\, this evaluation is based on recent high-resolution transmiss ion and capture high-resolution measurements of natCe and 142Ce conducted at JRC-GEEL at the Geel Linear Accelerator facility\, as well as recently measured thermal constants available from the EXFOR database [1]. Starting from the resonance parameters from the ENDF/B-VIII.0 library [2] and foll owing a preliminary R-matrix analysis [3]\, an updated set of resonance pa rameters and corresponding covariance information was derived by the fit o f these experimental datasets using the Reich-Moore approximation of the R -matrix theory as implemented in the SAMMY code system [4]. The resolved r esonance region upper energy limit for 140Ce was kept at 200 keV while the 142Ce resonance region was extended from 13 to 26 keV. This new evaluatio n was found to be in good agreement not only with several integral quantit ies of interest to the reactor physics community\, but also with the stell ar Maxwellian-averaged cross section [5].\n\nAcknowledgments\n\nThis work was supported by the U.S. Department of Energy (DOE) Nuclear Criticality S afety Program\, which is funded and managed by the National Nuclear Securi ty Administration for DOE.\n\n* This manuscript has been authored by UT-Ba ttelle\, LLC\, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher\, by accepting t he article for publication\, acknowledges that the US government retains a nonexclusive\, paid-up\, irrevocable\, worldwide license to publish or re produce the published form of this manuscript\, or allow others to do so\, for US government purposes. DOE will provide public access to these resul ts of federally sponsored research in accordance with the DOE Public Acces s Plan (http://energy.gov/downloads/doe-public-access-plan).}\n\n\nReferen ces\n\n[1] V. V. Zerkin\, B. Pritychenko\, “The experimental nuclear rea ction data (EXFOR): Extended computer database and Web retrieval system\, ” Nuclear Instruments and Methods in Physics Research Section A: Acceler ators\, Spectrometers\, Detectors and Associated Equipment\, 888\, pp. 31- 43 (2018).\n[2] D. A. Brown et al\, “ENDF/B-VIII.0: The 8th Major Releas e of the Nuclear Reaction Data Library with CIELO-project Cross Sections\, New Standards and Thermal Scattering Data\,” Nuclear Data Sheets\, 148\ , pp. 1-142 (2018).\n[3] C. W. Chapman\, M. T. Pigni\, K. Guber\, “Progr ess on 140\,142Ce Neutron Cross Section Resolved Resonance Region Evaluati ons\,” ICNC2019-11th International Conference on Nuclear Criticality Saf ety\, 15-20 September 2019 - Paris\, France.\n[4] N. M. Larson\, “Update d user’s guide for Sammy: Multilevel R-matrix fits to neutron data usin g Bayes’ equations\,” Tech. Rep. ORNL/TM-9179/R8\, ENDF-364/R2\, Oak R idge National Laboratory (2008).\n[5] B. Pritychenko\, S. F. Mughabghab\, “Neutron Thermal Cross Sections\, Westcott Factors\, Resonance Integrals \, Maxwellian Averaged Cross Sections and Astrophysical Reaction Rates Cal culated from the ENDF/B-VII.1\, JEFF-3.1.2\, JENDL-4.0\, ROSFOND-2010\, CE NDL-3.1 and EAF-2010 Evaluated Data Libraries\,” Nuclear Data Sheets\, 1 13\, pp. 3120-3144 (2012).\n\nhttps://indico.frib.msu.edu/event/52/contrib utions/684/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/684/ END:VEVENT BEGIN:VEVENT SUMMARY:Total absorption beta decay studies for reactor decay heat calcula tions DTSTART:20220725T190900Z DTEND:20220725T192100Z DTSTAMP:20260420T153400Z UID:indico-contribution-679@indico.frib.msu.edu DESCRIPTION:Speakers: A Algora (1) Instituto de Física Corpuscular\, CSIC -Univ. de Valencia\, E-46071 Valencia\, Spain)\n\nA. Algora1\,2\, V. Guadi lla3\, J. L. Tain1\, M. Fallot4\, M. Estienne4\, A. Porta4\, L. Giot4\, L. Le Meur4\, A. Beloeuvre et al. for the DTAS Jyvaskyla Collaboration\n\n1 )Instituto de Física Corpuscular\, CSIC-Univ. de Valencia\, E-46071 Valen cia\, Spain\n2)Institute of Nuclear Research (ATOMKI)\, P.O. Box 51\, H-40 01 Debrecen\, Hungary\n3)Faculty of Physics\, University of Warsaw\, 02-09 3\, Warsaw\, Poland\n4)Subatech\, IMT-Atlantique\, Univ. de Nantes\, CNRS- IN2P3\, F-44307\, Nantes\, France\n\n\nTotal absorption spectroscopy provi des beta decay data free from the Pandemonium systematic error [1-3]. Avoi ding this systematic error is of great relevance for nuclear structure\, a strophysics and practical applications [3]. \n\nIn this contribution we wi ll present an overview of recent results from the research work performed by our collaboration employing this technique\, which is relevant for reac tor applications\, in particular for decay heat summation calculations. Th e measurements\, we are presenting here\, have been performed at the Unive rsity of Jyväskylä IGISOL IV Facility [4] using trap-assisted spectrosco py that provided radioactive beams of very high isotopic purity [5].\n\nIn this presentation we will emphasize mainly on highlights coming from our experimental campaign performed in 2014 [6-10] where special emphasis was devoted to cases that required isomeric separation [8]. This data has been shown to be of relevance in calculations of the decay heat and in calcula tions of the antineutrino spectrum from reactors [3\,11]. The impact of th e new results in nuclear structure and astrophysics will also be discussed . Some of the studied cases are beta delayed neutron emitters\, for which gamma competition above the neutron separation energy has been determined [9]. In the framework of these analyses a new procedure to determine groun d state to ground state feedings has also been introduced [10]. \n\nThe im pact of all the measurements performed until know by our collaboration for reactor decay heat calculations will be also discussed [12-16] and future perspectives presented. \n\n\n[1] J. C. Hardy et. al.\, Phys. Lett. B 71\ , 307 (1977) \n[2] B. Rubio et al.\, Journal of Physics G: Nuclear and Par ticle Physics 31\, S1477 (2005)\n[3] A. Algora et al.\, Eur. Phys. J. A 57 \, 85 (2021)\n[4] I. D. Moore et al.\, Nucl. Instrum. and Methods B 317\,2 08 (2013)\n[5] T. Eronen et al.\, Eur. Phys. J. A 48\, 46 (2012)\n[6] V. G uadilla\, PhD Thesis\, Univ. of Valencia\, Spain\, (2017)\n[7] L. Lemeur\, PhD Thesis\, Univ. of Nantes\, France\, (2018)\n[8] V. Guadilla et al.\, Phys. Rev. Lett. 122\, 042502 (2019)\n[9] V. Guadilla et al.\, Phys. Rev. C 100\, 044305 (2019)\n[10] V. Guadilla et al\, Phys. Rev. C 102\, 064304 (2020)\n[11] M. Estienne et al.\, Phys. Rev. Lett. 123\, 022502 (2019)\n[1 2] A. Algora et al.\, Phys. Rev. Lett. 105\, 202501 (2010)\n[13] D. Jordan et al.\, Phys. Rev. C 87\, 044318 (2013)\n[14] A. A. Zakari-Issoufou et a l.\, Phys. Rev. Lett. 115\, 102503 (2015)\n[15] J. L. Tain et al.\, Phys. Rev. Lett. 115\, 062502 (2015)\n[16] E. Valencia et al.\, Phys. Rev. C 95\ , 024320 (2017)\n[17] S. Rice et al.\, Phys. Rev. C 96\, 014320 (2017)\n[ 18] V. Guadilla et al.\, Phys. Rev. C C 100\, 024311 (2019)\n\nhttps://in dico.frib.msu.edu/event/52/contributions/679/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/679/ END:VEVENT BEGIN:VEVENT SUMMARY:On Systematics of Double-Beta Decay Half Lives DTSTART:20220728T140000Z DTEND:20220728T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-964@indico.frib.msu.edu DESCRIPTION:Speakers: Boris Pritychenko (NNDC\, BNL)\n\nRecommended 2$\\be ta$(2$\\nu$) half-lives and their systematics [1] are examined in the fram ework of a semi-empirical approach. Impacts of nuclear deformation\, trans ition energy\, and forbidden decay on half-live values were observed. Thes e findings were used to predict T$_{1/2}$ for 35 isotopes of interest. Cur rent results are compared with other theoretical and experimental works.\n \n[1] B. Pritychenko\, Nuclear Data Sheets 120\, 102 (2014).\n\nhttps://in dico.frib.msu.edu/event/52/contributions/964/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/964/ END:VEVENT BEGIN:VEVENT SUMMARY:Generating nucleon-nucleus scattering data by Gaussian process reg ression DTSTART:20220728T133600Z DTEND:20220728T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-962@indico.frib.msu.edu DESCRIPTION:Speakers: Shoto Watanabe (Hokkaido University)\n\nhttps://indi co.frib.msu.edu/event/52/contributions/962/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/962/ END:VEVENT BEGIN:VEVENT SUMMARY:Probing Nuclear Uncertainties in Kilonova Modeling DTSTART:20220728T132400Z DTEND:20220728T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-961@indico.frib.msu.edu DESCRIPTION:Speakers: Kelsey Lund (North Carolina State University)\n\nThe rapid neutron capture (r-process) is one of the main mechanisms whereby e lements heavier than iron are synthesized\, and is responsible for the cre ation of the heaviest stable isotopes of the actinides. Kilonova emissions are modeled as being largely powered by the radioactive decay of species synthesized via the r-process and in principle\, observations of these off er insight into nucleosynthetic processes that occur in the merger. Given that the r-process occurs far from nuclear stability\, nucleosynthesis cal culations are subject to large uncertainties from unmeasured quantities. W e investigate these uncertainties by incorporating a variety of different theoretical nuclear physics inputs\, including mass models\, decay rates\, and fission yields\, into nucleosynthesis calculations. We show the range of uncertainty these can generate and show the impact on nuclear heating\ , light curve evolution and nuclear cosmochronometry.\n\nhttps://indico.fr ib.msu.edu/event/52/contributions/961/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/961/ END:VEVENT BEGIN:VEVENT SUMMARY:Proton-induced activation cross sections in the energy range below 10 GeV DTSTART:20220728T191900Z DTEND:20220728T193100Z DTSTAMP:20260420T153400Z UID:indico-contribution-982@indico.frib.msu.edu DESCRIPTION:Speakers: Igor Moskalenko (Stanford University)\n\nModern theo retical studies and industrial applications related to the design\, radiat ion protection\, and reliability of nuclear facilities\, medical applicati ons\, as well as space research and exploration are relying on extensive s imulations and modeling. Computer codes realizing various semi-classical a nd quantum molecular dynamics (QMD) approaches are often employed to make up for the lack of accelerator data on many nuclear reactions at intermedi ate and high energies (above 10s of MeV per nucleon) and are in high deman d nowadays. \n\nThis contribution focuses on the methodology of generating reliable proton-induced cross section data on $^{56}$Fe nucleus required for activation analysis and other applications in the energy range below 1 0 GeV. We developed a problem-oriented computer framework based on MCNPX [ 1] and CASCADE/INPE [2] codes to calculate activation cross section data a t intermediate and high energies. Goodness of the fits of nucleon-nucleus interaction models to the existing data is evaluated based on elaborated a lgorithms. The method is based on the analysis of a large set of experimen tal data and calculated cross sections for $^{56}$Fe and different residua l nuclei in a wide range of energies of incident protons using numerous co incidence criteria.\n\nIn practice\, this could be done in different ways. One way is tuning the model parameters and algorithms to fit required exp erimental data subset. Another way is to try to achieve unification and co nsistency of fundamental parameters for all considered reactions. The pres ented framework is pursuing the latter approach. We use proton-induced rea ctions on $^{56}$Fe nucleus to illustrate the application of the developed multi-criteria algorithm\, where we use all reaction cross section data b elow 10 GeV available from the EXFOR experimental data library and the IAE A CRP "Benchmark of Spallation Models." We demonstrate that the analysis o f the predictive power of various intermediate and high-energy models base d on the multi-criteria algorithm allows more sophisticated selection of a ppropriate models in a given energy range and target nuclei domain.\n\nThe major obstacle in improving an accuracy of the nuclear codes is the scarc ity of the available measurements. We are aiming at using the NICA facilit y (Nuclotron-based Ion Collider fAcility) [3] – a new accelerator comple x at the Joint Institute for Nuclear Research (JINR\, Dubna\, Russia). NIC A will provide variety of beam species from p to Au ions. Heavy ions will be accelerated up to kinetic energy of 4.5 GeV/nucleon\, protons – up to 12.6 GeV. \n\nMeasurements of the isotopic cross sections will be conduct ed using proton and ion beams and thin targets. Besides\, NICA can be used for studies of secondary neutron and γ-ray emission – of interest for simulations of the radiation environment at the rocky surfaces of planets and asteroids. New data will be used to tune models of nuclear reactions a nd for astrophysical applications.\n\nAcknowledgements: IVM acknowledges s upport from NASA grant No. NNX17AB48G.\n\nReferences:\n[1] D. B. Pelowitz\ , et al.\, "MCNPX 2.7.0 Extensions"\, LA-UR-11-02295 (2011).\n[2] V.S. Bar ashenkov\, A.Y. Konobeyev\, Y.A. Korovin\, V.N. Sosnin\, At. Energy 87 (4) (1999) 742.\n[3] E.Syresin et al.\, NICA accelerator complex at JINR\, Pro c. IPAC2019\, Melbourne\, Australia\, doi:10.18429/JACoW-IPAC2019-MOPMP01\ ; https://nica.jinr.ru/\n\nhttps://indico.frib.msu.edu/event/52/contributi ons/982/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/982/ END:VEVENT BEGIN:VEVENT SUMMARY:Residual nuclei production in (p\,π$^0$γ) reaction DTSTART:20220727T183600Z DTEND:20220727T184800Z DTSTAMP:20260420T153400Z UID:indico-contribution-958@indico.frib.msu.edu DESCRIPTION:Speakers: Igor Moskalenko (Stanford University)\n\nA series of benchmark experiments with thin targets was carried out at ITEP in 1994 - 2009 in support of subcritical systems with an external neutron source (A ccelerator Driven Systems\, ADS) [1-3].\n\nThe cross sections for the for mation of residual products of nuclear reactions were determined by the ac tivation method ͟using precision γ-spectrometry. Thin samples made of ma terial considered for ADS target and structures (Ø 10.5 mm\, 0.1 - 2 mm t hick) were irradiated with protons in the energy range 40 - 2600 MeV. More than 14500 residual nuclei production cross sections were measured\, with a half-life from 6.56 m ($^{29}$Al) to 52.5×10$^3$ y ($^{202}$Pb). A com plete list of target nuclei and energies is presented in Table 1.\n\n\n\n\ n\n\n\n\n\n\n\n\nThe data obtained were added to the EXFOR database and us ed to verify nuclear models. Investigations of irradiated lead targets are ongoing with \, an ultra-low-background GeTHU spectrometer from China's J ing-Pin underground laboratory [4].\n\nAnalysis of the latest results made it possible to identify the poorly studied process in which the reaction products are formed as a result of the reaction (p\,π$^0$γ). This report presents the experimental and calculated excitation functions for only tw o residual nuclei $^{56}$Fe(p\,π$^0$γ)$^{57}$Co and $^{206}$Pb (p\,π$^0 $γ)$^{207}$Bi [2\,3\,5]. A third reaction with a similar formation channe l of $^{232}$Th(p\,π$^0$γ)$^{233}$Pa was also identified\, but since $^{ 233}$Pa was also formed through another formation channel\, $^{232}$Th(n\, γ)$^{233}$Th(β$^-$)\, it was not considered in this work [1].\n\nCompari son of the experimental and simulated results of the first two reactions s howed their significant discrepancy. Therefore\, an analysis was performed of target nuclei in which this reaction can be recorded and\, accordingly \, their cross sections can be measured. An important outcome is that the list of target nuclei for determining experimental excitation functions ca n be extended to 148 items (targets). Such a large number is due to the ne ed to use targets highly enriched in target isotope. A set of experimental excitation functions will help to understand the discrepancy between meas urements and simulations and\, accordingly\, lead to improvements in moder n high-energy transport models used in various fields of physics\, includi ng astrophysical applications.\n\nThe research was carried out with financ ial support of the Russian Foundation for Basic Research (RFBR) and the Na tional Natural Science Foundation of China (NSFC) in the framework of scie ntific projects #20-52-53021 and #12011530057 respectively\, as well as Fr amework agreement for cooperation between NRC ‘‘Kurchatov Institute’ ’ - ITEP\, Russia and Belgian Nuclear Research Center SCK CEN\, Belgium # CO-90-06-1988-03.\n \nReferences\n1. Yu.E. Titarenko et. al.\, Experime ntal and Theoretical Study of the Yields of Residual Product Nuclei in Thi n Targets Irradiated by 100 – 2600 MeV Protons\, IAEA\, Nuclear Data Sec tion\, Wagramer Strasse 5\, A-1400 Vienna\, INDC(CCP)-434\, September 2002 \, pp. 1–319\, https://www-nds.iaea.org/publications/indc/indc-ccp-0434/ .\n2. Yu. E. Titarenko et. al.\, Experimental and Theoretical Studies of the Yields of Residual Product Nuclei Produced in Thin Pb and Bi Targets I rradiated by 40 – 2600 MeV. Wagramer Strasse 5\, A-1400 Vienna\, INDC(C CP)-0447\, October 2009\, pp. 1–692\, https://www-nds.iaea.org/publicati ons/indc/indc-ccp-0447/.\n3. Yu.E. Titarenko et. al.\, Experimental and th eoretical study of the residual nuclide production in 40 - 2600 MeV proton -irradiated thin targets of ads structure materials. IAEA\, Nuclear Data S ection\, Wagramer Strasse 5\, A-1400 Vienna\, INDC(CCP)-0453\, IAEA\, Oct ober 2009\, https://www-nds.iaea.org/publications/indc/indc-ccp-0453/.\n4. Zhi Zeng\, et. al.\, The characteristics of a low background germanium ga mma ray spectrometer at China JinPing underground laboratory\, Applied rad iation and isotopes\, 91 (2014) 165–170\, ttps://doi.org/10.1016/j.aprad iso.2014.05.022.\n5. Yu.E. Titarenko\, et. al.\, 208\,207\,206\,natPb(p\ ,x)207Bi and 209Bi (p\,x)207Bi excitation functions in the energy range of 0.04 - 2.6 GeV\, Nucl. Instrum. Methods\, A 984 (2020) 164635\, https://d oi.org/10.1016/j.nima.2020.164635.\n\nhttps://indico.frib.msu.edu/event/52 /contributions/958/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/958/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Using benchmark similarity for more granular validatio n of nuclear data DTSTART:20220727T155700Z DTEND:20220727T160900Z DTSTAMP:20260420T153400Z UID:indico-contribution-998@indico.frib.msu.edu DESCRIPTION:Speakers: Wim Haeck (LANL)\n\nA set of Python tools useful for benchmarking\, benchmark selection\, nuclear data validation\, and nuclea r data evaluation support called Faust is currently under development at L os Alamos National Laboratory. The goals and objectives for Faust are to:\ n- Provide input and output processing for different calculation codes\n- Allow for exchanging results between different applications and codes\n- R un benchmarks and process the results\n- Automate and simplify plotting an d report generation\n- Provide a basis for developing applications useful for nuclear data evaluators\n\nFaust now includes tools to assess similari ties (or similarity coefficients) between benchmarks using precalculated s ensitivity profiles. This new features is the subject of the present contr ibution.\n\nSensitivity profiles indicate by how much a given observable ( or response) will change following a change in a specific parameter. These sensitivity profiles are used in various applications. They are for insta nce used as input in error propagation of nuclear data for application by folding them with covariance matrices using the Sandwich rule [A]. Another use of these sensitivities is to calculate the impact of a nuclear data c hange on the values of the associated observables - as long as that change is small enough so that linear perturbation theory still applies [B]. In this paper\, we will explore the use of sensitivity profiles for assessing the similarity of benchmarks in benchmark selection.\n\nWhen performing n uclear data validation and testing during evaluation work\, we prefer to w ork with a small set of benchmarks. The benchmarks in this set should be t he most diverse (or dissimilar) ones we can find. They should also represe nt the highest sensitivity to the nuclide or nuclides being considered in the evaluation work.\n\nSimilarity between two benchmarks can be assessed in many different ways\, depending on how similarity is defined. For insta nce\, one can argue that two criticality benchmarks are similar to one ano ther when they have roughly the same neutron spectrum. In this case\, the similarity is assessed based on the average system behavior defined by the neutron spectrum.\n\nSensitivity profiles offer another way of assessing a similarity between benchmarks. Sensitivity profiles tell us what the imp act is of a given change in a nuclear data parameter (such as a cross sect ion in a specific energy region) on the observable (such as an effective m ultiplication factor). When the shape of a sensitivity profile for two dif ferent benchmark is the same\, then the impact of a change in the associat ed parameter will be the same as well. This feature can be used to define a similarity coefficient.\n\nOne way to assess this is by looking at the s ensitivity profiles as if they are vectors in an n-dimensional space. A no rmalized inner product between such vectors will tell us how well aligned they are with one another\, and thus provide a measure of similarity betwe en two benchmarks. This can be calculated for a single profile\, or for a previously selected set of profiles for different nuclides and/or reaction s. In this last case\, the profiles need to be sorted by nuclide and react ion first.\n\nIn this contribution we investigate the possibility of using sensitivity profiles for a series of very similar criticality benchmarks to obtain a more detailed and more precise insight in the differences betw een transport calculations of effective multiplication factors for these b enchmarks. We’ll show that under certain conditions such information can be obtained without performing actual transport calculations. For example \, the two benchmarks\, MIX-MET-FAST-007-01 and MIX-MET-FAST-007-02\, with similarity coefficient of 0.9975\, MCNP calculates respectively 102 and 5 62 pcm above measured values. The difference between the two biases is th us 460 pcm. A very simple algebraic formula operating on the integrated s ensitivities yields 455 pcm (i.e.\, agrees within ~1% with the MCNP calcul ations). This 455 pcm is partitioned into individual contributions from al l materials/reactions to which the benchmarks are sensitive. \n\nSuch simi larity analysis offers a number of advantages:\n- Ascertain which of the n uclear reactions might be responsible for the bias in the calculation\n- P oint to potential problems with the benchmark if difference in the benchma rk biases cannot be reproduced with reasonable changes in the nuclear data \n- Wisely designed series of experiments may provide stringent constraint s on selected nuclear reactions\n- Precision of the above-mentioned constr aints may be considerably higher than the precision of the benchmarks them selves because by operating on the relative differences most of the source s of systematic uncertainties are eliminated leaving only uncertainties re lated to the change of configuration.\n\nhttps://indico.frib.msu.edu/event /52/contributions/998/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/998/ END:VEVENT BEGIN:VEVENT SUMMARY:Reexamining intermediate resonant structures in the 242Pu fission cross section DTSTART:20220728T174000Z DTEND:20220728T175200Z DTSTAMP:20260420T153400Z UID:indico-contribution-977@indico.frib.msu.edu DESCRIPTION:Speakers: Carole Chatel (CEA)\n\nThe neutron fission cross sec tion of the 242Pu target nucleus is being studied both experimentally and theoretically since at least five decades. Past studies include early meas urements and derived resonance analyses as those by Auchampaugh et al. [1\ ,2] and Weigmann et al. [3] and\, since 2008\, date of a renewed High Prio rity Request List demand according to the fission experimental data\, a ne w series of high-resolution measurements was carried out that started in 2 009 by the comprehensive work by Tovesson et al. [4]. However\, no very sp ecific analysis of the resonant structures observed in the 242Pu fission c ross section was recently performed\; likely because of the fertile charac ter of this nucleus that makes it less important for neutron reactor appli cations. The present talk is revisiting the topic by methodically analyzin g and modeling the observed fluctuations in the fission cross section over the neutron energy range from thermal to 3 MeV. This objective was achiev ed using complementary features of three codes\, meaning the CONRAD code [ 5] offering the capability to treat with a Lorentzian penetrability possib ly observed class-II states in the resolved resonance range\, the TALYS-EC IS06 system [6] of codes (Cadarache version) to treat the unresolved reson ance structures above 1.15 keV in the same spirit and\, finally the combin atorial Quasi-Particle-Vibrational-Rotational Level Density (QPVRLD) metho d [7] implemented in the AVXSF-LNG computer program. The latter approach w as intensively used in this work to simulate the most plausible level dens ities according to the inner and outer fission barriers of the 243Pu compo und nucleus as well as for the density of (class-II) states in the second well of the fission barrier. We will conclude this talk by arguing on a si zeable structure observed around 1.1 MeV neutron energy\, with in particul ar bringing some explanation according to its origin. The Figure 1 display s the modeling dedicated to this broad structure using the TALYS code and QPVR-based level densities using the single-particle orbital database made available by P. Möller [8].\n\n[1] G.F. Auchampaugh\, J.A. Farrell\, D.W . Bergen\, NPA 171\, 31-43 (1971).\n[2] G.F. Auchampaugh\, C.D. Bowman\, P RC 7\, 5\, (1972).\n[3] H. Weigmann\, J.A. Wartena\, C. Bürkholz\, NPA 43 8 333-353 (1985).\n[4] Tovesson et al.\, Phys. Rev. C 79\, 014613 (2009).\ n[5] C. De Saint Jean et al.\, EPJ Nuclear Sci. Technol. 7 10 (2021).\n[6] A.J. Koning and D. Rochman\, Nuclear Data Sheets 113\, Issue 12\, 2841-29 34 (2012).\n[7] O. Bouland\, J.E. Lynn and P. Talou\, Phys. Rev. C 88 0546 12 (2013).\n[8] P. Möller\, private communication (2021).\n\nhttps://indi co.frib.msu.edu/event/52/contributions/977/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/977/ END:VEVENT BEGIN:VEVENT SUMMARY:Role of direct interactions in $(d\,p)$ and $(d\,2p)$ reactions DTSTART:20220728T160200Z DTEND:20220728T161400Z DTSTAMP:20260420T153400Z UID:indico-contribution-971@indico.frib.msu.edu DESCRIPTION:Speakers: Cristian Costache (Horia Hulubei National Institute for Physics and Nuclear Engineering)\, Marilena Avrigeanu (Horia Hulubei N ational Institute for Physics and Nuclear Engineering (IFIN-HH))\, Vlad Av rigeanu\n\n\\documentclass[aps\,prc\,groupedaddress\,amsmath\,amssymb\,12p t\,tightenlines]{revtex4}\n\\usepackage{graphics}\n\\usepackage{longtable} \n\n\\begin{document}\n\n\\title{Role of direct interactions in $(d\,p)$ a nd $(d\,2p)$ reactions}\n\n\\author{M.~Avrigeanu} \\email{marilena.avrigea nu@nipne.ro}\n\\author{C.~Costache}\n\\author{V.~Avrigeanu}\n\n\\affiliati on{Horia Hulubei National Institute for Physics and Nuclear Engineering\, 077125 Bucharest-Magurele\, Romania}\n\n\\maketitle \n%\\begin{abstract}\n {\\bf Abstract} \n\nDeficiencies in describing the elastic and especially the inelastic breakup (BU) motivate the actual full parametrization of the available deuteron data [1] better than TENDL-2017 deuteron sub-library [ 2] based on the widely-used TALYS nuclear model code system [3]. Various m erely phenomenological description of the available direct-reactions (DR) stripping $(d\,p)$ experimental data are also yet adopted [4] while micros copic calculation of inclusive BU and DR cross sections ({\\it e.g.}\, [5\ ,6]) are still numerically tested. On the other hand\, due consideration o f all elastic-breakup (EB)\, breakup-fusion (BF)\, DR\, pre-equilibrium em ission (PE)\, and evaporation from fully equilibrated compound nucleus (CN ) processes ({\\it e.g.}\, [7])\, has been found crucial [8] for a consist ent analysis of the deuteron-reaction data and even high production of pro ton-rich nuclei [9]\, while insufficient treatment and separation between different reaction mechanisms such as DR and BU components [10] may be rel ated to deviations between measurements and advanced surrogate reaction st udies [11].\n\nConsequently\, elastic-scattering analysis for optical-pote ntial validation\, EB and BU parametrization [12\,13] checked by microscop ical Continuum-Discretized Coupled-Channels (CDCC) formalism calculations\ , BF enhancement of various $(d\,x)$ reaction cross sections\, DR results using DWBA spectroscopic factors from data analysis of available particle- emission angular distributions\, as well as PE+CN statistical decay have b een consistently involved within suitable account of all available excitat ion-function data of deuterons up to 60 MeV on $A\\sim$90 nuclei. The same approach being previously involved for similar analysis for the target nu clei $^{27}$Al\, $^{51\,nat}$V\, $^{50\,52\,53\,54\,nat}$Cr\, $^{55}$Mn\, $^{54\,56\,57\,58\,nat}$Fe\, $^{59}$Co\, $^{58\,60\,61\,62\,64\,nat}$Ni\, $^{63\,65\,nat}$Cu\, and $^{93}$Nb ([14] and Refs. therein)\, the BU enhan ced role with the target-nucleus mass/charge increase has been concerned a s well as the BU dominance around the Coulomb barrier for heavy nuclei as\ , {\\it e.g.}\, $^{231}$Pa. \n\nThe overall agreement between the measured data and model calculations validates this theoretical approach while the comparison to the global predictions underlines the effects of overlookin g the BF enhancement as well as the stripping and pick-up processes. This is particularly important for the $(d\,p)$ and $(d\,2p)$ excitation functi ons on target nuclei from $^{27}$Al to $^{100}$Mo\, the stripping and brea kup disregard leading to the apparent discrepancies. In fact\, the dominan t role of the stripping mechanism in $(d\,p)$ reactions is taken by the BF processes for the $(d\,2p)$ reactions\, all of them being of interest for the evaluation of the H production ({\\it e.g.}\, [15]). Actually\, due t o the related predictive power\, update of the theoretical framework of de uteron-nucleus interaction will improve the evaluation predictions for tar get nuclei and incident energies where data are still missing\, but strong ly requested by the current engineering design projects.\n\n%\\end{abstrac t}\n\n\\bigskip\n\n[1] J. Engle {\\it et al.}\, Nuclear Data Sheets {\\bf 155}\, 56 (2019).\n\n[2] A.J. Koning {\\it et al.}\, Nuclear Data Sheets { \\bf 155}\, 1 (2019). \n\n[3] A.J. Koning\, S. Hilaire\, and M. C. Duijves tijn\, http://www.talys.eu/home/\n\n[4] F. T\\' ark\\' anyi {\\it et al.}\ , Eur. Phys. J. A {\\bf 57}\, 21 (2021)\; {\\it ibid.} {\\bf 57}\, 223 (20 21).\n\n[5] Y.S. Neoh {\\it et al.}\, Phys. Rev. C {\\bf 94}\, 044619 (201 6).\n\n[6] K. Ogata and K. Yoshida\, Phys. Rev. C {\\bf 94}\, 051603(R) (2 016).\n\n[7] M. Avrigeanu {\\it et al.}\, Phys. Rev. C {\\bf 89}\, 044613 (2014)\; {\\it ibid.} {\\bf 94}\, 014606 (2016).\n\n[8] V. Jha\, V. Parkar \, and S. Kailas\, Physics Reports {\\bf 845}\, 1 (2020).\n\n[9] H. Wang { \\it et al.}\, Communications Physics {\\bf 2}\, 78 (2019).\n\n[10] M. Avr igeanu and V. Avrigeanu\, J. Phys. Conf. Ser. {\\bf 724}\, 012003 (2016).\ n\n[11] J.J. Cowan {\\it et al.}\, Rev. Mod. Phys. {\\bf 93}\, 015002 (202 1).\n\n[12] M. Avrigeanu {\\it et al.}\, Fus. Eng. Design {\\bf 84}\, 418 (2009).\n\n[13] M. Avrigeanu and V. Avrigeanu\, Phys. Rev. C {\\bf 95}\, 024607 (2017).\n\n[14] M. Avrigeanu {\\it et al.}\, Phys. Rev. C {\\bf 101 }\, 024605 (2020).\n\n[15] N. Zimber {\\it et al.}\, J. Nucl. Mat. {\\bf 5 35}\, 152160 (2020).\n\n\\vspace{1in}\n\\noindent\n{\\it This work has bee n partly supported by Autoritatea Nationala pentru Cercetare Stiintifica ( Project PN-19060102) and carried out within the framework of the EUROfusio n Consortium and has received funding from the Euratom research and traini ng programme 2014-2018 and 2019-2020 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of th e European Commission.}\n\n\\end{document}\n\nhttps://indico.frib.msu.edu/ event/52/contributions/971/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/971/ END:VEVENT BEGIN:VEVENT SUMMARY:Recent developments in the Point Wise Neutron treatment for FLUKA v4 DTSTART:20220728T183000Z DTEND:20220728T184200Z DTSTAMP:20260420T153400Z UID:indico-contribution-978@indico.frib.msu.edu DESCRIPTION:Speakers: Vasilis Vlachoudis (CERN)\n\nFLUKA [1\,2\,3] is a mu ltipurpose Monte Carlo code for the simulation of particle transport and i nteraction with matter. FLUKA relies on dedicated models for hadronic inte ractions\, with the notable exception of low-energy neutrons (below 20 MeV )\, for which a group-wise treatment based on evaluated nuclear data has b een employed for a sizable list of relevant isotopes. A point-wise treatme nt was made available only for a few isotopes and channels of practical re levance. The advantages of the group-wise neutron treatment are that it re quires a very modest memory footprint and it is considerably faster than o ther methods\, rendering this approach optimal for shielding calculations and deep-penetration problems. However\, it suffers from several drawbacks \, including insufficient precision in resonance regions\, self-shielding issues\, and a too coarse discretization of the energy and angular distrib ution of emitted secondaries. These drawbacks unfortunately limit the use of group-wise neutron transport for several applications.\n\nIn this work\ , a revised point-wise treatment for low-energy neutron transport in FLUKA v4 (distributed by CERN) is described\, relying on the processed evaluate d neutron cross section libraries that are used by Geant4 [4\,5\,6]. Speci al attention is devoted to the implementation decisions adopted in order t o ensure energy and momentum conservation at every interaction\, to respec t the supplied distributions of emitted particles\, preserving correlation s and avoiding discretizations to the extent possible\, while trying to ke ep the implementation as performant as possible. \n\nOur implementation d ivides the low-energy neutron interactions into four categories: elastic\, inelastic (including 36 individual sub-channels)\, radiative capture\, an d fission. All cross sections are Doppler broadened [7] during initializat ion for the temperatures requested by the user. For thermal neutron energi es (En < 4 eV) the implementation accounts for chemical-binding effects. Molecular and crystal-lattice effects are accounted for via an S(α\,β) t reatment\, including coherent and incoherent effects for a few selected ma terials. Finally\, in view of the ongoing evolution of the FLUKA code\, th e implementation presented here is written as a C++ module that can be eas ily linked with other codes. Benchmarks against experimental data and othe r transport codes are provided.\n\nReferences:\n 1. http://fluka.cern \ n 2. G. Battistoni\, T. Boehlen\, F. Cerutti\, P.W. Chin\, L.S. Esposit o\, A. Fassò\, A. Ferrari\, A. Lechner\, A. Empl\, A. Mairani\, A. Meregh etti\, P. Garcia Ortega\, J. Ranft\, S. Roesler\, P.R. Sala\, V. Vlachoudi s\, G. Smirnov\, "Overview of the FLUKA code"\, Annals of Nuclear Energy 8 2\, 10-18 (2015).\n 3. T.T. Bohlen\, F. Cerutti\, M.P.W. Chin\, A. Fass ò\, A. Ferrari\, P.G. Ortega\, A. Mairani\, P.R. Sala\, G. Smirnov\, and V. Vlachoudis\, "The FLUKA Code: Developments and Challenges for High Ener gy and Medical Applications"\, Nuclear Data Sheets 120\, 211-214 (2014).\n 4. E. Mendoza\, D. Cano-Ott\, T. Koi and C. Guerrero\, IEEE Trans. Nuc l. Science 61 (2014) 2357.\n 5. E. Mendoza\, D. Cano-Ott\, C. Guerrero\ , and R. Capote\, “New Evaluated Neutron Cross Section Libraries for the Geant4 Code”\, IAEA technical report INDC(NDS)-0612\, Vienna\, 2012. Da ta available online at Geant4.\n 6. E. Mendoza\, D. Cano-Ott\, “Updat e of the Evaluated Neutron Cross Section Libraries for the Geant4 Code”\ , IAEA technical report INDC(NDS)-0758\, Vienna\, 2018.\n 7. D.Cullen\, C.Weisbin\, “Exact Doppler Broadening of Tabulated Cross Sections”\, Nucl Sci and Eng 60\, 199-229 (1976)\n\nhttps://indico.frib.msu.edu/event/ 52/contributions/978/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/978/ END:VEVENT BEGIN:VEVENT SUMMARY:A new model for low-energy (<150 MeV/n) deuteron nuclear reactions in FLUKA DTSTART:20220728T184300Z DTEND:20220728T185500Z DTSTAMP:20260420T153400Z UID:indico-contribution-979@indico.frib.msu.edu DESCRIPTION:Speakers: Gabriela Moryc (European Organization for Nuclear Re search (CERN))\, Francesc Salvat Pujol (European Organization for Nuclear Research (CERN))\n\nA dedicated model for low-energy (<150 MeV/n) deuteron nuclear reactions has been a long-standing shortcoming of FLUKA [1-3]\, a general-purpose code for the Monte Carlo simulation of radiation transpor t. In view of the recently increasing interest in deuteron transport (e.g. for radioisotope production in medical applications [4-5] and for nuclear fusion studies [6])\, a model for low-energy-deuteron nuclear reactions h as been included in FLUKA v4.2.\n\nThe model consists of the following mai n components. First\, deuteron stripping to the continuum is accounted for on the basis of the Serber model [7]\, describing the (uncorrelated) ener gy- and angle distribution of the first emitted nucleon. The interaction o f the conjugate nucleon with the target nucleus is then performed via FLUK A's model for hadron-nucleus inelastic interactions [8]. Next\,nucleon tra nsfer to discrete levels of the compound nucleus (typically the ground sta te and the first few low-lying excited levels) is treated for a selection of target isotopes within the distorted-wave Born approximation (DWBA) [9] \, with a minor adjustment of the underlying optical-potential-model param eters. Then\, deuteron elastic break-up both in the Coulomb and in the nuc lear field of the target nucleus is likewise described within the DWBA [10 ]. Finally\, FLUKA's complete fusion model for low-energy nucleus-nucleus inelastic collisions has been invoked to enhance the experimentally observ ed [11] emission of fragments heavier than a nucleon.\n\nAn overview of th e performance of the model for various target isotopes (from deuterium to uranium) and various energies (up to 150 MeV/n) shall be provided by way o f comparison with experimental double-differential (energy and angle) cros s sections\, as well as thick target yields [11].\n\n\nRefs:\n\n[1] FLUKA website: https://fluka.cern\n[2] G. Battistoni et al.\, "Overview of th e FLUKA code"\, Ann. Nucl. Ene. 82\, 10-18 (2015).\n[3] T.T. Bohlen et al .\, "The FLUKA Code: Developments and Challenges for High Energy and Medic al Applications"\, Nuclear Data Sheets 120\, 211-214 (2014).\n[4] C. Alli ot et al.\, "Is there an interest to use deuteron beams to produce non-con ventional radionuclides?"\, Front Med 2 31 (2015). \n[5] M. Sitarz et al. \, "Production of Sc medical radioisotopes with proton and deuteron beams" \, Appl. Rad. Isot. 142 104-112 (2018).\n[6] N. Chaivin et al.\, "Deutero n beam commissioning of the linear IFMIF protoype accelerator ion source a nd low energy beam transport"\, Nucl. Fus. 59 106001 (2019).\n[7] R. Ser ber\, "The production of high-energy neutrons by stripping"\, Phys. Rev. 7 2\, 1008-1016 (1947).\n[8] A. Ferrari et al.\, "The physics of high-energ y reactions"\, Proc. Workshop on Nuclear Reaction Data and Nuclear Reactor Physics\, Design\, and Safety 424 (1998).\n[9] L. Titus\, "Effects of no n-locality on transfer reactions"\, PhD thesis\, Michigan State University (2016).\n[10] G. Baur et al.\, "Investigations of the deuteron break-up o n heavy nuclei above the Coulomb barrier"\, Nucl Phys A 265 101-112 (1976) .\n[11] N. Otuka et al.\, "Towards a more complete and accurate experiment al nuclear reaction data library (EXFOR): international collaboration betw een nuclear reaction data centres (NRDC)"\, Nuclear Data Sheets 120 272-27 6 (2014).\n\nhttps://indico.frib.msu.edu/event/52/contributions/979/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/979/ END:VEVENT BEGIN:VEVENT SUMMARY:Integrating Nuclear Shell Model and Hauser Feshbach Calculations f or Fission Fragment Studies DTSTART:20220728T134800Z DTEND:20220728T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-963@indico.frib.msu.edu DESCRIPTION:Speakers: Jutta Escher\, Calvin Johnson (San Diego State Unive rsity)\, Oliver Gorton (San Diego State University)\n\nCurrently\, reactio n measurements on fission products are being planned by the Nuclear Scienc e PG at both Argonne Nat. Lab and at FRIB (Facility for Rare Isotopes\, Mi chigan State). These indirect experiments produce specific short-lived nuc lei via beta decay\, and the subsequent neutron and gamma emission are stu died. Some initial experiments found a surprising overabundance of gamma e mission. Two possible explanations are 1) an inadequate description of sta tes populated in beta-decay and 2) an enhanced gamma-ray strength function (related to the gamma emission probability). Resolving the issue is of br oad importance and requires theoretical development. We are developing an integrated nuclear data workflow that connects advanced nuclear shell mode l codes for describing the beta decay in these experiments with a contempo rary nuclear reaction model code.\n\nhttps://indico.frib.msu.edu/event/52/ contributions/963/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/963/ END:VEVENT BEGIN:VEVENT SUMMARY:MEASUREMENT OF THE REACTION CROSS SECTIONS OF THE SHORT- AND LONG- LIVED β+ EMITTERS FOR PET RANGE VERIFICATION IN PROTON THERAPY AT CNA\, W PE AND HIT DTSTART:20220725T190900Z DTEND:20220725T192100Z DTSTAMP:20260420T153400Z UID:indico-contribution-648@indico.frib.msu.edu DESCRIPTION:Speakers: Maria Teresa Rodriguez Gonzalez (University of Sevil la)\n\nIn proton therapy\, Positron Emission Tomography (PET) range verifi cation\, which is based on the detection of the short-lived (online monito ring) or the long-lived (offline monitoring) $\\beta^{+}$ emitters produce d in the body of the patient\, has been proved to be a well-suited techniq ue to monitor the beam range $^{[1]}$. This technique requires the compari son of the observed activity distribution with a simulated one using a Mon te Carlo code. As the reliability of the simulated activity distribution d epends on the accuracy of the underlying cross sections for producing the $\\beta^{+}$ emitters of interest $^{[2][3][4]}$\, several studies confirm the need for more and better measurements and evaluations $^{[4][5][6]}$. New data related to the production of the short-lived nuclides involved i n real-time verification $^{[7][8][9]}$ are especially needed\, as there a re no data available yet in the energy range of interest\, up to 200 MeV.\ n\nIn this context\, we have developed two methods to measure the producti on cross sections of the mentioned long-lived ($^{11}$C with t$_{1/2}$ = 2 0.4 min\, $^{13}$N with t$_{1/2}$ = 9.97 min and $^{15}$O with t$_{1/2}$ = 122 s) and short-lived ($^{12}$N with t$_{1/2}$ = 11 ms\, $^{29}$P with t $_{1/2}$ = 4.14 s and $^{38mK}$ with t$_{1/2}$ = 924 ms) $\\beta^{+}$ emit ters. The methods are based on the multifoil activation technique combined with dynamic PET scanner imaging that is performed either in-beam (for sh ort-lived $\\beta^{+}$ emitters) or outside the irradiation room (for long -lived $\\beta^{+}$ emitters). The technique has been first validated at t he 18 MeV cyclotron of CNA in Spain $^{[10]}$\, and then applied up to a n ominal proton beam energy of 200 MeV at the WPE and HIT clinical facilitie s in Germany\; in the first case using a commercial PET/CT scanner for $\\ beta^{+}$ long-lived emitters and in the latter using a state-of-the-art m iniPET made of four i-TED $^{[11][12]}$ detectors for short-lived $\\beta^ {+}$ emitters. The results from both experimental campaigns will be presen ted and the relevance of the new data for PET range verification will be d iscussed.\n\n\n$^{[1]}$ A. C. Kraan et al.\, Frontiers in Oncology 5 150 ( 2015)\n$^{[2]}$ U. Oelfke\, G. K. Lam and M. S. Atkins\, Physics in Medici ne and Biology 41 177 (1996)\n$^{[3]}$ K. Parodi et al.\, Physics in Medic ine and Biology 52 3369-3387 (2007)\n$^{[4]}$ Tárkányi et al. J. Radioan alytical and Nuclear Chemistry. 319 533–666 (2019)\n$^{[5]}$ S. España et al.\, Phys. Med. Biol. 56(9) 2687-2698 (2011)\n$^{[6]}$ E. Seravalli et al.\, Phys. Med. Biol. 57 1659 (2012)\n$^{[7]}$ P. Dendooven et al.\, Phy s. Med. Biol. 64 129501 (2019)\n$^{[8]}$ H. J. Buitenhuis et al.\, Phys. M ed. Biol. 62 4654 (2017)\n$^{[9]}$ I. Ozoemelam et al.\, Phys. Med. Biol. 65 245013 (2020)\n$^{[10]}$ T. Rodríguez-González et al.\, Rad. Phys. an d Chem. 190 109759 (2022)\n$^{[11]}$ C. Domingo-Pardo. Nucl. Inst. and Met hods A 825 78-86 (2016)\n$^{[12]}$ V. Babiano et al.\, Nucl. Inst. and Met hods A 953 163228 (2020)\n\nhttps://indico.frib.msu.edu/event/52/contribut ions/648/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/648/ END:VEVENT BEGIN:VEVENT SUMMARY:Study on the generation method of thermal neutron scattering law d ata in nuclear data processing code NECP-Atlas DTSTART:20220728T174000Z DTEND:20220728T175200Z DTSTAMP:20260420T153400Z UID:indico-contribution-959@indico.frib.msu.edu DESCRIPTION:Speakers: Yongqiang Tang (Xi'an Jiaotong University)\n\nAccura tely describing the scattering behavior of thermal neutrons can guarantee the accuracy of neutronics calculation. The thermal neutron scattering law (TSL) data is used to describe the scattering property of a materials. In this work\, some efforts have been made to improve the accuracy of TSL da ta. The anisotropic displacement parameters method is used to remove the c ubic approximation in the traditional method\, and the one-phonon correcti on method is used to consider the distinct scattering term of one-phonon i gnored by the incoherent approximation method. The methods mentioned above have been implemented into sab_calc\, a module developed for TSL calculat ion in the nuclear data processing code NECP-Atlas. Furthermore\, the cohe rent and incoherent elastic scattering can be considered simultaneously in sab_calc. The influence of the improved method on the accuracy of neutron ics calculation is quantitatively analyzed based on the criticality benchm arks. The numerical results show that the TSL data\, scattering cross sect ion and total cross section calculated by the improved method are more con sistent with the experimental values\, and the calculation accuracy of rea ctor reactivity in the benchmarks is significantly improved. Simultaneousl y considering the coherent and incoherent elastic scattering has tens of p cm effects on *k*eff of the analyzed TRIGA reactors.\n\nhttps://indico.fri b.msu.edu/event/52/contributions/959/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/959/ END:VEVENT BEGIN:VEVENT SUMMARY:Methods for processing and use of thermal neutron scattering data in OpenMC DTSTART:20220728T172800Z DTEND:20220728T174000Z DTSTAMP:20260420T153400Z UID:indico-contribution-957@indico.frib.msu.edu DESCRIPTION:Speakers: Paul Romano (Argonne National Laboratory)\n\nThis pa per describes methods for processing and use of thermal neutron scattering data in OpenMC. OpenMC relies on NJOY to process thermal scattering ENDF evaluations into ACE files\, which are then converted to HDF5 files by Ope nMC's Python API. This process is fully automated with OpenMC producing an NJOY input deck containing appropriate options for each module and coveri ng every temperature available on the original ENDF evaluation. OpenMC kee ps a list of recognized thermal scattering evaluations for determining wha t isotopes should be associated with a particular evaluation as well as th e number of atom types in a mixed moderator.\n\nIn many cases\, NJOY proce ssing results in probability distributions for the cosine of the scatterin g angle\, $\\mu$\, and outgoing energy (for incoherent scattering) that ar e represented as a series of equally-likely discrete values. Without speci al treatment\, these discrete values can produce unphysical artifacts in t he observed angle and energy distributions of neutrons. For incoherent ine lastic scattering\, NJOY does support an option to produce a continuous di stribution of outgoing energies. Both the older discrete format and newer continous format for incoherent inelastic scattering are supported in Open MC.\n\nFor incoherent elastic scattering\, NJOY does not have an option to produce a continuous distribution for the scattering cosine. Instead of u sing discrete cosines from the ACE file\, OpenMC uses a novel\, continuous sampling method based on the differential cross section\, which can be ex pressed analytically as\n$$\n\\frac{d\\sigma}{dE' d\\Omega} (E\\rightarrow E'\, \\mu\, T) = \\frac{\\sigma_b}{4\\pi} e^{-2EW'(T)(1 - \\mu)} \\delta( E - E')\n$$\nwhere $\\sigma_b$ is the characteristic bound cross section a nd $W'(T)$ is the the Debye-Waller integral as a function of temperature\, $T$. A probability density function for the cosine of the scattering angl e can be sampled by using inverse transform sampling based on the above eq uation\, resulting in the following algorithm:\n$$\n\\xi \\gets U(0\,1)\n$ $\n$$\n\\mu \\gets \\frac{1}{c} \\log \\left ( 1 + \\xi \\left ( e^{2c} - 1 \\right ) \\right) - 1\n$$\nwhere $U(0\,1)$ is a uniformly distributed r andom number on the interval $[0\,1)$ and $c = 2EW'$. Note that this metho d requires that $\\sigma_b$ and $W'(T)$ be stored in the HDF5 data files\; to support this\, OpenMC pulls the appropriate data directly from ENDF fi les to augment the ACE data produced by NJOY. Comparisons of observed angu lar distributions for a variety of thermal neutron scattering evaluations with incoherent elastic scattering\, to be presented in the full paper\, d emonstrate the advantages of this method.\n\nOpenMC has several other attr active features related to thermal scattering. It supports the use of part ial $S(\\alpha\,\\beta\,T)$ tables\, wherein the user can indicate that th ermal scattering data should only apply to some fraction of the atoms in a material. This makes it possible to spatially homogenize materials\, some of which should use thermal scattering data and some of which should not. OpenMC has also recently been updated to support new ENDF-6 formatted eva luations that contain both coherent and incoherent elastic scattering (so- called ``mixed'' elastic scattering).\n\nhttps://indico.frib.msu.edu/event /52/contributions/957/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/957/ END:VEVENT BEGIN:VEVENT SUMMARY:Phenomenological R-Matrix parameterization of direct\, doorway\, a nd compound nuclear reactions DTSTART:20220728T155000Z DTEND:20220728T160200Z DTSTAMP:20260420T153400Z UID:indico-contribution-970@indico.frib.msu.edu DESCRIPTION:Speakers: Goran Arbanas (ORNL)\n\nhttps://indico.frib.msu.edu/ event/52/contributions/970/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/970/ END:VEVENT BEGIN:VEVENT SUMMARY:Automated Nuclear Data Evaluation Tool\; Nonconvex Decomposition M ethod for Resonance Regression and Uncertainty Quantification DTSTART:20220725T171800Z DTEND:20220725T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-769@indico.frib.msu.edu DESCRIPTION:Speakers: Noah Walton (University of Tennessee)\, Jordan Armst rong\n\nNuclear data evaluation is a process that takes a long time partly due to resonance identification having to be performed manually by expert nuclear data evaluators. This procedure is laborious\, time-consuming\, a nd irreproducible from evaluator to evaluator. Additionally\, it is well-d ocumented that a systematic evaluation of the uncertainty on the evaluated cross section is unreliably low. Having these uncertainties that are “t oo small” results in additional work for the resonance evaluator to sear ch for a non-systematic\, artisanal way to make the estimated uncertainty be an appropriate size.\nWe offer an automated tool for the evaluation pro cess to serve as a starting point for the evaluators by posing the resonan ce characterization problem as a mixed integer nonlinear program (MINLP). Since the number of resonances present is unknown\, the model must be able to be determine the number of parameters to properly characterize the cro ss section curve as well as calculate the appropriate values for those par ameters. Due to the size of the problem and nonconvexity of the parameteri zation\, the optimization formulation is too difficult to solve as whole. We propose a novel method of decomposing the problem into small\, overlapp ing windows that are now solvable\, as well as method to stich the windows back together via parameter cardinality and value agreement routines to a chieve the global solution. Lastly\, a version of quantile regression is r un on the windows to provide an uncertainty estimate on the parameter valu es. The results demonstrate the model being robust to finding the proper n umber of resonances\, the appropriate values of the parameter values\, and that the uncertainty estimation is directly reflective of the experimenta l conditions. Hence\, this tool serves as a fast\, accurate\, and reproduc ible tool for nuclear data evaluators to have a starting place in their wo rk.\n\nhttps://indico.frib.msu.edu/event/52/contributions/769/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/769/ END:VEVENT BEGIN:VEVENT SUMMARY:Application-Dependent Multigroup Weighting applied to Critical Ben chmarks DTSTART:20220728T170400Z DTEND:20220728T171600Z DTSTAMP:20260420T153400Z UID:indico-contribution-985@indico.frib.msu.edu DESCRIPTION:Speakers: Thomas Saller (LANL)\, Andrew Till (LANL)\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/985/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/985/ END:VEVENT BEGIN:VEVENT SUMMARY:Quantum computing calculations for nuclear structure and nuclear d ata DTSTART:20220725T165400Z DTEND:20220725T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-766@indico.frib.msu.edu DESCRIPTION:Speakers: Isaac Hobday\n\nQuantum computing opens up new possi bilities for the simulation of many-body nuclear systems.\n\nAs the number of particles in a many-body system increases\, the size of the associated Hamiltonian increases exponentially. This presents a challenge when perfo rming calculations on large systems when using classical computing methods . By using a quantum computer\, one may be able to overcome this difficult y thanks to the exponential way the Hilbert space of a quantum computer gr ows with the number of quantum bits (qubits). \n\nOur aim is to develop qu antum computing algorithms which can reproduce and predict nuclear structu re such as level schemes and level densities. As a sample Hamiltonian\, w e use the Lipkin-Meshkov-Glick model [1] and have further tested our metho ds against recent quantum computing calculations of the deuteron binding e nergy [2].\n\nWe use an efficient encoding of the Hamiltonian onto many-q ubit systems\, and have developed an algorithm allowing the full excitatio n spectrum of a nucleus to be determined with a variational algorithm capa ble of implementation on today's quantum computers with a limited number o f qubits. Our algorithm uses the variance of the Hamiltonian\, $\\langle H^2\\rangle-\\langle H\\rangle^2$\, as a cost function for the widely-used variational quantum eigensolver (VQE).\n\nIn our presentation\, we will s how the motivations for the work\, the simplified encoding method\, and ex ample results obtained using variational quantum algorithms to produce nuc lear excited states spectra\, as well as commenting on prospects for futur e applications.\n\n\n[1] H. J. Lipkin\, N. Meshkov\, and A. J. Glick\, Nul cear Physics 62\, 188 (1965)\n\n[2] E. F. Dumitrscu \\textit{et al.}\, Phy sical Review Letters 120\, 210501 (2018)\n\nhttps://indico.frib.msu.edu/ev ent/52/contributions/766/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/766/ END:VEVENT BEGIN:VEVENT SUMMARY:Development of a New Fixed-source Sensitivity Tally Capability in the MCNP® Code DTSTART:20220725T190900Z DTEND:20220725T192100Z DTSTAMP:20260420T153400Z UID:indico-contribution-772@indico.frib.msu.edu DESCRIPTION:Speakers: Michael Rising\n\nThe development of a new fixed-sou rce sensitivity tally capability\, targeted toward nuclear data parameters \, is currently underway in the MCNP code. In recent research and develop ment efforts that utilize machine learning to both seek problematic nuclea r data as well as design experiments optimized to improve the nuclear data \, the adjoint-weighted k-eigenvalue sensitivity tally capabilities have b een essential. In this paper\, the motivation to expand the sensitivity t ally capabilities beyond k-eigenvalues toward diverse fixed-source problem s along with preliminary results and verification will be discussed.\n\nht tps://indico.frib.msu.edu/event/52/contributions/772/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/772/ END:VEVENT BEGIN:VEVENT SUMMARY:Development and Verification of Capability for Processing the Gene ralised Nuclear Database Structure (GNDS) in Nuclear Data Processing Code NECP-Atlas DTSTART:20220728T171600Z DTEND:20220728T172800Z DTSTAMP:20260420T153400Z UID:indico-contribution-987@indico.frib.msu.edu DESCRIPTION:Speakers: Yihan Huang (Xi'an Jiaotong University)\n\nThe lates t evaluated nuclear data libraries\, including ENDF/B-VIII.0\, TENDL2019\, all have two formats\, the Evaluated Nuclear Data File (ENDF-6) nuclear d ata format\, and the Generalised Nuclear Database Structure (GNDS). The fi rst official public documentation of all of the options for storing data i n GNDS was released by the Working Party on International Nuclear Data Eva luation Co-operation(WPEC) of the Nuclear Energy Agency. The generalized d erived class is designed to be compatible with ENDF-6 and GNDS in nuclear data processing code NECP-Atlas\, and the GNDS toolkit is developed in NEC P-Atlas to parse and convert GNDS. ACE format library and MATXS library ar e generated based on GNDS\, and they are used in the Monte-Carlo code and deterministic based code to compare with ENDF-6. The numerical results sho w that GNDS libraries can be processed by NECP-Atlas competently to genera te specific format library and the difference in ENDF-6 and GNDS is very s mall.\n\nhttps://indico.frib.msu.edu/event/52/contributions/987/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/987/ END:VEVENT BEGIN:VEVENT SUMMARY:Recent Developments in the Nuclear Data Processing Code AMPX DTSTART:20220728T172800Z DTEND:20220728T174000Z DTSTAMP:20260420T153400Z UID:indico-contribution-988@indico.frib.msu.edu DESCRIPTION:Speakers: Jordan McDonnell\, Andrew Holcomb (Oak Ridge Nationa l Laboratory)\n\n\\documentclass[11pt]{article}\n\\usepackage{geometry} % See geometry.pdf to learn the layout options. There are lot s.\n\\geometry{letterpaper} % ... or a4paper or a5paper or ... \n%\\geometry{landscape} % Activate for for rotated page geometry\n%\\usepackage[parfill]{parskip} % Activate to begin para graphs with an empty line rather than an indent\n\\usepackage{graphicx}\n\ \usepackage{amssymb}\n\\usepackage{epstopdf}\n\\usepackage{hyperref}\n\\us epackage{graphics\,amsmath\,amsfonts\,amssymb\,bm}\n\\usepackage{authblk}\ n\\DeclareGraphicsRule{.tif}{png}{.png}{`convert #1 `dirname #1`/`basename #1 .tif`.png}\n\\begin{document}\n\\title{Recent Developments in the Nucl ear Data Processing Code AMPX\\footnote{This manuscript has been authored by UT-Battelle\, LLC\, under contract DE-AC05-00OR22725 with the US Depart ment of Energy (DOE). The US government retains and the publisher\, by acc epting the article for publication\, acknowledges that the US government r etains a nonexclusive\, paid-up\, irrevocable\, worldwide license to publi sh or reproduce the published form of this manuscript\, or allow others to do so\, for US government purposes. DOE will provide public access to the se results of federally sponsored research in accordance with the DOE Publ ic Access Plan (http://energy.gov/downloads/doe-public-access-plan).}}\n\\ author[1]{Andrew M. Holcomb}\n\\author[1]{Dorothea Wiarda}\n\\author[1]{Je sse M. Brown}\n\\affil[1]{%Nuclear Energy and Fuel Cycle Division\, \nOak Ridge National Laboratory\, Oak Ridge\, TN 37831\, USA}\n\\date{} % Activate to display a given date or no date\n\\maketitle\n\\thispagestyle{empty}\n%\\section{Abstract}\n\\vspace {-1cm}\n\nPointwise and covariance reading/writing for the new General Nuc lear Data Structure (GNDS) \\cite{GNDS} format proposed by the Working Par ty on International Nuclear Data Evaluation Co-operation (WPEC) at the Nuc lear Energy Agency (NEA) established Subgroup 38 (SG38) \\cite{WPEC} in 20 12 has been implemented in AMPX \\cite{AMPX}. In addition\, WPEC establish ed Subgroup 38 (SG38) in 2012 to develop a more modern format for the eval uated nuclear data files (ENDF)\, currently called GND (General Nuclear Da ta format). The SG38 has formally ended\, the final report has been issued \, and the format for GNDS files has been finalized. Two new subgroups wer e formed to follow up on the development of the new format: EG GNDS\, the subgroup that will govern the new format\, and SG43\, the subgroup that is tasked with developing an Application Programming interface (API) to the new format. ORNL has been involved in both subgroups.\n\nThe ORNL processi ng code suite AMPX processes ENDF formatted files and needs to support bot h the old and new formats. Of special interest to ORNL are the formats in the resolved resonance range (RRR) and the covariance matrix for the reson ance parameters\, as these formats are used in both AMPX and SAMMY \\cite{ SAMMY}\, which is used to generate new ORNL resonance evaluations for dist ribution to the National Nuclear Data Center (NNDC). The code was develope d to read and write the new GNDS formatted files and will be used in both AMPX and SAMMY. Because the format has not yet been finalized\, support fo r the GNDS is included into the modernized code only on an experimental ba sis. The AMPX classes are automatically generated from the GNDS low level classes directly from the JSON files (on which the official GNDS documenta tion is based). Only point-wise data and covariance matrix information is currently processed. New ENDF/B-VIII.0 data libraries are provided in both formats and consistency between AMPX libraries generated from GNDS and EN DF-6 formats has been verified internally.\n\nAdditionally\, AMPX will now prevent mathematically incorrect covariance matrices from being added to final covariance libraries. In order to ensure robust behavior in sensitiv ity/uncertainty applications\, covariance data from ENDF/B must be process ed and corrected for mathematical consistency. Ideally\, covariance data f rom ENDF could be straightforwardly processed into SCALE COVERX formats fo r use in sensitivity/uncertainty applications. PUFF is responsible for per forming the difficult task of processing ENDF/GNDS formatted data into the SCALE Coverx format. While there is no rubric for grading the quality of the covariance data itself\, there are mathematics we can check and enforc e on the processed data. The constraints enforced on the processed data en sure that SCALE codes will be able to faithfully propagate the uncertainty data onto quantities of interest in a rigorously correct manner. The new implementation of the rigorous mathematical checks and processing fixes wi ll be presented.\n\n{\\bf Acknowledgments:} This work was supported by the U.S. Department of Energy (DOE) Nuclear Criticality Safety Program\, whic h is funded and managed by the National Nuclear Security Administration fo r DOE.\n\n\n\\thispagestyle{empty}\n\\begin{thebibliography}{1}\n\\bibitem {SAMMY} N.M. Larson\, {\\em ``Updated Users' Guide for SAMMY: Multilevel R -matrix Fits to Neutron Data Using Bayes' Equations"}\, ORNL/TM-9179/R8 (2 008)\n\n\\bibitem{WPEC} WPEC Subgroup 38 (SG38)\, “Beyond the ENDF forma t: A modern nuclear database structure”\, http://www.oecd-nea.org/scienc e/wpec/sg38/ (2012).\n \n\\bibitem{AMPX} D. Wiarda\, M. L. Williams\, C. Celik\, and M. E. Dunn\,\n {\\em AMPX-2000: A Cross-Section Processing Sy stem for Generating Nuclear Data for Criticality Safety Applications}\,\n International Conference on Nuclear Criticality Safety (ICNC 2015).\n\n\\ bibitem{GNDS} Specifications for the Generalised Nuclear Database Structur e (GNDS)\n \\href{https://www.oecd-nea.org/science/wpec/documents/7519-GND S.pdf}{https://www.oecd-nea.org/science/wpec/documents/7519-GNDS.pdf}\,\n( accessed September 15\, 2021).\n\n\\end{thebibliography}\n\n\\end{document }\n\nhttps://indico.frib.msu.edu/event/52/contributions/988/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/988/ END:VEVENT BEGIN:VEVENT SUMMARY:Preequilibrium models for 58Ni(n\,xp) reaction in neutrons at 8\, 9\, 9.4\, 11 and 14.8 MeV using the EMPIRE and TALYS codes DTSTART:20220727T171600Z DTEND:20220727T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-1137@indico.frib.msu.edu DESCRIPTION:Speakers: Leila Yettou\n\nIn this study\, the calculations of proton emission spectra produced by 58Ni(n\,xp) reaction are used in the f ramework of preequilibrium models with the EMPIE and TALYS codes. Exciton model predictions combined with the Kalbach angular distribution syqtemati cs were used\, and some necessary parameters have been investigated for ou r calculations. The comparison witj experimental data shows clear improvem ent over the Exciton model calculations.\n\nhttps://indico.frib.msu.edu/ev ent/52/contributions/1137/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1137/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of differential and double differential cross-section for natural Gallium at 8.0 MeV neutrons DTSTART:20220726T150300Z DTEND:20220726T150600Z DTSTAMP:20260420T153400Z UID:indico-contribution-1097@indico.frib.msu.edu DESCRIPTION:Speakers: Xichao Ruan (CIAE)\, Jie Ren (CIAE)\, Hanxiong Huang (CIAE)\n\nThe metal gallium is a very interesting element on earth. It is a liquid at temperatures greater than 29.76 °C and has a very high boili ng point (2229 ◦C). Gallium has widely been used to make alloys with low melting points and has become a candidate element in Chinese Initiative A ccelerator Driven Systems (CIADS) project for liquid–metallic coolant [ ]. The neutron cross section of gallium is useful for nuclear device desig n. The experimental differential cross section data is still rare in fast neutron energy region. The secondary neutron emission differential and dou ble-differential cross sections (DX and DDXs) of n + natGa have been measu red at the neutron energy of 8MeV using the multi-detector fast neutron ti me-of-flight (NTOF) spectrometer in China Institute of Atomic Energy (CIAE ). The data was derived by comparing the measured NTOF spectra with Monte Carlo simulation\, and corrected with n-p scattering cross section in smal l angles. Measured differential cross sections are compared with evaluated data base. It was found that the experimental results of angular distribu tion were in agreement with CENDL-3.2 data base better than ENDF/B-VIII.0 data base.\n\nhttps://indico.frib.msu.edu/event/52/contributions/1097/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1097/ END:VEVENT BEGIN:VEVENT SUMMARY:BNCODE – THE SCIENTIFIC SUPERVISOR SIMULATION CODE FOR A COMPUTA TIONAL SUPPORT OF THE BN REACTORS DTSTART:20220727T165700Z DTEND:20220727T170000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1128@indico.frib.msu.edu DESCRIPTION:Speakers: Viacheslav Mishin (JSC "SSC RF-IPPE")\n\nThe necessi ty to operatively concern the growing needs of the BN-600 reactor support as well as the commissioning of the BN-800 reactor which also has a task o f scientific support have led to the necessity of a new generation simulat ion support code development. This new generation code would make it possi ble to flexibly consider actual demands of scientific support of both reac tors. In future it could be also adopted for the support of the BN-1200 re actor being designed. Such a code should have more developed computational capabilities\, more flexible\, suitable and modern interface.\nThe TRIUM8 00 system specially developed for the computational support of the BN-800 reactor was served as a first version of the new code. The given code at t his moment is widely being used in its application area. Unlike the previo us system it is based on the use not only the diffusion but also the trans port approximation. It is included the following program complexes as comp utational modules: TRIGEX (diffusion approximation\; up to 26 energy group s)\, MMK-K and MMK-C (transport PN-approximation\; Monte-Carlo technique\; 26 and 299 energy groups or using the pointwise neutron data\, similar to how it is done in the MCNP program). There is a possibility of an element -by-element calculation of the CPS control members and combined experiment al FAs.\nThe development of the advanced new generation support code BNCod e has been finished at this moment. This BNCode combines BN-600 and BN-800 reactors under its unified platform.\nThe calculated and experimental dis crepancies of the CPS rods efficiency\, maximum reactivity margin\, critic ality parameter and etc. will be demonstrated in the report during the ope ration of:\n– hybrid BN-800 reactor core\n– BN-600 reactor during the 75th between refueling period\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/1128/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1128/ END:VEVENT BEGIN:VEVENT SUMMARY:Simultaneous evaluation of uranium and plutonium fast neutron fiss ion cross sections up to 200 MeV for JENDL-5 DTSTART:20220726T173000Z DTEND:20220726T174200Z DTSTAMP:20260420T153400Z UID:indico-contribution-710@indico.frib.msu.edu DESCRIPTION:Speakers: Osamu Iwamoto (Japan Atomic Energy Agency)\, Naohiko Otsuka (International Atomic Energy Agency)\n\nThe fast neutron fission c ross sections of 233\,235\,238U and 239\,240\,241Pu were evaluated for the JENDL-5 library up to 200 MeV. The experimental fission cross sections an d their ratios in the EXFOR library were reviewed with the source articles . Additionally\, Poenitz’s data compiled in his GMA database were review ed. We found about 160 datasets are archived with the uncertainty informat ion sufficient for covariance matrix construction and converted them from EXFOR to an experimental database with their covariance matrices. When the uncertainty information in the source article is missing in the EXFOR ent ry\, we updated the EXFOR entry. We minimized corrections to the experimen tal database to make our evaluation becomes traceable.\n\nThe least-square s fitting was performed to the logarithms of the cross sections and their rations in the experimental database by using the simultaneous least-squar es fitting code SOK. The best precisions of the group-wise cross sections were achieved around 2 to 3 MeV\, where the external uncertainties are 1% (235\,238U)\, 1.5% (233U\, 239Pu) or 2.5% (241Pu). Well documented experim ental fission cross sections are desired for 235U between 100 and 300 keV and 241Pu in the whole energy range since the numbers of the usable experi mental datasets are limited and it makes the uncertainties in our evaluati on relatively high.\n\nThe evaluated cross sections were also validated ag ainst the spectrum averaged fission cross sections measured under the 252C f and Σ-Σ neutron fields\, and we found the newly evaluated cross sectio ns are consistent with the experimental spectrum averaged cross sections w ell except for 238U fission cross sections measured in the 252Cf neutron f ields\, which is underestimated by the newly evaluated cross sections as w ell as those in many other data libraries.\n\nhttps://indico.frib.msu.edu/ event/52/contributions/710/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/710/ END:VEVENT BEGIN:VEVENT SUMMARY:Target mass dependence of photoneutron spectrum for 16.6MeV photon s on medium-heavy mass targets DTSTART:20220726T150600Z DTEND:20220726T150900Z DTSTAMP:20260420T153400Z UID:indico-contribution-1098@indico.frib.msu.edu DESCRIPTION:Speakers: Toshiya Sanami (KEK/SOKENDAI)\n\nExperimental data o n photoneutron spectrum for reaction of 16.6MeV mono-energetic polalized p hotons on medium-heavy mass targets were obtained at BL-01\, NewSUBARU\, H yogo\, Japan. The data consists of low energy neutrons having energy distr ibution similar to tail of Maxwellain and relatively high energy ones orig inated from decay of pre-equilibrium status. In this presentation\, quanti ties characterized the spectrum shape are presented as a function target m ass. The discussions on the parameters expressing ratio of neutrons from p re equilibrium to equilibrium states are presented in comparison with past experimental data.\n\nhttps://indico.frib.msu.edu/event/52/contributions/ 1098/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1098/ END:VEVENT BEGIN:VEVENT SUMMARY:Implementation of the RESKR module in NJOY DTSTART:20220727T170300Z DTEND:20220727T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-1130@indico.frib.msu.edu DESCRIPTION:Speakers: Alain Hébert (Polytechnique Montréal)\n\n**Abstrac t**\n\nThe Blackshaw-Murray[1] elastic kernel represents the effect of neu tron up-scattering caused by thermal motion of target nuclei and resonance elastic scattering on the multigroup scattering matrices. A first impleme ntation of this model was proposed by Ouisloumen and Sanchez and made avai lable in proprietary cross-sections libraries of the PARAGON and APOLLO la ttice codes.[2] Later\, the\nsame technique was reimplemented as module RE SK in the NECP-Atlas cross-section generating code by J. Xu\, T. Zu and L. Cao.[3\,4] Here\, we propose an Open-Source implementation of the same mo dule\, renamed RESKR in NJOY-2012 and NJOY-2016.[5]\n\n**Introduction**\n\ nThe new RESKR module of NJOY generates Doppler-broadened resonance elasti c scattering kernels (RESKs) in PENDF format starting from piecewise linea r cross sections also in PENDF format. The input cross sections are recove red from RECONR *and* from a previous BROADR run.\n\nThe exact Doppler br oadened energy transfer kernel produces a strong up-scattering effect in t he resolved resonance energy range\, above the upper limit where the $S(\\ alpha\,\\beta)$ free gas model of the THERMR module is set. The RESKR modu le is used to pursue Doppler broadening of the elastic kernel for resonant nuclides above the thermal domain considered by THERMR.\n\nThe RESKR modu le implements the Blackshaw-Murray kernel according\nto the Ouisloumen and Sanchez formulas. Firstly\, the resonance elastic scattering kernel (RESK ) formulations for anisotropic scattering up to any Legendre order is adop ted to represent the exact Doppler broadened energy transfer kernels. A se mi-analytical integration method is applied to perform the RESK calculatio ns. Combining with the RESK calculations\, a linearization algorithm is pr oposed to generate the RESK interpolation tables. These interpolation tabl es are Legendre moments $\\ell$ of the elastic scattering\nkernels of the form $P_\\ell(E \\rightarrow E')$. They are written in the\noutput PENDF f ile as a new MF6 MT300 reaction type.\n\nThe main entry point is subroutin e RESKR exported by module reskm. The coding logic of module reskm is simi lar to the one used by module thermm.\n\nAn unassigned reaction type numbe r MT300 in ENDF-6 format is assigned to store and output the interpolation table of the RESK data and the MF3 MT300 and MF6 MT300 reaction types are defined. The incident energy grid of reaction MF3 MT300 is a subset of en ergy grid in MF3 MT2 selected between lower (elo) and upper (ehi) incident energy boundaries for the RESK calculation. The incident energy grid of r eaction MF6 MT300 is a coarser grid set to reduce computing cost.\n\nAt ea ch reconstructed incident energy\, the moments of energy transfer kernels for the different orders are linearized simultaneously on a single unioniz ed grid by the conventional interval-halving techniques of Cullen[6]. It e nsures that all orders of the moments are reconstructed smoothly. Meanwhil e\, the moments of energy transfer kernels for the different orders are in terpolated simultaneously once the interpolation interval is found.\n\nA d ata structure in ENDF-6 format is defined as described in Table 1 where HE AD\, TAB2\, TAB1 and LIST are the standard types of records\; ZA and AWR a re the standard material charge and mass parameters\; NL is the maximum Le gendre order number of this table\; EP is the secondary energy\; P0 indica tes the 0th moment of energy transfer kernel and P1 represents the 1st mom ent of energy transfer kernel. The TAB1 structure with embedded LIST struc tures is repeated for all NE incident energies. Each TAB1 structure contai ns NL$-1$ embedded LIST structures containing kernel values for $P_1$\, $P _2$ and higher Legendre moments.\n\n**Table 1: MF6 MT300 reaction type**\n [MAT\, 6\, MT / ZA\, AWR\, NL\, 0\, 0\, 0 ] HEAD\n[MAT\, 6\, MT / T\, 0.0\ , 0\, 0\, NR\, NE / (INT) ] TAB2\n[MAT\, 6\, MT / 0.0\, E1\, 0\, 0\, NRP\, NEP / EP / P0(E1->EP) ] TAB1\n[MAT\, 6\, MT / 0.0\, 0.0\, 0\, 0\, NW\, 0 / P1(E1->EP) ] LIST\nRepeat the LIST structure for all NL-1 orders\nRepeat the TAB1 structure for all NE incident energies\n\nAfter the processing\, the data will be output into derived files which are the point-ENDF (PEND F) files. The reusable PENDF files can be used for generating the differen t multi-group cross sections and scattering matrices faced with the differ ent requirements of dilutions and energy group structures.\n\n**References **\n\n[1] G. L. Blackshaw and R. L. Murray\, ``Scattering functions for lo w-energy neutron collisions in a Maxwellian monoatomic gas\," *Nucl. Sci. Eng.*\, **27**\, 520--532 (1967).\n\n[2] M. Ouisloumen and R. Sanchez\, `` A Model for Neutron Scattering of Heavy Isotopes that Acccounts for Therma l Agitation Effects\," *Nucl. Sci. Eng.*\, **107**\, 189--200 (1991).\n\n[ 3] T. Zu\, J. Xu\, Y. Tang\, H. Bi\, F. Zhao\, L. Cao and H. Wu\, ``NECP-A tlas: A new nuclear data processing code\,'' *Ann nucl. Energ*\, **123**\, 153--161 (2019).\n\n[4] J. Xu\, T. Zu and L. Cao\, ``Development and veri fication of resonance elastic scattering kernel processing module in nucle ar data processing code NECP Atlas\,'' *Progress nucl. Energy*\, **110**\, 301--310 (2019).\n\n[5] R. E. MacFarlane and A. C. Kahler\, ``Methods for Processing ENDF/B-VII with NJOY\," *Nuclear Data Sheets*\, **111**\, 2739 (2010).\n\n[6] D. E. Cullen\, ``Program SIGMA1 (Version 74-1)\,'' Lawrenc e Livermore Laboratory report UCID-16426 (January 1974).\n\nhttps://indico .frib.msu.edu/event/52/contributions/1130/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1130/ END:VEVENT BEGIN:VEVENT SUMMARY:Time dependence of prompt fission $\\gamma$-ray emission DTSTART:20220726T151200Z DTEND:20220726T151500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1100@indico.frib.msu.edu DESCRIPTION:Speakers: Andreas Oberstedt (Extreme Light Infrastructure - Nu clear Physics)\n\nPrompt fission $\\gamma$ rays (PFG) account for 40% of t he total $\\gamma$ heating in the core of a typical fast reactor\, which i n turn constitutes about 10% of the total energy release in fission [1]. T herefore\, precise knowledge about multiplicities and $\\gamma$-ray energi es is important. Prompt fission $\\gamma$ rays are commonly defined as tho se emitted in coincidence with fission fragments\, i.e. prior to $\\beta$ decay. To assess all those $\\gamma$ rays in an experiment is difficult\, for two reasons: $\\textit{i)}$ nuclear level lifetimes may reach up to mi croseconds\, while a chosen prompt timing window usually is of the order o f tens of nanoseconds at most\, $\\textit{ii)}$ extending the prompt windo w will include contributions from delayed $\\gamma$ rays. Fortunately\, th e latter effect is negligible.\n\nNot very long ago\, the time dependence of PFG spectral characteristics\, in particular the multiplicity\, was alr eady studied experimentally\, however only during the first 10 ns after th e spontaneous fission of $^{252}$Cf [2]. In a recent experiment with VESPA (VErsatile $\\gamma$ SPectrometer Array) at JRC Geel\, we managed to exte nd this time region considerably\, including late $\\gamma$-ray emission u p to 100 $\\mu$s after the instance of fission. Multiplicities were determ ined for different time bins\, covering the entire time range. The observe d time dependence is compared to results from calculations [3] with the Mo nte Carlo Hauser-Feshbach code CGMF [4\, 5]. We will give details on the r ecent experiment\, present the obtained results\, and discuss them in term s of nuclear lifetimes.\n\nReferences\n[1] G. Rimpault\, D. Bernard\, D. B lanchet\, C. Vaglio-Gaudard\, S. Ravaux\, A. Santamarina\, Phys. Procedia $\\textbf{31}$\, 3 (2012).\n[2] A. Oberstedt\, A. Gatera\, A. Göök\, and S. Oberstedt\, Eur. Phys. J. A $\\textbf{56}$ 196 (2020).\n[3] P. Talou\, T. Kawano\, I. Stetcu\, J. P. Lestone\, E. McKigney\, and M. B. Chadwick\ , Phys. Rev. C $\\textbf{94}$\, 064613 (2016).\n[4] T. Kawano\, P. Talou\, M. B. Chadwick and T. Watanabe\, J. Nucl. Sci. Tech. $\\textbf{47}$\, 462 (2010).\n[5] P. Talou\, B. Becker\, T. Kawano\, M. B. Chadwick\, and Y. D anon\, Phys. Rev. C $\\textbf{83}$\, 064612 (2011).\n\nhttps://indico.frib .msu.edu/event/52/contributions/1100/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1100/ END:VEVENT BEGIN:VEVENT SUMMARY:Comparison of binding energy from Atomic Mass Evaluation (AME-202 0) with statistical model calculations. DTSTART:20220727T171800Z DTEND:20220727T172000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1140@indico.frib.msu.edu DESCRIPTION:Speakers: Ranjan Sariyal (Department of Physics\, Panjab Univ ersity\, Chandigarh\, India)\n\n\\documentclass[12pt\,a4paper]{article}\n\ \usepackage[utf8]{inputenc}\n\\usepackage{amsmath}\n\\usepackage{mathtools }\n\\usepackage{graphics}\n\\usepackage{amssymb}\n\\usepackage{graphicx}\n \\usepackage{authblk}\n\\font\\myfont=cmr12 at 10pt\n\\title{\\myfont{\\te xtbf{Comparison of binding energy from Atomic Mass Evaluation (AME-2020) with statistical model calculations}.}}\n\\begin{document}\n%\\author[1\,2 ]{}\n\\author[1\,2]{\\fontsize{12}{10}R. Sariyal}\n\\affil[1]{\\fontsize{1 2}{10}Department of Physics\, Panjab University\, Chandigarh 160014\, Indi a.}\n\\affil[2]{\\fontsize{12}{10}Department of Atomic and Nuclear Physics \,Tata Institute of Fundamental Research\, Mumbai 400005\, India.}\n\\date {}\n\\maketitle{}\n\\section*{\\hspace{5.5cm}Abstract}\nRealistic model ca lculations are fundamental to any physical problem. Statistical model cont inues to remain one of the important theoretical basis formalism in nuclea r reaction and structure field\, which is based on the assumption that onc e compound nucleus (CN) is formed with different projectile and target com bination above coulomb barrier with certain excitation energy is fully equ ilibrated in all degrees of freedom (i.e. energy\, angular momentum) befor e the decay takes place. In this letter\, we have compared the recently me asured binding energies from The Atomic Mass Evaluation 2020 \\cite{AMC-20 20} with calculated values based on FORTRAN code known as CASCADE\\cite{pu l}. This comparison becomes very important from the fact that code calcula tes everything from excitation energy\, Q-value of reaction to cross-secti ons based on binding energy and is used frequently by nuclear research com munity throughout the world. We have given brief explanation on how code c alculates and comparison of calculated Binding energy with recently measur ed binding energies from The Atomic Mass Evaluation 2020 \\cite{AMC-2020}. A total of 254 stable nuclides binding energies are compared. \n%\\secti on*{Q-Value:}\n\\\\\nQ-value is one of the very important ingredient which determines whether nuclear reaction process will take place or not. It ma y be defined as the mass difference between initial reactants and products . In terms of binding energy it can be defined as difference of binding e nergy of products and reactants.\nQ-value of nuclear reaction can be given by: $$ a + b \\hspace{3mm}{\\rightarrow} \\hspace{3mm}c $$ \n\\begin{equ ation} \\label{1}\n Q = [m(a) + m (b) - m(c) ]c^2\n\\end{equation}\n\\h space{7cm}Or\n\\begin{equation} \\label{2}\n Q = B(c) - B(b) - B(a)\n \\ end{equation}\nwhere B is binding energy.\nCASCADE calculates Q value of r eaction using binding energy of reactants and products. So\, it is crucial to compare experimental binding energy value with calculated ones. The Na tional Nuclear Data Center\, Brookhaven National Laboratory which is a rep ository of nuclear data e.g. nuclear structure\, decay\, and reaction data \, publishes atomic masses from time to time. Recently masses are updated and published as a part of Atomic Mass Evaluation-2020 by Meng Wang et. al \\cite{AMC-2020}. Binding energy per nucleon of 254 stable nuclides are c ompared and shown in figure \\ref{fig1}.\\begin{figure}\n \\centering\n \\includegraphics[width=10cm\, height=6cm]{comparison.eps}\n \\capt ion{Comparison of experimental binding energy per nucleon with calculated values from CASCADE. }\n \\label{fig1}\n\\end{figure}\nBinding energy o f nuclei is calculated by s using Myers and Swiatecki \\cite{myers}\n\\beg in{equation} \\label{3}\n (B)_{A\,Z}= - c_1 A + c_2 A^{2/3} + \\frac{c_3 Z^2}{A^{1/3}} - \\frac{c_4 Z^2}{A} + \\delta\n \\end{equation}\n where $c _1 \, c_2\,c_3\,c_4\,\\delta$ are different variables.\n Calculated values are almost same within the error bar. \n\\begin{thebibliography}{}\n\\bib item{AMC-2020} Meng Wang\, W.J. Huang\, F.G. Kondev\, G. Audi and S. Naim i\, Chinese Phys. C \\textbf{45}\, 030003 (2021).\n\n\\bibitem{myers}W. D. Myers and W. J. Swiatecki\, Nucl. Phys. \\textbf{81}\, 1 (1966).\n\\bibit em{pul}F.Puhlhofer\, Nucl. Phys. A \\textbf{280}\,267 (1977).\n\n\n\n\\end {thebibliography}\n\n\n\n\n\n\n\\end{document}\n\nhttps://indico.frib.msu. edu/event/52/contributions/1140/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1140/ END:VEVENT BEGIN:VEVENT SUMMARY:First on-beam measurements with the new detection system for the m easurements of light-ion products of nuclear reactions induced by fast neu trons with energies from 18 to 33 MeV DTSTART:20220726T150900Z DTEND:20220726T151200Z DTSTAMP:20260420T153400Z UID:indico-contribution-1099@indico.frib.msu.edu DESCRIPTION:Speakers: Martin Ansorge (Nuclear Physics Institute of the Cze ch Academy of Sciences)\n\nThe new detection device for measurements of li ght ions (p\, d\, t\, α) emitted as products of the\nnuclear reactions in duced by fast neutrons was recently developed at the Nuclear Physics Insti tute of \nthe Czech Academy of Sciences. The device consists of the vacuum chamber and rotational table with\nthe detection telescopes composed of t wo Si detectors for dE–E charged particle recognition. It is \ncoupled w ith the collimated beams of fast neutrons produced by an isochronous cyclo tron U-120M \ndriven generator. The device can measure the double differen tial cross-sections with respect to the\nangle of emitted light ions and t o the incident neutron energy. The experimental data measured on \nbeams p roduced with the p(35 MeV)+Be(2.5mm) will be presented. The neutron field \ncharacterizations by Proton-recoil-Method measured with the chamber will be shown and the \nmeasured count rates will be compared with the estimat ions calculated by Geant4 simulations. In the \nfuture\, this new Chamber- for-Light-Ion-Detection (CLID) will produce new differential nuclear data of \nhigh interest for the material applications related to the fusion and aerospace technologies and \npotentially test and validate models of nucl ear reactions themselves.\n\nhttps://indico.frib.msu.edu/event/52/contribu tions/1099/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1099/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of delayed neutrons in a thermal nuclear reactor by me ans of a long run pile noise experiment in sub-critical state DTSTART:20220727T154500Z DTEND:20220727T155700Z DTSTAMP:20260420T153400Z UID:indico-contribution-1116@indico.frib.msu.edu DESCRIPTION:Speakers: Grégoire DE IZARRA (CEA Cadarache)\, Alix SARDET\, Romain BOFFY (CEA Cadarache)\, Benoit GESLOT\, Guillaume Truchet (CEA)\n\n The transfer function of a zero-power thermal reactor was successfully mea sured by means of a pile noise experiment at low frequency. During a month -long experimental campaign\, neutron fluctuations were acquired using exc ore fission chambers in a sub-critical state of the reactor. The analysis made use of the Cross-Power Spectral Density (CPSD) methodology. Firstly\, the prompt neutrons kinetic parameters\, such as $\\alpha_p$\, ${\\beta_\ \text{eff}}$\, and $\\Lambda$\, were obtained from a short measurement in a critical state. It required a power calibration that was carried out usi ng in-core gold foil activation and a calibrated fission chamber. Secondly \, these parameters were used to normalize the subcritical transfer functi on to extract the 8-group delayed neutrons abundances. A substantial effor t was put into day-to-day reactivity monitoring in order to allow data ave raging. A standard point kinetic model was used to fit that data by means of Bayesian inference and Markov Chain Monte-Carlo programs\, namely CONRA D and Stan\, respectively. A very good agreement was found between the exp erimental a$_i$ and the ones computed by TRIPOLI-4 Monte-Carlo transport c ode along with the JEFF3.1.1 nuclear data library. C/E on the 5th and 8th groups\, which are the largest and smallest groups\, are $+ 0.9 \\pm 6.7$ % and $+4.6 \\pm 56$ %\, respectively. The uncertainties on prior abundanc es between 6 to 101 %\, held mainly by nuclear data\, were lowered between 4 to 56 %\, depending on delayed groups. When ENDF/B.VII rev.0 or rev.1 n uclear data were employed\, the results of this study suggest a correction of -13 % on the mean lifetime of delayed neutrons.\n\nThe CPSD is reporte d in the Figure below and compared to the 8-group point kinetic model fed with kinetic parameters computed with TRIPOLI-4 $\\times$ JEFF3.1.1.\n\nht tps://indico.frib.msu.edu/event/52/contributions/1116/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/1116/ END:VEVENT BEGIN:VEVENT SUMMARY:Results from the ARTIE experiment DTSTART:20220725T195700Z DTEND:20220725T200900Z DTSTAMP:20260420T153400Z UID:indico-contribution-869@indico.frib.msu.edu DESCRIPTION:Speakers: Luca Pagani (UC Davis)\n\nA measurement of the trans mission coefficient for neutrons through a thick ($\\sim 3$ atoms/b) liqui d natural argon target in the energy range $30$-$70$ keV was performed by the Argon Resonance Transmission Interaction Experiment (ARTIE) using a ti me of flight neutron beam at Los Alamos National Laboratory.\nIn this ener gy range theory predicts an anti-resonance in the $^{40}$Ar cross section near $57$ keV\, but the existing data\, coming from an experiment performe d in the 90s (Winters. et al.)\, does not support this.\nThis discrepancy gives rise to significant uncertainty in the penetration depth of neutrons through liquid argon\, an important parameter for next generation neutrin o and dark matter experiments.\nIn this talk\, the final results from the ARTIE experiment will be presented.\nThe ARTIE measurement of the total cr oss section as a function of energy confirms the existence of the anti-res onance near $57$ keV\, but not as deep as the theory predicts.\n\nhttps:// indico.frib.msu.edu/event/52/contributions/869/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/869/ END:VEVENT BEGIN:VEVENT SUMMARY:Prediction of prompt neutron spectra of the photon induced reactio ns on the 238U and 232Th targets at incident energies from 4 and 22 MeV DTSTART:20220726T151500Z DTEND:20220726T151800Z DTSTAMP:20260420T153400Z UID:indico-contribution-1101@indico.frib.msu.edu DESCRIPTION:Speakers: Dan Mihai Filipescu (National Institute of Nuclear P hysics and Engineering Horia Hulubei)\, Adriana Ioana Gheorghe (National I nstitute of Nuclear Physics and Engineering Horia Hulubei)\, Anabella Tudo ra (University of Bucharest)\n\nThe prediction of prompt neutron spectra o f the photon-induced reactions on the 238U and 232Th targets are needed in the treatment of experimental data of the reactions induced by quasi mono chromatic γ-ray beams produced in laser Compton-scattering at the NewSUBA RU synchrotron radiation facility.\nUnfortunately any experimental informa tion concerning both the fission fragments and the prompt emission quantit ies for the monochromatic photon induced fission of 238U and 232Th is comp letely missing. Consequently the only way to predict the prompt neutron sp ectra of γ + 238U and γ + 232Th at incident energies Eγ ranging from 4 to 22 MeV\, remains the use of the most probable fragmentation approach (k nown as the Los Alamos (LA) model) with input parameters provided by syste matics. The LA version of Madland and Kahler [1] which consider different residual temperature distributions of the light and heavy fragment and the recent systematic of its input parameters [2] are employed.\nAt Eγ up to about 12 MeV\, the spectra of prompt neutrons emitted only from the fissi on fragments of the main nucleus undergoing fission (i.e. 238U and 232Th\, respectively) are considered. At higher Eγ multiple fission chances occu r\, so that the contributions of both\, the prompt neutrons emitted from t he fission fragments (FF) of each fissioning nucleus formed at the respect ive Eγ and of the so-called pre-fission neutrons must be taken into accou nt.\nAt Eγ up to 22 MeV\, only the fissioning nuclei of the main chain ar e involved (i.e. 238-236U\, 232-230Th)\, their average excitation energies (at which the prompt emission calculations are performed) being given by iterative equations according to Refs.[3 - 6] and references therein.\nThe individual spectra of prompt neutrons emitted from the fission fragments Ni(E) of each fission chance (indexed i) and of each evaporated pre-fissio n neutron φev i(E) are then calculated without to need of the fission pro babilities. \nThe total prompt neutron spectrum at a given Eγ is obtained as N(E) = NFF(E) + Nprefiss(E) in which both components NFF(E) and Nprefi ss(E) are calculated as a superposition of individual spectra Ni(E) and φ ev i(E) respectively\, weighted with the fission probabilities of each cha nce PFi and the average numbers of prompt neutrons. The fission probabilit ies can be taken as photo-fission cross-section ratios resulting from nucl ear reaction calculations\, i.e. RFi = σγ\,xnf / σγ\,F (in which x = i-1). \nThe present prediction of prompt neutron spectra is based on RFi o btained from the photon induced reaction calculations performed with the E MPIRE code\, according to Ref.[7] \n\n[1] D.G.Madland and A.C.Kahler\, Nuc l.Phys.A 957 (2017) 289-311 and corrigeum Nucl.Phys.A 961 (2017) 216-217. \n[2] A.Tudora\, Eur.Phys.J. A\, 56 (9)\, (2020) 225.\n[3] A.Tudora\, G.Vl aduca\, B.Morillon\, Nucl.Phys.A 740 (2004) 33-58. \n[4] R.Capote et al. N ucl.Data Sheets 131 (2016) 1-106.\n[5] A.Tudora\, F.-J.Hambsch\, V.Tobosar u\, Phys.Rev.C 94 (2016) 044601.\n[6] A.Tudora\, F.-J.Hambsch\, V.Tobosaru \, Nucl.Sci.Eng. 192 (2018) 52-69.\n[7] M.Sin\, R.Capote\, M.W.Herman\, A. Trkov\, B.V.Carlson\, Phys.Rev.C 103 (2021) 054605.\n\nhttps://indico.frib .msu.edu/event/52/contributions/1101/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1101/ END:VEVENT BEGIN:VEVENT SUMMARY:Re-measurement of the $^{146}$Sm and $^{147}$Sm half-lives using h igh resolution 4π microcalorimeters DTSTART:20220728T174000Z DTEND:20220728T175200Z DTSTAMP:20260420T153400Z UID:indico-contribution-927@indico.frib.msu.edu DESCRIPTION:Speakers: Alexander Kavner (LLNL)\, Geon-Bo Kim (LLNL)\n\nWe a re re-measuring the half-lives of $^{146}$Sm and $^{147}$Sm to improve the accuracy of Sm-Nd chronometers for early solar system chronology. The sam arium sources are fully embedded into small Au foils and coupled to cryoge nic microcalorimeters that measure heat released from each Sm alpha decay. This new detection method provides near 100% detection efficiency and a f ew keV energy resolution\, which makes it well suited for accurate decay c ounting of low activity samples. After the decay counting is completed\, t he Sm sources will be chemically separated from Au foils and accurately qu antified by thermal-ionization mass spectrometry with Sm standards to dete rmine the number of Sm atoms that were embedded in each detector. Half-liv es will be obtained by combining activity measurements from decay counting along with the number of atoms from mass spectrometry. We will report the $^{147}$Sm half-life from our work (figure 1)\, as well as progress on th e $^{146}$Sm half-life measurement using the same technique.\n\nhttps://in dico.frib.msu.edu/event/52/contributions/927/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/927/ END:VEVENT BEGIN:VEVENT SUMMARY:Federated Transfer Learning for Scalable Condition based Monitorin g of Nuclear Power Plant Components DTSTART:20220727T163000Z DTEND:20220727T163300Z DTSTAMP:20260420T153400Z UID:indico-contribution-1117@indico.frib.msu.edu DESCRIPTION:Speakers: Vivek Agarwal\, Koushik Araseethota Manjunatha (Ida ho National Laboratory)\n\nCondition-based monitoring (CBM) techniques are widely being adopted for maintenance activities in nuclear power plants. Asset operational data are collected by smart sensors mounted on and aroun d the components. The sensed data is often gathered and processed by a mon itoring and diagnostic center to garner various component fault signatures . These fault signatures are subsequently used as input to train predictiv e machine learning (ML) models for the specific component. Development of ML models require a significant amount of healthy and fault data. As fault s are rare events\, it is highly unlikely that all the potential fault mod es are captured for a single component. Moreover\, new components without historical data cannot contribute to ML model development. Additionally\, fault signatures extracted from a single component cannot be robust enough to handle unseen fault patterns in same or different components. Privacy\ , security\, legal\, and commercial concerns often prevent data sharing ac ross different plant systems.\nThis research presents federated transfer l earning (FTL) to scale ML models for CBM across components or plant system s by combining federated learning (FL) and transfer learning (TL) approach es as shown in Figure 1. FL enables developing local models at the compone nt level across different units that are securely shared to a centralized server to aggregate into a global model. TL enables application of the dev eloped aggregated global model to different but related systems within the same plant site\, or to the same system at different plant sites. FTL was demonstrated for the circulating water system from two nuclear plant site s (representing three units) to predict the health of circulating water pu mps. The FTL framework was verified using a multi-kernel adaptive support vector machine and an artificial neural network. The results show signific ant improvement in prediction performance while reducing over-fitting issu es.\n\nhttps://indico.frib.msu.edu/event/52/contributions/1117/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1117/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of 233U-HU Substitution Reactivity Worth in KUCA for Validation of 233U Nuclear Data DTSTART:20220725T171800Z DTEND:20220725T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-673@indico.frib.msu.edu DESCRIPTION:Speakers: Tadafumi Sano (Kindai University)\n\nAs engineering discussions of the feasibility of new reactor systems\, it is necessary to evaluate the impact of the fuels and materials for the neutronics charact eristics such as criticality\, conversion rate\, and fuel balance. It is i mportant to perform the validation of 233Th and 233U nuclear data for a th orium-based nuclear reactor\, because those nuclear data contribute signif icantly to the neutronics characteristics of the reactor.\n In this study\ , in order to perform integral evaluation of 233U nuclear data\, measureme nts of substitution reactivity worth between 233U sample and high enrichme nt uranium (HU) sample in Kyoto University Critical Assembly (KUCA) were c arried out.\n In KUCA with solid moderator core\, fuel and moderator plate s in fuel element were set in a 1.5 mm thickness aluminum sheath and all m aterial plates have nominal cross section of 2” square. In this study\, the experimental core was consist of 24 fuel elements and 1 special fuel e lement. A fuel element was consisted of 31 unit cells and sandwiched by a upper and a lower polyethylene reflector. The unit cell has one enriched u ranium (EU) plates of 1/16” thickness\, three polyethylene plates of 1/8 ” thickness. In addition\, a special fuel element was loaded in the cent er of the core. A 233U of HU sample was installed in the central cell of t he fuel element (S). The 233U sample was about 9 g U3O8-Al and the HU samp le was about 9 g U3O8-Al. The substitution reactivity worth was defined as difference of excess reactivates between 233U or HU inserted core. The ex cess reactivates were measured by positive period method. \n As the experi mental results\, the substitution reactivity was obtained 0.0146 ± 0.0006 %dk/k. On the other hand\, a numerical results by MVP-3 with JENDL-4.0 wa s 0.0141±0.0006 and the C/E was 0.966 ± 0.041.\n\nhttps://indico.frib.ms u.edu/event/52/contributions/673/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/673/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron cross section measurements for burn-up credit approaches DTSTART:20220725T192100Z DTEND:20220725T193300Z DTSTAMP:20260420T153400Z UID:indico-contribution-682@indico.frib.msu.edu DESCRIPTION:Speakers: Stefan Kopecky (European Commission\, Joint Research Centre (JRC))\, Carlos Paradela (European Commission\, Joint Research Cen tre (JRC))\n\nCriticality safety analysis is needed at various stages of t he nuclear fuel cycle\, including the back-end of the fuel cycle\, i.e. re processing\, transport\, storage and final disposal of spent nuclear fuel (SNF). In the past\, criticality safety assessments for SNF management for out-of-reactor applications assumed that the fuel is in its most reactive condition\, which is usually prior to irradiation of the fuel in a reacto r. Since the 80's\, an effort is being made by the nuclear industry\, rese arch organisations and regulatory authorities to use more realistic and le ss conservative estimates of the nuclear reactivity of SNF by accounting f or the reduction in reactivity due to fuel burnup in a (sub-)criticality a nalysis. This concept is referred to as Burn Up Credit (BUC). \nSpecific p rogrammes to validate nuclear data of fission products that are important for criticality safety studies based on a BUC approach reveal shortcomings in these data. To improve the status of cross sections for fission produc ts for BUC approaches a dedicated programme was defined as part of a colla boration between the CEA Cadarache (France) and the JRC Geel (Belgium). It includes experiments at the time-of-flight facility GELINA to characteris e the samples that were used for the MINERVE experiments [1\,2\,3] and to produce accurate total and capture cross section data to improve the evalu ated data in the resonance region. This collaborative effort triggered the interest of other institutes and organisation such as the IFIN-HH (Romani a)\, INFN Bologna (Italy) and INRNE (Bulgaria) by participating in the exp eriments at GELINA and assisting in the data reduction and analysis.\nIn t his report\, the status of cross section data for $^{103}$Rh\, $^{107\,109 }$Ag and $^{155\,157}$Gd is discussed and results of a resonance shape ana lysis of new capture and transmission experiments at GELINA are presented. In addition\, recommendations to improve the evaluated cross section data in the resonance region for these nuclides are given. \n\n\n[1] Gruel et al.\, “Interpretation of fission product oscillations in the MINERVE rea ctor\, from thermal to epithermal spectra”\, Nucl. Sci. Eng. 169 (2011) 229.\n[2] Šalamon et al.\, “Neutron resonance transmission analysis of cylindrical samples used for reactivity worth measurements”\, J. Radioan al. Nucl.Chem. 321 (2019) 519.\n[3] Fei Ma et al.\, “Non-destructive ana lysis of samples with a complex geometry by NRTA”\, J. Anal. At. Spectro m. 35 (2020) 478.\n\nhttps://indico.frib.msu.edu/event/52/contributions/68 2/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/682/ END:VEVENT BEGIN:VEVENT SUMMARY:From fission yield measurements to evaluation: correlations of mul ti-observable analysis DTSTART:20220725T163000Z DTEND:20220725T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-663@indico.frib.msu.edu DESCRIPTION:Speakers: Grégoire Kessedjian (CEA Cadarache IRESNE/DER/SPRC/ LEPh)\n\nFrom fission yield measurements to evaluation: correlations of mu lti-observable analysis\nS.M. Cheikh 1\, G. Kessedjian 1\, A. Chebboubi 1\ , O. Serot 1 and C. Sage 2 \n\n1 CEA\, DES\, IRESNE\, DER\, SPRC\, LEPh\, Cadarache center\, F-13108 Saint Paul lez Durance\, France\n2 LPSC\, Unive rsité Grenoble-Alpes\, CNRS/IN2P3\, 38026 Grenoble\, France\n\nTopics for submission: Fission yield evaluation\nKeywords: fission yields\, evaluati on\, variance-covariance matrix\n\nAbstract: The study of fission yields h as a major impact on the characterization and understanding of the fission process and its applications. The fission products have a direct influenc e on the amount of neutron poisons that limit the fuel burnup and on the e valuation of the decay heat of the reactor after shutdown. \n Fission yi eld evaluation represents the synthesis of experimental and theoretical kn owledge in order to perform the best estimation of mass and independent fi ssion product yields. Today\, the lack of correlations between the differe nt fission observables induces inconsistencies in the evaluations. For ins tance\, the mass yield uncertainties are drastically overestimated while t his observable is the best known. This last decade\, different covariance matrices have been proposed but the experimental part of those are neglect ed. A consistent covariance matrix depends on the evaluation process. This consistency is deeply entangled to the statistical agreement between each data sets. Moreover\, the experimental covariance data are crucial in the evaluation process and covariance of model parameters does not represent the only contribution to the covariance matrix associated to evaluation. A large range of data are present in the EXFOR data bank but most of them c over partial mass range\, for different incident neutron energy\, without necessarily an absolute mass or isotopic identification. Thus\, the mix of data could lead to several solutions\, which then has to be ranked. \n T he LEPh Laboratory of CEA Cadarache develops a new methodology in the fiel d of the fission products for the future version of the JEFF-library. Stat istical test of datasets and data ranking are requested in order to define the confident region of the fission yield knowledge. A complete evaluatio n of the mass and independent fission product yields of the 235U(nth\,f) r eaction will be presented with the associated covariance matrix their impa ct on nuclear reactor calculations.\n\nhttps://indico.frib.msu.edu/event/5 2/contributions/663/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/663/ END:VEVENT BEGIN:VEVENT SUMMARY:Testing the hypothesis of a universal behavior of the cross-sectio n probability tables in the unresolved resonance region DTSTART:20220726T132400Z DTEND:20220726T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-689@indico.frib.msu.edu DESCRIPTION:Speakers: Matteo Vorabbi (Brookhaven National Laboratory)\n\nI n the unresolved resonance region (URR)\, cross sections for neutrons inte racting with nuclei have resonances that cannot be measured nor predicted\ , hence only statistical values are provided. Often\, proper simulations b y neutronic transport codes require special data and handling in the URR t o account for the variation in the cross sections in this region. The curr ent methodology used to describe this behavior is to construct the probabi lity table of the cross section. This table is generated by extrapolating the average resonance widths and average resonance spacings from the reson ance region\, generating Monte Carlo realizations of resonance ladders and using these realizations to construct the probability tables. Although th is is a standard and widely used technique\, it is computationally very ex pensive. Therefore\, an analytical fit would be preferable due to the cons iderable speed up of the computational time in real life applications. Sin ce the only input for these tables is the average resonance parameters\, w hich are functions of energy\, orbital angular momentum\, and total angula r momentum\, our hypothesis is that the probability tables might display a “universal” form for each reaction channel regardless of the nuclear species. If this is true\, a single functional form per reaction channel c ould be used to parametrize the probability table for every nucleus. To te st this hypothesis\, our goal is to generate probability tables for differ ent spin groups\, different reaction channels\, and different nuclei. As a first step\, these tables will be analyzed searching for regularities and \, if our hypothesis proves correct\, as a second step we will use modern computational techniques to produce accurate analytical fits for each spin group.\n\nhttps://indico.frib.msu.edu/event/52/contributions/689/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/689/ END:VEVENT BEGIN:VEVENT SUMMARY:Supplying Accurate Nuclear Data for energy and non-energy Applicat ions – The SANDA Euratom project DTSTART:20220726T130000Z DTEND:20220726T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-687@indico.frib.msu.edu DESCRIPTION:Speakers: Enrique M. González Romero (CIEMAT)\n\nThe SANDA H2 020-EURATOM project\, Supplying Accurate Nuclear Data for energy and non-e nergy Applications\, brings together the majority of the European nuclear data community (35 partners from 19 countries)\, infrastructures and resou rces to produce accurate and reliable nuclear data tools including data\, codes and methodologies that can be used to simulate\, analyse\, optimize\ , exploit and evaluate the safety of nuclear energy and non-energy applica tions.\n\nThe project covers all the aspects of the nuclear data cycle rel evant to the needs for energy applications\, including thermal and fast re actors and Accelerator Driven Systems (ADS)\, waste management\, storage\, reprocessing or disposal\, decommissioning of nuclear facilities and othe r non-energy applications such as metrology\, standards\, medical imaging techniques\, electron and proton cancer therapy and the production of isot opes for medical and industrial applications. \n\nSANDA has been built tak ing into account the High Priority Nuclear Data needs list from OECD/NEA a nd IAEA to provide the final users with immediately usable data and tools for the cases where this is feasible during the project duration. In parti cular\, it will bring at reach the target precision for some important iso topes/reactions. In addition\, the R&D of SANDA will contribute to prepare the path (new detectors\, facilities and methods) for future experiments addressing the remaining nuclear data needs in the years to come.\n\nThe s tructure of the project\, outlook of the expected results and a selection of results achieved will be presented during the conference\, including:\n \n - The progress on new techniques\, detectors and evaluation methods add ressing high priority data needs: (n\,f) and (n\, $\\gamma$) cross section s of highly radioactive isotopes\, advanced detection setups (n\,n)\, (n\, n’$\\gamma$) and (n\,xn) reactions\, $\\beta$-decay experiments and fiss ion yields.\n \n - Advances in data evaluation and uncertainty assess ment\, verification and validation of libraries and codes with selected in tegral experiments.\n \n - Nuclear data needs and applicability for nucl ear reactor safety and fuel cycle analysis.\n\nMore information on SANDA c an be found at http://www.sanda-nd.eu/.\n\nhttps://indico.frib.msu.edu/eve nt/52/contributions/687/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/687/ END:VEVENT BEGIN:VEVENT SUMMARY:From $^{232}Th$ $(n\,n’\\gamma)$ cross sections to level product ion and total neutron inelastic scattering cross sections. DTSTART:20220726T170600Z DTEND:20220726T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-707@indico.frib.msu.edu DESCRIPTION:Speakers: Roberto Capote\, Catalin Borcea\, Marian Boromiza\, Alexandru Negret\, Arjan Plompen\, Phillippe Dessagne\, Maelle Kerveno\, E liot Party\, Marc Dupuis\, Adina Olacel\, Markus Nyman\, Greg Henning\, Fr ancois Claeys\, Nicolas Dari Bako (IPHC/CNRS)\n\nFor the improvement of Ge neration IV nuclear reactors simulation\, accurate evaluated data are requ ired. Among others\, a reaction of interest is the neutron inelastic scatt ering as it modifies the energy distribution of neutrons. In the context o f the innovated Th/U cycle and for a better knowledge of the neutron inela stic scattering on thorium 232\, experiments have been performed at EC-JRC /GELINA. \nUsing the prompt gamma ray spectroscopy and the GRAPhEME device to detect the emitted photons\, 70 $(n\,n'\\gamma)$ transition cross sect ions have been measured . From these cross sections and nuclear structure data\, such as gamma intensities or internal conversion coefficients (ICC) \, one can determine inelastic level production cross sections and the tot al neutron inelastic scattering cross section. Assumptions had to be made regarding the multipolarity of several gamma transitions as they were not experimentally known. They enabled to exploit more data and obtain more le vel production cross sections. \nThe obtained cross sections\, presented i n this poster\, have shown that conversion electrons are a relevant parame ter. The misreading of this parameter and its associated uncertainty have a large impact on the total neutron inelastic scattering cross section unc ertainty. There is also a need to probe deeper the thorium 232 nuclear str ucture in order to get more accurate inelastic level production cross sect ions.\nComparisons made with the nuclear reaction code TALYS\, using defau lt parameters and improved input data (TENDL files)\, have revealed that i nelastic level production cross sections are not well predicted by the cod e. Studies are ongoing to improve the TALYS predictions.\n\nhttps://indico .frib.msu.edu/event/52/contributions/707/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/707/ END:VEVENT BEGIN:VEVENT SUMMARY:The effect of nuclear data uncertainties and sensitivities on the potential use of uranium nitride fuels in current and future light water r eactors. DTSTART:20220726T133600Z DTEND:20220726T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-692@indico.frib.msu.edu DESCRIPTION:Speakers: Robert William Mills (UK National Nuclear Laboratory )\n\nThe Advanced Fuel Cycle Programme funded by the UK Government through the Department for Business\, Energy & Industrial Strategy revolves aroun d developing capability and capacity for nuclear while seeking to reduce c osts across the nuclear lifecycle\, to ensure that nuclear can play a part in delivering secure\, low-carbon energy in the global market. This inclu des the development of Advanced Technology Fuels which are targeted at pro viding increased efficiency within current generation reactors. One novel fuel type that is being considered is uranium nitride to replace existing uranium dioxide fuels in current and future reactors. This fuel having imp roved thermal conductivity and higher actinide density. The use of such fu el will require the ability to accurately simulate its performance in a ra nge of operational and safety scenarios across the fuel cycle. \n\nThis wo rk considers the uncertainties introduced from nuclear data during calcula tions supporting manufacturing\, irradiation\, and waste management. The n uclear data sensitivities are studied from all sources but are principally concerned with the capture and scattering cross-sections of the nitrogen isotopes. As no experimental benchmarks exist to validate simulations of u ranium nitride fuel\, the original measurements and evaluations are studie d in terms of their uncertainties. Additionally\, the sensitivity of impor tant parameters such as criticality\, fuel life and increased ${^{14}}$C p roduction are considered over a range of possible uranium enrichments in n atural nitrogen and nitrogen reduced in ${^{14}}$N\n\nhttps://indico.frib. msu.edu/event/52/contributions/692/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/692/ END:VEVENT BEGIN:VEVENT SUMMARY:Application of Multipole humped fission barriers in the Unified Ha user-Feshbach and Exciton Model for Fission Nuclei DTSTART:20220726T151800Z DTEND:20220726T152100Z DTSTAMP:20260420T153400Z UID:indico-contribution-1102@indico.frib.msu.edu DESCRIPTION:Speakers: Yuan Tian (China Institute of Atomic Energy)\n\nWe h ave added the multipole humped fission barriers model into the Unified Hau ser-Feshbach and Exciton Model for Fission Nuclei (FUNF). With the help of the MINUIT\, we optimized the parameters of FUNF to reproduce the cross-s ection of neutron-induced $^{238}U$. The double-humped fission barrier can be used to explain the low energy resonance structure of $n+^{238}U$ fiss ion cross-section at low energy.\n\nhttps://indico.frib.msu.edu/event/52/c ontributions/1102/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1102/ END:VEVENT BEGIN:VEVENT SUMMARY:Expanded COG Criticality Validation Suite for Inter-Laboratory Ben chmark Data Comparison DTSTART:20220727T172200Z DTEND:20220727T172300Z DTSTAMP:20260420T153400Z UID:indico-contribution-1144@indico.frib.msu.edu DESCRIPTION:Speakers: Scott McKinley (Lawrence Livermore National Laborato ry)\, David Heinrichs (Lawrence Livermore National Laboratory)\, Soon Kim (Lawrence Livermore National Laboratory)\n\nThe COG suite of criticality b enchmarks has been formally expanded to 3\,368 to cover the entire energy range from thermal to fast neutron spectra under a variety of reflector an d moderator conditions and fissile materials. The number of benchmark cas es in each of these six major categories is summarized in Table 1.\n\n\nTa ble 1. Number of Benchmark Cases.\nCategory Number of Cases\nPU 766\nHEU 1 \,046\nIEU 206\nLEU 801\n233U 193\nMixed 356\nTotal 3\,368\n\n\nCOG result s have been compared with benchmark values from the International Critical ity Safety Benchmark Evaluation Project Handbook for ENDF/B-VII.1\, ENDF/B -VIII.0 and JEFF-3.3. COG results have been also compared with a MERCURY validation suite. Most of the results agree with the benchmark values with in ±3σ. Among the three cross section data\, cases with ENDF/B-VIII.0 pe rformed best with about 85% of the total cases within ±3σ range. Source s of error may come from 1) cross section data\, 2) possible errors from m odeling of the experiments\, or 3) errors in the benchmark evaluation or t he experiments themselves. A major inter-comparison project between COG\, MCNP\, MORET\, and SCALE for ENDF/B-VIII.0 and JEFF-3.3 is on-going. Int er-comparison with MERCURY is just beginning. LLNL participation in this project will result in development of significantly more COG benchmark cas es as our goal is to overlap the VALID\, WHISPER\, and IRSN compendia of c riticality benchmarks to the extent possible\, which will be beneficial to international code user communities.\n\n \n\n\nACKNOWLEDGMENTS\n\nThis wo rk was performed under the auspices of the U.S. Department of Energy by La wrence Livermore National Laboratory under Contract DE-AC52-07NA27344 and was funded by the U.S. Department of Energy Nuclear Criticality Safety Pro gram.\n\nhttps://indico.frib.msu.edu/event/52/contributions/1144/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1144/ END:VEVENT BEGIN:VEVENT SUMMARY:Role of transport coefficients in fission dynamics DTSTART:20220726T152100Z DTEND:20220726T152300Z DTSTAMP:20260420T153400Z UID:indico-contribution-1103@indico.frib.msu.edu DESCRIPTION:Speakers: Takahiro Wada (Department of Pure and Applied Physic s\, Kansai University)\, Kazuki Okada (Department of Pure and Applied Phys ics\, Kansai University)\n\nThe Langevin approach has been widely used in the study of fission. In this approach\, the fission process is described as the time evolution of the shape deformation of the nucleus\, and the fr agment mass and kinetic energy distributions can be calculated. The physic al inputs for the Langevin equation are the potential energy of deformatio n and two transport coefficients: the inertia and the friction tensor. The inertia tensor represents the geometric structure of the coordinates\, wh ile the friction tensor represents the coupling between collective and the rmal nucleonic degrees of freedom. The fission process is mainly governed by the potential energy\, such as the saddle points and the fission valley s. In the range from the ground state to the fission barrier\, nuclear def ormation can be roughly understood as a thermal equilibrium distribution d ue to the potential. On the other hand\, the process from the saddle to sc ission is a dynamical motion governed by both the potential and the transp ort coefficients. \n\nTo elucidate the role of the transport coefficients\ , we have adopted two alternative methods: the Smoluchowski limit and the Metropolis walk [1\, 2]. The Smoluchowski limit corresponds to the strong friction limit of the Langevin equation\, which does not include the inert ia tensor but depends on the friction tensor and the potential. The Metrop olis walk is a method to simulate a random walk on the potential. This met hod chooses to stay or to move to the next point depending on the thermal probability based on the Boltzmann factor. With this method\, the fission process can be calculated using only the potential. It should be noted tha t the Metropolis walk provides the evolution of the shape\, but it is not the time evolution.\n\nIn this study\, we compare the results calculated w ith the three methods in the actinide region. First\, we focus on $^{264}$ Fm which can be divided into a pair of stable double magic nuclei $(Z\,\\\ , N) = (50\,\\\,82)$ and hence strongly induces 132+132 symmetric fission. To simplify the comparison\, the temperature is fixed at 1 MeV and shell damping is neglected. As collective coordinates\, we adopt three deformati on parameters $\\{\\alpha$\, $\\alpha_1$\, $\\alpha_4\\}$ corresponding to elongation\, mass asymmetry\, and quadrupole deformation of fragments\, r espectively\, in Cassini shape parameterization [3]. Figure 1 shows the fr agment mass distribution calculated with the three methods. In the Metropo lis walk\, the yield of symmetric fission is much large than that of asymm etric fission. In contrast\, in the Langevin equation and the Smoluchowski limit\, the yields of symmetric and asymmetric fission are almost the sam e.\n\nTo understand the origin of this different behavior\, we analyze the fission paths along the fission valleys. The deformation energy is calcul ated with the microscopic-macroscopic method [4]. In the three-dimensional deformation space\, we obtain the symmetric and the asymmetric saddle poi nts which have almost the same height for $^{264}$Fm. These points are con nected to the symmetric and the asymmetric fission valleys\, respectively. Near scission\, the symmetric fission valley is deeper than the asymmetri c one. In the Metropolis walk\, it is found that the trajectories move fro m the asymmetric valley to the symmetric one. On the other hand\, in the L angevin equation and the Smoluchowski limit\, the change in the mass-asymm etric degree of freedom is suppressed by the friction tensor when the neck becomes thin. It should be noted that the friction tensor is calculated u sing the completed wall-and-window formula which is a sum of the one-body wall-and-window friction and the friction regarding the mass transfer betw een the fragments [5]. From this analysis\, we conclude that the Metropoli s walk needs to be used with caution\, in particular\, when the distributi on near the saddle region is different from that near scission. \n\nThe co mparison between the Langevin equation and the Smoluchowski limit shows on ly a small difference. This indicates that the driving and friction force strongly contribute to the fission dynamics. On the other hand\, around th e saddle point where those forces are weak\, it is found that the distribu tion of the trajectories is wider for the Langevin equation than for the S moluchowski limit. This can be due to the effect of the inertia tensor. \n \nAs another example\, we examined $^{236}$U and we found the asymmetric f ragment mass distributions in the three models. When the potential is exam ined\, the saddle point of the elongated symmetric fission is higher than that of the compact asymmetric fission and the asymmetric fission valley i s more pronounced. The peak position of the mass distribution essentially coincides with the bottom of the valley. In such a case\, Metropolis walk may give a similar result with that of the Langevin equation and the Smolu chowski limit. \n\nThe yield of the symmetric fission in $^{264}$Fm was sm aller than expected. We have performed the four-dimensional Langevin calcu lation by adding a new parameter $\\alpha_6$ corresponding to the octupole deformation of the fragments. In our study of the Fm isotope\, it was fou nd that the four-dimensional calculation better describes the saddle point and the valley of the symmetric fission. We found that the symmetric fiss ion is dominant for $^{264}$Fm. \n\n[1] J. Randrup and P. Moller\, Phys. Rev. Lett. **106**\, 132503 (2011).\n[2] J. Randrup and P. Moller\, Phys. Rev C **88**\, 064606 (2013).\n[3] V. V. Pashkevich\, Nucl. Phys. A **169* *\, 275 (1971).\n[4] V. M. Strutinsky\, Nucl. Phys. A **95** \, 420 (1967) .\n[5] J. Randrup and W. J. Swiatecki\, Nucl. Phys. A **429**\, 105 (1984) .\n\nhttps://indico.frib.msu.edu/event/52/contributions/1103/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1103/ END:VEVENT BEGIN:VEVENT SUMMARY:Unscented Transform Kalman filter for Optical model parameter unce rtainty quantification DTSTART:20220727T164200Z DTEND:20220727T164500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1122@indico.frib.msu.edu DESCRIPTION:Speakers: Aman Sharma (Department of Physics\, Banaras Hindu U niversity\, Varanasi-221005\, India)\, Aman Gandhi (Department of Physics\ , Banaras Hindu University\, Varanasi-221005\, India)\, A Kumar (Departmen t of Physics\, Banaras Hindu University\, Varanasi-221005\, India)\n\nhttp s://indico.frib.msu.edu/event/52/contributions/1122/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1122/ END:VEVENT BEGIN:VEVENT SUMMARY:Application of Machine Learning algorithms for experimental data p rocessing and estimation of 96Mo (n\, p) 96Nb reaction cross section DTSTART:20220727T163900Z DTEND:20220727T164200Z DTSTAMP:20260420T153400Z UID:indico-contribution-1121@indico.frib.msu.edu DESCRIPTION:Speakers: Sangeetha Prasanna Ram\n\n\\begin{center}\n\\textbf{ \\large Application of Machine Learning algorithms for experimental data p rocessing and estimation of $^{96}$\\emph{Mo}(n\, p)$^{96}$\\emph{Nb} rea ction cross section }\\\\ \n\\vspace{-10pt}\n\\hspace{10pt}\n\n% Author na mes and affiliations\nSangeetha Prasanna Ram$^1$\, Jayalekshmi Nair$^1$\, Singh Vivek Virendra$^2$\, Dhanamma Jagli$^2$\, S. Ganesan$^3$\, S. V. Sur yanarayana$^3$ \\\\\n\n\\hspace{10pt}\n\\vspace{-15pt}\n\n$^1$ Department of Instrumentation\, V. E. S. Institute of Technology\, Mumbai\, India 400 074 \\\\\n$^2$ Department of Master of Computer Application\, V. E. S. Ins titute of Technology\, Mumbai\,India 400074 \\\\\n$^3$ Former Scientist\, Nuclear Physics Division\, Bhabha Atomic Research Centre\, Mumbai\, India 400085 \\\\\n\\end{center}\n\\vspace{-20pt}\n\\begin{abstract}\nNuclear da ta available in articles and research papers\, goes through the nuclear da ta pipeline process comprising of acquiring published data\, compiling\, e valuating and processing them into high quality data prior to applying the m in various fields such as nuclear medicine\, nuclear power\, simulations and many more. Among the various steps in the nuclear data pipeline\, nuc lear data evaluation is the process of combining the experimental and theo retical model data for determining the optimally recommended value of nucl ear data such as reaction cross section\, along with its uncertainties\, o ver a large incident neutron energy range \\cite{1}. However\, experimenta l data available in IAEA-EXFOR database library \\cite{2}\, entered by exp erimenters based on the nuclear experiment performed by them\, do not cove r the entire range and are sparsely distributed. This results in the nucle ar data evaluators to largely depend on theoretical model data for nuclear data evaluation. To overcome this\, the nuclear data evaluators work on t he analysis of the experimental data and its covariance to estimate its va lues at the energy points where actual experimental data is unavailable.\n \\par In this study\, for the first time\, estimation of experimental dat a of $^{96}$\\emph{Mo}(n\, p)$^{96}$\\emph{Nb} reaction cross section data at neutron energies where actual data is not available\, is performed usi ng Machine Learning (ML) regression algorithms\, as shown in Fig \\ref{fig :my_label}. This has been performed by initially studying all the EXFOR pa pers corresponding to $^{96}$\\emph{Mo}(n\, p)$^{96}$\\emph{Nb} reaction f rom EXFOR database in order to understand the facility and procedure emplo yed during the nuclear data experiment. Then based on the detailed study i nclusion of an experimental data in the nuclear evaluation was decided and outliers were identified. At the same time\, a Python code for cleaning t he data and for identifying the outliers was also developed and the outcom e of both the methods were compared and found to be satisfactory. Also\, some of the experimental data was renormalized by considering the latest v alues of the attributes. \n\\par Further to the cleaning and preparing of nuclear experimental data\, it was then split as training and testing dat a in the ratio of 80:20 and an estimation model was developed based on tra ining data set. Three popular simple linear regression ML algorithms namel y Ordinary Least Square (OLS)\, Least Absolute Shrinkage and Selection Ope rator (Lasso) and Ridge regression \\cite{3}\, were employed in this study \, for developing the model. Lasso and Ridge regression techniques\, which are less influenced by large outliers unlike OLS technique\, are improvis ations of least square regression analysis. These regression techniques pe rform both variable selection and regularization for improving the predict ion accuracy. The training data points of $^{96}$\\emph{Mo}(n\, p)$^{96}$\ \emph{Nb} reaction cross section along with its uncertainties\, were used by the ML algorithms\, to learn and develop the model parameters. The opti mal model was selected based on the minimum root mean square error for pre diction. The selected model was then subjected to the test data and based on its prediction accuracy\, tuning of the model hyperparameters was perfo rmed to get the best results \\cite{4}. \n\\par Finally\, the model was va lidated based on unseen data and the model giving the best prediction accu racy was selected as the most suitable model. For this study of developing the regression model for experimental data of $^{96}$\\emph{Mo}(n\, p)$^{ 96}$\\emph{Nb} reaction cross section\, both Lasso and Ridge regression te chniques were found to be giving marginally better results than the OLS re gression technique.\\vspace{-10pt}\n\\begin{figure}[!h]\n \\centering\n \\includegraphics[scale=0.89]{image.png}\n \\vspace{-19pt}\n \\caption{Experimental data processing and estimation using Machine Learn ing algorithms}\n \\label{fig:my_label}\n\\end{figure}\n\\end{abstract} \n\\vspace{-35pt}\n\\begin{thebibliography}{}\\vspace{-10pt}\n\\bibitem{1} Donald L. Smith (1996)\, \\emph{Some guidelines for the Evaluation of Nucl ear data}\, BNL-NCS-63006.\\vspace{-10pt}\n\\bibitem{2}IAEA-EXFOR Database available at http://www-nds.iaea.org/exfor.\\vspace{-10pt}\n\\bibitem{3}F rank Emmert-Streib\, Matthias Dehmer (2019)\,\n\\emph{"High-Dimensional LA SSO-Based Computational Regression Models: Regularization\, Shrinkage\, an d Selection\, Machine Learning and Knowledge Extraction"}\, Vol. 1(1)\, 35 9-383.\\vspace{-10pt}\n\\bibitem{4}Sangeetha Prasanna Ram\, Jayalekshmi Na ir\, et al.\, \n\\emph{"Application of Kalman filtering technique for Eval uation of neutron cross section data of 100Mo (n\, 2n) 99Mo reaction"}\, a ccepted for publication in - Nuclear Instruments and Methods in Physics Re search Section A\, Article No. 165850. \\vspace{-10pt}\n\\end{thebibliogra phy}\n\nhttps://indico.frib.msu.edu/event/52/contributions/1121/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1121/ END:VEVENT BEGIN:VEVENT SUMMARY:Towards a Langevin Model for the Stochastic Dynamics of Nuclear Fi ssion DTSTART:20220726T152300Z DTEND:20220726T152500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1104@indico.frib.msu.edu DESCRIPTION:Speakers: Trevor Sprouse (Los Alamos National Laboratory)\, Ma tthew Mumpower\, Ionel Stetcu\n\nA robust description of the process of nu clear fission is essential to many research domains ranging from nuclear e nergy\, national security\, and nuclear data. However\, owing to the nucle ar many-body problem\, a description of fission based on nucleon-nucleon interactions is unfeasible given current computational limitations\, which has led to a number of alternative methods that greatly reduce the overal l complexity of this difficult problem. In this work\, we present results of recent efforts to model the process of nuclear fission from the perspec tive of a microscopic-macroscopic model of the atomic nucleus\, where fiss ion proceeds from an initially excited state to scission as a stochastic p rocess according to a progression of increasingly sophisticated treatments of the stochastic dynamics. In contrast with our past work\, which has tr eated fission in the strongly-damped limit described by a random-walk proc ess\, this approach furnishes the kinetic energies associated with the nas cent fragments\, which is subsequently used to model the de-excitation pro perties of fission fragments. LA-UR-21-29350\n\nhttps://indico.frib.msu.ed u/event/52/contributions/1104/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1104/ END:VEVENT BEGIN:VEVENT SUMMARY:Fission Cross-section Measurement of U-233 with Time-of-Flight Met hod at the KURNS-LINAC DTSTART:20220725T173000Z DTEND:20220725T174200Z DTSTAMP:20260420T153400Z UID:indico-contribution-675@indico.frib.msu.edu DESCRIPTION:Speakers: Jun-ichi Hori (Kyoto University)\n\nAs engineering d iscussions of the feasibility of new reactor systems\, it is necessary to evaluate the impact of the fuels and materials for the neutronics characte ristics such as criticality\, conversion rate\, and fuel balance. It is im portant to perform the validation of 232Th and 233U nuclear data for a tho rium-based nuclear reactor\, because those nuclear data contribute signifi cantly to the neutronics characteristics of the reactor.\nWe have measured the fission cross section of 233U by the neutron time-of-flight method us ing a 12 m flight path and a 46-MeV electron linear accelerator at the Ins titute for Integrated Radiation and Nuclear Science\, Kyoto University (KU RNS-LINAC). Experiments were performed with two different linac operation modes. One was for low-energy measurement below about 1 eV with 50 Hz and an average current of about 18 μA. Another was for high-energy measuremen t above 1 eV with 200 Hz and an average current of about 72 μA. In the la tter case\, a Cd sheet with 0.5-mm thickness was inserted into the TOF bea m line to prevent the overlap component from the previous pulse due to hig h frequency. Pulse width was 100 ns for both operation modes. \nA back-to- back type fission chamber was used for the detection of the fission fragme nts and to discriminate the decayed alpha-particles. A sample of uranium-2 33 oxide was electrodeposited on the stainless steel disk (28 mm in diamet er and 0.2 mm thickness). A relative measurement to the 6Li(n\,α) standar d reaction was also made using a 6Li-glass detector\, and normalized to th e evaluated value from the JENDL-4.0 at thermal neutron energy. We have ob tained the fission cross sections of 233U in the energy region from 0.002 eV to 1 keV.\nThe present results were compared with the previous experime ntal data and the evaluated values. Moreover\, the resonance parameters we re obtained by using SAMMY code for the principal resonances below about 1 00 eV.\n\nhttps://indico.frib.msu.edu/event/52/contributions/675/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/675/ END:VEVENT BEGIN:VEVENT SUMMARY:Theoretical calculation and evaluation for n+232\,234\,236\,237U r eactions DTSTART:20220726T152500Z DTEND:20220726T152700Z DTSTAMP:20260420T153400Z UID:indico-contribution-1105@indico.frib.msu.edu DESCRIPTION:Speakers: Yinlu Han (China Institute of Atomic Energy)\n\nAbst ract\nIn order to reduce the uncertainties in the design and operation of accelerator-driven systems (ADSs)\, high-precision nuclear data for neutro n- and proton-induced reactions on a variety of isotopes in the energy ran ge below 200 MeV are necessary. As the important component of the spent fu el of current nuclear power plants\, U isotopes will be loaded into ADSs t o produce energy and neutrons. Therefore\, accurate nuclear data for neutr on-induced reactions on U isotopes are needed in the calculation of neutro n and energy balance and the prediction of transmutation rates of the vari ous radioactive species. To meet this requirement\, all cross sections\, a ngular distributions\, energy spectra\, double differential cross sections of neutron\, proton\, deuteron\, triton\, helium-3 and alpha emissions an d the number of neutron per fission for n+232\,234\,236\,237U reactions ar e consistently calculated and analyzed by theoretical nuclear models in th e energy range of En≤200 MeV. The optical model\, the unified Hauser-Fes hbach theory and the exciton model\, the evaporation models\, the linear a ngular momentum dependent exciton state density model\, the fission model\ , the intranuclear cascade model\, the distorted-wave Born approximation a nd the coupled channel theory. The calculated results reproduce the experi mental data well\, and the variation tendency of reaction cross sections r elated to the target mass numbers is obtained.\n\nhttps://indico.frib.msu. edu/event/52/contributions/1105/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1105/ END:VEVENT BEGIN:VEVENT SUMMARY:Gamma ray spectrum measurement from capture reactions of Uranium-2 38 for thermal and resonance energy neutrons DTSTART:20220725T170600Z DTEND:20220725T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-672@indico.frib.msu.edu DESCRIPTION:Speakers: Yasushi Nauchi (Central Research Institute of Electr ic Power Industry)\n\nFor safe use of nuclear reactor core\, slowing down of neutrons and reaction rates inside the core should be predicted accurat ely. They have made tremendous efforts to improve the calculation methods and the nuclear data for the prediction. However\, the calculated neutron spectrum and the reaction rates have been validated only by post irradiati on measurement of gamma rays. As an in-situ measurement technique\, the au thors have focused on spectrum measurement of prompt gamma rays. Nauchi et al. have succeeded in estimation of 238U(n\,γ) reaction rates by detecti on of 4060 keV gamma rays [1]. Then they tried to determine energy of neut ron which induces capture reactions of 238U. For that\, neutron energy dep endent gamma ray spectrum was measured for 238U at KURNS LINAC neutron sou rce facility. Uranium metallic samples of the natural enrichment were irra diated by the pulsed neurons of white spectrum. The gamma rays were measur ed with a HP-Ge detector of 35% relative efficiency. The energy of neutron s which induces capture was measured by the time of flight technique. The gamma ray spectrum measured for the neutrons of thermal energy and resonan ces (En=6.67eV and 20.9eV) are shown in Fig. 1. Compared to the published literature [2]\, the spectrum was obtained with better resolution\, and di fferences in peak gamma ray spectra for the thermal and resonances energy neutrons were observed. By measuring the gamma ray spectrum from a reactor core\, the reaction rates ratio of the thermal and the resonance neutron energy might be unfolded taking advantage of the difference of the gamma r ay spectrum.\n[1] Y. Nauchi\, T. Sano\, H. Unesaki\, et al.\, Proceedings of 11th International conference on nuclear criticality safety\, ICNC 2019 \, September 15-20\, 2019 – Paris\, France.\n[2] H. Harada S. Goko\, A. Kimura et al.\, Journal of Korean Physical Society 59(2) 1547-1552\, 2011. \n\nhttps://indico.frib.msu.edu/event/52/contributions/672/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/672/ END:VEVENT BEGIN:VEVENT SUMMARY:Calculations and Evaluations of n+ 107\,109Ag Reactions below 20 M eV DTSTART:20220727T164500Z DTEND:20220727T164800Z DTSTAMP:20260420T153400Z UID:indico-contribution-1124@indico.frib.msu.edu DESCRIPTION:Speakers: Yinlu Han\, Min Jia (North China University of Water Resources and Electric Power)\, Tingtai Wang (Zhongyuan University of Te chonology)\n\nAll the cross sections of neutron-induced reactions\, angula r distributions\, energy spectra\, and double-differential cross sections for n+ 107\, 109Ag reactions are calculated and analyzed below 20 MeV by u sing UNF code. The isomeric cross sections are also calculated. Furthermor e the theoretical results are compared with the available experimental dat a and the evaluated results in ENDF/B-Ⅷ.0\, JENDL-4.0\, and TENDL-2019.\ n\nhttps://indico.frib.msu.edu/event/52/contributions/1124/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1124/ END:VEVENT BEGIN:VEVENT SUMMARY:Fission product depletion chain simplification method based on qua ntitative contribution function DTSTART:20220727T170900Z DTEND:20220727T171200Z DTSTAMP:20260420T153400Z UID:indico-contribution-1132@indico.frib.msu.edu DESCRIPTION:Speakers: Lili Wen (China Institute of Atomic Energy)\n\nRecen tly\, an advanced neutronics lattice code called Kylin-2 has been develope d by Nuclear Power Institute of China. In order to develop multi-group lib rary for Kylin-2\, a fission product depletion chain simplification method was proposed in this paper to generate burnup data for the multi-group li brary. This method constructed two quantitative contribution functions bas ed on the thought of transmutation trajectory analysis (TTA)\, according t o these contribution functions\, a code was developed to identify importan t fission product nuclides and then a simplification depletion chain was r econstructed using these important nuclides. Verification and validation s howed that this method successfully identify important fission product nuc lides and accurate the depletion accuracy.\n\nhttps://indico.frib.msu.edu/ event/52/contributions/1132/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1132/ END:VEVENT BEGIN:VEVENT SUMMARY:Calculation of fission product mass distribution by using a semi-e mpirical model and neutron multiplicity data DTSTART:20220726T152900Z DTEND:20220726T153100Z DTSTAMP:20260420T153400Z UID:indico-contribution-1106@indico.frib.msu.edu DESCRIPTION:Speakers: Peter Schillebeeckx\, Tae-Sun Park (Institute for Ba sic Science)\, Young-Ouk Lee (KAERI)\, Seung-Woo Hong (Sungkyunkwan Univer sity)\, Jounghwa Lee\n\nFission fragments are highly excited after scissio n\, and they de-excite by the emission of neutrons and the subsequent gamm a emission. The products before and after the emission of neutrons and gam mas are called pre- and post-neutron fission fragments\, respectively. Pre - and post-neutron emission fission product yields (FPY) can be related th rough the emitted neutrons\, i.e. neutron multiplicity. To have comprehens ive understanding of the fission process\, one need to describe both pre- and post-neutron FPY data by taking into account the neutron multiplicity. \nIn this work\, we attempt to describe post-neutron emission FPY by using pre-neutron FPY and neutron multiplicity data. We propose a simple empiri cal model for the calculation of pre-neutron FPY. Then\, the experimental data for the neutron multiplicity of each fission fragment mass are used t o calculate the post-neutron FPY. The probability of the number of emitted neutrons from each fragment is not known\, and thus a few different assum ptions for the neutron multiplicity are made. Despite naive approximations \, calculated post-neutron fission product mass distributions reproduce th e experimental data well. In this manner\, we may describe the pre- and po st-neutron emission FPY and the neutron multiplicity in a consistent way.\ n\nhttps://indico.frib.msu.edu/event/52/contributions/1106/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1106/ END:VEVENT BEGIN:VEVENT SUMMARY:Charge polarization calculated with a microscopic model for the fi ssion fragments of U-236 DTSTART:20220727T133600Z DTEND:20220727T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-1087@indico.frib.msu.edu DESCRIPTION:Speakers: Satoshi Chiba\, Chikako Ishizuka\, Shin Okumura\, Sh uichiro Ebata\n\nThe charge distribution of fission fragments is a signifi cant quantity to estimate and evaluate the neutron emission yields from fi ssion fragments. The distribution has been evaluated as the deviation fr om the unchanged charge distribution (UCD) assumption in which the fragmen ts keep the neutron-proton ratio of the fissile parent nucleus. The devia tion is called the charge polarization (CP). \n\nFor the major fission rea ctions in the nuclear reactor\, their CP have been compiled in a library c alled Wahl's systematics. Although the library is designed for the nucle ar engineering field\, this is not suitable to predict the fission fragmen ts from unmeasured fissile nuclei.\n\nIn order to provide the CP of fragme nts generated from unknown fissile nuclei without empirical ways\, we sugg est a new method based on the microscopic nuclear theory. We employ the mean-field theories\, which are the constrained Skyrme Hartree-Fock+BCS th eory and the canonical-basis time-dependent Hartree-Fock-Bogoliubov theory \, represented in three-dimensional space. \n\nIn the presentation\, we wi ll report the calculated CP of the fission products on the $^{236}$U\, ass uming the reaction of $^{235}$U absorbed a thermal neutron. We will discu ss the effectiveness of our method and will mention the dynamical effects on the CP through the comparison among results calculated by static\, dyna mic mean-field models and the data in Wahl's systematics.\n\nhttps://indic o.frib.msu.edu/event/52/contributions/1087/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/1087/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Improving the prediction of TSL on-the-fly based on de ep neural networks using experimentally measured double differential data and dynamic structure factor DTSTART:20220726T152700Z DTEND:20220726T152900Z DTSTAMP:20260420T153400Z UID:indico-contribution-1107@indico.frib.msu.edu DESCRIPTION:Speakers: Vaibhav Jaiswal (Institut de Radioprotection et de S ûreté Nucléaire (IRSN))\n\n**Improving the prediction of TSL on-the-fly based on deep neural networks using experimentally measured double differ ential data and dynamic structure factor** \n\nVaibhav Jaiswal$^{1\,*}$\, Arthur Pignet$^2$\, and Luiz Leal$^1$\n\n$^1$Insititut de Radioprotection et de Sûreté Nucléaire (IRSN)\, Fontenay-aux-Roses\, France\n$^2$MINES ParisTech\, PSL - Research University\, Centre for Material Forming (CEMEF )\, CNRS UMR 7635\, CS 10207\, Sophia Antipolis Cedex\, 06922\, France\n\n $^*$Corresponding author: vaibhav.jaiswal@irsn.fr\n\n\nThe slowing down of neutrons generated in a fission reaction\, from the MeV range to the meV range\, is governed by the scattering process. In the low energy region\, when the energy of the neutron is comparable to the energy of the scatteri ng medium\, the probability of this interaction is described by Thermal Sc attering Law (TSL). TSLs for moderator materials takes into account the dy namical properties of the system and governs the energy and momentum excha nge between the neutron and the moderator. The TSLs libraries available to users in the ENDF evaluations are for fixed temperatures\, and one makes various approximations and mechanisms to use for non-available temperature s in the evaluations. It is well known that direct interpolation of the TS L to obtain data at intermediate temperature leads to misleading results [ 1]. A recent approach to overcome this limitation is to interpolate the LE APR parameters and re-run NJOY to obtain TSL at the required temperatures [2]. This is not a practical solution when multi-physics calculations dema nd TSL for a very fine grid of temperatures and running NJOY on-the-fly wi ll not be a feasible solution. On the other hand\, storing TSLs for a fine grid of temperatures is memory and data intensive to use with Monte Carlo codes.\n\nThis paper demonstrates the capabilities of deep neural network s to overcome the above challenges and that TSLs can be reconstructed for any temperatures preserving the dynamics of the system. This approach prov ides reliable and accurate results within the required memory and size of the data. Several recent works have been carried out in this domain that i nvolves both machine learning and deep learning to carry out nuclear cross -section data processing on-the-fly. In particular\, a recent work for TSL \, focuses on training the neural network model using the alpha\, beta\, a nd temperature as parameters [3]. This paper proposes a new methodology to incorporate not only the alpha\, beta and temperatures\, but also the exp erimentally measured double differential data and the dynamic structure fa ctor to improve the deep learning network's prediction capabilities and ac curacy.\n\nPresently\, the most common thermal scattering cross-section ev aluation tool is the LEAPR module of the NJOY code. In the LEAPR framework \, the entire physics related to the dynamic structure factor of the mater ial is reduced as a function of the phonon frequency spectrum. This method ology seems to perform well but can be improved involving the experimental ly measured dynamic structure factor and the double differential data. Dou ble differential data and the derived dynamic structure factor for light w ater data measured at the SNS facility at the Oak Ridge national laborator y [4-5] have been used in this work to train the deep learning model. This paper demonstrates an example of TSL for light water\, but this method ca n be applied on a more generalized approach to proceed towards on-the-fly sampling of the TSL in Monte Carlo codes.\n\n[1] W. Haeck and N. Leclaire. “Thermal scattering data and criticality safety”\, International Conf erence on the Physics of Reactors “Nuclear Power: A Sustainable Resource ”\, Casino-Kursaal Conference Center\, Interlaken\, Switzerland\, Septem ber 14-19\, 2008.\n[2] Vaibhav Jaiswal\, “Theoretical and experimental a pproach towards generation of thermal scattering law for light water”\, Ph.D. thesis\, University of Lille\, 2018.\n[3] C. A. Manring\, A. I. Hawa ri\, “Development of neural thermal scattering (NeTS) modules for reacto r multi-physics simulations”\, EPJ Web of Conferences 247\, 20004 (2021) .\n[4] Luiz Leal\, Vaibhav Jaiswal\, and Alexander I. Kolesnikov\, “High -resolution neutron time-of-flight measurements for light water at the Spa llation Neutron Source (SNS)\, Oak Ridge National Laboratory”\, EPJ Web of Conferences 239\, 14005 (2020).\n[5] Vaibhav Jaiswal\, Luiz Leal\, and Alexander I. Kolesnikov\, “Analysis of the time-of-flight neutron scatte ring cross-section data for light water measured at the SEQUOIA spectromet er\, Spallation Neutron Source (SNS)”\, EPJ Web of Conferences 239\, 140 07 (2020).\n\nhttps://indico.frib.msu.edu/event/52/contributions/1107/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1107/ END:VEVENT BEGIN:VEVENT SUMMARY:Target Accuracy Requirements for MYRRHA DTSTART:20220726T140000Z DTEND:20220726T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-697@indico.frib.msu.edu DESCRIPTION:Speakers: Pablo Romojaro (SCK CEN)\n\nThe Multi-purpose hYbrid Research Reactor for High-tech Applications (MYRRHA) is a flexible experi mental facility being designed at SCK CEN\, Mol\, Belgium. It is conceived to operate both in sub-critical mode\, as an Accelerator Driven System\, and in critical mode\, as a lead-bismuth cooled fast reactor.\n\nIn order to comply with MYRRHA reactor design requirements\, uncertainties must be quantified. In nuclear reactor design the uncertainties mainly come from m aterial properties\, fabrication tolerances\, operating conditions\, simul ation tools and nuclear data. Indeed\, the uncertainty in nuclear data is one of the most important sources of uncertainty in reactor physics simula tions\, and significant gaps between the uncertainties and the target accu racies (i.e.\, maximum acceptable uncertainties for a certain parameter) h ave been systematically shown in the past. Meeting the target accuracy is required not only to achieve the requested level of safety for MYRRHA\, bu t also to minimize the increase in the costs due to additional safety meas ures.\n\nTarget accuracy assessments allow identifying nuclear data needs and requirements (by nuclide\, nuclear reaction and energy channel). Since the accuracy and priorities strongly depend on the assumed initial uncert ainty data and since numerous nuclear data libraries with updated uncertai nty evaluations have been released in the recent years (i.e.\, ENDF/B-VIII .0\, JEFF-3.3\, TENDL-2019) and new evaluations are currently being produc ed\, such as JEFF-4 and JENDL-5\, it is necessary to provide updated targe t accuracies for advanced reactor design parameters and nuclear data.\n\nT herefore\, in this work we present a Target Accuracy Requirement Assessmen ts of the latest MYRRHA reactor design. The capability of calculating the uncertainty data requirements has been implemented in SANDY\, a Python pac kage that can read\, write and perform a set of operations on nuclear data files written in the standard ENDF-6 format. Afterwards\, SANDY has been used to perform Target Accuracy Requirement Assessments on a homogenised o n fuel assembly level MYRRHA reactor model with JEFF-4T0 and other state-o f-the-art nuclear data libraries. Nuclides and reactions in need of improv ement have been identified to provide feedback to the NEA Nuclear Data Hig h Priority Request List and the JEFF community.\n\nhttps://indico.frib.msu .edu/event/52/contributions/697/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/697/ END:VEVENT BEGIN:VEVENT SUMMARY:Experimental spectrum average cross sections in $^{252}$Cf(sf) neu tron field and its impact on evaluation of Neutron Standards DTSTART:20220727T170000Z DTEND:20220727T170300Z DTSTAMP:20260420T153400Z UID:indico-contribution-1129@indico.frib.msu.edu DESCRIPTION:Speakers: Roberto Capote (IAEA NDS)\n\nEvaluation of Neutron D ata Standards have been a critical component of ENDF/B library releases wh ich is currently coordinated by the IAEA. The latest Neutron Data Standard s were released in 2017 [1] and were adopted for the ENDF/B-VIII.0 library [2]. Since very early on\, the Neutron Data Standards have been derived using the Bayesian GMA code originally developed by W. Poenitz with an ext ensive database of vetted experimental data. These data include the simple st integral data\, namely spectrum averaged cross sections (SACS) measured in the reference 252Cf(sf) reference neutron field. \nNote that the refer ence Cf(sf) neutron field has been originally evaluated by Mannhart and ha s been validated as a reference neutron field in IRDFF-II library [3]. We can use the reference Cf(sf) neutron spectra to convolute evaluated Neutro n Standard cross sections\, to derive SACS and corresponding uncertainties . At the same time Mannhart evaluated the experimentally measured SACS in the reference Cf(sf) spectrum [4]. A comparison of fission SACS measured i n the Cf(sf) spectrum for dosimetry reactions U235(n\,f)\, Np237(n\,f)\, U 238(n\,f)\, and Pu239(n\,f) vs fission SACS derived from Neutron Standard s is given in table 1.\n\nTable 1: Fission SACS calculated in a Cf-252(sf) reference neutron spectrum \n IAEA STD 2017 [3] Mannhart Eva l. [4] Ratio STD/Mannhart \nU235nf 1.2267E+03 (1.21) 1 .210E+3 (1.2) 0.986 \nU238f 3.2154E+02 (1.29) 3.257E+2 (1.6 ) 1.013 \nPu239f 1.7978E+03 (1.25) 1.812E+3 (1.4) 1.0 08 \nNp237f 1.3598E+03 (1.70) 1.361E+3 (1.6) 1.001 \n \nTable 2: Spectral indexes (SI) in a Cf-252(sf) reference neutr on spectrum \n IAEA STD 2017 [3] Mannhart Eval. [ 4] Ratio STD/Mannhart \nPu9f/U5f 1.465 1.4975 0.978 \nU8f/U5f 0.262 0.269 0.973 \nNp7/U5f 1.108 1. 125 0.985 \n \nU-235 fission SACS deri ved from the IAEA STD are -1.2% lower than Mannhart evaluation while Pu-23 9 fission SACS are +0.8% higher. Those ratios result in a 2.2% underestima tion of the Pu9f/U5f spectral index calculated with STD cross sections com pared to those values derived from Mannhart evaluation. A similar effect is seen for the U8f/U5f SI. \n\nA similar discrepancy was observed by Casp erson [5] in fission reaction rates in critical assemblies. In particular\ , the C/E Godiva (HMF001) data and the C/E Flaptop-25 (HMF028) data are li sted in Tables 3 and 4\, where the underestimated SI are highlighted in cy an.. \n\nTable 3. Godiva SI – HMF001 (exp. data from ENDF/B-VII.1 paper [6]\, exp B evaluated by Hansen)\n Measured Calc. C/E\nPu9f/U5f 1.4152(1.0%) 1.3841(1.7%) 0.978\nNp7/U5f 0.8516(1.4%) 0.8338(2.1%) 0.979\nU8f/U5f 0.16 43 (1.0%) 0.1584(1.7%) 0.972\n\nTable 4. Flaptop-25 – HMF028 (exp. Data from ENDF/B-VII.1 paper [6]\, exp B evaluated by Hansen)\nMeasured calc C/E\nPu9f/U5f 1.3847 (0.9%) 1.3615 (1.7%) 0.985 \nNp7f/U5f 0.7804 (1.3%) 0.7751 (2 .1%) 0.9932 \nU8f/U5f 0.1492 (1.1%) 0.1450 (1.7 %) 0.972 \n\nFinally note that published NIFFTE PU9f/U5f [7] an d U8f/U5f [8] cross-section ratios are larger than corresponding STD ratio s by about 2% which is like above discussed discrepancies. Further investi gation of the existing SACS experiments and of the SACS evaluation is warr anted. A new evaluation of measured SACS by using Mannhart code with updat ed inputs from experimental data will be presented\; results will be compa red to above described calculations. \n\n[1] A.D. Carlson\, V.G. Pronyaev\ , R. Capote et al.\, Evaluation of the Neutron Data Standards\, Nucl. Data Sheets 148\, 143-188 (2018)\n[2] D.A. Brown et al.: “ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections\, New Standards and Thermal Scattering Data”\, Nuclear D ata Sheets 148 (2018) 1–142.\n[3] A. Trkov et al\, IRDFF-II: A New Neutr on Metrology Library\, Nucl. Data Sheets 163\, 1-108 (2020)\n[4] W. Mannha rt in International Reactor Dosimetry File 2002 (IRDF-2002)\, Tech. Report Series 452\, IAEA (2006)\; numerical data: https://www-nds.iaea.org/irdf2 002/. \n[5] R.J. Casperson\, “The benefit of adjusting with criticality and reaction rate data”\, mini-CSWEG 2021. \n[6] M.B. Chadwick\, M.W. He rman\, P. Oblozinsky et al.\, ENDF/B-VII.1 nuclear data for science and te chnology: cross sections\, covariances\, fission product yields and decay data\, Nucl. Data Sheets 112\, 2887 (2012)\n[7] L. Snyder et al.\, “Meas urement of the 239Pu(n\,f)/235U(n\,f) Cross-Section Ratio with the NIFFTE fission Time Projection Chamber\, arXiv 2107.02881 [nucl-ex] (2021).\n[8] R.J. Casperson et al\, Measurement of the normalized U-238(n\,f)/U-235 (n\ ,f) cross section ratio from threshold to 30 MeV with the NIFFTE fission T ime Projection Chamber\, Phys. Rev. C97 (2018) 034618\n\nhttps://indico.fr ib.msu.edu/event/52/contributions/1129/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1129/ END:VEVENT BEGIN:VEVENT SUMMARY:Comparison of double-differential cross section between nuclear da ta library and experimental data for photoneutron production DTSTART:20220726T144500Z DTEND:20220726T144800Z DTSTAMP:20260420T153400Z UID:indico-contribution-1088@indico.frib.msu.edu DESCRIPTION:Speakers: Kim Tuyet Tran (SOKENDAI)\n\nRadiation shielding and calculation are essential for the construction and operation of accelerat or facilities. High energy gamma-rays in accelerators can produce secondar y neutrons\, which can penetrate through shielding materials and produce a dditional dose rate by activating accelerator components\; thus\, the doub le differential cross sections (DDXs) of photoneutron are very essential. Calculation of radiation and shielding in accelerators can be carried out by Monte Carlo simulation tools using nuclear data library (NDL). The DDXs of ($\\gamma$\,xn) reactions of a polarized photon beam with the mono ene rgy of 16.6 MeV and different materials (including Pb\, Au\, Sn\, Fe\, Cu\ , and Ti) are reported in Reference [1]. In this study\, we will show the comparisons in the DDXs between the experimental data measured in Referenc e [1] and the DDXs from NDL for medium-heavy atomic mass targets. Our pyth on-based software extracted the DDXs from NDL to construct the neutron ene rgy spectra\, which were later analyzed considering the abundances of each target's isotopes\, energy resolution of photon beam\, and energy resolut ion of neutron detectors. For Pb\, Au\, Sn and Cu targets\, the experiment al DDX data at neutron energy higher 4 MeV are larger than the DDX values obtained from NDL. For Fe and Ti targets\, the experimental DDX data are q uite consistent with that of the NDL. The inconsistency between the neutro n spectra of experimental data and NDL implies a need to improve physical models in generating the spectrum of photoneutron.\n\nKeywords: differenti al double cross-section\, photoneutron\, polarized monoenergetic photon.\n [1] T.K. Tuyet\, T. Sanami\, H. Yamazaki et al.\, “Energy and angular di stribution of photo-neutrons for 16.6 MeV polarized photon on medium-heavy targets”\, Nuclear Inst. and Methods in Physics\, A 989 (2021)164965.\n \nhttps://indico.frib.msu.edu/event/52/contributions/1088/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1088/ END:VEVENT BEGIN:VEVENT SUMMARY:GRE@T-PIONEeR: teaching the nuclear data pipeline using innovative pedagogical methods DTSTART:20220725T194500Z DTEND:20220725T200900Z DTSTAMP:20260420T153400Z UID:indico-contribution-717@indico.frib.msu.edu DESCRIPTION:Speakers: N. Garcia-Herranz\, C. Demazière\, S. Dulla\, R. Mi ró\, R. Macian\, E. Buchet\, F. Errecart\, M. Szieberth\, Oscar Cabellos\ n\nGRE@T-PIONEeR - GRaduate Education Alliance for Teaching the PhysIcs an d safety Of NuclEar Reactors - is a new project funded by the Euratom – Horizon 2020 Framework Programme. The project started on November 1st\, 20 20 for a duration of three years and gathers eight universities throughout Europe.\n\nThe project aims at developing and providing specialised and a dvanced courses in computational and experimental reactor physics at the g raduate level (MSc and PhD levels) and post-graduate level\, as well as th e staff members working in the nuclear industry.\n\nAlthough reactor physi cs has always been a core discipline in nuclear engineering\, computationa l reactor physics relies on sophisticated models\, databases and algorithm s\, which the engineer needs to understand\, so that the tools are used mo st efficiently and in relevant applications. Moreover\, these computationa l courses are often taught via advanced courses with fewer students.\n\nOn e of the Work Package of GRE@T-PIONEeR is devoted to a specific course on the nuclear data pipeline processes and the role of nuclear data for calcu lations of nuclear reactor systems. It covers all steps starting from the measurements to their validation and final use in nuclear reactor calculat ions. The main topics covered in this course are: i) the process of genera tion and evaluation of nuclear data libraries\, ii) the processing of nucl ear data libraries for use in nuclear applications\, iii) the assessment o f nuclear data uncertainties\, iv) the importance of nuclear data adjustme nts\, v) and\, finally\, the presentation of activities\, projects and int ernational networks on nuclear data. \n\nBeyond the technical contents of the courses being developed\, the novelty of the project lies with the use of innovative pedagogical methods\, such as flipped classes\, aimed at pr omoting student learning. Before attending interactive sessions organised under the close supervision of the teachers\, the students will have acces s to a handbook with the whole content of the course jointly with short vi deos summarising the key concepts\, and online quizzes allowing testing on e’s understanding of those concepts.\n\nThe interactive sessions are bas ed on active learning\, during which the students have to implement and us e the techniques they learned in hands-on training exercises designed to p romote learning. These exercises are computer-based assignments with exist ing open software and tools such as ENDF Utilities\, NJOY\, PREPRO\, JANIS \, DICE and NDaST. Finally\, the students will be introduced to nuclear da ta adjustments algorithms and machine learning advanced techniques applied to the nuclear data field.\n\nFurthermore\, a set of experiments with dir ect application to cross-sections measurements will be carried out in rese arch reactors: i) activation analysis experiments for a set of irradiated foils \, ii) Doppler feedback measurement in the BME Training Reactor at t he Budapest University of Technology and Economics\, and iii) reactivity w orth of samples using pile-oscillation techniques in the research reactors : AKR-2 at the Technical University Dresden and CROCUS at the École Polyt echnique Fédérale de Lausanne.\n\nIn addition to the flipped classroom p edagogy\, most of the interactive sessions are offered in a hybrid format: the students can decide to attend the interactive sessions either on-site or online. The sessions are also given in a condensed format. Combined wi th the hybrid set-up\, the courses are very well suited for lifelong learn ing. \n\nAcknowledgement. This project has received funding from the Europ ean Union’s Euratom research and training programme 2019-2020 under the Grant Agreement n°890675.\n\nhttps://indico.frib.msu.edu/event/52/contrib utions/717/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/717/ END:VEVENT BEGIN:VEVENT SUMMARY:Using Monte-Carlo method to analyze experimental data and produce uncertainties and covariances. DTSTART:20220726T145400Z DTEND:20220726T145700Z DTSTAMP:20260420T153400Z UID:indico-contribution-1091@indico.frib.msu.edu DESCRIPTION:Speakers: A. Olacel\, Carlos Paradela Dobarro (European Commis sion - Joint Research Center)\, Nicolas Dari Bako (CNRS/IPHC)\, Pascal Rom ain (CEA DAM DIF)\, Markus Nyman\, Marian Boromiza\, Marc Dupuis\, Catalin Borcea\, Stephane Hilaire\, Ruud Wynants\, Jean-Claude Drohé\, Arjan Plo mpen\, François Claeys (CEA/CNRS)\, Phillippe Dessagne\, Roberto Capote\, Alexandru Negret\, Cyrille de Saint Jean\, Maëlle Kerveno (CNRS/IPHC\, S trasbourg)\, Greg Henning (CNRS - IPHC)\n\nThe production of useful and hi gh-quality nuclear data requires experimental measurements with high preci sion and extensive information on uncertainties and possible correlations. When performing experimental measurement data analysis\, the physicist us es many external parameters (detector efficiencies\, distance of flight\, …) in addition to the raw data. All the steps of the data processing (ev ent selection\, calibration\, …) may introduce uncertainties and correla tions.\n\n\nThe usual method for combining and computing uncertainties is to use analytical developments based on the perturbation theory (e.g. 〖u _(f(x))〗^2=(∂f/∂x)^2×u_x^2). This method works well for simple case s\, but with multiple parameters and sources of uncertainty\, deriving the final total combined uncertainty can be long and complex. Reporting the f ormula into the analysis code becomes a tedious process where mistakes can appear and the final uncertainty value will be wrong.\n\n\nFurthermore\, it strictly applies only to small deviations from the central values\, whi ch is not always the case. Finally\, this method makes calculation of cova riances hard and the inclusion of some unusual form of uncertainty (assyme tric\, non Gaussian) even more difficult.\n\n\nTo overcome this issue\, on e may rely on random sampling methods (a.k.a Monte Carlo). With modern com puting infrastructures\, large storage space and many computing units are available to process data. This allows\, within a reasonable time and codi ng budget\, the repeated processing of data with variation of input parame ters within their nominal distribution probability. From the collection of results\, a central value\, uncertainties and covariances can be extracte d easily.\n\nThe **poster** will present an example of how the method is u sed in production of (n\, n’ gamma) cross-sections with uncertainties. T he advantages and drawbacks will be discussed\, and the method will be com pared to the analytical one.\n\nhttps://indico.frib.msu.edu/event/52/contr ibutions/1091/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1091/ END:VEVENT BEGIN:VEVENT SUMMARY:Educational activity by using nuclear chart in Japan: constructing three-dimensional nuclear chart and distributing nuclear charts through c rowdfunding DTSTART:20220725T200900Z DTEND:20220725T202100Z DTSTAMP:20260420T153400Z UID:indico-contribution-719@indico.frib.msu.edu DESCRIPTION:Speakers: Hiroyuki Koura\n\n(1) JAEA nuclear chart\nJAEA has p ublished a paper-based nuclear chart which is a sheet of 12 or 16 pages in A4 size\, every four years since 1976. The chart is a two-dimensional cha rt that shows the number of protons on the vertical axis and the number of neutrons on the horizontal axis in order to represent the properties of v arious nuclei\, and we distribute them to (mainly) researchers on nuclear science.1) \n\n(2) Three-dimensional nuclear chart and educational activit ies\nNuclear chart is very useful\, however\, such a character-based chart is not rather friendly to be used. We constructed three-dimensional (3D) nuclear charts created using toy blocks\, which represent the atomic mass es per nucleon number and the total half-lives as heights of blocks for ea ch nucleus in the entire region of the nuclear mass to visualize them intu itively2) (Fig.). The size is 96 (width) x 56 (depth) x 30 (maximum height ) cm. By using the atomic-mass chart\, for example\, generation of atomic energy from nuclei\, like nuclear fusion and fission\, can be understood a s a slope of the masses. Subsequently\, these charts were used in outreach activities for the general public and high school students. As an example \, an application for a lecture on nucleosynthesis in stars is introduced\ , and some explanations for the abundance of iron and the origin of uraniu m and heavy elements on the Earth are given with the 3D chart. \nUsing our charts\, lectures entitled 'Alchemy of the Universe' were delivered to va rious places (science café\, science lecture in high school\, etc.) more than twenty times till now. We made some video movies3).\n\n(3) Crowdfundi ng for distributing nuclear chart to high school students in Japan\nIn 202 0\, we started a crowdfunding project “one nuclear chart for one high sc hool."4) The purpose of the project is to deliver nuclear chart to high sc hools in Japan. The projected budget is 1.5 million Yen (~15\,000 USD as 1 USD=100Yen) and the term of donation is set from Jan. to Mar. in 2020 (8 w eeks). Finally\, it was succeeded: the total amount of the donation reache d to 1.731 million Yen (~17\,310 USD) by 157 supporters. After that\, we c onstructed 1\,200 sheets of the chart written in Japanese\, and distribute d to 284 science-programmed high-schools\, namely super science high schoo l (SSH) approved by the ministry for education\, overall Japan\, 122 high schools in Fukushima prefecture\, 98 high schools in Ibaraki prefecture\, and 57 colleges of national institute of technology.\n\nIn our paper\, we will show our educational activities with nuclear chart in Japan\, includi ng an introduction of the 3D charts and a crowdfunding project\, and some examples of outreach lectures for heigh-schools.\n\n \nFigure: Three-dimen sional nuclear chart. The height of the block represents atomic mass exces s per nucleon. The color of the block represents the length of half-lives of nuclei.\n\nReferences\n1) H. Koura\, T. Tachibana\, J. Katakura\, F. Mi nato\, Chart of the nuclides 2014\, Japanese Nuclear Data Committee and Nu clear Data Center of JAEA (2015).\nhttps://www.jaea.go.jp/02/press2014/p15 031202/ (in Japanese)\n2) H. Koura\, Three-dimensional nuclear chart - und erstanding nuclear physics and nucleosynthesis in stars\, Phys. Educ. 49 ( 2014) 215: Three-minute video abstract can also be seen:\nhttps://iopscien ce.iop.org/article/10.1088/0031-9120/49/2/215\n3) The promotion division o f JAEA: (1) ‘Cosmic alchemy’ (2013)\, and (2) ‘Contributed to the Sy nthesis of New Element NIHONIUM - The World of Heavy Element Nuclear Scien ce’ (2017)\, in the series of the JAEA official movie ‘JAEA Channel’ \nhttp://www.jaea.go.jp/english/jaea_channel/\n4) A crowdfunding project “one nuclear chart for one high school” since 2020\nhttps://academist- cf.com/projects/169?lang=ja (in Japanese)\n\nhttps://indico.frib.msu.edu/e vent/52/contributions/719/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/719/ END:VEVENT BEGIN:VEVENT SUMMARY:Development of an Interactive System for the Use of Nuclear Data ( ISIDA) DTSTART:20220727T170600Z DTEND:20220727T170900Z DTSTAMP:20260420T153400Z UID:indico-contribution-1131@indico.frib.msu.edu DESCRIPTION:Speakers: Darya Panova (JSC "SSC RF - IPPE")\n\nThe main objec tive of the article is development of a digital platform for visualization and processing of nuclear data.\nIt is based on the idea of saving the ex perience accumulated over many years of working with libraries of nuclear- physical data for various purposes. The main task is to provide users with open and convenient access to various types of nuclear data archives for conducting computational research in the field of fast reactors\, verifica tion and validation of software tools being developed\, both within the fr amework of fundamental and design scientific developments.\nThe developed digital platform "Interactive System for the Use of Nuclear Data" (ISIDA) will provide quick access to databases and numerical values\, a graphical representation of the information available in databases\, both directly i n the process of their formation\, and when comparing with the available s imilar data in modern versions of the world nuclear libraries. The digital platform ISIDA will be useful in the training and education of youth work ers in the nuclear industry at universities and at industry enterprises.\n As a result of the work done\, a concept and a pilot version of the digita l platform ISIDA with an interactive interface and a convenient graphical module have been developed. The shell of the new digital platform is devel oped in the C# programming language. The integration of the RUSFOND Neutro n Data Library into the digital platform of the Russian Library with the p ossibility of connecting any other foreign nuclear database library in the ENDF format was performed. A graphical module has been developed for visu alizing cross-sections and comparing them.\nA module for automating the pr eparation of constant libraries for use in neutron-physical calculations\, both for precision Monte-Carlo calculations and for multigroup calculatio ns\, has been developed. Integration with the program for preparing group constants CONSYST was performed.\n\nhttps://indico.frib.msu.edu/event/52/c ontributions/1131/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1131/ END:VEVENT BEGIN:VEVENT SUMMARY:Fusion excitation function studies in the reactions forming medium heavy compound system DTSTART:20220726T145100Z DTEND:20220726T145400Z DTSTAMP:20260420T153400Z UID:indico-contribution-1090@indico.frib.msu.edu DESCRIPTION:Speakers: Visakh A C (Central University of Kerala)\n\nNuclear fusion is a complex process involving a complete re-arrangement of quantu m systems with many degrees of freedom. Heavy ion fusion exhibits a strong entrance channel dependence at near fusion barrier energies and could be reasonably explained by coupled channels formalism [1\,2] that explicitly includes the effects of internal degrees of freedom. Though tremendously s uccessful in describing the data at near barrier energies\, coupled channe ls theories fail to describe fusion at deep sub barrier and well above the fusion barrier energies [3]. Alternate theories [4\,5] proposed recently also could not give a reasonable explanation to the experimental observati ons till date. Scarcity of experimental data spanning deep sub barrier to well above the barrier also adversely affect the theoretical developments to a great extent. It is pointed that instead of a coherent coupled channe ls approach\, a model with a gradual onset of decoherence [6] between the superposed states may be required to describe fusion.\n\nEvaporation resid ue (ER) excitation function measurements have been performed using the hea vy ion reaction analyzer (HIRA) [7] at the Inter University Accelerator Ce nter\, New Delhi. The measurements were performed for the $^{16}$O+$^{142\ ,150}$Nd reactions in the beam energy range 12% below the barrier to 50% a bove the barrier. Pulsed beams of $^{16}$O with a pulse separation of 4 μs\, was used to bombard the isotopically enriched $^{142}$Nd and $^{150} $Nd targets. The measured ER cross section represents the total fusion cro ss section at near barrier energies\, as fission cross section is negligib ly small.\n\nThe fusion cross section at different energies is estimated b y using the standard expression [8]. Coupled channels code CCFULL has been used to analyse the measured fusion cross sections for the two reactions. Nuclear potential parameters V$_0$\, $r_0$ and $a$ were first fixed using the Akyüz-Winther parameterisation [9]. The measured excitation function is found to be significantly enhanced relative to the one-dimensional bar rier penetration model (1-DBPM). Vibrational coupling of $2^+$ and $3^-$ states of $^{142}$Nd is found to explain the sub barrier fusion enhanceme nt in $^{16}$O+$^{142}$Nd reaction. Vibrational effects of $^{16}$O seem t o play no role in sub-barrier fusion in this reaction. The degree of fusio n enhancement is larger for the $^{16}$O+$^{150}$Nd reaction\, compared to $^{16}$O+$^{142}$Nd. Rotational couplings of ($2^+$ and $4^+$states) of t he deformed target reproduced the fusion cross sections reasonably well in $^{16}$O+$^{150}$Nd reaction at sub- and near barrier energies.\n\nThough CC calculations assuming AW potential parameters reasonably reproduce the fusion cross sections at below barrier energies\, they overpredict fusion at energies well above the barrier. This difference is observed to increa se with increasing beam energy. Careful analysis indicates that the observ ed difference is not due to fission or α particle emission. Diffuseness p arameter in the range 1.0 - 1.1 fm is required to fit the cross sections. These values are significantly larger than the values obtained from elasti c scattering measurements. The inadequacy of AW potential parameters hints the role of dynamical effects in fusion at higher energies.\n![The experi mental fusion excitation function for the 16 O + 142\,150 Nd reaction alon g with CC calculations.][1]\n![The experimental fusion excitation function for the 16 O + 142\,150 Nd reaction along with CC calculations.][2]\n \n\ n\n [1]: http://Home/CCFULL_142Nd%20(final).png\n [2]: http://Home/CCFUL L_150Nd(Final).png\n\nhttps://indico.frib.msu.edu/event/52/contributions/1 090/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1090/ END:VEVENT BEGIN:VEVENT SUMMARY:Present status of an R-matrix analysis code AMUR for cross-section evaluation in resolved resonance region DTSTART:20220727T133600Z DTEND:20220727T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-909@indico.frib.msu.edu DESCRIPTION:Speakers: Satoshi Kunieda (Japan Atomic Energy Agency)\n\nFor thorough understanding resonant theories and cause of discrepancies among different cross-section measurements\, development of an R-matrix analysis code AMUR is being progressed.\nThe code is organized by “theoretical ” and “experimental” classes based on the object-oriented framework. In the theoretical class\, with sharing the same compound nucleus\, the i ndependent distant poles can optionally be assumed for the simultaneous an alysis of different projectile + nucleus pairs to see the relation between the channel radius and the theoretical background. In the experimental c lass\, to simulate experimental conditions\, calculated cross-sections can be corrected by the Doppler broadening\, resolution functions\, re-normal ization\, adding contaminant elements.\nI demonstrate some example analyse s of measured cross-sections with AMUR both for the light and heavier nucl ei to show effects of those new options. Also\, preliminary results will b e shown from analyses for experimental data of J-PARC/ANNRI.\n\nhttps://in dico.frib.msu.edu/event/52/contributions/909/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/909/ END:VEVENT BEGIN:VEVENT SUMMARY:Evaluation of Thermal Neutron Scattering Law and Cross Sections fo r Calcium Hydride DTSTART:20220726T153500Z DTEND:20220726T153600Z DTSTAMP:20260420T153400Z UID:indico-contribution-1111@indico.frib.msu.edu DESCRIPTION:Speakers: Benjamin K. Laramee (North Carolina State University )\, Ayman I. Hawari (North Carolina State University)\n\nMetal hydrides ha ve a variety of mechanical\, thermal\, and neutronic properties that are i deal for applications to nuclear technologies. As a result\, zirconium hyd ride has been used in the fuel of TRIGA reactors for over half a century. More recently\, calcium hydride (CaH${}_{2}$)\, a saline hydride\, has bee n investigated and shows promise for use as a moderator in microreactors. As of yet\, there is not a Thermal Scattering Law (TSL) evaluation for CaH ${}_{2}$ in the ENDF database. In addition\, the evaluation that exists in the European counterpart\, JEFF\, contains physical inaccuracies in the C a portion of the cross section due to limitations in the thermal neutron s cattering code used for the evaluation. The purpose of this work is to eva luate the thermal neutron scattering cross sections of CaH${}_{2\\ }$from first principles\, using accurate physical models\, for publication and us e in reactor design.\n\nThe probability of a thermal neutron to scatter fr om incident energy E into energy E${}^{'}$ through solid angle $\\mathrm{\ \Omega }$ is described by the double differential scattering cross section and\, therefore\, the TSL. In the case of CaH${}_{2}$\, the incoherent\, harmonic\, and cubic approximations are implemented in the calculation of the TSL\, which is performed using a phonon expansion where all second- an d higher-order terms represent inelastic scattering via the exchange of ph onons. The phonon density of states (DOS)\, also known as the vibrational DOS\, is a key input in this calculation under the cubic approximation. Us ing ab initio lattice dynamics (AILD)\, density functional theory (DFT) ca lculations were performed using the Vienna ab initio simulation package (V ASP) with a GGE-PBE pseudopotential. The structure optimization led to lat tice constant and atom positions that differ by less than 1% from experime nt and determined that a plane wave cutoff energy of 675 eV and a 9x9x9 Mo nkhorst-Pack k-point mesh were sufficient. The obtained Hellman-Feynman fo rces were used in the PHONON code to calculate the phonon dispersion curve s and DOS using the dynamical matrix method. Finally\, the cross sections were calculated\, under the incoherent approximation\, using the Full Law Analysis Scattering System Hub\, $FLASSH$\, a code developed by the Low En ergy Interaction Physics (LEIP) group at North Carolina State University. \n\nConsequently\, this work produced a phonon DOS that closely matches ex periment and thermal neutron scattering cross sections for the three CaH${ }_{2}$ nonequivalent sites (Ca\, H${}_{1}$\, H${}_{2}$) that demonstrate t he expected physical behavior. In addition to the incoherent inelastic cro ss sections\, the Ca evaluation contains a coherent elastic component that accounts for interference effects from the entire CaH${}_{2}$ lattice\, w hile the H${}_{1}$ and H${}_{2\\ }$evaluations contain incoherent elastic contributions. Additionally\, the hydrogen inelastic cross sections demons trate oscillatory behavior that was predicted by Fermi in 1936.${}^{\\ }$T he cross sections calculated in this work are being finalized for entry in to the ENDF database.\n\nhttps://indico.frib.msu.edu/event/52/contribution s/1111/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1111/ END:VEVENT BEGIN:VEVENT SUMMARY:Experimental measurement of 183W(n\, n’γ) and (n\, 2nγ) cross sections (preliminary) DTSTART:20220726T145700Z DTEND:20220726T150000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1092@indico.frib.msu.edu DESCRIPTION:Speakers: Maëlle Kerveno\, Arjan Plompen\, Marc Dupuis\, Jean -Claude Drohé\, Ruud Wynants\, A. Olacel\, Phillippe Dessagne\, Markus Ny man\, Alexandru Negret\, Pascal Romain (CEA DAM DIF)\, Carlos Paradela Dob arro\, François Claeys (CEA/CNRS)\, Catalin Borcea\, Stephane Hilaire\, M arian Boromiza\, Roberto Capote\, Cyrille de Saint Jean\, Nicolas Dari Bak o (CNRS/IPHC)\, Greg Henning\n\nMost nuclear reactor developments rely on evaluated databases for numerical simulations to optimize and predict perf ormance and reactor control parameters. However\, these databases still pr esent large uncertainties\, preventing calculations from reaching the requ ired precision. An improvement of evaluated databases requires new measure ments and better theoretical descriptions of involved reactions. Among the reactions of interest\, inelastic neutron scattering (or (n\, xn)) are of great importance for the operation of a reactor as they modify the neutro n spectrum\, the neutron population\, and produce radioactive species.\n\n \nThe CNRS-IPHC group is running an experimental program with the GRAPhEME setup installed at the neutron beam facility EC/JRC-GELINA (Geel\, Belgiu m) to measure (n\, xn gamma) reaction cross-sections using prompt gamma-ra y spectroscopy and neutron energy determination by time-of-flight [1-3]. T he obtained exclusive experimental data provide strong constraints on nucl ear reaction mechanisms models. A measurement of (n\, xn gamma) cross-sect ion have been performed for 183W\, which will be discussed in this contrib ution\, in addition to numerous isotopes such as 232Th\, 235\,238U\, natZr and 182\,184\,186W.\n\nTungsten is not an active element in nuclear react ors\, but\, because of its chemical and mechanical properties\, it is used in many alloys. The interaction of neutrons with tungsten is therefore of importance for reactor physics\, in particular for fusion reactors\, in w hich tungsten is one of the most exposed material to high energy neutrons. From a theoretical point of view\, a better description of (n\, xn) react ions on tungsten nuclei allows an improvement of models for other key nucl ei in reactors fuel. Indeed\, tungsten isotopes are deformed like actinide s\, but also easier to describe as they do not present a neutron-induced f ission channel. Still\, there are very few measurements available today to test evaluations [4]. Our new experimental data will provide an extensive and constraining test to the predictability of models.\n\nThe experimenta l setup and the data analysis method will be presented. The preliminary ex perimental results for the 183W isotope will be compared to predictions fr om the usual nuclear reaction codes.\n\n\n- [1] “What can we learn from (n\, x n γ) cross sections about reaction mechanism and nuclear structure ?”\, by Kerveno\, Maëlle and Dupuis\, Marc and Borcea\, Catalin and Bo romiza\, Marian and Capote\, Roberto and Dessagne\, Philippe and Henning\, Greg andHilaire\, Stéphane and Kawano\, Toshihiko and Negret\, Alexandra and Nyman\, Markus and Olacel\, Adina and Party\, Eliot and Plompen\, Arj an and Romain\, Pascal and Sin\, Mihaela. ND 2019 : International Conferen ce on Nuclear Data for Science and Technology (2019). 10.1051/epjconf/2020 23901023 https://hal.archives-ouvertes.fr/hal-02957494 \n- [2] “How to p roduce accurate inelastic cross sections from an indirect measurement meth od ?”\, by Kerveno\, Maëlle and Henning\, Greg and Borcea\, Catalin and Dessagne\, Philippe and Dupuis\, Marc and Hilaire\, Stéphane and Negret\ , Alexandru and Nyman\, Markus and Olacel\, Adina and Party\, Eliot and Pl ompen\, Arjan in EPJ N - Nuclear Sciences & Technologies 4\, (2018). 10.10 51/epjn/2018020 https://hal.archives-ouvertes.fr/hal-02109918 \n- [3] “F rom γ emissions to (n\,xn) cross sections of interest : The role of GAINS and GRAPhEME in nuclear reaction modeling”\, by Kerveno\, M. and Bacqui as\, A. and Borcea\, C. and Dessagne\, Ph. and Henning\, G. and Mihailescu \, C. and Negret\, A. and Nyman\, M. and Olacel\, A. and Plompen\, M. and Rouki\, C. and Rudolf\, G. and Thiry\, C. in European Physical Journal A 5 1\, 12 (2015). 10.1140/epja/i2015-15167-y https://hal.archives-ouvertes.fr /hal-02154831\n- [4] Experimental Nuclear Reaction Data (EXFOR) https://ww w-nds.iaea.org/exfor/\n\nhttps://indico.frib.msu.edu/event/52/contribution s/1092/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1092/ END:VEVENT BEGIN:VEVENT SUMMARY:A segmented total energy detector (sTED) for (n\, γ) cross sectio n measurements at n_TOF EAR2 DTSTART:20220728T160200Z DTEND:20220728T161400Z DTSTAMP:20260420T153400Z UID:indico-contribution-1094@indico.frib.msu.edu DESCRIPTION:Speakers: Victor Alcayne (CIEMAT (Spain))\n\nA segmented total energy detector (sTED) for (n\, γ) cross section measurements at n_TOF E AR2\n\nV. Alcayne1\, D. Cano-Ott1\, E. González-Romero1\, T. Martínez1\, E. Mendoza1\, A. Sánchez-Caballero1\, J. Balibrea2\, C. Domingo-Pardo2\, J. Lerendegui2 and n_TOF collaboration3\n1CIEMAT\, Spain\n2IFIC CSIC-UV\, Spain\n3CERN\, Switzerland\n\nThe neutron time-of-flight facility n_TOF [ 1] is characterised by its high instantaneous neutron intensity\, high-res olution and broad neutron energy beams\, especially conceived for neutron- induced reaction cross sections measurements. Two TOF experimental areas a re available at the facility: the experimental area 1 (EAR1)\, located at the end of the 185 m horizontal flight path from the spallation target\, a nd the experimental area 2 (EAR2) [2]\, placed at 20 m from the target in the vertical direction.\n\nThe neutron beam in EAR2 is ~300 times more int ense than in EAR1 in the relevant time window\, since it has a ~30 times l arger neutron fluence and a ~10 times shorter flight times. It was designe d to carry out challenging cross-section measurements with low mass sample s (<1 mg)\, reactions with small cross-sections or highly radioactive samp les. The first (n\,γ) cross section measurement at EAR2 performed with su b milligrams samples of 244\,246\,248Cm isotopes [4] has shown the enormou s potential of the EAR2.\n\nThe high instantaneous fluence of EAR2 results in high counting rates that challenge the existing detection systems. The refore\, new devices capable of supporting very large counting rates are u nder development. For the case of the (n\,γ) cross section measurements\, a new segmented total energy detector (sTED) has been built. It consists of a physically segmented array of nine small volume C6D6 scintillators wi th reduced size photosensors. In comparison to standard size C6D6 detector s [5]\, the segmentation reduces the high counting rates and the saturatio n of high energy signals originated in the spallation process. In addition \, the reduced size of each module allows the use of more compact readout devices (PMTs or SiPMs) with a reduced sensitivity to the background of ul tra-relativistic particles coming from the spallation target.\nWe will pre sent at the conference the design and construction of the sTED detector ar ray and results of its performance in a reference capture measurement at n _TOF EAR2.\n\n\n References\n[1] Guerrero\, C. et al. Eur. Phys. J. A 49\ , 27 (2013).\n[2] C. Weiss\, et al Nuc. Inst. Meth. Phy. Res. Sec. A\, 799 :90–98\, (2015).\n[3] M. Sabaté-Gilarte et al.\, Eur. Phys. J. A 53\, 2 10(2017).\n[4] V. Alcayne et al.\, EPJ Web Conf. 239 01034 (2020).\n[5] R. Plag et al.\, Instrum. Meth. Phys. Res. A 496. 425-436 (2003).\n\nhttps: //indico.frib.msu.edu/event/52/contributions/1094/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/1094/ END:VEVENT BEGIN:VEVENT SUMMARY:Experiment-based determination of the excitation function for the production of $^{44}$Ti in proton-irradiated vanadium samples DTSTART:20220726T150000Z DTEND:20220726T150300Z DTSTAMP:20260420T153400Z UID:indico-contribution-1095@indico.frib.msu.edu DESCRIPTION:Speakers: Mario Veicht (Paul Scherrer Institut (PSI)\; École polytechnique fédérale de Lausanne (EPFL))\n\nThe artificial production of radionuclides has considerable significance for many different applicat ions. Recently\, we observe increasing interest in the field of nuclear me dicine\, with $^{44g}$Sc being one of the promising nuclides for positron emission tomography. Besides its direct production routes by irradiating s uitable targets like Sc or Ti with charged particles\, $^{44}$Ti is in the spotlight of radiopharmaceutical research because of the possibility to r ealize a $^{44}$Ti/$^{44g}$Sc radionuclide generator. Therefore\, explorin g the possible production routes for the mother nuclide is of great intere st\, and spallation reactions on V induced by high-energetic protons seem to be one of the most promising ones. \nWe determined the excitation funct ion for the production of $^{44}$Ti in the nuclear reaction $^{nat}$(p\,X) $^{44}$Ti (1). Seven metallic vanadium disks were proton irradiated withi n an energy range of 111 to 954 MeV between 1995 to 1996. The experiments ’ cross sections were determined using two independent measurements by c ombining $\\gamma$ spectrometry with both a low-energy germanium detector and a high-purity germanium detector. The maximum cross section was observ ed for energies of 145 $\\pm$ 1.2 and 150.2 $\\pm$ 1.2 MeV with values of 803 ± 28 and 805 $\\pm$ 27 $\\mu$b\, respectively\, and are in good agree ment with former unpublished results (Fig. 1a). In combination with these earlier measurements\, a consistent data set for the $^{nat}$V(p\,X) $^{44 }$Ti excitation function from 111 to 1350 MeV was obtained. Model calculat ions using Liège Intranuclear Cascade (INCL)/ABLA reproduce the shape of the excitation function correctly but over-predict the absolute values by factors of 2 to 3 (Fig. 1b). Some considerations regarding this already ea rlier observed systematic overestimation of neutron-poor residues are disc ussed and the experimental results will trigger new approaches in code dev elopment in order to improve the predictions.\n\n![Figure 1: \\textbf{(a)} Experimental results of the $^{44}$Ti production from p-induced reactions \, shown in comparison with previous data\, and \\textbf{(b)} comparison o f the excitation function for the $^{44}$Ti production][1]\n\n**Reference* *:\n(1) Veicht\, M.\, Kajan\, I.\, David\, J. C.\, Chen\, S.\, Strub\, E.\ , Mihalcea\, I.\, & Schumann\, D. (2021). "Experiment-based determination of the excitation function for the production of Ti44 in proton-irradiated vanadium samples". $\\textit{Physical Review C}$\, 104(1)\, 014615.\n\n\n **Acknowledgements**:\nThe authors acknowledge the funding from Swissnucle ar (LRC_20_02)\, from the Marie Skłodowska-Curie Grant (No. 701647)\, and further\, from the Swiss National Science Foundation (Grant No. 177229).\ n\n\n [1]: https://indico.bnl.gov/event/9462/abstracts/2526/attachments/2 08/Merging_Fig_2a_b.pdf\n\nhttps://indico.frib.msu.edu/event/52/contributi ons/1095/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1095/ END:VEVENT BEGIN:VEVENT SUMMARY:Theoretical calculation and evaluation for n+239\,240\,241\,242\,2 42m\,243\,244Am reactions DTSTART:20220726T174200Z DTEND:20220726T175400Z DTSTAMP:20260420T153400Z UID:indico-contribution-712@indico.frib.msu.edu DESCRIPTION:Speakers: Yongli Xu\n\nIn order to reduce the uncertainties in the design and operation of accelerator-driven systems (ADSs)\, high-prec ision nuclear data for neutron- and proton-induced reactions on a variety of isotopes in the energy range below 200 MeV are necessary. Knowledge of accurate neutron-induced fission cross sections is crucially important for the design of various reactor systems. Therefore\, accurate nuclear data for neutron-induced reactions on Am isotopes are needed in the calculation of neutron and energy balance and the prediction of transmutation rates o f the various radioactive species. To meet this requirement\, all cross se ctions\, angular distributions\, energy spectra\, double differential cros s sections of neutron\, proton\, deuteron\, triton\, helium-3 and alpha em issions and the number of neutron per fission for n+239\,240\,241\,242\,24 2m\,243\,244Am reactions are consistently calculated and analyzed by theor etical nuclear models in the energy range of En≤200 MeV. The correspondi ng models include the optical model\, the unified Hauser-Feshbach theory a nd the exciton model\, the improved Iwamoto-Harada model\, the evaporation models\, the linear angular momentum dependent exciton state density mode l\, the fission model\, the intranuclear cascade model\, the distorted-wav e Born approximation and the coupled channel theory. The calculated result s reproduce the experimental data well\, and the variation tendency of rea ction cross sections related to the target mass numbers is obtained.\n\nht tps://indico.frib.msu.edu/event/52/contributions/712/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/712/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the delayed-neutron yield and group parameters in t he thermal neutron induced fission of 239Pu DTSTART:20220726T175400Z DTEND:20220726T180600Z DTSTAMP:20260420T153400Z UID:indico-contribution-699@indico.frib.msu.edu DESCRIPTION:Speakers: Pierre Leconte\n\nDelayed neutron data is essential in inherent reactor safety and in reactor control since it is used to esti mate the reactivity. The quantities of interest related to delayed neutron s are the average delayed neutron yield\, and the group constants that def ine the kinetics of delayed neutron emission.\nDiscrepancies among the eva luated data as well as missing covariance in most of international databas es result in excessive conservatism in the safety margins. In order to imp rove this status\, a collaboration among CEA and CNRS was settled to produ ce high-quality delayed neutron data for several fissioning systems of int erest in GEN-II & III reactors. \nFollowing successful campaigns at ILL (I nstitut Laue-Langevin) in 2018 and 2019\, devoted to 235U\, a new campaign was realized in march 2021\, focusing on the thermal fission of 239Pu. Th e experiment consists of a cold neutron beam hitting a fissile target\, p laced at the center of a long-counter made of a polyethylene matrix in whi ch 16 helium-3 tubes are introduced. After a defined irradiation length\, during which fissions occur and precursors buid up\, the beam is quickly interrupted and the delayed neutrons emitted by the precursors' is detecte d. First estimations of the delayed neutron yield and group constants are proposed and discussed in this paper\, in comparison with data from the li terature.\n\nhttps://indico.frib.msu.edu/event/52/contributions/699/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/699/ END:VEVENT BEGIN:VEVENT SUMMARY:Network-based Data Acquisition and Control for BGS and FIONA exper iments DTSTART:20220727T163300Z DTEND:20220727T163600Z DTSTAMP:20260420T153400Z UID:indico-contribution-1118@indico.frib.msu.edu DESCRIPTION:Speakers: John Gooding\n\nExperiments done at the 88-Inch Cycl otron at Lawrence Berkeley National Laboratory to study super heavy elemen ts and their basic physics and chemistry using the Berkeley Gas-filled Sep arator (BGS) and For the Identification of Nuclide A (FIONA) apparatuses a re complex and employ dozens to hundreds of pieces of individual equipment setup in series and parallel along the beam-line.\n\nOver the past two ye ars experimental improvements were made by changing\, upgrading\, or other wise converting each device to communicate with Ethernet and TCP/IP as opp osed to other communication protocols such as serial RS-232\, RS-485\, USB \, and GPIB. Getting each part of the experiment onto a common network all ows for a centralized command and control structure\, while enabling task flow automation to reduce human error and improve workflow efficiency. Add itionally\, this allows for a great simplification of the recording and lo gging of auxiliary data for each device to gain greater insight into the p erformance of the experiment and to identify issues with equipment before they occur\, allowing for planned maintenance and downtime\, thus reducing lost experiment time.\n\nIn this presentation I will discuss the details of how this was implemented using open-source software and modern software development and information technology operations (DevOps) practices\, su ch as configuration as code\, Docker containers\, orchestration\, continuo us integration and deployment (CI/CD)\, etc. Special focus will paid to ho w the system was designed to be general and modular so that new parts can be easily added and removed as the experiments evolve overtime\, and how i t can be reproduced and applied elsewhere.\n\nSupport was provided by the U.S. Department of Energy (DOE)\, Office of Science\, Office of Nuclear Ph ysics under contract DEAC02-05CH1123.\n\nhttps://indico.frib.msu.edu/event /52/contributions/1118/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1118/ END:VEVENT BEGIN:VEVENT SUMMARY:Uncertainty Quantification for Phenomenological Optical Potentials DTSTART:20220727T140000Z DTEND:20220727T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-727@indico.frib.msu.edu DESCRIPTION:Speakers: Rida Rahman (Lawrence Livermore National Laboratory) \, Jutta Escher (Lawrence Livermore National Laboratory)\, Cole Pruitt (La wrence Livermore National Laboratory)\n\nPhenomenological optical model po tentials (OMPs) have played an essential role in scattering calculations f or several decades. Despite their successes\, none have had their parametr ic uncertainty fully quantified\, making reliable extrapolation difficult. To address this gap\, we have developed a generic OMP uncertainty quantif ication framework that leverages Markov-Chain Monte Carlo for OMP paramete r inference. Using this framework\, we have revisited the original analyse s for the Koning-Delaroche and Chapel Hill '89 potentials\, assigned well- calibrated uncertainties\, and validated their effectiveness against a bro ad test corpus of recent experimental scattering data. Finally\, we propag ate these new uncertainties into two illustrative studies: predictions of neutron cross sections along well-studied isotopic chains\, and examinatio n of selected proton-induced reactions relevant for astrophysical nucleosy nthesis. We conclude that\, contrary to common practice\, the substantial inherent uncertainty of standard OMPs can no longer be ignored.\n\nThis wo rk was performed in part under the auspices of the U.S. Department of Ener gy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27 344.\n\nhttps://indico.frib.msu.edu/event/52/contributions/727/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/727/ END:VEVENT BEGIN:VEVENT SUMMARY:The Nuclear Data Working Group in the United States and Workshop O utcomes DTSTART:20220725T202100Z DTEND:20220725T203300Z DTSTAMP:20260420T153400Z UID:indico-contribution-720@indico.frib.msu.edu DESCRIPTION:Speakers: Catherine Romano\n\nThe Nuclear Data Working Group ( NDWG) was established in 2015 to identify cross-cutting nuclear data needs \, and to facilitate communication and collaboration across programs on nu clear data activities. The NDWG currently consists of over forty members who represent the needs of program offices across the Department of Energy \, the National Nuclear Security Administration\, and other programs. Nat ional Laboratory representatives have been added to the NDWG to contribute knowledge of laboratory research needs and priorities. The NDWG meets an nually to plan outreach activities and discuss collaboration on cross-cutt ing nuclear data priorities. The Nuclear Data Interagency Working Group ( NDIAWG) is a federal program manager group led by the Department of Energy \, Office of Science\, Office for Nuclear Physics (NP). They meet regular ly to coordinate funding efforts for nuclear data. Several of the program s collaborate through a multi-program Funding Opportunity Announcement man aged by NP. The NDWG maintains a website that contains information about the NDWG activities and provides access to workshop reports\, nuclear data needs documents and introductory presentations. The website link can be f ound on the National Nuclear Data Center webpage\, and at www.nndc.bnl.gov /ndwg/. \nThe primary outreach mechanism of the NDWG is the annual Worksho p for Applied Nuclear Data Activities (WANDA). Since 2015\, the NDWG has organized six WANDA workshops which bring together nuclear data experts\, the user community and program managers. The workshops include six to eig ht topical breakout sessions that encourage input from all attendees throu gh facilitated discussion to identify and prioritize nuclear data needs\, and to recommend tasks to improve the nuclear data. The recommendations a re summarized in a workshop report. Many of the nuclear data tasks recomm ended in the WANDA workshops have received funding demonstrating the succe ss of this type of collaborative interaction. This presentation will summ arize the recommendations from the WANDA workshops and discuss recent outr each activities and future plans.\n\nhttps://indico.frib.msu.edu/event/52/ contributions/720/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/720/ END:VEVENT BEGIN:VEVENT SUMMARY:Investigating the production of medical imaging radioisotopes usin g laser-accelerated protons. DTSTART:20220725T163000Z DTEND:20220725T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-654@indico.frib.msu.edu DESCRIPTION:Speakers: Aarón Alejo Alonso\, Dolores Cortina-Gil\, Adrian B embibre\, Camilo Ruiz\, Michael Seimetz\, Juan Peñas\, Jose Benlliure\n\n The development of novel medical imaging techniques like PET (Positron Emi ssion Tomography) or SPECT (Single-Photon Emission Computed Tomography) ha s led to the increase in the demand of nuclear radioisotopes for medical d iagnostics. At present\, radioisotope production for medical imaging and treatment is principally done at conventional accelerators (cyclotrons) an d dedicated nuclear reactors. In the particular case of + emitters used in PET imaging\, the current approach is based on the production of + radiot racers at large singular facilities\, which are in charge of the radioisot ope supply at a regional or national scale. Due to the cost of radiotracer production centers\, accelerators\, radiopharmacy\, and particularly radi ation shielding\, the economic viability of these centers is based on the mass-scale production of single doses distributed to as many as possible h ospitals and research centers. As a result of this regional scope\, commer cial isotope production of PET radioisotopes is mainly limited to 18 F: wi th a half-life of around 110 min\, it can endure the time required for the production\, the post-processing\, and the distribution. For this reason\ , the production of a limited number of doses of shorter-lived radioisotop es such as 11 C (~20 min)\, 13 N(~10 min)\, or 15 O (~2 min) is generally out of the scope of these facilities. On this subject\, over the last dec ades\, the use of ultra-short\, ultra-intense lasers for radioisotope prod uction has been proposed as a cost efficient alternative for on-demand pro duction of single doses of short-lived radioisotopes. Through the Target N ormal Sheath Acceleration (TNSA) mechanism\, ultra-intense laser pulses (I >10 18 W/cm 2 ) impinging on a micrometric target sheet can result in the acceleration of ion beams up to several tens of MeV. The nature and prope rties of the laser-induced acceleration process solve the main constraint of conventional production facilities. As the laser-target interaction occ urs in a micrometric spatial length\, shielding requirements are much lowe r in comparison to nuclear reactors or accelerators. Thus\, laser systems of this class become significantly more affordable for hospitals\, clinics \, and research centers. They could then produce radioisotopes on demand\, and even explore shorter-lived emitters which are out of actual productio n scheme based on conventional accelerators and nuclear reactors. In this work we present the main achievements of the Laser Laboratory for Acceler ation and Applications at the University of Santiago de Compostela (Spain) in developing the technologies required for this new technology to become a real breakthrough on medical radioisotope production.\n\nhttps://indico .frib.msu.edu/event/52/contributions/654/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/654/ END:VEVENT BEGIN:VEVENT SUMMARY:Determination of positron emission probability in the decay of 86Y DTSTART:20220725T165400Z DTEND:20220725T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-656@indico.frib.msu.edu DESCRIPTION:Speakers: M. S. Uddin (Institut für Neurowissenschaften und M edizin\, INM-5:Nuklearchemie\, Forschungszentrum Jülich\, D-52425 Jülich \, Germany\; Tandem Accelerator Facilities\, INST\, Atomic Energy Research Establishment\, Savar\, Dhaka\, Bangladesh)\, Shamsuzzoh Basunia (Nuclear Science Division\, Lawrence Berkeley National Laboratory\, Berkeley\, Cal ifornia 94720\, USA)\, B. Scholten\, B. Neumaier\, S. M. Qaim\, I. Spahn\, L. A. Bernstein\n\nIn nuclear medicine\, the positron emitting $^{86}$Y (14.7 h) is an emerging imaging isotope for use in combination with the $\ \beta$$^-$ emitting therapeutic radionuclide $^{90}$Y (2.7 d)\, the pair b eing commonly called as a matched theranostic pair [1]. To produce the rad ionuclide $^{86}$Y via the $^{86}$Sr(p\,n) reaction in a pure form\, 96.4% enriched thin $^{86}$SrCO$_3$ targets were irradiated with protons of ene rgies 7 and 8 MeV at BC1710 cyclotron\, Forschungszentrum Jülich (FZJ)\, Germany. We have determined the positron emission probability P$_\\beta$$^ +$ in the $\\epsilon$+$\\beta$$^+$ decay of $^{86}$Y (14.7 h) by measuring the 511 keV annihilation $\\gamma$-ray using an ORTEC HPGe detector. Duri ng counting\, each irradiated $^{86}$SrCO$_3$ sample was placed inside a c ircular groove (diameter 1 cm\, depth 0.01 cm) of a Cu disk (diameter 3 cm \, height 0.5 cm) and covered with another one of the same type and size. The Cu enclosure served to annihilate almost all $\\beta$$^+$ particles in $^{86}$Y decay\, Q$^+$($^{86}$Y)=5.24$\\pm$0.01 MeV\, within its geometri c volume. Several corrections were made including that for the counting g eometry to deduce the final results. The electron capture probability P($\ \epsilon$+$\\beta$$^+$) has also been determined as an additional check\, since %P($\\epsilon$+$\\beta$$^+$)=100\, by measuring the K$_\\alpha$ and K$_\\beta$ X-rays of energies 14.1 and 15.8 keV\, respectively\, using a s pecial ORTEC HPGe detector\, with a 0.3 mm thick Be window\, for low-energ y $\\gamma$-rays. The positron emission and electron capture probabilities are determined to be 27.6$\\pm$1.4% and 72.2$\\pm$4.0%\, respectively. Th e normalization yields %P$_\\beta$$^+$=27.7$\\pm$1.5 and %P$\\epsilon$=72. 3$\\pm$1.5. The positron emission probability of this work is found to be in good agreement with the value 27.9$\\pm$1.2% [2]\, deduced using the ne wly constructed $\\gamma$-decay/level-scheme of $^{86}$Sr and calculation of electron capture to positron decay ratio for each beta feeding levels\, and is lower by 14% compared to the latest evaluated value of 32.5$\\pm$2 .0 [3]\, obtained using the prior $\\gamma$-decay/level-scheme of $^{86}$S r and the same method of Ref. [2]. The deduced electron capture probabilit y of the present work provided an additional confirmation for the measured positron emission probability of $^{86}$Y.\n\nReferences:\n\n1.F. Rösch\ , H. Herzog\, and S. M. Qaim\, Pharmaceuticals 10\, UNSP article 56 (2017) .\n2.A. C. Gula\, E. A. McCutchan\, C. J. Lister\, J. P. Greene\, S. Zhu\, P. A. Ellison\, R. J. Nickles\, M. P. Carpenter\, S. V. Smith\, and A. A. Sonzogni\, Phys. Rev. C 102\, 034316 (2020).\n3.A. Negret and B. Singh\, Nuclear Data Sheets 124\, 1 (2015).\n\nhttps://indico.frib.msu.edu/event/5 2/contributions/656/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/656/ END:VEVENT BEGIN:VEVENT SUMMARY:Characterisation of the n_TOF 20 m beam line at CERN with the new spallation target DTSTART:20220726T140000Z DTEND:20220726T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-706@indico.frib.msu.edu DESCRIPTION:Speakers: Jose Antonio Pavon Rodriguez (University of Seville and CERN)\n\nThe n_TOF Collaboration operates the neutron time-of-flight f acility at CERN [1]\, based on a 20 GeV/c pulsed proton beam impinging on a lead target employing water to moderate the spallation neutrons. The fa cility is characterized by a high-instantaneous neutron beam intensity\, h igh energy resolution and a wide neutron energy spectrum\, spanning from s ub-thermal to GeV. The first experimental area\, EAR1 [2]\, in operation s ince 2001\, is located at 185 m from the spallation target nearly in the s ame direction as the incoming proton beam. In 2014\, a new experimental ar ea was commissioned\, EAR2 [3]\, located at 20 m above the target in the p erpendicular direction with respect to the proton beam. Thanks to the shor ter flight path\, this new beam line features a neutron flux around two or ders of magnitudes bigger in the thermal region and about 30 times higher in the rest of the neutron energy spectrum compared to EAR1 [4]. Moreover\ , it presents a better signal to background ratio. This offers a unique op portunity of performing neutron induced cross section measurements for iso topes with very short half-life or small cross sections\, paving the way f or new challenging measurements in very diverse fields. Such is the case o f the first measurement performed in EAR2 to determine the feasibility of neutron-induced fission\, the 240Pu(n\,f) cross section measurement [5]\, of special interest in nuclear waste management in the field of Nuclear En ergy. In Astrophysics\, the 7Be(n\,α) and 7Be(n\,p) reactions cross-secti on were measured for the first time in the energy regions of interest for the Big Bang nucleosynthesis [6-7]\, which are of importance to solve the Cosmological Lithium Problem or the 26Al(n\,α) reaction which has a criti cal influence on the abundance of the 26Al cosmic γ-ray emitter [8]. Addi tionally\, in the field of Medical Physics\, the 33S(n\,α) cross section was measured and data were provided for the first time from thermal to 10 keV [9].\n\nIn the course of CERN's second long shutdown (2019-2020)\, the facility has gone through a major upgrade comprised of the installation o f a new spallation target design to fully optimise the features of the n_T OF experimental areas\, unlike the previous one specifically designed for EAR1. These changes impact the characteristics of the neutron beam\, i.e. the neutron flux\, the energy resolution and the beam profile. The flux pl ays a key role in the determination of the energy dependence of the neutro n induced cross-section. The energy resolution is the main feature in the characterization of the resonance region of the measured cross-sections. C ompared to the previous target\, the energy resolution and the characteris tics of the flux are significantly improved\, enhancing the capabilities o f the facility EAR2. \n\nDuring a commissioning phase in 2021 the changes in the characteristics of EAR2 were investigated. This work presents the f eatures of the neutron beam with the new spallation target: neutron energy flux and neutron energy resolution. The characterisation of the neutron f lux required of the combination of a series of measurements\, making use o f several detection systems such as micro-megas\, parallel plate avalanche counters and silicon monitors\, with diverse neutron-converting reactions considered standard in different energy regions. The preliminary results of the neutron flux measurement in EAR2 compared to extensive Monte Carlo simulations\, as well as an overview of the improvement of the neutron ene rgy resolution will be presented. \n\n[1] C. Rubbia et al.\, A High Resolu tion Spallation Driven Facility ATTHE CERN-PS to Measure Neutron Cross Sec tions in the Interval from 1 eV to 250 MeV: a Relative Performance Assess ment\, CERN/LHC/98-002-EET\, 1998\n[2] Guerrero C. et al\, Performance of the neutron time-of-flight facility n_TOF at CERN\, Eur. Phys. J. A 49\, 2013 \n[3] Colonna N. et al\, The Second Beam-Line and Experimental Area a t n_TOF: A New Opportunity for Challenging Neutron Measurements at CERN\, Nuclear Physics News\, 25\, 2015\n[4] Sabaté-Gilarte M. et al\, High-accu racy determination of the neutron flux in the new experimental area n_TOF- EAR2 at CERN\, Eur. Phys. J. A 53\, 2017\n[5] Stamatopoulos A. et al. Inve stigation of the 240Pu(n\,f) reaction at the n_TOF/EAR2 facility in the 9 meV–6 MeV range\, Phys. Rev. C 102\, 2020\n[6] Barbagallo M. et al. Be(n \,α)4He Reaction and the Cosmological Lithium Problem: Measurement of the Cross Section in a Wide Energy Range at n_TOF at CERN\, Phys. Rev. Lett. 117\, 2016\n[7] Damone L. et al\, 7Be(n\,p)7Li Reaction and the Cosmologic al Lithium Problem: Measurement of the Cross Section in a Wide Energy Rang e at n_TOF at CERN. Phys. Rev. Lett. 121\, 2018\n[8] C. Lederer-Woods et a l\, Destruction of the cosmicγ-ray emitter 26Al in massive stars: Study o f the key 26Al(n\,α) reaction\, Phys. Rev. Lett. C 104\, 2021\n[9] Sabat é-Gilarte M. et al\, The 33S(n\,α)30Si cross section measurement at n_TO F-EAR2 (CERN): From 0.01 eV to the resonance region\, EPJ Web Conf. 146\, 2017\n\nhttps://indico.frib.msu.edu/event/52/contributions/706/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/706/ END:VEVENT BEGIN:VEVENT SUMMARY:Mesurement of the 160Gd(n\, γ) cross section at n_TOF and its med ical implications DTSTART:20220725T170600Z DTEND:20220725T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-657@indico.frib.msu.edu DESCRIPTION:Speakers: Giuseppe Tagliente\, Nicola Colonna\, Alberto Mengon i\, Sergio Cristallo\, Cristian Massimi\, and the n_TOF Collaboration\, Ma rio Mastromarco (INFN and UniBa\, Bari\, Italy)\n\n1. Istituto Nazionale d i Fisica Nucleare\, Sez. di Bari\, Bari\, Italy\n2. Università degli stud i di Bari\, Dipartimento Interateneo di Fisica\, Bari\, Italy\n3. Istituto Nazionale di Fisica Nucleare\, Sez. di Perugia\, Perugia\, Italy\n4. Isti tuto Nazionale di Astrofisica\, Osservatorio Astronomico d’Abbruzzo\, Te ramo\, Italy\n5. Istituto Nazionale di Fisica Nucleare\, Sez. di Bologna\, Bologna\, Italy\n6. Università di Bologna\, Dipartimento di Fisica e Ast ronomia\, Bologna\, Italy\n7. European Organization for Nuclear Research\, Geneva\, Switzerland\n8. ENEA Research Centre E. Clementel\, Bologna\, It aly\n\nThe neutron capture reaction cross section of gadolinium isotopes p lay an important role in several fields of Physics\, for instance in Nucle ar Astrophysics for the understanding of the nucleosynthesis of heavy elem ents (beyond iron) in stars via the s- and r-processes [1] and in nuclear technology. Another important application of gadolinium is linked to the p roduction of Terbium\, that offers a set of clinically interesting isotope s for theranostics\, characterized by complementary physical decay charact eristics. In particular\, the low-energy β- emitter Terbium-161 is very s imilar to Lutetium-177 in terms of half-life (6.89 d)\, β-energy and chem ical properties. Being a significant emitter of conversion/Auger electrons \, greater therapeutic effect can therefore be expected in comparison to L u-177 [2\, 3]. For this reason\, in the last decade\, the study of neutron capture reaction $^{160}$Gd(n\,γ)$^{161}$Gd and the subsequent β-decay in Terbium-161 is getting particular attention. As the nuclear data on the Gd-160 neutron capture reaction are quite scarce and inconsistent\, a new measurement of the capture cross section of Gd-160 at the CERN neutron Ti me-Of-Flight facilty will provide high resolution\, high-accuracy data on this important reaction of interest for Nuclear Astrophysics and Nuclear M edicine\, in the energy range from thermal to tens of keV. In this talk\, the preliminary results of the n_TOF measurement will be presented.\n\n\nR eferences:\n\n[1] F. Käppeler\, R. Gallino\, S. Bisterzo\, Wako Aoki\, Re v. Mod. Phys. **83**\, 157 (2011)\n[2] C. Müller\, K. Zhernosekov et al.\ , Jour. of Nucl. Med. **53** (12) 1951 - 1959\n[3] S. Lehenberger\, C. Bar khausen et al.\, Nucl. Med. and Biol. **38** (2011) 917 - 924\n\nhttps://i ndico.frib.msu.edu/event/52/contributions/657/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/657/ END:VEVENT BEGIN:VEVENT SUMMARY:Stochastically Estimated Fission Yield Covariance Matrices DTSTART:20220727T134800Z DTEND:20220727T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-726@indico.frib.msu.edu DESCRIPTION:Speakers: Lee Bernstein\, Eric Matthews\n\nA Monte-Carlo metho d for the generation of correlation and covariance matrices for independen t and cumulative fission yields has been developed. The method uses a cons trained Monte-Carlo resampling structure in order to vary evaluated fissio n yield libraries in a way that meets basic conservation principles. This results in the generation of correlation/covariance matrices with limited model bias and uncertainty\; the matrices are primarily reflective of the evaluated fission yield uncertainties and correlations that arise from the evaluation process. This method has been applied to generate correlation and covariance matrices for all of the fissioning systems of the ENDF/B-VI II.0 and JEFF-3.3 evaluations\, marking the first time such matrices have been generated for all of these systems. These covariance matrices have be en published online for immediate public use. Presented is the method by w hich these matrices were generated\, a discussion of the results\, and exa mples of the use of these matrices in applications.\n\nhttps://indico.frib .msu.edu/event/52/contributions/726/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/726/ END:VEVENT BEGIN:VEVENT SUMMARY:Toward an exact Bayesian inference of fission nuclear data DTSTART:20220727T132400Z DTEND:20220727T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-724@indico.frib.msu.edu DESCRIPTION:Speakers: David Regnier\n\nEvaluating nuclear data reduces the information of a set of experimental data and theoretical models to prov ide the best estimate of a physical quantity. In the last decade safety ap plications pushed the evaluation community toward better quantification of the uncertainties associated to evaluated nuclear data. The Bayesian infe rence appears as a standard and versatile mathematical framework to estima te such uncertainties. As a matter of fact\, it is now a widespread tool t o evaluate neutron cross sections\, especially in the resolved resonance r egion [1]. On the other hand\, the current JEFF evaluations related to the fission cross sections at higher energies as well as the neutron multipli cities and prompt neutron spectra do not often rely on a rigorous applica tion of a Bayesian inference and if so only within some approximated treat ments [1\,2]. In a long term objective to better ground the determination of uncertainties in evaluations\, we explore the feasibility of an exact B ayesian inference of the nuclear data associated to fission.\n\nIn this pr esentation\, I will emphasize our preliminary attempts to perform an exact Bayesian inference to evaluate the total neutron induced cross section of an actinide in the continuum energy range as well as on the prompt neutro n multiplicity and spectrum. I will emphasize our current results and conc lude on the difficulties and challenges of such developments.\n\n[1] C. DE SAINT JEAN\, P. ARCHIER\, E. PRIVAS\, G. NOGUÈRE\, B. HABERT\, P. TAMAGN O\, Nuclear Data Sheets 148\, 383-419 (2018)\n[2] D. ROCHMAN\, E. BAUGE\, A. VASILIEV\, H. FERROUKHI\, S. PELLONI\, A.J. KONING\, J.Ch. SUBLET\, Eur opean Physical Journal Plus 133\, 537 (2018)\n\nhttps://indico.frib.msu.ed u/event/52/contributions/724/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/724/ END:VEVENT BEGIN:VEVENT SUMMARY:Statistical Uncertainty Quantification of Probability Tables for U nresolved Resonance Cross Sections DTSTART:20220725T193300Z DTEND:20220725T194500Z DTSTAMP:20260420T153400Z UID:indico-contribution-862@indico.frib.msu.edu DESCRIPTION:Speakers: Kenichi Tada (Japan Atomic Energy Agency)\n\nThe sel f-shielding effect in the unresolved resonance region has a large impact o n the fast- and intermediate-spectrum reactors. The probability table meth od is widely used for continuous-energy Monte Carlo calculation codes to t reat the effect. In this method\, a table provides the probability distrib ution of the cross-section for a nuclide in the given energy grid points. The table is generated by averaging with a lot of “ladders” which repr esent pseudo resonance structures. Though many nuclear data processing cod es require the number of ladders as an input parameter to generate the pro bability table\, an optimal number of ladders has not been investigated. O ur previous study revealed that the suitable number of ladders depends on the nuclide and its resonance parameters. This result indicates that it is very difficult for users to find the optimal number of ladders.\n We dev eloped the calculation method of the statistical uncertainty for the proba bility table generation. The product of the probability table and total cr oss-section in each probability bin is considered as the target of statist ical uncertainty of the probability table. The central limit theorem (CLT) method\, the Bootstrap method\, and the Jackknife method are used to calc ulate the statistical uncertainty and the statistical uncertainties of the se methods are compared. The calculation results indicate that the statist ical uncertainty of the CLT method is similar to that of the other methods . The CLT method is the best way to calculate the statistical uncertainty of the probability table with a short computational time.\n This statisti cal uncertainty calculation method for the probability table generation wi ll be implemented in the next version of the nuclear data processing code FRENDY\, i.e.\, FRENDY version 2. Users can generate the probability table with the optimal number of ladders when users set the criterion of the st atistical uncertainty of the probability table as the input parameter.\n\n https://indico.frib.msu.edu/event/52/contributions/862/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/862/ END:VEVENT BEGIN:VEVENT SUMMARY:Burnup Calculation Uncertainty Using Statistical Sampling Method DTSTART:20220725T193300Z DTEND:20220725T194500Z DTSTAMP:20260420T153400Z UID:indico-contribution-775@indico.frib.msu.edu DESCRIPTION:Speakers: Xiaofei Wu\n\nThe nuclear data are the basic data fo r reactor burnup calculation. It is significant to study the contribution of their uncertainty to the uncertainty of reactor burnup calculation for improving the safety and economy of reactor. we propagated the uncertainti es coming from the nuclear data to the isotopic inventory of sample SF95-4 . A Monte Carlo sampling code was developed and used to propagate the deca y constant uncertainties\, cross-section covariance information and uncert ainties of the fission yields. The results showed that the impact of decay constant uncertainties was inappreciable and the contribution of cross-se ction covariance mostly affected the uncertainties of the actinides. Fissi on yields appeared to have the largest impact on the uncertainties of the fission products.\n\nhttps://indico.frib.msu.edu/event/52/contributions/77 5/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/775/ END:VEVENT BEGIN:VEVENT SUMMARY:EMU: Evaluated Means and Uncertainties DTSTART:20220727T152100Z DTEND:20220727T153300Z DTSTAMP:20260420T153400Z UID:indico-contribution-731@indico.frib.msu.edu DESCRIPTION:Speakers: Ali Dreyfuss (LLNL)\, Kyle Wendt (Lawrence Livermore National Laboratory)\n\nEvaluated Means and Uncertainties\, or EMU\, is a new suite of tools for generating statistical realizations of nuclear dat a libraries encoded in the Generalized Nuclear Database Structure (GNDS). Built upon the For Updating Data and Generating Evaluations (FUDGE) packag e from LLNL\, EMU is capable of reading and generating realizations of nea rly any accessible nuclear data library\, whether they originate in ENDL\, ENDF\, of GNDS formats. EMU was developed with two run modes\; a traditio nal command line interface that creates realized GNDS files for a reaction \, and a “sample map” mode that can automate large scale uncertainty q uantification involving many different materials and even different librar ies. This sample map mode can also automate the processing of GNDS files s o that reactions at the different temperatures and groupings are correctly related to each other within the realization. I will review the general s tructure of EMU and what makes it unique\, and give an overview of how it can easily integrate into other uncertainty quantification workflows.\nThi s work was performed under the auspices of the U.S. Department of Energy b y Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344. \n\nhttps://indico.frib.msu.edu/event/52/contributions/731/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/731/ END:VEVENT BEGIN:VEVENT SUMMARY:WPEC SG50: Developing an Automatically Readable\, Comprehensive an d Curated Experimental Nuclear Reaction Database DTSTART:20220726T132400Z DTEND:20220726T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-863@indico.frib.msu.edu DESCRIPTION:Speakers: Amanda Lewis (Naval Nuclear Laboratory)\n\nThe EXFOR database is the major source to retrieve experimental data as input for n uclear data evaluations. It aggregates decades worth of international nucl ear data measurements. EXFOR is specifically designed to store experimenta l data as it was reported by the experimentalists\, with limited correctio ns made as needed. For this reason\, the database does not store the subje ctive alterations to the data sets by users\, such as evaluators. For exa mple\, evaluators may re-normalize data sets or augment uncertainties to i ncrease consistency between data sets in their evaluation. These altered d ata sets\, which are needed to reproduce the evaluations\, are not readily available to others in the field. To improve the reproducibility of evalu ations\, the choices made by the evaluators need to be stored in a databas e that builds on the EXFOR database. In addition\, some data in EXFOR are not easy to interpret automatically\, including meta-data about experimen ts. If the new database improves the interpretability of this data with a different format\, applying automatic processing and using machine learni ng techniques will be more tenable. To design this new database\, an inter national collaboration has been established through the Organisation for E conomic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) Wo rking Party on International Nuclear Data Evaluation Co-operation (WPEC) S ubgroup 50 (SG50): Developing an Automatically Readable\, Comprehensive an d Curated Experimental Reaction Database. The goals of SG50 are to create a requirements document\, a specifications document\, and example files. T he requirements document will contain the metadata to be stored in the new database\, while the specifications document will outline the data struct ures used to store the information. This presentation will outline the cur rent progress of SG50.\n\n LA-UR-21-28324\n\nhttps://indico.frib.msu.edu/e vent/52/contributions/863/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/863/ END:VEVENT BEGIN:VEVENT SUMMARY:Overview of experimental nuclear data from the n_TOF Collaboration DTSTART:20220726T133600Z DTEND:20220726T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-864@indico.frib.msu.edu DESCRIPTION:Speakers: Emmeric Dupont (CEA)\n\nThe n_TOF neutron spallation source at CERN is used since 2001 for high quality nuclear data measureme nts from sub-thermal energy up to hundreds of MeV for the benefit of vario us communities in the fields of nuclear physics\, nuclear astrophysics and nuclear technology. In the past twenty years\, a considerable amount of v aluable experimental results has been obtained and published\, and measure ments are still ongoing. In line with the CERN open data policy\, the n_TO F Collaboration has taken actions [1] to preserve its unique data\, to fac ilitate access to them\, and to allow their re-use by expert users. For th e vast majority of published results\, reaction yields\, cross sections an d resonance parameters are now available in the international EXFOR databa se. However\, these results have not been fully exploited yet for the bene fit of the end-users\, in particular for the improvement of evaluated nucl ear data libraries. This contribution aims at updating the status and avai lability of n_TOF data\, and to discuss ongoing efforts for better integra tion of the results in the evaluated library projects.\n\n[1] E. Dupont et al. (The n_TOF Collaboration)\, Dissemination of data measured at the CER N n_TOF facility\, EPJ Web Conf. 146 (2017) 07002\n\nhttps://indico.frib.m su.edu/event/52/contributions/864/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/864/ END:VEVENT BEGIN:VEVENT SUMMARY:Dissemination of nuclear structure and decay data DTSTART:20220726T134800Z DTEND:20220726T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-866@indico.frib.msu.edu DESCRIPTION:Speakers: Paraskevi Dimitriou (International Atomic Energy Age ncy)\n\nThe availability of reliable\, up-to-date and well-structured nucl ear data libraries\, with user-friendly visualization and retrieval interf aces\, is a valuable tool for both nuclear specialists in the applications fields and nuclear physics researchers.\n\nThe International Atomic Energ y Agency (IAEA) has been coordinating the international network of Nuclear Structure and Decay Data evaluators (NSDD) which maintains the Evaluated Nuclear Structure Data File (ENSDF) since 1974. In addition\, it has been organising and leading a series of international projects with the purpose of collecting\, evaluating and disseminating nuclear structure and decay data to address specific user needs. The output of the network activity an d projects are disseminated via publications and online databases with use r-friendly visualization and retrieval interfaces. \n\nIn this paper we pr esent the status of the following three data development and dissemination efforts carried out at the IAEA:\n\na) Live Chart: interactive interface to the Evaluated Nuclear Structure Data File (ENSDF) produced by the NSDD network (https://www-nds.iaea.org/livechart/) \nb) Reference database for beta-delayed neutrons: online database and interactive interface to the co mpiled and evaluated beta-delayed neutron data produced by an IAEA Coordin ated Research Project (https://www-nds.iaea.org/beta-delayed-neutron/datab ase.html) \nc) Nuclear moments database: online database and interactive i nterface to the compiled and recommended magnetic dipole and electric quad rupole moments produced by N.J. Stone with contributions from experts with in an IAEA project (https://www-nds.iaea.org/nuclearmoments/)\n\nhttps://i ndico.frib.msu.edu/event/52/contributions/866/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/866/ END:VEVENT BEGIN:VEVENT SUMMARY:GNDS-2.0 DTSTART:20220726T130000Z DTEND:20220726T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-861@indico.frib.msu.edu DESCRIPTION:Speakers: Caleb M Mattoon (Lawrence Livermore National Labora tory)\, David Brown (NNDC\, Brookhaven National Laboratory)\n\nThe General ised Nuclear Database Structure is a new standard for representing reactio n and decay data in nuclear data libraries and is slated to replace the le gacy ENDF-6 format. GNDS is designed to be both human readable and easy to work with so that downstream code developers can create software that sup ports GNDS. The specifications for GNDS-1.9 were published in 2020\; this version describes the GNDS format used in the ENDF/B-VIII.0 library relea se. Work on GNDS-2.0 began soon after GNDS-1.9 was published with the foc us on satisfying all of the requirements defined by WPEC Subgroup 38. In this contribution\, we will detail the major changes in GNDS-2.0 including a new thermal neutron scattering markup that allows for mixed mode modera tors\, an expressive documentation format supporting rich meta data and im proved support for covariance data\, including thermal neutron scattering covariances. In addition\, GNDS-2.0 improves and simplifies the resonance parameter descriptions\, supports map-files (the GNDS equivalent of an AC E xsdir file)\, and provides a host of other smaller improvements. We wil l outline the timeline for finalizing GNDS-2.0 and the implementation stat us in processing codes.\n\nThis work was supported by the Nuclear Critical ity Safety Program\, funded and managed by the National Nuclear Security A dministration for the Department of Energy. The work at Brookhaven Nation al Laboratory was sponsored by the Office of Nuclear Physics\, Office of S cience of the U.S. Department of Energy under Contract No. DE-AC02-98CH108 86 with Brookhaven Science Associates\, LLC.\n\nhttps://indico.frib.msu.ed u/event/52/contributions/861/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/861/ END:VEVENT BEGIN:VEVENT SUMMARY:The National Nuclear Data Center is a Public Reusable Research (Pu Re) Data Resource DTSTART:20220726T165400Z DTEND:20220726T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-889@indico.frib.msu.edu DESCRIPTION:Speakers: Elizabeth McCutchan (BNL)\, Benjamin Shu (National N uclear Data Center)\, Alejandro Sonzogni (NNDC - BNL)\, Donnie Mason\, Ram on Arcilla (NNDC-BNL)\, David Brown\n\nIn May 2021\, the National Nuclear Data Center (NNDC) was designated by the US Department of Energy Office of Science (SC) as a Public Reusable Research (PuRe) Data Resource. The DOE defines "PuRe Data Resources are data repositories\, knowledge bases\, an alysis platforms\, and other activities that make data publicly available to enable better communication\, better stewardship\, and better science." The NNDC is the only PuRe resource in SC's Nuclear Physics program. Suc h a designation is a source of great pride for the NNDC\, but comes with n umerous conditions\, obligations and opportunities. In this talk\, we will outline the NNDC's progress towards implementing the requirements of bein g a PuRe resource: the generation of Document Object Identifiers for all N NDC managed libraries\, modernization of the NNDC website\, modernization of the underlying library infrastructure\, and development of a robust dat a preservation strategy.\n\n\nThe work at Brookhaven National Laboratory w as sponsored by the Office of Nuclear Physics\, Office of Science of the U .S. Department of Energy under Contract No. DE-AC02-98CH10886 with Brookha ven Science Associates\, LLC.\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/889/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/889/ END:VEVENT BEGIN:VEVENT SUMMARY:Welcome address DTSTART:20220725T130000Z DTEND:20220725T131500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1240@indico.frib.msu.edu DESCRIPTION:Speakers: Kim Budil (LLNL)\n\nhttps://indico.frib.msu.edu/even t/52/contributions/1240/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1240/ END:VEVENT BEGIN:VEVENT SUMMARY:A decay database of coincident $\\gamma/\\gamma$ and $\\gamma/X$-r ay branching ratios for in-field applications DTSTART:20220726T140000Z DTEND:20220726T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-868@indico.frib.msu.edu DESCRIPTION:Speakers: Aaron Hurst (University of California\, Berkeley)\n\ nCurrent fieldable spectroscopy techniques often use single detector syste ms heavily impacted by interferences from intense background radiation fie lds. These effects result in low-confidence measurements that can lead to misinterpretation of the collected spectrum. To help improve interpretat ion of the fission products and short-lived radionuclides produced in a co mposite sample\, a coincidence-$\\gamma$ database is being developed in su pport of a robust portable $\\gamma$/$X$-ray coincidence detector system c oncurrently under development at the Pacific Northwest National Laboratory for in-field deployment. Hitherto\, no database exists containing coinci dent $\\gamma/\\gamma$ and $\\gamma/X$-ray branching ratios on an absolute scale that will greatly enhance isotopic identification for in-field appl ications.\n\n As part of this project\, software has been developed to pa rse all radioactive-decay data sets from the Evaluated Nuclear Structure D ata File (ENSDF) archive to enable translation into more useful eXtensible Markup Language (XML) and JavaScript Object Notation (JSON) formats that more readily support query-based data manipulation. The coincident databa se described in this work is the first of its kind and contains coincidenc e $\\gamma/\\gamma$\, $\\gamma/X$-ray\, and $\\gamma/< particle >$ branch ing ratios (where $< particle >$ = $\\alpha$\, $\\beta^{-}$\, $\\beta^{+}$ \, $\\epsilon$) and their corresponding uncertainties\, together with auxi liary metadata associated with each decay data set. Both XML and JSON for mats provide a convenient and portable means of data storage that can be i mported into analysis frameworks with relatively low overhead allowing for meaningful comparison with measured data.\n\nhttps://indico.frib.msu.edu/ event/52/contributions/868/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/868/ END:VEVENT BEGIN:VEVENT SUMMARY:The Modular Cosmic Ray Detector (MCORD) at physics and astrophysic s experiments. DTSTART:20220727T144500Z DTEND:20220727T150900Z DTSTAMP:20260420T153400Z UID:indico-contribution-743@indico.frib.msu.edu DESCRIPTION:Speakers: Kamil Wojcik (Silesia University)\, Seweryn Kowalski (Silesia University)\, Dominik Rybka (National Centre for Nuclear Researc h)\, Tomasz Szczesniak (National Centre for Nuclear Research)\, Krystian G rodzicki (National Centre for Nuclear Research)\, Piotr Kolasinski (Warsaw University of Technology)\, Pawel Kankiewicz (Jan Kochanowski University) \, Mikolaj Sowinski (Warsaw University of Technology)\, Wojciech Zabolotny (Warsaw University of Technology)\, Jaroslaw Szewinski (National Centre f or Nuclear Research)\, Jaroslaw Grzyb (National Centre for Nuclear Researc h)\, Grzegorz Kasprowicz (Warsaw University of Technology)\, Elzbieta Jawo rska (National Centre for Nuclear Research)\, Aleksandr Bancer (National C entre for Nuclear Research)\, Lukasz Swiderski (National Centre for Nuclea r Research)\, Michal Kiecana (National Centre for Nuclear Research)\, Krzy sztof Pozniak (Warsaw University of Technology)\, Slawomir Mianowski (Nati onal Centre for Nuclear Research)\, Maciej Rybczynski (Jan Kochanowski Uni versity)\, Agnieszka Syntfeld-Kazuch (National Centre for Nuclear Research )\, Marcin Bielewicz (National Centre for Nuclear Research)\n\nIt has been proposed to design and build an modular\, a simple and effective cosmic r ay detector (muon detector) that can be used both in laboratory measuremen ts and in great physics experiments. The main goal of this system is to pr ovide information from cosmic muons that pass the other detector in both i n-beam and off-beam experiments for testing and calibration. Moreover\, ob servation of muons originating from decays of collision products will also be possible. The system could also be very useful for observations of cos mic showers initiated by high energy primary particles\, it can expand the possibilities of collecting scientific data with astrophysical observatio ns. The proposed detector is called the Modular COsmic Ray Detector (MCORD ). The MCORD is designed as a universal\, fast triggering system built as a modular reconfigurable construction. We describes the second stage of th e project (demonstrator) and third stage (potential use in big experiments ) of the MCORD detector based on plastic scintillators with silicon photom ultiplier photodetectors (SiPM) for scintillation readout and electronic d ata analyze system based FPGA electronic on MicroTCA crate .\n\nhttps://in dico.frib.msu.edu/event/52/contributions/743/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/743/ END:VEVENT BEGIN:VEVENT SUMMARY:239Pu R-matrix Analysis and Neutron Multiplicities in the Neutron Energy Region up to a few keVs DTSTART:20220726T171800Z DTEND:20220726T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-892@indico.frib.msu.edu DESCRIPTION:Speakers: Marco Pigni (ORNL)\n\nThe evaluation of $^{239}$Pu n eutron resonance parameters coupled to neutron multiplicities $\\bar{\\nu} _{p}$ is of particular importance to investigate the $(n\,\\gamma f)$ reac tion in which a $\\gamma$-ray emission occurs before the scission of the c ompound nuclear. This reaction has offered one explanation for the fluctua tions in the measured values of $\\bar{\\nu}_{p}$. In this regard\, the co mpetition between $(n\,\\gamma f)$ reaction and the direct fission process can be also included in the $R$-matrix analysis of fission and capture me asured data.\n\nThe goal of this work is the coupled evaluation of the $n$ +$^{239}$Pu resonance parameters and related neutron multiplicities by ens uring the adoption of thermal neutron constants recently evaluated at the International Atomic Nuclear Energy as well as the recommended (thermal-ne utron) induced prompt neutron fission spectrum. Moreover\, this new set of physical evaluated quantities should also guarantee the agreement for hig h-leakage solution benchmarks while keeping the good performance of large thermal solution assemblies.\n\nhttps://indico.frib.msu.edu/event/52/contr ibutions/892/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/892/ END:VEVENT BEGIN:VEVENT SUMMARY:Bayesian network evaluation of neutron-induced reactions of Fe-56 DTSTART:20220726T183900Z DTEND:20220726T185100Z DTSTAMP:20260420T153400Z UID:indico-contribution-897@indico.frib.msu.edu DESCRIPTION:Speakers: Roberto Capote (IAEA)\, Georg Schnabel (IAEA)\n\nWe present the progress made in the evaluation of neutron-induced reactions o f Fe-56 using a Bayesian network. The Bayesian network framework facilitat es the incorporation of a diverse set of measurements\, such as residual p roduction cross sections and angular distributions. A nuclear physics mode l code in combination with Gaussian processes to take into account model i mperfections is used in the fast energy range. In the energy range between about one and five MeV\, we use a flexible Gaussian process construction instead of a physics model. The Bayesian network framework enables us to e valuate these two energy ranges simultaneously with a smooth transition be tween them and sum rule constraints between channels being respected.\n\nh ttps://indico.frib.msu.edu/event/52/contributions/897/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/897/ END:VEVENT BEGIN:VEVENT SUMMARY:Back-n Facility Status and Recent Nuclear Data Measurements DTSTART:20220726T130000Z DTEND:20220726T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-676@indico.frib.msu.edu DESCRIPTION:Speakers: J. Tang (CSNS/CADS/IHEP)\n\nThe Back-n white neutron source at CSNS (China Spallation Neutron Source) has been in operation si nce 2018. As a multidisciplinary research platform\, Back-n has its main f ocus on nuclear data measurements. With its unique beamline using the back -streaming neutrons from a proton beam of 100 kW in beam power impinging o n a thick spallation target in tungsten\, Back-n owns the highest neutron flux for a given flight path among white neutron sources. The other excell ent properties include a wide neutron energy spectrum covering from 0.3 eV to 200 MeV and a good time resolution of a few per mille in most of the e nergy range. Currently available detector systems or spectrometers are FIX M for fission cross-section measurements\, C6D6 detectors and GTAF-II for neutron capture measurements\, LPDA for light-particle emission measuremen ts\, NTOX for total cross-section measurements\, and user-owned HPGe detec tors for in-beam gamma spectrum measurements. All the above types of exper iments have been carried out regularly at Back-n with an averaged beam tim e of 3000 hours per year. In addition\, the experimental study on the time reversal violation with neutrons is also under way. This presentation wil l introduce the improvements of the Back-n facility in the last years\, in cluding proton beam power ramp-up\, enhanced measurements on the neutron e nergy spectrum\, detector systems\, and also a summary of the nuclear data measurements.\n\nhttps://indico.frib.msu.edu/event/52/contributions/676/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/676/ END:VEVENT BEGIN:VEVENT SUMMARY:The TENDL library: progress\, success\, and lessons learned DTSTART:20220725T163000Z DTEND:20220725T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-852@indico.frib.msu.edu DESCRIPTION:Speakers: Arjan Koning (IAEA)\, Jean-Christophe Sublet (IAEA)\ , Dimitri Rochman (Paul Scherrer Institute)\n\nThe TALYS Evaluated Nuclear Data Library (TENDL) had 11 releases since 2008. A\nnumber of achievement s has been realized\, translated in a growing user group\, as well\nas a h igh interaction with other library projects. The backbone of this achievem ent\nis simple and robust: completeness\, quality and reproducibility. In this presentation\,\nthe strong points of TENDL will be outlined\, as well as the existing weaknesses\nwith regards to the current nuclear data land scape. Finally\, future improvements\nwill be discussed\, based on the use r needs\, as well as realities from the nuclear data\ncommunities.\n\nhttp s://indico.frib.msu.edu/event/52/contributions/852/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/852/ END:VEVENT BEGIN:VEVENT SUMMARY:New Capabilities of the RPI Gamma-Multiplicity Detector to Measure Gamma Production DTSTART:20220726T165400Z DTEND:20220726T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-714@indico.frib.msu.edu DESCRIPTION:Speakers: Amanda Lewis (Naval Nuclear Laboratory)\, Adam Ney ( Rensselaer Polytechnic Institute)\, Michael Rapp (Naval Nuclear Laboratory )\, Dominik Fritz (Rensselaer Polytechnic Institute)\, Peter Brain (Rensse laer Polytechnic Institute)\, Yaron Danon (Rensselaer Polytechnic Institut e)\, Sukhjinder Singh (Rensselaer Polytechnic Institute)\, Benjamin Wang ( Rensselaer Polytechnic Institute)\, Ezekiel Blain (Rensselaer Polytechnic Institute)\, Katelyn Cook (Rensselaer Polytechnic Institute)\n\nAccurate g amma production in capture reactions is critical for simulation of nuclear reactor applications. This includes modeling of strength functions and le vel densities and calculating cross sections from resonance parameters. To improve this work\, the Rensselaer Polytechnic Institute (RPI) 16-segment gamma-multiplicity NaI(Tl) detector at the Gaerttner Linear Accelerator C enter (LINAC) has been upgraded by implementing a digitizing data acquisit ion system. The new digitized system can measure the gamma energy distribu tion in each individual detector\, and gamma-multiplicity values as a func tion of neutron time-of-flight. With the new capabilities\, high precision capture (and fission) yield measurements can be made\, and the accuracy o f simulation tools used to predict the capture gamma cascades can be teste d. To validate the yield measurements completed with the updated system\, an experiment was performed using a natural Ta sample to measure $^{181}$T a and $^{180m}$Ta resonance capture yield as a function of neutron energy by detecting prompt gammas emitted from neutron capture interactions using the time-of-flight method. Capture yield was also calculated as a functio n of the measured gamma multiplicity of each capture event. The Ta results confirm earlier measurements and agree with theoretical yield in the low energy resonance region from 1 to 20-eV. This measurement also includes th e 0.01-eV thermal region\, where there is currently little experimental da ta. In addition to the yield validation\, a measurement of $^{238}$U was p erformed to generate gamma emission spectra for observed multiplicities. F or capture gamma cascades where the total gamma energy deposition is close to the neutron binding energy\, gamma emission spectra were measured for individual resonance energies for the $^{238}$U(n\, γ) reaction. The resu lts were compared to a recent measurement done using the Detector for Adva nced Neutron Capture Experiments (DANCE) array at Los Alamos Neutron Scien ce Center (LANSCE)\, and Monte-Carlo n-particle simulations. The measured gamma emission spectra for observed two step cascades had general agreemen t with the LANSCE shape\; however\, there were noticeable differences betw een the current measurement (RPI) and previous work (LANSCE).\n\nhttps://i ndico.frib.msu.edu/event/52/contributions/714/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/714/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron Filtering System for Neutron Capture Cross Section Measure ment at the ANNRI beamline of MLF/J-PARC DTSTART:20220727T180000Z DTEND:20220727T181200Z DTSTAMP:20260420T153400Z UID:indico-contribution-749@indico.frib.msu.edu DESCRIPTION:Speakers: Gerard Rovira Leveroni (Japan Atomic Energy Agency)\ n\nAccurate nuclear data for neutron capture reactions of minor actinides (MA) are required to estimate the production and the transmutation rates d ue to their preponderant role in the study and design of transmutation sys tems related to nuclear waste management. Since its construction in 2009\, continuous research efforts have been carried out to measure neutron-indu ced reactions at the Accurate Neutron Nucleus Reaction Measurement Instrum ent (ANNRI) of the Japan Proton Accelerator Research Complex (J-PARC). Neu tron capture cross section experiments have been performed involving the c omplementary use of the two detector setups installed at ANNRI\, a large a rray of high-purity Ge detectors and a NaI(Tl) spectrometer. \nNonetheless \, ever since the J-PARC accelerator was switch onto double-bunch mode\, n eutron capture cross section measurements have become unfeasible using keV neutron. In the keV region\, the 0.6 µs time difference between neutron generating events\, i.e.\, spallation reactions\, is not negligible. Hence \, the double-bunch mode introduces serious ambiguities in keV-neutron-ind uced reactions due to the overlapped contribution of the two neutron-gener ating events.\nA neutron filtering system has been installed at the ANNRI beamline in order to bypass the doublet structure of the incident neutron beam in the keV region. Thick cylindrical slabs of $^{nat}$Fe\, $^{nat}$Si and $^{nat}$Cr which share the characteristic of a sharp minimum in the n eutron total cross section\, were separately introduced in an intermediate stage of the beamline\, before the NaI(Tl) spectrometer experimental area . The filtered neutron beams were analyzed by means of both neutron captur e and transmission experiments. Moreover\, further information about the n eutron energy distribution within the filtered peaks was derived through t he use of Monte-Carlo simulations with the PHITS code [1].\nThis presentat ion will provide an overview of the neutron filtering system implemented a t ANNRI. The main characteristics of the filtered neutron beams for $^{nat }$Fe and $^{nat}$Si\, already published here [2]\; and $^{nat}$Cr will be presented together with 197Au standard experimental results to assess the performance of the neutron filtering system in neutron capture cross secti on experiments. \nThis work is supported by the Innovative Nuclear Researc h and Development Program from the Ministry of Education\, Culture\, Sport s\, Science and Technology of Japan\n\n[1] T. Sato et al. J. Nucl. Sci. Te chnol. 55\, 684 (2018) \n[2] G. Rovira et al.\, Nucl. Instr. Meth. 1003\, 165318 (2021)\n\nhttps://indico.frib.msu.edu/event/52/contributions/749/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/749/ END:VEVENT BEGIN:VEVENT SUMMARY:Gamma-ray Beamline SLEGS at Shanghai Light Source DTSTART:20220727T150900Z DTEND:20220727T152100Z DTSTAMP:20260420T153400Z UID:indico-contribution-744@indico.frib.msu.edu DESCRIPTION:Speakers: Gongtao Fan (Shanghai Advanced Research Institute\, Chinese Academy of Sciences)\n\nShanghai Light Source has been operated si nce 2009 to provide synchrotron radiations to 40 beamlines of the electron storage ring at a fixed electron energy\, 3.5 GeV. The Shanghai Laser Ele ctron Gamma Source (SLEGS) is approved as one of 16 beamlines in the Phase II project in 2016 to produce energy-tunable gamma-ray beams in the inver se Compton slant-scattering of laser photons from a 100 W CO2 laser on the 3.5 GeV electrons as well as in the back-scattering [1\,2]. The laser Com pton slant-scattering was pioneered as early as in 1996 [3] and more recen tly used to produced gamma rays [4]. The slant-scattering makes the usage of energy-tunable gamma-ray beams compatible with that of the synchrotron radiation in synchrotron radiation facilities operated at a fixed electron beam energy worldwide.\nThe SLEGS is designed to produce gamma rays in th e energy range of 0.66 – 21.7 MeV with a flux of 105 – 107 photons/s a nd an energy spread of 4.2 – 4.6 % with an aperture of 2 mm of the doubl e collimator system [2]. We have confirmed the generation of gamma-ray bea ms in the slant-scattering from 20o to 160o as well as in the back-scatter ing at 180o in the commissioning of the SLEGS beamline. We plan to open th e SLEGS beamline to international users in the summer of 2022. We present the performance of the SLEGS beamline based on results of the commissionin g and test measurements.\n\n[1] H.H. Xu et al.\, to be submitted to Nuclea r Inst. and Methods\, Physics Research A. \n[2] Z.R. Hao et al.\, Nuclear Inst. and Methods\, Physics Research A 1013\, 165638 (2021). \n[3] R.W. Sc hoenlein et al.\, Science 274\, 236-238 (1996).\n[4] Y. Taira et al.\, Nuc lear Inst. Methods\, Phys. Res. A 652\, 696-700 (2011).\n\nhttps://indico. frib.msu.edu/event/52/contributions/744/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/744/ END:VEVENT BEGIN:VEVENT SUMMARY:Laser Compton Slant-scattering and Double Collimator System at SLE GS of Shanghai Light Source DTSTART:20220727T152100Z DTEND:20220727T153300Z DTSTAMP:20260420T153400Z UID:indico-contribution-748@indico.frib.msu.edu DESCRIPTION:Speakers: Gongtao Fan (Shanghai Advanced Research Institute\, Chinese Academy of Sciences)\n\nThe laser Compton slant-scattering is a ke y technique to achieve the energy tunability in producing gamma-ray beams at synchrotron radiation facilities operated at a fixed electron energy. A pioneering attempt was made of generating MeV gamma-ray beams in the slan t-scattering at 70 – 110o in the UVSOR-II electron storage ring [1]. The Shanghai Laser Electron Gamma Source (SLEGS) is dedicated to systematical ly producing gamma-ray beams in the slant-scattering for international use rs. \n An interaction chamber involving a rotating laser optical system was designed to ensure the slant-scattering of laser photons from a 100 W CO2 laser on 3.5 GeV electrons in the storage ring in the angular range of 20 - 160o\, producing gamma rays in the energy range of 0.66 – 21.1 MeV with a flux of 4.8×105 – 1.5×107 photons/s [2]. The SLEGS is also equ ipped with a double collimator system consisting of a revolver-type coarse collimator and a camera-shutter-type fine collimator [3]. Since gamma ray s produced at Eγ> Emax/2 are confined within the divergence angle 0.2 mra d\, the highest energy part is selected by the double collimator system. T hus\, quasi-monochromatic gamma-ray beams with an energy spread of 4.2 – 4.6 % are produced at the target position by using an aperture of 2 mm of the double collimator system. Generation of gamma-ray beams in the slant- scattering as well as in the back-scattering has been confirmed in the com missioning of the SLEGS beamline. We present the performance of the intera ction chamber and the collimator system in producing gamma-ray beams in th e laser Compton slant-scattering based on the commissioning and test measu rements in detail. \n\n\n[1] Y. Taira et al.\, Nuclear Inst. Methods\, P hys. Res. A 652\, 696-700 (2011).\n[2] H.H. Xu et al.\, to be submitted to Nuclear Inst. and Methods in Physics Research A. \n[3] Z.R. Hao et al.\, Nuclear Inst. and Methods in Physics Research A 1013\, 165638 (2021).\n\nh ttps://indico.frib.msu.edu/event/52/contributions/748/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/748/ END:VEVENT BEGIN:VEVENT SUMMARY:The new Device for Indirect Capture Experiments on Radionuclides a t LANSCE: Efforts on measuring the resonance(s) responsible for the extrem ely large 88Zr(n\,g) cross section DTSTART:20220726T173000Z DTEND:20220726T174200Z DTSTAMP:20260420T153400Z UID:indico-contribution-718@indico.frib.msu.edu DESCRIPTION:Speakers: Thanos Stamatopoulos (Los Alamos National Laboratory )\n\nThe new Device for Indirect Capture Experiments on Radionuclides at L ANSCE: Efforts on measuring the resonance(s) responsible for the extremely large 88Zr(n\,g) cross section \n\nA. Stamatopoulos1\, P. Koehler1\, E. B ond2\, T. A. Bredeweg2\, A. Couture1\, B. DiGiovine1\, M. E. Fassbender2\, A. C. Hayes-Sterbenz3\, G. Keksis2\, A. Matyskin2\, K. Parsons4\, G. Ruse v2\, J. Ullmann1\, C. Vermeulen2\n\n\n\n1. Physics division\, Los Alamos N ational Laboratory\, 87545\, NM\, USA\n2. Chemistry division\, Los Alamos National Laboratory\, 87545\, NM\, USA\n3. Theory Division\, Los Alamos Na tional Laboratory\, 87545\, NM\, USA\n4. X-Computational Physics division\ , Los Alamos National Laboratory\, 87545\, NM\, USA\n\n\nThe thermal neutr on capture cross section of 88Zr was recently reported1 to be the second l argest in nature with the largest resonance integral2 measured. Presumably \, these very large values are caused by a resonance or resonances very ne ar thermal energy\, and determining their energies and widths\, and hence the shape of the cross section away from thermal energy\, would be very us eful for applications. The short half-life (83.4 days) and associated larg e background renders direct measurements of the neutron capture cross sect ion impossible using current techniques. However\, it is possible to measu re the total neutron cross section\, and hence the resonance properties\, using the newly commissioned Device for Indirect Capture Experiments on Ra dionuclides (DICER)3 at the Los Alamos Neutron Science Center (LANSCE). Tr ansmission measurements are utilized as a surrogate method to perform capt ure measurements. The 88Zr needed for a DICER measurement was produced at the Isotope Production Facility (IPF) and cleanly separated from the produ ction target material. The final steps of loading the ~1 g 88Zr sample into DICER and performing the measurement are expected to be completed ver y soon. A description of the new instrument and efforts on 88Zr will be pr esented.\n\n\n\n1. J. Shusterman et al.\, Nature volume 565\, pages 328– 330 (2019)\n2. J. Shusterman et al.\, Phys. Rev. C 103\, 024614 (2021) \n3 . A. Stamatopoulos et al.\, submitted to Nucl. Instrum. Meth. A (2021)\n\n \nLA-UR-21-29581\n\nhttps://indico.frib.msu.edu/event/52/contributions/718 / LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/718/ END:VEVENT BEGIN:VEVENT SUMMARY:Design\, construction\, commissioning and early operation of the t hird-generation n_TOF neutron spallation target at CERN DTSTART:20220726T132400Z DTEND:20220726T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-701@indico.frib.msu.edu DESCRIPTION:Speakers: Jean-Louis Grenard\, Simone Gilardoni\, Javier Praen a\, Michael Bacak\, Fabio Pozzi\, José Maria Martin Ruiz\, Keith Kershaw\ , Francesco Dragoni\, Alberto Mengoni\, Vasalis Vlachoudis\, Matteo Ferrar i\, Dominika Senajova\, Oliver Aberle\, Ana-Paiula Bernardes\, Raffaele Es posito\, Marco Calviani (CERN)\n\nThe European Laboratory for Particle Phy sics (CERN) is equipped with a top-class\, high-brightness\, neutron spall ation source dedicated to high-resolution neutron time-of-flight experimen ts: the n_TOF Facility. \n\nDuring CERN’s Long Shutdown 2 (LS2\, 2019-20 21)\, the n_TOF neutron spallation target has been exchanged and the facil ity is now operating with its third-generation target [1]. The neutron pro duction target is based on a segmented pure Pb (>99.9%) core\, cooled by g aseous nitrogen at atmospheric pressure. The target has been designed for a single bunch proton beam impacting on the production target at 20 GeV/c with up to 1013 protons/bunch\, and with a bunch length of 6 ns RMS. The p roduced neutrons span 11 orders of magnitude in kinetic energy\, from sub- thermal to GeV and are serving two time-of-flight experimental stations pl us an irradiation station. The initially fast neutrons are moderated by tw o independent moderator circuits\, each one dedicated to an experimental s tation\, that can be filled with either by demineralized water or by borat ed water in saturation.\n\nThe contribution will detail the physics optimi zation and engineering design processes that brought the facility from the second-generation target to the current evolutionary one. The work will i nclude a description of the new target design features\, its mechanical as sembly\, and its compliance with safety and physics performance requiremen ts as well as the R&D which has been carried out\, including beam testing at the CERN’s HiRadMat facility [2]. The contribution will also detail t he first hardware results coming from the 2021 facility commissioning\, fi rst radiation protection assessments in the target zone and from early ope ration in 2022.\n\nThe paper will also discuss the plans for an autopsy of the second-generation target to investigate the status of the water-coole d monolithic Pb core after 10 years of operation and its impact on the rad ioactive waste characterization and in the operation of the third-generati on target.\n\n\n[1] R. Esposito et al.\, Design of the third-generation le ad-based neutron spallation target for the neutron time-of-flight facility at CERN\, Phys. Rev. Accel. Beams 24\, 093001 (2021)\n\n[2] R. Esposito a nd M. Calviani\, Design of the third-generation neutron spallation target for the CERN’s n_TOF facility\, J. Neutron Res. 22\, 221 (2020)\n\nhttps ://indico.frib.msu.edu/event/52/contributions/701/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/701/ END:VEVENT BEGIN:VEVENT SUMMARY:Status and perspectives of the n_TOF Facility at CERN following th e upgrades and consolidation during CERN’s Long Shutdown 2 DTSTART:20220726T133600Z DTEND:20220726T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-702@indico.frib.msu.edu DESCRIPTION:Speakers: Steven Sorlut\, José Maria Martin Ruiz\, Raffaele E sposito\, Francesco Dragoni\, Matteo Ferrari\, Vasilis Vlachoudis\, Damien Grenier\, Oscar Fjeld\, Alberto Mengoni\, Keith Kershaw\, Fabio Pozzi\, J ean-Louis Grenard\, Dominika Senajova\, Giuseppe Lerner\, Simone Gilardoni \, Ana-Paiula Bernardes\, Oliver Aberle\, Marco Calviani (CERN)\n\nThe Eur opean Laboratory for Particle Physics (CERN) is equipped with a top-class\ , high-brightness\, neutron spallation source dedicated to high-resolution neutron time of flight experiments: the n_TOF Facility.\n\nThe Facility h as been constructed in 2000 [1] and has evolved significantly over the las t 20 years\, encompassing the creation of a new vertical experimental area on top of the spallation target [2] and the capability to handle unsealed radioactive samples in the two experimental stations. During CERN’s Lon g Shutdown 2 (2019-2021)\, a significant upgrade has been implemented to g uarantee reliable operation of n_TOF for the years to come\, maximizing th e physics reach of the infrastructure.\n\nThe contributions will detail th e upgrades and the status of the facility\, including the construction of a third-generation spallation target [3]\, the consolidation of the neutro n collimation systems\, the complete overhaul of the target pit shielding as well as the realization of a new irradiation station (NEAR) for materia ls very close to the neutron spallation target. \n\nPerspectives for opera tion and considerations for further upgrades of the facility will be provi ded as well.\n\n[1] C. Borcea et al.\, Results from the commissioning of t he n_TOF spallation neutron source at CERN\, Nucl. Instr. Meth. A 513 (3)\ , 524-537 (2003) \n\n[2] M. Sabaté-Gilarte et al.\, High-accuracy determi nation of the neutron flux in the new experimental area n_TOF-EAR2 at CERN \, Eur. Phys. J A 53\, 210 (2017)\n\n[3] R. Esposito et al.\, Design of th e third-generation lead-based neutron spallation target for the neutron ti me-of-flight facility at CERN\, Phys. Rev. Accel. Beams 24\, 093001 (2021) \n\nhttps://indico.frib.msu.edu/event/52/contributions/702/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/702/ END:VEVENT BEGIN:VEVENT SUMMARY:Experimental evaluation of energy resolutions for pulsed neutron b eam in the KURNS-LINAC DTSTART:20220726T190300Z DTEND:20220726T191500Z DTSTAMP:20260420T153400Z UID:indico-contribution-735@indico.frib.msu.edu DESCRIPTION:Speakers: Yasunori Matsuo (Kindai University)\n\nEnergy resolu tions of pulsed neutrons are one of the important parameters for nuclear d ata measurement by TOF method. The energy resolutions are a facility-speci fic parameters\, and has been evaluated experimentally and numerically at various TOF facilities using pulsed neutrons.\nKURNS-LINAC is an L-band el ectron linear accelerator with maximum acceleration voltage of 46 MeV esta blished at Institute for Integrated Radiation and Nuclear Science\, Kyoto University. By using a target according to a research purpose\, we can use various types of particle beam sources\, i.e. neutron\, electron\, and ph oton. In addition\, the pulsed width of the electron beam can be easily ch anged. For a pulsed neutron source\, a water-cooled tantalum (Ta) target a s a photo-neutron target and various moderator are used. A typical neutron flight tube used for nuclear data measurement at KURRI-LINAC is installed in the direction of 135 degree to the LINAC electron beam line\, and the neutron flight path from the Ta target to a sample is about 12.7 m.\n In t his study\, experimentally evaluations for the energy resolution of pulsed neutron flux in the neutron path were carried out. The capture gamma-rays from a Ta-181 sample were measured by a BGO detector with a TOF method an d the TOF spectra for well-known resonances were obtained. The energy reso lution was evaluated by comparing the full width at half maximum of the Ta -181 resonances in the JENDL-4.0. In order to obtain relationships between the energy resolution and the pulsed neutron beam width\, the measurement s were carried out with the pulsed neutron beam width of 100 nsec\, 1 μse c and 4 μsec\, respectively. As the experimental results\, the energy res olution of neutron energy range from 4 eV to 100 eV corresponding to each pulse width were evaluated. For example\, the energy resolution at 4.28 eV (Ta-181 first resonance peak) was about 1.0 % for a pulse width of 4 μse c.\n\nhttps://indico.frib.msu.edu/event/52/contributions/735/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/735/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Science: Meeting the Challenges of the Future DTSTART:20220725T131500Z DTEND:20220725T134500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1242@indico.frib.msu.edu DESCRIPTION:Speakers: William D. Magwood (NEA Director General)\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/1242/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1242/ END:VEVENT BEGIN:VEVENT SUMMARY:Combining neutron/gamma radiography and tomography at CNA DTSTART:20220726T170600Z DTEND:20220726T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-715@indico.frib.msu.edu DESCRIPTION:Speakers: Maria de los Ángeles Millán Callado (Centro Nacion al de Aceleradores (CNA\, CSIC-US-Junta de Andalucía) - Dpto. Física At ómica\, Molecular y Nuclear (FAMN)\, Universidad de Sevilla (US))\n\nCent ro Nacional de Aceleradores (CNA) is a joint interdisciplinary research ce nter from Universidad de Sevilla\, Junta de Andalucía and CSIC (Spanish N ational Research Council) open to external users. CNA has six different fa cilities\, namely: a 3 MV Pelletron tandem accelerator\, an 18/9 MeV Cyclo tron accelerator\, a 1 MV mass spectrometer accelerator\, a PET/CT scanner \, a 200 kV radiocarbon dating system\, and a Co-60 irradiator. In additio n\, a Mo x-ray tube is available for cultural heritage studies\, among oth er uses. \n\nRadiography is a non-destructive imaging technique that uses the attenuation of penetrating radiation passing through a sample to study its internal structure. Although the term usually refers to x-rays\, diff erent kinds of radiation can be used as a probe. Each type of radiation fe atures different mechanisms of interaction with matter\, revealing differe nt structures and properties of an object. Therefore\, the combined inform ation from different types of radiographies of a given object provides a m ore complete knowledge about said sample.\n\nThis work presents the commis sioning of a mobile imaging setup at CNA with the capability of combining four different radiography types taking advantage of the different facilit ies available at the center: fast neutron radiography\, thermal neutron ra diography\, gammagraphy\, and conventional x-ray imaging. Among these\, fa st neutron imaging is the only technique that is not yet commercially avai lable despite having great interest in industry due to the high penetratio n range and the possibility of contrast under strongly shielded objects.\n \nAt CNA\, acceptable quality images in exposures of several minutes can b e obtained\, distinguishing between different materials and different thic knesses of the same material and resolving millimetric structures. Further more\, since 2021\, neutron and gamma tomography are also available\, comp lementing the flexibility of this setup with volumetric information of a s ample. This new feature consolidates the imaging techniques as a new tool at CNA\, with widespread use in industry and research\, particularly inter esting for cultural heritage applications.\n\nhttps://indico.frib.msu.edu/ event/52/contributions/715/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/715/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear data at GELINA: from experiment to production and validati on of evaluated data DTSTART:20220727T153300Z DTEND:20220727T154500Z DTSTAMP:20260420T153400Z UID:indico-contribution-745@indico.frib.msu.edu DESCRIPTION:Speakers: Andreea Oprea\, Carlos Paradela Dobarro (European Co mmission - Joint Research Centre)\, Peter Schillebeeckx (EC-JRC Geel)\, Ar jan Plompen (EC-JRC Geel)\, Jan Heyse (European Commission\, Joint Researc h Centre (JRC))\, Stefan Kopecky (European Commission - Joint Research Cen tre)\n\nGELINA is a neutron time-of-flight facility installed at the Europ ean Commission Joint Research Centre (JRC) in Geel (Belgium)\, dedicated t o neutron-induced cross section measurements for more than 50 years. GELIN A’s experimental program focusses on nuclear applications and is strongl y connected to the JEFF project. Measurements of the most relevant partial cross sections (capture\, elastic\, inelastic and fission) as well as tot al cross sections can be performed\, with the experimental setups undergoi ng regular modernization. The resulting data\, mainly in the resolved and unresolved resonance region\, feed into evaluations that are performed ei ther in-house or by collaboration partners.\nDuring the last years efforts focused on developing experimental and analytical (procedures and softwar e) tools to produce and validate evaluated nuclear data. A transmission st ation has been equipped with an industrial furnace for measurements with s amples at high temperature\, allowing the study of Doppler broadening effe cts. Other experimental activities include integral experiments in high-in tensity radiation fields inside the GELINA target hall and measurements at a dedicated transmission station to validate resonance parameter files. I mproved data analysis procedures allow now for accurate transmission measu rement of “fuel pins” used in MINERVE integral experiments and softwa re tools allow for a simple comparison of (thick sample) transmission data with evaluated data libraries. \nTo broaden the experimental programme an electron beam line to produce bremsstrahlung for investigating gamma-indu ced reactions is being commissioned.\nMost of the work has been performed together with collaboration partners\, many of which were participating in the EUFRAT open-access program\, a program open to researchers from EU Me mber States\, candidate and associated countries.\n\nhttps://indico.frib.m su.edu/event/52/contributions/745/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/745/ END:VEVENT BEGIN:VEVENT SUMMARY:UGGLA - a facility designed to measure specific radioactivity of b iological samples DTSTART:20220727T181200Z DTEND:20220727T182400Z DTSTAMP:20260420T153400Z UID:indico-contribution-750@indico.frib.msu.edu DESCRIPTION:Speakers: Erik Andersson Sundén (Uppsala University)\n\nThe C hernobyl accident in 1986 deposited radioisotopes like $^{137}$Cs over lar ge parts of Europe. Having a half-life of 30.2 years\, $^{137}$Cs is still present in nature\, including in mushrooms as well as wild boars\, and ha s become an integrated part in many natural food chains. \n\nIn this artic le\, we describe our facility UGGLA (Uppsala Generic Gamma Lab). UGGLA is designed to measure specific radioactivity of biological samples using a H igh Purity Germanium detector in a lead cavity. In the paper\, we discuss our experiences on how to get help from the general public to collect biol ogical and geological samples from nature. We will also cover the challeng es of specific radioactivity measurements in the cases of variation in den sity\, chemical content and geometrical configuration in the context of of the ambition to measure a large amount of samples to correctly map large geographical areas.\n\nWild boars are notorious for their digging foraging style and love of mushrooms. They have recently immigrated to areas in Sw eden with high cesium deposit. This has again actualized the question abou t how much $^{137}$Cs is present in food accessible for humans through for aging of mushroom and berries\, or as game.\n\nUGGLA is involved in the me asurement of the specific activity of the meat of wild boars in the projec t called ObeliCs. In the project\, we will measure the seasonal variation of the specific activity of the meat. In the paper\, we will use measureme nts from ObeliCs to illustrate the challenges of such projects.\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/750/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/750/ END:VEVENT BEGIN:VEVENT SUMMARY:Overview of Recent Advances in Experimental Capabilities DTSTART:20220725T143000Z DTEND:20220725T150000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1243@indico.frib.msu.edu DESCRIPTION:Speakers: Alexandra Gade (FRIB)\n\nhttps://indico.frib.msu.edu /event/52/contributions/1243/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1243/ END:VEVENT BEGIN:VEVENT SUMMARY:JRC MONNET - the intense fast-neutron source for fundamental and a pplication-driven research DTSTART:20220727T140000Z DTEND:20220727T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-742@indico.frib.msu.edu DESCRIPTION:Speakers: Cristiano Lino Fontana (European Commission\, Joint Research Centre (JRC))\n\nMONNET is a fast neutron source based on a tande m-accelerator\, located at the Geel (BE) site of the Joint Research Centre (JRC). It became operational in 2020. MONNET may deliver intense neutron beams in the energy range from $30~\\text{keV}$ to $10.1~\\text{MeV}$ and from $12.8~\\text{MeV}$ to $24~\\text{MeV}$. Neutrons are produced with pr otons or deuterons on lithium\, tritium or deuterium targets. MONNET deliv ers a neutron flux of up to $10^9~\\text{n/sr/s}$\, depending on the produ cing reaction and the neutron energy. Neutron beams are essentially mono-e nergetic ($\\Delta E_n/E_n < 6%$ with $E_n > 300~\\text{keV}$). The accele rator may also be used with proton\, deuteron and alpha beams. The product ion of photon beams is possible and presently under investigation.\n\nThe MONNET neutron source is a user facility within the JRC EUFRAT Open Access program. Proposal evaluation by an independent panel is taking place twic e per year.\n\nThe research program ranges from cross section measurements \, _e.g._ $(n\, f)$\, $(n\, p)$\, $(n\, \\gamma)$ as well as $(p\, p')$\, $(p\, n)$ and $(p\, \\gamma)$\, nuclear fission studies\, material studies (_e.g._ radiation-induced damage)\, to the investigation of advanced meth ods in nuclear technologies\, safety and security. The activities may have exploratory character for the development of new scientific concepts or t esting of new equipment.\n\nWe will give a detailed overview of the MONNET infrastructure\, the possibilities offered to scientists and will report about first experiment campaigns.\n\nhttps://indico.frib.msu.edu/event/52/ contributions/742/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/742/ END:VEVENT BEGIN:VEVENT SUMMARY:First results of the Neutrons For Science Facility DTSTART:20220727T154500Z DTEND:20220727T155700Z DTSTAMP:20260420T153400Z UID:indico-contribution-746@indico.frib.msu.edu DESCRIPTION:Speakers: Xavier Ledoux (Ganil)\n\nX. Ledoux on behalf of the NFS collaboration\nThe neutrons for science (NFS)[1] is the running facili ty of SPIRAL-2 located at GANIL (France). It provides intense neutron beam s in the 1-40 MeV range\, produced by the interaction of proton or deutero n beams\, delivered by the LINEAR accelerator of SPIRAL-2\, with lithium o r beryllium converters. The intense neutrons flux available and the large time-of-flight area make NFS a perfect facility for fast neutron induced-r eaction studies. Large number of physics cases will be studied at NFS\, fr om fundamental research to industrial applications. NFS received its first beam in December 2019 and the commissioning started in the fall of 2020 w ith proton beams. After a quick reminder of the characteristics of NFS\, w e will present the results of the first measurements performed during the commissioning and show the characteristics of the facility. The first expe riments are being carried out between October and December 2021 and some r emarkable results of this campaign will be discussed.\nReference :\n[1] X. Ledoux\, et al. Eur. Phys. J. A\, 57\, 257 (2021)\n\n\n----------\n\nhttp s://indico.frib.msu.edu/event/52/contributions/746/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/746/ END:VEVENT BEGIN:VEVENT SUMMARY:Charged particle induced reactions on beryllium as a fast neutron source for irradiation experiments DTSTART:20220727T182400Z DTEND:20220727T183600Z DTSTAMP:20260420T153400Z UID:indico-contribution-751@indico.frib.msu.edu DESCRIPTION:Speakers: Milan Stefanik (Nuclear Physics Institute of The Cze ch Academy of Sciences\, p.r.i.)\n\nThe compact accelerator-driven fast ne utron sources represent cheaper and smaller alternative to research nuclea r reactors. They can be used (as a primary or supplementary tool) for many research activities realized at the nuclear reactors\, such as the isotop e production\, sub-surface exploration\, material research\, neutron activ ation analysis\, nuclear data provisioning\, boron neutron capture therapy \, neutron imaging\, etc. Just as the research nuclear reactors\, the comp act accelerator-based neutron sources are also capable to be involved in i nterdisciplinary research. Depending on used neutron source reaction\, the neutron fields provided by the accelerator-driven neutron sources represe nt the useful tools\, e.g.\, for application of neutron activation analysi s\, material research\, and nuclear data validation. For such purposes\, t he neutron sources that utilize the deuteron or proton beams with energies up to 10 to 30 MeV and thick targets are more convenient. Many compact ne utron sources in the world uses the beryllium layers (thick targets)\, and their neutron fields are based on the p+Be and d+Be source reactions. \nN uclear Physics Institute of the Czech Academy of Sciences (NPI CAS) in Rez operates the compact accelerator-driven NG-2 fast neutron source. The NG- 2 neutron source uses proton (up to 35 MeV) and deuteron (up to 20 MeV) be ams extracted from the isochronous cyclotron U-120M and beryllium target s tation for broad neutron spectrum production and lithium target station fo r quasi-monoenergetic neutron field production (the p+Li(C) reaction on th in target). These sources are primarily focused on nuclear data measuremen t and validation\, especially for the future fusion energetics (DEMO and I FMIF-DONES research programs). To extend their experimental utilizations m ostly towards some more traditional research reactor applications (such as the neutron activation analysis and material research)\, the neutron fiel ds generated by the p+Be and d+Be source reactions for various energies of charged particle beams provided by the U-120M cyclotron have been recentl y studied using the multi-foil activation technique.\nThe matter of the p+ Be and d+Be neutron sources\, operated both at the NPI CAS and worldwide\, and properties of their neutron energy spectra as well as their utilizati on for various research activities (such as nuclear data validation\, radi oanalytical application\, materials research) are described in the article .\n\nhttps://indico.frib.msu.edu/event/52/contributions/751/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/751/ END:VEVENT BEGIN:VEVENT SUMMARY:GENESIS: A $\\gamma-n$ coincident spectrometer for nuclear data in quiry DTSTART:20220726T171800Z DTEND:20220726T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-716@indico.frib.msu.edu DESCRIPTION:Speakers: Josh Brown (UC Berkeley)\n\nThe Gamma Energy Neutron Energy Spectrometer for Inelastic Scattering (GENESIS) was commissioned a t the 88-Inch Cyclotron at Lawrence Berkeley National Laboratory (LBNL). T he array consists of up to 27 EJ-309 organic scintillators capable of $n-\ \gamma$ particle discrimination. The $\\gamma$-ray detectors include two C ompton-suppressed 4-fold segmented Eurosys CLOVER HPGe detectors\, several ORTEC PopTop single-crystal HPGe detectors\, and LaBr inorganic scintilla tors. GENESIS includes a custom software analysis suite and modeling frame work. The modeling framework for the system is a Geant4-based modular simu lation\, which can be easily adapted to match changes in the experimental configuration as needed. In order to benchmark the model and provide syste m characterization\, several auxiliary measurements were conducted. These include a long-dwell-time measurement using a 10~mCi $^{252}$Cf source for validating the neutron detection array model\, coincident timing resoluti on measurements\, and coincident time calibration measurements. Initial ex periments have focused on $(n\,n'\\gamma)$ reactions\, but the use of GENE SIS for providing measurements of correlated fission observables is also b eing explored. Preliminary results from a measurement using a 42~g natural uranium target will be presented. The GENESIS array will enable a variety of nuclear physics measurements providing differential measurements of co rrelated observables for neutrons and $\\gamma$ rays.\n\nhttps://indico.fr ib.msu.edu/event/52/contributions/716/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/716/ END:VEVENT BEGIN:VEVENT SUMMARY:Simulation of the neutron-physical characteristics of the subcriti cal facility Yalina DTSTART:20220727T155700Z DTEND:20220727T160900Z DTSTAMP:20260420T153400Z UID:indico-contribution-747@indico.frib.msu.edu DESCRIPTION:Speakers: Tamara Korbut (Joint Institute for Power and Nuclear Research - Sosny)\n\nThe non-proliferation issues caused by the civilian use of highly enriched uranium (HEU) were solved by using of several inter national agreements. Accordingly\, efforts were made to reconstruct existi ng research reactors for using of low enriched uranium (LEU) and to encour age the usage of LEU in the development of new research reactors and other nuclear facilities\, such as subcritical systems driven by external sourc e (Accelerator driven system or ADS). ADS systems are considered as promis ing for energy production and transmutation of long-lived fission products and minor actinides [1]. The study of the processes occurring in\nADS sys tems with low enrichment uranium fuel is of high interest in the developme nt of projects for innovative installations. The driven by external source s subcritical assembly Yalina-Booster [2] (Scientific Institution JIPNR-So sny) makes it possible to study the neutron-physical characteristics and p arameters of breeding media with fast and thermal neutron spectra with\nsu bcriticality levels of $k_{eff} \\le $ 0.975. Neutron-physical characteris tics that can be measured in the ADS system can also be calculated by usin g modern simulation programs based on the Monte-Carlo method. In this pape r results of simulation of the neutron- physical characteristics of the su bcritical facility Yalina which consist from two subcritical assemblies Ya lina-Thermal and Yalina-Booster.\n\n 1. IAEA-TECDOC-1821\, Use of Low Enri ched Uranium Fuel in Accelerator Driven\nSubcritical System\n 2. Gohar\, Y . Smith\, D. L. et al.\, YALINA Facility A Sub-Critical Accelerator-Driven System (ADS) for Nuclear-Energy Research Facility Description and an Over view of the Research Program\, Report of Argonne National Laboratory (Unit ed States). Funding organization: USDOE Office of Nuclear Energy\, Science and Technology (United States)\n\nhttps://indico.frib.msu.edu/event/52/co ntributions/747/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/747/ END:VEVENT BEGIN:VEVENT SUMMARY:A new decay station for precision decay spectroscopy at Brookhaven DTSTART:20220727T184800Z DTEND:20220727T190000Z DTSTAMP:20260420T153400Z UID:indico-contribution-755@indico.frib.msu.edu DESCRIPTION:Speakers: Alejandro Sonzogni\, Elizabeth McCutchan\, Andrea Ma ttera (Brookhaven National Laboratory - NNDC)\, Shaofei Zhu\, Chris Morse (BNL)\n\nNuclear data is an integral part of the activities in many discip lines\,\nincluding basic research\, nuclear medicine\, power generation\, and others.\nIn order to meet the needs of practitioners in these fields\, nuclear data must\nbe made available for their use and kept up-to-date. Doing so requires\nthat said data be produced and disseminated in an effic ient manner.\n\nBrookhaven National Laboratory (BNL) has a long history of producing\nradioisotopes. The Brookhaven Linac Isotope Producer (BLIP) u ses high-energy\nproton beams to produce radioactive isotopes used primari ly in nuclear medicine\,\nwhile the Brookhaven Tandem Van de Graaff provid es heavy ion beams for multiple\napplications.\nBNL is also home to the Na tional Nuclear Data Center (NNDC)\, which serves\nas a central repository for nuclear data storage and retrieval. However\,\nBNL currently lacks a facility for conducting comprehensive and precise\nmeasurements of the dec ay radiation emitted by unstable isotopes. Such a\ncapability would allow isotopes of interest to nuclear data applications to\nbe produced\, analy zed\, and included in NNDC databases in-house\, creating a\nmechanism for the rapid generation of high-quality nuclear data.\n\nTo address this shor tcoming\, a new decay station is currently under\nconstruction at the NNDC . This detector system will be a multiparameter\nspectrometer to enable c omplete and precise characterization of the radiation\nemitted from unstab le isotopes. Pixelated silicon detectors will allow the\ndetection of $\\ alpha$ and $\\beta$ particles\, while germanium detectors will\nbe used to detect X-ray and $\\gamma$-ray emission. Data collection will be\nperfor med with a commercially available digitizer system\, which will minimize\n dead time and enable pulse-shape analysis. Particle-$\\gamma$ and\n$\\gam ma$-$\\gamma$ coincidence measurements will allow energies\, level schemes \,\nlifetimes\, and branching ratios to be precisely measured. In combina tion with\naccelerator facilities at BNL\, it will also enable reaction cr oss section\nmeasurements by assaying the products of irradiation campaign s. The addition of\na decay station to the arsenal of tools available at BNL\nwill form a complete pipeline for the creation and publication of nuc lear data.\n\nThe performance of the new system will be presented\, along with first\nmeasurements from the commissioning runs.\n\nThis Research is sponsored by the U.S. Department of Energy\, Office of Science\,\nOffice o f Nuclear Physics under contract DE-AC02-98CH10946.\n\nhttps://indico.frib .msu.edu/event/52/contributions/755/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/755/ END:VEVENT BEGIN:VEVENT SUMMARY:A next-generation neutron detector with interaction localization c apabilities and its application to beta-delayed neutron spectroscopy DTSTART:20220726T183900Z DTEND:20220726T185100Z DTSTAMP:20260420T153400Z UID:indico-contribution-732@indico.frib.msu.edu DESCRIPTION:Speakers: Noritaka Kitamura (University of Tennessee\, Knoxvil le)\n\nThe new generation of radioactive ion beam facilities will allow th e production of unstable nuclei far away from the valley of stability. In the very neutron-rich region\, the beta-decay energy window is much larger than the neutron separation energy of the daughter nucleus. Thus\, delaye d neutron emission after beta decay becomes a prevalent decay mode. To obt ain information about the nuclear structure of these nuclei\, precise spec troscopic measurements of beta-delayed neutrons are essential. The Neutron dEtector with Xn Tracking (NEXT) array has been designed to measure neutr on energies via the time-of-flight technique with improved precision [1]. A single NEXT module is composed of a highly segmented plastic scintillato r bar and position-sensitive photomultipliers. This design enables the loc alization of the neutron interaction point\, reducing the uncertainties as sociated with neutron time-of-flight measurement without sacrificing the n eutron detection efficiency.\nThe NEXT prototyping phase has already been completed\, and the construction of 40 NEXT modules is ongoing. The array will be fully implemented by fall 2022. We will present NEXT construction status along with key results from characterization measurements. Details on the readout electronics will also be covered.\n[1] J. Heideman et al.\, Nucl. Instrum. Methods Phys. Res.\, Sect. A 946\, 162528 (2019).\n\nhttps ://indico.frib.msu.edu/event/52/contributions/732/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/732/ END:VEVENT BEGIN:VEVENT SUMMARY:First estimation of the kinetic parameters of LR-0 mock-up reactor in a reference configuration DTSTART:20220727T190000Z DTEND:20220727T191200Z DTSTAMP:20260420T153400Z UID:indico-contribution-756@indico.frib.msu.edu DESCRIPTION:Speakers: Timothée Kooyman (CEA)\n\nIn the operation of nucle ar reactors\, the kinetic behaviour of the neutron population is driven by the delayed neutrons. The delayed neutrons fraction is thus one of the ke y parameters associated to nuclear safety. \nThe kinetic parameters (delay ed neutrons fraction and generation time) of the LR-0 reactor operated by Centrum výzkumu Řež were measured by CEA using a current-mode neutron n oise measurement technique. The reactor’s fission rate\, which was neede d to analyse the data\, was calibrated using metallic foils activation (in cluding gold\, iron and tantalum). The results obtained show a good agreem ent with calculations carried out using TRIPOLI-4®\, with a calculated va lue of 787 pcm (JEFF 3.1.1) for a measured value of 782 pcm.\nThe experime ntal campaign was also focused on studying the impact of the detector setu p. Two fission chambers provided by CV Rez were used in several configurat ions. One detector was located in the reflector and was moved away from th e core. As expected\, a degradation of the signal obtained with the periph eral detector was observed\, which led to an increasing bias in the result s. Standard-point kinetic model were found insufficient to analyse the dat a obtained in configurations with a peripheral detector far from the core. \nWith the objective of completing the IRPhE benchmark of LR-0 with a bes t estimate value of the delayed neutron fraction in the reference configur ation (LR(0)-VVER-RESR-003_CRIT-SPEC)\, a detailed uncertainty analysis wa s carried out. When integrating dosimetry uncertainty\, calculated factors and experimental dispersion\, the overall uncertainty is less than 3% (on e standard deviation).\n\nhttps://indico.frib.msu.edu/event/52/contributio ns/756/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/756/ END:VEVENT BEGIN:VEVENT SUMMARY:The n_TOF NEAR Station: Physics case and commissioning DTSTART:20220726T141200Z DTEND:20220726T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-708@indico.frib.msu.edu DESCRIPTION:Speakers: Elisso Stamati\, Joao Azevedo\, Mario Mastromarco\, Emilio Mendoza\, Zinovia Eleme\, Collaboration n_TOF\, Sotirios Chasapoglo u\, Maria Peoviti\, Goula Styliani\, Carlos Guerrero\, Pablo Perez-Maroto\ , Isabel Lopez-Casas\, Vasalis Vlachoudis\, Pablo Torres-Sanchez\, Alberto Mengoni\, Roza Vlastou\, Maria Diakaki\, Javier Praena\, Nicola Colonna\, Michael Kokkoris\, Altieri Saverio\, Veatriki Michalopoulou\, Nikolaos Pa tronis (Department of Physics\, University of Ioannina\, 45110 Ioannina\, Greece)\n\nA new experimental area\, the NEAR Station\, has recently been setup at the n_TOF facility at CERN. It is located at ~3 m distance from t he spallation target\, just outside the target-moderator shielding wall [1 ]. The main purpose of the new experimental area is to exploit the extreme ly high neutron flux in the vicinity of the spallation target to perform i rradiation and activation measurements on short-lived radioactive isotopes or on small mass samples\, of interest for Nuclear Astrophysics. The use of a suitable moderator and of filters of different thickness\, is current ly investigated\, as is expected to produce Maxwellian-like neutron spectr a of different temperatures\, enabling challenging measurements of Maxwell ian Averaged Cross Sections for nuclear astrophysics and other application purposes. Additionally\, the extremely high intensity of the neutron beam is very convenient for measurements related to technological applications \, such as material and fusion-technology related studies [2].\nFollowing the completion of the NEAR Station [1]\, an extensive campaign for its com missioning has been undertaken\, aiming at determining the spectral featur es of the neutron beam. The measurements rely on the use of the multi-foil activation method\, as well as of a thermalization detector based on the activation of gold foils at different depths inside a moderator along the neutron beam direction (see contribution to this conference [3]). \nIn th is presentation\, the main characteristics of the newly built NEAR Station will be presented\, together with Monte Carlo simulations of the moderato r/filter assembly and of the foreseen physics program. Finally\, the first results of the commissioning campaign will be reported.\n\nReferences\n[1 ] A.-P. Bernardes\, et al.\, Design\, construction\, operation and first e xperimental results of the NEAR station at the n_TOF Facility\, submitted to ND2022\n[2] Mengoni\, A. et al. (The n_TOF Collaboration)\, The new n_T OF NEAR station\, Reports \nNo. CERN-INTC-2020-073 and No. INTC-I-222\, CE RN\, Geneva\, 2020\, \nhttps://cds.cern.ch/record/2737308 \n[3] P. Perez-M aroto et al.\, ANTILoPE: A NeuTron multi-foIL sPEctrometer for measuring n eutron energy distributions up hundreds of MeV\, submitted to ND2022\n\nht tps://indico.frib.msu.edu/event/52/contributions/708/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/708/ END:VEVENT BEGIN:VEVENT SUMMARY:Time projection chamber for nuclear data measurement at CSNS Back- n white neutron source DTSTART:20220727T183600Z DTEND:20220727T184800Z DTSTAMP:20260420T153400Z UID:indico-contribution-753@indico.frib.msu.edu DESCRIPTION:Speakers: Han Yi (Institute of High Energy Physics\, CAS)\n\nT he group of CSNS White Neutron Source (Back-n) has developed a prototype T PC for the physical experiments. The main design goal of white neutron sou rce TPC is to measure the neutron induced light charged particle emitting nuclear reactions\, and at the same time\, it takes into account many appl ications such as fission cross section measurement\, beam spot measurement and neutron radiography. At present\, our research team has carried out s everal beam tests and experiments with this TPC\, and obtained preliminary experimental results\, which verified the feasibility of TPC for neutron nuclear reaction measurement.\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/753/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/753/ END:VEVENT BEGIN:VEVENT SUMMARY:Contributions to Integral Nuclear Data in ICSBEP and IRPhEP since ND 2019 DTSTART:20220727T180000Z DTEND:20220727T182400Z DTSTAMP:20260420T153400Z UID:indico-contribution-999@indico.frib.msu.edu DESCRIPTION:Speakers: Lori Scott (Idaho National Laboratory (subcontractor ))\, Ian Hill (OECD NEA)\, Julie-Fiona Martin (OECD NEA)\, Tatiana Ivanova (OECD NEA)\, John Bess (JFoster & Associates\, LLC)\n\nThe status of the two neutronics international benchmark projects sanctioned by the Organisa tion for Economic Co-operation and Development Nuclear Energy Agency (OECD NEA)\, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Proje ct (IRPhEP)\, was last directly discussed with the international nuclear d ata community at the 14th International Conference on Nuclear Data for Sci ence and Technology (ND2019) in Beijing\, China. The primary purpose of t he ICSBEP and IRPhEP is to provide extensively peer-reviewed integral benc hmark experiment data to the international nuclear community to support va lidation and testing of nuclear data and models. Users of the handbooks a re found throughout the nuclear data\, reactor physics\, criticality safet y\, and mathematics/computation communities. The contents of these handbo oks support validation of analytical methodologies utilized in reactor phy sics\, fuel cycle characterization\, nuclear facility safety analysis and design\, advanced modelling and simulation\, training\, education\, and nu clear data.\n\\\\\\\\\nSince ND2019\, the quantity of available integral b enchmark data to support nuclear data testing has increased. The 2021 edi tion of the \\textit{International Handbook of Evaluated Criticality Safet y Benchmark Experiments} (ICSBEP Handbook) now contains 587 evaluations wi th benchmark specifications for 5\,098 critical\, near-critical\, or subcr itical configurations\, 45 criticality alarm placement/shielding configura tion with multiple dose points apiece (contained within 7 evaluations)\, a nd 237 configurations that have been categorized as fundamental physics me asurements that are relevant to criticality safety applications (contained within 10 evaluations). An additional 838 configurations deemed unaccept able to support criticality safety are also preserved within the handbook. \n\\\\\\\\\nThe 2021 edition of the \\textit{International Handbook of Eva luated Reactor Physics Benchmark Experiments} (IRPhEP Handbook) contains d ata from 169 different experimental series that were performed at 57 uniqu e nuclear facilities. Currently 165 of the 169 evaluations are published as approved benchmarks with the remaining four evaluations published as dr aft benchmarks only. Measurements found in the IRPhEP Handbook include cr iticality\, buckling and extrapolation length\, spectral characteristics\, reactivity effects\, reactivity coefficients\, kinetics\, reaction-rate d istributions\, power distributions\, isotopic compositions\, and/or other miscellaneous types of measurements for various types of reactor systems.\ n\\\\\\\\\nA total of 28 countries have contributed to the past and contin ued success of these projects as benchmark evaluations\, technical reviews \, and experimental data using their own time and resources: 26 to the ICS BEP and 25 to the IRPhEP. Contributing countries include the following: A rgentina\, Austria\, Belarus\, Belgium\, Brazil\, Canada\, People's Republ ic of China\, Czech Republic\, Denmark\, France\, Germany\, Hungary\, Indi a\, Israel\, Italy\, Japan\, Kazakhstan\, Poland\, Republic of Korea\, Rus sian Federation\, Serbia\, Slovenia\, South Africa\, Spain\, Sweden\, Swit zerland\, United Kingdom\, and the United States of America.\n\\\\\\\\\nKe y contributions to the handbooks over the past three years can only be hig hlighted within this paper. Full technical details and benchmark experime nt descriptions can be located within the benchmark reports distributed wi thin recent editions of the handbooks. Evaluations are periodically updat ed as errors are identified\, additional evaluated data are incorporated\, or clarifications are provided based upon handbook-user feedback. Users of the handbooks are strongly encouraged to utilize the Database for the I nternational Handbook of Evaluated Criticality Safety Benchmark Experiment s (DICE) and the IRPhEP Database and Analysis Tool (IDAT) to verify the la test benchmark evaluation versions contained within their respective handb ooks.\n\\\\\\\\\n\nhttps://indico.frib.msu.edu/event/52/contributions/999/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/999/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Data Production System of RAON DTSTART:20220727T130000Z DTEND:20220727T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-737@indico.frib.msu.edu DESCRIPTION:Speakers: Young-Ouk Lee (KAERI)\, Sung-Chui Yang (KAERI)\, Kyo ungho Tshoo (RISP\, Institute of Basic Science)\, Seok Ho Moon (UNIST)\, Y ukinobu Watanabe\, Dalho Moon (Sungkyumkwan University)\, Tae-Yung Song (K AERI)\, Katsuhisa Nishio (JAEA)\, Nobuhiro Shigyo (Kyushu University)\, Se ung-Woo Hong (IBS/SKKU)\, Satoshia Chiba\, Cheolmin Ham (RISP\, Institute of Basic Science)\, Moses Chung (UNIST)\, Junyeong Jeong (UNIST)\, Donghyu n Kwak (UNIST)\, Ghoong-Sup Gil (KAERI)\, Sangjin Lee (RISP\, Institute of Basic Science)\, Do Heon Kim (KAERI)\, Yoolim CHEON (UNIST)\n\nThe Nuclea r Data Production System (NDPS) is an experimental system for measuring nu clear data by use of neutron Time-of-Flight detection systems built at Dae jeon\, Korea. The RAON (Rare isotope Accelerator complex for ON-line exper iment) provides deuterons and protons up to 98 MeV and 83 MeV\, respective ly. They are accelerated by a superconducting driver LINAC and are deliver ed to the neutron production target to produce neutrons. Pulsed beams with intensities up to ~12 μA can be used to do experiments for measuring neu tron-induced cross sections. The range of the beam repetition rate is to b e 1 kHz ~ 500 kHz while the RF frequency of the LINAC is 81.25 MHz. The pu lse width of the beams is an important factor in determining the accuracy of nuclear data and is aimed to be as small as 1~2 ns. Both white neutrons and monoenergetic neutrons will be produced. White neutrons will be gener ated by thick C (graphite) targets\, while thin Li targets will produce mo noenergetic neutrons. Beam lines for charged particles and neutrons togeth er with a neutron collimator and beam dumps are constructed. Nuclear data such as (n\, fission)\, (n\, xn)\, and (n\,γ) cross sections can be measu red with various detectors. Neutron detectors based on MICROMEGAS and PPAC with converters are installed for monitoring neutron flux. The current st atus of the construction of the NDPS will be presented.\n\nhttps://indico. frib.msu.edu/event/52/contributions/737/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/737/ END:VEVENT BEGIN:VEVENT SUMMARY:Overview of Nuclear Data Production System at RAON DTSTART:20220727T132400Z DTEND:20220727T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-738@indico.frib.msu.edu DESCRIPTION:Speakers: Cheolmin Ham (Rare Isotope Science Project\, Institu te for Basic Science\, Republic of Korea)\n\nNeutron beams have been utili zed not only in the basic science\, but also in the various industry secto rs such as nuclear power\, aerospace\, defense industry\, and semiconducto r industry\, over the past decades. Although the needs for the nuclear dat a using the neutron beam extensively have been increased worldwidely\, how ever\, it is still insufficient\, in particular for the high energy neutro n-induced cross sections due to the lack of the high energy neutron beam f acility. A neutron beam facility\, so-called Nuclear Data Production Syste m (NDPS)\, is being constructed\, so as to measure the nuclear data by emp loying Time-of-Flight (ToF) technique at Rare isotope Accelerator complex for ON-line experiment (RAON) in Korea. NDPS is planning to complete the i nstallation in 2023. which will provide both white and mono-energetic neut rons using 49 MeV/nucleon deuteron and 83 MeV/nucleon proton beams with gr aphite and lithium targets\, respectively. Since the ToF technique is empl oyed in NDPS\, pulsed beams at least less than 200 kHz repetitions with 1- 2 nsec width of micro bunch are required in order to obtain sufficient acc uracy of the nuclear data. The current status of NDPS will be presented al ong with the brief overview of RAON.\n\nhttps://indico.frib.msu.edu/event/ 52/contributions/738/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/738/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron monitoring detector system for Nuclear Data Production Sys tem of RAON DTSTART:20220727T133600Z DTEND:20220727T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-739@indico.frib.msu.edu DESCRIPTION:Speakers: Dal-Ho Moon (Sungkyunkwan University)\n\nThe Nuclear Data Production System (NDPS) which is a neutron time-of-flight (TOF) exp erimental facility of RAON is under construction. The proton and deuteron beams are accelerated up to 83 and 98 MeV\, respectively. The proton beams bombarded with a thin Li target will produce mono-energetic neutrons\, an d continuous-energy neutron spectra will be generated by colliding deutero n beams to a thick C target. To monitor the neutron flux we developed neu tron monitoring detectors based MICROMEGAS and PPAC. In order to convert n eutrons to charged particles\, Thorium converters of 6 cm diameter are ins talled. The electrodeposition method was used with isopropyl alcohol as a solvent to dissolve thorium nitrate powder. The amount of deposited Th was measured by using alpha spectroscopy. These neutron monitoring detectors were tested with a $^{252}$Cf neutron source. The test results of these tw o monitoring detectors will be presented.\n\nhttps://indico.frib.msu.edu/e vent/52/contributions/739/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/739/ END:VEVENT BEGIN:VEVENT SUMMARY:Use of nickel sphere and copper cube with Cf-252 neutron source in the centre for test of nuclear data library ENDF/B-VII\, ENDF/B-VIII\, J EFF-3.3\, BROND-3.1 and ROSFOND DTSTART:20220727T133600Z DTEND:20220727T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-989@indico.frib.msu.edu DESCRIPTION:Speakers: Bohumil Jansky (Research Centre Rez)\n\nAbstract\nTh e leakage neutron spectra measurements have been done on benchmark spheric al assembly-nickel sphere with diameter of 50 cm and copper cube with an e dge of 48.4 cm. The Cf-252 neutron source was placed into the centre of ni ckel sphere and copper cube. The proton recoil method was used for neutro n spectra measurement using spherical hydrogen proportional detectors (HPD ) with pressure of 400 and 1000 kPa (diameter of detectors is 4 cm) and us ing scintillation stilbene detector (diam. 1x1 cm). The neutron energy ran ge of spectrometer is 0.06-1.3MeV for HPD (HPD region) and 1-10MeV for s tilbene (stilbene region). The adequate MCNP neutron spectra calculations based on data libraries ENDF/B-VII.1\, ENDF/B-VIII.0\, JEFF-3.3\, BROND-3 .1 and ROSFOND-2010 were done. The neutron energy structure used for calc ulations and measurements was 40 and 200 groups per decade (gpd) and step of 100 keV for stilbene. Structure 200 gpd represents lethargy step about of 1%.\n\nhttps://indico.frib.msu.edu/event/52/contributions/989/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/989/ END:VEVENT BEGIN:VEVENT SUMMARY:Outcomes of WPEC SG47 on »Use of Shielding Integral Benchmark Arc hive and Database for Nuclear Data Validation« DTSTART:20220727T130000Z DTEND:20220727T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-776@indico.frib.msu.edu DESCRIPTION:Speakers: Ivan Alexander Kodeli (CCFE/UKAEA Abingdon)\n\nWorki ng Party on International Nuclear Data Evaluation Co-operation Subgroup 47 (WPEC SG47) entitled "Use of Shielding Integral Benchmark Archive and Dat abase for Nuclear Data Validation" was started in June 2019 with the objec tives to promote a more systematic and wider use of shielding benchmark ex periments in nuclear data and transport code validation and development\, to provide feedback on the Shielding Integral Benchmark Archive and Databa se (SINBAD)\, and to promote its further development in coordination with Expert Group on Physics of Reactor Systems (EGPRS). Altogether 6 meetings\ , the large majority (5) held remotely by videoconference\, were organised during the past 3 years to discuss the experience on the use of SINBAD\, new benchmark experiment evaluations and improvements to be contributed to the database which is severely malnourished and lacking maintenance since the past ~10 years or more. Several proposals for new or updated benchmar k evaluation were presented and discussed\, such as FNG copper\, LLNL puls ed spheres\, CIAE iron sphere\, KFK 1977 gamma measurements\, Rez Fe spher e\, ASPIS\, Oxygen ORNL broomstick\, TIARA and other benchmark experiments . Complementing the database with new features was also discussed. For exa mple\, providing nuclear data sensitivity profiles more systematically wou ld facilitate and better guide the use of data. Also\, the information on the geometry\, (radiation source) and materials in CAD format is expected to allow an easier and less error prone computational model preparation fo r different transport codes. Inputs for various transport codes and other benchmark data from participants have been shared via NEA GitLab which cou ld hopefully in future evolve and form a bases for critically checked and validated set for computer code analysis tools. \nExamples of the use and some views on future development of the SINBAD benchmark database will be presented in the paper.\n\nhttps://indico.frib.msu.edu/event/52/contributi ons/776/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/776/ END:VEVENT BEGIN:VEVENT SUMMARY:Analyses of JAEA/FNS iron in-situ experiment with latest nuclear d ata libraries DTSTART:20220727T183600Z DTEND:20220727T184800Z DTSTAMP:20260420T153400Z UID:indico-contribution-1001@indico.frib.msu.edu DESCRIPTION:Speakers: Chikara Konno (Japan Atomic Energy Agency)\n\nFor th e JENDL development we analyzed the iron in-situ experiment at the DT neut ron source facility FNS in JAEA with the two-dimensional Sn code DORT and the latest nuclear data libraries: JENDL-4.0\, ENDF/B-VIII.0 and JEFF-3.3. As a result\, we found that the result with ENDF/B-VIII.0 reproduced the measured data worse than those with JENDL-4.0 and JEFF-3.3. Here we invest igate this issue.\n\nThe problems of the result with ENDF/B-VIII.0 were as follows.\n1. The neutron flux below a few keV is overestimated more in th e front region of the iron test assembly.\n2. The reaction rate of In115(n \,n’)In115m sensitive to neutrons above 0.3 MeV is underestimated more w ith the depth of the iron assembly.\n3. The neutron flux above 10 MeV is u nderestimated more with the depth of the iron assembly.\n\nIn order to cla rify reasons of the first and second problems\, we compared each reaction data of iron in ENDF/B-VIII.0 with that in ENDF/B-VII.1 because the proble ms did not appear in the analysis with ENDF/B-VII.1 and it was useful to d emonstrate what was changed from ENDF/B-VII.1 to ENDF/B-VIII.0. The compar ison and additional study specified that the inelastic scattering data of Fe-56 in ENDF/B-VIII.0 mainly caused the problems. \n\nFor the third probl em\, we investigated ENDF/B-VIII.0 and JENDL-4.0 in the same manner as the above one because JENDL-4.0 did not cause the problem while ENDF/B-VII.1 did. The study indicated that the angular distribution data of the elastic scattering and the cross section of the (n\,2n) reaction of Fe-56 in ENDF /B-VIII.0 caused the problems. \n\nIt is noted that the iron data in ENDF/ B-VIII.0 are not always better than those in ENDF/B-VII.1\, though ENDF/B- VIII.0 is the major revised version of ENDF/B-VII.1. We recommend revising the Fe-56 data of ENDF/B-VIII.0 in the next version of ENDF/B based on th is study.\n\nhttps://indico.frib.msu.edu/event/52/contributions/1001/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/1001/ END:VEVENT BEGIN:VEVENT SUMMARY:Reactivity Worth Measurement of Calcium Hydride Sample in UTR-KINK I Reactor DTSTART:20220727T182400Z DTEND:20220727T183600Z DTSTAMP:20260420T153400Z UID:indico-contribution-1000@indico.frib.msu.edu DESCRIPTION:Speakers: Takashi Kanda (Kindai University)\n\nA small modular reactor (SMR) employing calcium hydride (CaH2) as a moderator have attrac ted attention to the passive safety and economic efficiency. Some integral experiments should be carried out to validate nuclear data of CaH2\, howe ver\, no integral experiment by reactor for the validation have been repor ted. As the first integral experiment by reactor\, a series of reactivity worth measurements of CaH2 samples was conducted in a university training and research reactor (UTR-KINKI) of Kindai University.\nThe UTR-KINKI reac tor is a light-water-moderated and graphite-reflected two-core (coupled-co re) reactor. A graphite region between the two cores has been employed as a standard irradiation field which has a standard neutron spectrum consist ing of 1/v and Maxwell distributions. The CaH2 sample was placed in a cavi ty located at the center of the irradiation field.\nThe sample reactivity worth was determined from a difference between two excess reactivities of the respective reactors with and without the sample. The respective excess reactivities were measured using positive period method. The reactivity w orth measurements were repeated for 21.20 g\, 41.00 g\, and 72.78 g of CaH 2 sample.\nFrom the present experiment\, the following reactivity worth co uld be determined.\n 1) For 21.29 g of CaH2\, -0.00417±0.00028 [ %∆k⁄k]\n 2) For 41.00 g of CaH2\, -0.00861±0.00028 [%∆k⁄ k]\n 3) For 78.72 g of CaH2\, -0.01587±0.00041 [%∆k⁄k].\nFur thermore\, the sample reactivity worth was calculated using the continuous energy Monte Carlo codes MVP3.0 with the nuclear library JEFF-3.1\, where each cross section of H and Ca constituting a molecule of CaH2 was taken into the thermal neutron scattering law (S(α\,β)). The ratios of calcula ted to experimental values (C/E) were 1.19±0.72\, 0.806±0.347 and 0.874 ±0.189 for 21.29 g\, 41.00 g and 78.72 g of the samples\, respectively.\n \nhttps://indico.frib.msu.edu/event/52/contributions/1000/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/1000/ END:VEVENT BEGIN:VEVENT SUMMARY:Recent Advances in Nuclear Theory and Astrophysics DTSTART:20220725T150000Z DTEND:20220725T153000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1244@indico.frib.msu.edu DESCRIPTION:Speakers: Karl-Heinz Langanke (GSI)\n\nhttps://indico.frib.msu .edu/event/52/contributions/1244/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1244/ END:VEVENT BEGIN:VEVENT SUMMARY:New setup for measurement of prompt gammas from neutron interactio ns. DTSTART:20220727T152100Z DTEND:20220727T153300Z DTSTAMP:20260420T153400Z UID:indico-contribution-995@indico.frib.msu.edu DESCRIPTION:Speakers: Zdenek Matej (Masaryk University\, Botanická 15\, B rno 612 00\, Czech Republic)\, Evzen Losa (Centrum Vyzkumu Rez ltd.)\, Fil ip Mravec (Masaryk University\, Botanická 15\, Brno 612 00\, Czech Republ ic)\, Evzen Novak (Centrum Vyzkumu Rez ltd.)\, Jan Simon (Centrum Vyzkumu Rez ltd.)\, Frantisek Cvachovec (University of Defence\, Kounicova 65\, Br no 612 00\, Czech Republic)\, Michal Kostal (Centrum Vyzkumu Rez ltd.)\, T omas Czakoj (Centrum Vyzkumu Rez ltd.)\n\nA new setup is being prepared in Centrum Výzkumu Řež for the measurement of prompt capture and inelasti c gammas coming from neutron interactions. These gammas are important for safety during reactor operations (worker’s protection or radiation damag e) or have applications in many areas like element identification in soil and space.\nThe setup consists of an aluminum sphere with a 50 cm diameter filled with liquid target material – usually different materials dissol ved in demineralized water. Prompt gamma radiation is excited by a well-de fined 252Cf spontaneous fission source or AmBe source. 252Cf source\, with lower average neutron energy\, is more suitable for prompt capture gamma (due to the high cross-section in thermal energies)\, and the AmBe source is more suitable for inelastic scattering. The gamma spectrum is measured by a well-defined HPGe detector and scintillation detector. HPGe detector is shielded by borated polyethylene\, cadmium\, and enriched 6Li shielding plate to prevent radiation damage from neutrons. A lead shield can be pre sent to suppress prompt capture gammas from shielding and to suppress low gamma background. Both neutron and gamma transport are simulated using MCN P6.2 code. The HPGe efficiency curve is determined using MCNP6.2 and exper imentally determined HPGe parameters. The source term of studied prompt ga mmas is tested using various nuclear data libraries. The scintillation det ector is used for testing the HPGe shielding. It is worth noting that the first tests of validation of 16O inelastic scattering gamma using the well -defined AmBe source show discrepancy up to 90% for ENDF/B-VII.1.\n\nhttps ://indico.frib.msu.edu/event/52/contributions/995/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/995/ END:VEVENT BEGIN:VEVENT SUMMARY:New Plutonium Critical Experiments to Test Polyethylene and Lucite Thermal Scattering Laws DTSTART:20220727T144500Z DTEND:20220727T150900Z DTSTAMP:20260420T153400Z UID:indico-contribution-993@indico.frib.msu.edu DESCRIPTION:Speakers: Rene Sanchez (Los Alamos National Laboratory)\, Mark Lee (C.S. Engineering)\, Catherine Percher (Lawrence Livermore National L aboratory)\n\nThe goal of the U.S. Nuclear Criticality Safety Program’s (NCSP) Thermal/Epithermal eXperiments (TEX) is to design and conduct new c ritical experiments to address high priority nuclear data needs from the n uclear criticality safety and nuclear data communities. The first set of five TEX experiments\, using layers of plutonium-aluminum Zero Power Physi cs Reactor (ZPPR) plates stacked with varying thicknesses of polyethylene (PE) moderators to tune the neutron spectrum of the assembly\, was benchma rked as PU-MET-MIXED-002 (PMM-002) in the 2020 International Criticality S afety Benchmark Evaluation Project (ICSBEP) Handbook. Two of the cases\, Cases 4 and 5 of PMM-002\, had thermal fission fractions above 50% and pro vided useful validation cases for testing PE thermal scattering laws (TSLs ) and showed that the new PE TSL provide as part of the ENDF/B-VIII.0 libr ary improved agreement between the calculated and experimental benchmark r esults as compared to ENDF/B-VII.1. Case 5 is one of the most sensitive b enchmarks to polyethylene thermal scattering\, due to the general lack of appropriate integral experiments in ICSBEP. Based on these results\, two additional TEX-Pu experiments were executed in 2021 that incorporate thick er PE moderators to provide greater sensitivity to the PE TSLs. Two simil ar experiments were also executed that incorporated thick polymethyl metha crylate (C5O2H8\, commonly called Lucite or Plexiglass) moderators.\n\nIni tial experimental results indicate that the PE cases were over predicted b y approximately 0.5% in keff when compared to the predicted critical confi gurations calculated with MCNP6 and ENDF/B-VIII.0. The temperature of the stack was seen to have a large impact on reactivity of the critical confi guration\, as a 1-2 °C change produced reactivity differences of 25 pcm ( 0.00025) in keff. The two Lucite cases also appeared to be overpredicted based on the design calculations\, and to a much higher degree than polyet hylene. The critical Lucite calculations calculate approximately 1-1.5% t oo high in keff.\n\nhttps://indico.frib.msu.edu/event/52/contributions/993 / LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/993/ END:VEVENT BEGIN:VEVENT SUMMARY:Facilitating Rapid Provenance Assessment using Intentional Nuclear Forensics Approaches DTSTART:20220725T153000Z DTEND:20220725T160000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1245@indico.frib.msu.edu DESCRIPTION:Speakers: Naomi Marks (LLNL)\n\nhttps://indico.frib.msu.edu/ev ent/52/contributions/1245/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1245/ END:VEVENT BEGIN:VEVENT SUMMARY:Validation of calculational determination of 18O(p\,n) secondary n eutron field DTSTART:20220726T153600Z DTEND:20220726T153700Z DTSTAMP:20260420T153400Z UID:indico-contribution-1112@indico.frib.msu.edu DESCRIPTION:Speakers: Marek Zmeškal (Research Centre Řež s.r.o.)\n\nThe medical cyclotrons intended to produce medical isotopes are relatively wi despread. Nowadays\, it is popular to place small and compact accelerators directly to hospitals. This approach simplifies handling with produced ra diopharmaceuticals\, but it imposes radiation safety measures during produ ction. Radiation protection issues are gaining on importance especially as production increases on current cyclotrons which leads to higher radiatio n loads than originally designed. For optimal utilization of isotope produ ction cyclotron\, the exact knowledge of leakage neutron field is essentia l due to the deep penetration ability of the high energy neutrons and acco mpanied secondary radiation production. Our paper presents measurement of neutron leakage spectra in various angles from open target assembly locate d in research laboratory of Czech academy of sciences. These spectra are c ompared with data obtained from compact medical cyclotron IBA Cyclone 18/9 accelerator in the UJV Rez cyclotron laboratory. The neutron spectra were measured by the organic scintillator coupled with fast two-parameter spec trometric system NGA-01 equipped with an active voltage divider. The spect ra measurement was accompanied by reaction rates measurement of reactions with various threshold for validation of the shape of neutron spectra. The preliminary results show significant disagreement between experiments and theoretical predictions in both cases\, open target assembly and producti on cyclotron IBA 18/9. These findings could have implications not only to the nuclear data community but also to the production accelerators’ oper ators at the licensing stage.\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/1112/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1112/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the 140Ce(n\,γ) cross section at astrophysical ene rgies at n_TOF DTSTART:20220726T171800Z DTEND:20220726T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-696@indico.frib.msu.edu DESCRIPTION:Speakers: Simone Amaducci (Laboratori Nazionali del Sud (IT))\ n\nIt is well ascertained since the late '50\, that the vast majority of t he elements above the iron peak are synthesized in stars\, via sequences o f neutron captures and β-decays. Among the nucleosynthesis mechanisms\, t he slow (s-)process represents one of the better known and is very effecti ve into modelling the stellar evolution. Thanks to the high accuracy of th e nuclear data available in the major libraries\, the s-process models can predict the final element abundances from iron to lead with high precisio n.\nAn accurate measurement of the 140Ce(n\,γ) energy dependent cross sec tion has been performed at the n_TOF facility at CERN. This measurement wa s motivated by the significant discrepancy in the cerium abundance observe d in the globular cluster M22 and the value predicted by theoretical stell ar models [1].\n\nThe experimental apparatus was based on a highly enriche d 140Ce sample and on C6D6 liquid scintillators to detect the γ produced following the neutron capture events. The experimental data up to 65 keV a llowed us to resolve 81 neutron resonances\, which provides the largest co ntribution to the MACS at the temperature of interest for the s-process. T he n_TOF data show large discrepancies compared to the cross section repor ted in the major nuclear data libraries\, as shown in Fig.1 (Resonance Sha pe Analysis of a p-wave resonance: n_TOF data presents large disceprancies compared to both ENDF/B-VIII and JENDL-4.0 libraries.).\n\nThe robustness of the n_TOF results is ensured by a good agreement with the MACS measure d by activation by Käppeler et al. [2] at kT = 30 keV. At lower temperatu res\, high discrepancy with respect to the values provided by KADoNiS has been observed. The experimental results of the 140Ce(n\,γ) cross section and the astrophysical impact of the new MACS on the s-process modelling in the Ba-Ce-Nd region will be presented.\n\n[1] O. Straniero\, S. Cristallo \, L. Piersanti. Heavy elements in globular clusters: the role of asympto tic giant branch stars\, ApJ 2014\, 785\, 77.\n[2] F. Käppeler et al. Ne utron capture cross sections of the cerium isotopes for s- and p-process s tudies\, Phys. Rev. C 1996\, 53\, 1397.\n\nhttps://indico.frib.msu.edu/eve nt/52/contributions/696/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/696/ END:VEVENT BEGIN:VEVENT SUMMARY:$^{77\,78}$Se(n\,$\\gamma$) and $^{68}$Zn(n\,$\\gamma$) Cross-sect ion Measurements at n\\_TOF Relevant for the Astrophysical $s$-process DTSTART:20220726T170600Z DTEND:20220726T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-693@indico.frib.msu.edu DESCRIPTION:Speakers: Nikolay Sosnin (University of Edinburgh)\n\nAround h alf of the elements heavier than iron are produced via the slow neutron ca pture process ($s$-process)\, whereby a seed nucleus undergoes a series of neutron captures and beta decays\, with the timescales of the captures be ing slower than those of beta decays. The $s$-process is further subdivide d into several different components which occur in different types of star s. Of particular interest to this presentation is the weak $s$-process com ponent\, which occurs in massive ($>$10M$_\\odot$) stars during He-core an d C-shell burning\, and is responsible for producing elements between mass numbers 60 and 90.\n\nA recent study by Nishimura $et$ $al$. [1] showed t hat $^{77}$Se(n\,$\\gamma$)\, $^{78}$Se(n\,$\\gamma$) and $^{68}$Zn(n\,$\\ gamma$) reactions have a key impact on the prediction of the $^{77}$Se and $^{78}$Se abundances\, respectively\, considering the current large uncer tainties ($>$10% [2]) in their stellar cross sections. \n\nRecently\, $^{7 7}$Se\, $^{78}$Se and $^{68}$Zn neutron capture cross sections have been m easured at the Neutron Time-of-Flight (n\\_TOF) Facility at CERN\, chosen for its wide spectrum of neutron energies relevant to stellar environments and high neutron energy resolution. The campaign was conducted using C$_6 $D$_6$ gamma-ray detectors at the experimental area at the end of the 185- meter measurement station. The details of the experiments and subsequent a nalyses and results will be presented.\n\n[1] N. Nishimura et al.\, Uncert ainties in s-process nucleosynthesis in massive stars de-\ntermined by Mon te Carlo variations\, MNRAS 469\, Issue 2\, 2017\n[2] I. Dillman et al.\, The Karlsruhe Astrophysical Database of Nucleosynthesis in Stars\nProject – Status and Prospects\, Nuclear Data Sheets 120\, pp. 171-174\, 2014\n\ nhttps://indico.frib.msu.edu/event/52/contributions/693/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/693/ END:VEVENT BEGIN:VEVENT SUMMARY:Status of ENSDF DTSTART:20220729T130000Z DTEND:20220729T131500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1246@indico.frib.msu.edu DESCRIPTION:Speakers: Elizabeth McCutchan\n\nhttps://indico.frib.msu.edu/e vent/52/contributions/1246/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1246/ END:VEVENT BEGIN:VEVENT SUMMARY:First measurements with new high resolution neutron detector NEXT. DTSTART:20220728T172800Z DTEND:20220728T174000Z DTSTAMP:20260420T153400Z UID:indico-contribution-926@indico.frib.msu.edu DESCRIPTION:Speakers: Shree Neupane (University of Tennessee)\n\nAn effici ent neutron detection system with good energy resolution is required to co rrectly characterize decays of neutron-rich nuclei where beta-delayed neut ron emission is a dominant decay mode. Precision neutron spectroscopy inst rumentation is essential to probe nuclear structure effects in neutron-ric h nuclei in new generation radioactive beam facilities. A new high-resolut ion neutron detector\, Neutron dEtector with Xn Tracking(NEXT)\, has been constructed\, characterized\, and tested in decay and reaction experiment s. The interaction position localization capabilities enabled improvement in energy resolution and detection efficiency in the neutron time-of-fligh t measurement. First measurements were performed with beta-delayed neutron emitters using NEXT at Argonne National Laboratory(ANL) and National Supe rconducting Cyclotron Laboratory(NSCL). The results from the decay measure ment of nitrogen and oxygen isotopes near the neutron drip line will be pr esented.\n\nhttps://indico.frib.msu.edu/event/52/contributions/926/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/926/ END:VEVENT BEGIN:VEVENT SUMMARY:Charged-particle production and inelastic cross sections induced b y neutrons on $^{54}$Fe DTSTART:20220728T152600Z DTEND:20220728T153800Z DTSTAMP:20260420T153400Z UID:indico-contribution-851@indico.frib.msu.edu DESCRIPTION:Speakers: Hyeong Il Kim (Korea Atomic Energy Research Institut e)\n\nNew evaluations of neutron-induced nuclear reactions on $^{54\,56\,5 7\,58}$Fe through the CIELO [1] international collaboration were adopted b y the ENDF/B-VIII.0 [2] library\, released in 2018. These evaluations were performed by adjusting model inputs to reproduce available experimental d ata above neutron resonance regions. Since the latest release\, two new ex perimental data sets are available\; one is inelastic scattering cross sec tions performed at the Geel Electron LINear Accelerator facility (GELINA) [3] and the other is neutron-induced charged particle reaction cross secti ons\, such as (n\,p)\, (n\,np)\, (n\,d)\, and (\,$\\alpha$)\, performed us ing the LENZ (Low Energy Neutron-induce Charged-particle (Z) Chamber) inst rument at Los Alasmos Neutron Science Center (LANSCE) up to 30 MeV [4]. Wi th these additional data above 10 MeV\, we observed the discrepancy betwee n experimental cross sections and the current ENDF/B-VIII.0 evaluation on $^{54}$Fe. In this work\, we present the investigation of input parameters for the Hauser-Feshbach model\, in order to better reproduce experimental cross-section data of neutron-induced charged particle reactions and inel astic scattering on $^{54}$Fe.\n\n\n *This work benefits from the LANSCE a ccelerator facility and is supported by the U.S. Department of Energy unde r contract No. 89233218CNA000001\, by the US-ROK International Nuclear Ene rgy Research Initiative (I-NERI) program of Department of Energy\, Office of Nuclear Energy and the National Research Foundation of Korea under cont ract No. NRF-2020M2A8A1000930\, and by the US Nuclear Data Program under t he Office of Science of the U.S. Department of Energy.*\n\n[1] M. Chadwick \, et al.\, Nucl. Data Sheets 118\, 1 (2014)\n[2] D. Brown\, et al.\, Nucl . Data Sheets 148\, 1 (2018)\n[3] A. Olacel\, et al.\, Eur. Phys. Jour. A 54\, 183 (2018)\n[4] A. Georgiadou et al. *under review* (2021)\n\n\nLA-UR -21-29638\n\nhttps://indico.frib.msu.edu/event/52/contributions/851/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/851/ END:VEVENT BEGIN:VEVENT SUMMARY:Benchmark study of large-angle neutron scattering cross section of tungsten using two shadow bars at 14 MeV DTSTART:20220728T145000Z DTEND:20220728T150200Z DTSTAMP:20260420T153400Z UID:indico-contribution-842@indico.frib.msu.edu DESCRIPTION:Speakers: Indah Rosidah Maemunah (Osaka University\, Bandung I nstitute of Technology)\n\nAbstract\nIn fusion reactor design\, neutron le aks intensively from blanket material through a gap. In this streaming phe nomenon\, back scattering cross section is known to be very crucial. In th e present study\, the author’s team carried out a new experiment for ben chmarking the large-angle scattering cross section of tungsten using a DT neutron source of OKTAVIAN facility\, Osaka University\, Japan. Tungsten c ontaining material is under consideration as the radiation shield in fusio n reactor. The experimental geometry consists of a DT neutron source\, two shadow bars\, niobium foil\, and tungsten target. Four irradiations were performed at neutron energy of 14 MeV using DT neutrons to extract only th e contribution of large-angle scattering cross section. By using two shado w bars\, room return contribution was effectively suppressed. Consequently \, only back scattering neutrons were measured by using a niobium foil. In the present benchmark study\, obtained experimental data were compared wi th numerical calculations by MCNP5 using various nuclear data libraries in cluding JENDL-4.0\, JEFF-3.3\, and ENDF/B-VIII.\n\nKeywords: benchmark\, s cattering cross section\, tungsten\, back scattering\, 14 MeV\, OKTAVIAN.\ n\nhttps://indico.frib.msu.edu/event/52/contributions/842/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/842/ END:VEVENT BEGIN:VEVENT SUMMARY:Design study of benchmark experiment for large angle scattering cr oss section for non-solid target with 14 MeV neutron DTSTART:20220727T164800Z DTEND:20220727T165100Z DTSTAMP:20260420T153400Z UID:indico-contribution-1125@indico.frib.msu.edu DESCRIPTION:Speakers: Sota Araki (Osaka University)\n\nAbstract:\nAccuracy of large angle scattering cross section in nuclear data have a large infl uence on precision of neutron transport calculation in fusion reactor desi gn. In previous research\, benchmark experiments for solid target were car ried out\, however\, non-solid targets\, which are covered by a casing\, c ould not be dealt with. This is because we could not remove the casing eff ect in the previous method. In this study\, we performed design study of b enchmark experiment on large angle scattering cross section for non-solid target covered by a casing. We carried out precise neutron transport in o ur experimental system with Monte Carlo code\, MCNP5\, and discussed possi bility of measuring large angle scattering neutron flux using an appropria te activation foil. As a result\, we found that we could successfully remo ve effects of neutrons except large angle scattering neutrons from the sam ple\, i.e.\, neutrons scattered by the container as well as forward scatte ring neutrons. Now we carrying out experiments and will present the result s in the conference.\n\nKeywords: \nneutron\, large angle scattering cross section\, non-solid target 14MeV\, benchmark\, MCNP5\, activation foil me thod\n\nhttps://indico.frib.msu.edu/event/52/contributions/1125/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1125/ END:VEVENT BEGIN:VEVENT SUMMARY:Global Analysis of 4He System with RAC DTSTART:20220727T165100Z DTEND:20220727T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-1126@indico.frib.msu.edu DESCRIPTION:Speakers: Libo Zhou\n\nBoth neutron nuclear reaction data and fusion reaction data of $^4$He system play an important role in astrophysi cs and energy fields. Especially the microscopic nuclear cross section of the fusion reaction D(d\,n)$^3$He is the core data among them. However\, t here are obvious differences among current experimental data for the incid ent energy from 0.2 to 1 MeV\, and there is no experimental data available above 6 MeV. The relevant evaluation value has not been published in the main nuclear data evaluation library. "Generalized reduced R-matrix theory "\, with the corresponding program RAC\, analyzes all experimental data ab out $^4$He system simultaneously\, which includes the database of n+$^3$He \, d+D\, and p+T\, and provides a complete set of self-consistent evaluati on values for the incident energy between threshold and 30 MeV. RAC calcul ation outputs the integral cross sections and corresponding covariance mat rices. In particular\, D(d\,n)$^3$He and $^3$He(n\,d)D are inverse cross s ections of each other\, and they achieve precise matching to ensure the re liability of the final evaluation values. \nThe main feature of RAC is to adopt the $\\chi^2$ expression of "Conventional Least-Squares" or "General Least-Squares"\, instead of "Approximate Least-Squares" which being widel y used. In "Approximate Least-Squares"\, only the diagonal elements of the experimental data covariance matrix are considered\, in essence\, systema tic errors are treated as statistical errors\, and the correlation between the statistical errors and the experimental data is reduced\, this makes the data fitting lose the sensitivity to obtain the optimal normalization coefficient. In "Conventional Least-Squares" or "General Least-Squares"\, all elements of the covariance matrix of experimental data are considered\ , that is\, the correlation between statistical errors and experimental da ta is considered completely. In order to avoid the occurrence of "PPP"\, i t will force the evaluator to carefully normalize the experimental data\, so that the experimental data set can achieve a high degree of internal co nsistency\, so as to obtain the most reliable evaluation value.\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/1126/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1126/ END:VEVENT BEGIN:VEVENT SUMMARY:Status of CENDL DTSTART:20220729T131500Z DTEND:20220729T133000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1247@indico.frib.msu.edu DESCRIPTION:Speakers: Zhizang GE\n\nhttps://indico.frib.msu.edu/event/52/c ontributions/1247/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1247/ END:VEVENT BEGIN:VEVENT SUMMARY:Resonance Region Evaluation of O16 for Criticality Safety and Reac tor Applications DTSTART:20220726T165400Z DTEND:20220726T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-703@indico.frib.msu.edu DESCRIPTION:Speakers: Luiz Leal (IRSN)\n\nRecent experimental data measure ments\, namely transmission and (n\, alpha)\, have motivated revising the O16 resonance region evaluation. Issues with the normalization of the (n\, alpha) cross sections have been investigated and a very dependable measur ement has been carried out at the GELINA facility at the Joint Research Ce nter Geel from the energy threshold (2.354 MeV) to 9 MeV. Additionally\, t ransmission measurements were done at the nELBE time of flight facility at Helmholtz-Zentrum Dresden - Rossendorf (HZDR). Experimental data used in previous evaluation were also considered in the evaluation. \nThe resonanc e evaluation was performed in the energy range from 0 eV to 6 MeV using th e computer code SAMMY resulting in a set of resonance parameters (RPs) tha t describes well the experimental data used in the evaluation. The recent transmission measurements and the (n\, alpha) cross section data are well reproduced in the RPs. The RPs were converted to the evaluated nuclear dat a file (ENDF) format using the R-Matrix Limited format option LRF=7. The i ntent of the full paper is to describe the procedures used in the evaluati on of the RPs and the use of the RPs in calculations of critical benchmark experiments. Preliminary results for Pu-SOL-THERM-041 (PST-041) configura tions listed in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook indicates an improvement on the average keff val ues with calculated keff being consistent with the benchmark keff\, discre pancies on keff not exceeding the combined effect of experimental and Mont e Carlo uncertainties. This series of 40 experiments performed at Valduc r esearch center involves solutions of low 240Pu content (3 %) plutonium nit rate with a concentration in plutonium varying between 20 g/L and 190 g/L\ , in a 500 mm/200 mm annular tank. In particular\, for the PST-041 series the changes in keff values indicate that these benchmarks are sensitive to the (n\, alpha) cross section of 16O and that the new measurements were e ssential to improve the benchmark results.\n\nhttps://indico.frib.msu.edu/ event/52/contributions/703/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/703/ END:VEVENT BEGIN:VEVENT SUMMARY:Beta spectrum shape studies for the predictions of the antineutrin o spectrum from reactors DTSTART:20220725T184500Z DTEND:20220725T190900Z DTSTAMP:20260420T153400Z UID:indico-contribution-677@indico.frib.msu.edu DESCRIPTION:Speakers: Gustavo Alcalá (Instituto de Física Corpuscular\, CSIC-Univ. de Valencia\, E-46071 Valencia\, Spain.)\n\nNuclear reactors ar e copious sources of antineutrinos. This is the main reason why reactors h ave played a key role in the discovery of the neutrino and in the study of neutrino oscillation phenomena. The comparison of the neutrino flux measu rements performed at short baselines with the improved conversion procedur e by Huber [1] and Mueller [2] led to the discovery of the so-called react or antineutrino anomaly [3]\, a surplus in the number of predicted antineu trinos compared with the measured\, and more recently\, to the finding of a spectrum distortion around 5 MeV [4]. There is another alternative for t he prediction of the antineutrino spectrum\, the summation calculation met hod\, which has recently achieved a precision comparable to the conversion procedure [5]. \n\nBoth methods of calculations of the antineutrino spect rum require assumptions on the shape of the beta transitions. In [6\,7] it was argued that not taking into account the shape of first forbidden tran sitions could itself explain a large part of the discrepancy related to th e anomaly. \n\nWith this motivation in mind\, we have developed a new setu p to measure the beta shape of the beta spectrum of relevant decays for th e calculation of the antineutrino spectrum. In this presentation\, the new setup\, and some preliminary measurements performed at Jyväskylä with p ure isotopic beams will be presented. The possible impact of the measureme nts in the calculations will be discussed. \n\n[1] P. Huber\, Phys. Rev. C 84\, 024617 (2011).\n[2] Th. A. Mueller\, et al.\, Phys. Rev. C 83\, 054 615 (2011).\n[3] G. Mention\, et al.\, Phys. Rev. D 83\, 073006 (2011).\n[ 4] Double Chooz and Reno Collaborations in Proceedings of the Neutrino 201 4 Conference\, http://neutrino2014.bu.edu/\; Daya Bay Collaboration in Pro ceedings of the ICHEP 2014 Conference\, http://ichep2014.es/.\n[5] M. Esti enne\, et al.\, Phys. Rev. Lett. 123\, 022502 (2019).\n[6] A. C. Hayes\, et al.\, Phys. Rev. Lett. 112\, 202501 (2014).\n[7] L. Hayen\, et al.\, Ph ysical Review C 100\, 054323 (2019).\n\nhttps://indico.frib.msu.edu/event/ 52/contributions/677/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/677/ END:VEVENT BEGIN:VEVENT SUMMARY:Photo-Disintegration of Deuterium: from Evaluations to Application s DTSTART:20220726T163000Z DTEND:20220726T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-700@indico.frib.msu.edu DESCRIPTION:Speakers: J. Atfield\, J.C. Chow\, S. Nguyen\, L. Yaraskavitch \, Danila Roubtsov (Canadian Nuclear Laboratories (CNL))\n\nAmong the phot o-nuclear reactions of light nuclides\, the photo-disintegration of deuter ium\, $^2{\\mathrm H}(\\gamma\,{\\mathrm n})^1{\\mathrm H}$\, is arguably the most important one for nuclear systems with heavy/light water. In mul tiplying/critical systems\, this reaction is also a source of delayed neut rons due to the delayed gamma emission of certain fission products. There fore\, it is important to review the modern evaluations of photo-nuclear r eaction data of deuterium\, their processability from the ENDF format into application specific ones (e.g.\, ACE)\, and from the standpoint of Monte Carlo neutron and gamma transport applications\, the sampling of out-goin g neutron energy and direction by modern Monte Carlo codes. The necessary application of relativistic kinematics vs. non-relativistic limits in sam pling of neutrons and protons will be discussed in detail. In addition\, a comparison with the $^2{\\mathrm H}({\\mathrm n}\,2{\\mathrm n})^1{\\mat hrm H}$ reaction will be made for completeness of the physics background o f deuterium disintegration in the coupled neutron and gamma flux.\n\nIn st udying the time-dependent phenomena in critical systems\, a standard tool in nuclear engineering is the application of the point kinetic equations. Some Monte Carlo codes can be used to analyze time-dependent phenomena in neutronics without the assumption that the system of interest is a ``poin t'' in space. While feasible in theory\, coupled neutron-gamma transport with the rigorous inclusion of photo-nuclear reactions is still practicall y beyond the reach of time-dependent Monte Carlo methods. However\, simila r to the point kinetics treatment of systems with heavy water/beryllium\, extra delayed neutron groups can be added to the existing delayed group da ta of actinides (6 or 8 delayed groups)\, but the extra data blocks have t o be prepared in the ENDF format. As a result\, the treatment of time-dep endent phenomena in heavy water systems with a time-dependent Monte Carlo method (and using nuclear data libraries in ACE format) will be possible\, and time scale constrained by the delayed photo-neutrons can be reached. The problem of adding extra delayed neutron groups to the nuclear data fi les of actinides (e.g.\, $^{235}$U and $^{238}$U in ENDF/B-VIII.0 and JEFF -3.3) and post-processing/testing of the results will be discussed in deta il. In addition\, some interesting examples of modelling steady-state and time-dependent phenomena in the ZED-2 (heavy water) reactor at the Chalk River Laboratories (Canada) will be discussed from the standpoint of coupl ed neutron gamma transport and photo-nuclear data applications.\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/700/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/700/ END:VEVENT BEGIN:VEVENT SUMMARY:CONFLUX – A Flexible\, Modular Reactor Neutrino Flux Calculation Framework DTSTART:20220727T165400Z DTEND:20220727T165700Z DTSTAMP:20260420T153400Z UID:indico-contribution-1127@indico.frib.msu.edu DESCRIPTION:Speakers: Xianyi Zhang (Lawrence Livermore National Laboratory )\n\nThe predicted reactor antineutrino flux is an important ingredient fo r particle physics measurements and neutrino-based safeguards applications \, ranging from neutrino oscillation measurements to monitoring reactor fu el and operations. Over the past decade\, comparisons between predictions and reactor neutrino experiments have revealed significant discrepancies w hich have motivated new neutrino and nuclear data measurements. CONFLUX is a new software framework that aims to provide a flexible and modular tool for multiple communities. \nThis new framework is being developed to stan dardize the input and output of the neutrino flux calculation\, increase t he accessibility of neutrino\, nuclear data to the community\, and package benchmark reactor and nuclear data. The software integrates three differe nt prediction modes: summation\, beta-spectra conversion\, and direct neut rino measurements. The comprehensive and flexible inclusion of nuclear dat a allow users to perform sensitivity studies\, evaluate impact of new data \, monitoring studies\, assess novel reactor types\, etc. In this presenta tion\, we describe the structure of the framework\, the calculation of bet a spectra and fission products\, as well as the nuclear data and beta\, ne utrino measurements used in the calculations. We will discuss possible app lications of the framework.\n\n\nThis work was performed under the auspice s of the U.S. Department of Energy by Lawrence Livermore National Laborato ry under Contract DE-AC52-07NA27344. LLNL-ABS-827390\n\nhttps://indico.fri b.msu.edu/event/52/contributions/1127/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1127/ END:VEVENT BEGIN:VEVENT SUMMARY:Stopping Power and Neutron Scattering Measurements in Support of S pace Exploration DTSTART:20220726T141200Z DTEND:20220726T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-685@indico.frib.msu.edu DESCRIPTION:Speakers: Lee Bernstein (LBNL/UCB)\n\nThe galactic cosmic ray (GCR) background presents creates a hostile\, high-dose environment for as tronauts and the electronics they rely. While the GCR spectrum extends to 10’s of GeV/nucleon\, much of the dose in electronics is attributable t o the final slowing of heavy ion at the end of their path\, e.g.\, the “ Bragg peak”\, and the location and magnitude of the Bragg peak is in tur n highly sensitive to the stopping power. In contrast\, long range dose a ttributable to the “neutron albedo” from backscattered neutrons arisin g from high-energy GCR cascades present a chronic health concern for long- term human habitation the surface of the moon and Mars. Researchers worki ng to address these concerns rely on robust nuclear data to guide the mode ling of both electronic stopping powers and neutron scattering. However\ , recent work by Sigmund and Baldez highlight the need for improved electr onics stopping power data. In this talk I will review the charged-particl e and neutron data needs relevant to space exploration and present a frame work for how to address them through a program heavy-ion and neutron beams using the LBNL 88-Inch cyclotron. This work is supported .by the Lawren ce Berkeley National Laboratory\, USA under Contract No. DE-AC02-05CH11231 for the US Nuclear Data Program.\n\nhttps://indico.frib.msu.edu/event/52/ contributions/685/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/685/ END:VEVENT BEGIN:VEVENT SUMMARY:Prospects for Measurements of Production Cross Sections of Light N uclei at RHIC DTSTART:20220726T134800Z DTEND:20220726T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-683@indico.frib.msu.edu DESCRIPTION:Speakers: Daniel Cebra (University of California\, Davis)\n\nT he damage due to cosmic rays is a serious concern for astronauts\, electro nics\, and spacecraft. Although the cosmic ray flux is comprised mostly o f protons and helium nuclei\, there is a non-negligible component comprise d of heavy-ions up to and including iron nuclei. The importance of the hea vy-ion component is enhanced because the damage due to ionization goes as $Z^2$. In addition to the damage due to primary ionization from a heavy-io n\, the damage from secondary production of p\, d\, t\, $^3$He\, and $^4$H e is also significant. Extensive double differential measurements for ligh t fragment production have been made for projectile energies below 3 GeV/n . Many of these measurements have been made at the NASA Space Radiation La boratory (NRSL)\, which uses beams extracted from the Booster synchrotron at Brookhaven National Laboratory (BNL). No light nucleus production data exist for heavy-ion projectile energies from 3-50 GeV/n. The Space Radiati on Protection community has identified this high energy regime as an area of need. Both cross section data and models to describe those data are nee ded. Although several facilities that could produce heavy-ion beams in thi s high energy range are either under construction or planned\, FAIR at GSI \, NICA at Dubna\, and an ion driver at JPARC\, currently the only facilit ies that can address the needs in this high energy range are the Super Pro ton Synchrotron (SPS) at CERN (13-200 GeV/n) and the Relativistic Heavy Io n Collider (RHIC) at BNL (3-125 GeV/n). Although RHIC is a collider\, the Solenoidal Tracker at RHIC (STAR) experiment has installed a fixed-target and the Collider Accelerator Division (CAD) has developed an efficient con duct of operations to deliver ion beams to the target. In the past few yea rs\, the RHIC/STAR fixed-target program has completed an energy scan with gold projectiles from 3 to 100 GeV/n on a gold foil target. Although gold ion beams are not relevant for space radiation concerns\, these measuremen ts demonstrate the capabilities of the STAR detector to make the light nuc leus production cross section measurements using particle identification w ith both ionization density ($dE/dx$) and time-of-fight (TOF). RHIC is a f lexible facility and can deliver the ion beam species (He\, C\, Si\, Fe) a nd energies (3-125 GeV/n) of need to the Space Radiation Community. STAR c an install the targets of interest (C\, Al\, Fe) and can make the necessar y light nucleus production cross section measurements. This talk will disc uss the prospects for making these measurements during the RHIC ion beam r unning periods from 2023-2025.\n\nhttps://indico.frib.msu.edu/event/52/con tributions/683/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/683/ END:VEVENT BEGIN:VEVENT SUMMARY:75 Years of Experimental Nuclear Reaction Data Compilations DTSTART:20220728T130000Z DTEND:20220728T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-879@indico.frib.msu.edu DESCRIPTION:Speakers: Boris Pritychenko (NNDC\, BNL)\n\nThe comprehensive experimental nuclear reaction data compilations were pioneered at the Meta llurgical Laboratory (University of Chicago) and Los Alamos National \nLab oratory [1\,2] for the Manhattan Project needs. In 1947 many Manhattan Pro ject alumni moved to a newly created Brookhaven National Laboratory to wor k on nuclear physics research and data compilations [3\,4] in support of n uclear science and reactor research activities. Since the beginning\, the data project has relied heavily on computer technologies available at the time\, and Brookhaven compilations have been stored in the Sigma Center I nformation Storage and Retrieval System (SCISRS) that predated the EXFOR d atabase. \n\nThe experimental data compilation efforts have always had an important international component. The IAEA Nuclear Data Section has been involved in this work since its creation in 1964. Other early contributors include NEA Data Bank\, Paris\, France\, and the Institute of Physics and Power Engineering\, Obninsk\, USSR which were founded in 1964 and 1963\, respectively. In 1969 an agreement on an exchange format was reached betwe en four centers and July 1970 was chosen as the starting date for transmis sion of neutron data between the partners in the EXFOR data interchange fo rmat.\n\nCurrently\, the compilation efforts are coordinated by the Nuclea r Reaction Data Centers network (NRDC) worldwide\, which was founded in 19 79 and operates under the auspices of the IAEA. The data compilations in t he USA are coordinated by the National Nuclear Data Center (NNDC)\, Brook haven National Laboratory for the United States Nuclear Data Program (USND P). In recent years\, the EXFOR compilations became even more popular worl dwide\, and many organizations have joined. The database compilations repr esent one of the oldest continuously operated scientific collaborations th at continue to archive and disseminate \nnuclear data for nuclear science and technology.\n\n\n[1] H.H. Goldsmith\, H.W. Ibser\, B.T. Feld\, ``Neut ron Cross Sections of the Elements A Compilation\," Rev. Mod. Phys. 19\, 259 (1947).\n[2] R.R. Wilson\, ``Los Alamos Technical Series\; Nuclear Ph ysics\," LA-1009\, Vol.3\, Sec.A (1947).\n[3] D.J. Hughes\, T.W. Bonner\ , H. Goldstein\, W.W. Havens\, Jr.\, L. Kaplan\, C.O. Muehlhause\, A.H. Sn ell\, J.R. Stehn\, T.M. Snyder\, R.F. Taschek\, A. Wattenberg\, C.W. Zabel \, ``Neutron cross sections\; a compilation of the AEC Neutron Cross Secti on Advisory Group. May 15\, 1952\," BNL-170 (1952).\n[4] D.J. Hughes\, J. A. Harvey\, ``Neutron Cross Sections. July 1\, 1955\," BNL-325 (1955).\n\n https://indico.frib.msu.edu/event/52/contributions/879/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/879/ END:VEVENT BEGIN:VEVENT SUMMARY:Resolved Resonance Region Analysis of $^{206}$Pb\, $^{207}$Pb\, AN D $^{208}$Pb in Support of Next Generation Lead-Cooled Fast Systems. DTSTART:20220725T192100Z DTEND:20220725T193300Z DTSTAMP:20260420T153400Z UID:indico-contribution-860@indico.frib.msu.edu DESCRIPTION:Speakers: Peter Brain (RPI)\n\n{Evaluated nuclear data files a re the basis for representing radiation interactions with nuclei in most m odern transport and diffusion codes. It is therefore important to verify a nd update isotopic evaluations periodically to ensure they incorporate up- to-date experimental data and reaction theory in the hope to accurately mo del systems with low uncertainty. Recently\, great interest has been gener ated in using lead as a coolant for fast neutron systems and as a result i t is important to investigate the ENDF/B-VIII.0\\cite{ENDF} isotopic evalu ations that comprise stable lead. To this end\, resonance parameters for $ ^{206}$Pb\, $^{207}$Pb\, and $^{208}$Pb were re-evaluated because their re solved resonance regions extend beyond 0.5 MeV meaning resonance parameter s used in reconstructing cross sections and elastic scattering angular dis tributions impact fast systems. The impact of resonance parameters is demo nstrated by the differences between the evaluations in predicting experime ntal results from the fully modeled RPI Quasi-Differential Scattering Expe riment\\cite{RPIscatter} in MCNP\\cite{MCNP}\, Figure \\ref{fig:RPIScat2}. In addition\, MCNP KCODE calculations of lead-sensitive fast spectra crit ical benchmarks showed variations of k$_{\\mathit{eff}}$ on average of 200 pcm\, caused solely from differences in elastic scattering angular distri butions in $^{208}$Pb. Re-evaluation entailed fitting data with the progra m SAMMY\\cite{SAMMY}. Resonance energies as well as neutron and radiation widths were fit sequentially to previously available high resolution trans mission measurements and new capture yield experiments made available afte r the release of ENDF/B-VIII.0. Constraints for resonance parameters inclu ded SAMMY's reduced chi-square\, resonance statistics (Wigner\, Porter-Tho mas\, and summed strength plots)\, and resonance properties (scattering le ngths\, thermal quantities\, and resonance integrals). Preliminary validat ion\, done via a suite of critical benchmarks containing lead as well as M CNP simulations of the RPI scattering experiment\, shows better agreement from the RPI evaluation for fast spectra criticality and scattering simula tions than ENDF/B-VIII.0\, JENDL-4.0 \\cite{JENDL}\, and JEFF-3.3\\cite{JE FF}.\n\nhttps://indico.frib.msu.edu/event/52/contributions/860/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/860/ END:VEVENT BEGIN:VEVENT SUMMARY:Status of ENDF DTSTART:20220729T133000Z DTEND:20220729T134500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1248@indico.frib.msu.edu DESCRIPTION:Speakers: Gustavo Nobre\n\nhttps://indico.frib.msu.edu/event/5 2/contributions/1248/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1248/ END:VEVENT BEGIN:VEVENT SUMMARY:Current status of the GALILEE-1 processing code DTSTART:20220725T171800Z DTEND:20220725T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-855@indico.frib.msu.edu DESCRIPTION:Speakers: Cédric Jouanne (CEA Saclay)\n\nGALILEE-1 is the new verification and processing system for evaluated data\, developed at CEA. \nWe have already presented in the past the reconstruction and Doppler bro adening of cross-sections implemented in the GTREND module of GALILEE-1. T he results obtained are of very good quality and we can explain the discre pancies observed with respect to other processing codes such as NJOY and P REPRO. This intensive comparison phase has increased the reliability of th e GTREND module. GTREND is already able to handle the R-Matrix Limited for mat (LRF=7) with a large number of channels in the Resolved Resonance Regi on (RRR).\nThe treatment of the Unsolved Resonance Range is a more complex problem because it is difficult to obtain an experimental or theoretical reference to evaluate the different results of the various processing code s. We have chosen to implement two approaches in order to produce usable d ata for the deterministic and Monte Carlo transport codes\, APOLLO3® and TRIPOLI-4® respectively\, developed at CEA. These transport codes use URR cross-section data in the form of multi-group probability tables on an en ergy mesh chosen by the user. This job was previously done by the CALENDF code. The description of these probability tables is different from that o f the NJOY PURR module\, which produces pointwise probability tables on a coarse energy mesh using an interpolation method.\nWe will thus present a method that allows us to obtain a random pointwise representation over the whole energy range of URR\, and a method similar to that of NJOY with a c alculation on some energy points. Both approaches yield multi-group probab ility tables. Simulations of mono-atomic configurations and criticality be nchmark configurations will be studied.\n\nA new feature of the GTREND pro cessing module is the possibility of processing thermal scattering data in a similar way as the THERMR module of NJOY. Some comparisons between GTRE ND and NJOY will be performed concerning the incoherent inelastic cross-s ection\, the transfer probability density function and the angular distrib ution. The new capabilities of GTREND will be shown using an optimal proce ssing for H1 bound in ZrH.\n\nhttps://indico.frib.msu.edu/event/52/contrib utions/855/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/855/ END:VEVENT BEGIN:VEVENT SUMMARY:Deuteron and alpha sub-libraries of JENDL-5 DTSTART:20220728T153800Z DTEND:20220728T155000Z DTSTAMP:20260420T153400Z UID:indico-contribution-893@indico.frib.msu.edu DESCRIPTION:Speakers: Shinsuke Nakayama (Japan Atomic Energy Agency)\n\nJE NDL-5 contains several sub-libraries to contribute to various applications . This presentation outlines the deuteron and alpha ones.\nNuclear data on neutron-production reactions induced by deuteron are required in the fiel ds of design of accelerator-based neutron sources. In such facilities\, ($ d\,xn$) reactions on Li\, Be\, or C are employed to generate neutron beams . We have recently developed JENDL/DEU-2020[1]\, which is the deuteron nuc lear library for $^{6\,7}$Li\, $^{9}$Be\, and $^{12\,13}$C up to 200 MeV. In the deuteron sub-library of JENDL-5\, the data of JENDL/DEU-2020 are pa rtially revised. In addition to that\, the data on accelerator structural materials such as $^{93}$Nb and $^{63\,65}$Cu are newly evaluated.\nAs for nuclear data on neutron-production reactions induced by alpha particle\, they are important in the fields of nuclear backend. Alpha particles emitt ed from the decay of actinide nuclides in spent nuclear fuel can induce ($ \\alpha\,xn$) reaction on surrounding light nuclides such as oxygen. Infor mation on not only the amounts but also energy spectra of the emitted neut rons is important for the evaluation of safe transportation\, storage\, an d reprocessing. In the alpha sub-library of JENDL-5\, we revise the outgoi ng neutron energy and angular distribution data and form for some of the 1 7 nuclides from $^{6}$Li to $^{30}$Si in JENDL/AN-2005[2]. This revision i s partially based on the founding in Ref. [3]. Moreover\, the data of elas tic scattering and those of the alpha particle and gamma ray spectra emitt ed together with the neutron emission channel have been added for each tar get nuclide.\nAn overview of the evaluation and validation of the above tw o sub-libraries will be provided.\nThis work was partially supported by JS PS KAKENHI Grant Number 19K15483.\n\n[1] S. Nakayama et al.\, J. Nucl. Sci . Technol. 58\, 805 (2021).\n[2] T. Murata et al.\, JAEA-Research 2006-052 (2006).\n[3] D.P. Griesheimer et al.\, Nucl. Eng. Technol. 49\, 1199 (201 7).\n\nhttps://indico.frib.msu.edu/event/52/contributions/893/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/893/ END:VEVENT BEGIN:VEVENT SUMMARY:General-purpose nuclear data library JENDL-5 and to the next DTSTART:20220728T145000Z DTEND:20220728T151400Z DTSTAMP:20260420T153400Z UID:indico-contribution-886@indico.frib.msu.edu DESCRIPTION:Speakers: Osamu Iwamoto (Japan Atomic Energy Agency)\n\nJapane se Evaluated Nuclear Data Library version 5 (JENDL-5) was released in 2021 . JENDL-5 is intended to extend its generality from JENDL-4.0 by covering a wide variety of nuclear data for applications not only to nuclear design and decommissioning\, but also to radiation-related fields. Overview of J ENDL-5 and a future plan for the next of JENDL-5 are presented.\n\nJENDL-5 includes up-to-date neutron reaction cross sections incorporating other v arious types of data such as newly evaluated nuclear decay\, fission yield \, and thermal neutron scattering law. The neutron induced reaction cross sections especially on minor actinides in the resonance regions are improv ed by the experimental data measured at ANNRI. The extensive benchmark ana lyses on neutron nuclear data were made and the performance of JENDL-5 was confirmed by benchmark tests of ICSBEP and IRPhEP as well as fast reactor s\, radiation shielding calculations\, and so on.\n\nSo far\, several JEND L special-purpose files have been developed for various applications. The data cover neutron\, charged particles\, and photon induced reactions. As the neutron induced reaction files\, two special purpose files of JENDL/AD -2017 and JENDL/ImPACT-2018 were released to meet needs of nuclear backend applications including activation evaluation for nuclear facilities and n uclear transmutations of high-level radioactive wastes of long-lived fissi on products\, respectively. Furthermore\, the photon\, proton and deuteron data were released as JENDL/PD-2016.1\, JENDL-4.0/HE and JENDL/DEU-2020\, respectively\, for accelerator applications. With updating the data\, the y were incorporated in JENDL-5 as sub-libraries for facilitation of usabil ity of JENDL.\n\nAs the next step of JENDL-5\, we are planning to provide the proper and sufficient covariance data that will contribute to uncertai nty estimation in various applications.\n\nhttps://indico.frib.msu.edu/eve nt/52/contributions/886/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/886/ END:VEVENT BEGIN:VEVENT SUMMARY:Status of JEFF DTSTART:20220729T134500Z DTEND:20220729T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1249@indico.frib.msu.edu DESCRIPTION:Speakers: Arjan Plompen\n\nhttps://indico.frib.msu.edu/event/5 2/contributions/1249/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1249/ END:VEVENT BEGIN:VEVENT SUMMARY:Updates and Validation for the n+63\,65Cu Cross Sections DTSTART:20220725T194500Z DTEND:20220725T195700Z DTSTAMP:20260420T153400Z UID:indico-contribution-865@indico.frib.msu.edu DESCRIPTION:Speakers: Jordan McDonnell (UT-Battelle)\n\nThe neutron induce d total\, elastic\, and capture cross sections of 63\,65Cu iso- topes were selected for evaluation in the resolved and unresolved resonance energy r anges by the National Criticality Safety Program to resolve discrepancies related to benchmark performance. This is especially evident for the serie s of ZEUS benchmarks in which copper is used as a reflector. Because coppe r is also used as structural material in both fission and fusion reactors\ , the need to address benchmark discrepancies linked to nuclear data defic iencies is a task of primary importance. The aim of this work is to descri be the steps of evaluation work towards a consistent improvement of the be nchmark performance.\nThe R-matrix analysis with the SAMMY code focused on the 63Cu(n\,γ) reaction channel between 100-300 keV coupled to unresolve d resonance region parameters up to 650 keV to fit average cross section d ata from a recent experiment. Due to the high sensitivity of many benchmar ks to elastic scattering angular distribution data\, especially for the 65 Cu isotope\, the impact of these data was tested by generating Legendre co efficients from both\nresonance parameters and the Hauser-Feshbach model. Guided by the findings of Shaw et al.\, the performance of the current eva luation for 65Cu was compared to that of ENDF/B-VII.1 and ENDF/B-VIII.0 by testing the reactivity coefficients corresponding to the validation suite of experimental criticality benchmarks for thermal\, intermediate\, and f ast systems taken from the International Criticality Safety Benchmark Expe riments Project Handbook. The benchmark performance is especially sensitiv e to 63Cu(n\,γ) and 65Cu elastic scattering for neutron energies in the 1 00–500 keV region\, whereas 100 keV is the upper limit of the resolved r esonance region in the ENDF/B-VIII.0 evaluations for 63\,65Cu. The results highlight the need to handle the transition from the resolved resonance r egion to the high energy region carefully.\n\nhttps://indico.frib.msu.edu/ event/52/contributions/865/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/865/ END:VEVENT BEGIN:VEVENT SUMMARY:The current status of nuclear data processing code NECP-Atlas DTSTART:20220725T174200Z DTEND:20220725T175400Z DTSTAMP:20260420T153400Z UID:indico-contribution-857@indico.frib.msu.edu DESCRIPTION:Speakers: Tiejun Zu (Xi'an Jiaotong University)\n\nIn the prev ious version of nuclear data processing code NECP-Atlas reported in the la st ND-2019\, the code could process the evaluated nuclear data into applic ation libraries of typical formats with the conventional processing method s. NECP-Atlas is under continuous development and verification during the past years. Several new capabilities have been developed in the code.\n(1) The code is extended to process the GNDS formatted evaluated nuclear data library. A generalized derived class is designed to be compatible with EN DF-6 and GNDS in nuclear data processing code NECP-Atlas\, and the GNDS to olkit is developed in NECP-Atlas to parse and convert GNDS\n(2) The module to calculate the thermal scattering law is updated to improve the accurac y. A method named anisotropic displacement parameters (ADP) is implemented to improve the coherent elastic scattering data. The 1-phonon correction method is implemented to improve the inelastic elastic scattering data. \n (3) A new module named RESK is developed to generate Doppler-broadened res onance elastic scattering kernel in PENDF format. And then the data is pro cessed into S(α\, β) table used by Monte Carlo codes\, and multi-group c ross sections and scattering matrix used by deterministic based codes.\n(4 ) The capability to generate photon data is newly developed. The code not only can provide the prompt parts of neutron-induced gamma production\, bu t it can also generate the decayed gamma which is produced by decay of fis sion products.\n(5) The capability to calculate neutron\, electron\, photo n displacement cross section is newly developed. For the displacement dama ge model\, apart from traditional NRT model\, state-of-the-art ARC model i s applied. Accuracy MOTT cross section is used as the electron different s cattering cross section to improve the accuracy.\n\nhttps://indico.frib.ms u.edu/event/52/contributions/857/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/857/ END:VEVENT BEGIN:VEVENT SUMMARY:Database work for the new Cross Section Standards Evaluation DTSTART:20220728T132400Z DTEND:20220728T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-880@indico.frib.msu.edu DESCRIPTION:Speakers: Denise Neudecker (Los Alamos National Laboratory)\, Georg Schnabel (IAEA)\, Vladimir Pronyaev (PI Atomstandart\, Russia\, reti red)\, Roberto Capote (IAEA)\, Allan Carlson (NIST and BNL)\n\nAn effort i s now underway to produce a new evaluation of the neutron cross section st andards. \nIt is important to maintain experimental programs to increase t he quality and extend the database\nfor the neutron cross section standard s in order to improve evaluations of them that will be used to convert cro ss section measurements made relative to those standards. \nMeasurements h ave been made for most of the standard cross sections since the last evalu ation of the standards. The improved database includes the cross sections for the H(n\,n)\, $^6$Li(n\,t)\,$^{10}$B(n\,αγ)\,\n$^{10}$B(n\,α)\, C( n\,n)\, Au(n\,γ)\, $^{235}$U(n\,f) and $^{238}$U(n\,f) standard reactions and ratios among them. The database also includes the $^{238}$U(n\,γ) an d $^{239}$Pu(n\,f) cross sections in addition to the standard cross sectio ns. Those data were included since there are many ratio measurements of th ose cross sections with the standards and absolute data are available on t hem. Thus they will have an impact on the standards in the evaluation pro cess that includes ratio data. In addition to the standard cross section m easurements\, work has been done and is ongoing on nubar for $^{252}$Cf.\n The results obtained from the work on this project will be given at this m eeting.\n\nhttps://indico.frib.msu.edu/event/52/contributions/880/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/880/ END:VEVENT BEGIN:VEVENT SUMMARY:Status and perspective of the development of JEFF-4 DTSTART:20220728T155000Z DTEND:20220728T160200Z DTSTAMP:20260420T153400Z UID:indico-contribution-894@indico.frib.msu.edu DESCRIPTION:Speakers: Arjan Plompen (European Commission\, Joint Research Centre\, Geel)\n\nFollowing the release of JEFF-3.3 in late 2017\, the JEF F coordination group took a step back to review its goals for a new major release\, JEFF-4: for users\, in terms of fields of application and perfor mance\, and within the project to modernize the methods for the production \, testing and benchmarking of its evaluated files. Given the broad range of applications of a nuclear data library and the general expectation of p rofessional users of best estimates with uncertainty through computer simu lations\, ambitious goals were set. To cover all interests\, the library m ust be truly general purpose\, provide best physics data with uncertaintie s and covariances\, be as complete as possible and be broadly tested and v alidated. To enable this\, an important focus is on enhanced quality assur ance and improved working methods. In support of this objective\, the OECD -NEA Databank continues to improve a new platform to sustain and enhance t he JEFF-4 developments: JEFF-lab\, a collaboration environment based on Gi tLab.\n\nA stakeholder workshop\, held in 2018\, indicated where to improv e performance for end-user applications beyond those of the JEFF working g roup members. In addition\, in 2021\, the Coordination Group surveyed the needs of the organizations participating in JEFF\, as well as of the expec ted contributions to the new library. A plan for testing and validation wa s established. There is an important emphasis on performance beyond the cu rrent NEA-Mosteller test case suite\, in the present-day and prospective r eactor and fuel cycle applications.\n\nFor JEFF-4\, we are aiming\, amongs t others\, for new major actinide evaluations\, a much-needed update of mi nor actinide evaluations\, new thermal scattering libraries\, new oxygen a nd iron files\, a systematic replacement of legacy files\, new thermal fis sion yields evaluations for U-235 and Pu-239\, a significant update of the decay data library. To enhance completeness and meet the goal of best phy sics estimates with uncertainties for a large number of nuclides\, JEFF co llaborates closely with the TENDL project. A large number of files in JEFF will be from TENDL. A number of the contributed dedicated evaluations wil l result from using the T6 system or TALYS.\n\nThe presentation will provi de an overview of the JEFF-4 development\, about 2.5 years before its fore seen date of release at the end of 2024.\n\nhttps://indico.frib.msu.edu/ev ent/52/contributions/894/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/894/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the $^{232}$Th/$^{235}$U fission cross section rati os at the Back-n white neutron source of CSNS DTSTART:20220725T190900Z DTEND:20220725T192100Z DTSTAMP:20260420T153400Z UID:indico-contribution-760@indico.frib.msu.edu DESCRIPTION:Speakers: Zijie Han\, Yonghao Chen\, Yiwei Yang\, Zhongwei Wen \, Jie Wen\, Rong Liu\, Han Yi\, Qiping Chen\, Zhizhou Ren\n\nNeutron-indu ced fission cross section of 232Th has important applications in the Th/U fuel cycle. A measurement of the 232Th/235U fission cross section ratios i n 1-20 MeV energy region was carried out by the time-of-flight method and Fast Ionization Chamber Spectrometer for Fission Cross Section Measurement (FIXM) at the China Spallation Neutron Source (CSNS)- Back-n white neutro n source (Back-n). The fission event-energy spectrum and amplitude spectru m of 232Th and 235U have been measured in the single-bunch and double-bunc h operation modes. The time-of-flight (TOF) spectrum under double-bunch mo de was unfolded by using Bayes method and the results of fission cross sec tion ratios of 232Th/235U was obtained after various modifications. The re sults under single-bunch mode was also obtained and the experimental uncer tainty of the two datasets was analyzed. The results of 232Th/235U fission cross section ratios under the two modes are in agreement in the range of experimental uncertainty. The results are compared with the main evaluati on database and the previous experimental results. The current results can provide experimental data support for evaluation of relevant nuclear data and design of Th/U cycle nuclear system.\n\nhttps://indico.frib.msu.edu/e vent/52/contributions/760/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/760/ END:VEVENT BEGIN:VEVENT SUMMARY:Updated Chinese Evaluated Nuclear Data Library and Its Application s DTSTART:20220728T152600Z DTEND:20220728T153800Z DTSTAMP:20260420T153400Z UID:indico-contribution-891@indico.frib.msu.edu DESCRIPTION:Speakers: Zhigang GE (China Institute of Atomic Energy/China N uclear Data Center)\n\nAs the main output of CENDL project\, the updated C hinese Evaluated Nuclear Data Library\, CENDL-3.2 released in June 2020\, which contains the neutron reaction data file which contained 272 material s\, and the evaluated activation\, fission yields\, decay data and photonu clear data file are also included CENDL-3.2.\nOut of all 272 materials\, t he data for 135 materials are totally new，partly updated evaluations\, w hile the other 137 materials were inherited and adopted as it was from pre vious version\, CENDL-3.1. 1) 58 nuclides are brand newly evaluated on the basis of latest experimental information and model calculations\, coverin g a broad spectrum of nuclides from n-1 to 241Am\; 2) 14 nuclides are re-v iewed and re-evaluated from previous version\, with part of the data set m odified\, including 2H\, 7Li\, 93Nb and major actinides isotopes Th\, U\, Np and Pu\; 3) through an estimation of the uncertainties of theoretical m odel parameters within the generalized least square scheme\, model depende nt covariances for main reaction cross section data are added for fission product nuclei.\nFission yield sub-library of CENDL-3.2 contains the fissi on yields for the neutron induced 235U\, 238U and 239Pu fission systems\, including the independent and cumulative yields. The evaluation performed with fission model calculations based on available measured data. \nCENDL- 3.2 also contained the evaluated decay data for about 1400 nuclides betwee n A=66 to A=172 region. The Q-values of the decay modes are updated to the Atomic Mass Evaluation (AME) released recently. All T1/2 are revised by n ew measurements\, and mean energies for beta & gamma taken from TAGS measu rements or theoretical calculation. \nActivation sub-library of CNEDL-3.2 contains evaluated excitation functions for about 400 isotopes for inciden t neutron with energies up to 20 MeV. The isotopes range from Ti to W with stable or T1/2>1h. The reaction cross sections\, decay data and isomeric branching ratios\, nuclide production cross sections are given.\nPhotonucl ear data sub-library contained photonuclear data for 266 nuclei. The globa l estimation based on various Lorentzian models for all elements is perfor med. The calculation for the competing photonuclear data is performed base d on MEND-G and GUNF codes for light nuclei.\nThe systematic comparisons b etween CENDL-3.2 and other major evaluated libraries: ENDF\, JENDL\, BROND \, JEFF and TENDL\, as well as experimental data available have been imple mented. Moreover\, the benchmarking test of CENDL-3.2 was performed\, an i ntegrated benchmarking test system including more than 1200 criticality be nchmark configurations.\nThe CENDL3.2 have been applied in the Chinese dom estic nuclear industry\, including the design of CFR600 and TMSR\, ADS pro ject\, and other application of reactor physics simulations\, shielding be nchmarks studies etc.\n\nhttps://indico.frib.msu.edu/event/52/contribution s/891/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/891/ END:VEVENT BEGIN:VEVENT SUMMARY:Enhancing User Experience to Facilitate Nuclear Physics Research t hrough NuDat DTSTART:20220727T182400Z DTEND:20220727T183600Z DTSTAMP:20260420T153400Z UID:indico-contribution-874@indico.frib.msu.edu DESCRIPTION:Speakers: Donnie Mason\n\nThe National Nuclear Data Center (NN DC) at Brookhaven National Laboratory (BNL) has developed and maintained N uDat\, a web application where users can explore several databases contain ing nuclear structure\, nuclear decay\, and neutron-induced nuclear reacti on information. NuDat is the primary web application used to query and vis ualize meticulously evaluated recommended values derived from all publishe d experimental nuclear structure and decay data contained within the Evalu ated Nuclear Structure Data File (ENSDF). NuDat was first developed over 1 5 years ago and now there are over 4 million queries to NuDat each year fo r research\, education\, and a wide range of applications. In order to pro vide an enhanced user experience\, NuDat 3.0 is currently being developed and incorporating the latest computing technologies.\n \n The moderniz ed NuDat 3.0 is implemented using HTML Canvas to create a dynamic chart of nuclides. Users can seamlessly interact with over 3\,300 nuclides with in tuitive pan and zoom gestures. NuDat 3.0 is accompanied by interactive plo ts that are similarly controlled. NuDat 3.0 has a full range of features to support exploring the nuclear data contained within ENSDF. For example\ , the supplementary plots can be synced to automatically plot data display ed in the current view of the interactive chart of nuclides. The goal is t o create responsive nuclear data visualizations to support user needs and uniquely visualize the vast amounts of data that ENSDF has to offer. \n\n Beyond the interactive chart of nuclides\, NuDat offers a full suite of web applications to search and visualize nuclear data. The Advanced Cross- Variable Plot provides users with an interface to create various plots by selecting axis variables from a multitude of observable properties. These plots have been modernized to generate feature rich and dynamic visualizat ions that are both highly interactive and customizable. NuDat 3.0 also pro vides fully interactive level and decay schemes for relevant nuclei. Users can intuitively navigate and customize these complex schemes to precisely view the desired nuclear data properties.\n\n NuDat has considerably ev olved since its inception. NuDat 3 will continue to improve based on feedb ack from the community with a focus on developing novel visualization tool s to provide users with an intuitive interface to the nuclear data within ENSDF and ENDF. The ubiquitous demand for meticulously evaluated nuclear d ata emphasizes the need for modernizing NuDat using the latest computing t echnologies\, in order to provide an enhanced user experience. \n\n This Research is sponsored by Office of Nuclear Physics\, Office of Scienc e\,US Department of Energy\, under contracts DE-AC02-98CH10946 (BNL).\n\nh ttps://indico.frib.msu.edu/event/52/contributions/874/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/874/ END:VEVENT BEGIN:VEVENT SUMMARY:Processing of JEFF nuclear data libraries for the SCALE Code Syste m and testing with criticality benchmark experiments DTSTART:20220728T164000Z DTEND:20220728T165200Z DTSTAMP:20260420T153400Z UID:indico-contribution-983@indico.frib.msu.edu DESCRIPTION:Speakers: Antonio Jimenez-Carrascosa (Universidad Politécnica de Madrid)\n\nNuclear data processing is the procedure devoted to the con version of evaluated nuclear data into libraries suitable for specific fin al applications such as neutron transport or inventory calculations. AMPX is the modular processing code of SCALE Code System that takes basic cross section data in Evaluated Nuclear Data File format to provide both multig roup and continuous energy libraries for their use within SCALE.\n\nIn the last years\, a new version of the Joint Evaluated Fission and Fusion File (JEFF) data library\, namely JEFF-3.3\, has been released with relevant u pdates in the neutron reaction\, thermal neutron scattering and covariance sub-libraries. Its application within SCALE system is a valued asset\, en abling the use of JEFF state-of-the-art nuclear data libraries with the ex tensively tested and verified SCALE codes for nuclear analysis. Within the EU H2020 SANDA project\, the nuclear data processing route recommended by AMPX is being applied and validated in order to allow such application an d contribute to the improvement of new versions of JEFF data file. That ro utine is used for processing the continuous energy JEFF-3.3 neutron librar y and also the well-established JEFF-3.1.1 using the latest version of the AMPX processing code in SCALE6.3beta version which includes relevant upda tes regarding the treatment of the unresolved resonance region of the neut ron cross sections.\n\nIn this paper\, an overview about the processing of JEFF-3.3 and JEFF-3.1.1 nuclear data libraries with AMPX for their applic ation within the SCALE Code System is presented. These libraries are verif ied and tested using a comprehensive set of criticality benchmarks from IC SBEP\, by comparing both with results provided by other processing and neu tron transport codes and experimental data. Both libraries are successfull y processed and the discrepancies observed during the testing phase are ex plained establishing the applicability domain of the library. Processing o f JEFF-3.3 covariances is also addressed along with their corresponding ve rification using covariances processed with NJOY for a variety of systems. In conclusion\, a detailed analysis is carried out paving the way towards the final goal of releasing an AMPX-formatted continuous energy JEFF-3.3 and JEFF-3.1.1 neutron data libraries through the Nuclear Energy Agency/Co mputer Program Services (NEA/CPS).\n\nhttps://indico.frib.msu.edu/event/52 /contributions/983/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/983/ END:VEVENT BEGIN:VEVENT SUMMARY:Status of JENDL DTSTART:20220729T140000Z DTEND:20220729T141500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1250@indico.frib.msu.edu DESCRIPTION:Speakers: Osamu Iwamoto\n\nhttps://indico.frib.msu.edu/event/5 2/contributions/1250/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1250/ END:VEVENT BEGIN:VEVENT SUMMARY:Status of the ENDF/B-VIII.1 Library DTSTART:20220728T151400Z DTEND:20220728T152600Z DTSTAMP:20260420T153400Z UID:indico-contribution-888@indico.frib.msu.edu DESCRIPTION:Speakers: Gustavo Nobre (BNL)\, David Brown\n\nThe Cross Secti on Evaluation Working Group (CSEWG) is actively working to assemble its ne xt library release\, ENDF/B-VIII.1. In this contribution\, we will outlin e progress toward this release. From the neutron sublibrary\, there are s everal new evaluations from the INDEN collaboration (Cr\, Mn\, Fe\, Si\, 2 35U\, 233U\, 239Pu\, 16\,18O)\, and from others in CSEWG (140\,142Ce\, 63\ ,65Cu\, 86Kr\, Pb\, 181Ta\, 103Rh and minor revisions). With these changes \, all main components of stainless steel have now been updated. In the t hermal neutron scattering library\, the number of changes is enormous and includes Be2C\, 7LiH\, 7LiD\, UH3\, YH2\, ZrH2 and ZrHx from the Naval Nu clear Laboratory\; metal Be\, graphite\, SiC\, and UC from North Carolina State University\; MgO\, MgF2 and BeF2 from University of Sharjah\; and mo re than 200 evaluations generated from the NCrystal by the European Spalla tion Source. These changes far exceed the number of available MAT numbers in the legacy ENDF-6 format. Several of the new TSL evaluations use the mixed mode moderator format backported to the ENDF-6 format from GNDS-2.0. Several improvements to the SFY\, NFY and decay sublibraries have been m ade including the addition of antineutrino spectra\, enabling new nonproli feration applications. There are also new alpha sublibrary additions to s upport nuclear safeguards applications. Other changes include several oth er charged particle evaluations and the full adoption of the IAEA Photonuc lear Library. ENDF/B-VIII.1 will be released in both GNDS-2.0 and the leg acy ENDF-6 format. Due to the COVID-19 pandemic\, much of the experimenta l work has been delayed and in-person meetings have been canceled. As a r esult\, the ENDF/B-VIII.1 release will be delayed until February 2024.\n\n \nThis work was supported by the Nuclear Criticality Safety Program\, fund ed and managed by the National Nuclear Security Administration for the Dep artment of Energy. The work at Brookhaven National Laboratory was sponsore d by the Office of Nuclear Physics\, Office of Science of the U.S. Departm ent of Energy under Contract No. DE-AC02-98CH10886 with Brookhaven Science Associates\, LLC.\n\nhttps://indico.frib.msu.edu/event/52/contributions/8 88/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/888/ END:VEVENT BEGIN:VEVENT SUMMARY:Experimental activities and plans at the neutron time-of-flight fa cility n_TOF at CERN DTSTART:20220725T163000Z DTEND:20220725T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-592@indico.frib.msu.edu DESCRIPTION:Speakers: The n_TOF Collaboration\, Alberto Mengoni\n\nBased o n an idea by Carlo Rubbia\, the n_TOF facility has been operating during t he last 20 years at CERN. n_TOF is a spallation neutron source\, driven by the 20 GeV/c proton beam from the CERN PS accelerator. A massive Lead spa llation target is feeding two experimental areas set at 185 meters (EAR1\, horizonal with respect to the proton beam direction) and at 20 meters (EA R2\, in the vertical direction) from the spallation source. Neutrons in a very wide energy range - from GeV down to sub-eV kinetic energy - are gene rated and selected by the time-of-flight technique\, with the long flight paths ensuring the possibility of performing very high-resolution measurem ents.\n\nOver the course of two decades\, more than one hundred experiment s have been performed by the n_TOF Collaboration\, in the domain of nuclea r data for advanced technologies (neutron capture\, neutron induced fissio n and (n\,cp) reactions for accelerator driven systems\, Gen-IV and Th/Ufu el cycle)\, in nuclear astrophysics (synthesis of the heavy elements in st ars\, big bang nucleosynthesis\, nuclear cosmo-chronology)\, and for basic nuclear science (nuclear structure and decay of highly excited compound s tates). Overall\, measurements at n_TOF generated ~100 entries in the EXFO R database\, covering over 90% of the data released by the n_TOF Collabora tion.\n\nDuring the planned shutdown of the CERN accelerator complex\, bet ween 2019 and 2021\, the facility went through a substantial upgrade with a new target-moderator assembly\, refurbishing of the neutron beam lines a nd experimental areas. An additional station (the NEAR Station) has been s et up at approximately 2 m from the target-moderator assembly. The NEAR St ation capabilities for performing material irradiation studies\, neutron i nduced activation and new physics opportunities are presently explored.\n\ nAn overview of the experimental activities performed at n_TOF will be pre sented\, with a particular emphasis on the most recent results and plannin g for the future.\n\n___\n(*) Spokesperson of the n_TOF Collaboration\n\nh ttps://indico.frib.msu.edu/event/52/contributions/592/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/592/ END:VEVENT BEGIN:VEVENT SUMMARY:History of fission nuclear data from 1939-1945 and evolution to to day's understanding DTSTART:20220725T184500Z DTEND:20220725T190900Z DTSTAMP:20260420T153400Z UID:indico-contribution-759@indico.frib.msu.edu DESCRIPTION:Speakers: Mark Chadwick\n\nNuclear physics advances in the Uni ted States and Britain from 1939 to 1945 are described. The Manhattan Proj ect’s work led to a rapid advance in our knowledge of nuclear science. A conference in April 1943 at Los Alamos provided a simple formula used to compute critical masses and laid out the research program needed to determ ine the key nuclear constants. In short order\, four university accelerato rs were disassembled and reassembled at Los Alamos\, and methods were esta blished to make measurements on extremely small samples owing to the initi al lack of availability of enriched 235U and plutonium. I trace the progra m that measured fission cross sections\, fission-emitted neutron multiplic ities and their energy spectra\, and transport cross sections\, comparing the measurements with our best under-standing today as embodied in the Eva luated Nuclear Data File ENDF/B-VIII.0. The large nuclear data uncertainti es at the beginning of the project\, which often exceeded 25% to 50%\, wer e reduced by 1945 often to less than 5% to 10%. Uranium-235 and plutonium- 239 fission cross-section assessments in the fast mega-electron-volt range were reduced following more accurate measurements\, and the neutron multi plicity ν increased. By a lucky coincidence of canceling errors\, the ini tial critical mass estimates were close to the final estimated masses. Som e images from historical documents from our Los Alamos archives are shown. Many of the original measurements from these early years have not previou sly been widely available. Through this work\, these data have now been ar chived in the international experimental nuclear reaction data library (EX FOR) in a collaboration with the International Atomic Energy Agency and Br ookhaven National Laboratory.\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/759/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/759/ END:VEVENT BEGIN:VEVENT SUMMARY:Results on the $n+ ^{233}$U $\\alpha$-ratio\, prompt fission $\\ga mma$-ray spectra and isomeric fission states measured at n_TOF DTSTART:20220725T192100Z DTEND:20220725T193300Z DTSTAMP:20260420T153400Z UID:indico-contribution-761@indico.frib.msu.edu DESCRIPTION:Speakers: Emmeric Dupont\, Vasilias Vlachoudis\, Stefan Kopeck y\, Jan Heyse\, Peter Schillebeeckx\, Eric Berthoumieux\, Gilbert Bélier\ , Julien Taieb\, Frank Gunsing\, Maria Diakaki\, Ludovic Mathieu\, Michael Bacak\n\nThe 233U nucleus plays a key role as the fissile isotope in the Th-U fuel cycle. Consequently the accurate knowledge of its fission and ca pture cross sections is essential for a potential reactor design. As highl ighted by the NEA High Priority Request List\, the 233U(n\,g) is of high i mportance for the production and destruction of 233U and is required to fa cilitate defining the reprocessing scheme for a molten salt reactor. Due t o the 233U(n\,f) reaction's inherent gamma-ray background the measurement of 233U(n\,g) requires an efficient background discrimination. This can be achieved by employing a fission and a gamma-ray detector in anti-coincide nce. For this purpose a pocket-sized fast fission chamber was designed and used together with the n_TOF Total Absorption Calorimeter 4$\\pi$ gamma-r ay detector at the n_TOF EAR1 facility at CERN. A brief description of the experimental setup is given and the fission detector and coupled detector s' performance will be presented. A description of the analysis methodolog y and procedure discussing relevant sources of background for the measurem ent will be given. The setup's capability to identify the fission gamma-ra ys for background estimation in turn allows us to extract information on t he average energy and multiplicity of the prompt fission gamma-rays which are compared with other recent measurements and theoretical models. Furthe rmore\, a careful analysis of the coincidence spectra enables to study the half-lives of 233U isomeric fission states. A good agreement with simulat ed gamma-ray cascades of the captured nucleus allows us to calculate the e xperimental detection efficiencies and finally the results on the 233U $\\ alpha$-ratio and 233U(n\,g) will be shown and compared to existing data se ts and evaluations.\n\nhttps://indico.frib.msu.edu/event/52/contributions/ 761/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/761/ END:VEVENT BEGIN:VEVENT SUMMARY:Status of TENDL DTSTART:20220729T141500Z DTEND:20220729T143000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1251@indico.frib.msu.edu DESCRIPTION:Speakers: Arjan Koning (IAEA)\n\nhttps://indico.frib.msu.edu/e vent/52/contributions/1251/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1251/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Data User Perspective: Reactor Physics DTSTART:20220729T150000Z DTEND:20220729T153000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1252@indico.frib.msu.edu DESCRIPTION:Speakers: Patrick Blaise\n\nhttps://indico.frib.msu.edu/event/ 52/contributions/1252/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1252/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Data User Perspective: DOE Isotope Program DTSTART:20220729T153000Z DTEND:20220729T160000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1253@indico.frib.msu.edu DESCRIPTION:Speakers: Ethan Balkin\n\nhttps://indico.frib.msu.edu/event/52 /contributions/1253/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1253/ END:VEVENT BEGIN:VEVENT SUMMARY:ND2025 Announcement DTSTART:20220729T170000Z DTEND:20220729T171000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1255@indico.frib.msu.edu DESCRIPTION:Speakers: Enrique M. González Romero (CIEMAT)\n\nhttps://indi co.frib.msu.edu/event/52/contributions/1255/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1255/ END:VEVENT BEGIN:VEVENT SUMMARY:Methods for calculating self-shielded multigroup displacement dama ge cross section DTSTART:20220726T141200Z DTEND:20220726T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-705@indico.frib.msu.edu DESCRIPTION:Speakers: Shengli Chen\n\nNeutron irradiation damage is a key factor that influences behaviors of nuclear materials. Folding the specifi c neutron flux to the pre-calculated displacement damage cross section is a widely used method for quantifying neutron irradiation damage in nuclear reactors. This method has been implemented in various neutron transport c odes\, such as ERANOS and OpenMC. However\, because the displacement damag e cross section is a generalization of nuclear cross section\, current the ories on the computation of self-shielded multigroup cross section are not directly applicable for the damage cross section.\nDisplacement damage cr oss section\, briefly noted by Displacement per Atom (DPA) cross section h ereinafter\, is proportional to the product of nuclear reaction cross sect ion and the average damage energy: σ_DPA (E)∝σ(E) E_a (E). There are t hree approaches to calculate the multigroup DPA cross section. Figure 1 sh ows the multigroup DPA cross sections computed with the three methods alon g with the quasi-point-wise (ECCO 1968 group) one for neutron elastic scat tering on 56Fe. The first method is mathematically rigorous for computing multigroup cross section\, but the self-shielding corrections on nuclear c ross section cannot be directly applied. The latters can directly use the self-shielding corrections on nuclear cross section\, whereas they are not mathematically well defined for multigroup reaction rate calculation.\nTh e present work thoroughly studies the three approaches for computing multi group DPA cross section and their influences on DPA rate based on Fe in th e core and Mg in the reflector of a typical sodium-cooled fast breeder rea ctor. In addition\, the uncertainty induced by the approximate treatments of self-shielded multigroup DPA cross sections is also quantified.\n\nhttp s://indico.frib.msu.edu/event/52/contributions/705/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/705/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Data User Perspective: Nuclear Nonproliferation DTSTART:20220729T160000Z DTEND:20220729T163000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1254@indico.frib.msu.edu DESCRIPTION:Speakers: David Matters\n\nhttps://indico.frib.msu.edu/event/5 2/contributions/1254/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1254/ END:VEVENT BEGIN:VEVENT SUMMARY:Closing remarks DTSTART:20220729T171000Z DTEND:20220729T172000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1256@indico.frib.msu.edu DESCRIPTION:https://indico.frib.msu.edu/event/52/contributions/1256/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1256/ END:VEVENT BEGIN:VEVENT SUMMARY:Study of decay properties for Ce to Nd nuclei (A~160) relevant for the formation of the r-process rare-earth peak DTSTART:20220728T150200Z DTEND:20220728T151400Z DTSTAMP:20260420T153400Z UID:indico-contribution-917@indico.frib.msu.edu DESCRIPTION:Speakers: Max Pallàs Solís (Universitat politecnica de catal unya (UPC))\n\nAround half of the nuclei heavier than iron are created via the rapid neutron capture process (r-process). For nuclear masses $A>100$ \, there are two main peaks in the r-process elemental solar system abunda nces\, located at $A\\sim 130$ and $A\\sim 195$\, which are associated wit h the neutron shell closure during the $(n\,\\gamma)$ $\\leftrightarrow$ $ (\\gamma \,n)$ equilibrium. In contrast\, the rare-earth peak (REP) is a s mall - but clear - peak around mass $A=160$\, which originates from the fr eeze-out during the late phases after neutron exhaustion. The formation of the REP offers a unique probe for the study of the late-time conditions o n the r-process site. According to theoretical models and sensitivity stud ies\, half-lives $(T_{1/2})$ and beta-delayed neutron emission probabiliti es $(P_{n})$ of very neutron-rich nuclei for $55\\le Z\\le64$ are the most influential ones on the formation of the REP [1\,2].\nThe BRIKEN project [3\,4]\, launched in 2016 at the RIBF in the RIKEN Nishina Center\, aims t o measure $\\beta$-decay properties for a large number of nuclei on the pa th of the r-process. Accordingly\, $T_{1/2}$ and $P_{n}$-values for the mo st influential nuclei to the REP formation from Ba to Eu ($A\\sim 160$) ha ve been measured for the first time with BRIKEN. In this work\, the detail s of the measurements of about 25 isotopes in the region from Ce to Nd wil l be discussed. The first experimental results will be presented.\n\n\nRef erences\n\n[1] M. R. Mumpower et al. Phys. Rev. C 85\, 045801 (2012). \n[2 ] A. Arcones and G. Martinez Pinedo\, Phys. Rev. C 83\, 045809 (2011)\n[3] J.L. Tain et. al\, Acta physica polonica B\, 49(03) (2018) 417–428.\n[4 ] A. Tolosa-Delgado and et. al\, NIM A 925 (2019) 133 – 147\n\nhttps://i ndico.frib.msu.edu/event/52/contributions/917/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/917/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear structure data obtained by the $(n_{th}\, 2\\gamma)$ react ion DTSTART:20220728T134800Z DTEND:20220728T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-908@indico.frib.msu.edu DESCRIPTION:Speakers: Nikola Jovancevic (University of Novi Sad)\n\nN. Jov ancevic$^1$\, D. Knezevic$^2$\, A.M. Sukhovoj$^3$\, L.V. Mitsyna$^3$ M. Kr mar$^1$\, \n\n$^1$) Department of Physics\, Faculty of Science\, Universi ty of Novi Sad\, Serbia \\\\\nnikola.jovancevic@df.uns.ac.rs\\\\\n$^2$) In stitute of Physics Belgrade\, University of Belgrade\, Belgrade\, Serbia\\ \\\n$^3$)Frank Laboratory of Neutron Physics\, Joint Institute for Nuclear Research\, Dubna\, Russian Federation\\\\\n\n\n\nDetermination of the acc urate values for gamma transitions\, level scheme\, nuclear level density and radiative strength function are one of the most important tasks in nuc lear physics below the giant electric dipole resonance region. Accurate ex perimental values of those parameters are very important for the analysis of astrophysical reactions\, production rare isotope beams for fundamental research\, reactor technology\, etc. One of the most suitable techniques for the determination of the nuclear matter parameters is the two-step gam ma cascades method [1\,2\,3]. It is based on the measurements of gamma coi ncidences following neutron capture. This technique enables the reconstruc tion of the gamma transitions and level scheme of the atomic nucleus as we ll as to determinate level density and the radiative gamma strength functi on by fitting the detected intensities of two-steps gamma cascades by the predicted models\, or by using iterative procedures [4\,5\,6]. Here\,we pr esent the results obtained for 43 nuclei in mass region of $28 \\leq A \\l eq 200$. Obtained data are necessary for better understanding of nuclear structure and development of reactor technology. \n\n[1] Boneva\, S.\, Khi trov\, V.\, Sukhovoj\, A.\, Vojnov\, A. Nucl. Phys. A 589\, 293 (1995).\n [2] Vasilieva\, E. V.\, Sukhovoj\, A. M.\, Khitrov\, V. A. Phys. of Atomi c Nuclei 64\, 153 (2001).\n[3] D. C. Vu et al.\, Phys. Atom. Nucl. 80\, 2 37 (2017).\n[4] N. Jovancevic et al.\, Journal of the Korean Physical Soci ety\, Vol. 75\, No. 2\, July 2019\, pp. 100∼116.\n[5] Knezevic\, D.\, et al.\, (2019)\, NPA\, 992\, 121628.\n[6] Knezevic\, D.\, et al.\,Nuclear P hysics A\, Volume 993\, January 2020\, 121645\n\nhttps://indico.frib.msu.e du/event/52/contributions/908/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/908/ END:VEVENT BEGIN:VEVENT SUMMARY:Evolution of collectivity in $^{126\,128}$Xe studied in Coulomb ex citation measurements DTSTART:20220728T151400Z DTEND:20220728T152600Z DTSTAMP:20260420T153400Z UID:indico-contribution-919@indico.frib.msu.edu DESCRIPTION:Speakers: Stanimir Kisyov (Lawrence Livermore National Laborat ory\, Livermore\, California 94550\, USA)\n\nThe even-A stable Xe isotopes are placed in a mass region where a variety of nuclear phenomena emerge. In particular\, $^{126}$Xe and $^{128}$Xe exhibit characteristics of trans itional nuclei\, a possible critical point in the shape transition from sp herical to γ-soft\, O(6)-like nuclei [1].\n\nIn order to probe the struct ure and collectivity of $^{126\,128}$Xe\, their properties were studied in low-energy Coulomb excitation measurements. An experiment was performed a t the The National Superconducting Cyclotron Laboratory (NSCL) Re-accelera tor facility at Michigan State University (MSU). The $^{126}$Xe and $^{128 }$Xe nuclei were accelerated to 3.74 MeV/u and 3.81 MeV/u\, respectively\, and impinged on $^{196}$Pt and $^{208}$Pb targets. The scattered nuclei w ere detected in coincidence with de-excitation gamma-rays using the Joint Array for Nuclear Structure (JANUS) experimental setup. The detector confi guration included a pair of segmented double-sided Si detectors and the Se gmented Ge Array (SeGA) comprising of sixteen 32-fold segmented high-purit y germanium detectors\, placed around the target chamber. \n\nTransition a nd diagonal matrix elements were determined from the experimental data usi ng the GOSIA code [2]. They were further used to calculate E2 reduced tran sition probabilities and quadrupole moments for states in $^{126\,128}$Xe. The results for the B(E2) values are in agreement with literature data fr om previous Coulomb excitation measurements [3\,4]. The new results for qu adrupole moments give a more detailed insight on the structure of the even -A Xe isotopes. The values suggest a deviation from the O(6) dynamical sym metry which was thought to describe well the properties of even-A Xe in th is mass region. \n\nThis material is based upon work supported by the U.S. Department of Energy\, Office of Science\, Office of Nuclear Physics. Wor k at LLNL is supported by the U.S. DOE under Contracts No. DE-AC52-07NA273 44\, 89233218CNA000001.\n\n[1] R. M. Clark et al.\, Phys. Rev. C **69**\, 064322 (2004).\n[2] T. Czosnyka\, D. Cline\, and C. Y. Wu\, Bull. Am. Phys . Soc. **28**\, 745 (1983).\n[3] L. Coquard et al.\, PRC **83**\, 044318 ( 2011).\n[4] J. Srebrny et al.\, Nuclear Physics A **557**\, 663 (1993).\n\ nhttps://indico.frib.msu.edu/event/52/contributions/919/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/919/ END:VEVENT BEGIN:VEVENT SUMMARY:Method to Compare Fission-To-Scattering Ratios using Uranium-238 DTSTART:20220725T195700Z DTEND:20220725T200900Z DTSTAMP:20260420T153400Z UID:indico-contribution-764@indico.frib.msu.edu DESCRIPTION:Speakers: Michael Rapp\, Ezekiel Blaine\, Devin Barry\, Brian Epping\, Robert Block\, Yaron Danon\, Adam Daskalakis\n\nNeutron time-of-f light quasi-differential high energy scattering measurements of uranium-23 8 and natural iron were made at the Rensselaer Polytechnic Institute (RPI) Gaerttner Linear Accelerator Center. Data from the measurements were comp ared to evaluated nuclear data libraries using MCNP to identify energy-ang le discrepancies from 0.5 to 20 MeV\, and elastic-to-inelastic scattering ratios were generated using the detectors’ measured response functions f rom 1.4 to 2.0 MeV. A new analysis technique was applied to pre-existing u ranium-238 data to derive uranium-238 fission response functions at severa l energies. Combining the scattering and fission response functions has al lowed for the calculation of scattering-to-fission ratios for uranium-238. These response functions can also be used to isolate the scattering contr ibution and to constrain nuclear data physics models used in the developme nt of evaluated nuclear data libraries.\n\nhttps://indico.frib.msu.edu/eve nt/52/contributions/764/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/764/ END:VEVENT BEGIN:VEVENT SUMMARY:A new approach to precisely measure gamma-ray intensities for long -lived fission products DTSTART:20220728T171600Z DTEND:20220728T172800Z DTSTAMP:20260420T153400Z UID:indico-contribution-924@indico.frib.msu.edu DESCRIPTION:Speakers: Nicholas Scielzo (Lawrence Livermore National Labora tory)\n\nFission-product yields are one of the most fundamental pieces of nuclear data associated with nuclear fission\, and they play an important role in fundamental neutrino science\, nuclear energy\, nuclear medicine\, and national security. One of the most straightforward and reliable ways to determine fission-product yields is via detection of the characteristic γ rays emitted following the β decay of the fission products. Currently \, much of the nuclear data suffer from large uncertainties\, which contri butes to the uncertainties in the determined fission yields. We have devel oped a new experimental method [1] that takes advantage of radioactive-ion beams at CARIBU and a well-characterized detection system [2] to determin e γ-ray intensities following the β decay of long-lived species to a fra ctional precision of 1%. We will present results for 144Ce and 147Nd and d iscuss plans for future measurements.\n\n[1] K. Kolos et al.\, "New approa ch to precisely measure gamma-ray intensities for long-lived fission produ cts\, with results for the decay of 95Zr" Nucl. Instrum. Methods A 1000 16 5240 (2021)\n[2] R. G. Helmer\, et. al.\, Nucl. Instrum. Methods A 511 360 (2003)\n\nThis work was supported under Contract DE-AC52-07NA27344 (LLNL) \, Office of Nuclear Physics Contract DE-AC02-06CH11357 (ANL)\, and DE-FG0 3-93ER40773 (Texas A&M).\n\nhttps://indico.frib.msu.edu/event/52/contribut ions/924/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/924/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of neutron-induced fission cross sections of U-235 and U-238 relative to n-p scattering at CSNS Back-n facility DTSTART:20220725T194500Z DTEND:20220725T195700Z DTSTAMP:20260420T153400Z UID:indico-contribution-763@indico.frib.msu.edu DESCRIPTION:Speakers: Ruirui Fan\, Shengda Tang\, Yiwei Yang\, Zhizhou Ren \, Rong Liu\, Wei Jiang\, Yonghao Chen\n\nNeutron-induced fission cross se ctions of U-235 and U-238 are ones of the most important nuclear data sinc e they are fundamental to nuclear energy. Fission cross sections of U-235 and U-238 have been evaluated as standard data up to 200 MeV and they are always used as references for other cross section measurements. However\, the experimental data in high neutron energy region are scarce. Especially above 30 MeV of neutron energy\, there are only a few measurements with o bvious discrepancies. Thus conducting a measurement in high energy region is quite necessary meaningful.\n\nThe back-streaming neutron facility (Bac k-n) at China Spallation Neutron Source (CSNS) is a newly built neutron be amline started commissioning since 2018. Back-n provides neutrons from 0.5 eV to 200 MeV with an achievable flux of 1.6×10^7 n/cm2/s at 55 meters away from the spallation target. It is therefore a good platform for nucle ar data measurement. We performed an experiment at Back-n for measuring th e fission cross sections of U-235 and U-238 relative to n-p elastic scatte ring. The U-235 and U-238 samples are sealed in an ionization chamber for measuring their fission reactions. A polythene (PE) foil and several recoi ling proton telescopes (RPT)\, consisting of silicon detectors and cesium iodide scintillators\, are setup in a vacuum chamber located at the downst ream of the fission chamber. The proton events are selected by the ΔE-E i dentification. The proton events produced via 12C(n\, p) reactions are obt ained by measuring a graphite sample with equivalent thickness\, which is used to correct the proton reaction rate measured with the PE sample. \n\n We will firstly introduce the CSNS Back-n facility. Then we will go to det ails of the data analysis of fission chamber and RPT. Finally the prelimin ary results of fission cross section of U-235 and U-235 from 10 to 100 MeV will be shown.\n\nhttps://indico.frib.msu.edu/event/52/contributions/763/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/763/ END:VEVENT BEGIN:VEVENT SUMMARY:The Stellar $^{72}\\mathrm{Ge}(n\,\\gamma)$ Cross Section for weak s-process: A First Measurement at n_TOF DTSTART:20220726T132400Z DTEND:20220726T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-779@indico.frib.msu.edu DESCRIPTION:Speakers: Claudia Lederer-Woods\, the n_TOF Collaboation\, Mir co Dietz\n\nThe slow neutron capture process (s-process) is responsible fo r producing about half of the elemental abundances heavier than iron in th e universe. Neutron capture cross sections on stable isotopes are a key nu clear physics input for s-process studies. The $^{72}\\mathrm{Ge}(n\,\\gam ma)$ Maxwellian-Averaged Cross Section (MACS) has an important influence o n production of isotopes between Ge and Zr in the weak s-process in massiv e stars [1] and so far only theoretical estimations are available [2].\n\n An experiment was carried out at the neutron time-of-flight facility n$\\_ $TOF [3] at CERN to measure the $^{72}\\mathrm{Ge}(n\,\\gamma)$ reaction f or the first time at stellar neutron energies. At n$\\_$TOF\, the neutron beam covers a large energy range (few meV to several GeV). The capture me asurement was performed using an enriched $^{72}\\mathrm{GeO}_2$ sample at a flight path length of $184\\\,$m\, which provided high neutron energy r esolution. The prompt gamma rays produced after neutron capture were detec ted with a set of liquid scintillation detectors (C$_6$D$_6$). The neutro n capture yield is derived from the counting spectra taking into account t he neutron flux and the gamma-ray detection efficiency using the Pulse Hei ght Weighting Technique [4].\n\nOver $70$ new neutron resonances were iden tified\, providing an improved resolved reaction cross section to calculat e experimental MACS values for the first time. Furthermore\, averaged re sonance parameters such as $\\langle \\Gamma_\\gamma \\rangle$ and $D_0$ w ere derived from the resonance data. In summary\, the experiment\, data an alysis and the new MACS results will be presented including their impact o n stellar nucleosynthesis\, which was investigated with $\\mathsf{mppnp}$ [5] using a $25$ solar mass model. \n\nReferences:\n[1] M. Pignatari et al .\, The Astroph. J. 33\, 1557-1577 (2010).\; [2] I. Dillmann et al.\, Nucl ear Data Sheets 120\, 171-174 (2014)\; (http://www.kadonis.org).\; [3] C. Guerrero et al.\, Eur. Phys. J. A 49\, 27 (2013).\; [4] U. Abbondanno et a l.\, Nucl. Instr. Meth. Phys. Res. A 521\, 454-467 (2004).\; [5] M. Pignat ari et al.\, The Astroph. J.\,Suppl. Ser. 225\, 24 (2016).\n\nhttps://indi co.frib.msu.edu/event/52/contributions/779/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/779/ END:VEVENT BEGIN:VEVENT SUMMARY:Direct measurements of $^2$H(α\, γ)$^6$Li cross section at Big B ang energies and the primordial lithium problem. DTSTART:20220726T133600Z DTEND:20220726T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-780@indico.frib.msu.edu DESCRIPTION:Speakers: Gianpiero Gervino\n\nThe correct prediction of the a bundances of the light nuclides produced during of Big Bang Nucleosynthesi s (BBN) is one of the main topics of modern cosmology. In order to precise ly determine BBN 6 Li production the cross-section of the nuclear reaction 2H(α\, γ)6Li must be directly measured within the astrophysical energy range of 30-400 keV. This measurement requires ultra low gamma-ray backgro und\, as obtained at LUNA\, the deep underground accelerator laboratory in stalled in the INFN Gran Sasso National Laboratory (LNGS)\, Italy. On the basis of the new experimental data\, the 2H(α\, γ)6Li thermonuclear reac tion rate has been derived. Our rate is even lower than previously reporte d\, thus increasing the discrepancybetween predicted Big Bang 6Li abundanc e and the amount of primordial 6Li inferred from observations. The primord ial 6Li/7Li isotopic abundance ratio has been consequently determined to b e (1.5 ± 0.3) × 10^(−5) within standard BBN theory. The much higher 6L i/7Li values reported for halo stars will likely require a non-standard ph ysics explanation\, as discussed in the literature.\n\nhttps://indico.frib .msu.edu/event/52/contributions/780/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/780/ END:VEVENT BEGIN:VEVENT SUMMARY:Stopping power of ions in matter: current status of experimental d ata and theoretical description DTSTART:20220726T134800Z DTEND:20220726T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-781@indico.frib.msu.edu DESCRIPTION:Speakers: Paraskevi Dimitriou\, Claudia Montanari\n\nStopping powers are relevant to a wide range of applications\, such as ion beam ana lysis\, deposition ranges\, ion implantation\, and radiation damage\, to n ame a few. Reliable values of stopping powers are also needed in isotope p roduction for medical applications\, in fusion technologies and detector d evelopment.\n\nIn this work we present the state of the art of the stoppin g power of ions in matter. We give an overview of our present knowledge\, and discuss the areas of strength and weaknesses and where data is lacking \, on the basis of the comprehensive experimental stopping power database of the International Atomic Energy Agency (IAEA) \\cite{iaea\,Montanari_SD B_2017}. \n\nThe field of stopping powers in matter is evolving with new t rends in materials of interest\, including oxides\, polymers\, and biologi cal targets \\cite{MATERNA20211\,Provenzano_2015}. An example for differe nt ions in Mylar is displayed in Figure \\ref{fig:mylar}. Our goal is to i dentify areas of interest and emerging data needs to meet the requirements of a continuously developing user community. \n\n\n\\begin{figure}[h]\n \\centering\n \\includegraphics[width=0.75\\textwidth]{Mylar_new.eps} \n \\caption{Stopping cross section of ions in Mylar compared with SRIM results \\cite{srim} (lines). Experimental data (symbols) are from\n \ \cite{iaea}\; black triangles are recent data for Cs fragments reported in \\cite{MATERNA20211} . }\n \\label{fig:mylar}\n\\end{figure}\n\n\\begi n{thebibliography}{00}\n\n\\bibitem{iaea} IAEA Stopping Database. Electron ic Stopping Power of Matter for Ions: Graphs\, Data\, Comments and Program s\, Available at https://wwwnds.iaea.org/stopping/ (last update: June 2021 ).\n\\bibitem{Montanari_SDB_2017} Montanari\, C. C.\; Dimitriou\, P. Nucle ar Instruments and Methods in Physics Research B: 408\,50–55 (2017).\n\\ bibitem{MATERNA20211} Materna T. et al\, Nuclear Instruments and Methods i n Physics Research B: 505\, 1–16 (2021).\n\\bibitem{Provenzano_2015} Pro venzano L. et al\, Journal of Physics: Conference Series 583\, 012047 (201 5).\n\\bibitem{srim} Ziegler\, J. SRIM. The Stopping and Range of Ions in Matter\, Available at http://www.srim.org/ (last update: 2013).\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/781/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/781/ END:VEVENT BEGIN:VEVENT SUMMARY:Activation Cross-Sections for Short-Lived Reaction Products on Haf nium Isotopes Induced by 1 – 20 MeV Neutrons DTSTART:20220726T165400Z DTEND:20220726T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-785@indico.frib.msu.edu DESCRIPTION:Speakers: Dimitar Tonev\, Angel Demerdjiev\, Andree Moens\, Ar jan Plompen\, Naohiro Otsuka\, Valentina Semkova\n\nNeutron-induced reacti on cross-sections on hafnium isotopes are important for research and nucle ar applications. Hafnium is considered as a constituent of the control ele ments and structural materials of nuclear reactors due to its high absorpt ion cross-section for thermal neutrons\, good mechanical properties and ex tremely high resistance to corrosion. Hafnium is an alloying element of lo w activation materials. The majority of the neutron-induced reactions on h afnium isotopes populate metastable states. Experimental cross-sections pr ovide a database for investigation of the sensitivity of nuclear models to level properties and decay schemes. The present study is an integral part of previous measurements on Hf\, W and Ta isotopes and contributes to the database for consistent nuclear modelling in this mass region. Activation cross-section data for short-lived reaction products on hafnium isotopes are very scarce. Results of cross-section measurements will be presented for the following reactions. 178Hf(n\,n’)178m1Hf\, 179Hf(n\,2n)178m1Hf\, 179Hf(n\,n’g)179m1Hf\, 180Hf(n\,2n)179m1Hf. The irradiations were carri ed out at the 7-MV Van de Graaff accelerator at EC-JRC\, Geel. Neutrons in the 1-3 MeV energy range were produced via the 3H(p\,n)3He reaction. Deut erium beam and a deuterium gas target were used to produce 5.6 and 6.5 MeV neutrons. For the production of quasi-monoenergetic neutrons between 15 a nd 20 MeV the 3H(d\,n)4He reactions was employed. Both samples with natura l composition and isotopic enrichment were employed to differentiate react ions leading to the same product. The half-lives of 178m1Hf and 179m1Hf ar e 4.0 s and 18.67 s\, respectively. An automated pneumatic transport syste m was used for sample transport from the irradiation to the measurement po sition. Cycles of irradiations and measurements were repeated to enhance c ounting statistics. Corrections were applied for the gamma-ray self-absorp tion\, secondary background neutrons\, coincidence summing correction\, in terference between reactions leading to the same reaction product. The stu died cross-sections were determined relative to 27Al(n\,alpha)24Na reactio n cross-section. Stacks with monitor foils were irradiated in separate irr adiations in order determine flux density distributions. The neutron flux for the short irradiations was determined by normalization to the count ra tes registered by a Long Counter. Cross-section data for the 178Hf(n\,n ’)178m1Hf reaction were obtained for the first time. For the other react ions the new result extended the range of the experimental data to higher energy.\n\nhttps://indico.frib.msu.edu/event/52/contributions/785/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/785/ END:VEVENT BEGIN:VEVENT SUMMARY:Transmission measurements of thick $^{\\rm nat}$Fe targets at nELB E DTSTART:20220726T171800Z DTEND:20220726T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-787@indico.frib.msu.edu DESCRIPTION:Speakers: Roland Beyer\, Daniel Bemmerer\, Stefan Müller\, Ko nrad Schmidt\, Sebastian Urlaß\, Toni Kögler\, Thomas Hensel\, Ronald Sc hwengner\, Steffen Turkat\, Katja Römer\, Roberto Capote\, Joseph Alexand er Bunker Turko\, Arnd Junghans\n\nSignificant shortcomings in the resolve d resonance region of all existing evaluations of iron isotopes have been identified from leakage neutron measurements to be related to inaccurate e lastic cross sections minima between 50 and 700 keV [1\,2]. Those regions are only sensitive to highly accurate transmission measurements through ve ry thick samples. The overestimation of the measured yield in leakage neu tron measurements reach 30-40% around 300 keV. Similar disagreements have been identified from 50 up to 700 keV. Therefore\, new transmission measur ements are needed to improve the description of the measured minima of the total cross section. The total cross section in this energy range is domi nated by elastic scattering\, as the capture cross section above 70 keV is only a correction of the order 10$^{-3}$. We have measured the neutron tr ansmission of 30\, 50 and 90 mm thick iron samples with high statistical a ccuracy at the nELBE neutron time-of-flight setup [3] at Helmholtz-Zentru m Dresden-Rossendorf in 16.5 days of beam time. The neutron transmission w as measured using a plastic scintillator in the energy range above 100 ke V with a short flight path of 868 cm. The new transmission and total cross section data of iron can be used to improve the elastic scattering cross section minima in the INDEN-III (structural materials) evaluation of IAEA [4]. This project has received funding from the Euratom research and tra ining programme 2014-2018 under grant agreement No 847594 (ARIEL). \n\n[ 1] B.Jansky et al.\, JEFFDOC-1918\, NEA (2018) \n[2] M. Schulc et al.\, Ap p. Rad. and Isotopes 130 (2017) 224\n[3] A.R. Junghans et al.\, EPJ Web o f Conferences 239 (2020) 01006\n[4] International Nuclear Data Evaluation Network on the Evaluated Nuclear Data of the Structural Materials\, IAEA V ienna\, 2018 INDEN-III\n[INDEN-III webpage][1]\n\n\n [1]: https://www-nd s.iaea.org/index-meeting-crp/CM-INDEN-III-2018/\n\nhttps://indico.frib.msu .edu/event/52/contributions/787/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/787/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the $^{233}$U(n\,$\\gamma$) cross section at LANSCE DTSTART:20220726T191500Z DTEND:20220726T192700Z DTSTAMP:20260420T153400Z UID:indico-contribution-795@indico.frib.msu.edu DESCRIPTION:Speakers: Gencho Rusev\, Aaron Couture\, Esther Leal Cidoncha\ n\nThe $^{233}$U plays an important role in the Th-U fuel cycle\, that has been proposed as an alternative to the U-Pu fuel cycle due to its reduced amount of transuranium elements. The available experimental $^{233}$U(n\, $\\gamma$) cross section data in the literature are scarce and were measur ed decades ago [1-3]. In 2008\, the $^{233}$U(n\,$\\gamma$) cross section was investigated at LANL using the DANCE detector combined with a PPAC\, h owever the statistics in the keV regime were inadequate for a reliable ext raction of the cross section at 100 keV. An accurate measurement of the $^ {233}$U(n\,$\\gamma$) cross section is required by the NCSP (National Crit ically Safety Program) to complete the neutron-induced cross section data\ , and also\, as reported by the ORNL\, a new evaluation with revised (reno rmalized) fission cross section is needed on $^{233}$U.\n\nhttps://indico. frib.msu.edu/event/52/contributions/795/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/795/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of Photoneutron Yields Using the RPI LINAC and Assessm ent of Evaluated Photoneutron Data for Tantalum and Beryllium DTSTART:20220726T173000Z DTEND:20220726T174200Z DTSTAMP:20260420T153400Z UID:indico-contribution-788@indico.frib.msu.edu DESCRIPTION:Speakers: Devin Barry\, Sheldon Landsberger\, Yaron Danon\, Ma tthew Gray\, Adam Daskalakis\, Peter Brand\, Robert Block\, Michael Bretti \, Larry Krusieski\, Azeddine Kerdoun\, Michael Rapp\, Ezekiel Blain\, Bri an Epping\n\nA new experiment configuration was designed\, developed and i mplemented to measure photoneutron yields using the Rensselaer Polytechnic Institute (RPI) electron linear accelerator (LINAC) at the RPI Gaerttner LINAC Center. The new experiment configuration includes a new target asse mbly that converts the LINAC electron beam into a high energy bremsstrahlu ng photon flux incident upon a sample material of interest. The photons e xcite nuclei in the sample of interest\, which can subsequently emit neutr ons (photoneutrons). The photoneutrons emitted in the direction of the de tector system (90 degree orientation from the initial electron beam) trave l through a series of collimated vacuum pipes before reaching a pair of pr oton-recoil (EJ-301) high energy neutron detectors. The signals generated by the neutron detectors are processed using a digital data acquisition s ystem and subsequently analyzed to determine the energy-dependent photoneu tron yield from the sample of interest.\n\nThe new experiment configuratio n was used to perform proof-of-concept experiments to measure the photoneu tron yields from samples of tantalum and beryllium. The measured results were then compared against the results from Monte Carlo simulations of the detailed experiment configurations to perform preliminary assessments of evaluated photoneutron data libraries. For example\, comparing the measur ed photoneutron spectrum from a tantalum sample with a Monte Carlo simulat ion using the ENDF/B-8.0 evaluation showed overall good agreement in the e nergy range from 0.5-20 MeV\; however\, differences observed in the range of 5-9 MeV warrant further investigation. Lessons learned and potential u pgrades were identified and documented to support improving the photoneutr on measurement capability for future experiments and allow more rigorous v alidation assessments of evaluated photoneutron data libraries.\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/788/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/788/ END:VEVENT BEGIN:VEVENT SUMMARY:Thermal cross section measurements at the RPI LINAC DTSTART:20220726T174200Z DTEND:20220726T175400Z DTSTAMP:20260420T153400Z UID:indico-contribution-789@indico.frib.msu.edu DESCRIPTION:Speakers: Kemal Ramic (Oak Ridge National Laboratory)\, Michae l Zerkle (NNL)\, Timothy Trumbull (NNL)\, Jesse Holmes (NNL)\, Adam Ney\, Benjamin Wang\, Goran Arbanas\, Michael Rapp\, Sukhjinder Singh\, Katelyn Cook\, Peter Brain\, Chris Chapman\, Xunxiang Hu\, Jesse Brown\, Yaron Dan on\, Dominik Fritz\n\nRecently\, a cold moderator was designed and develop ed for use at the RPI LINAC. This cold moderator proved to easily and safe ly couple to an existing neutron producing target\, while enhancing neutro n flux below 0.02 eV by cooling polyethylene down to 29 K. This cold moder ator capability allowed for significantly improved counting statistics bel ow 0.02 eV not previously possible due to a poor signal to background rati o. Additionally\, testing was performed to characterize the energy resolut ion of the new cold moderator system and found the system easily capable o f resolving resonances in Ta-181 at 4 and 10 eV\, while also clearly resol ving the Bragg edges found in Be metal below 0.01 eV. Following the desig n and development of a cold polyethylene moderator\, a series of thermal t otal cross section measurements were performed for polyethylene\, polystyr ene\, Plexiglas and yttrium hydride in the thermal region. These measureme nts serve to help validate thermal scattering law (TSL) evaluations in the 0.0006 – 20 eV energy range. For polyethylene and polystyrene\, two set s of experiments were performed – one with the Enhanced Thermal Target ( ETT) and another with the ETT plus the new cold moderator capability (ETTC ). The yttrium hydride and Plexiglas measurements were only performed with the ETTC. The measurements for polyethylene help to validate the data pro cessing methodology when using the ETTC\, while extending the measured ran ge of polyethylene down to 0.0007 eV. Two different Plexiglas\, Plexiglas G and Plexiglas G-UVT\, and two different concentrations of yttrium hydrid e\, H/Y = 1.85 and 1.68\, were measured. Overall\, all materials had gener ally good agreement with their ENDF/B-VIII.0 TSL evaluations\, though some discrepancies were noticed. In the case of the yttrium hydride\, the high energy oscillations in the hydrogen cross section and the low energy Brag g edges in the yttrium cross section were clearly seen. These measurements represent the first total cross section measurements that encompass the e ntire thermal region from 0.0006 – 3 eV for polystyrene and yttrium hydr ide.\n\nhttps://indico.frib.msu.edu/event/52/contributions/789/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/789/ END:VEVENT BEGIN:VEVENT SUMMARY:Indirect measurements of neutron-induced reaction cross-sections a t storage rings DTSTART:20220726T181500Z DTEND:20220726T183900Z DTSTAMP:20260420T153400Z UID:indico-contribution-790@indico.frib.msu.edu DESCRIPTION:Speakers: Manfred Grieser\, Michele Sguazzin\, Olivier Roig\, Bertrand Thomas\, Vincent Meot\, Jacobus Swartz\, Yury Litvinov\, Rene Rei farth\, Klaus Blaum\, Jerome Pibernat\, Jan Glorius\, Beatriz Jurado\n\nOb taining reliable cross sections for neutron-induced reactions on unstable nuclei is a highly important task and a major challenge. These data are es sential for understanding the synthesis of heavy elements in stars and for applications in nuclear technology. However\, their measurement is very c omplicated as both projectile and target are radioactive. The NECTAR (Nucl Ear reaCTions At storage Rings) project aims to circumvent these problems by using the surrogate reaction method in inverse kinematics\, where the n ucleus formed in the neutron-induced reaction of interest is produced by a reaction (typically a transfer or an inelastic-scattering reaction) invol ving a radioactive heavy-ion beam and a stable\, light target nucleus. The probabilities as a function of the compound-nucleus excitation energy for gamma-ray emission\, neutron emission and fission\, which can be measured with the surrogate reaction\, are particularly useful to constrain model parameters and to inform more accurate predictions of neutron-induced reac tion cross sections [1]. \n\nYet\, the full development of the surrogate method is hampered by the numerous long-standing target issues. The object ive of the NECTAR project is to solve these issues by combining surrogate reactions with the unique and largely unexplored possibilities at heavy-io n storage rings. In a storage ring heavy radioactive ions revolve at high frequency passing repeatedly through an electron cooler\, which will great ly improve the beam quality and restore it after each passage of the beam through the internal gas-jet serving as ultra-thin\, windowless target. Th is way\, excitation energy and decay probabilities can be measured with un rivaled accuracy.\n\nIn this contribution\, we will present the conceptual idea of the setup\, which will be developed within NECTAR to measure for the first time simultaneously the fission\, neutron and gamma-ray emission probabilities at the storage rings of the GSI/FAIR facility. We will also discuss the developments that are being carried out towards these measure ments. In particular\, we will present the first results of a proof of pri nciple experiment\, which will be conducted in June 2022 at the ESR storag e ring of GSI/FAIR.\n\n [1] R. Pérez Sánchez\, B. Jurado et al.\, Phys. Rev. Lett. 125 (2020) 122502\n\n*Acknowledgement:* This work has received funding from the European Research Council (ERC) under the European Union ’s Horizon 2020 research and innovation programme (ERC-Advanced grant NE CTAR\, grant agreement No 884715).\n\nhttps://indico.frib.msu.edu/event/52 /contributions/790/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/790/ END:VEVENT BEGIN:VEVENT SUMMARY:Properties of compound nucleus decay width predicted by Gaussian O rthogonal Ensemble nuclear reaction model DTSTART:20220728T153800Z DTEND:20220728T155000Z DTSTAMP:20260420T153400Z UID:indico-contribution-969@indico.frib.msu.edu DESCRIPTION:Speakers: Toshihiko Kawano (Los Alamos National Laboratory)\n\ nFluctuation in the observed resonance decay widths is often characterized by the Porter-Thomas distribution\, or the chi-square distribution. Compo und nucleus reaction modelings\, in which the Gaussian Orthogonal Ensemble (GOE) is involved as a propagator\, have been successfully applied to stu dy the properties of fluctuation in the S-matrix (or the cross section). I n the GOE models\, the fluctuation is understood as a decay amplitude in t he spectral decomposition expression\, $\\gamma_\\lambda \\gamma_\\lambda^ \\dagger / (E - E_\\lambda$)\, where $E_\\lambda$ is the eigenvalue of the GOE Hamiltonian. Such an expression can be explicitly written in terms of the S and K matrices\, where the definition of the decay width is slightl y different. We study the compound nucleus reaction by employing the GOE m odel that allows us to explore the wide model parameter space\, and demons trate how these matrix representations predict the distributions of compou nd nucleus decay width.\n\nhttps://indico.frib.msu.edu/event/52/contributi ons/969/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/969/ END:VEVENT BEGIN:VEVENT SUMMARY:Time-of-flight measurements of MINERVE samples containing fission products and neutron absorbing isotopes DTSTART:20220726T183900Z DTEND:20220726T185100Z DTSTAMP:20260420T153400Z UID:indico-contribution-792@indico.frib.msu.edu DESCRIPTION:Speakers: Benoit Geslot\, Carlos Paradela\, Stefan Kopecky\, P ierre Leconte\, Peter Schillebeeckx\, Mathilde Pottier\, Adrien Gruel\, Gi lles Noguere\n\nThe zero-power reactor MINERVE (CEA Cadarache) was designe d to perform reactivity worth measurements by the oscillation technique. T he various experimental programs\, undertaken for the last thirty years\, involved cylindrical samples with a diameter of about 1 cm and a height ra nging from a few cm to 10 cm. Most of the samples are composed of UO2 pell ets with a given fission product\, actinide or neutron absorbing isotope i n a double-sealed Zry-4 container. \n\nAn experimental program started in 2015 in collaboration with the Joint Research Centre of Geel to study the MINERVE samples at the time-of-flight facility GELINA by the neutron trans mission technique. The two main objectives consist of checking both the co mposition of the MINERVE samples provided by the manufacturer and the qual ity of the resonance parameters recommended in the evaluated neutron data library JEFF-3.3 [1]. The pioneer experiments on MINERVE samples containin g 107Ag and 109Ag revealed a substantial Tungsten contamination that was n ot reported by the manufacturer [2]. Such a Tungsten contamination is rela ted to the manufacturing process of the sample pellets by powder compactin g. The observed Tungsten contaminations lead to non-negligible increases o f the C/E ratios up to a few percent. A second experimental campaign on MI NERVE samples containing 99Tc provided useful insight on the quality of th e 99Tc resonance parameters measured at the GELINA facility at the end of the 90s [3].\n\nThe ongoing program continuing through 2022 will deliver d ata for samarium (natural\, 147\, 149\, 152)\, neodymium (natural\,143\,14 5)\, gadolinium (natural\, 155)\, europium (151\, 153)\, rhodium (103)\, C esium (133)\, hafnium (180)\, dysprosium (160\, 161\, 162\, 163\, 164) and erbium (168\, 170). The present work will focus on the data analysis tech nique developed for long cylindrical samples with a diameter smaller than the neutron beam\, and on the grain size distribution model implemented in the resonance shape analysis REFIT and CONRAD. \n\nReferences\n[1] A. J. M. Plompen et al\, The joint evaluated fission and fusion nuclear data lib rary JEFF-3.3\, Eur. Phys. J. A (2020) 56:181 \n[2] L. Salamon et al.\, Ne utron resonance transmission analysis of cylindrical samples used for reac tivity worth measurements\, J. Radioanal Nucl. Chem. https://doi.org/10.10 07/s10967-019-06611-9 (2019)\n[3] G. Noguere et al.\, Average neutron cros s sections of Tc\, Phys. Rev. C 102\, 015807 (2020)\n\nhttps://indico.frib .msu.edu/event/52/contributions/792/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/792/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the $^{235}$U(n\,f) cross section relative to the $ ^{10}$B(n\,α) reaction with Micromegas detectors at the CERN n_TOF facili ty: first results DTSTART:20220726T185100Z DTEND:20220726T190300Z DTSTAMP:20260420T153400Z UID:indico-contribution-793@indico.frib.msu.edu DESCRIPTION:Speakers: Michail Kokkoris\, Athanasios Stamatopoulos\, Roza V lastou\, Peter Schillebeeckx\, Zinovia Eleme\, Enrico Chiaveri\, Andrea Ts inganis\, Laurent Tassan-Got\, Nicola Colonna\, Daniela Macina\, Maria Dia kaki\, Nikolaos Patronis\, Jan Heyse\, the n_TOF Collaboration\, Veatriki Michalopoulou\n\nNeutron induced reaction cross section measurements are o ften performed relative to a neutron cross-section standard. Thus\, the ac curacy of the neutron standards determines the accuracy of the neutron cro ss section measurements. The $^{235}$U(n\,f) cross section is widely used as reference reaction\, while it is considered as standard at 0.0253 eV (t hermal energy)\, between 7.8 and 11 eV and from 0.15 to 200 MeV [1].\n\n Moreover\, it is a very important reaction for neutronic calculations of n uclear reactors and has been the subject of many experimental and theoreti cal works. Nevertheless\, certain issues with the cross section of this re action have been pointed out\, especially in the energy region below 100 k eV (e.g. [2] - [4] etc). \n\nFor this reason\, high accuracy and high reso lution cross section data for the $^{235}$U(n\,f) reaction are needed to i mprove the accuracy of this reaction cross section and to extend the energ y range of the Resolved Resonances Region above 2.5 keV.\nIn this context\ , the $^{235}$U(n\,f) reaction cross has been measured relative to the sta ndard $^{10}$B(n\,α) cross section within the n_TOF collaboration\, with an independent experimental setup from the previous measurement of Amaducc i et al. [4] in n_TOF. The measurement was carried out in experimental are a EAR-1 of the n_TOF facility at CERN\, with the aim to cover the widest e nergy range possible. The high purity targets were produced at JRC-Geel in Belgium\, while the experimental setup was based on Micromegas detectors. \nThe preliminary results from this work will be presented and discussed.\ n\n[1] A.D.Carlson et al.\, Nucl. Data Sheets **148** (2018) 143\n[2] M. B arbagallo et al.\, Eur. Phys. J. A **49** (2013) 156 \n[3] M. Jandel et al .\, Phys. Rev. Lett. **109** (2012) 202506 \n[4] S. Amaducci et al.\, Eur. Phys. J. A **55** (2019) 120\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/793/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/793/ END:VEVENT BEGIN:VEVENT SUMMARY:Design and Simulation of a Next-Generation Dual n-gamma Detector A rray at Los Alamos National Laboratory DTSTART:20220726T190300Z DTEND:20220726T191500Z DTSTAMP:20260420T153400Z UID:indico-contribution-794@indico.frib.msu.edu DESCRIPTION:Speakers: John O'Donnell\, Keegan Kelly\, Matthew Devlin\, Eam es Bennett\n\nMeasurements of neutron elastic scattering and angular distr ibutions remain one of the largest uncertainties in simulations of fission -driven nuclear systems. Current experimental techniques are limited by is sues arising from measuring only neutrons or gammas or\, in the case where both particles are measured\, the relatively small number of angles curre nt dual n-gamma detectors are capable of covering. Next-generation elpasol ite detectors offer near-perfect n-gamma pulse shape discrimination across a wide array of energies and the availability of these detectors in suffi cient quantities make the construction of a large\, highly-segmented detec tor array a possibility for the first time. Preliminary studies have isola ted CLYC detectors as the ideal candidate for use in measuring neutron ela stic scattering. We describe the mechanical design and simulation of the C orrelated gamma-neutron Array for sCattering (CoGNAC) utilizing these dete ctors currently under development at Los Alamos National Laboratory. Addit ionally\, we discuss the results of an initial experimental campaign on $^ 9$Be\, $^{27}$Al\, and $^{56}$Fe utilizing a partially completed CoGNAC in conjunction with Chi-Nu’s existing array of 54 liquid scintillator dete ctors.\n\nhttps://indico.frib.msu.edu/event/52/contributions/794/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/794/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron capture and total cross-section measurements on $^{94\,95\ ,96}$Mo at n_TOF and GELINA DTSTART:20220726T183900Z DTEND:20220726T185100Z DTSTAMP:20260420T153400Z UID:indico-contribution-820@indico.frib.msu.edu DESCRIPTION:Speakers: Alberto Mengoni\, Sergio Cristallo\, Christian Massi mi\, Peter Schillebeeckx\, Andree Moens\, Carlos Paradela Dobarro\, Stefan Kopecky\, Goedele Sibbens\, the n_TOF Collaboration\, Riccardo Mucciola\n \nCross-sections for neutron-induced interactions with molybdenum\, in par ticular for the neutron capture reaction\, play an important role in vario us fields ranging from nuclear astrophysics to safety assessment of conven tional nuclear power plants and the development of innovative technologies . It is found as a pollutant in pre-solar silicon carbide grains and it ha s a crucial role in stellar nucleosynthesis in Asymptotic Giant Branch (AG B) stars[1]. During reactor operation molybdenum is produced as a fission product. Moreover\, the use of molybdenum for the production of Accident T olerant Fuel (ATF) is under study [2]. It is a promising candidate for new generation research reactors using UMo alloys with Low Enriched Uranium (LEU)[3]. This shows the importance of an accurate knowledge of the total and capture cross-section for molybdenum isotopes.\n\nExperimental data in the literature for the capture cross-section of Mo isotopes suffer from l arge uncertainties. This is also reflected in the large uncertainties of t he cross-sections recommended in the ENDF/B-VIII.0 library[4]. Below 1 eV the relative uncertainty of the capture cross-section is above 18% for $^{ 94}$Mo and around 40% for $^{96}$Mo\, while above 2 keV the uncertainties are in the order of 10-20% for $^{94\,95\,96}$Mo. One of the reasons for these large uncertainties is related to the absence of transmission data f or enriched samples.\n \nIn this contribution results of accurate transmis sion and capture cross-section measurements using natural Mo samples and s amples enriched in $^{94}$Mo\, $^{95}$Mo and $^{96}$Mo are presented. The data cover an energy region from thermal energy (0.025 eV) up to hundreds of keV. The capture measurements are performed at the n_TOF facility at C ERN (CH) and the GELINA facility at JRC-Geel (BE). The transmission measur ements are performed at GELINA. The experimental data\, i.e. transmissions and capture yields\, will be delivered to the EXFOR data library and will be used to improve the evaluated cross-section data for neutron interacti ons with $^{94\,95\,96}$Mo in the resolved and unresolved resonance region . \n\nREFERENCES\n[1] N.Liu\, T.Stephan\, S.Cristallo et al.\, Astrophysic al Journal\, 881\, 28 (2019).\n[2] B. Cheng\, Y.-J. Kim\, P. Chou\, Nuclea r engineering and Technology\, 48\, 16-25 (2016).\n[3] P. Herve et al.\, E PJ Nuclear Sciences & Technologies\, 4\, 49 (2018).\n[4] D.A. Brownet et al.\, Nuclear Data Sheets\, 148\, 1 (2018).\n\nhttps://indico.frib.msu.edu /event/52/contributions/820/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/820/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of neutron capture cross section and capture gamma-ray spectrum of Te-128 in keV-neutron energy region DTSTART:20220726T190300Z DTEND:20220726T191500Z DTSTAMP:20260420T153400Z UID:indico-contribution-823@indico.frib.msu.edu DESCRIPTION:Speakers: Masayuki Igashira\, Michal Valasik\, Tatsuya Katabuc hi\n\nTellurium isotopes are produced in nuclear reactors as fission produ cts. Evaluation of neutron nuclear data of Tellurium isotopes was made rec ently [1]. On the other hand\, $^{128}$Te is one of the candidate nuclides for neutrino-less double beta decay searches. Neutron-induced reactions o f $^{128}$Te are important to evaluate background in measurement [2]. Howe ver\, experimental data of the neutron capture cross section of $^{128}$Te at neutron energies below 1 MeV are old and have large uncertainties. Thu s\, in this work\, new measurements were carried out to determine the capt ure cross section of $^{128}$Te using the time-of-flight (TOF) method in t he keV energy region. Experiments were performed at the Laboratory for Zer o Carbon Energy at the Tokyo Institute of Technology. Incident neutrons we re generated through the $^7$Li(p\,n)$^7$Be reaction by a pulsed proton be am from a Pelletron accelerator bombarding a lithium target. Experiments w ere carried out in the two different neutron energy regions: 15 – 100 ke V and around 550 keV. The incident neutron energy spectrum was measured by the TOF method. Capture gamma-rays from the sample were detected with an anti-Compton NaI(Tl) spectrometer in the TOF experiments. The capture cros s sections were obtained from the pulse height spectra by the pulse-height weighting technique. A comparison of the present results with past experi mental data and evaluated cross sections was made. Gamma-ray spectra by un folding the pulse height spectra with the detector response function were also derived.\n\nReferences\n 1. K. Shibata\, Journal of Nuclear Science a nd Technology\, 52\, 490-502 (2015).\n 2. W. Tornow et al.\, EPJ web of Co nferences\, 146\, 09013 (2017).\n\nhttps://indico.frib.msu.edu/event/52/co ntributions/823/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/823/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron Capture Cross Section Measurement and Resonance Analysis o f Pd-107 Using ANNRI at MLF/J-PARC DTSTART:20220726T192700Z DTEND:20220726T193900Z DTSTAMP:20260420T153400Z UID:indico-contribution-825@indico.frib.msu.edu DESCRIPTION:Speakers: Hideto Nakano\, Tatsuya Katabuchi\, Gerard Rovira Le veroni\, Yu Kodama\, Masayuki Igashira\, Taihei Matsuhashi\, Kazushi Terad o\, Brian Hales\n\nThe long-term accumulation of Long-Lived Fission Produc ts (LLFPs) in nuclear waste has been a significant issue in nuclear indust ry due to their long half-life. The nuclear transmutation of LLFPs into sh ort-lived or stable nuclides is expected to contribute reducing the curren t amount of high-level radioactive waste. Highly accurate nuclear data for the neutron-induced nuclear reactions are necessary in order to design LL FPs nuclear transmutation systems. \n\nPalladium-107 (half life: 6.5×10$^ {6}$ y) is one of the important LLFPs\, and accurate data for the neutron capture cross section are needed for the study on LLFPs transmutation syst ems. Nevertheless\, only a few experiments to measure the neutron capture cross section of Pd-107 have been performed. The neutron energy regions of most of the measurements are limited. A new measurements with a wide neut ron energy range from the thermal to keV energies is needed to improve the neutron capture cross section of $^{107}$Pd.\n\nIn the present work\, the neutron capture cross section measurements were carried out using the Acc urate Neutron Nucleus Reaction Measurement Instrument (ANNRI) at the Mater ials and Life Science Facility (MLF) of the Japan Proton Accelerator Resea rch Complex (J-PARC). A high intensity pulsed neutron beam from Japan Spal lation Neutron Source at the MLF using the 3 GeV proton beam was utilized. NaI(Tl) detectors of ANNRI were used for capture measurements. The time-o f-flight (TOF) method was employed to determine the incident neutron energ y. Two-dimensional data\, TOF and pulse-height (PH)\, were acquired and th e data were analyzed based on a PH weighting technique. Resonance paramete rs were derived from resonance analysis using the REFIT code.\n\nhttps://i ndico.frib.msu.edu/event/52/contributions/825/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/825/ END:VEVENT BEGIN:VEVENT SUMMARY:The past and the future of the GAINS spectrometer @ GELINA DTSTART:20220727T130000Z DTEND:20220727T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-796@indico.frib.msu.edu DESCRIPTION:Speakers: Greg Henning\, Carlos Paradela Dobarrro\, Myroslav K avatsyuk\, François Claeys\, Arjan Plompen\, Philippe Dessagne\, Marian B oromiza\, Maëlle Kerveno\, Andreea Oprea\, Markus Nyman\, Catalin Borcea\ , Liviu Stoica\, Nasser Kalantar-Nayestanaki\, Alexandru Negret\, Adina Ol acel (Horia Hulubei National Institute for R&D in Physics and Nuclear Engi neering (IFIN-HH))\n\nThe GAINS spectrometer operating at the GELINA neutr on source (EC-JRC-Geel) is one of the best known setups within the nuclear data community. It provides reliable\, high resolution $\\gamma$-producti on cross-section data of importance both for the fundamental nuclear physi cs research and its many applications. The story of this spectrometer star ted around 2000 with just 2 large volume HPGe detectors and a Fission Cham ber but\, during the following years\, it extended to 12 detectors allowin g our group to perform numerous measurements ($^{52}$Cr\, $^{208}$Pb\, $^{ 23}$Na\, $^{28}$Si\, $^{76}$Ge\, $^{56}$Fe\, $^{24}$Mg\, $^{206}$Pb\, $^{4 6-50}$Ti\, $^{7}$Li\, $^{57}$Fe\, $^{54}$Fe\, $^{16}$O\, $^{58\,60\,61\,62 \,64}$Ni\, $^{40}$Ca) [1-17]. The extracted data were consistently used\, among others\, in several evaluations and also for establishing a new inel astic $\\gamma$-production reference cross section. This talk presents an overview of the work done within the JRC – IPHC – IFIN-HH collaboratio n at GELINA (which recently extended to include also ESRIG and University of Helsinki)\, focusing on the achievements of GAINS. We will not only des cribe past work but we will also emphasize the future plans: upcoming expe riments ($^{14}$N\, $^{56}$Fe\, $^{35-37}$Cl) and moving to a new digital acquisition system (both hardware and software upgrades) and others.\n\n$^ {1}$L. C. Mihailescu\, PhD Thesis\, University of Bucharest (2006).\n$^{2} $L.C. Mihailescu\, et al.\, Nucl. Phys. A786\, 1 (2007).\n$^{3}$L.C. Mihai lescu\, et al.\, Nucl. Phys. A811\,1 (2008).\n$^{4}$C. Rouki\, et al.\, Nu cl. Instrum. Meth. Phys. Res. A672\, 82 (2012).\n$^{5}$A. Negret\, et al.\ , Phys. Rev. C88\, 034604 (2013).\n$^{6}$C. Rouki\, et al.\, Phys. Rev. C8 8\, 054613 (2013).\n$^{7}$A. Negret\, et al.\, Phys. Rev. C90\, 034602 (20 14).\n$^{8}$A. Olacel\, et al.\, Phys. Rev. C90\, 034603 (2014).\n$^{9}$A. Negret\, et al.\, Phys. Rev. C91\, 064618 (2015).\n$^{10}$A. Olacel\, PhD Thesis\, University of Bucharest (2016).\n$^{11}$A. Olacel\, et al.\, Phys . Rev. C96\, 014621 (2017).\n$^{12}$M. Nyman\, et al.\, Phys. Rev. C93\, 0 24610 (2016).\n$^{13}$A. Negret\, et al.\, Phys. Rev. C96\, 024620 (2017). \n$^{14}$A. Olacel\, et al.\, Eur. Phys. Journal A54 (2018).\n$^{15}$M. Bo romiza\, PhDThesis\, University of Bucharest (2018).\n$^{16}$M. Boromiza\, et al.\, Phys. Rev. C 101\, 024604 (2020).\n$^{17}$A. Olacel et al.\, Art icle in preparation (2021).\n\nhttps://indico.frib.msu.edu/event/52/contri butions/796/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/796/ END:VEVENT BEGIN:VEVENT SUMMARY:Quantum Computing for Nuclear Systems DTSTART:20220728T130000Z DTEND:20220728T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-960@indico.frib.msu.edu DESCRIPTION:Speakers: Joe Carlson (Los Alamos National Laboratory)\, Aless andro Baroni (Los Alamos National Laboratory)\, Ionel Stetcu (Los Alamos N ational Laboratory)\n\nIt is reasonable to believe that in the not-too-dis tant future\, quantum computing will revolutionize our ability to model an d understand atomic nuclei and their interactions\, and will find applicat ions well beyond basic research. Advances in technologies that allow the p roduction of quantum hardware with a larger number of qubits and significa ntly smaller error rates are still a few years away\, time that can be spe nt on developing and testing algorithms that can be used in treating the c omplicated nuclear many-body problem. Existing algorithms are non-trivial\ , and testing for even relatively small problems requires the use of inter actions that mimic the complexity of inter-nucleon interactions. In this c ontribution\, we will explore different algorithms for preparing ground st ates (e.g.\, unitary coupled cluster approach\, widely used in quantum che mistry) and for determining the energy spectrum or transition strengths. T he testing ground will be the phenomenological shell model\, where only a small number of particles are active\, but the interaction is complicated enough\, with exact solutions readily available. We will use both simulato rs on classical computers and available quantum hardware. The main goal wi ll be to understand how current algorithms work\, how one can improve them \, and how to translate them to realistic approaches for the ab initio nuc lear problem\, like no-core shell model or lattice implementations. Additi onally\, we will investigate the required quantum hardware resources neede d to solve realistic nuclear structure and reaction problems.\nLA-UR-21-28 550\n\nhttps://indico.frib.msu.edu/event/52/contributions/960/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/960/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear data completion for analog simulations DTSTART:20220728T190700Z DTEND:20220728T191900Z DTSTAMP:20260420T153400Z UID:indico-contribution-981@indico.frib.msu.edu DESCRIPTION:Speakers: Camilo Cordero Ramirez (CEA)\n\nNuclear data in the different libraries (ENDF/B\, JEFF\, JENDL\, CENDL) for the description of the outgoing particles are very often expressed as averaged distributions . This is the case\, for example\, of the (n\,2n) reaction\, for which we find only one energy distribution with a multiplicity equal to 2. The situ ation is quite similar for neutron capture (n\,g) with an average photon n umber and an average energy spectrum.\nSimulation and modeling of recent e xperiments such as STEREO require a better knowledge of the emitted partic les with possible coincident events that are not accessible with the curre nt data.\nThis work focuses on completing the currently available data to satisfy these new requirements.\nFirstly\, we determined the gamma-decay c ascades of excited states reached by inelastic scattering when the photon production data is averaged in MF6 sections. Then\, we wrote MF12 sections that allow us to perfectly reconstruct the correlations between the gamma rays of the cascade\, and verified that both types of data yielded the sa me gamma production spectrum.\nSecondly\, we treated neutron capture\, whi ch in most cases presents a combination of a discrete and a continuous pho ton spectra. For this\, we used RIPL-3\, ENSDF\, JEFF data with spin conse rvation assumptions to reconstruct gamma cascades for this reaction. We ca n compare this cascade with those obtained with PHITS in terms of gamma mu ltiplicity and energy conservation. It was observed that the presence of a rotational band in 156 Gd\, when studying 155 Gd neutron capture\, result s in a cascade of around 10 gammas as frequent as the cascades of 4 gammas \, which are the physically allowed ones\, and it was reported to the PHIT S team. The multiplicity distribution was tested in other nuclei in a simi lar mass range and no anomalies were found. We thus obtain multiplicities that are in relatively good agreement with the multiplicity data in the ev aluation files. It was also found that some discrepancies between PHITS da ta and ENSDF introduce biases in the simulation of (n\,g) reactions.\nThe third reaction of interest is the (n\,2n) reaction. For this\, we treat ne utron emission by sampling the distributions given in the evaluations and taking into account kinematic limitations: correlated emission spectra can thus be produced.\nThese new models are tested in the Monte Carlo codes T RIPOLI-4® and PATMOS developed at CEA.\nThis work is carried out in the f ramework of a PhD thesis.\n\nhttps://indico.frib.msu.edu/event/52/contribu tions/981/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/981/ END:VEVENT BEGIN:VEVENT SUMMARY:An assessment of neutron resonance data for mid-mass isotopes DTSTART:20220727T140000Z DTEND:20220727T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-925@indico.frib.msu.edu DESCRIPTION:Speakers: James Benstead (AWE)\n\nA survey has been conducted of the resonance data available in the major evaluated libraries for a ran ge of mid-mass isotopes. Although many isotopes have data derived from exp erimental measurements and rigorous analyses\, the data for some others\, particularly for isotopes that are unstable\, are purely theoretically gen erated\, e.g. via the use of the TARES code.\nA subsequent project has dev eloped a suite of automated tools to rapidly inspect the resonance data av ailable for a specified isotope. These tools calculate a range of values a nd distributions for the available data (e.g. cumulative number of resonan ces versus neutron energy) and use a comparison against expected theoretic al values (e.g. a Porter-Thomas distribution) to suggest their physical va lidity or otherwise. \nThe motivation of this study\, the automated tools developed\, and results for a number of isotopes\, will be presented.\n\n* Corresponding author: james.benstead@awe.co.uk\n\nUK Ministry of Defence © Crown Owned Copyright 2021/AWE\n\nhttps://indico.frib.msu.edu/event/52/ contributions/925/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/925/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear reaction modeling for neutron inelastic scattering process DTSTART:20220727T132400Z DTEND:20220727T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-920@indico.frib.msu.edu DESCRIPTION:Speakers: Osamu Iwamoto\, Marc Dupuis\, Roberto Capote\, Toshi hiko Kawano (Los Alamos National Laboratory)\, Maelle Kerveno\n\nNeutron i nelastic scattering is one of the major nucleon-nucleus interactions in th e fast energy range\, and its cross section constantly increases above the threshold energy of the first excited state up to a few MeV. Since the in elastic scattering process changes the momentum of interacting neutrons an d produces characteristic gamma-rays\, high quality nuclear data for this process are important in many applications. Experimental information avail able for evaluating the inelastic scattering cross sections is rather limi ted\, e.g.\, the neutron inelastic scattering for a few isolated excited s tates and/or the gamma-ray productions for discrete transitions. To infer the total inelastic scattering process from this partial information\, com plementary theoretical modeling is essential\, which includes the compound \, pre-equilibrium\, and direct reactions. Ongoing efforts on the theoreti cal development include the coupled-channels and DWBA methods for the dire ct reaction\, the quantum-mechanical pre-equilibrium theories\, the statis tical Hauser-Feshbach decay for deformed targets\, and so on. In this stud y we summarize these theories and their interconnection to better understa nd the whole inelastic scattering process\, and demonstrate how the curren tly available model codes\, EMPIRE\, TALYS\, CCONE\, and CoH3\, predict th e inelastic scattering cross section.\n\nhttps://indico.frib.msu.edu/event /52/contributions/920/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/920/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurements of $^{35}$Cl(n\,x) reaction cross sections DTSTART:20220727T132400Z DTEND:20220727T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-798@indico.frib.msu.edu DESCRIPTION:Speakers: T. A. Laplace\, B. L. Goldblum\, D. L. Bleuel\, L. A . Bernstein\, C. Apgar\, C. Brand\, J. M. Gordon\, J. Bevins\, J. A. Brown \, J. Batchelder\, B. Frandsen\, G. Mills\, Tyler Nagel\n\nMeasurements of $^{35}$Cl(n\,x) reaction cross sections were conducted at Lawrence Berkel ey National Laboratory’s (LBNL) 88-Inch Cyclotron using neutrons produce d via thick target deuteron breakup from a 14 MeV deuteron beam. These cro ss sections are vital to the design of Molten Chloride Fast Reactors (MCFR )\, especially in the 0.1 MeV – 1.0 MeV region where little experimental data exist but almost half of the MCFR neutron spectrum lies. The nuclear data evaluation process that produces the cross sections used for the des ign of an MCFR assumes a fixed total $^{35}$Cl(n\,x) cross section. The r esult is that an increase in one channel causes a corresponding decrease i n one or more other evaluated channel(s). To address this aspect of nucle ar data evaluation\, we performed an experiment with the goal of measuring all energetically possible reaction channels. The experiment consisted of three independent parts. First\, energy-angle differential (n\,n’${\\ga mma}$) cross sections were obtained using the GENESIS array\, a collection of high-purity germanium detectors and LaBr inorganic scintillators for $ {\\gamma}$-ray detection as well as EJ-309 organic scintillators for neutr on detection. Second\, (n\,p) and (n\,${\\alpha}$) energy differential cro ss sections were obtained using a CLYC elpasolite scintillator as an activ e target. Finally\, energy integral (n\,p) and (n\,${\\alpha}$) cross sect ions were obtained from the production of the $^{35}$S and $^{32}$P activa tion products in a pressed NaCl tablet. The results were compared to react ion modeling using the TALYS reaction code package. \n\nThis work was per formed under the auspices of the U.S. Department of Energy (DOE) by Lawren ce Berkeley National Laboratory under Contract DE-AC02-05CH11231\, the DOE Nuclear Energy University Program (NEUP)\, and Lawrence Livermore Nationa l Laboratory under Contract DE-AC52- 07NA27344.\n\nhttps://indico.frib.msu .edu/event/52/contributions/798/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/798/ END:VEVENT BEGIN:VEVENT SUMMARY:Evaluation of the neutron-induced cross sections of actinides usin g the CONRAD computer program DTSTART:20220728T164000Z DTEND:20220728T170400Z DTSTAMP:20260420T153400Z UID:indico-contribution-972@indico.frib.msu.edu DESCRIPTION:Speakers: Gilles Noguere (CEA\, DEN Cadarache)\n\nThe CONRAD c omputer code is being developed by the nuclear data group of CEA Cadarache by since mid-2000. It was originally designed to analyse neutron-induced reactions in the resonance energy range and then\, was extended to higher energies (several MeV) treatment with inclusion of charged-particles penet ration factor. In the resonance range\, nuclear models implemented in the CONRAD program rely on R-matrix model fits with in particular\, improved t reatment of the fission penetration factor. A procedure was also implement ed to manage the so-called ‘Thermal Neutron Constants’\, especially de voted to the 239Pu\, 241Pu\, 233U and 235U nuclei. A two-step (n\,gf) proc ess was made available to describe the fluctuations of the prompt neutron multiplicity in the resonance range. The neutron continuum energy region o f the observed cross sections can be analysed either with the TALYS code o r an in-house optical model code named CCCP that is followed by Hauser-Fes hbach calculations according to the compound nucleus deexcitation channels . Non-model least squares fitting procedures have been tested for neutron cross sections adjustment in the “continuum” energy range\, and such\, extensively applied in the framework of the standard cross section group at the IAEA (Vienna). \n\nThis presentation will focus on the various eval uation works performed with CONRAD on minor and major actinides (235\,238U \, 237Np\, 239\,240\,242Pu) in the resonance range but also in the neutron continuum region with special emphasis on the experimental corrections su itable to reproduce time-of-flight experiments. Issues on the Doppler broa dening corrections with a crystal lattice model will be discussed. \n\nRef erence\n[1] C. De Saint Jean et al.\, CONRAD – a code for nuclear data m odeling and evaluation\, EPJ Nuclear Sci. Technol. 7\, 10 (2021)\n\nhttps: //indico.frib.msu.edu/event/52/contributions/972/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/972/ END:VEVENT BEGIN:VEVENT SUMMARY:Direct measurements of neutron-induced charged-particle reactions on radioactive $^{59}$Ni and $^{56}$Ni DTSTART:20220727T133600Z DTEND:20220727T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-799@indico.frib.msu.edu DESCRIPTION:Speakers: B. DiGiovine\, Hye Young Lee\, Anastasia Georgiadou\ , Pelagia Tsintari\, Lukas Zavorka\, Georgios Perdikakis\, Shea Mosby\, To shihiko Kawano\, Christiaan Vermeulen\, Mike Herman\, Hyeong Il Kim\, Vero nika Mocko\, Daniel Votaw\, Sean Kuvin\n\nNuclear reaction data for neutro n induced reactions on unstable nuclei are critical for a wide range of ap plications spanning from studies of nuclear astrophysics\, nuclear reactor designs\, and for radiochemistry diagnostics. However\, due to the diffi culty in performing this class of measurements\, and the resulting lack of experimental data\, nuclear data evaluations of the reaction cross sectio ns are typically unavailable or unreliable. In this work\, we present part ial and total $^{59}$Ni(n\,p)$^{59}$Co and $^{59}$Ni(n\,$\\alpha$)$^{56}$F e cross sections that were measured directly with a radioactive $^{59}$Ni target\, using the fast neutrons available at the WNR facility at LANSCE. The results are compared to the available nuclear data evaluations and to a recent study of the $^{59}$Ni(n\,xp) reaction cross section that was per formed via an indirect surrogate ratio method. The current study of $^{59} $Ni was also used to inform some of the background contributions in our re cent direct measurement of the $^{56}$Ni(n\,p)$^{56}$Co reaction using a r adioactive $^{56}$Ni (T$_{1/2}$ = 6 days) target. This $^{56}$Ni target wa s produced at the Isotope Production Facility at LANSCE and measured using the recently commission hotLENZ experimental setup at the WNR facility. D etails on the target fabrication process\, technical considerations for th e experimental setup\, and preliminary analysis of the $^{56}$Ni(n\,p)$^{5 6}$Co measurement will also be presented.\n\nhttps://indico.frib.msu.edu/e vent/52/contributions/799/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/799/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron-induced inelastic γ-production cross sections on $^{58\,6 0\,64}$Ni DTSTART:20220728T170400Z DTEND:20220728T171600Z DTSTAMP:20260420T153400Z UID:indico-contribution-834@indico.frib.msu.edu DESCRIPTION:Speakers: Greg Henning\, Catalin Borcea\, A. J. M. Plompen\, P hilippe Dessange\, Adina Olacel\, Maelle Kerveno\, Markus Nyman\, Liviu St oica\, Alexandru Negret\, Marian Boromiza\n\nA new (n\,n'γ) experiment wa s performed at the Geel Electron LINear Accelerator (GELINA) of the Europe an Commission-Joint Research Center (EC-JRC) to measure high resolution ne utron cross-sections on several nickel isotopes. To detect the radiation o f interest we made use of the Gamma Array for Inelastic Neutron Scattering (GAINS) spectrometer which consists of twelve HPGe detectors with 100% re lative efficiency placed at 110\, 125 and 150 degrees relatively to the di rection of incoming neutron beam. The incident neutrons\, which had energi es ranging from 0.5 to 20 MeV\, were scattered on a natural nickel target with the following characteristics: areal density 2.661(21) mg/cm^2 and di ameter 8.23(3) cm. A fission chamber with 235U deposits was also used for data normalization. We will shortly present the data analysis procedure\, the most important experimental particularities and the extracted results: the angle-integrated γ-production cross sections for all the observed tr ansitions coming from the inelastic channel on 58\,60\,64Ni.\n\nhttps://in dico.frib.msu.edu/event/52/contributions/834/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/834/ END:VEVENT BEGIN:VEVENT SUMMARY:A new measurement on $^{56}$Fe(n\,inl) using GAINS at GELINA DTSTART:20220727T134800Z DTEND:20220727T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-800@indico.frib.msu.edu DESCRIPTION:Speakers: M. Boromiza\, G. Henning\, M. Kerveno\, N. Kalantar- Nayestanaki\, C. Paradela\, M. Kavatsyuk\, A. Plompen\, M. Nyman\, A. Olac el\, A. Oprea\, C. Borcea\, Ph. Dessagne\, L. Stoica\, Alexandru Negret\n\ nThe extended dataset of 56Fe(n\,ng) cross sections measured by our group more than a decade ago at GELINA [1] was used in many recent evaluations l ike ENDF\, JEFF and CIELO. Despite the special measures we took to ensure reliability and accuracy\, concerns were raised by various groups with reg ard to several features of our dataset (absolute normalization an/or shape ) and therefore the 56Fe(n\,inl) cross section is still under the evaluati on by the International Nuclear Data Evaluation Network (INDEN) [2]. Conse quently a new experiment is now under preparation aiming to take advantage of the numerous experimental improvements of the GAINS setup implemented over the years. While gamma spectroscopy combined with the time-of-flight method will remain the main techniques involved\, several other experiment al details will differ substantially:\n- A new enriched target is already available\,\n- The number of HPGe detectors of GAINS increased from 4 to 1 2\,\n- The ToF flight path decreased from 200 m to 100 m\,\n- A new digiti zed data acquisition for GAINS is being implemented.\nWe will present all these aspects with the purpose of updating the community about our experim ental plans while triggering the debate over any additional experimental f eatures that could be considered.\n\n[1] A. Negret\, C. Borcea\, Ph. Dessa gne\, M. Kerveno\, A. Olacel\, A.J.M. Plompen\, and M. Stanoiu\, Physical Review C90\, 034602 (2014)\n[2] https://www-nds.iaea.org/INDEN/\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/800/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/800/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Data Gone Awry: Error in the IAEA Beam Monitor Reference C ross Section\, $^{\\rm nat}$Ni(n\,x)$^{61}$Cu\, Discovered while Measuring a Discrepant $^{40}$Ar(n\,p)$^{41}$Ar Reaction. DTSTART:20220727T150900Z DTEND:20220727T152100Z DTSTAMP:20260420T153400Z UID:indico-contribution-806@indico.frib.msu.edu DESCRIPTION:Speakers: Joseph Caggiano\, Scott Anderson\, Josh Brown\, Thib ault Laplace\, Bethany Goldblum\, Joseph Gordon\, Keegan Harrig\, Brian Ru snak\, Roark Marsh\, Mairead Montague\, Jonathan Morrell\, Ray Souza\, And rew Ratkiewicz\, Lee Bernstein\, Micah Johnson\, James Hall\, Carol Velsko \, Darren Bleuel\n\nTo investigate the use of argon as a deuteron beam sto pping volume\, the $^{40}$Ar(d\,p)$^{41}$Ar cross section was measured at average deuteron energies of 3.6 MeV\, 5.5 MeV\, and 7.0 MeV using an acti vation method. Natural nickel foils were used as both beam degraders and monitors\, as the $^{nat}$Ni(d\,x)$^{61}$Cu reaction has historically been one of only a few IAEA-recommended beam monitor reactions to measure deut eron fluence. A discrepancy\, well outside reported uncertainties\, was o bserved between the accepted and measured values of the intensity ratio of the two strongest gamma rays following $^{61}$Cu $\\beta$ decay. This di screpancy has significant impact since a considerable number of published cross sections measured in ratio to that beam monitor cross section may de pend on the choice of either the first or second strongest gamma ray in th ose calculations. To determine the magnitude of this error\, over a hundr ed separate measurements of the 283 keV to 656 keV gamma-ray emission rati o were collected from seven experiments and a variety of detectors and det ection geometries. A weighted average of all these ratios indicates an er ror in the value listed in the Nuclear Data Sheets of 11%\, most probably in the second-highest intensity gamma ray\, 656 keV. This has potentially introduced an 11% error in $^{61}$Cu production cross section measurement s\, cross sections using nickel activation as a deuteron beam current moni tor\, or in dose rates when $^{61}$Cu is used in nuclear medicine. Adjust ment of the $^{nat}$Ni(d\,x)$^{61}$Cu cross section\, which was primarily based on the erroneous gamma-ray intensity\, then agreed closely with our direct charge collection. Following this correction\, the $^{40}$Ar(d\,p) $^{41}$Ar cross section was determined from activation and found to be ~40 % higher than a previous measurement and an order of magnitude higher than TENDL\, further demonstrating the need for multiple\, independent measure ments of often-accepted nuclear data.\n\nhttps://indico.frib.msu.edu/event /52/contributions/806/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/806/ END:VEVENT BEGIN:VEVENT SUMMARY:Photoneutron cross section measurements on $^{208}$Pb DTSTART:20220727T152100Z DTEND:20220727T153300Z DTSTAMP:20260420T153400Z UID:indico-contribution-807@indico.frib.msu.edu DESCRIPTION:Speakers: V. W. Ingeberg\, S. Belyshev\, D. Symochko\, W. Paul sen\, N. Lalić\, F. L. Bello Garrote\, T. Aumann\, I. Gheorghe\, L. G. Pe dersen\, H. Scheit\, P. Kuchenbrod\, F. Raez\, H. Utsunomiya\, T. Eriksen\ , T. Ari-Izumi\, M. Baumann\, P. van Beek\, S. Miyamoto\, Adriana Ioana Gh eorghe\n\nPhotoneutron reactions on $^{208}$Pb in the Giant Dipole Resonan ce (GDR) energy range have been investigated at the $\\gamma$-ray beam lin e of the NewSUBARU synchrotron radiation facility in Japan. The double mag ic $^{208}$Pb is a benchmark case for theoretical modeling of electric dip ole response in nuclei. It has been extensively investigated through photo nuclear reactions as well as through inelastic hadron scattering experimen ts. However\, there are systematic discrepancies between the total and par tial ($\\gamma$\,n) and ($\\gamma$\,2n) photoneutron cross sections obtain ed at the Saclay and Livermore positron in flight annihilation facilities: the Saclay results [1] for the ($\\gamma$\,abs) and ($\\gamma$\,n) cross sections are systematically higher than the Livermore ones [2]\, while Liv ermore ($\\gamma$\,2n) cross sections overestimate the Saclay ones. We not e that the evaluations adopted in the 1999 and 2019 IAEA Photonuclear Data Libraries follow the recommendation of Berman et al. [3] of lowering the Saclay data by 7% and increasing the Livermore results by 22%\, although a single renormalization factor fails to simultaneously solve the inconsist encies for both the ($\\gamma$\,n) and ($\\gamma$\,2n) channels.\n\nMaking use of quasi-monochromatic laser-Compton scattering (LCS) $\\gamma$-ray b eams and of a novel flat-efficiency neutron detection system along with th e associated direct neutron-multiplicity sorting method [4]\, total and pa rtial ($\\gamma$\,xn) photoneutron cross sections with x = 1 to 4 have bee n measured for $^{208}$Pb in a broad energy range covering the neutron thr eshold up to 38 MeV. In agreement with preceding data\, resonant structure s have been observed in the low-energy part of the GDR. Taking advantage o f the flat-efficiency in the neutron multiplicity sorting\, we extracted a lso the average kinetic energies of neutrons emitted in the ($\\gamma$\,xn ) reactions. Similar to the behavior observed in our previous $^{209}$Bi s tudy [5]\, a non-statistical emission of high energy neutrons was register ed starting in the vicinity of the neutron emission threshold up to ~11 Me V excitation energy.\n \n[1] A. Veyssiere et al.\, Nuclear Physics A159\, 561-576 (1970).\n[2] R.R. Harvey et al.\, Phys. Rev. 136\, 126 (1964).\n[3 ] B.L. Berman et al.\, Phys. Rev. C 36\, 1286 (1987).\n[4] H. Utsunomiya e t al.\, Nuclear Inst. and Methods in Physics Research\, A 871 (2017) 135.\ n[5] I. Gheorghe et al.\, Phys. Rev. C 96\, 044604 (2017)\, Erratum Phys. Rev. C 99\, 059901(E) (2019).\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/807/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/807/ END:VEVENT BEGIN:VEVENT SUMMARY:Cross Section Measurements of (n\,x) Reactions at 17.9 and 18.9 Me V Using Highly Enriched Ge Isotopes DTSTART:20220727T180000Z DTEND:20220727T182400Z DTSTAMP:20260420T153400Z UID:indico-contribution-808@indico.frib.msu.edu DESCRIPTION:Speakers: Michael Axiotis\, Veatriki Michalopoulou\, Rosa Vlas tou\, Thanos Stamatopoulous\, Maria Diakaki\, Marilia Savva\, Anastasios L agoyannis\, Georgios Gkatis\, Sotirios Harissopoulos\, Michael Kokkoris\, Theodora Vasiliopoulou\, Claudia Lederer-Woods\, Ion Stamatelatos\, Sotiri os Chasapoglou\n\nThe study of neutron induced reactions on Ge isotopes is of major importance\, both for practical applications and fundamental res earch in Nuclear Physics. Practical applications include dosimetry\, nucle ar medicine\, astrophysical projects\, reactor and detector technology. As far as the fundamental research is concerned\, some of the residual nucle i following (n\,2n) and (n\,a) reactions are produced in high spin isomeri c states\, the decay of which is governed by the spin distribution of the continuum phase space and the spins of the discrete levels involved. Throu gh the accurate experimental determination of isomeric cross sections\, th e formation and the de-excitation of the compound nucleus can be studied. Finally\, the optimization of input parameters in statistical model calcul ations can also be achieved\, via the simultaneous reproduction of a pleth ora of reaction channels in Ge isotopes.\n Usually a $^{nat}Ge$ target is used\, containing 5 natural isotopes ($^{70}Ge$\, $^{72}Ge$\, $^{73}Ge$\, $^{74}Ge$ and $^{76}Ge$). However\, the residual nucleus produced in some reaction channels can also be produced by interfering reaction channels fr om neighbouring isotopes\, acting as a contamination to the measured react ion. This contribution can be compensated for\, via theoretical correction s based on Hauser-Feshbach calculations\, that will insert extra uncertain ties in the final cross section results. The use of highly enriched target s on the other hand\, yields more accurate experimental results\, since no interfering reactions from neighbouring isotopes take place\, and no theo retical corrections are needed. In this scope\, five highly enriched Ge sa mples of ~2g each have been used in this work. These samples have become a vailable from the CERN n_TOF collaboration\, with enrichment levels reachi ng up to ~97.71%. The irradiations of the samples were carried out at the neutron beam facility of the NCSR “Demokritos” at the 5.5 MV Tandem Va n de Graaff accelerator. The quasi mono energetic neutron beam was produce d via the $^{3}H(d\,n)^{4}He$ reaction at neutron energies of 17.9 and 18. 9 MeV and the Ge targets were irradiated together with high purity Al refe rence foils. The accurate cross section results for the $^{70}Ge(n\,2n)^{6 9}Ge$\, $^{72}Ge(n\,p)^{72}Ga$\, $^{72}Ge(n\,α)^{69m}Zn$\, $^{73}Ge(n\,p) ^{73}Ga$\, $^{73}Ge(n\,n+p)^{72}Ga$\, $^{73}Ge(n\,n+a)^{69m}Zn$\, $^{74}Ge (n\,α)^{71m}Zn$\, $^{74}Ge(n\,n+p)^{73}Ga$ and $^{76}Ge(n\,2n)^{75}Ge$ st udied in the present work\, that are produced via the use of highly enrich ed targets\, could improve the existing theoretical models and evaluation curves.\n\nhttps://indico.frib.msu.edu/event/52/contributions/808/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/808/ END:VEVENT BEGIN:VEVENT SUMMARY:First LANSCE result on differential cross sections of the $^{16}$O (n\,$\\alpha$) reaction DTSTART:20220727T182400Z DTEND:20220727T183600Z DTSTAMP:20260420T153400Z UID:indico-contribution-809@indico.frib.msu.edu DESCRIPTION:Speakers: Mark Paris\, Shea Mosby\, Daniel Votaw\, Gerry Hale\ , Brad DiGiovine\, Lukas Zavorka\, Sean Kuvin\, Morgan White\, Hye Young L ee\n\nOxygen is present in many materials - water\, oxides\, concrete and elsewhere - and the uncertainties in its nuclear data can have a significa nt impact on many nuclear applications. The current status of the oxygen-1 6 data is a 30-50 % discrepancy among various $^{16}$O(n\,$\\alpha$) and $^{13}$C($\\alpha$\,n) cross section measurements. Reconciling these disc repancies and settling on a best value requires new measurements for confi rmation.\n\nWe have performed the $^{16}$O(n\,$\\alpha$) reaction cross se ction measurement using the unmoderated white neutron source with the LENZ (Low Energy NZ-neutron induced charged particle detection) instrument at LANSCE. Double differential cross sections of $^{16}$O(n\,$\\alpha_0$) and $^{16}$O(n\,$\\alpha_2+\\alpha_3$) at multiple angles are deduced from t his work. The LENZ angular distributions are compared with previous measur ements and evaluated cross section libraries. Using the newly developed LE NZ postprocessing tool based on the MCNP's PTRAC output\, experimental yie lds are compared with simulated yields using ENDF/B-VII.1 and ENDF/B-VIII. 0. Within the experimental uncertainties\, we report the 2017 LENZ cross s ections with the angle-integrate ENDF/B-III.0 cross section using the LENZ 's angle-response function. In addition\, we will present the 2021 LENZ an gular distributions with reduced systematic uncertainties\, therefore to b e directly used with other experimental data for the R-matrix analysis.\n\ nhttps://indico.frib.msu.edu/event/52/contributions/809/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/809/ END:VEVENT BEGIN:VEVENT SUMMARY:Monoenergetic neutrons from the $^9$Be(p\,n)$^9$B reaction induced by 35\, 40 and 45 MeV protons DTSTART:20220727T184800Z DTEND:20220727T190000Z DTSTAMP:20260420T153400Z UID:indico-contribution-812@indico.frib.msu.edu DESCRIPTION:Speakers: Vrushalee Gore\, Dalho Moon\, Cheolmin Ham\, Tae-Sun Park\, Byunghyun Park\, Eun Jin In\, Seung-Woo Hong\, Vasant Bhoraskar\, Sang-In Bak\, Seyong Oh\, Vivek Chavan\n\nThe development of accelerator d riven systems\, spallation neutron sources and other nuclear technologies require cross section data of neutron-induced reactions above 20 MeV. But the cross section data for neutron energies above 30 MeV are not so abunda nt in EXFOR\, mainly due to the difficulties in obtaining monoenergetic ne utron sources. Therefore\, the activation cross sections have been measure d by using quasi-monoenergetic neutrons. Quasi-monoenergetic or continuous -energy neutrons above 20 MeV have been produced by inducing reactions suc h as $^7$Li(p\,n)$^7$Be\, $^9$Be(p\,n)$^9$B\, $^6$Li(d\,n)$^7$Be and $^9$B e(d\,n)$^1$$^0$B. The work reported in the literature show that the beryll ium target has so far been used for producing only such quasi-monoenergeti c neutrons with a finite width in energy\, and has not been used to produc e monoenergetic neutron beams. The PHITS code which combines incorporating the intra-nuclear cascade (INC) model with the Distorted Wave Born Approx imation (DWBA) method\, was developed for the simulation of the neutron yi elds of the $^7$Li(p\, n)$^7$Be and $^9$Be(p\, n)$^9$B reactions over the energy range of 10 to 50 MeV. \nIn the present work\, it is observed that by bombarding 0.25 mm thick beryllium with protons\, produce two monoenerg etic neutron peaks are produced due to the $^9$Be(p\,n)$^9$B reaction. For 35\, 40 and 45 MeV protons\, respectively\, two peaks of neutrons for eac h proton energy appear at the neutron energies of (i) 29.4 and 31.8 MeV\, (ii) 34.5 and 36.8 MeV\, and (iii) 39.7 and 42.0 MeV. For validating the s imulated monoenergetic neutron peaks\, two experimental approaches were em ployed: one by inducing nuclear reactions with ‘effective’ threshold e nergies in-between the two peaks of monoenergetic neutrons\, and other was to measure the 209Bi(n\,4n)206Bi reaction cross section. In validating th e monoenergetic neutron peak due to the ground state of $^9$B\, samples of $^9$$^3$Nb\, $^6$$^3$Cu and $^2$$^0$$^9$Bi were irradiated with neutrons from the $^9$Be(p\,n)$^9$B reaction with 35\, 40 and 45 MeV protons. The i nduced activity of $^9$$^0$Nb\, $^6$$^0$Cu and $^2$$^0$$^4$Bi radioisotope s observed in gamma ray spectrum provided evidence that $^9$$^3$Nb(n\,4n)$ ^9$$^0$Nb\, $^6$$^3$Cu(n\,4n)$^6$$^0$Cu and $^2$$^0$$^9$Bi(n\,6n) $^2$$^0$ $^4$Bi reactions were induced\, respectively\, by the neutrons of higher e nergies. These neutron energies are just above the ‘effective’ thresho ld energies of the respective (n\, xn) reactions. In addition\, the cross sections of the $^2$$^0$$^9$Bi(n\,4n)$^2$$^0$$^6$Bi reaction were measured at 29.6\, 31.8\, 34.5\, 36.8\, 39.7 and 42.0 MeV. These newly measured cr oss sections are close to those predicted by the EAF-2010 and TALYS. The p resent studies show that the simulated two peaks of monoenergetic neutrons can be experimentally validated and can be used to measure the cross sect ions for the neutron induced reactions and other applications.\n\nhttps:// indico.frib.msu.edu/event/52/contributions/812/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/812/ END:VEVENT BEGIN:VEVENT SUMMARY:Prompt fission neutron spectra in the $^{235}$U(n\,f) reaction DTSTART:20220728T130000Z DTEND:20220728T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-814@indico.frib.msu.edu DESCRIPTION:Speakers: O. Roig\, K. T. Schmitt\, D. Etasse\, J. M. O'Donnel l\, J. Taieb\, B. Laurent\, R. C. Haight\, G. Bélier\, K. J. Kelly\, P. M orfouace\, J. A. Gomez\, A. Chatillon\, M. Devlin\, P. Marini\, Benoit Ma uss\n\nNeutrons emitted in fission events can be detected with remarkable precision using the highly segmented Chi-Nu neutron liquid scintillator ar ray at the Weapons Neutron Research facility of the Los Alamos Neutron Sci ence Center. In two recent studies\, prompt fission neutron spectra (PFNS) [1] and average prompt fission neutron multiplicities [2] from $^{238}$Pu (n\,f) were measured with respect to $^{252}$Cf for incident neutron energ ies from about 1 MeV to 700 MeV. The setup consisted of a newly designed h igh efficiency and fast-timing fission chamber coupled to the Chi-Nu array . The double time-of-flight technique was used to deduce the incident neut ron energies from the spallation target and the outgoing neutron energies from the fission chamber. \n\n We will report on a follow-up study of PFNS from $^{235}$U(n\,f) measured with respect to $^{252}$Cf using the same s etup. The PFNS were measured down to 100 keV and up to 12 MeV for incident neutron energies from 0.3 to 700 MeV. Typical PFNS uncertainties obtained in the preliminary results are below 2% up to about 6 MeV at all incident energies. Neutron average kinetic energies as a function of incident neut ron energy were obtained with uncertainties below 0.5%. These results alon g with average prompt fission neutron multiplicities as a function of inci dent energy will be shown and compared to existing data and evaluations.\n \nReferences:\n[1] P. Marini et al. PRC 101\, 044614 (2020)\n[2] P. Marini et al. PRL\, accepted\n\nhttps://indico.frib.msu.edu/event/52/contributio ns/814/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/814/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the $^{241}$Am neutron capture cross section at the n_TOF facility at CERN DTSTART:20220728T132400Z DTEND:20220728T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-815@indico.frib.msu.edu DESCRIPTION:Speakers: Frank Gunsing\, Andreea Oprea\n\nThe neutron capture cross section of $^{241}$Am is an important quantity for nuclear energy p roduction and fuel cycle scenarios. Several measurements have been perform ed in recent years with the aim to reduce uncertainties in evaluated data. Two previous measurements [1\,2]\, performed at the 185 m flight-path sta tion EAR1 of the neutron time-of-flight facility n\\_TOF at CERN\, have pe rmitted to substantially extend the resolved resonance region\, but suffer ed in the near-thermal energy range from the unfavorable signal-to-backgro und ratio resulting from the combination of the high radioactivity of $^{2 41}$Am and the rather low thermal neutron flux. The here presented $^{241} $Am(n\,$\\gamma$) measurement\, performed with C_{6}D_{6} liquid scintilla tor gamma detectors at the 20 m flight-path station EAR2\, took advantage of the much higher neutron flux. Results for the thermal region and the re sonances below 10 eV will be presented and compared with existing data.\n\ n[1] K. Fraval et al.\, Phys. Rev. C 89 (2014)\n[2] E. Mendoza et al.\, Ph ys. Rev. C 97 (2018)\n\nhttps://indico.frib.msu.edu/event/52/contributions /815/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/815/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the Neutron Capture Cross Section of Am-243 with th e ANNRI beamline\, MLF/J-PARC DTSTART:20220728T134800Z DTEND:20220728T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-817@indico.frib.msu.edu DESCRIPTION:Speakers: Gerard Rovira Leveroni\, Shunsuke Endo\, Yaoki Sato\ , Jun-ichi Hori\, Nobuyuki Iwamoto\, Hideto Nakano\, Yuji Shibahara\, Tats uya Katabuchi\, Shoji Nakamura\, Atsushi Kimura\, Kazushi Terada\, Yu Koda ma\n\nThe management of high-level nuclear waste (HLW) from nuclear power plants is a significant issue to continue using nuclear energy in the futu re. To solve this\, studies of nuclear transmutation system such as the ac celerator-driven system (ADS) that transmute long-lived nuclides to shorte r or stable ones due to neutron-induced reactions have been ongoing in rec ent years. Precise nuclear data for Minor Actinides (MA) are essential for the design of nuclear transmutation systems. \nAm-243 is one of the most abundant MA isotopes in HLW. Cross section data for the neutron capture cr oss section of Am-243 are important for the calculation of nuclear reactor parameters of ADS. However\, the current uncertainties of the cross secti on data are far from the required accuracy. The uncertainty of the capture cross section for the neutron energy range from 0.5 to 500 keV was evalua ted to be 10% or higher\, while the target uncertainty was set to 2% in a sensitivity study [1]. \nThe measurements were performed using the Accurat e Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline at the Japan Proton Accelerator Research Complex (J-PARC). An intense pulsed neut ron beam was produced via spallation reaction in the mercury target of the Materials and Life Science Experimental Facility (MLF) by the 3-GeV proto n beam of the J-PARC facility. A time of flight (TOF) method using a NaI(T l) detector was employed in these measurements and a pulse-height weightin g technique was used to derive the neutron capture yield.\nA sample of Am- 243 with a mass of 38.14 mg (281.8 MBq) was used for the measurements. The neutron energy spectrum was obtained by measuring the 478 keV gamma-rays from the $^{10}$B(n\,$\\alpha \\gamma$)$^7$Li reaction with a boron sample containing enriched $^{10}$B up to 90%. A preliminary value for the captu re cross section of Am-243 will be presented in the contribution.\n\n[1] S alvatore M *et al*.\, “Uncertainty and target accuracy assessment for in novation systems using recent covariance data evaluations.\, WPEC-26\, OEC D NEA. San Diego (CA): Elsevier\; 2008.\n\nhttps://indico.frib.msu.edu/eve nt/52/contributions/817/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/817/ END:VEVENT BEGIN:VEVENT SUMMARY:Photo activation measurements of the $^{209}$Bi($\\gamma$\,xn) nuc lear reaction parameters at the LINAC 200\, JINR facility in the energy ra nge from 40 MeV to 100 MeV DTSTART:20220728T140000Z DTEND:20220728T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-818@indico.frib.msu.edu DESCRIPTION:Speakers: M. Gostkin\, V. Kobets\, M. Kmar\, S. Porokhovoy\, U . Kruchonak\, A. Nozdrin\, D. Demin\, D. Malatic\, D. Knezevic\, S. Abou E l-Azm\, T. Shneydman\, A. Zhemchugov\, M. Demichev\, Nikola Jovancevic\n\n N. Jovancevic$^1$\, M. Krmar$^1$\, S. Abou El-Azm$^2$\, M. Demichev$^2$\, D. Demin$^2$\, M. Gostkin$^2$\, V. Kobets$^2$\, U. Kruchonak$^2$\, A. Nozd rin$^2$\, S. Porokhovoy$^2$\, T.Shneydman$^2$\, A. Zhemchugov$^2$\, D. Kne zevic$^3$\, D. Maletic$^{3}$\n\n$^1$) Department of Physics\, Faculty of S cience\, University of Novi Sad\, Serbia \\\\\nnikola.jovancevic@df.uns.ac .rs\\\\\n$^2$) Dzhelepov Laboratory of Nuclear Problems\, Joint Institute for Nuclear Research (JINR)\, Dubna\, Russian Federation\\\\\n$^3$) Instit ute of Physics Belgrade\, University of Belgrade\, Belgrade\, Serbia\n\nIn this work we are presented research that would aim to obtain new experime ntal data on the parameters of photo nuclear reactions using the electron accelerator LINAC 200[1]\, located at the Dzhelepov Laboratory of Nuclear Problems of the JINR\, Dubna\, Russia. Unique characteristics of the LINAC 200 provide excellent conditions for collecting reliable data on photo-nu clear reaction. At the LINAC 200 facility the electron beams with energy i n the range from 20 MeV up to 200 MeV are available. The possibilities of obtaining reliable data at the LINAC 20 0were analyzed in this study duri ng photo activation measurements of $^{209}$Bi.\n\nNatural bismuth targets were irradiated in Bremsstrahlung photon beams at four end point energie s: 40 MeV\, 60MeV\, 80 MeV and 100 MeV. The advantages of bismuth are that it is a natural monoisotope of $^{209}$Bi and products of $^{209}$Bi($\\g amma$\,xn) nuclear reactions have a sufficiently long half-life to be regi stered in standard activation measurement\, when the gamma spectra are col lected off-line. In this work the reaction yields of several $^{209}$Bi($\ \gamma$\,xn) photo nuclear reactions in a wider energy range were extracte d. Another objective of this work was to compare experimentally obtained v alues of the reaction yields with results of theoretical calculations. The used theoretical model is explained in detail in this work. The present r esults are the first experimental data on these photo nuclear reactions in energy region between 40 and 100 MeV and this study will be the basis for future measurements at the LINAC 200 facility. \n\n[1] M. Krmar\, Y. Tet erev\, A.G. Belov\, S. Mitrofanov\, S. Abou El-Azm\, M. Gostkin\, V. Kobet s\, U. Kruchonak\, A. Nozrin\, S. Porokhovoy\, M. Demichev\, Beam energy m easurement in LINAC-200 accelerator and energy calibration of scintillatio n detectors by electrons in range from 1 MeV to 25 MeV\, Nuclear Instrumen ts and Methods in Physics Research A 935\, 83-88 (2019)\, 10.1016/j.nima.2 019.04.104.\n\nhttps://indico.frib.msu.edu/event/52/contributions/818/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/818/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurements of the $^{56}$Fe(n\,n'$\\gamma$) reaction at GENESIS DTSTART:20220728T155000Z DTEND:20220728T160200Z DTSTAMP:20260420T153400Z UID:indico-contribution-832@indico.frib.msu.edu DESCRIPTION:Speakers: T. A. Laplace\, D. L. Bleuel\, C. A. Brand\, B. Fra ndsen\, J. Bevins\, J. Batchelder\, L. A. Bernstein\, J. A. Brown\, B. L. Goldblum\, Joseph Gordon\n\nImproved inelastic neutron scattering and neut ron-induced gamma-ray production data are needed for the next generation o f nuclear technologies\, from advanced reactors to space exploration\, shi elding applications\, and detection platforms based on prompt neutron inte rrogation analysis.\nThe Gamma Energy Neutron Energy Spectrometer for Inel astic Scattering (GENESIS)\, located at the 88-Inch Cyclotron at Lawrence Berkeley National Lab\, is the first-ever array of neutron detectors coupl ed to high-purity germanium detectors designed to address these nuclear da ta needs.\nIn addition to single particle measurement of quantities like d ouble-differential gamma-ray production\, GENESIS can more accurately meas ure secondary neutron energy-angle distributions by tagging on coincident\ , characteristic gamma-rays.\n\nExperiments with a $99.98\\%$-enriched $^{ 56}$Fe target were performed at GENESIS. These experiments used a broad-e nergy collimated\, time-resolved incident neutron spectrum from 14 MeV Thi ck-Target Deutron Breakup (TTDB)\, measured \\textit{in situ} with a newly developed\, kinematic-based neutron spectrometer. Frame-overlap between neutrons of temporally-sequential deuteron beam pulses created a degenerac y in the determination of neutron energy from time-of-flight.\nThis issue motivated the development of a forward modeling approach that naturally in cludes contributions from different neutron energies in the analysis and i nterpretation of GENESIS data.\n\nThis presentation will describe the desi gn of the forward model\, including the development of a nuclear data driv en event generator. Preliminary results from the $^{56}$Fe experiments wi ll also be presented\, including double-differential gamma ray production cross sections\, and gamma-ray tagged scattered neutron angular distribut ions.\n\nhttps://indico.frib.msu.edu/event/52/contributions/832/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/832/ END:VEVENT BEGIN:VEVENT SUMMARY:Compton imaging for enhanced sensitivity (n\,$\\gamma$) cross sect ion TOF experiments: status and prospects DTSTART:20220728T172800Z DTEND:20220728T174000Z DTSTAMP:20260420T153400Z UID:indico-contribution-836@indico.frib.msu.edu DESCRIPTION:Speakers: Adria Casanovas\, Victor Babiano-Suárez\, David Cal vo\, Luis Caballero\, Javier Balibrea-Correa\, Jorge Lerendegui-Marco\, Io n Ladarescu\, the n_TOF Collaboration\, Cesar Domingo Pardo\n\nRadiative n eutron-capture cross sections are of pivotal importance in many fields suc h as nucleosynthesis studies or innovative reactor technologies. A large n umber of isotopes have been measured with high accuracy\, but there are st ill a large number of relevant isotopes whose cross sections could not be experimentally determined yet\, at least with sufficient accuracy and comp leteness\, owing to limitations in detection techniques\, sample producti on methods or in the facilities themselves.\n\nIn the context of the HYMNS (High-sensitivitY Measurements of key stellar Nucleo-Synthesis reactions) project [1] over the last five years we have developed a novel detection technique aimed at background suppression in radiative TOF neutron capture cross-section measurements. This new technique utilizes the latest positi on-sensitive photon-detection technology in combination with advanced Mach ine-Learning algorithms\, both of them optimized for the harsh background conditions of the neutron laboratory\, in order to enhance the signal-to-b ackground by means of Compton imaging. The latter allows efficient distinc tion between true capture events arising from the sample under study and c ontaminant background events from the surroundings. \n\nA summary on the m ain results [2-3] of this project will be given in this contribution toget her with an update on forthcoming experiments at CERN n_TOF and an outlook on future development steps.\n\n\n[1] Project funded by the European Rese arch Council under ERC grant agreement Nr. 681740\n[2] V. Babiano-Suarez e t al.\, The European Physical Journal A\, Volume 57\, Issue 6\, article id .197 (2021)\n[3] V. Babiano et al.\, Nuclear Inst. and Methods in Physics Research\, A\, Volume 953\, article id. 163228 (2020)\n\nhttps://indico.fr ib.msu.edu/event/52/contributions/836/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/836/ END:VEVENT BEGIN:VEVENT SUMMARY:Cross section measurement of residues produced in proton- and deut eron-induced spallation reactions on $^{79}$Se at 200 MeV/u using the inve rse kinematics method DTSTART:20220728T183000Z DTEND:20220728T185400Z DTSTAMP:20260420T153400Z UID:indico-contribution-839@indico.frib.msu.edu DESCRIPTION:Speakers: He Wang\, Hiroyoshi Sakurai\, Takashi Nakamura\, Yuk inobu Watanabe\, Misaki Saitsu\, Hideaki Otsu\, Keita Nakano\, Nobuyuki Ch iga\, Satoshi Takeuchi\, Shoichiro Kawase\n\nThe long-lived fission produc ts (LLFPs) produced in nuclear reactors have been an important issue becau se of the difficulty of disposal due to their long lifetimes. Therefore\, some treatment methods to transform the LLFPs into short-lived or low-toxi c materials are desired\, and nuclear transmutation technology is expected to be one of the solutions. However\, the reaction data of LLFPs required to design optimal pathways of the transmutation process are scarce so far . One of the reasons is considerable difficulty in manufacturing and handl ing LLFP targets\, which are necessary for the conventional measurement in normal kinematics such as the activation method. \n\nIn this study\, we e mployed the inverse-kinematics method. By this method\, the nuclide to be measured is delivered as a beam\, so there is no need to handle the radioa ctive targets. In addition\, this method has a crucial advantage in which one can measure the production yield over a wide range of isotopes regardl ess of their lifetimes\, including stable isotopes. \n\nWe carried out an experiment to measure isotopic production cross section on ${}^{79}\\mathr m{Se}$\, an LLFP nuclide with a half-life of $3.27 \\times 10^5$ years\, t hrough the proton- and deuteron-induced spallation reactions at RIKEN RI B eam Factory (RIBF). A beam including ${}^{79}\\mathrm{Se}$ at 200 MeV/$u$ was produced by in-flight fission of a ${}^{238}\\mathrm{U}$ beam at 345 M eV/$u$ and separated and identified using the BigRIPS in-flight separator. Then the beam bombarded liquid $\\mathrm{H}_2$ and $\\mathrm{D}_2$ target s. The fragments produced through the spallation reaction were identified event-by-event by using the SAMURAI spectrometer. The obtained cross secti ons corresponding for proton and deuteron injection were compared with the theoretical calculations with the CCONE code based on the exciton and Hau ser-Feshbach models and the PHITS code based on the intra-nuclear cascade and statistical decay models. The detail of the experiment and the result of the analysis will be discussed. \nThis work was supported in part by Im PACT Program of Council for Science\, Technology and Innovation (Cabinet O ffice\, Government of Japan).\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/839/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/839/ END:VEVENT BEGIN:VEVENT SUMMARY:Importance of the residual nucleus level density model in the calc ulation of the $^{239}$Pu$(n\,2n)^{238}$Pu excitation function DTSTART:20220728T171600Z DTEND:20220728T172800Z DTSTAMP:20260420T153400Z UID:indico-contribution-974@indico.frib.msu.edu DESCRIPTION:Speakers: Olivier Bouland (CEA Cadarache France)\n\nThe evalua tion state-of-the-art according to the $^{239}$Pu(n\,2n) angular-integrate d reaction cross section is well synthesized by Fig.1\, enclosed\, on whi ch are drawn from one side\, experimental data and on the other side\, som e major evaluated curves. Recent evaluations\, by contrast to the old JEF- 2.2 data file\, remain consistent except near threshold and at energies ab ove the maximum of the excitation function. In the light of the long histo rical story of the JEF(F) European project according to the evaluation of the $^{239}$Pu$(n\,2n)^{238}$Pu reaction cross section and the recent mea surement by M\\'eot \\etal~\\cite{meo:21}\, this presentation aims to shed another light on this topic by reviewing methodically the impact of the l evel density model for the $^{239}$Pu residual nucleus on the final shape of the left-tail of the excitation function. To achieve this goal\, the AV XSF-LNG computer program~\\cite{bou:13} has been upgraded to model second- chance reactions using its decay-probability module~\\cite{bou:19\,bou:20} and\, then chained to the TALYS-ECIS06 nuclear reaction system of codes~ \\cite{kon:12}. This presentation will come back on the question of the mo st relevant type of level density for second chance preequilibrium neut ron emission calculation. According to TALYS\, the spin-dependent populati on calculated after compound nucleus emission works well with the exciton model whereas the MSD-MSC quantum mechanical preequilibrium model is more adequately represented by a spin distribution based on particle-hole stat e densities. As far as a spectrum simulation of a few number of individual excitations is desired\, the combinatorial Quasi-Particle-Vibrational-Ro tational Level Density method~\\cite{bou:13} implemented in the AVXSF-LNG computer program is well suited to reach that goal. Several residual nuc leus level densities have been tested in this work using the AVXSF-LNG cod e features\, including total level density and the level density obtained after compound nucleus emission. This presentation will also include the t esting of the Quasi-particle Random Phase Approximation-based result of Re f.~\\cite{dup:17}. Finally\, the proportion of 'preequilibrium' upon the m odel of residual nucleus level density\, will be quantified against the we ll-known compound nucleus contribution building then the total (n\,2n) cro ss section. \n\n\n\n\n\n\n\n\n\n\\bibitem{mcn:01} D.P. McNabb\, J.D. Ander son\, R.W. Bauer\, J.A.Becker\, F. Dietrich\, P. Navratil\, M.B.Chadwick\, and P.G.Young\, {\\it Evaluation of the 239Pu(n\,2n) integrated cross sec tion}\, UCRL-ID-143325\, (2001)\n\\bibitem{meo:21} V.~M\\'eot\, O.~Roig\, B.~Laurent\, P.~Morel\, J.~Aupiais\, O.~Delaune\, G.~Haouat and O. Bouland \, Phys. Rev C {\\bf 103}\, 054609 (2021). \n%239Pu(n\,2n) 238Pu cross sec tion measurement using a recoil method\n\\bibitem{bou:13} O.~Bouland\, J.E .~Lynn and P.~Talou\, Phys. Rev. C \\textbf{88} 054612 (2013).\n%{\\it $\\ mathcal{R}$-matrix analysis and prediction of low-energy neutron-induced f ission cross sections for a range of Pu isotopes}\n\\bibitem{bou:19} O.~Bo uland\, %{\\it Reexamining fission-probability data using $\\mathcal{R}$-m atrix Monte Carlo simulations: Beyond the surrogate-reaction method}\, \nP hys. Rev. C {\\bf 100}\, 064611 (2019).\n\\bibitem{bou:20} O.~Bouland and G.~Nogu\\`ere\, %{\\it Reconciling surrogate-reaction probabilities and n eutron-induced cross sections}\, \nPhys. Rev. C {\\bf 102}\, 054608 (2020 ). \n\\bibitem{kon:12} A.J.~Koning and D.~Rochman\, Nuclear Data Sheets \\ textbf{113}\, Issue 12\, Pages 2841-2934 (2012).\n%Modern Nuclear Data Ev aluation with the TALYS Code System\n\\bibitem{dup:17} M.~Dupuis\, S.~Hila ire\, S.~P\\'eru\, E.~Bauge\, M.~Kerveno\, P.~Dessagne\, and G.~Henning\, EPJ Web of Conferences 146\, 12002 (2017).\n\nhttps://indico.frib.msu.edu/ event/52/contributions/974/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/974/ END:VEVENT BEGIN:VEVENT SUMMARY:Neutron production cross sections for proton induced reactions on $^{\\rm nat}$Cu and $^{27}$Al with a flat-efficiency neutron detector DTSTART:20220728T185400Z DTEND:20220728T190600Z DTSTAMP:20260420T153400Z UID:indico-contribution-840@indico.frib.msu.edu DESCRIPTION:Speakers: Cristina Clisu-Stan\, Dan Mihai Filipescu\, Alexandr u Negret\, Gry Merete Tveten\, Irina Stiru\, Therese Renstrøm\, Christoph e Sotty\, Mateusz Krzysiek\, Andrei Turturica\, Alina Ionescu\, Fabio Zeis er\, Franco Camera\, Lucian Stan\, Nicoleta Florea\, Oliver Wieland\, Adin a Olacel\, Rares Suvalla\, Hiroaki Utsunomiya\, Giulia Gosta\, Esra Acikso z\, Cristina Petrone\, Cristina Nita\, Sebastian Toma\, Andreea Serban\, I oana Gheorghe\, Adam Maj\, Sorin Ujeniuc\, Marian Boromiza\n\nA high-and-f lat efficiency moderated neutron detection array has been recently develop ed for photoneutron cross section measurements at the future ELI-NP gamma- ray beam source. It is composed of three concentric rings of 4\, 8 and 16 $^3$He proportional counters embedded in a high density polyethylene block and has a ~37% efficiency flat within 5% in the 10 keV to 5 MeV neutron e nergy interval. We performed a commissioning experiment using proton beams delivered by the 9 MV Tandem accelerator of IFIN-HH. We measured the neut ron production cross sections for proton induced reactions on $^{nat}$Cu a nd $^{27}$Al. During irradiations\, the proton beam current was continuous ly monitored using four charge integrator units coupled to the electricall y insulated Faraday cup\, collimator\, reaction chamber and target. The ch arge collection was validated against separate activation measurements on $^{nat}$Cu. \n\nThe (p\,xn) reactions on $^{nat}$Cu were investigated in t he 4.5 MeV to 14 MeV proton energy range with 250 keV steps. The low energ y measurements below 10 MeV served to validate the detection efficiency ca libration against well-known $^{nat}$Cu(p\,n) cross sections. The measurem ents above the $^{65}$Cu(p\,2n) reaction threshold at 10 MeV were performe d in both continuous and pulsed proton beam conditions. Neutron multiplici ty sorting techniques were applied to the pulsed beam data in order to ext ract the $^{nat}$Cu(p\,n) and $^{nat}$Cu(p\,2n) components\, where only th e $^{65}$Cu isotope contributed to the (p\,2n) channel. Using ring-ratio i nformation\, the average total kinetic energies of neutrons emitted in the $^{nat}$Cu(p\,xn) reactions have also been determined for the entire inve stigated energy range.\n\nThe $^{27}$Al(p\,n) reaction was investigated in the 5.8 MeV to 6.75 MeV energy range with 5 keV steps. Our measured cross sections reproduce the resonant structures previously observed also by Se kharan [1] and Bubb [2]. The new cross sections are in good agreement with the ones reported by Sekharan [1]\, which are systematically higher than the results of Bubb [2]. \n\nWe here present the new experimental result s for the $^{nat}$Cu(p\,xn) and $^{27}$Al(p\,n) measurements in comparison with preceding data. The $^{nat}$Cu(p\,xn) reactions cross sections and a verage energies of the neutron emission spectra are compared to statistica l model calculations. \n\n[1] K.K.Sekharan *et al.*\, Nuclear Instruments and Methods **133**\, 253 – 257 (1976).\n[2] I.F. Bubb *et al.*\, Nucle ar Physics **65**\, 656 – 661 (1965).\n\nhttps://indico.frib.msu.edu/eve nt/52/contributions/840/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/840/ END:VEVENT BEGIN:VEVENT SUMMARY:Interchange\, Extension\, and Validation of R-matrix fits for gamm a production DTSTART:20220726T183900Z DTEND:20220726T185100Z DTSTAMP:20260420T153400Z UID:indico-contribution-903@indico.frib.msu.edu DESCRIPTION:Speakers: Ian Thompson (LLNL)\n\nThe R-matrix method of Lane a nd Thomas is the standard procedure for modelling resonances at low energi es\, to determine widths and angular distributions needed for nuclear eval uations. Many different codes have been written\, all with different input and output file formats. To ensure that results can be replicated\, I hav e written a python code FERDINAND using FUDGE to read & write ENDF\, GNDS standard formats\, read AMUR\, AZURE\, EDA\, FRESCO and RAC formats\, and write AZURE\, EDA\, FRESCO\, HYRMA and latex formats.\n\nBecause of the in creasing need for gamma production information\, R-matrix codes are being extended to include primary and secondary gammas and predict the angular d istributions for both of kinds. More excited states of residual nuclei nee d to be included in the fits\, since these give directly many of the secon dary gamma decays. These place computational demands on the codes\, and u sing Google’s Tensorflow framework enables the development of GPU codes such as LLNL’s RFLOW for fitting.\n\nThere is also a need to go higher-e nergy states in the compound nucleus. This will require theory development s to ensure smooth transitions from unresolved and/or overlapping resonanc es in an R-matrix code to Hauser-Feshbach predictions that are based on tr ansmission coefficients derived from optical potentials. A good connection between these two methods should be possible because the Hauser-Feshbach method may be derived as an approximation to R-matrix resonance descriptio ns.\n\nReactions of n+14N and other reactions producing 15N* have been eva luated as part of the INDEN project. The thresholds for n+14N\, p+14C and +11B are close to each other\, and so all three channels must be fitted simultaneously. ENDF has a 1992 evaluation with these three channels up t o 2 MeV\, and Notre Dame has recently re-evaluated them up to higher energ ies. Here I report on assessments that include the higher excited states o f 14N and 11B that are responsible for high-energy gamma production.\n\nTh is work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344 .\n\nhttps://indico.frib.msu.edu/event/52/contributions/903/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/903/ END:VEVENT BEGIN:VEVENT SUMMARY:Non-statistical Behaviour of (n\,2n) Cross Sections for 14-15 MeV Neutrons DTSTART:20220727T171400Z DTEND:20220727T171600Z DTSTAMP:20260420T153400Z UID:indico-contribution-1136@indico.frib.msu.edu DESCRIPTION:Speakers: Odsuren Myagmarjav (Nuclear Research Center\, Nation al University of Mongolia\, Ulaanbaatar\, Mongolia School of Engineering a nd Applied Sciences\, National University of Mongolia\, Ulaanbaatar\, Mong olia)\n\nFast neutron induced nuclear reaction cross section data are nece ssary for both nuclear energy technology and the study of nuclear physics research. The information of (n\,2n) cross sections is quite essential in nuclear reactor technology as a significant portion of the fission neutron spectrum lies above the threshold of (n\,2n) reaction for most structural materials. Furthermore\, the application of the fast neutron induced nucl ear reaction cross section data have been increasing in the fields of biom edical applications\, accelerator driven transmutation\, material irradiat ion experiments concerning research and development for fusion reactor tec hnology. On the other hand\, systematics of fast neutron induced reaction cross sections is useful to clarify nuclear reaction mechanisms. Also\, it is often necessary\, in practice\, to use the systematical analysis for e valuation of the neutron cross sections of the nuclides\, for which no exp erimental data are available.\nA systematic dependence of (n\,2n) reaction cross sections on the neutron number excess parameter (N-Z)/A for target nuclei was studied in a number of works. Purely empirical formulaeand semi -empirical formulae based on the statistical model\, pre-equilibriumand di rect reaction mechanismswere suggested to explain this regular behaviour o f the (n\,2n) cross sections. However\, a strict and unified theoretical v alidity no up to now is available for explanation of the neutron cross sec tion regularity which in the literature is termed as the isotopic effect.\ nIn this work new formulae for the (n\,2n) cross section are deduced using the concepts of statistical and non-statistical nuclear reaction mechanis ms. In the calculation of the statistical share of the cross section the c onstant nuclear temperature approximation\, evaporation model and Weizsäc ker’s formula for binding energy were utilized. Non-statistical part was obtained by subtraction of statistical model cross section from total one . The total cross section was determined by geometrical cross section of t arget nuclei as an upper limit of interaction of neutrons with nuclei. \nI t was shown that non-statistical part of the (n\,2n) cross section is in a greement with known experimental data taken from EXFOR library.\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/1136/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1136/ END:VEVENT BEGIN:VEVENT SUMMARY:Open-source Release of CGMF 1.1 and Integration into the MCNP6.3® Code DTSTART:20220728T185500Z DTEND:20220728T190700Z DTSTAMP:20260420T153400Z UID:indico-contribution-980@indico.frib.msu.edu DESCRIPTION:Speakers: Michael Rising (LANL)\n\nThe CGMF code\, which model s the correlated particle emissions from fission events of various spontan eous and neutron-induced fissile systems\, is now available as open-source software [1]. In the previous release of MCNP\, version 6.2\, the CGMF c ode was integrated and was optionally available to perform inline low-ener gy fission event simulations targeted toward nuclear nonproliferation and safeguards applications. In this paper\, the new release of the CGMF code version 1.1 is discussed along with its extended capabilities available i n the recently released MCNP6.3 code.\n\nReferences\n[1] Patrick Talou\, I onel Stetcu\, Patrick Jaffke\, Michael E. Rising\, Amy E. Lovell\, and Tos hihiko Kawano\, “Fission Fragment Decay Simulations with the CGMF Code\, ” Comp. Phys. Comm.\, 269 (2021)\, Article 108087. DOI: 10.1016/j.cpc.20 21.108087\n\nhttps://indico.frib.msu.edu/event/52/contributions/980/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/980/ END:VEVENT BEGIN:VEVENT SUMMARY:A novel R-matrix formalism for three-body channels DTSTART:20220726T190300Z DTEND:20220726T191500Z DTSTAMP:20260420T153400Z UID:indico-contribution-912@indico.frib.msu.edu DESCRIPTION:Speakers: Helmut Leeb (TU Wien\, Atominstitut)\, Benedikt Raab (TU WIEN)\n\nThree-body break-up channels play an important role in light nuclear systems even at low incident energies. In standard two-body R-mat rix theory these processes can only be treated approximatively for instanc e by using sequential decay models. We will present a novel three-body R-m atrix formalism that is based on a proposal by Glöckle [1]. In this frame work the Faddeev equations are solved by dividing the space of Jacobi-coor dinates into interior regions with strong local interactions and an asympt otic exterior region. Using the asymptotic form of the three-body wave fun ctions one obtains a system of linear equations which includes the boundar y conditions at the division of the Jacobi-coordinates. Its solution direc tly yields the elastic and the break-up transition amplitudes and thus the elastic and the breakup cross sections. The form of these equations resem bles a similar one in the standard R-matrix theory and justifies its denom ination.\n\nIn a first step we generalized the proposal of Glöckle to thr ee spinless particles with different masses. A first numerical implementat ion indicated severe shortcomings as well as ill-posedness of the algorith m. Significant changes especially with regard to the conditions and the ch oice of basis functions as well as the normalization of bound states were required leading to a novel formalism of Glöckle type. The ill-posedness of the equations has been cured by regularization. The novel formalism was first applied to the neutron-deuteron system. Systematic studies of diff erent sets of basis functions and regularization parameters were performed and stable results were achieved. The calculated break-up cross section a nd the elastic cross section are in fair agreement to the experimental dat a up to 10 MeV since we include s-waves only. Furthermore\, we present an outlook and first results regarding the n+9Be system.\n \nAcknowledgement: The work has been carried out within the framework of the EUROfusion Cons ortium and has received funding from the European research and training pr ogramme 2014-2018 and 2019-2020 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the Eur opean Commission.\n\n[1] W. Glöckle\, Z. Phys. 271\, 31 (1974)\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/912/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/912/ END:VEVENT BEGIN:VEVENT SUMMARY:Testing the Extended SRM against the $^{238}$U($^{3}$He\,$^{4}$He) $^{237}$U$^*$ surrogate probabilities DTSTART:20220728T152600Z DTEND:20220728T153800Z DTSTAMP:20260420T153400Z UID:indico-contribution-968@indico.frib.msu.edu DESCRIPTION:Speakers: Olivier Bouland (CEA Cadarache France)\n\nSince its introduction\, the so-called surrogate-reaction method (SRM) has motivated the development and improvement of theories in connection to direct react ions. A recent paper~\\cite{bou:20} has shown that the assimilation of exp erimental probabilities in the neutron cross section evaluation process ca n still be better estimated using tools resulting from the efforts made ov er the two last decades. In particular\, this paper has put forward a new prescription\, named after the SRM as extended SRM (ESRM)\, to convert\, w ith reasonable confidence\, measured direct-reaction induced probabilities to pseudo experimental neutron-induced cross sections. Applied to the $^{ 174}$Yb($^{3}$He\,p\\gamma)$^{176}$Lu$^*$ transfer reaction\, the ESRM has demonstrated much more precision than the standard use of the historical SRM to make that conversion. Beyond 'direct' analysis of direct-reaction induced probabilities using the right modeling as developed in Ref.~\\cite {bou:19}\, it is worth to try converting the measured probabilities in pse udo experimental neutron-induced cross sections for neutron reactor data a pplications. In the present talk\, we demonstrate that the ESRM is also su itable for fissile isotopes. The ESRM formula will be applied to gamma-emi ssion and fission probabilities measured in the $^{238}$U($^{3}$He\,$^{4}$ He)$^{237}$U$^*$ reaction\, transforming them into neutron-incident (n+$^{ 236}$U) data. Figure 1\, enclosed\, extracted from Ref.~\\cite{jur:17}\, shows the disagreement commonly observed between decay probabilities reco vered using the Weisskopf-Ewing limit of the SRM from neutron-incident eva luated cross sections and\, the actually measured probabilities. \n\n\n\n \n\\bibitem{bou:20} O.~Bouland and G.~Nogu\\`ere\, %{\\it Reconciling surr ogate-reaction probabilities and neutron-induced cross sections}\, \nPhys. Rev. C {\\bf 102}\, 054608 (2020). \n\\bibitem{bou:19} O.~Bouland\, %{\\ it Reexamining fission-probability data using $\\mathcal{R}$-matrix Monte Carlo simulations: Beyond the surrogate-reaction method}\, \nPhys. Rev. C {\\bf 100}\, 064611 (2019).\n\\bibitem{jur:17} B.~Jurado\, P.~Marini \\et al~\, EPJ Web Conf. 146\, 11006 (2017).\n\nhttps://indico.frib.msu.edu/eve nt/52/contributions/968/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/968/ END:VEVENT BEGIN:VEVENT SUMMARY:Double-humped barrier effects in the R-matrix for fitting of fissi le isotope DTSTART:20220727T141200Z DTEND:20220727T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-930@indico.frib.msu.edu DESCRIPTION:Speakers: Gilles Noguere (CEA\, DEN Cadarache)\, Luiz Leal (IR SN)\, Olivier Bouland (CEA\, DES\, IRESNE Cadarache)\n\nReich-Moore (RM) a pproach has been extensively used in the resolved resonance energy range ( RRR) for a wide range of isotopes. The Reich-Moore approximation was sugge sted late in the fifties for cross section representation of fissile isoto pes since experimental fission width distribution according to given reson ance spin and parity showed that only a few degrees of freedom (DoF) was i nvolved during the fission process. On this ground\, experimental cross se ction data in RRR were successfully reproduced and the interference in fis sion channels were well described. The fitting of the fission cross sectio n data was done according to one or two fission channels for a given reson ance spin (J) and parity (π). By using the two-fission channel RM represe ntation\, channel interference effects observed on cross section data for fissile heavy isotopes were adequately treated but only on a phenomenologi cal basis. Indeed\, this approach is physically unsatisfactory since no fi ssion penetrability is involved in reduced fission channel width evaluatio n and therefore no actual connection between R-matrix fission channel widt hs and Aage Bohr transition fission channels can be made neither in terms of individual barrier height nor by the shape. Our intent is to address th is long-standing model deficiency by including ’fluctuating’ fission b arrier penetrability as a function of resonance spin and parity over the R RR for fissile isotopes. Fissile systems are easier to model since we can refer to a statistical representation of the double-humped barrier. In thi s representation\, the neutron-induced fissile system excitation is assume d to be much above the energy of the fission barrier such that a statistic al equilibrium among all degrees of freedom in the compound system occurs. The partial transmission coefficient of the whole barrier is calculated a s TF (μ) = (TATB (μ))/ (TA + TB ) where TA and TB are the total fission transmission coefficients across the inner barrier transition states seque nce and the μ outer barrier transition states sequence\, respectively. TA and TB are calculated using the Hill-Wheeler formula. The strength of eac h Jπ resonance fission channel width depends on the effective number of t ransitions states of same Jπ available for fission. A list of collective DoF\, ideally represented by their spin projection (Kπ) onto the elongati on axis of the nucleus under fission\, was set up. They serve as band head s to build an adequate discrete sequence of Jπ rotational levels on top o f each barrier hump. Application is made to the fissile system (n+235U) to determine a new set of fission widths over the RRR (0 - 2.25 keV) accordi ng to the two s-wave j=3- and 4- spins. It leads to truly physical fitted fission widths and requires a four-fission channel RM representation\; eac h of those devoted to a set of (J\, K\, π) quantum numbers.\n\nhttps://in dico.frib.msu.edu/event/52/contributions/930/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/930/ END:VEVENT BEGIN:VEVENT SUMMARY:Microscopic description of target spin distribution afterinelastic scattering to the continuum DTSTART:20220727T130000Z DTEND:20220727T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-918@indico.frib.msu.edu DESCRIPTION:Speakers: Stephane Hilaire (CEA/DAM/DIF)\, Maëlle Kerveno (CN RS/IPHC\, Strasbourg)\, Toshihiko Kawano (Los Alamos National Laboratory)\ , Marc Dupuis (CEA\, DAM\, DIF)\n\nNucleon inelastic scattering to the con tinuum can be adequately described through the exciton or quantum mechanic al multistep direct (MSD) and multistep compound (MSC) pre-equilibrium mo dels\, as they account not only for the high energy component of particle emission spectrum\, but also it provides initial conditions of the formed Compound Nucleus (CN).\n\nIt was previously shown that an accurate description of the spin and parity distributions in the residual nuc leus populated after the fast inelastic collision has a strong impact on t he description of (n\,n’γ) reactions [1\,2]. These previous works sugge sted that\, in some specific cases\, a spin distribution given as an ad-ho c prescription\, e.g.by Gruppelaar [3]\, to complement the exciton model is insufficient since such modeling does not conserve angular mo mentum and parity.\n\nIn contrast\, while a fully quantum mechanical mode ling of the pre-equilibrium process satisfies the conservation laws in phy sics\, it is not always ideal for applying to nuclear energy and astrophys ics because of large computing time. In this regard\, the classical excit on model\, which allows a quick determination of the particle emission ene rgy spectrum\, seems better suited. We propose an extended semi-classi cal exciton model\, where the spin-parity distributions in the res idual CN are constrained by microscopic approaches\, would be a good pragm atic solution.\n\nFrom microscopic pre-equilibrium calculations for neutro n scattering up to 30 MeV on a largevariety of target nuclei\, we deduce s ystematic formulae that can be used in conjunction with the exciton model and be easily implemented in general reaction modeling codes such as TALYS \,EMPIRE\, CoH3\, and CCONE. These formulae are tested by looking at (n\,x nγ) reactions andisomer productions\, and recommendations for a future us e are given.\n\n[1] D. Dashdroj\, et al.Phys. Rev. C\, 75:054612 2007.\n[2 ] M. Kerveno\, et al.Phys. Rev. C\, 2021 (in press).\n[3] H. Gruppelaar\, IAEA Advisory Group Meeting\, BNL report\, pp.143–160\, 1983.\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/918/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/918/ END:VEVENT BEGIN:VEVENT SUMMARY:New developments in fission studies within the time-dependent dens ity functional theory framework DTSTART:20220725T163000Z DTEND:20220725T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-596@indico.frib.msu.edu DESCRIPTION:Speakers: Ibrahim Abdurrahman\, Kyle Godbey\, Ionel Stetcu\, A urel Bulgac\n\nLA-UR-21-28456\n\nWe have extended significantly our descri ption of fission by examining a larger set of observables and more nuclei. We extract neutron and proton numbers of fission fragments\, their spins and fission fragments relative orbital angular momentum and their correlat ions\, investigate neutrons emitted at or shortly after scission\, excitat ion energy sharing mechanism\, total kinetic energy of fission fragments. So far\, we have performed simulations with two independent nuclear energy density functionals on a number of uranium\, plutonium\, fermium\, mercur y isotopes\, and spontaneous fission of 252Cf and we will extend these stu dies to a number of radon\, polonium isotopes in the coming year (2022) an d have results ready to present by the time of the meeting.\n\nhttps://ind ico.frib.msu.edu/event/52/contributions/596/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/596/ END:VEVENT BEGIN:VEVENT SUMMARY:Investigation of photodisintegration cross sections for virtual st ates DTSTART:20220727T152100Z DTEND:20220727T153300Z DTSTAMP:20260420T153400Z UID:indico-contribution-941@indico.frib.msu.edu DESCRIPTION:Speakers: Myo T (General Education\, Faculty of Engineering\, Osaka Institute of Technology\, Osaka 535-8585\, Japan\; Research Center f or Nuclear Physics (RCNP)\, Osaka University\, Ibaraki 567-0047\, Japan)\, Kato K (Nuclear Reaction Data Centre\, Faculty of Science\, Hokkaido Univ ersity\, Sapporo 060-0810\, Japan)\, Odsuren Myagmarjav (School of Enginee ring and Applied Sciences and Nuclear Research Center\, National Universit y of Mongolia\, Ulaanbaatar 210646\, Mongolia)\n\nThe first excited $1/2^+ $ state in $^9$Be has been observed as a sharp peak just above the $^8$Be+ $n$ threshold energy in the photo-disintegration cross section of $^9$Be. Since the size of the peak has a strong influence on the reaction rate of the $^9$Be synthesis\, experimental data have been investigated [1\, 2].\n \nWe performed calculations using an $\\alpha+\\alpha+n$ three-cluster mod el [3\, 4] together with the complex scaling method (CSM) [5\, 6]\, which well reproduces the measured photo-disintegration cross section. The resul ts indicate that the virtual-state character of the $1/2^+$ state plays an important role in formation of the peak structure appearing in the cross section observed above the $^8$Be+$n$ threshold. However\, the virtual sta te cannot be directly obtained as an isolated pole solution in the CSM\, b ecause the scaling angle in the CSM cannot be increased over the position of the virtual state pole on the negative imaginary axis of the complex mo mentum plane. \n\nThe pole position of the virtual state is discussed calc ulating the continuum level density\, the scattering phase shift\, and sca ttering length calculated in the CSM [7\, 8]. In the next step\, we need t o distinguish a virtual state from a resonant state and to calculate their contributions in the photo-disintegration cross sections. For this purpos e\, we apply the CSM to a simple schematic two-body model which simulates the 8Be+n system [8]. In this schematic two-body model\, both clusters ($^ 8$Be and $n$) are assumed to be structureless and spinless. To understand the origin of a low-energy peak in the photodisintegration cross section j ust above the breakup threshold energy in 9Be\, we calculate the contribut ions of the components of the strength function. The decomposed $E1$ trans ition strength is shown in Fig. 1. From the results\, we can see that the real part of the matrix element $M^2$ and the imaginary part of $\\rho(E)$ are dominant. This property is consistent with the $R$-matrix description [8]\, in which the peak is described as results from a resonant state. Th e asymmetric peak\, displayed as solid curve in Fig. 1\, implies the exist ence of a virtual state or a resonant state near zero energy.\n\nhttps://i ndico.frib.msu.edu/event/52/contributions/941/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/941/ END:VEVENT BEGIN:VEVENT SUMMARY:Spin assignments of neutron resonances with Machine Learning DTSTART:20220726T185100Z DTEND:20220726T190300Z DTSTAMP:20260420T153400Z UID:indico-contribution-904@indico.frib.msu.edu DESCRIPTION:Speakers: Gustavo Nobre (BNL)\n\nThe different processes known in astrophysics to govern the successions of nuclear formation and decay\ , r-process and s-process\, depend strongly on nuclear properties such as the intrinsic density of levels of a given nucleus and how they behave whe n emitting or absorbing particles such as neutrons\, protons and/or photon s. There are few experimental constraints that we can use to narrow down s uch properties and most of the information we know comes from experimental measurements of resonance states seen in compound nuclei formed by neutro n-induced reactions. These resonances are seen as sharp increases in measu red neutron transmission and capture due to the proximity of the neutron e nergy with excited levels in the compound nucleus.\nTherefore\, a proper a nd reliable account of all resonances is crucial for the description of nu clear reactions. We have developed a Machine-Learning method\, the Bayesia n Resonance Reclassifier\, to make use of the statistical properties of re sonances to train an algorithm capable to identify missing and misassigned resonances. We are able to train the model on synthetic data and use tran sfer learning to assess resonance sequences from the Atlas of Neutron Reso nances\, evaluated files or experimental data. We performed an extensive o ptimization through multiple grid search of hyper-parameter values for eac h of the classifiers studied. We were also able to use experimental resona nce data obtained through measurements with polarized neutron beams as a v alidation tool to assess the quality of the method\, with encouraging resu lts.\n\nhttps://indico.frib.msu.edu/event/52/contributions/904/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/904/ END:VEVENT BEGIN:VEVENT SUMMARY:Recent advances within the QRPA framework to improve gamma strengt h function prediction DTSTART:20220727T144500Z DTEND:20220727T150900Z DTSTAMP:20260420T153400Z UID:indico-contribution-931@indico.frib.msu.edu DESCRIPTION:Speakers: Stéphane Goriely (ULB)\, Sophie Péru (CEA\, DAM\, DIF)\, Stéphane Hilaire (CEA\, DAM\, DIF)\n\nThe Gogny-based QRPA approac h developed in CEA\, DAM\, DIF [1] can be applied to spherical as well as to axially deformed nuclei\, from light (i.e. oxygen) to superheavy elemen ts [2]. For electric and magnetic dipole modes\, intensive computational e fforts have been made to produce a large-scale data set of gamma-ray stren gth functions with as little as possible phenomenological corrections. The resulting photon strength functions have been shown to reproduce the bulk of experimental data with a high level of accuracy [3]. The most recent c alculations also include the transition probabilities for the decay of the QRPA excited states down towards the ground state\, regardless of the ele ctromagnetic multipolarity.\n\nIn this talk\, I will also present some suc cesses obtained by the QRPA approach in the reproduction of additional exp erimental data. More particularly\, the method has been applied to the N=1 00 isotones in order to describe their 4- isomeric states. Since the calcu lated half-lives of pure K=4 states are too large by several orders of mag nitude\, the Coriolis coupling between QRPA states has been introduced to reproduce and interpret the variation of the lifetime along the N=100 isot onic chain [4]. Such a coupling requires the calculation of transition pro babilities between QRPA excited states that can also be used to describe m icroscopically and consistently the low-energy de-excitation photon streng th function\, known as the upbend\, observed in Oslo data and of particula r relevance for reaction and astrophysical studies.\n\n\n(1) S. Péru and H. Goutte\, Phys.Rev. C 77\, 044313 (2008)\n(2) S. Péru et al\, Phys.Rev. C 83\, 014314 (2011)\n(3) S. Goriely et al.\, European Physical Journal A 55\, 172 (2019)\n(4) L. Gaudefroy\, S. Péru et al\, Phys.Rev. C 97\, 064 317 (2018).\n\nhttps://indico.frib.msu.edu/event/52/contributions/931/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/931/ END:VEVENT BEGIN:VEVENT SUMMARY:Fission In R-process Elements (FIRE) DTSTART:20220725T194500Z DTEND:20220725T195700Z DTSTAMP:20260420T153400Z UID:indico-contribution-613@indico.frib.msu.edu DESCRIPTION:Speakers: Patrick Talou\, Matthew Mumpower\, Elizabeth McCutch an\, Alejandro Sonzogni\, Ramona Vogt (LLNL\, UC Davis)\, Rebecca Surman\, Toshihiko Kawano\, Gail McLaughlin\, Nicolas Schunck\n\nThe goal of the F IRE topical collaboration in nuclear theory (2017-2021) was to determine t he astrophysical conditions of the rapid neutron capture process (r-proces s)\, which is responsible for the formation of heavy elements. This was ac hieved by including in r-process simulations the most advanced models of f ission (spontaneous\, neutron-induced\, β-delayed) that are beeing devel oped at LLNL and LANL. The collaboration was composed of LLNL (lead) and L ANL for work on fission and nuclear models\, BNL for nuclear data manageme nt\, and the university of Notre Dame and North Carolina State University for r-process simulations. I will give a summary of the results obtained b y the collaboration and their impact on nuclear data.\n\nhttps://indico.fr ib.msu.edu/event/52/contributions/613/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/613/ END:VEVENT BEGIN:VEVENT SUMMARY:Improved measurements and reaction modeling for the production of Sn-117m and Te-119m via proton bombardment on natural antimony up to 200 M eV DTSTART:20220728T141200Z DTEND:20220728T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-965@indico.frib.msu.edu DESCRIPTION:Speakers: Catherine Apgar (Department of Nuclear Engineering\, University of California\, Berkeley\, Berkeley\, California 94720\, USA)\ n\nThe Auger-emitting nuclides $^{119}Sb$ (for which $^{119m}Te$ is a gene rator) and $^{117m}Sn$ are promising candidates for the treatment of small tumors and for use in radiosynoviorthesis\, but there is little informati on available regarding the formation of these nuclei when targets are bomb arded with high energy protons in large-scale isotope production facilitie s. A more precise cross section measurement will inform a production pathw ay with high yield and minimal co-produced impurities. As part of the Tri- Lab Evaluated Nuclear Data Effort (TREND)\, cross sections for production of these isotopes have been measured for energies up to 200 MeV.\n\nCross sections for multiple channels were measured for proton-induced reactions up to 55 MeV at Lawrence Berkeley National Lab\, up to 100 MeV at the Isot ope Production Facility at Los Alamos National Lab\, and up to 200 MeV at the Brookhaven Linac Isotope Producer at Brookhaven National Lab.\n\nThe r esults of cross section measurements\, together with data from other measu rements by the TREND collaboration on natural niobium\, arsenic and thal lium nuclides\, will be compared to the predictions from charged particle reaction modeling codes\, such as TALYS and EMPIRE\, employing physically defensible level density and optical model adjustments as investigated in (Fox et al.\, 2021). To build on these results\, measurements of prompt ga mma emissions from irradiations of antimony and thallium will provide yiel ds for both very long-lived or stable isotopes and very short-lived isotop es\, as well as detailed information regarding the population of residual nuclei as a function of angular momentum and parity. These additional reac tion channels will provide insight into nuclear level density and particle transmission coefficients as a function of excitation energy and will hel p advise further parameter adjustments in nuclear reaction modeling.\n\nTh is research is supported by the U.S. Department of Energy Isotope Program\ , managed by the Office of Science for Isotope R&D and Production\, carrie d out under Lawrence Berkeley National Laboratory (Contract No. DE-AC02-05 CH11231)\, Los Alamos National Laboratory (Contract No. 89233218CNA000001) \, and Brookhaven National Laboratory (Contract No. DEAC02-98CH10886).\n\n https://indico.frib.msu.edu/event/52/contributions/965/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/965/ END:VEVENT BEGIN:VEVENT SUMMARY:Evaluation of neutron-induced reactions on $^{239}$Pu DTSTART:20220728T172800Z DTEND:20220728T174000Z DTSTAMP:20260420T153400Z UID:indico-contribution-976@indico.frib.msu.edu DESCRIPTION:Speakers: Gregory Potel Aguilar (LLNL)\n\nNeutron-induced cros s sections on fissile nuclei such as $^{239}$Pu are important for defense and energy applications\, as well as for basic science. The quality of the se values rely on two basic pillars: a) the availability of high-quality\, curated experimental data. Within this context\, it is essential to const antly update the existing database with the new experiments carried out in facilities where neutron beams are available. b) the implementation and f ine-tuning of theoretical models\, ensuring the consistency of the variety of observables among themselves\, as well as with our knowledge of the s tructure of the nuclei involved. Theory then provides energy-dependent cro ss sections that can be used in transport codes and reaction networks calc ulations\, even for energies where experimental data might not be currentl y available. I present here the results obtained in the evaluation of $^{ 239}$Pu neutron-induced cross sections\, for incident neutron energies 4 k eV$ < E_n < 20$ MeV. We incorporate to the experimental database the rece nt measurement of the $^{239}$Pu($n\,f$)/$^{235}$U($n\,f$) cross section r atio\, performed at the Los Alamos Neutron Science Center (LANSCE) with t he NIFFTE collaboration's fission TPC. The reaction and decay processes ar e described within the Hauser-Feshbach statistical decay framework and the coupled-channels reaction formalism\, implemented in the codes YAHFC and FRESCO\, respectively.\n\nhttps://indico.frib.msu.edu/event/52/contributio ns/976/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/976/ END:VEVENT BEGIN:VEVENT SUMMARY:Model calculation for nucleon-induced $^{6\,7}$Li reactions DTSTART:20220727T182400Z DTEND:20220727T183600Z DTSTAMP:20260420T153400Z UID:indico-contribution-951@indico.frib.msu.edu DESCRIPTION:Speakers: Xiaojun Sun (Guangxi Normal University)\n\nBased on the statistical theory of light nucleus reactions\, the description of the complicated emission processes of proton and light composite charged part icles are further improved through considering the effects of Coulomb barr iers both in incident and different outgoing reaction channels. Moreover\, the analysis of the reaction channels including the sequential and simult aneous emission processes for p + $^7$Li reaction is performed in detail. So the partial spectra of all of outgoing particles are also obtained for different reaction processes. The calculated double-differential cross sec tions of total outgoing proton\, deuteron\, and triton at Ep =14 MeV agree well with the available experimental data for different outgoing angles. The ENDF-6 formatted data\, which includes all of the reaction cross secti ons\, elastic angular distributions\, double-differential cross sections o f nucleon\, and light composite charged particles for the p + 7Li reaction \, are also obtained by PUNF code.\nRegarded as important for applications and theoretical studies\, the differential cross sections of the emitted triton for the neutron-induced $^6$Li reaction at low incident energies we re calculated\, based on the zero-range distorted-wave Born approximation theory with the assumption of $^6$Li nucleus consisting of t +$^3$He or d + α. As a function of widths and excited energies of the discrete energy levels\, an effective excited energy formula was proposed to describe thei r partial contributions. In addition\, the optical model potential paramet ers\, which had been successfully used to reproduce the double-differentia l cross sections of the emitted neutrons in our previous works in incident energy range from 5.0 to 20.0 MeV were extended in a low-energy range fro m 1.0 eV to 3.0 MeV in this paper. The calculated results agreed well with the measured differential cross sections recently published in 2020 and w ere further consistent with the measured angle-integrated cross sections. This indicates that the knock-out process and heavy-particle knockout proc ess were dominant in an energy range from 1.0 eV to 3.0 MeV\, whereas the shapes of the measured angular distributions in incident energy range from 0.1 to 1.0 MeV could be successfully explained by the Hauser-Feshbach mod el.\n\nReferences\n[1]PHYSICAL REVIEW C 103\, 044611 (2021)\n[2] PHYSICAL REVIEW C 101\, 034616 (2020)\n\nhttps://indico.frib.msu.edu/event/52/contr ibutions/951/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/951/ END:VEVENT BEGIN:VEVENT SUMMARY:Modern Description of Nuclear Structure and Reactions: The Deforme d QRPA Transition Densities for Inelastic Scattering Descriptions DTSTART:20220727T150900Z DTEND:20220727T152100Z DTSTAMP:20260420T153400Z UID:indico-contribution-939@indico.frib.msu.edu DESCRIPTION:Speakers: Sophie Péru (CEA\, DAM\, DIF)\, Jutta Escher\, Wali d Younes (Lawrence Livermore National Laboratory)\, Emanuel Chimanski (Ins tituto Tecnológico de Aeronáutica)\n\nNuclear structure and inelastic sc attering have key roles in the study of the origin of elements in the Univ erse as well as in the modern medical treatments. A precise knowledge of r eaction rates and particle absorption are of fundamental importance in the mass aggregation mechanism of r-process and increase the accuracy of radi o isotopes production and radiation therapies. The theoretical description of such events is required to supplement or even provide the necessary nu clear data. For example\, inelastic scattering calculations can provide di rect and indirect information about reactions involving unstable targets\, systems where measurements cannot be performed due to the fast decay of t he nuclei involved. Most of today’s nuclei of interest are not spherical and the extra degrees of freedom associated with their deformation increa ses the complexity of the calculations. We are improving the predictive po wer of nuclear reaction calculations by combining a modern reaction formul ation with the state-of-the-art nuclear structure description. We have ext ended the transition density formalism to reactions with deformed targets in an axially deformed QRPA (Quasi-Particle Random Phase Approximation) fr amework. Folding with an effective interaction provides the necessary ingr edients to perform inelastic scattering predictions. One of our objective s is to obtain cross-sections for data evaluations and enable the indirect determination of neutron capture cross-sections for s-process branch poin ts. Capture cross-sections for s-process branch points will be combined w ith isotopic analyses of pre-solar grains\, carried out by the Stardust co llaboration at LLNL\, will provide valuable constraints on models of stell ar evolution.\n\nhttps://indico.frib.msu.edu/event/52/contributions/939/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/939/ END:VEVENT BEGIN:VEVENT SUMMARY:Statistical properties of neutron-rich strontium isotopes DTSTART:20220728T145000Z DTEND:20220728T151400Z DTSTAMP:20260420T153400Z UID:indico-contribution-966@indico.frib.msu.edu DESCRIPTION:Speakers: Adriana Sweet (LLNL)\n\nOur understanding of neutron -induced reactions on nuclei far from stability\nhas far reaching implicat ions for cosmogenic nucleosynthesis and fundamental\nnuclear physics. Dire ct measurement of the radiative-capture cross section is experimentally in accessible for these short-lived nuclei\; however\, indirect methods such as the $\\beta$-Oslo Method enable the experimental constraint of key nucl ear properties that are inputs for reaction-theory calculations.\n\nAn exp eriment to determine the $\\gamma$-ray strength function ($\\gamma$SF) and nuclear level density (NLD) for $^{94\,95\,96}$5Sr isotopes using high-in tensity Californium Rare Isotope Breeder Upgrade (CARIBU) beams is being p erformed at Argonne National Laboratory (ANL). The $\\gamma$SF and NLD\, p roperties extracted from the measured $\\gamma$-ray spectra using the $\\b eta$-Oslo Method\, contribute the greatest uncertainty in Hauser-Feshbach calculations of neutron-capture reaction rates for short-lived neutron-ric h nuclei. The experimental techniques and preliminary results of this work will be presented. Furthermore\, the results of this work will shed light on nuclear structure properties for Sr isotopes\, leading to significantl y improved predictive reaction modeling.\n\nPrepared by LLNL under Contrac t DE-AC52-07NA27344.\n\nhttps://indico.frib.msu.edu/event/52/contributions /966/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/966/ END:VEVENT BEGIN:VEVENT SUMMARY:INDEN evaluation of neutron-induced reactions on $^{239}$Pu DTSTART:20220728T170400Z DTEND:20220728T171600Z DTSTAMP:20260420T153400Z UID:indico-contribution-973@indico.frib.msu.edu DESCRIPTION:Speakers: Roberto Capote (IAEA NDS)\n\nA comprehensive reevalu ation of $^{239}$Pu transport cross sections from subthermal energies up t o 30 MeV within the INDEN collaboration is presented. Softer prompt fissio n neutron spectra (PFNS) for thermal neutron-induced fission with an avera ge energy of 2.08 MeV from the IAEA evaluation is combined with new resona nce parameters and new nubar evaluation to preserve the good criticality p erformance of the ENDF/B-VIII.0 evaluation for plutonium thermal solution (PST) benchmarks. A new LANL PFNS evaluation\, based on ChiNu and CEA data \, is used in the fast energy region above 500 keV. A new evaluation of th e fast neutron cross sections based on updated Neutron Standard fit for th e fission channel (including fissionTPC data and covariances updated with templates of expected measurement uncertainties) and EMPIRE nuclear reacti on modeling was undertaken. A soft rotator optical model potential that co uples the ground state rotational band with K$^{\\pi}$=1/2+ and the octupo lar rotational band with K$^{\\pi}$=1/2- starting at 469 keV is employed t o obtain consistent scattering cross sections in the fast neutron range. D WBA inelastic scattering to the continuum is included to get a better agre ement with 14 MeV Kammerdiener double differential cross section data. The calculated (n\,2n) cross section is in good agreement both with latest CE A measurements by Meot et al and with ENDF/B-VIII.0 evaluation. \nThis new INDEN evaluation is shown to improve benchmark performance for Livermore 14-MeV Pulsed Spheres compared to ENDF/B-VIII.0 (Fig. 1) and preserve the good criticality performance of the ENDF/B-VIII.0 file. \n\nFig. 1: The IN DEN evaluation p27 performs better in predicting LLNL pulsed sphere neutro n spectra for a Pu sphere than ENDF/B-VIII.0 and INDEN p26 compared with d ata (UCID-16372).\n\nhttps://indico.frib.msu.edu/event/52/contributions/97 3/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/973/ END:VEVENT BEGIN:VEVENT SUMMARY:Improving nuclear data evaluations with predictive reaction theory and indirect measurements DTSTART:20220728T151400Z DTEND:20220728T152600Z DTSTAMP:20260420T153400Z UID:indico-contribution-967@indico.frib.msu.edu DESCRIPTION:Speakers: Jutta Escher (Lawrence Livermore National Laboratory )\n\nThe availability of reliable nuclear data with quantified uncertainti es is essential for basic and applied science. The last decade has seen mu ch progress in the development of theory tools that allow us to achieve mo re accurate evaluations for compound (statistical) nuclear reactions. Inte grated nuclear structure and reaction descriptions provide the basis for a chieving consistent evaluations across multiple isotopes and also enable i ndirect (surrogate) measurements of cross sections that are difficult to m easure directly. This is particularly important for applications involving reactions with unstable nuclei\, such as multi-physics simulations undert aken to understand stellar evolution and the synthesis of the elements.\n\ nI will discuss recent advances at the intersection of direct and compound -nuclear reactions. Progress made in describing direct reactions that pop ulate doorway states has provided new insights into the formation of compo und nuclei and enabled indirect measurements of compound-nuclear reactions . The reaction descriptions require the integration of nuclear-structure information that is not part of typical reaction calculations\, as well as explicitly accounting for higher-order reaction processes. I will summar ize the extensions of the theory and the experimental evidence that prompt ed them. The theory developments have enabled the successful extraction of neutron-capture cross sections from measurements of transfer reactions wi th stable beams [1\,2]. I will discuss the use of inelastic scattering as another indirect (surrogate) mechanism\, the feasibility of determining ( n\,2n) and other desired cross sections\, and possible experiments at radi oactive-beam facilities. \n\n[1] Escher et al.\, PRL 121\, 052501 (2018)\ n[2] Ratkiewicz et al.\, PRL 122\, 052502 (2019)\n\n*This work is performe d under the auspices of the U.S. Department of Energy by Lawrence Livermor e National Laboratory under Contract DE-AC52-07NA27344. Support from the L aboratory Directed Research and Development Program at LLNL\, Projects No. 19-ERD-017\, 20-ERD-030\, 21-LW-032\, 22-LW-029\, is acknowledged.\n\nhtt ps://indico.frib.msu.edu/event/52/contributions/967/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/967/ END:VEVENT BEGIN:VEVENT SUMMARY:Influence of fission fragment distributions on prompt emission qua ntities DTSTART:20220725T165400Z DTEND:20220725T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-597@indico.frib.msu.edu DESCRIPTION:Speakers: Anabella Tudora\n\nThe influence of fragment distrib utions (experimental or theoretical) on the prompt emission results deserv es a special investigation\, as a part of methods and procedures used for the validation of fission fragment distributions. Such investigations are based on the primary model results (which consist of matrices of different prompt emission quantities as a function of fragment A\, Z and its kineti c energy) already validated by their good description of existing experime ntal data. These validated matrices are then averaged over the studied fis sion fragment distributions. This paper includes the investigation of the influence of 4 fragment distributions Y(A\,TKE) (three experimental and o ne theoretical) of 235U(nth\,f) and 3 distributions (2 experimental and on e theoretical) of 252Cf(SF) on prompt emission model results (as single di stributions\, e.g. prompt neutron multiplicity ν(A)\, ν(TKE) and centre- of-mass energy <ε>(A)\, <ε>(TKE) etc. and total average values\, e.g. < ν>\, <ε>\, prompt neutron spectra\, prompt γ-ray energy etc.).\nThe ant i-correlation between the single fragment distribution TKE(A) and the dist ribution of total excitation energy of fully accelerated fragments TXE(A) reflected in the distribution of prompt neutron multiplicity of fragment p air νpair(A) is envisaged. The important role played on the distributions of different prompt emission quantities as a function of A by both the fi ssion fragment distribution and the energy partition in fission is highlig hted. Other correlations related to Y(TKE) and prompt emission quantities as a function of TKE as well as the role played by Y(A\,TKE) on different total average prompt mission quantities are discussed\, too.\n\nhttps://i ndico.frib.msu.edu/event/52/contributions/597/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/597/ END:VEVENT BEGIN:VEVENT SUMMARY:Fission yield model for astrophysical use based on the four-dimens ional Langevin model DTSTART:20220725T170600Z DTEND:20220725T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-598@indico.frib.msu.edu DESCRIPTION:Speakers: Kohsuke Tsubakihara\, Mark Usang\, Satoshi Chiba\, T aiki Kouno\, Xuan Zhang\, Chikako Ishizuka\n\nNuclear fission is expected to play an essential role in the r-process nucleosynthesis via the fission recycling process. However\, the impact of the fission recycling process on the r-process is still unclear due to the ambiguity of the fission yiel ds for nuclei far from the beta-stability line and superheavy nuclei.\n\nO ur four-dimensional Langevin model can reproduce experimental nuclear fiss ion properties\, such as fission fragment mass distributions and total kin etic energies in a systematical manner including their sudden change due t o shell structure. Then we developed a phenomenological yield model for nu clei Z=92 to 122\, ranging from neutron deficient to very neutron-rich one s\, by fitting the fission fragment mass yield obtained by the Langevin mo del with five Gaussians. We use the charge distributions for each isobar b ased on a parametrization which we have evaluated based on thousands of ex perimental data of actinides\, to obtain the fission yields in the form of (Z\, N) distribution.\n\nWhat is unique here is that sudden change of the mass distribution from 2-peak to 1-peak structure for the region of Fm-25 6\, and appearance of 5-peak structure for superheavy nuclei are predicted by the 5-D Langevin calculation\, and these features are taken into accou nt.\n\nhttps://indico.frib.msu.edu/event/52/contributions/598/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/598/ END:VEVENT BEGIN:VEVENT SUMMARY:Microscopic simulation of symmetric boost fission with antisymmetr ized molecular dynamics DTSTART:20220725T173000Z DTEND:20220725T174200Z DTSTAMP:20260420T153400Z UID:indico-contribution-600@indico.frib.msu.edu DESCRIPTION:Speakers: Satoshia Chiba\, Satoshi Chiba\, Akira Ono\, Chikako Ishizuka\, Jingde Chen\n\nWe present our first results for a microscopic simulation of symmetric boost fission in terms of the antisymmetrized mole cular dynamics (AMD)\, which incorporates the mean-field effects (as the T DDFT) via SLy4 effective interaction as well as stochastic 2-nucleon coll isions similar to the cascade model. Due to these features\, AMD is capabl e of obtaining not only the “expectation value” or “mean trajectory ”\, but “distributions” or “fluctuation” of observables can be o btained. We prepare the ground states of fissioning nuclei by the friction al cooling\, which yielded the nuclear mass to accuracy of 50 keV/u. Then \, each system is boosted symmetrically to split into 2 fragments. We calc ulated the total kinetic energy (TKE) and spins of the fission fragments. Dependence of the TKE on Z2/A1/3 of the fissioning system was found to be almost linearly increasing. We have also obtained orbital angular momenta of each fragment\, their mutual orientation and their orientation with res pect to the linear momenta. From this analysis\, we can elucidate origin of the spins of fission fragments\, either it is by the bending\, wrigglin g\, twisting or tilting motion. Furthermore\, we have observed several t ernary fission events\, emitting tritons or 4He from the neck region\, and average energy and angles of these ternary particles with respect to the fission axis were found to be in accord with experimental data.\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/600/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/600/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of Independent Fission Product Yields with SPIDER DTSTART:20220726T170600Z DTEND:20220726T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-618@indico.frib.msu.edu DESCRIPTION:Speakers: Christopher Prokop\, Sean Kuvin\, Jack Winkelbauer\, Shea Mosby\, Devin Connolly\, Panagiotis Gastis\n\nIndependent fission pr oduct yields (FPY)\, i.e.\, yields of fission products right after the pro mpt neutron emission\, but before beta decay\, are an important piece of d ata for nuclear fission modeling and fission applications. The Spectromete r for Ion Determination in fission Research (SPIDER)\, was developed at Lo s Alamos Neutron Science Center (LANSCE) for measuring FPYs from neutron-i nduced fission using the 2E-2v method\, eventually spanning from thermal u p to 20 MeV in incident neutron energy. SPIDER has recently undergone vari ous improvements for increasing the fidelity and resolution of the extract ed data. In particular\, a gamma-ray tagging system has been implemented f or improving the accuracy of the mass calibration by measuring strong gamm a-ray transitions from isotopes of known mass. In this presentation\, an o verview of the upgraded SPIDER system and preliminary results from FPY mea surements on $^{252}$Cf(sf)\, $^{235}$U(n$_{th}$\,f)\, and $^{239}$Pu(n$_{ th}$\,f) will be discussed. \n\n\n*This work is supported by the US Depart ment of Energy through the Los Alamos National Laboratory\, Contract No. 8 9233218CNA000001 (LA-UR-21-29666)\n\nhttps://indico.frib.msu.edu/event/52/ contributions/618/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/618/ END:VEVENT BEGIN:VEVENT SUMMARY:Modeling the angular momentum removal from fission fragments DTSTART:20220725T174200Z DTEND:20220725T175400Z DTSTAMP:20260420T153400Z UID:indico-contribution-601@indico.frib.msu.edu DESCRIPTION:Speakers: Toshihiko Kawano\, Patrick Talou\, Aurel Bulgac\, Sa ra Pozzi\, Amy Lovell\, Stefano Marin\, Ionel Stetcu\n\nFission fragment p roperties are set\, to a large extent\, during the scission process. It is generally assumed that the fully accelerated fission fragments can be tre ated as compound nuclei\, and their de-excitation towards a long-lived sta te via prompt neutron and gamma emissions can be treated within a statisti cal model like the Hauser-Feshbach approach to nuclear reactions. Accurate modeling of prompt fission neutrons\, and to a lesser extent prompt fissi on gamma-rays\, is important\, as measurements cannot detect fission fragm ents before neutron emission\, and have to correct for the emitted particl es to extract information about the scission process. One often makes the assumption that because most of the prompt fission neutrons are emitted wi th energies of about 1 MeV in the center-of-mass frame of the fragment\, t hey do not carry much angular momentum when emitted from fission fragments . Using our state-of-the-art code CGMF\, which treats the fission fragment s as compound nuclei\, we show that a significant number of neutrons are e mitted with angular momentum of 3/2 and higher. As a consequence of quantu m effects\, the p-wave strength function peaks in the 90 – 100 mass regi on (the Ramsauer effect)\, emphasizing the importance of higher partial wa ves for the light fission fragments even at low neutron energies. When all of the contributions to the angular momentum removal from neutrons and st atistical gamma rays (emitted before electromagnetic transitions between d iscrete levels) are counted\, we find that on average the statistical deca ys remove about 4-5 units of angular momentum\, with comparable standard d eviation. This finding can be at odds with some other statistical models a nd assumptions made in the analysis of experimental data\, and blurs the c onnection with the scission process\, making difficult a direct connection between observables before and after neutron emission. We show that we ca n reproduce the shape of the average fission fragment spins as a function of their mass\, as recently measured by Wilson et al.\, with somewhat diff erent assumptions regarding the initial spin of the fission fragment\, as illustrated in Fig. 1. We also show the impact of the known nuclear struct ure information\, in particular isomeric states\, illustrated in Fig. 1 by the difference between the CGMF results marked by green circles and purpl e pentagons. Finally\, because different models disagree on details of the angular momenta of neutrons and statistical gamma rays\, one should be aw are of the possible model dependence when interpretation for some measurem ents is given.\n\nLA-UR-21-28347\n\nhttps://indico.frib.msu.edu/event/52/c ontributions/601/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/601/ END:VEVENT BEGIN:VEVENT SUMMARY:Generation of Fragment Angular Momentum in Fission DTSTART:20220725T184500Z DTEND:20220725T190900Z DTSTAMP:20260420T153400Z UID:indico-contribution-608@indico.frib.msu.edu DESCRIPTION:Speakers: Ramona Vogt (LLNL\, UC Davis)\, Jorgen Randrup\n\nTh e origin and character of the fission fragment angular momenta are current ly topics of intense theoretical study. We describe how the angular-momen tum bearing modes of the evolving dinuclear complex are being agitated at different rates by multiple transfers of individual nucleons\, the mechani sm long understood to be the primary cause of the transport phenomena disp layed by damped nuclear reactions\, including the generation of the angula r momenta of the fragments [1\,2]. The resulting fragment angular momenta are predominantly perpendicular to the fission axis and\, although they a re built up from collective rotational modes in which the two spins are hi ghly correlated\, they nevertheless emerge as largely independent [3\,4]\, a feature supported by recent experimental data [5].\n\nThe fission simul ation code FREYA [6]\, which treats angular momentum as suggested by the n ucleon-exchange mechanism\, presents a powerful tool for exploring observa tional consequences of the correlated fragment spin distributions and a nu mber of examples will be discussed. For example\, there is a marked corr elation between the fragment spin magnitudes and the photon multiplicity [ 4].\n\n[1] J. Randrup\, Transport of angular momentum in damped nuclear re actions\, Nucl. Phys. A **383**\, 468 (1982).\n\n[2] T. Dossing and J. Ran drup\, Dynamical evolution of angular momentum in damped nuclear reactions : (I) Accumulation of angular momentum by nucleon transfer\, Nucl. Phys. A **433**\, 215 (1985).\n\n[3] J. Randrup and R. Vogt\, Generation of fragm ent angular momentum in fission\, Phys. Rev. Lett. **127**\, 062502 (2021) .\n\n[4] R. Vogt and J. Randrup\, Angular momentum effects in fission\, Ph ys. Rev. C **103**\, 014610 (2021).\n\n[5] J. Wilson *et al.*\, Angular mo mentum generation in nuclear fission\, Nature **590**\, 566 (2021).\n\n[6] J.M. Verbeke\, J. Randrup\, and R. Vogt\, Fission Reaction Event Yield Al gorithm FREYA 2.0.2\, Comp. Phys. Comm. **222**\, 263 (2018).\n\nhttps://i ndico.frib.msu.edu/event/52/contributions/608/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/608/ END:VEVENT BEGIN:VEVENT SUMMARY:Novel Fully Microscopic Description of Fission: Odd-Even Staggerin g\, Charge Polarization and Machine Learning DTSTART:20220725T190900Z DTEND:20220725T192100Z DTSTAMP:20260420T153400Z UID:indico-contribution-610@indico.frib.msu.edu DESCRIPTION:Speakers: Irene Kim\, David Regnier\, Nicolas Schunck\, Petar Marevic\, Marc Verriere\n\nNuclear fission is the fundamental mechanism th at determines energy production in nuclear power plants. Predictive fissio n models are necessary for national security applications and are also key to explain the relative abundances of the elements in the universe. In th e first part of this talk\, we present a novel approach based on particle- number restoration techniques in the fission fragments to predict the pren eutron fragment distributions. We show that we can obtain for the first ti me a qualitatively good description of the mass and charge yields Y(Z\, A) using such microscopic approaches. In addition\, our method can also desc ribe fine-structural effects such as the odd-even staggering in the charge yields and the charge-polarization of the fission-fragments distributions . In the second part of this talk\, we outline a new machine-learning fram ework to predict microscopic configurations at different nuclear deformati ons.\n\n**Acknowledgments:** This work was supported in part by the NUCLEI SciDAC-4 collaboration DE-SC001822 and was performed under the auspices o f the U.S.\\ Department of Energy by Lawrence Livermore National Laborator y (LLNL) under Contract DE-AC52-07NA27344. Computing support came from the LLNL Institutional Computing Grand Challenge program. Support was also pr ovided by the LLNL Laboratory Directed Research \\& Development (LDRD) 21- ERD-001.\n\n**Release number:** LLNL-ABS-827074\n\nhttps://indico.frib.msu .edu/event/52/contributions/610/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/610/ END:VEVENT BEGIN:VEVENT SUMMARY:Correlations of Gamma-Ray Emission Between Fission Fragments: Expe rimental and Theoretical Challenges DTSTART:20220725T192100Z DTEND:20220725T193300Z DTSTAMP:20260420T153400Z UID:indico-contribution-611@indico.frib.msu.edu DESCRIPTION:Speakers: Shaun Clarke\, Mustafa Stephan Okar\, Sara Pozzi\, S tefano Marin\n\nFollowing the binary fission process\, the two energetic f ission fragments radiate their energy and angular momenta in the form of n eutron and gamma-ray emission. These electrically neutral particles repres ent important signatures of fission in non-destructive assay of nuclear ma terial and an analysis of the emitted radiation can be used to characteriz e the fissioning source. The emission of neutrons and gamma rays often rep resents the only probe we have of the nuclear fission process and the stat e of the fragments immediately following fission. Recent theoretical and e xperimental results have sparked renewed interest in the correlations betw een fission fragments. Of particular interest are the correlations between the fission fragment angular momenta. The most important observable relat ed to the fission fragment angular momenta is the emission of gamma rays. It is thus of current interest to determine the correlations in the emissi on of gamma rays between fragments. While several conflicting models exist to model these correlations\, experimental data is limited or inconclusiv e. In this work\, we review the theoretical models showing how different m odels can give rise to differences in the gamma-ray emission correlations. We then review the experimental evidence\, highlighting the experimental challenges involved and the expected systematic biases. Lastly\, we presen t novel experimental techniques that allow us\, for the first time\, to di rectly determine the desired gamma-ray correlations. The technique general izes the Maier-Leibniz Doppler-Shift method. In the original technique\, t he average yield of gamma rays is inferred from the small aberration of ga mma-rays due to the speed of the emitting fragments. We have derived new s ets of equations based on the same assumptions\, showing that the aberrati on of gamma rays can be exploited to determine the second moment of the mu ltiplicity distribution of gamma rays\, i.e.\, the variances of the distri butions and their covariance. We discuss this new technique\, its applicab ility\, and the experimental setups required to utilize it.\n\nhttps://ind ico.frib.msu.edu/event/52/contributions/611/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/611/ END:VEVENT BEGIN:VEVENT SUMMARY:Angular momentum of spherical fission products: experimental and t heoretical aspects DTSTART:20220725T193300Z DTEND:20220725T194500Z DTSTAMP:20260420T153400Z UID:indico-contribution-612@indico.frib.msu.edu DESCRIPTION:Speakers: Y. H. Kim\, Jehaan Nicholson\, Olivier Litaize\, Oli vier Meplan\, Christophe Sage\, Mourad Rahmdame\, Abdelaziz Chebboubi\, Ul li Koester\, Grégoire Kessedjian\, Olivier Serot\n\nDespite the numerous theoretical [1] and experimental [2] works published very recently\, the w ay in which fission fragments acquire their angular momentum is still an o pen question. This angular momentum generation mechanism is important not only for improving our understanding of the fission process\, but also for nuclear energy applications\, since fission fragments angular momentum st rongly impact the prompt gamma spectra and consequently decay heat in a re actor.\nIn this context\, within the framework of a collaboration between the ‘Laboratoire de Physique Subatomique et Corpusculaire’ (LPSC\, Fra nce)\, the ‘Institut Laue Langevin’ (ILL\, France) and the CEA-Cadarac he (France)\, an experimental program was developed on the LOHENGRIN mass- spectrometer with the aim of measuring isomeric ratio of some fission prod ucts for different thermal neutron induced fission reactions. This present ation will be focused on results obtained for the spherical nucleus 132-Sn following thermal neutron induced fission of both 235-U and 241-Pu target s. To further constrain the angular momentum generation models\, 132-Sn is omeric ratio (IR) is measured as a function of its kinetic energy (Ek). Th e angular momentum is determined by combining our experimental data with c alculations performed with the FIFRELIN Monte-Carlo code [3]. A clear angu lar momentum decrease with Ek is observed for both reactions. A comparison of the present work with the predictions of the Madland-England model [4] \, the GEF [5] code and the FIFRELIN code will be also discussed.\nLastly\ , we investigate the dependence of the 132-Sn angular momentum with the in cident neutron energy\, from thermal region up to the first chance fission . For that\, the four free available parameters in FIFRELIN are selected i n order to reproduce the average prompt neutron multiplicity. In this way\ , the angular momentum is deduced for each neutron energy. These results a re discussed in terms of the impact of the fission fragment deformation at scission on the spin assignment.\n\n**References**\n[1] J. Randrup and R. Vogt\, Phys. Rev. Lett. 127\, 062502 (2021)\, and references therein\n[2] C.J. Sears et al.\, Nuclear Data Sheets 173 (2021) 118–143\, and refere nces therein\n[3] O. Litaize\, O. Serot\, and L. Berge\, Eur. Phys. J. A 5 1\, 177 (2015)\n[4] D. G. Madland and T. R. England\, Nucl. Sci. Eng. 64\, 859 (1977)\n[5] K. H. Schmidt et al.\, Nucl. Data Sheets 131\, 107 (2016) \n\nhttps://indico.frib.msu.edu/event/52/contributions/612/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/612/ END:VEVENT BEGIN:VEVENT SUMMARY:New Results in the Modeling of Fission and Radiative Neutron Capt ure with FIFRELIN DTSTART:20220726T131200Z DTEND:20220726T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-604@indico.frib.msu.edu DESCRIPTION:Speakers: David Lhuillier (CEA)\, Olivier Serot (CEA)\, Grégo ire Kessedjian (CEA)\, Thomas Materna (CEA)\, Valentin Piau (CEA)\, Alf G öök (KTH Royal Institute of Technology)\, Stephan Oberstedt (EC-JRC)\, D . Mancusi (CEA)\, T. Ogawa (JAEA)\, Achment Chalil\, Abdelhazize Chebboubi (CEA)\, Frank Gunsing (CEA)\, Andreas Oberstedt (ELI-NP)\, LoÏc Thullie z (CEA)\, Olivier Litaize (CEA)\n\nThe nuclear de-excitation process (thro ugh neutron\, gamma and electron emission) simulated by the Monte Carlo co de FIFRELIN [1] has been improved recently and compared with results from fission and radiative neutron capture experiments. Several examples will b e presented during this conference.\n\nFirstly\, the initial goal of the c ode is to predict fission observables and associated correlations. That wa y a dedicated fission experiment has been performed at JRC Geel involving a fission chamber and several neutron and gamma scintillators (VESPA). FIF RELIN code has been used to calculate the relevant observables and especia lly the average neutron and gamma multiplicities as a function of fission fragment mass and kinetic energy [2]. Up to now it was very difficult to o btain a reasonable agreement for both neutron and gamma multiplicities wit hin the same code using a unique set of model parameters. New calculations performed with HFB microscopic combinatorial level densities are in very good agreement with measured neutron and gamma multiplicities (as a functi on of mass or total kinetic energy). \nSecondly\, the code is used to est imate\, among others\, the gamma and electron cascades resulting from a ne utron capture reaction. In a context of electron antineutrino spectrum emi tted in a research reactor\, the simulation of the STEREO compact detector was recently improved by applying the FIFRELIN 155\,157Gd(nth\,g) cascade s [3]. As the detection efficiency has to be controlled to the %-level\, a precise description of gamma cascades in Gd is necessary. The nuclear lev el scheme constructed from the RIPL-3 database and extended to initial cap turing state at neutron separation energy has been updated with dedicated latest data from the EGAF database. Finally\, a calculation of the angular distribution of gamma rays has been included in the code\, with a perfect reproduction of all angular correlations [4].\nIn addition\, FIFRELIN has been coupled with the depletion code DCHAIN to estimate delayed fission c omponents and first results will be briefly presented [5].\n\n[1] O. Litai ze et al.\, Eur. Phys. J. A (2015) 51:177.\n[2] M. Travar\, V. Piau et al. \, Physics Letters B 817\, 136293 (2021).\n[3] H. Almazán et al.\, Eur. P hys. J. A (2019) 55:183.\n[4] A. Chalil et al.\, submitted to EPJA.\n[5] T . Ogawa\, private communication.\n\nhttps://indico.frib.msu.edu/event/52/c ontributions/604/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/604/ END:VEVENT BEGIN:VEVENT SUMMARY:Simulation and design of a new ion guide for neutron-induced fissi on at the IGISOL facility DTSTART:20220726T133600Z DTEND:20220726T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-606@indico.frib.msu.edu DESCRIPTION:Speakers: Stephan Pomp\, Ali Al-Adili\, Simone Cannarozzo\, An dreas Solders\, Matthias Lantz\, Zhihao Gao\n\nIndependent fission yield s in neutron-induced fission at high neutron energy is important fo r the understanding of the fission process\, and it is also in relevant fo r reactor physics applications. So far\, measurements of independent fissi on yields in proton-induced fission has been performed at the IGISOL facil ity at the University of Jyväskylä\, using the Penning trap as a high re solving-powermass-filter. In order to also facilitate neutron-induced mea surements\, a dedicated ion guide and a proton-to-neutron converter was developed. However\, the first measurements [1] indicate that fewe r fission products than expected reach the Penning trap. To explore poten tial reasons and possible improvements\, a simulation model was developed [2\, 3] and benchmarked [4]. The benchmark showed that the model is able to reproduce the performance of the ion guide remarkably well\, but tha t the neutron flux from the converter has been over-estimated.\n\ nBased on the benchmark\, the parameters of the setup\, including the geometry of neutron converter\, the distance from the converter to the uranium targets\, and the size of the uranium targets and volume of t he ion guide\, have been optimized with regards to the production of fissi on products. However\, the collection efficiency of the ion guide still limits the intensity of extracted fission products.\n\nTo significant ly improve the collecting efficiency\, as well as the extraction time\, an electric field guidance system\, inspired by the RF-system used in the CARIBU gas catcher [5]\, is considered to be deployed. In the gas catcher\, fission products are prevented from hitting the walls of t he ion guide by the RF-structure\, and are guided by a DC electric field toward an extraction nozzle. With this poster we present the design of the guiding system for the IGISOL ion guide\, as well as a simulation model for estimates of the extraction yields of fission products from the ion guide.\n\nRferences:\n[1] A. Mattera et al. Production of sn and sb i sotopes in high-energy neutron-induced fission of $^{nat}$U. Eur. Phys. J. A\,54:33\, 2018.\n[2] A. Al-Adili et al. Simulations of the fission-prod uct stopping efficiency in IGISOL.Eur. Phys. J. A\,51:59\, 2015.\n[3] K. Jansson et al. Simulated production rates of exotic nuclei from the ion gu ide for neutron-induced fission at IGISOL. Eur. Phys. J. A\,53:243\, 2017. \n[4] Zhihao et al.Benchmark of simulation of the ion guide for neutron-i nduced fission products. Submitted to Eur. Phys. J. A.\n[5] G. Savard\, A .F. Levand\, and B.J. Zabransky. The caribu gas atcher. Nucl.Inst. Meth. B\,376:246–250\, 2016.\n\nhttps://indico.frib.msu.edu/event/52/contribut ions/606/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/606/ END:VEVENT BEGIN:VEVENT SUMMARY:The fast neutron induced fission of actinide nuclei-TKE and Mass D istributions DTSTART:20220726T163000Z DTEND:20220726T164200Z DTSTAMP:20260420T153400Z UID:indico-contribution-615@indico.frib.msu.edu DESCRIPTION:Speakers: Alexander Chemey\, Ashley Pica\, Walter Loveland\n\n The study of the fast neutron (En = 3-100 MeV) induced fission of actinide nuclei allows us to study the relative role of Coulomb and dissipative fo rces in a large scale nuclear collective motion. One is aware of the prac tical applications of knowing the energy release and its dependence on neu tron energy and fragment mass. We have been engaged in studies of the tota l kinetic energy release in the fast neutron induced fission of 232Th\, 23 3U\, 235U\, 237Np and 239Pu\, which we will summarize. We have prepared t he targets for these studies by vapor deposition which leads to very unifo rm\, high purity targets\, an essential component of such studies.\n\nOur experiments were done at the LANSCE facility at LANL using the WNR “whit e” neutron spectrum beams\, with typical intensities of 105 n/s. The ne utron energies were measured by time of flight with typical uncertainties of 5%. Fission fragments were detected by 9 pairs of Si PIN diode detector s. Corrections were applied for the pulse height defect of the detectors a nd the fragment energy loss in the target and backing. Our apparatus\, tar gets\, etc. were benchmarked by measuring the TKE release in the thermal n eutron induced fission of 233U\, 235U and 239Pu. No normalizations of the data were needed and thus our measurements are absolute measurements.\n\nT he TKE distributions for each system studied were Gaussian in shape. In F igure 1\, we show the measured TKE values (as a function of neutron energy ) for several of the systems we have studied. The data are in good agreem ent with previous work with some deviations at higher energies. The data c an be parameterized in terms of Viola scaling. The variances of the TKE d istributions show jumps at neutron energies corresponding to 2nd\, 3rd\, e tc\, chance fission. \nThe fission mass distributions show the expected e volution from asymmetric fission at low neutron energies to symmetric fiss ion at higher neutron energies. The data clearly show the importance of sh ell closures near A=134 reflecting the extra stability of Z=56\, due to oc tupole deformation. The data are in general agreement with the predictions of the GEF model but with smaller jumps in the TKE release at nth chance fission energies.\n\nhttps://indico.frib.msu.edu/event/52/contributions/61 5/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/615/ END:VEVENT BEGIN:VEVENT SUMMARY:Experimental Prompt Fission Neutron Spectra for the $^{235\,238}$U (n\,f)\, $^{239}$Pu(n\,f)\, and $^{240\,242}$Pu(sf) Reactions DTSTART:20220726T164200Z DTEND:20220726T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-616@indico.frib.msu.edu DESCRIPTION:Speakers: Denise Neudecker\, John O'Donnell\, Jack Henderson\, Jamie A. Gomez\, Roger Henderson\, Ching-Yen Wu\, Eames Bennett\, John L. Ullmann\, Robert Haight\, Nicolaos Fotiades\, Matthew Q. Buckner\, Keegan Kelly\, Matthew Devlin\n\nThe Chi-Nu project at the Los Alamos Neutron Sc ience Center (LANSCE) continues to measure Prompt Fission Neutron Spectra (PFNS) as accurately and completely as possible\, with fully understood un certainties including uncertainty correlations. These measurements use the LANSCE/WNR white-spectrum neutron beam and cover incident neutron energie s from below 1 MeV to 20 MeV\, and were originally focussed on the major a ctinides. However\, the program has grown to include PFNS measurements for neutron-induced fission of $^{240}$Pu\, as well as some spontaneous fissi oning nuclei. Two neutron detector arrays are used\, combined with multi-c ell Parallel Plate Avalanche Counters[3] or a single-cell fission chamber (for $^{242}$Pu) for fission detection. Detailed Monte Carlo simulations o f the experimental setup were used to model the neutron response and deter mine PFNS for each case\, as a function of incident neutron energy for the neutron-induced cases. The experimental details are discussed in detail i n Ref. [1].\n\nTo date\, Chi-Nu PFNS data have been reported on neutron-in duced fission of $^{239}$Pu[1] and $^{235}$U[2]\, and data on neutron-indu ced fission of $^{238}$U and spontaneous fission of $^{242}$Pu and $^{240} $Pu have been taken. These data will be presented and compared with prior data and current evaluations. All of these data sets were taken using simi lar detector arrangements and analysis methods\, so comparisons of the PFN S of the various isotopes can be made with improved accuracy\, as some of the uncertainties are similar in all cases. We will discuss a few such com parisons. Such comparisons will also be discussed and compared to evaluati ons and integral experiment results.\n\nThis work is supported by the U.S. Department of Energy under Contracts No. 89233218CNA000001 (LANL) and DE- AC52-07NA27344 (LLNL).\n\n[1] K.J. Kelly\, et al.\, Phys. Rev. C 102\, 034 615 (2020).\n[2] M. Devlin\, et al.\, Nucl. Data Sheets 148\, 322 (2018).\ n[3] C.-Y. Wu\, et al.\, Nucl. Instr. And Meth. A794\, 76 (2015).\n\n\nLA- UR-21-29659\n\nhttps://indico.frib.msu.edu/event/52/contributions/616/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/616/ END:VEVENT BEGIN:VEVENT SUMMARY:Fission Product Yields from Neutron-Induced Fission of Major Actin ides at 6.5 MeV DTSTART:20220726T165400Z DTEND:20220726T170600Z DTSTAMP:20260420T153400Z UID:indico-contribution-617@indico.frib.msu.edu DESCRIPTION:Speakers: Jack Silano\, Werner Tornow\, Fnu Krishichayan\, Cal vin Howell\, Jerry Wilhelmy\, Matthew Gooden\, Anthony Ramirez\, Mark Stoy er\, Anton Tonchev\, Sean Finch\, Ronald Malone\n\nFission product yields (FPY) are an important observable for fundamental and applied nuclear phys ics. We are conducting a comprehensive study of the cumulative FPY from ne utron-induced fission of $^{235}$U\, $^{238}$U\, and $^{239}$Pu between 0. 5 and 15 MeV at the Triangle Universities Nuclear Laboratory. Actinide foi ls are irradiated using monoenergetic neutron beams produced by a tandem a ccelerator. The activation foils are placed in a dual fission chamber with thin reference foils of the same isotope to determine the total number of induced fission events in the target. Fission products in the sample are identified following gamma-ray spectra measurements with high-purity germa nium detectors in a low-background counting facility. Gamma rays from deca y of about 40 fission products with half-lives between 10 minutes and a fe w days have been measured after 1 hour of irradiation. Details of the expe riment setup and preliminary results for FPY at a neutron energy of 6.5 Me V will be presented.\n\nThis work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.\n\nhttps://indico.frib.msu.edu/event/52/contri butions/617/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/617/ END:VEVENT BEGIN:VEVENT SUMMARY:The Extension of the Deterministic Hauser-Feshbach Fission Fragmen t Decay Model to Multi-chance Fission and its Extension to $^{239}$Pu DTSTART:20220726T171800Z DTEND:20220726T173000Z DTSTAMP:20260420T153400Z UID:indico-contribution-619@indico.frib.msu.edu DESCRIPTION:Speakers: Matthew Mumpower\, Patrick Talou\, Shin Okumura\, Io nel Stetcu\, Toshihiko Kawano\, Amy Lovell\n\nThe Hauser-Feshbach fission fragment decay model HF$^3$D calculates the statistical decay of fission f ragments through both prompt and delayed neutron and $\\gamma$-ray emissio ns in a deterministic manner. While previously limited to the calculation of only first-chance fission\, the model has recently been extended to in clude multi-chance fission\, up to neutron incident energies of 20 MeV. T he deterministic decay takes as input pre-scission quantities—fission pr obabilities\, pre-fission neutron energies\, and the average energy causin g fission—and post-scission quantities—yields in mass\, charge\, total kinetic energy\, spin\, and parity. From those fission fragment initial conditions\, the full decay is followed through both prompt and delayed pa rticle emissions. The evaporation of the prompt neutrons and $\\gamma$ ra ys is calculated through the Hauser-Feshbach statistical theory\, taking i nto account the competition between neutron and $\\gamma$-ray emission\, c onserving energy\, spin\, and parity. The delayed emission is taken into account using time-independent calculation using decay data. This whole f ormulation allows for the calculation of prompt neutron and $\\gamma$-ray properties\, such as multiplicities and energy distributions\, both indepe ndent and cumulative fission yields\, and delayed neutron observables\, in a consistent framework. Here\, we describe the implementation of multi-c hance fission into the HF$^3$D model\, and show an example of prompt and d elayed quantities beyond first-chance fission\, using the example of neutr on-induced fission on $^{239}$Pu. This expansion represents significant p rogress in consistently modeling the emission of prompt and delayed partic les from fissile systems.\nLA-UR-21-28700\n\nhttps://indico.frib.msu.edu/e vent/52/contributions/619/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/619/ END:VEVENT BEGIN:VEVENT SUMMARY:Energy Dependent Fission Product Yields from Neutron Induced Fissi on DTSTART:20220726T183900Z DTEND:20220726T185100Z DTSTAMP:20260420T153400Z UID:indico-contribution-621@indico.frib.msu.edu DESCRIPTION:Speakers: Nicolas Schunck\, Fnu Krishichayan\, Roger Henderson \, Sean Finch\, Matthew Gooden\, Jack Silano\, Anthony Ramierez\, Jerry Wi lhelmy\, Ronald Malone\, Calvin Howell\, Werner Tornow\, Mark Stoyer\, Ant on Tonchev\n\nFission product yields (FPY) are essential ingredients for a ddressing questions relevant to a range of basic and applied physics. Exam ples include the cosmic nucleosynthesis processes that created the element s from iron to uranium\, decay heat release in nuclear reactors\, reactor neutrino studies\, radioisotope production\, development of advanced react or and transmutation systems\, and many national security applications. Wh ile new applications will require accurate energy-dependent FPY data over a broad set of incident neutron energies\, the current evaluated FPY data files contain only three energy points: thermal\, fast\, and 14-MeV incide nt energies. The goal of this study is to provide high-precision and energ y dependent FPY data using monoenergetic neutron beams with energies betwe en 0.5 and 15 MeV. \n\nAbsolute cumulative fission product yields have bee n determined for about 100 fission products representing 40 mass chains du ring neutron-induced fission of 235U\, 238U\, and 239Pu. Using rapid belt- driven irradiated target transfer system (RABITTS) and irradiations with v arying duration\, gamma-ray decay history of fission products between 1 se cond to a few days have been measured. The number of fissions during the i rradiation times was determined via a dual fission ionization chamber load ed with thin electroplated foils with the same actinide material. The obta ined new FPY data provides a complete picture of the fission product yield landscape\; from the initial distribution produced directly by fission\, through the complex\, time-dependent evolution of the yields from beta-dec ay and neutron emission. This work also provides a unique capability to br idge short-lived fission product yields to our measured long-lived chain f ission yields [1]. An overview of the recent experimental results will be presented.\n \nThis work was performed under the auspices of the U.S. Depa rtment of Energy by Lawrence Livermore National Laboratory under contract DE-AC52-07NA27344.\n\n[1] M. Gooden et al.\, Nucl. Data Sheets 131\, 319 ( 2016).\n\nhttps://indico.frib.msu.edu/event/52/contributions/621/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/621/ END:VEVENT BEGIN:VEVENT SUMMARY:Measuring the $^{235}$U(n\,f)/$^6$Li(n\,t) cross section ratio in the NIFFTE fissionTPC DTSTART:20220726T185100Z DTEND:20220726T190300Z DTSTAMP:20260420T153400Z UID:indico-contribution-623@indico.frib.msu.edu DESCRIPTION:Speakers: the NIFFTE Collaboration\, Maria Anastasiou\n\nWhile nuclear data play an important role in nuclear physics applications\, it has become important to have a better understanding and try to minimize th eir uncertainties. In particular\, there is a need for precision neutron-i nduced fission cross section measurements on fissile nuclei. Neutron-induc ed fission cross sections are typically measured as ratios\, with a well-k nown standard in the denominator. While the $^{235}$U(n\,f) standard is we ll measured\, some light particle reactions are also well-known and their use as reference can provide information to remove shared systematic uncer tainties that are present in an actinide-only ratio. The NIFFTE collaborat ion’s fission time projection chamber (fissionTPC) is a 2×2π charged p article tracker designed for measuring neutron-induced fission. Detailed 3 D track reconstruction of the reaction products enables evaluation of syst ematic effects and corresponding uncertainties which are less directly acc essible by other measurement techniques. This work focuses on the recent m easurement of the $^{235}$U(n\,f) using as a reference the standard $^6$Li (n\,t) reaction. Preliminary data of the $^{235}$U(n\,f)/$^6$Li(n\,t) meas urement deployed at the Los Alamos Neutron Science Center will be presente d. \n\nLLNL-ABS-800573. This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.\n\nhttps://indico.frib.msu.edu/event/52/contri butions/623/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/623/ END:VEVENT BEGIN:VEVENT SUMMARY:Spectral averaged cross sections as a probe to a high energy tail of $^{235}$U PFNS DTSTART:20220726T190300Z DTEND:20220726T191500Z DTSTAMP:20260420T153400Z UID:indico-contribution-624@indico.frib.msu.edu DESCRIPTION:Speakers: Jan Simon\, Roberto Capote\, Michal Kostal\, Evzen N ovak\, Tomas Czakoj\, Martin Schulc\n\nThe systematic evaluations of spect rum averaged cross sections of dosimetric reactions over a broad range of energies were performed in 252Cf (spontaneous fission) and 235U(nth\,f) ne utron fields. The neutron sources used in this study were LR-0\, VR-1 zero power research light water reactors\, LVR-15 10 MW research light water r eactor\, and 252Cf high emission isotopic source with emission specified p recisely by the manganese sulphate bath. All spectral averaged cross secti ons were inferred from measured reaction rates. Reaction rates were derive d from gamma spectrometry using a high purity germanium detector with a va lidated computational efficiency determination. These gamma spectrometry m easurements were performed using single detector in all cases. The ratios of 252Cf and 235U spectral averaged cross sections can be used to specify the high energy tail of the 235U prompt fission neutron spectrum as 252Cf spontaneous fission spectrum is considered as a standard. Dosimetric cross sections were validated in 252Cf neutron field. Furthermore\, ratios are independent on cross section uncertainties since uncertainties in the cros s sections are eliminated. Theoretical models of fission can be tested bas ed on our ratios measurements. The calculations were performed in MCNP6.2 transport code using different prompt fission neutron spectra and IRDFF-II cross sections for threshold reactions. The ratios are in good agreement using only ENDF/B-VIII.0 235U prompt fission neutron spectrum suggesting h arder 235U(nth\,f) prompt fission neutron spectrum than in other evaluatio ns.\n\nhttps://indico.frib.msu.edu/event/52/contributions/624/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/624/ END:VEVENT BEGIN:VEVENT SUMMARY:New measurement of the $^{235}$U($n_{\\rm th}$\,f) fission yields and development of a Time of Flight line at the LOHENGRIN spectrometer DTSTART:20220727T130000Z DTEND:20220727T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-625@indico.frib.msu.edu DESCRIPTION:Speakers: Maxime Houdouin-Quenault (CEA)\, Olivier Guillaudin\ , David Bernard\, Olivier Litaize\, Abdelazziz Chebboubi\, Olivier Serot\, Olivier Meplan\, U. Köster\, Mourad Ramdhane\, Grégoire Kessedjian\, Y. H. Kim\, Marie-Laure Gallin-Martel\, Jean-François Muraz\, Sara Marcatil i\, Denis Dauvergne\, Christophe Sage\n\nThe study of nuclear fission yiel ds has a major impact on the characterization and understanding of the fis sion process and is mandatory for reactor applications. In the framework o f a collaboration between the CEA\, the LPSC and the ILL\, a program of ac tinide fission yields measurements has been initiated for several years at the LOHENGRIN spectrometer. However\, the measurement of very low fission yields in the symmetry region and the heavy wing of the distributions are difficult to achieve due to the strong contamination by other masses with much higher yields and require the development of a new experimental setu p.\n\nThis talk will first present the results of an absolute measurement of the $^{235}$U(n$_{th}$\,f) mass yields using an ionization chamber plac ed at the exit of the spectrometer. Although very well documented in the l iterature\, these yields show uncertainties lying from 3% to 10% with larg e discrepancies between libraries and a lack of correlation matrices. New experimental data obtained at the LOHENGRIN spectrometer will be detailed\ , along with the measurement method and the production of experimental cov ariance matrices.\n\nThe second part will show the development of a Time o f Flight (ToF) line in order to improve the background rejection in the ma ss yield measurements. In the symmetry region\, the precision of the measu rement is limited by the background estimation due to the charge exchanges with the residual gas of the separator. We foresee to analyze the events using a triple coincidence (ΔE x E) x ToF\, whereas today only ΔE x E se lection is available. The new ToF line is built using Si$_3$N$_4$ foils an d electron detectors for the start and stop detectors. The talk will prese nt the choices made for the electron detectors technology along with the p rogress achieved on the ToF line characterization.\n\nhttps://indico.frib. msu.edu/event/52/contributions/625/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/625/ END:VEVENT BEGIN:VEVENT SUMMARY:Experimental determination of fission barrier parameters DTSTART:20220727T134800Z DTEND:20220727T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-628@indico.frib.msu.edu DESCRIPTION:Speakers: Stephan Oberstedt\, M. P. Reiter\, Timo Dickel\, Jia nwei Zhao\, Alexandru Pencu\, M. Wada\, Peter Thiroff\, Andreas Oberstedt\ n\nThe multi-humped fission barrier is the result of superposing microscop ic shell corrections to the macroscopic liquid drop model [1]. A manifesta tion of that is the existence of shape isomers [2\, 3]\, as observed in se veral actinide nuclides. However\, the - most often - double-humped barrie r is much more than just a concept\, since it is related to several fissio n observables. These data may have an impact on both fundamental nuclear p hysics and nuclear applications. Sometimes\, model calculations of the bar rier are performed and observables like various cross sections are predict ed [4]\, which then have to withstand comparison with experimental results . In a recent work [5] it was demonstrated how different measured data fro m the decay of the shape isomer in $^{235}$U together with fission fragmen t properties could be used to estimate barrier parameters and to construct the shape of the fission barrier. While that work is based on neutron-ind uced fission measurements\, a recent experiment at GSI was performed to st udy fission isomers\, produced in fragmentation reactions\, with the FRS. Data analysis from this experiment is still ongoing\, but we will give an overview of the results obtained so far and present the current status of the data treatment.\n\n\nReferences:\n[1] V. M. Strutinsky\, Nucl. Phys. $ \\textbf{A95}$\, 420 (1967).\n[2] S. Bjørnholm and J. E. Lynn\, Rev. Mod. Phys. $\\textbf{52}$\, 725 (1980).\n[3] P. Thirolf and D. Habs \, Prog. Part. Nucl. Phys. $\\textbf{49}$\, 325 (2002).\n[4] M. Sin\, R. Capote\, M.W. Herman\, and A.Trkov\, Nucl. Data Sheets $\\textbf{139}$\ , 138 (2017).\n[5] A. Oberstedt and S. Oberstedt\, Phys. Rev. C $\\textbf{ 104}$\, 024611 (2021).\n\nhttps://indico.frib.msu.edu/event/52/contributio ns/628/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/628/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the $^{239}$Pu(n\,f)/ $^{235}$U(n\,f) Cross-Section Ratio with the NIFFTE fission Time Projection Chamber DTSTART:20220727T182400Z DTEND:20220727T183600Z DTSTAMP:20260420T153400Z UID:indico-contribution-636@indico.frib.msu.edu DESCRIPTION:Speakers: Lucas Snyder (LLNL)\n\nThe goal of the Neutron Induc ed Fission Fragment Tracking Experiment (NIFFTE) is to measure fission cro ss sections with unprecedented precision. The NIFFTE Collaboration has des igned and built a Time Projection Chamber (TPC) for this purpose. The trac king capabilities of this device allow for the full reconstruction of char ged particles produced by neutron beam induced fissions from a thin centra l target. The wealth of information gained from this approach allowed cros s-section systematics to be studied in detail\, particularly those relatin g to particle identification and target and beam spatial uniformity. Here we present the results of the $^{239}$Pu(n\,f)/$^{235}$U(n\,f) cross-secti on ratio from measurements performed at the Los Alamos Neutron Science Cen ter (LANSCE) facility. \n\nThis work performed under the auspices of the U .S. Department of Energy by Lawrence Livermore National Laboratory under C ontract No. DE-AC52-07NA27344.\n\nLLNL-ABS-827323\n\nhttps://indico.frib.m su.edu/event/52/contributions/636/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/636/ END:VEVENT BEGIN:VEVENT SUMMARY:Fission Neutron Spectrum Induced Short-Lived Fission Product Yield s of $^{235}$U\, $^{238}$U\, $^{239}$Pu and $^{237}$Np DTSTART:20220727T152100Z DTEND:20220727T153300Z DTSTAMP:20260420T153400Z UID:indico-contribution-632@indico.frib.msu.edu DESCRIPTION:Speakers: N. Gharibyan\, G. Slavik\, K. Roberts\, Pihong Zhao\ , C. Palmer\, B. Pierson\, S. Menn\, A. S. Tamashiro\, D. Hayes\, J. Hutch ison\, S. Burcher\, S. Reese\, J. Goda\, J. Walker\, S. W. Padgett\, P. Ya p-chiongco\, N. Harward\, L. Greenwood\, Jason Harke\n\nOver the past deca de a series of measurements have been performed to determine fission produ ct yields from a series of actinides. The National Criticality Experiments Research Center operates several critical assemblies one of which is Godi va. Godiva was operated in burst mode to produce a prompt fission neutron spectrum to fission actinide materials so that their relative yields could be measured. To date\, U235\, U238\, Pu239 and Np237 have been irradiated using a prompt burst of fission spectrum neutrons from Godiva. Approximat ely one-hour after the irradiation the actinide target material was moved to a dedicated BeGe detector system and gamma-ray spectroscopic data was m easured. The gamma-ray spectra were recorded in time stamped list mode for up to one week following the irradiation. The spectra were binned into va rious time bins for analysis and the subsequent gamma-ray photopeaks were used to identify their respective isotopes. The decay curves were fit to c onfirm their half-life and then the fission product yields were determined . We will report on current status of the data analysis and results for th e above actinides.\n\nThis work was funded by the Office of Defense Nuclea r Nonproliferation Research and Development within the U.S. DOE - NNSA. Th is work was performed under the auspices of the U.S. DOE by LLNL under Con tract DE-AC52-07NA27344.\n\nhttps://indico.frib.msu.edu/event/52/contribut ions/632/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/632/ END:VEVENT BEGIN:VEVENT SUMMARY:Short-lived fission products from neutron-induced fission of $^{23 5\,238}$U DTSTART:20220727T153300Z DTEND:20220727T154500Z DTSTAMP:20260420T153400Z UID:indico-contribution-633@indico.frib.msu.edu DESCRIPTION:Speakers: Sean Finch\, Calvin Howell\, Mark Stoyer\, Ronald Ma lone\, Dave Viera\, Jerry Wilhelmy\, Matthew Gooden\, Jack Silano\, Werner Tornow\, Vanessa Linero\, Anton Tonchev\, Fnu Krishichayan\, Todd Bredewe g\, Anthony Ramirez\n\nThe LLNL-LANL-TUNL collaboration has been providing high-quality fission product yields (FPYs) from neutron-induced fission o f $^{235}$U\, $^{238}$U\, and $^{239}$Pu [1]. Fission products have been m easured using activation technique with monoenergetic and pulsed neutron b eam produced at the tandem accelerator at the Triangle Universities Nuclea r Laboratory (TUNL). The previous campaign concentrated on measuring long- lived cumulative FPYs with half-lives of hours to days in order to study t heir dependence with incident neutron energy. In an effort to broaden our experimental FPY landscape\, we extended these measurements to shorter-liv ed fission products using a recently installed RApid Belt-driven Irradiate d Target Transfer System (RABITTS) at TUNL. This automated system allows c yclic neutron activation technique permitting the measurement of fission p roducts with half-lives from minutes to seconds. Absolute yields have been determined for more than 40 fission products representing about 35 fissio n-product masses during the RABITTS activation. An overview of the RABITTS and preliminary data for neutron- induced fission of $^{235}$U and $^{238 }$U at E$_n$=4.6 and 14.8 MeV will be presented.\n\n[1] M. Gooden et al.\, Nucl. Data Sheets 131\, 319 (2016).\n\nThis work was performed under the auspices of the U.S. Department of Energy Lawrence Livermore National Labo ratory under contract DE-AC52-07NA27344.\n\nhttps://indico.frib.msu.edu/ev ent/52/contributions/633/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/633/ END:VEVENT BEGIN:VEVENT SUMMARY:Fission product Yields from Photon-induced Fission of $^{240}$Pu a nd Neutron-induced Fission of $^{239}$Pu as a Function of Incident Energy DTSTART:20220727T154500Z DTEND:20220727T155700Z DTSTAMP:20260420T153400Z UID:indico-contribution-634@indico.frib.msu.edu DESCRIPTION:Speakers: Calvin Howell\, Anton Tonchev\, Matthew Gooden\, Nic olas Schunck\, Sean Finch\, Anthony Ramirez\, Ronald Malone\, Fnu Krishich ayan\, Roger Henderson\, Mark Stoyer\, Werner Tornow\, Jack Silano\n\nThe Bohr Hypothesis\, one of the most fundamental assumptions in nuclear fissi on theory\, states that the decay of a compound nucleus with a given excit ation energy\, spin and parity is independent of its formation $^{[1]}$. U sing fission product yields (FPYs) as a sensitive probe\, we have performe d novel high-precision test of the combined effects of the entrance channe l\, spin and parity on the fission process. Two different reactions were u sed in a self-consistent manner to produce a compound $^{240}$Pu nucleus w ith the same excitation energy: neutron induced fission of $^{239}$Pu and photon-induced fission of $^{240}$Pu. The FPYs from these two reactions we re measured using quasimonoenergetic neutron beams from the Triangle Unive rsities Nuclear Laboratory’s (TUNL’s) FN tandem Van de Graaff accelera tor $^{[2]}$ and quasimonenergetic photon beams from the High Intensity Ga mma-ray Source (HIGS) facility. A comparison of the FPYs from $^{239}$Pu(n \,f) at E$_\\text{n}$=1.5 and 4.6 MeV with those from $^{240}$Pu(γ\,f) at E$_{γ}$=8 and 11.2 MeV will be presented.\n\nThis work was performed und er the auspices of the U.S. Department of Energy by Lawrence Livermore Nat ional Laboratory under contract DE-AC52-07NA27344. \n\n$^{[1]}$ N. Bohr an d J. A. Wheeler\, “The Mechanism of Nuclear Fission.” Physical Review **56**\, 426 (1939).\n$^{[2]}$ M.E. Gooden *et al.*\, “Energy Dependence of Fission Product Yields from $^{235}$U\, $^{238}$U and $^{239}$Pu for I ncident Neutron Energies Between 0.5 and 14.8 MeV.” Nuclear Data Sheets **131**\, 319 (2016).\n\nhttps://indico.frib.msu.edu/event/52/contribution s/634/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/634/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the neutron-induced fission cross section of $^{235 }$U relative to neutron-proton elastic scattering at CERN-n_TOF: results f rom 20 MeV to 200 MeV DTSTART:20220727T183600Z DTEND:20220727T184800Z DTSTAMP:20260420T153400Z UID:indico-contribution-637@indico.frib.msu.edu DESCRIPTION:Speakers: Alice Manna\, Laurent Tassan Got\, Ralf Nolte\, Nich olas Terranova\, Patrizio Console Campini\, Alberto Mangoni\, Désirée Ra deck\, Christian Massimi\, Quentin Ducasse\, Mirco Dietz\, Alberto Ventura \, Paolo Finocchiaro\, Nicola Colonna\, Luigi Cosentino\, the n_TOF Collab oration\, Elisa Pirovano\n\nThe $^{235}$U(n\,f) cross section is one of th e most important cross-sections in many applications\, and it is a standar d at the thermal neutron energy point (0.025 eV)\, and from 0.15 MeV to 20 0 MeV. Above 100 MeV\, it also plays an important role in understanding fu ndamental nuclear physics processes\, as it can be related to the properti es of excited nuclear matter. Above 50 MeV\, however\, the evaluation reco mmended by the IAEA is based on only two measurements\, and above 200 MeV no data are available. For these reasons\, a new measurement was carried o ut in 2018 at n_TOF\, the neutron time-of-flight facility of CERN\, aimed at measuring the $^{235}$U(n\,f) cross section relative to $^1$H(n\,n) in the high-energy neutron range\, from 10 MeV up to several hundred MeV.\n\n The setup consisted of ten $^{235}$U samples mounted in two reaction chamb ers\, and two polyethylene samples\, which were all irradiated simultaneou sly. The protons emitted from the polyethylene radiators after elastic neu tron scattering on hydrogen were detected and discriminated from other par ticles using three particle telescopes placed outside the beam at the labo ratory angles of 20 and 25 degrees. Considering the complexity of the expe riment and of its analysis\, this contribution will focus on the data cove ring the incident neutron energy range up to 200 MeV\, and the results abo ve 200 MeV will be discussed in the contribution of A. Manna for the n_TOF Collaboration\, submitted to ND2022. The challenges faced when carrying o ut an absolute measurement will be addressed\, especially those related to the determination of the incident neutron fluence\, and the normalization procedure relative to n-p scattering\, the primary standard for neutron c ross sections.\n\nhttps://indico.frib.msu.edu/event/52/contributions/637/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/637/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the $^{235}$U(n\,f) cross section relative to n-p s cattering up to 500 MeV at the n_TOF facility at CERN DTSTART:20220727T184800Z DTEND:20220727T190000Z DTSTAMP:20260420T153400Z UID:indico-contribution-638@indico.frib.msu.edu DESCRIPTION:Speakers: Désirée Radeck\, Ralf Nolte\, Nicholas Terranova\, Liugi Cosentino\, Christian Massimi\, Alberto Ventura\, Alberto Mengoni\, Elisa Pirovano\, Laurent Tassan Got\, Patricizo Console Campini\, Nicola Colonna\, Mirco Dietz\, Quentin Ducasse\, Paolo Finocchiaro\, the n_TOF Co llaboration\, Alice Manna\n\nThe $^{235}$U(n\,f) cross section is one of t he most important neutron cross-section standards\, and therefore it is re cognized as a convenient reference for several other reaction cross-sectio n measurements at thermal energy and between 0.15 MeV and 200 MeV. Outside these energy ranges the cross section is either not well known nor measur ed yet\, as for example above 200 MeV\, where evaluations can only rely on theoretical calculations. In this energy region\, $^{235}$U(n\,f) plays a n important role for fundamental nuclear physics as well as for several ap plications\, ranging from biological effectiveness\, via nuclear astrophys ics\, to nuclear technology.\n\nTherefore\, in spite of the continuous eff ort for the improvement of the standards by the International Atomic Energ y Agency (IAEA)\, together with ENDF/B\, the longstanding quest for $^{235 }$U(n\,f) cross section data turns out to be still pending above 20 MeV (o nly 2 data sets are present in the 20-200 MeV energy region). In particula r\, the request is for fission measurements relative to the neutron-proton elastic scattering\, which is considered the primary reference for neutro n cross section measurements.\n\nThe n\\_TOF facility at CERN offers the p ossibility to study such reaction thanks to the wide neutron energy spectr um available in its experimental area\, from thermal up to 1 GeV. Recently \, a dedicated measurement campaign was carried out to provide accurate an d precise cross section data of the $^{235}$U(n\,f) reaction in the energy region from 10 MeV to 500 MeV.\n\nThe experimental apparatus is essential ly developed by INFN (Italy)\, PTB (Germay) and IPN (France) with support from CERN. It consists\, which involves the efforts of several institutes (INFN\, PTB and IPN in addition to CERN)\, consisted of three flux and two fission detectors\, thus allowing to simultaneously record the number of neutrons impinging on the $^{235}$U samples (neutron flux) and of fission events\, as a function of the neutron energy. The neutron flux measurement is based on the neutron-proton elastic scattering reaction\, and it explo its the detection of the recoil protons from the n-p reaction in a polyeth ylene target using three Proton Recoil Telescopes.\n\nThe experimental app aratus and data analysis will be presented. Due to the complexity of the e xperiment and its challenging data analysis\, the results obtained in the energy range between 10 to 200 MeV are shown in the E. Pirovano for the n_ TOF Collaboration contribution to ND2022\, while I will focus on the resul ts obtained in the high-energy region\, above 200 MeV.\n\nhttps://indico.f rib.msu.edu/event/52/contributions/638/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/638/ END:VEVENT BEGIN:VEVENT SUMMARY:Fission-fragment yields and prompt-neutron multiplicity for Coulom b-induced fission of $^{234\,235}$U and $^{237\,238}$Np [1] DTSTART:20220728T130000Z DTEND:20220728T132400Z DTSTAMP:20260420T153400Z UID:indico-contribution-641@indico.frib.msu.edu DESCRIPTION:Speakers: Julien Taieb\, Julie-Fiona Martin\, Audrey Chatillon \n\nThe anatomy of nuclear fission - a complex many-body process that has challenged precise modeling for decades - is explored via a comprehensive inverse-kinematics experiment. A Coulomb-fission measurement of relativist ic $^{234\,235}$U and $^{237\,238}$Np projectiles at the GSI\, using the R 3B/SOFIA setup [1\,2\,3\,4]\, was performed to identify on an event-by-eve nt basis\, in terms of their mass and atomic numbers\, the fissioning nucl eus in coincidence with both fission fragments after prompt-neutron emissi on. \n\nThis experiment has provided some of the most precise fission-frag ment yields yet for these uranium isotopes and the first isotopic yields f or two neptunium isotopes. Moreover\, the high accuracy of our data allowe d us to study in detail total prompt-neutron multiplicity\, from the diffe rence of masses of the fissioning nucleus and fission fragments. Finally b y combining the measured isotopic yields with the measured total prompt-ne utron multiplicity\, a method to infer the number of neutrons of the prima ry fission fragments prior to the neutron evaporation phase is proposed. T he average number of neutron of the primary fission fragments as a functio n of their atomic number is thus obtained. \n\nBibliography:\n[1] J.-F. Ma rtin et al.\, accepted for publication in Phys. Rev. C.\n[2] E. Pellereau et al.\, Phys. Rev. C 95\, 054603 (2017).\n[3] A. Chatillon et al.\, Phys. Rev. C 99\, 054628 (2019).\n[4] A. Chatillon et al.\, Phys. Rev. Lett. 12 4\, 202502 (2020).\n\nhttps://indico.frib.msu.edu/event/52/contributions/6 41/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/641/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the prompt fission $\\gamma$-rays from $^{235}$U(n\ ,f) with STEFF DTSTART:20220728T132400Z DTEND:20220728T133600Z DTSTAMP:20260420T153400Z UID:indico-contribution-642@indico.frib.msu.edu DESCRIPTION:Speakers: Adhitya Sekhar\, N. V. Sosnin\, A. G. Smith\, Sam Be nnett\, the n_TOF Collaboration\, Tobias Wright\n\nThe average energy and multiplicity of prompt $\\gamma$-rays from near thermal neutron induced fi ssion of $^{235}$U have been measured using the STEFF detection setup at b oth the high-flux ILL research reactor and the neutron time-of-flight faci lity n\\_TOF. As highlighted by the NEA High Priority Request List\, these quantities are of importance to the heating of non-fuelled elements of a reactor core and concerted efforts have been made in recent years to impro ve the available data. STEFF is capable of measuring both fission fragment 's energy and velocity\, a so-called $2E2v$ device and the fragment veloci ties and energies are used to provide a clean and precise timing signal fo r a fission event. The central chamber is surrounded by an array of 11 127 $\\times$102 mm NaI scintillators which are used to record the time and en ergies of $\\gamma$-rays within a time window centered around the identifi ed time-of-fission. Both prompt fission $\\gamma$'s and those originating from secondary interactions by prompt fission neutrons are detected and a method is given here to distinguish between the two based on both the dete ction time and energy. Details on the full analysis methodology and proced ures will be presented and a comparison of the results from the two experi ments at thermal neutron energies will be given in order to quantify and i nvestigate any systematic uncertainties associated in each case\, particua lrly with regard to the functioning of STEFF in the high $\\gamma$-ray bac kground environment associated with EAR2 at n\\_TOF. The final results wil l be given and shall be compared to other recent measurements and evaluati ons.\n\nhttps://indico.frib.msu.edu/event/52/contributions/642/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/642/ END:VEVENT BEGIN:VEVENT SUMMARY:Prompt gamma-ray multiplicity in fast neutron-induced fission of $ ^{239}\\mathrm{Pu}$ DTSTART:20220728T133600Z DTEND:20220728T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-643@indico.frib.msu.edu DESCRIPTION:Speakers: James Baker\, Matthew Devlin\, Isabel Hernandez\, Sh aun Clarke\, Sara Pozzi\, Keegan Kelly\, Stefano Marin\, Nathan Giha\n\nHe avy nuclei toe a delicate balance between the attractive strong nuclear fo rce and the repulsive Coulomb force. When this balance is disrupted in fav or of the Coulomb force\, heavy nuclei may elongate and fission into two f ragments. Fission was first observed over eighty years ago and theoretical ly explained shortly thereafter. We now know that good macroscopic and mic roscopic fission models play a vital role in modeling the r-process of hea vy element synthesis\, which has sparked renewed interest in a more accura te understanding of fission. Much has been published in the past year abou t the mechanism of angular momentum generation of the nascent fission frag ments\, with several groups reaching conclusions at variance with one anot her. Systematic biases in past experiments make results more difficult to interpret. Fragments shed much of their angular momentum\, post-neutron ev aporation\, via gamma-ray emission. Thus\, the number of emitted gamma ray s is linked to the angular momentum of a fragment after neutron evaporatio n.\nScientists at the Los Alamos Neutron Science Center measured the $^{23 9}\\mathrm{Pu}(n\,f)$ prompt fission neutron spectrum over a range of inci dent neutron energies\, tagging fissions with a parallel-plate avalanche c ounter and measuring prompt fission neutrons and gamma rays with Chi-Nu\, a hemispherical array of EJ-309 liquid scintillator detectors [1\, 2].\nIn this work we further analyze the data set from Ref. [2] and present\, for the first time\, the change in total gamma-ray multiplicity as a function of inducing neutron energy (2 - 20 MeV) in the $^{239}\\mathrm{Pu}(n\,f)$ reaction. We present corrections to systematic biases that arise from alp ha contamination and neutron beam wraparound and then conclude that the mu ltiplicity increases with inducing neutron energy\, albeit more gradually than in the ENDF-B/VIII.0 evaluation [3]. This finding suggests that the e xcitation of the compound $^{240}\\mathrm{Pu}^*$ nucleus contributes to ex citation of higher rotational modes in the fragments.\n\n[1] C.Y. Wu\, et al. "A multiple parallel-plate avalanche counter for fission-fragment dete ction". Nuclear Instruments and Methods in Physics Research Section A: Acc elerators\, Spectrometers\, Detectors and Associated Equipment 794. (2015) : 76-79.\n\n[2] Kelly\, K. J. et al. "Measurement of the $^{239}\\mathrm{P u}(n\,f)$ prompt fission neutron spectrum from 10 keV to 10 MeV induced by neutrons of energy 1–20 MeV". Phys. Rev. C 102. (2020): 034615.\n\n[3] I. Stetcu\, et al. "Evaluation of the Prompt Fission Gamma Properties for Neutron Induced Fission of 235\,238U and 239Pu". Nuclear Data Sheets 163. (2020): 261-279.\n\nhttps://indico.frib.msu.edu/event/52/contributions/643 / LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/643/ END:VEVENT BEGIN:VEVENT SUMMARY:Photofission and photoneutron cross sections for $^{238}$U and $^{ 232}$Th DTSTART:20220728T134800Z DTEND:20220728T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-645@indico.frib.msu.edu DESCRIPTION:Speakers: I. Gheorghe\, K. Nishio\, H. Suzaki\, M. Inagaki\, K . Hirose\, M. Bjørøen\, H. Wang\, S. Miyamoto\, Y.-W. Lui\, K. Stopani\, T. Ari-izumi\, G. Fan\, A. Tudora\, T. Ohtsuki\, H. Utsunomiya\, Dan Miha i Filipescu\n\nPhotofission and photoneutron reactions on $^{238}$U and $^ {232}$Th were investigated in the energy range of 5.86 MeV – 20.12 MeV b y quasi-monochromatic $\\gamma$-ray beams produced in laser Compton-scatte ring at the NewSUBARU synchrotron radiation facility. Direct neutron-multi plicity sorting was performed with a flat-efficiency neutron detector [1]. Following Terrell’s prescription [2]\, a normal distribution was used t o describe the prompt-fission-neutron (PFN) multiplicity and thus separate the photofission and photoneutron contributions. We provide novel experim ental ($\\gamma$\,n)\, ($\\gamma$\,2n) and ($\\gamma$\,f) cross sections\, average energies of PFN and of photoneutrons emitted in ($\\gamma$\,n) a nd ($\\gamma$\,2n) reactions\, as well as the mean number of PFN per fissi on act. The new cross sections and average energies of ($\\gamma$\,n) and ($\\gamma$\,2n) neutrons are evaluated with statistical-model calculations performed with the EMPIRE code [3] in comparison with preceding data. \n\ n[1] H. Utsunomiya et al.\, Nucl. Instrum. Meth. A 871\, 135 (2017).\n[2] J. Terrell\, Phys. Rev. 108\, 783 (1957).\n[3] M. Herman et al.\, Nuclear Data Sheets 108\, 2655 - 2715 (2007).\n\nhttps://indico.frib.msu.edu/event /52/contributions/645/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/645/ END:VEVENT BEGIN:VEVENT SUMMARY:Consistent Evaluations of Prompt Neutron Observables DTSTART:20220728T140000Z DTEND:20220728T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-646@indico.frib.msu.edu DESCRIPTION:Speakers: Patrick Talou\, Amy Lovell\, Denise Neudecker\n\nLA- UR-21-29120\nHistorically\, there is little to no consistency between the various types of nuclear fission data in our libraries (Patrick Jaffke\, N SE 190\, 258 (2018))\, despite the fact that we know these observables to be correlated through the joint fission process underlying them all. For instance\, the energies and multiplicities of prompt neutrons and gamma ra ys are correlated through the excitation energy of the fission fragments\, but are usually evaluated separately with different types of models or\, in some cases\, entirely based on experimental data. \n\nTo address these inconsistencies and potential biases that arise from them\, correlated fis sion models have been developed in the last decade. One can\, for instance \, use the LANL-developed\, Monte Carlo Hauser-Feshbach statistical decay code\, CGMF (P. Talou\, et al.\, CPC 269\, 108087 (2021))\, to calculate t he prompt emission of neutrons and gamma rays from highly excited fission fragments\, conserving energy\, momentum\, spin\, and parity at each step in the decay. This code ultimately yields the desired $\\langle\\nu_p \\r angle$ and PFNS within the same framework. However\, these models do not predict $\\langle\\nu_p \\rangle$ and PFNS to the precision needed for nuc lear data evaluations and the application simulations they serve as the mo del parameter space is too large. To this end\, experimental data for thes e observables need to be included in a formal evaluation procedure.\n\n He re\, we present the first of such an evaluation for $\\langle\\nu_p \\rang le$ of major actinides underpinned by CGMF. We show\, for instance\, for the case of $^{239}$Pu(n\,f) $\\langle\\nu_p \\rangle$ that in addition to being able to reproduce experimental $\\langle\\nu_p \\rangle$\, the eval uation also produces reasonable results for other prompt observables that are comparable with available experimental data. Moreover\, these evaluate d data performed well in simulating various integral responses when combin ed with more recent $^{239}$Pu(n\,f) PFNS and fission cross sections.\n\nA cknowledgments\nWork at LANL was carried out under the auspices of the Nat ional Nuclear Security Administration (NNSA) of the U.S. Department of Ene rgy (DOE) under contract 89233218CNA000001. We gratefully acknowledge part ial support of the Advanced Simulation and Computing program at LANL and t he DOE Nuclear Criticality Safety Program\, funded and managed by NNSA fo r the DOE.\n\nhttps://indico.frib.msu.edu/event/52/contributions/646/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/646/ END:VEVENT BEGIN:VEVENT SUMMARY:Calculations and Evaluations of n + 58\,60\,61\,62\,64\,nat.Ni Rea ctions up to 200 MeV DTSTART:20220728T190600Z DTEND:20220728T191800Z DTSTAMP:20260420T153400Z UID:indico-contribution-670@indico.frib.msu.edu DESCRIPTION:Speakers: Min Jia (North China University of Water Resources a nd Electric Power)\n\nAll cross sections\, angular distributions\, energy spectra\, and double-differential cross sections for n + 58\,60\,61\,62\,6 4\, nat.Ni reactions are consistently calculated and analyzed in the incid ent neutron energies from 0.001 to 200 MeV by using nuclear theoretical mo dels\, including the optical model\, the unified Hauser-Feshbach theory an d the exciton model\, the improved Iwamoto-Harada model\, the evaporation models\, the linear angular momentum dependent exciton state density model \, the intranuclear cascade model\, the distorted-wave Born approximation and the coupled channel theory. The optical model potential parameters are obtained based on the experimental data of total\, nonelastic scattering cross sections and elastic scattering angular distributions. The theoretic al results are compared furtherly with the retrieved experimental data and the evaluated results in ENDF/B-VIII\, JENDL-4\, and TENDL-2019 libraries .\n\nhttps://indico.frib.msu.edu/event/52/contributions/670/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/670/ END:VEVENT BEGIN:VEVENT SUMMARY:The effect of high dose rate laser driven radiation on the integri ty of amino acids and implications in toxicity evaluation DTSTART:20220727T172000Z DTEND:20220727T172200Z DTSTAMP:20260420T153400Z UID:indico-contribution-1141@indico.frib.msu.edu DESCRIPTION:Speakers: Silvana Vasilca (National Institute for Physics and Nuclear Engineering IFIN-HH\, Extreme Light Infrastructure - Nuclear Physi cs ELI-NP & IRASM Departemnt\; 3University of Bucharest\, Faculty of Chemi stry\, Department of Analytical Chemistry)\n\nLately\, novel radiation the rapy methods using advanced laser technologies with ultra-high dose rates (“FLASH”)\, such as laser-accelerated particle beams and laser-driven ionizing radiation in pulses\, with time spans from fs to ns started to em erge\, having encouraging results in numerous studies concerning toxicity characterization [1\,2]. Significant parameters of radiation therapies lik e high radiation intensities and short irradiation times are intended to i mprove treatment’s outcome and to have a better individualized treatment for each patients’ needs. One of the most important issues in radiother apy is to find the right compromise between radiation’s efficacy to redu ce the tumor and its toxicity. Also\, it’s necessary to explain the mech anisms underlying the effects induced by ionizing radiation in biological matrices\, and for that reason\, endogenous molecules that provide informa tion on toxicity are required. Amino acids can be selected as viable candi dates for biomarkers due to their involvement in many cellular metabolic p rocesses determined by high dose-rate radiations.\nAs forerunner experimen ts of laser driven irradiation trials\, in this study we have investigated experimental models of gamma irradiated lyophilised glioblastoma cells li nes. The evaluation of amino acids was performed both from a qualitative a nd quantitative point of view\, using a Reversed Phase Liquid Chromatograp hy with diode-array detection (RPLC–DAD) employing a precolumn derivatiz ation method. This inquiry consisting in characterizing and profiling\, al lows us to have an insight into amino acids as biochemical evidences and t heir pathways in metabolic processes stimulated by radiation\, in order to anticipate whether low toxicity using FLASH radiation was achieved.\n\nht tps://indico.frib.msu.edu/event/52/contributions/1141/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1141/ END:VEVENT BEGIN:VEVENT SUMMARY:The cross sections and energy spectra of the particle emission in α induced reaction on 58\,60\,61\,62\,64\,nat.Ni DTSTART:20220728T193000Z DTEND:20220728T194200Z DTSTAMP:20260420T153400Z UID:indico-contribution-674@indico.frib.msu.edu DESCRIPTION:Speakers: Xinwu Su (Shanxi Datong University\, China)\n\nNucle ar data for alpha particle induced reactions on 58\,60\,61\,62\,64\,nat.Ni plays an important role in the application of nuclear techniques like cha rged particle activation analysis\, medical isotope production\, estimatio n of neutron yield and residual activity of accelerator components or simu lation of radiation damage. All cross sections of α-induced reactions\, a ngular distributions\, energy spectra and double differential cross sectio ns of neutron\, proton\, deuteron\, triton\, helium and α-particle emissi ons for 58\,60\,61\,62\,64\,nat.Ni are consistently calculated and analyze d at incident energy below 200 MeV. The optical model\, the intra-nuclear cascade model\, direct reaction theories\, the unified Hauser-Feshbach and exciton model which includes the improved Iwamoto-Harada model are used. Theoretically calculated results are compared with the existing experiment al data. Good agreement is generally observed between the calculated resul ts and the experimental data. Since the improved Iwamoto-Harada model has been included in the exciton model for the light composite particle emissi ons\, the theoretical models provide the good description of the shapes an d magnitude of the energy spectra and double differential cross section of emission deuteron\, triton\, helium and alpha. The evaluated data are giv en in the format of ENDF. Therefore\, these data can be effectively used i n different practical applications.\n\nhttps://indico.frib.msu.edu/event/5 2/contributions/674/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/674/ END:VEVENT BEGIN:VEVENT SUMMARY:Evaluation of delayed neutron yields and time spectra from photofi ssion of $^{238}U$ induced by $\\textit{Bremsstrahlung}$ photons below 9 M eV DTSTART:20220728T174000Z DTEND:20220728T175200Z DTSTAMP:20260420T153400Z UID:indico-contribution-665@indico.frib.msu.edu DESCRIPTION:Speakers: Roberto De Stefano (Université Paris-Saclay\, CEA\, List\, F-91120 Palaiseau\, France)\, Iaroslav Meleshenkovskii (Universit é Paris-Saclay\, CEA\, List\, F-91120 Palaiseau\, France)\, Romuald Woo ( Université Paris-Saclay\, CEA\, List\, F-91120 Palaiseau\, France)\, Maug an Michel (Université Paris-Saclay\, CEA\, List\, F-91120 Palaiseau\, Fra nce)\, Aly Elayeb (Université Paris-Saclay\, CEA\, List\, F-91120 Palaise au\, France)\, Adrien Sari (Université Paris-Saclay\, CEA\, List\, F-9112 0 Palaiseau\, France)\n\nFew data exist regarding the yields and the six g roup time spectra of delayed neutrons from the photofission reaction on ac tinides. In 1966\, Nikotin *et al.* published data for the photofission of 232Th\, 235U\, 238U and 239Pu induced by *Bremsstrahlung* photons with an endpoint energy at 15 MeV. In 1970\, Kull *et al.* presented data for the photofission of 235U and 238U at both 8 and 10 MeV. In 2009\, Macary *et al.* provided data for the photofission of 235U and 237Np for a couple of endpoint energies below 20 MeV. In this study\, new experimental data are reported for the photofission of 238U induced by *Bremsstrahlung* photons below 9 MeV. This work was conducted using a Linatron M9 linear electron a ccelerator manufactured by *Varex Imaging Corp.* and housed at the SAPHIR platform\, which is located at CEA Paris-Saclay\, France. Either 6 or 9 Me V electrons were converted to *Bremsstrahlung* photons thanks to its tungs ten target. Samples of 238U were positioned inside a high-density polyethy lene neutron detection array designed and optimized using the MCNP6 Monte- Carlo simulation code and including ten one meter-long 3He counters. The n ovel results presented in this study for the photofission of 238U induced by *Bremsstrahlung* photons below 9 MeV bring valuable information to the scarce – and sometimes contradictory – data available in the literatur e. Furthermore\, these new experimental data represent useful inputs for t he development of nuclear measurement systems based on the photofission re action. Such systems meet a significant interest in the field of nuclear w aste package characterization and for security-related applications.\n\nht tps://indico.frib.msu.edu/event/52/contributions/665/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/665/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of the neutron total cross section of 9Be at the Back- n white neutron source of CSNS DTSTART:20220728T191800Z DTEND:20220728T193000Z DTSTAMP:20260420T153400Z UID:indico-contribution-671@indico.frib.msu.edu DESCRIPTION:Speakers: Jiangbo Bai (Fudan university)\n\nThe neutron total cross section data of 9Be plays an important role in nuclear structure mod el of light nuclei and nuclear power installations. A measurement of the n eutron total cross section of 9Be in the 1eV-30MeV energy region has been carried out using time-of-flight method and transmission method by the neu tron total cross-sectional spectrometer (NTOX) based on the multi-layer fa st fission chamber at the China Spallation Neutron Source (CSNS)- Back-n w hite neutron source (Back-n). The fission count-energy distribution of 235 U and 238U with no sample and with Be samples in three thicknesses was mea sured in the double-bunch operation modes during beam power of 100 kW. The bayes method is used to eliminate the influence of the double-bunch probl em on neutron measurement in the high energy region. The unfolding results of neutron total cross section conform to ENDF/B-VIII.0 evaluation librar y data within the range of experimental uncertainty for most energy points in the 10keV-30MeV energy region. The neutron total cross section of 9Be measured by this experiment is also consistent with ENDF/B-VIII.0 evaluati on library data in 1eV-10keV energy region. The results of this experiment can provide technical support for further data analysis and related nucle ar data evaluation.\n\nhttps://indico.frib.msu.edu/event/52/contributions/ 671/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/671/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear fragmentation cross section measurements with the FOOT exp eriment DTSTART:20220725T184500Z DTEND:20220725T190900Z DTSTAMP:20260420T153400Z UID:indico-contribution-647@indico.frib.msu.edu DESCRIPTION:Speakers: Roberto Zarrella (University of Bologna - INFN Bolog na)\n\nFOOT (FragmentatiOn Of Target) is an applied nuclear physics experi ment with the aim of performing high precision cross section measurements for fragmentation reactions of interest in Hadrontherapy and Radioprotecti on in Space. An in-depth knowledge of the physical and biological effects caused by nuclear fragments is in fact of great interest for both the impr ovement of Hadrontherapy treatment planning and the development of effecti ve spacecraft shielding systems in long-term human missions in deep space (e.g. Mars explorations). However\, the data needed to accurately model th e behavior of nuclear fragments in these fields are currently scarce or to tally unavailable in literature. To fill in the gaps in nuclear databases\ , the FOOT collaboration will perform a set of measurements with light ion beams\, such as C and O\, in the energy range of 100-800 MeV/n impinging on tissue-like and shielding material targets.\n\nThe FOOT experiment allo ws for a precise identification of the produced nuclear fragments through the measurement of their kinematic characteristics. Each detector has been studied to give the best possible resolution with the aim of performing m easurements in inverse kinematics and with composite targets. To this purp ose\, the apparatus has been developed with the capability of accurately c haracterizing both the primary beam and all the fragments produced in nucl ear reactions with the target. The system comprehends two complementary se tups: an emulsion chamber spectrometer\, specialized in the detection of l ighter fragments (Z $\\leq$ 3)\, and an electronic setup\, dedicated to he avier particles (Z $\\geq$ 3)\, which includes a magnetic spectrometer\, a Time-Of-Flight system and a calorimeter.\n\nIn 2021\, two data acquisitio n campaigns have been carried out with the electronic setup: one with $^{1 6}$O beams at the GSI laboratories (Darmstadt\, Germany) and one with $^{1 2}$C ions at the CNAO facility (Pavia\, Italy). On both occasions\, fragme ntation measurements were performed using graphite and polyethylene target s.\nIn this contribution\, after an overview of the current status of the FOOT experiment\, the first cross section measurements obtained from the G SI and CNAO campaigns are presented.\n\nhttps://indico.frib.msu.edu/event/ 52/contributions/647/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/647/ END:VEVENT BEGIN:VEVENT SUMMARY:Ambient neutron dosimetry in particle therapy facilities DTSTART:20220725T194500Z DTEND:20220725T195700Z DTSTAMP:20260420T153400Z UID:indico-contribution-653@indico.frib.msu.edu DESCRIPTION:Speakers: Ariel Tarifeno-Saldivia\n\nNeutrons are a highly pen etrating radiation which can dominate the total adsorbed dose by the human body. Therefore\, in different kind of facilities\, it is essential to mo nitor neutron dose rates in order to ensure a minimal risk for workers\, p atients and public. This task is typically achieved by using commercial po rtable neutron detectors known as ambient neutron dosimeters. However\, th ere are several concerns about the reliability of commercial ambient neutr on dosimeters in modern facilities. In particular\, those producing radiat ion fields with an important high energy contribution (E>20MeV) or a compl ex time structure [1\, 2]. Reliability is a major issue indeed for the dos imetry and radiation protection in: 1) medical facilities\, such as proton therapy\, where high energy neutrons up to 250 MeV are produced as second ary stray radiation\; 2) around synchrotron or cyclotron facilities\, wher e either intended pulsed beams or beam losses produce short bursts of seco ndary neutron radiation\; 3) pulsed facilities for fundamental research an d applications\, such as spallation\, fusion neutron sources or high inten sity lasers. Moreover\, the International Commission on Radiation Units an d Measurements (ICRU) has recently recommended the use of alternative defi nitions for the operational quantities that are currently in use for radia tion protection. The new ICRU recommendation impacts directly on the expec ted performance of neutron dosimeters for energies lower than 100 eV and h igher than 50 MeV. Accordingly\, the LINrem project has been launched in 2 018 in order to provide solutions to the new requirements of energy sensit ivity and time resolution in neutron dosimetry with an special focus on me dical applications. \nIn this work\, the technical challenges for active a nd time-resolved neutron dosimetry in particle therapy are reviewed. It is discussed the impact of the new ICRU recommendation on the assessment\, u sing commercial dosimeters\, of neutron doses in hadron therapy. The nucle ar data needs for novel high energy detector designs are also discussed. T he conceptual design of LINrem dosimeters is presented and its performance is quantified by means of Monte Carlo simulations. Results are presented of the experimental validation of LINrem dosimeters in different facilitie s including proton therapy and pulsed neutron sources. \nReferences\n[1] J . Farah et al.\, Med. Phys. 42:5 (2015) 2572-2584.\n[2] M. Caresana et al. \, NIMA 737 (2014) 203–213.\n\nhttps://indico.frib.msu.edu/event/52/cont ributions/653/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/653/ END:VEVENT BEGIN:VEVENT SUMMARY:Measurement of displacement cross-sections of Nb irradiated by pro tons with kinetic energy range between 0.4 and 3 GeV DTSTART:20220728T185400Z DTEND:20220728T190600Z DTSTAMP:20260420T153400Z UID:indico-contribution-668@indico.frib.msu.edu DESCRIPTION:Speakers: Yosuke Iwamoto (Japan Atomic Energy Agency)\, Makoto Yoshida (J-PARC/KEK)\, Hiroki Matsuda (J-PARC/JAEA (present National Inst itutes for Quantum Science and Technology))\, Keita Nakano (J-PARC/JAEA)\, Shin-ichiro Meigo (J-PARC/JAEA)\n\nIn high-intensity proton accelerator f acilities such as Accelerator Driven System (ADS) and the spallation neutr on source\, it is crucial to evaluate the damage of beam-interception mate rials and accelerator components\, such as a magnet coil. The displacement per atom (dpa) is used as a damage index\, which is derived by integratin g the particle flux and the displacement cross section based on the Norger tt-Robinson-Torrens (NRT) model. Although the dpa is employed as the stand ard\, the experimental data of displacement cross section are scarce for a proton in the energy region above 20 MeV. \n\nThe difference exists about 8 times among the calculation models for W\, so experimental data of the displacement cross-section is crucial to validate the model. To obtain th e displacement cross section\, we have conducted the experiment in J-PARC. So far\, the cross sections of Al\, Cu\, Fe\, and W irradiated by protons with a kinetic energy range between 0.4 and 3 GeV were obtained at J-PARC [1\,2]. To obtain the data for superconducting materials for high-intensi ty accelerators and magnets\, we measured the displacement cross section o f Nb for proton irradiation with a kinetic energy range between 0.4 and 3 GeV. \n\nFollowing Matthiessen's rule\, the displacement cross section can be obtained with the observation of the electrical resistivity change in the sample divvied by proton fluence and the resistivity change by Franek pairs\, which is known with the uncertainty of ~20% by other works. To sus tain the damage in the sample\, the Nb sample is required to be cooled at a cryogenic temperature (~8 K)\, where the recombination of Frenkel pairs is well suppressed due to thermal motion with sustaining the normal conduc tivity to maintain Matthiessen's rule. To obttain the proton fluence corre ctly\, the sample was placed close to the beam profile monitor.\n\nCalcula tions of displacement cross section of Nb were made using the PHITS code\, which are compared with the present experimental results. The present res ults showed that the widely utilized Norgertt-Robinson-Torrens (NRT) model overestimates the cross section by a factor of 2\, as suggested by the pr evious works. It is also found that the calculation with a recently propos ed model of athermal recombination corrected (arc) model based on Molecula r Dynamics (MD) shows good agreement with the present data.\n\n\n**Referen ce**\n[1] S. Meigo\, H. Matsuda\, Y. Iwamoto\, et al.\, JPS Conf. Proc. 28 \, 061004 (2020).\n[2] H. Matsuda\, S. Meigo\, Y. Iwamoto\, et al.\, J. Nu cl. Sci. Technol. 57\, 1141-1151 (2020).\n\nhttps://indico.frib.msu.edu/ev ent/52/contributions/668/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/668/ END:VEVENT BEGIN:VEVENT SUMMARY:Experimental validation of thermal scattering evaluations DTSTART:20220728T145000Z DTEND:20220728T151400Z DTSTAMP:20260420T153400Z UID:indico-contribution-942@indico.frib.msu.edu DESCRIPTION:Speakers: Yaron Danon (Rensselaer Polytechnic Institute)\n\nIn recent years there has been resurgence in the field of thermal scattering law (TSL) evaluations and experiments. This comes after years that this f ield was dormant with little updates to ENDF evaluations. Evaluated TSL is based on atomistic calculations that in most cases results in a phonon sp ectrum that can be processed to create the scattering kernel for use in ap plications. The scattering kernel accounts for the thermal motion of the a toms in the target material (usually a moderator) which results in scatter ed neutrons both losing and gaining energy. As a result of this process th e scattering cross section generated from a TSL evaluation is very differe nt from the free-gas cross section at energies below a few eV\, particular ly for the elements in a moderator for example C and H in CH2 (polyethylen e). Similarly the angular distribution of the scattered neutrons can be ca lculated from the TSL and thus the neutron slowing down rate in a moderato r is function of the TSL. Thermal scattering evaluations will affect the c alculated results of criticality benchmarks\, but these systems usually in volve other materials that contribute to the uncertainty of the calculated multiplication factor\, thus experiments that are only sensitive to the T SL should be used for validation. These experiments must have the sensitiv ity to resolve differences between evaluations when they occur. The experi ments discussed include: accurate total thermal cross section measurements \, neutron die-away experiments\, and neutron leakage experiments. The exp erimental setups and results will be reviewed for some moderators includin g polyethylene\, and YHx. For the measurements preformed thus far\, there is generally good agreement between the measured total cross section and t he current TSL evaluation\, however in certain energy ranges differences w ere observed and can help resolve differences between evaluations.\n\nhttp s://indico.frib.msu.edu/event/52/contributions/942/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/942/ END:VEVENT BEGIN:VEVENT SUMMARY:Pulsed-Neutron Die-Away Experiments for Plastics DTSTART:20220728T151400Z DTEND:20220728T152600Z DTSTAMP:20260420T153400Z UID:indico-contribution-943@indico.frib.msu.edu DESCRIPTION:Speakers: Daniel Siefman (Lawrence Livermore National Laborato ry)\n\nPulsed-neutron die-away experiments (PNDA) can be useful benchmarks to validate neutron thermal scattering laws (TSLs). The experiment uses a neutron generator to impinge a short (~10-4 s) mono-energetic neutro n pulse on a target sample. After the pulse\, the neutron population withi n the sample moderates and reaches thermal equilibrium with a fundamental spatial mode and characteristic decay-time eigenvalue. The eigenvalue can be extracted from the experimental measurements of the neutron flux and us ed as an integral parameter in validation. For certain materials and geome tric configurations\, the eigenvalue is heavily influenced by thermal neut ron scattering of only the target material. For that reason\, a PNDA exper iment can have a higher sensitivity to TSLs than is commonly available in critical experiments. Herein\, we present results for a series of PNDA exp eriments with plastic materials (e.g.\, high-density polyethylene and Luci te). We compare the experimental integral parameters to simulated results and report trends in the biases. We evaluate the bias with different Monte Carlo transport codes (COG\, MC21\, and MCNP6.1) to see if differences in nuclear data processing or physics treatment between the codes significan tly impact the integral parameter.\n\nhttps://indico.frib.msu.edu/event/52 /contributions/943/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/943/ END:VEVENT BEGIN:VEVENT SUMMARY:The validation of S(α\,𝛽) thermal neutron scattering libraries using pulsed-neutron die-away experiments DTSTART:20220726T153300Z DTEND:20220726T153500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1110@indico.frib.msu.edu DESCRIPTION:Speakers: Benjamin Wang (RPI)\n\nValidation of the accuracy of S(α\,𝛽) thermal scattering law (TSL) evaluations for moderator materi als is an important task for the development of high-performance nuclear e ngineering systems. Many recent thermal neutron scattering evaluations ha ve had limited experimental validation. Like other nuclear data\, validat ion of TSL libraries has historically been by integral criticality benchma rks. While sufficient for general study\, these benchmarks often have lim ited sensitivity to the tested TSLs\, and compounding uncertainties from o ther nuclear data can make validation ambiguous. In some cases\, no criti cality benchmarks exist that are sensitive to the TSLs of interest. With the development of high-performance next-generation thermal nuclear reacto rs\, alternative validation of applicable TSLs is of high importance. \nB y performing thermal neutron measurements via pulsed-neutron die-away (PND A) experiments\, along with parallel simulations\, the integral performanc e of various TSL evaluations can be compared to measured experimental data . An experimental testbed using a D-T neutron generator\, moderator sampl e\, and thermal neutron detector was assembled at Rensselaer Polytechnic I nstitute. A Thermo Scientific D211 Deuterium-Tritium Neutron generator is used to generate 10 𝜇s neutron pulses. Various targets of different s izes and geometries are used to moderate the neutrons. Multiple detector types and configurations were tested to optimize the experiment. The room -temperature polyethylene TSL evaluation is well vetted and is similar acr oss different evaluations. This makes it an ideal evaluation to compare w ith the experimental results. Measurements with different sample sizes an d comparison to simulations will be discussed.\n\nhttps://indico.frib.msu. edu/event/52/contributions/1110/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1110/ END:VEVENT BEGIN:VEVENT SUMMARY:New thermal scattering libraries for cold and very-cold neutron so urces DTSTART:20220728T134800Z DTEND:20220728T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-937@indico.frib.msu.edu DESCRIPTION:Speakers: Douglas Di Julio (European Spallation Source ERIC)\n \nThe design of neutron sources\, using Monte-Carlo radiation transport co des\, relies on the usage of thermal scattering libraries in the ACE forma t. These libraries are derived from models of neutron interactions in the materials of interest. We report here on the development of such libraries for applications related to cold and very-cold neutron sources [1]. For t his purpose\, we have used path-integral molecular dynamics techniques [2\ ,3] to create temperature dependent input to models for liquid hydrogen an d deuterium\, currently existing in modified versions of NJOY\, and have e xtended these methods to investigate the neutron slowing down properties o f new materials\, for example liquid hydrogen-deuteride. Additionally\, wi th the recent advances of the NJOY+NCrystal tool\, we were able to create improved libraries for cold solid moderators\, such as solid deuterium. In this work\, we present an overview of these developments and some example neutronic calculations using the new libraries\, related to the upcoming European Spallation Neutron Source. \n\n[1] J.I. Marquez Damian\, D.D. DiJ ulio\, Günter Muhrer\, “Nuclear data development at the European Spalla tion Source”\, Journal of Neutron Research\, vol. 23\, no. 2-3\, pp. 157 -166 (2021)\n\n[2] E. Guarini et al.\, “Velocity autocorrelation in liqu id parahydrogen by quantum simulations for direct parameter-free computati ons of neutron cross sections”\, Phys. Rev. B 92\, 104303 (2015)\n\n[3] I.R. Craig and D.E. Manolopoulos\, “Quantum statistics and classical mec hanics: Real time correlation functions from ring polymer molecular dynami cs”\, The Journal of Chemical Physics 121(8) (2004)\, 3368–3373\n\nhtt ps://indico.frib.msu.edu/event/52/contributions/937/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/937/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Thermal neutron experiments and calculations on cryoge nic Ethane. II: Solid Ethane DTSTART:20220728T160200Z DTEND:20220728T161400Z DTSTAMP:20260420T153400Z UID:indico-contribution-945@indico.frib.msu.edu DESCRIPTION:Speakers: Florencia Cantargi (Atomic Energy Commission of the Argentine Republic\, Argentine Neutron Beam Laboratory\, Argentina.)\n\nVE SUVIO is a spectrometer at the ISIS Neutron and Muon Source\, Rutherford A ppleton Laboratory (United Kingdom) that allows the measurement of the tot al cross-section of a sample material by the transmission and time of flig ht techniques\, over a range of five decades in energy (10$^{-3}$ to 10$^{ 2}$ eV). At the same time\, it allows a precise determination of the effec tive temperature of each element present in the sample by using 198 detect ors that are spatially distributed around the sample.\nA neutron experimen t was performed at VESUVIO on a solid ethane (C$_2$H$_6$) sample at 80 K. This material is an organic compound with a high protonic density and a lo w rotational energy band in its frequency spectrum\, which makes it a good candidate to be used as a cryogenic moderator material. In a previous wo rk (ND2016) we have presented experimental and calculated results for liqu id Ethane at 100 K and 175 K\, emphasizing its capacity to act as a “coo l” moderator over an extended temperature range. \nThe phonon density of states of solid Ethane was evaluated using density functional theory tech niques (DFT)\, and used as input for the NJOY Nuclear Data Processing syst em. The total cross section thus generated shows a very good agreement wit h the measured points\, which represents a preliminary validation of the s cattering kernel construction and the cross section library generated in E NDF and ACE formats. \nEffective temperatures of hydrogen and carbon in th e ethane molecule were obtained by modeling the deep inelastic scattered n eutrons in the time of flight spectrum measured at each detector. The effe ctive temperatures of hydrogen and carbon in the ethane molecule were dete rmined by analyzing the time-of-flight spectra of the scattered neutrons m easured at each detector. The agreement between these results and the effe ctive temperature estimate obtained by means of a DFT of the simulated vib rational spectrum is also discussed.\n\nhttps://indico.frib.msu.edu/event/ 52/contributions/945/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/945/ END:VEVENT BEGIN:VEVENT SUMMARY:Thermal scattering libraries for cold and ultra-cold neutron refle ctor materials DTSTART:20220726T153100Z DTEND:20220726T153300Z DTSTAMP:20260420T153400Z UID:indico-contribution-1108@indico.frib.msu.edu DESCRIPTION:Speakers: Douglas Di Julio (European Spallation Source ERIC)\n \nReflectors play an important role at reactor and spallation neutron sour ces\, providing a means for otherwise lost neutrons to be potentially re-d irected towards the neutron science instruments. Such materials typically surround the moderating volume\, but can also be placed in the neutron bea m extraction area. We present developments of improved modelling methods s uch as including crystallite effects in traditional beryllium reflectors [ 1] in addition to developments using the NJOY+NCrystal code for new propos ed reflector materials such as Magnesium hydride and deuteride [2]. Of par ticular interest to very-cold and ultra-cold neutron sources is the possib ility of using nanodiamonds in the neutron beam extraction area [2\,3]. Fo r the simulations of such a system\, we present two alternative approaches . The first being the implementation of a small-angle neutron scattering m odel in OpenMC\, to be combined with the standard bulk diamond ACE file an d the second being the implementation of the small-angle scattering model inside NCrystal\, which is then called directly during the Monte-Carlo sim ulation. In this work we present examples of cross-section computed for th e above-mentioned materials and examples of Monte-Carlo calculations using the new developments. \n\nThis work was funded by the HighNESS project a t the European Spallation Source. HighNESS is funded by the European Frame work for Research and Innovation Horizon 2020\, under grant agreement 9517 82.\n\n[1] D.D. DiJulio et al.\, “Impact of crystallite size on the perf ormance of a beryllium reflector”\, Journal of Neutron Research\, vol. 2 2\, no. 2-3\, pp. 275-279\, 2020\n\n[2] V. Santoro et al.\, “Development of high intensity neutron source at the European Spallation Source” Jou rnal of Neutron Research\, vol. 22\, no. 2-3\, pp. 209-219\, 2020\n\n[3] V . Nesvizhevsky\, et al. "Fluorinated nanodiamonds as unique neutron reflec tor." Carbon\, 130\, 799-805\, (2018).\n\nhttps://indico.frib.msu.edu/even t/52/contributions/1108/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1108/ END:VEVENT BEGIN:VEVENT SUMMARY:Zirconium Hydride Thermal Scattering Law Data DTSTART:20220728T153800Z DTEND:20220728T155000Z DTSTAMP:20260420T153400Z UID:indico-contribution-949@indico.frib.msu.edu DESCRIPTION:Speakers: Andrej Trkov\, Ingrid Švajger (”Jozef Stefan” I nstitute)\n\nMany transition metals react with hydrogen to form stable met al hydrides. Metal hydrides are technologically attractive materials becau se of their ability to store large amounts of hydrogen. There is considera ble interest in zirconium hydrides in the nuclear industry because they ar e used as neutron moderators in nuclear reactors. TRIGA reactors have a un ique fuel composition: a homogeneous mixture of 20 % enriched uranium and zirconium hydride (ZrH ratio close to 1.6). This is the main reason for th e prompt negative temperature reactivity coefficient. Since the hydrogen i n the zirconium hydride acts as a moderator\, most of the moderation occur s in the fuel element itself and only a small part in the water surroundin g the fuel elements. Therefore\, any change in power and fuel temperature directly affects the moderator in the fuel element. In this case\, the fue l and the moderator directly affect the reactivity of the core. This under lines the need to understand the basic atomistic properties of zirconium h ydrides.\n\nIn the present work\, we adopt first-principles calculations t o obtain thermal neutron scattering law data (TSL) of ZrH2 in the ε phase (at room temperature dominant for x > 1.74). This work aims at evaluating our calculation method and compare our results with the current thermal n eutron scattering law data from the ENDF/B-VIII.0 library. The current END F/B-VIII.0 ZrHx nuclear data evaluations do not distinguish between phases . The thermal neutron scattering law data for ZrHx from the ENDF/B-VIII.0 library were generated using historical phonon spectra derived from a cent ral force model and assume incoherent elastic scattering for both bound hy drogen and zirconium\, neglecting the effects of crystal structures that a re important for the scattering from zirconium bound in ZrHx.\n\nThe syste m is modelled and relaxed to its ground state using the density functional theory (DFT) capable computer code VASP. The positions of the atoms are t hen perturbed and the interatomic force constants are calculated. Once the force constants are obtained\, they are transferred to the Phonopy code\, which performs lattice dynamics calculations that seek solutions to the d ynamical matrix problem. The solutions constitute the dispersion relations of the system\, from which the atomic vibrational density of states (DOS) are computed using a geometrical sampling procedure. Once the density of states is known\, the scattering law and all related quantities can be cal culated using the LEAPR module of the NJOY data processing system. The sca ttering law data are the basis for the analysis of thermal reactor systems \, which are frequently modelled by Monte Carlo transport codes to obtain the desired physical reactor parameters. The thermal nuclear data of our c alculated ZrH2 are compared to the ZrHx from the ENDF/B-VIII.0 library. Th e calculated thermal nuclear data is validated by comparing the calculated physical reactor parameters from the Monte Carlo transport code with meas urements of the physical reactor parameters from the TRIGA Mark II researc h reactor at Jožef Stefan Institute.\n\nhttps://indico.frib.msu.edu/event /52/contributions/949/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/949/ END:VEVENT BEGIN:VEVENT SUMMARY:FLASSH 1.0: Thermal Scattering Law Evaluation and Cross Section Ge neration DTSTART:20220728T171600Z DTEND:20220728T172800Z DTSTAMP:20260420T153400Z UID:indico-contribution-955@indico.frib.msu.edu DESCRIPTION:Speakers: N. Colby Fleming (Department of Nuclear Engineering\ , North Carolina State University)\n\nThe Full Law Analysis Scattering Sys tem Hub (*FLASSH*) is an advanced code which evaluates the thermal scatter ing law (i.e. TSL\, S($\\alpha$\,$\\beta$)) for thermal scattering cross s ections and resonance Doppler broadening. These features in the cross sect ion are both fundamentally driven by target atom vibrations\, which are im pacted by the nature of the chemical binding and temperature of the lattic e. The ability to accurately capture these two key cross section features is dependent on accurate\, high fidelity TSL evaluations. *FLASSH* 1.0 pro vides advanced physics capabilities resulting in an improved\, generalized TSL to most accurately represent the lattice dynamics within any material . This improved TSL will allow for consistent analysis in both the thermal and epithermal energy ranges. \n\nThe features for TSL analysis are packa ged within the *FLASSH* GUI for easy user interface. The GUI allows users to visually step through the evaluation process with the added benefit of built-in error checks and automatic input file formatting. The *FLASSH* GU I also provides automatic default values to inform user inputs as well as tool tips which describe variables and special formatting. After evaluatio n\, the GUI also produces plots which provide quick quality assurance chec ks for TSL and cross section output. This GUI makes advanced features in * FLASSH* accessible for users while also reducing the initial learning curv e. \n\nThe *FLASSH* code offers traditional means of evaluating the TSL\, including liquid diffusional contributions. These traditional codes\, howe ver\, are limited by the approximations included in their formulations. Hi storical approximations including the cubic\, incoherent\, and atom site a pproximation provide faster results and are computationally less expensive . Previous codes also were hard coded with a limited material selection. * FLASSH* offers both historical approximated TSL evaluation methods as well as advanced\, generalized formulations. All features in *FLASSH* are gene ralized to allow for any material to be evaluated. Generalized non-cubic f ormulations for both the TSL and elastic contributions are available in *F LASSH*. These non-cubic methods explicitly evaluate the directional depend ence of the lattice phonon modes. Additional contributions from the 1-phon on distinct terms adds increased accuracy to the evaluation. With both non -cubic and 1-phonon components\, the TSL can then be directly compared wit h experimental data for benchmarking. \n\n*FLASSH* produces as output many file formats ranging from formatted user tables to ENDF file 7 and ACE fi les. Free atom cross sections\, particularly the resonance region\, can al so be treated within *FLASSH*. Using the TSL evaluation which is published in the ENDF file 7\, the process of Doppler broadening can also be perfor med. To reproduce historical methods\, free gas Doppler broadening is also available. The improved physics from *FLASSH* linking the thermal scatter ing cross section analysis with the Doppler broadening of resonance cross sections will not only improve the individual components of the evaluation s but also will provide a consistent means of analysis for both energy ran ges. *FLASSH* provides superior physics in defining the TSL which will tra nslate into improve Doppler broadening as well as thermal scattering cross sections.\n\nhttps://indico.frib.msu.edu/event/52/contributions/955/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/955/ END:VEVENT BEGIN:VEVENT SUMMARY:Managing and processing nuclear data libraries with FUDGE DTSTART:20220728T165200Z DTEND:20220728T170400Z DTSTAMP:20260420T153400Z UID:indico-contribution-984@indico.frib.msu.edu DESCRIPTION:Speakers: Caleb Mattoon (Lawrence Livermore National Lab)\, Br et Beck\, Godfree Gert\n\nFUDGE (For Updating Data and Generating Evaluati ons) is an open-source code that supports reading\, visualizing\, checking \, modifying\, and processing nuclear reaction and decay data. For ease of use the frontend of FUDGE is written in Python while C and C++ routines a re employed for computationally intensive calculations.\n\nFUDGE has been developed primarily at Lawrence Livermore National Laboratory (LLNL) with contributions from Brookhaven National Laboratory (BNL). It is used by the LLNL Nuclear Data and Theory (NDT) group to deliver high-quality nuclear data libraries to users for a variety of applications. FUDGE is also the w orld leader in converting data to the Generalized Nuclear Database Structu re (GNDS) and working with GNDS data\, including processing and visualizin g. GNDS is a new extensible hierarchy that has been internationally adopte d as the new standard for storing and using nuclear data libraries\, repla cing the previous standard ENDF-6.\n\nA new version of FUDGE (FUDGE-5.0) i s under preparation for release at https://github.com/LLNL/fudge. This ve rsion has several important changes and adds new capabilities compared to the previous release (FUDGE-4.2.3). Changes include:\n- switching from Pyt hon 2 to Python 3 (the new version requires Python-3.6 or later)\,\n- supp ort for installing FUDGE with the pip Python package-management system\,\n - new interactive visualization tools using PyQT5\,\n- support for reading and writing data files in the GNDS-2.0 format (GNDS-2.0 is in draft form at the time of writing but is expected to be finalized soon)\,\n- enhanced support for processing thermal neutron scattering law data (TNSL)\, inclu ding new evaluations that contain both coherent and incoherent elastic sca ttering\,\n- support for writing hybrid XML/HDF5 GNDS files\, useful espec ially for improving data load times in large\, processed datasets\,\n- var ious fixes to ENDF-6 translation tools\, quality checking tools and data p rocessing.\n\n![Example of FUDGE Doppler broadening and visualization capa bilities][1]\n\n\nThis talk will present an overview of FUDGE\, including a quick tour of how to download and install the code and several examples of using it to perform both simple and not-so-simple nuclear data tasks. W e also present resources for users interested in gaining more experience w ith FUDGE and GNDS.\n\nPrepared by LLNL under Contract DE-AC52-07NA27344.\ n\nLLNL-ABS-827414\n\n\n [1]: https://indico.frib.msu.edu/event/52/contri butions/984/attachments/223/1481/282_Zr90.png\n\nhttps://indico.frib.msu.e du/event/52/contributions/984/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/984/ END:VEVENT BEGIN:VEVENT SUMMARY:Total nuclear reaction cross-section database for radiation protec tion in space applications DTSTART:20220726T133600Z DTEND:20220726T134800Z DTSTAMP:20260420T153400Z UID:indico-contribution-681@indico.frib.msu.edu DESCRIPTION:Speakers: Marco Durante (GSI)\, Lembit Sihver (Technische Univ ersität Wien\, Chalmers University of Technology)\, Martina Giraudo (Thal es Alenia Space)\, Cristoph Schuy (GSI)\, Anastasiia Quarz (GSI\, Hochschu le Darmstadt)\, Wouter de Wet (NASA Langley Research Center\, University o f New Hampshire)\, Felix Horst (GSI)\, Uli Weber (GSI)\, John Norbury (NAS A Langley Research Center)\, Ryan B Norman (NASA Langley Research Center)\ , Giovannia Santin (ESA ESTEC\, RHEA System)\, Laura Bagnale (GSI)\, Clair e-Anne Reidel (GSI)\, Francesca Luoni (GSI\, TUDa)\n\nMonte Carlo simulati on tools make use of models to describe the physics of everything that sur rounds us. For such tools to be reliable\, models as close to reality as p ossible need to be implemented in the simulation. Nuclear reaction cross-s ections play an essential role in simulations for radiation protection in space. Therefore\, a GSI-ESA-NASA collaboration project created a collecti on of total nucleus-nucleus reaction cross-sections\, which have been expe rimentally measured over the last few decades*. The database has been made public and can be found at: https://gsi.de/fragmentation.\nThe data from the collection have been systematically compared to the cross-section mode ls implemented in FLUKA\, PHITS and Geant4\, which are the most commonly u sed Monte Carlo codes for radiation protection in space. Such models are T ripathi\, Kox\, Shen\, Kox–Shen\, and Hybrid-Kurotama. An example of suc h a comparison for Fe-56 ions on C-12 target is shown in Figure 1.\nFinall y\, literature gaps have been identified and considerations have been made about which models fit best the existing data for the most relevant syste ms to radiation protection in space and heavy-ion therapy.\n\n*F Luoni et al 2021 New J. Phys. 23 101201\, DOI: https://doi.org/10.1088/1367-2630/ac 27e1\n\nhttps://indico.frib.msu.edu/event/52/contributions/681/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/681/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear data activities for medium mass and heavy nuclei at Los Al amos DTSTART:20220726T163000Z DTEND:20220726T165400Z DTSTAMP:20260420T153400Z UID:indico-contribution-885@indico.frib.msu.edu DESCRIPTION:Speakers: Matthew Mumpower (Los Alamos National Laboratory)\, Denise Neudecker\, Patrick Talou (LANL)\, Hirokazu Sasaki\, Trevor Sprouse (Los Alamos National Laboratory)\, Toshihiko Kawano\, Mike Herman\, G. We ndell Misch (Los Alamos National Lab)\, Amy Lovell\n\nNuclear data is crit ical for many modern applications from stockpile stewardship to cutting ed ge scientific research. Central to these pursuits is a robust pipeline for nuclear modeling as well as data assimilation and dissemination. We summa rize the ongoing nuclear data efforts at Los Alamos for medium mass to hea vy nuclei. We begin with a discussion of a novel toolkit for model paramet er optimization that is based on a Bayesian technique called hyperparamete r optimization. This mathematical framework affords the combination of dif ferent measured data in determining model parameters and their associated correlations. It also has the advantage of being able to quantify outliers in data. We exemplify the power of this procedure by highlighting evaluat ed cross sections along the Pu isotopic chain and emphasize the importance of model consistency in such evaluations. Finally\, we highlight the succ ess of our tools and pipeline by covering the insight gained from incorpor ating the latest nuclear modeling and data in astrophysical simulations as part of the Fission In R-process Elements (FIRE) collaboration.\n\nhttps: //indico.frib.msu.edu/event/52/contributions/885/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/885/ END:VEVENT BEGIN:VEVENT SUMMARY:Cross Section Measurements and Theoretical Study of the $^{174\,17 6}$Hf$(n\,2n) ^{173\,175}$Hf Reactions DTSTART:20220726T170600Z DTEND:20220726T171800Z DTSTAMP:20260420T153400Z UID:indico-contribution-786@indico.frib.msu.edu DESCRIPTION:Speakers: Eleni Tsivouraki\, Sotirios Harissopulos\, Andigoni Kalamara\, Sotirios Chasapoglou\, Anastasios Lagogiannis\, Michael Axiotis \, Michael Kokkoris\, Michael Serris\, Rosa Vlastou\n\nNeutron induced rea ctions can provide significant information in the field of nuclear physics and applications. Hafnium (Hf) is one of the rare-earth isotopes with a r elative large total neutron cross-section in the thermal neutron energy re gion and neutron induced reactions in reactor materials could lead to the production of long-lived isomeric states of Hf isotopes. Thus\, the knowle dge of neutron cross-sections on Hf isotopes is of great importance both f or applications concerning the interaction of neutrons with matter as well as for testing nuclear models. \n\nIn this study\, experimental cross sec tion measurements for the $^{176}$Hf$(n\,2n)^{175}$Hf and $^{174}$Hf$(n\,2 n)^{173}$Hf reactions were carried out\, using the activation technique. T he neutron beam energy at 15.3 and 17.1 MeV was produced via the $^{3}$H(d \,$n)^{4}$He reaction at the 5.5 MeV Tandem Van de Graaf accelerator labor atory of NCSR “Demokritos”. A thin metallic foil of natural Hf was use d\, while for the determination of the neutron flux at the target position \, reference foils of Al were placed at the front and back of the Hf targe t. The irradiation was continuous for 28 hours leading to a total neutron fluence of $10^{10}-10^{11}$ n/cm$^{2}$ and a BF3 detector was used for mo nitoring the neutron flux during the irradiation. After the end of the irr adiation\, the activity of the Hf target and the Al foils were measured of f-line by two HPGe detectors. The $^{176}$Hf$(n\,2n)^{175}$Hf reaction has been corrected from the contribution of the $^{177}$Hf$(n\,3n)^{175}$Hf a nd $^{174}$Hf$(n\,γ)^{175}$Hf reactions.\nStatistical model calculations based on the Hauser-Feshbach theory have also been performed using the cod e EMPIRE 3.3.2. The predictions have been compared with the data of the pr esent work as well as with data from literature.\n\nhttps://indico.frib.ms u.edu/event/52/contributions/786/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/786/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Data Pipeline DTSTART:20220722T160000Z DTEND:20220722T170000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1211@indico.frib.msu.edu DESCRIPTION:Speakers: Jo Ressler (LLNL)\n\nChair: Ali Dreyfuss\n\nhttps:// indico.frib.msu.edu/event/52/contributions/1211/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1211/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclide production cross sections in proton-induced reactions on Bi at GeV energies DTSTART:20220728T190600Z DTEND:20220728T191800Z DTSTAMP:20260420T153400Z UID:indico-contribution-843@indico.frib.msu.edu DESCRIPTION:Speakers: Hiroki Iwamoto\, Keita Nakano\, Fujio Maekawa\, Haya to Takeshita\, Shin-ichiro Meigo\, Hiroki Matsuda\n\nAn accelerator-driven transmutation system (ADS) is a potential candidate for treating high-lev el radioactive waste generated from nuclear power plants. For predicting t he radioactivity of the components of ADS and assessing impurity behavior in lead-bismuth eutectic (LBE)\, nuclide production cross sections play a vital role. So far\, we have measured 7 nuclide production cross sections in the proton-induced spallation reactions on Bi [1] at 0.4 and 3.0 GeV. I n this work\, a new measurement of nuclide production cross sections on Bi has been conducted at the reaction energies of 0.4\, 1.5\, and 3.0 GeV\, aiming to measure more various nuclide production\, especially Po isotopes by increasing the statistics. A high-intensity proton beam and beam monit oring system enables us to measure the nuclear data with higher accuracy. The theoretical models are employed to calculate the cross sections\, and the reproducibility is investigated.\n\nThe experiment was performed at J- PARC. The proton beams accelerated at 0.4\, 1.5\, and 3.0 GeV impinged ont o the 0.25-mm thick Bi target foils. The number of irradiated protons was estimated by using an integrating current transformer. After the irradiati on\, gamma-rays emitted from the produced nuclei were measured using HPGe detectors for three months. The nuclide production cross sections were der ived from the obtained decay curves.\n\nWe successfully obtained 114 cross sections\, including $^{97}$Ru production cross sections\, which have nev er been measured so far. The measured data were compared with the calculat ions by combining INCL4.6 [2] and GEM [3] implemented in PHITS [4] and by combining INCL++ [5] and ABLA07 [6] models. Also\, a comparison with nucle ar data library JENDL/HE-2007 [7] was performed. The details of the result s will be discussed in the presentation.\n\n**References**\n[1] H. Matsuda et al.\, EPJ Web of Conf. 239\, 06004 (2020).\n[2] A. Boudard et al.\, Ph ys. Rev. C 87\, 014606 (2013).\n[3] S. Furihata\, Nucl. Instrum. Meth. B 1 71\, 251 (2000).\n[4] T. Sato et al.\, J. Nucl. Sci. Technol. 55\, 529 (20 18).\n[5] D. Mancusi et al.\, Phys. Rev. C 90\, 054602 (2014).\n[6] A. Kel ic et al.\, arXiv:0906.4193 (2009).\n[7] Y. Watanabe et al.\, J. Korean Ph ys. Soc. 59\, 1040 (2011).\n\nhttps://indico.frib.msu.edu/event/52/contrib utions/843/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/843/ END:VEVENT BEGIN:VEVENT SUMMARY:Accelerator-based experiments for nuclear data and applications DTSTART:20220722T170500Z DTEND:20220722T180500Z DTSTAMP:20260420T153400Z UID:indico-contribution-1212@indico.frib.msu.edu DESCRIPTION:Speakers: Richard Hughes (LLNL)\n\nChair: Erin Good\n\nhttps:/ /indico.frib.msu.edu/event/52/contributions/1212/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1212/ END:VEVENT BEGIN:VEVENT SUMMARY:Activation Cross Section Measurement of the (n\,2n) Reaction on 20 3Tl DTSTART:20220726T144800Z DTEND:20220726T145100Z DTSTAMP:20260420T153400Z UID:indico-contribution-1089@indico.frib.msu.edu DESCRIPTION:Speakers: Maria Diakaki (Department of Physics\, National Tech nical University of Athens\, Zografou campus\, 15780 Athens\, Greece)\, Ma ria Diakaki (Department of Physics\, National Technical University of Athe ns\, Zografou campus\, 15780 Athens\, Greece)\n\nStudies of neutron-induce d reactions are of considerable significance\, both for their importance t o basic research in nuclear physics and for practical applications in nucl ear technology\, medicine and industry. Thallium is widely used in electro nics\, pharmaceuticals\, fiber optics\, infrared detectors and nuclear med icine. However\, little information is available in literature for neutron induced reactions on Tl isotopes\, with many discrepancies among the exis ting experimental data\, especially in the energy region above ~14 MeV.\n The aim of the present work was to study the cross-section of the (n\,2n) reaction on 203Tl\, by irradiating a natural TlCl pellet target w ith monoenergetic neutron beams at 16.9 and 18.9 MeV. The cross section of the 203Tl(n\,2n)202Tl reaction was measured implementing the activation m ethod\, with respect to the 197Au(n\,2n)196Au and 27Al(n\,α)24Na referenc e reactions. The monoenergetic neutron beam was generated at the 5.5 MV Ta ndem accelerator of NCSR Demokritos\, using the 3H(d\, n)4He reaction. The target and reference foil assembly was placed at approximately 1.5 cm fro m the tritium target\, thus limiting the angular acceptance to ± 23.5°\, where the produced neutrons are practically isotropic and monoenergetic. The fluctuation of the neutron beam flux was monitored with a BF3 detector located 3 m from the neutron source. After the irradiation\, the induced activity of the samples was measured with a HPGe detector of 80% efficienc y\, which was properly shielded with a lead block to reduce the contributi on of natural radioactivity. Monte Carlo simulations using the MCNP code h ave been performed to take into account the gamma-ray self-absorption with in the samples as well as the attenuation of the neutron flux through the target and reference foils. \n Theoretical calculations with the EMPIRE code will also be presented\, using the same parametrisation implemented i n the theoretical study of Ir [1] and Au [2] nuclei\, in an attempt to stu dy the systematics and find a suitable statistical model for the descripti on of all the experimental results in this mass region.\n\n1. A. Kalamara et al.\, Phys. Rev. C 98\, 034607 (2018).\n2. A. Kalamara et al.\, Phys. R ev. C 97\, 034615 (2018).\n\nhttps://indico.frib.msu.edu/event/52/contribu tions/1089/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1089/ END:VEVENT BEGIN:VEVENT SUMMARY:Nuclear Reactions & Applications DTSTART:20220722T182000Z DTEND:20220722T192000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1213@indico.frib.msu.edu DESCRIPTION:Speakers: Brett Carlson\n\nChair: Amy Lovell\n\nhttps://indico .frib.msu.edu/event/52/contributions/1213/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1213/ END:VEVENT BEGIN:VEVENT SUMMARY:X4Pro - universal\, fully relational EXFOR database DTSTART:20220727T183600Z DTEND:20220727T190000Z DTSTAMP:20260420T153400Z UID:indico-contribution-875@indico.frib.msu.edu DESCRIPTION:Speakers: Viktor Zerkin (International Atomic Energy Agency)\n \nEXFOR (EXchange FORmat) database contains experimental nuclear reaction data compiled by the NRDC (Nuclear Reaction Data Centers) network. The net work strictly regulates data format\, rules of compilation\, distribution of work and data exchange between data centers. The data dissemination is not regulated by the network - this includes output data formats\, various database services\, software distribution\, etc. The IAEA provides EXFOR data services through Web retrieval system\, standalone packages (with loc al database and software) for different tasks and computer environment\, a nd plain data files for Web downloading.\nNew tasks in data evaluation req uiring all details of experiments\, growing users’ programming skills an d achievements in computer technologies need new methods of access to EXFO R data and distribution. Some of them are presented here:\n - **X4Lite**: full EXFOR relational database implemented in modern database management s ystem SQLite\, including computational data in JSON table fields and distr ibuted as platform independent single file for PC\n - **EXFOR data correct ion system**: includes automatic re-normalization to new monitor cross sec tions and decay data\, database experts’ corrections and evaluators’ q uality flags available online\n - **X4-JSON/XML**: output from EXFOR retri eval systems in JSON and XML\, easy for use in modern programming language s: Python\, JavaScript\, etc.\, \n - **XC5**: EXFOR translated to computat ional format with possibility to renormalize data to new standards\, to ge nerate correlation matrix using partial uncertainties\, to calculate cross sections of inverse reaction\, etc.\nThe new tools can be useful for data evaluators\, developers of machine learning software and other automatiza tion computer systems\, can also encourage young generation of users to us e EXFOR data in various projects.\n\nhttps://indico.frib.msu.edu/event/52/ contributions/875/ LOCATION:Delta King URL:https://indico.frib.msu.edu/event/52/contributions/875/ END:VEVENT BEGIN:VEVENT SUMMARY:Scalable Risk-Informed Predictive Maintenance Strategy for Operati ng Nuclear Power Plants DTSTART:20220725T174200Z DTEND:20220725T175400Z DTSTAMP:20260420T153400Z UID:indico-contribution-1119@indico.frib.msu.edu DESCRIPTION:Speakers: Vivek Agarwal\n\nOver the years\, the nuclear fleet has relied on labor-intensive\, time-consuming preventive maintenance (PM) programs\, driving up operation and maintenance (O&M) costs to achieve hi gh capacity factors. The primary objective of the research presented in th is paper is to develop scalable technologies deployable across plant asset s and the nuclear fleet in order to achieve risk-informed predictive maint enance (PdM) strategies at commercial nuclear power plants (NPPs). A well- constructed risk-informed PdM approach for an identified plant asset was d eveloped in this research\, taking advantage of advancements in data analy tics\, machine learning (ML)\, artificial intelligence (AI)\, risk model\, and visualization. These technologies would allow commercial NPPs to reli ably transition from current labor-intensive PM programs to a technology-d riven PdM program\, eliminating unnecessary O&M costs.\n\nThe research and development approach (see Figure 1) presented in the paper is being devel oped as part of a collaborative research effort between Idaho National Lab oratory and Public Service Enterprise Group (PSEG) Nuclear LLC. This paper presents the results of analyzing the heterogeneous data associated with the circulating water system (CWS) from both the Salem and Hope Creek NPP sites. Fault modes present in the data were identified based on logs and c orrelated with data to develop salient fault signatures associated with ea ch fault mode. The fault signatures are used to develop diagnostic models using scalable predictive analytics and integrated with plant-level risk a nd economic models. The paper also outlines the development of a user-cent ric visualization application to ensure the right information is available to the right person\, in the right format\, and at the right time.\n\nThe research outcomes presented in this paper lay the foundation and provide a much-needed technical basis to start focusing on additional needs such a s explainability and trustworthiness of ML- and AI-based technologies as p art of future research.\n\nhttps://indico.frib.msu.edu/event/52/contributi ons/1119/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/1119/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Calculation of giant dipole resonance with noniterativ e finite amplitude method DTSTART:20220727T153300Z DTEND:20220727T154500Z DTSTAMP:20260420T153400Z UID:indico-contribution-933@indico.frib.msu.edu DESCRIPTION:Speakers: Hirokazu Sasaki (LosAlamos National Laboratory)\n\nT he giant dipole resonance (GDR) is one of the most well-known collective e xcitation modes since the dawn of research on nuclear physics. The origin of GDR is a collective motion of neutrons against protons inside the nucle us. Since its discovery in the photoabsorption cross section\, extensive t heoretical studies have been done to reveal the nature of such electric di pole excitation. The (quasiparticle) random-phase approximation [(Q)RPA] b ased on the nuclear density functional theory is commonly used to address the collective excitation. With the finite amplitude method (FAM)\, the li near equations of (Q)RPA are iteratively solved and the computational cost of (Q)RPA is significantly reduced. Here\, we analytically derive the lin ear terms of residual interactions and calculate cross section of GDR base d on FAM. In our FAM implementation\, the residual interaction is explicit ly linearized\, so that we can avoid iterative procedure as done in usual FAM and speed-up the calculation. The calculated photonuclear reactions cr oss sections are compared with available experimental data to demonstrate how the fully microscopic density functional theory predicts GDR without a ny phenomenological parameters.\n\nhttps://indico.frib.msu.edu/event/52/co ntributions/933/ LOCATION:Placerville URL:https://indico.frib.msu.edu/event/52/contributions/933/ END:VEVENT BEGIN:VEVENT SUMMARY:First precise measurement of the U-235 neutron capture cross-secti on at thermal and sub-thermal neutron energies DTSTART:20220726T181500Z DTEND:20220726T183900Z DTSTAMP:20260420T153400Z UID:indico-contribution-791@indico.frib.msu.edu DESCRIPTION:Speakers: Alfred Priller\, Peter Steier\, Jan Heyse\, Michaela Forehlich\, Roberto Capote\, Ulli Koester\, Karin Hain\, Christian Stiegh orst\, Stefaan Pomme\, Peter Schillebeeckx\, Tobias Jenke\, Jan Wagemans\, Zsolt Revay\, Stéphanie Roccia\, Torsten Soldner\, Anton Wallner\n\nThe recommended cross-section value for $^{235}$U neutron-capture at thermal energies is largely based on the difference from total and competing cross -sections of $^{235}$U. Despite its importance as a thermal neutron consta nt and its high value (100 barn)\, direct capture measurements are rare (o nly two exist for thermal energies) and exhibit large uncertainties. The r eason is the difficulty to measure the characteristic radiation of the rea ction product $^{236}$U within a dominant fission background and with $^{2 36}$U having a long half-life of 23.4 Myr. Importantly\, capture of $^{235 }$U may exhibit a significant deviation from a pure 1/v-behaviour around a nd below thermal energies. \n\nHere\, we present highly accurate capture d ata by applying a multi-isotope spike method to minimize systematic effect s: we used the combination of neutron activation and subsequent accelerato r-mass-spectrometry (AMS) for direct atom counting of the reaction product $^{236}$U. By utilizing different neutron fields we mapped the energy dep endence of the capture cross section in six activations from thermal to ul tra-cold energies: with an almost pure Maxwellian spectrum at room tempera ture at BR1 (Mol\, Belgium)\, with cold neutrons at MLZ (Munich\, Germany) and ILL (Grenoble\, France) as well as with very cold neutrons also at IL L. AMS was performed at the VERA laboratory in Vienna. Using AMS\, the cap ture cross-section is deduced simply by the measured isotope ratio $^{236} $/$^{235}$U divided by the neutron fluence. \n\nBy irradiating Uranium sam ples of natural U composition\, we measured also $^{239}$Pu\, the decay pr oduct of $^{239}$U produced from $^{238}$U(n\,γ) in the same samples. I.e . we deduced simultaneously the $^{236}$U/$^{239}$Pu ratio\, giving direct ly the cross-section ratio of $^{235}$U(n\,γ) relative to $^{238}$U(n\,γ ). The latter ratio is therefore completely independent of the neutron flu ence.\n\nActivation with AMS allowed for an accurate determination of the $^{235}$U(n\,γ) and $^{238}$U(n\,γ) cross sections with an uncertainty o f ~2% across the whole energy range. We will present our new experimental results and will also demonstrate the potential of this method for indepen dent and accurate nuclear reaction cross section measurements.\n\nhttps:// indico.frib.msu.edu/event/52/contributions/791/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/791/ END:VEVENT BEGIN:VEVENT SUMMARY:Session chair training DTSTART:20220721T130000Z DTEND:20220721T140000Z DTSTAMP:20260420T153400Z UID:indico-contribution-1263@indico.frib.msu.edu DESCRIPTION:Speakers: Ramona Vogt\n\nhttps://indico.frib.msu.edu/event/52/ contributions/1263/ LOCATION:Sacramento URL:https://indico.frib.msu.edu/event/52/contributions/1263/ END:VEVENT BEGIN:VEVENT SUMMARY:Development of new library of thermal scattering kernels using the NJOY+NCrystal tool DTSTART:20220728T164000Z DTEND:20220728T170400Z DTSTAMP:20260420T153400Z UID:indico-contribution-956@indico.frib.msu.edu DESCRIPTION:Speakers: Jose Ignacio Marquez Damian (European Spallation Sou rce)\n\nNJOY+NCrystal is an open source tool which can be used to generate thermal neutron scattering libraries in a format that supports both coher ent and incoherent elastic components for crystalline solids. The tool is based on a customized version of NJOY2016 [1] which calls the thermal scat tering software NCrystal [2] for the calculation of the elastic components . The libraries can both be generated in a modified ENDF-6 format that sto res both these components\, which requires the usage of a patched Monte-Ca rlo transport software to read these libraries\, and also in the current E NDF-6 standard format. We give some examples of libraries generated in the se ways for materials that are coherent-dominant\, incoherent-dominant and mixed-elastic scatterers. NJOY+NCrystal is available online [3] and can b e readily used to create thermal scattering libraries for future materials of interest for a large range of nuclear applications\, which is demonstr ated by the creation of 213 new and updated libraries [4]\, presented here .\n\nThis work was funded by the HighNESS project at the European Spallati on Source. HighNESS is funded by the European Framework for Research and I nnovation Horizon 2020\, under grant agreement 951782.\n\n[1] Macfarlane\, Rt\, Douglas W. Muir\, R. M. Boicourt\, Albert Comstock Kahler III\, and Jeremy Lloyd Conlin. The NJOY nuclear data processing system\, version 201 6. No. LA-UR-17-20093. (2017).\n[2] Cai\, X-X.\, and Thomas Kittelmann. NC rystal: A library for thermal neutron transport. Computer Physics Communic ations 246\, 106851 (2020).\n[3] https://github.com/highness-eu/\n[4] http s://github.com/highness-eu/NJOY-NCrystal-Library\n\nhttps://indico.frib.ms u.edu/event/52/contributions/956/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/956/ END:VEVENT BEGIN:VEVENT SUMMARY:Beta-delayed neutron emission - a new opening DTSTART:20220727T140000Z DTEND:20220727T142400Z DTSTAMP:20260420T153400Z UID:indico-contribution-911@indico.frib.msu.edu DESCRIPTION:Speakers: Robert Grzywacz (University of Tennessee)\n\nBeta-de layed neutron emission is a dominant decay mode for the very neutron-rich nuclei. With the opportunities offered by new generation radioactive beam facilities\, we can perform experiments with a larger and more exotic pool of isotopes. This enabled us to revisit the conventional views on the fun damentals of beta delayed neutron emission. However\, new data and improve d models are necessary because of the critical role of beta-delayed neutro n emission for astrophysics (r-process) and reactor physics. Using experim ental results obtained for very exotic isotopes with neutron arrays such a s VANDLE or BRIKEN\, I will show how these recent measurements enabled us to improve the understanding of this process. One of the central question s is if and how the nuclear structure effects may influence beta delayed n eutron emission. The results on competition of between 1n and 2n emission will be presented and explained using a combination of shell-model and sta tistical model description. I will also show examples where the assumpti on of statistical neutron emission from the compound nucleus may be broken . \nThis research is supported U.S. Department of Energy\, National Nuclea r Security Administration under the Stewardship Science Academic Alliances program through DOE Award No. DE-NA0002934 and DE-NA0003899\,and DOE Offi ce of Science Award No. DE-FG02- 96ER4093.\n\nhttps://indico.frib.msu.edu/ event/52/contributions/911/ LOCATION:Folsom URL:https://indico.frib.msu.edu/event/52/contributions/911/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Short-Lived Fission Product Yield Results At Oregon St ate University DTSTART:20220726T153700Z DTEND:20220726T153800Z DTSTAMP:20260420T153400Z UID:indico-contribution-1113@indico.frib.msu.edu DESCRIPTION:Speakers: Aaron Tamashiro (Oregon State University)\n\nFission product yields play an important role for nuclear reactor fuel cycle\, nu clear reactor\ndecay heat\, and nuclear reactor waste inventory. Multiple techniques have been used to determine\nfission product yields for many de cades to support reactor design. For our purposes\, we will be\nperforming $\\gamma$-ray spectroscopy on $\\beta$-decaying fission products followin g a prompt fission neutron\nspectrum irradiation. Previous work has been p erformed using the Godiva-IV critical assembly to\ndetermine fission produ ct yields starting 1 hour after irradiation and data was recorded for 7 da ys.\nIn order to observe shorter-lived fission products\, a new rabbit sys tem and $\\gamma$-ray counting setup is\nbeing developed by Lawrence Liver more National Laboratory (LLNL) and Oregon State University\n(OSU) for use in a campaign of measurements on $^{238}$U at the OSU TRIGA reactor. The counting\nsetup will consist of six BGO Compton-suppressed HPGe clover det ectors connected to a new\nVME-based digital data acquisition system. Data will be recorded in list-mode to analyze time-\ndependant behavior of the $\\gamma$-spectra. The clover detectors have relative efficiency of 150% (to 3×3\nin. NaI(Tl) crystal at 1.33 MeV) and the solid angle coverage of four detectors is approximately\n9% for the array. The $^{238}$U samples will be delivered in front of the detectors directly from the\nreactor cor e via the rabbit facility. One complication with rabbit systems is that th ere may exist trace elements that will undergo neutron capture reactions a nd introduce extraneous $\\gamma$-rays in the\ntime scale of interest. Thi s prompted a study of different pure polyethylene sample materials from\nv arious suppliers at the OSU TRIGA reactor and the development of a new rab bit. Results from this measurement will be discussed.\n\nhttps://indico.fr ib.msu.edu/event/52/contributions/1113/ LOCATION:Gold Rush URL:https://indico.frib.msu.edu/event/52/contributions/1113/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Benchmarking of Modern Radiation Transport Codesfor Ap plication to Fusion Neutronics DTSTART:20220728T155000Z DTEND:20220728T161400Z DTSTAMP:20260420T153400Z UID:indico-contribution-841@indico.frib.msu.edu DESCRIPTION:Speakers: Alex Valentine (UKAEA)\n\nThe accurate and efficient mapping of the radiation environment in a nuclear fusion reactor requires the most advanced radiation transport tools. The Monte Carlo method has l ong been deployed to deal with the complexity of fusion relevant geometrie s\, with MCNP the adopted industry standard code among the European and wi der international community in this field. However\, reliance on a single code\, particularly relating to the real and perceived limitations of MCNP and strict licensing conditions have driven explorations into alternative s. It is imperative that the transport codes meet: i) stringent modelling and analysis requirements for fusion\, and ii) may be used within an inte grated engineering design workflow that can support ITER\, DEMO\, STEP ana lysis as well as experimental devices such as JET and MAST. The radiation transport codes\, Serpent\, OpenMC as well as the framework for allowing C AD based transport\, DAGMC\, are being actively researched and have shown promise to improve the efficiency of at least one aspect of the current be st practices in fusion neutronics workflows. To date the codes have largel y been explored by researchers in isolation through simplified (and in lim ited cases\, more complex) fusion benchmarks against MCNP and to a lesser extent to experiment. The paper will present a detailed assessment of the explored transport codes adopting both CSG and CAD based workflows as well as rigorously validating the ability to interface with nuclear data\, inc luding reading in and correctly interpreting the data captured in ACE file format. Specifically\, FENDL and JEFF neutron transport libraries will be compared in determining several fusion relevant responses such as DPA\, n uclear heating and particle flux for several fusion-relevant benchmarks. T he study will be extended to the evaluation of dose rates through interfac ing with the MCR2S method calling TENDL activation files. A suitable set o f metrics for assessing the relative capabilities of the transport codes h as already been established\, as well as identifying and preparing a workf low for converting the computational and experimental models\, consistent run parameters and tallies into the relevant code input formats. For the l atter\, several experiments from the SINBAD database will be explored\, wi th contributions from this work supporting the activities of the Working P arty on International Nuclear Data Evaluation Co-operation Subgroup 47 (WP EC SG47). The capabilities and outstanding needs for the application of ea ch respective code to full-scale fusion neutronics will be concluded.\n\nh ttps://indico.frib.msu.edu/event/52/contributions/841/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/841/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) New experimental decay data for nuclei around $^{78}$N i and its astrophysical impact DTSTART:20220726T173000Z DTEND:20220726T174200Z DTSTAMP:20260420T153400Z UID:indico-contribution-694@indico.frib.msu.edu DESCRIPTION:Speakers: BRIKEN collaboration BRIKEN collaboration (BRIKEN co llaboration)\, Alvaro Tolosa-Delgado (University of Jyvaskyla\, Finland)\n \nHow elements are made in the Universe is an open long-standing question. Several processes are invoked to explain the observed elemental abundance s in our Solar System [1] and in our Galaxy [2].\nComplex simulations of a strophysical events are used to study the origin of the heavy elements and quantify the contribution of the r-process to the observed elemental abun dances [3]. This process proceeds through very neutron rich nuclei\, most of them experimentally inaccessible so far and theoretical estimates suppl y the lack of experimental data\, introducing large uncertainties in the c alculated abundances [4]. The main decay mode of such nuclei is beta-decay accompanied by the emission of one or more neutrons. Accurate experimenta l data of these nuclei\, particularly their half-lives $\\mathrm{T}_\\math rm{1/2}$ and neutron emission probabilities $\\mathrm{P}_\\mathrm{xn}$\, w ill contribute to reduce the uncertainties of the calculated elemental abu ndances and allow a critical comparison with several nuclear structure mod els.\nThe BRIKEN (Beta delayed neutron measurements at RIKEN) collaboratio n was launched to provide precise new measurements of $\\mathrm{T}_\\mathr m{1/2}$ and $\\mathrm{P}_\\mathrm{xn}$ of very neutron rich nuclei which a re important for r-process nucleosynthesis [5]. We will report new experim ental values from RIBF127 experimental campaign for 39 nuclei between $^\\ mathrm{75}$Co and $^\\mathrm{94}$Br\, for which 12 $\\mathrm{P}_\\mathrm{x n}$ and 7 $\\mathrm{T}_\\mathrm{1/2}$ are measured for first time and the remaining ones improved. The analysis methods [6] were refined and systema tic errors carefully considered in order to improve the accuracy of result s. The astrophysical impact in several scenarios was explored and the most relevant cases will be presented.\n\nhttps://indico.frib.msu.edu/event/52 /contributions/694/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/694/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Automated grouping of spatially distributed detectors in neutron time-of-flight experiments based on multivariate similarity DTSTART:20220725T173000Z DTEND:20220725T174200Z DTSTAMP:20260420T153400Z UID:indico-contribution-770@indico.frib.msu.edu DESCRIPTION:Speakers: Jose I. Robledo\n\nNowadays\, in neutron time of fli ght measurements\, there are experimental setups in which many detectors r ecord data during a single experiment. It is usually desirable to be able to sum several spectra in order to increase counting statistics\, and ther efore decrease uncertainties\, for further analysis. A problem arises in t ime-of-flight experiments when the available spectra are acquired with a s et of spatially distributed detectors\, each forming a different source-sa mple-detector angle and at different sample-detector distances. Since thes e spectra record the neutron’s time of flight after scattering\, and the neutron scattering depends on the Q vector\, then these spectra are not a rbitrarily summable. In this work\, we propose an automated methodology fo r wisely adding spectra based on their multivariate similarity by means of machine learning techniques\, such as k nearest neighbors combined with T -distributed Stochastic Neighbor Embedding (t-SNE). We exemplify it in the effective temperature determination of hydrogen in ethane and triphenylme thane samples by means of Deep Inelastic Neutron Scattering\, measured at the VESUVIO spectrometer (ISIS facility\, UK). The proposed methodology ca n be applied in other time-of-flight experiments\, in which detectors loca ted at different angles record complete spectra\, and with this method the ir degree of compatibility can be determined.\n\nhttps://indico.frib.msu.e du/event/52/contributions/770/ LOCATION:Sutter's Fort URL:https://indico.frib.msu.edu/event/52/contributions/770/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Simultaneous measurements of prompt fission γ-rays an d neutrons with CLLBC detectors DTSTART:20220726T134800Z DTEND:20220726T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-602@indico.frib.msu.edu DESCRIPTION:Speakers: Marzio Vidali\, Stephan Oberstedt\, Andreas Obersted t\, Cristiano Lino Fontana\n\nThe knowledge about prompt neutrons and $\\g amma$-rays spectral characteristics in nuclear fission is essential to und erstand the nuclear de-excitation process of fission fragments [1\,2]. Pre ferably\, these observables should be known in correlation with fragment p roperties like mass and kinetic energy.\n\nTypical multi-parameter experim ents require long measurement times and efficient detector systems. A part icular problem for prompt-neutron spectral measurements is that usual dete ctors are not sensible to low neutron energies. Liquid-scintillator (LS) d etectors\, which allow neutron-$\\gamma$ separation\, exhibit low-energy t hresholds for neutrons from $500~\\text{keV}$ to $700~\\text{keV}$. For st ilbene-based detectors this threshold is about $100~\\text{keV}$ lower. In order to overcome this low-energy limitation\, usually combined measureme nts are performed. Lithium-glass ($^6\\text{Li}$) detectors are employed f or lower-energy neutrons. Afterwards spectra coming from LS and $\\text{Li }$-glass need to be matched.\n\nRecently\, the so-called Caesium Lanthanum Lithium BromoChloride (CLLBC) detectors became available on the market. T he detector material consists of a lanthanide-halide compound. Due to the presence of $^6\\text{Li}$ and $\\text{Cl}$\, it is sensitive to $\\gamma$ rays and neutrons. The pulse shape discrimination capabilities allow to d istinguish between radiation types. We performed a full characterization o f this type of detectors in terms of energy resolution\, detection efficie ncy and coincidence-timing resolution using $\\gamma$-rays between $80\\te xt{keV}$ and $9\\text{MeV}$. We determined the neutron response relative t o the prompt-neutron spectrum from the spontaneous fission of $^{252}\\tex t{Cf}$.\n\nApplicability of CLLBC detectors for simultaneous measurements of prompt $\\gamma$ rays and neutrons in fission will be discussed.\n\n\n[ 1] O. Litaize _et al._\, Eur. Phys. J. A (2015) 51:177.\n[2] M. Travar\, V . Piau _et al._\, Physics Letters B 817\, 136293 (2021)\n\nhttps://indico. frib.msu.edu/event/52/contributions/602/ LOCATION:American River URL:https://indico.frib.msu.edu/event/52/contributions/602/ END:VEVENT BEGIN:VEVENT SUMMARY:(WITHDRAWN) Automation of Nuclear Data Validation through Integral Benchmarks DTSTART:20220727T140000Z DTEND:20220727T141200Z DTSTAMP:20260420T153400Z UID:indico-contribution-991@indico.frib.msu.edu DESCRIPTION:Speakers: Wim Haeck\, Cecile Toccoli\n\nVerification and valid ation are essential components of the nuclear data development process\, s ince only those data that have been demonstrated to accurately simulate re al-life applications can be relied upon for those applications. While most nuclear data work relies on so-called 'differential' measurements\, the v alidation of this work requires data from full systems also called Integra l Benchmarks. Thousands of integral benchmarks are available and their use for Nuclear Data validation requires an automated process to minimize wor k time and improve Quality Assurance. For this purpose\, an automated tool is developed at LANL.\n\nThe automated Nuclear Data Validation Tool is bu ilt as a tool kit. It is designed to be open source and user friendly. The automated tool is composed of five modules. When using all the modules su ccessively\, it aims at processing one or several ENDF format data file to be used by the MCNP transport code to run a selection of integral benchma rks and provide simulation results into graphs or tables. Each module can be run separately as well. \n\nThe first module encapsulates the NJOY dat a processing code to create a full or a partial nuclear data file library in the ACE format and its associated xsdir file. Parameters available to u sers are temperatures and the NJOY version code. The second module constit utes a database of MCNP input files associated to a search functionality. About 1\,200 of input files from the International Criticality Safety Benc hmark Evaluation Project (ICSBEP) are available. Benchmarks and benchmark input files can be selected through metadata and isotope occurrence. User- defined libraries or the regular MCNP libraries are available. The library definition operates at the isotope level. The third module is an MCNP run launcher. For a list of cases\, it submits runs either sequentially or si multaneously. Workstation as well as HPC platforms are supported\; 6.1 and newer versions of MCNP are accessible. Parallelism through MPI\, OMP or m ixed MPI/OMP is user-defined as well as the architecture of the computing platform. The postprocessing of the MCNP output files is performed in the fourth module. Results are stored in json files. This module can also perf orm comparisons to experimental values. \nThe last module is dedicated to documentation and the presentation of results through graphs and/or tables . For each plot\, all parameters are user-defined. Plot parameters can be saved and stored into a list of pre-defined graphs for further use.\n\nhtt ps://indico.frib.msu.edu/event/52/contributions/991/ LOCATION:Capitol URL:https://indico.frib.msu.edu/event/52/contributions/991/ END:VEVENT END:VCALENDAR