Conveners
Reactor Data: I
- Dan Roubtsov
Reactor Data: II
- Robert Mills
Reactor Data: III
- Luiz Leal (IRSN)
Reactor Data: IV
- Grégoire Kessedjian (CEA)
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Grégoire Kessedjian (CEA Cadarache IRESNE/DER/SPRC/LEPh)25/07/2022, 09:30
From fission yield measurements to evaluation: correlations of multi-observable analysis
S.M. Cheikh 1, G. Kessedjian 1, A. Chebboubi 1, O. Serot 1 and C. Sage 21 CEA, DES, IRESNE, DER, SPRC, LEPh, Cadarache center, F-13108 Saint Paul lez Durance, France
2 LPSC, Université Grenoble-Alpes, CNRS/IN2P3, 38026 Grenoble, FranceTopics for submission: Fission yield evaluation
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Keywords: fission... -
Abdelaziz Chebboubi (CEA)25/07/2022, 09:54
A. Chebboubi1, D. Bernard1, V. Vallet1, G. Kessedjian1, O. Méplan2, Y.H. Kim3, U. Köster3, Ch.E. Düllmann4,5,6, F. Géhin1, M. Houdouin-Quenault1,2, O. Litaize1, C. Mokry4,6, M. Ramdhane2, J. Runke4,5 ,C. Sage3, O....
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Yasushi Nauchi (Central Research Institute of Electric Power Industry)25/07/2022, 10:06
For safe use of nuclear reactor core, slowing down of neutrons and reaction rates inside the core should be predicted accurately. 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 irradiation measurement of gamma rays. As an in-situ...
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84. Measurement of 233U-HU Substitution Reactivity Worth in KUCA for Validation of 233U Nuclear DataProf. Tadafumi Sano (Kindai University)25/07/2022, 10:18
As engineering discussions of the feasibility of new reactor systems, it is necessary to evaluate the impact of the fuels and materials for the neutronics characteristics such as criticality, conversion rate, and fuel balance. It is important to perform the validation of 233Th and 233U nuclear data for a thorium-based nuclear reactor, because those nuclear data contribute...
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Jun-ichi Hori (Kyoto University)25/07/2022, 10:30
As engineering discussions of the feasibility of new reactor systems, it is necessary to evaluate the impact of the fuels and materials for the neutronics characteristics such as criticality, conversion rate, and fuel balance. It is important to perform the validation of 232Th and 233U nuclear data for a thorium-based nuclear reactor, because those nuclear data contribute...
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Gustavo Alcalá (Instituto de Física Corpuscular, CSIC-Univ. de Valencia, E-46071 Valencia, Spain.)25/07/2022, 11:45
Nuclear reactors are copious sources of antineutrinos. This is the main reason why reactors have played a key role in the discovery of the neutrino and in the study of neutrino oscillation phenomena. The comparison of the neutrino flux measurements performed at short baselines with the improved conversion procedure by Huber [1] and Mueller [2] led to the discovery of the so-called reactor...
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A Algora (1) Instituto de Física Corpuscular, CSIC-Univ. de Valencia, E-46071 Valencia, Spain)25/07/2022, 12:09
A. Algora1,2, V. Guadilla3, J. L. Tain1, M. Fallot4, M. Estienne4, A. Porta4, L. Giot4, L. Le Meur4, A. Beloeuvre et al. for the DTAS Jyvaskyla Collaboration
1)Instituto de Física Corpuscular, CSIC-Univ. de Valencia, E-46071 Valencia, Spain
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2)Institute of Nuclear Research (ATOMKI), P.O. Box 51, H-4001 Debrecen, Hungary
3)Faculty of Physics, University of Warsaw, 02-093, Warsaw,... -
Carlos Paradela (European Commission, Joint Research Centre (JRC))25/07/2022, 12:21
Criticality safety analysis is needed at various stages of the nuclear fuel cycle, including the back-end of the fuel cycle, i.e. reprocessing, 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...
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Chris Chapman (Oak Ridge National Laboratory)25/07/2022, 12:33
A resolved resonance region evaluation of 140,142Ce has been carried out by Oak Ridge National Laboratory. Requested by the US Nuclear Criticality Safety Program, this evaluation is based on recent high-resolution transmission 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...
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Dr Enrique M. González Romero (CIEMAT)26/07/2022, 06:00
The SANDA H2020-EURATOM project, Supplying Accurate Nuclear Data for energy and non-energy Applications, brings together the majority of the European nuclear data community (35 partners from 19 countries), infrastructures and resources to produce accurate and reliable nuclear data tools including data, codes and methodologies that can be used to simulate, analyse, optimize, exploit and...
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Matteo Vorabbi (Brookhaven National Laboratory)26/07/2022, 06:24
In the unresolved resonance region (URR), cross sections for neutrons interacting with nuclei have resonances that cannot be measured nor predicted, hence only statistical values are provided. Often, proper simulations by neutronic transport codes require special data and handling in the URR to account for the variation in the cross sections in this region. The current methodology used to...
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Dr Robert William Mills (UK National Nuclear Laboratory)26/07/2022, 06:36
The Advanced Fuel Cycle Programme funded by the UK Government through the Department for Business, Energy & Industrial Strategy revolves around developing capability and capacity for nuclear while seeking to reduce costs across the nuclear lifecycle, to ensure that nuclear can play a part in delivering secure, low-carbon energy in the global market. This includes the development of Advanced...
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Roberto Capote (IAEA NDS)26/07/2022, 06:48
New U-235 and U-238 evaluations [1-3] were undertaken within the OECD/NEA Data Bank CIELO Project [4] and were adopted for the ENDF/B-VIII.0 library [5], which was released in 2018. Since then, several reports and publications were released that showed serious discrepancies with the light water reactor (LWR) performance of the previous ENDF/B-VII.1 library [6] in criticality studies as the...
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Pablo Romojaro (SCK CEN)26/07/2022, 07:00
The Multi-purpose hYbrid Research Reactor for High-tech Applications (MYRRHA) is a flexible experimental 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.
In order to comply with MYRRHA reactor design requirements, uncertainties must be...
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Shengli Chen26/07/2022, 07:12
Neutron irradiation damage is a key factor that influences behaviors of nuclear materials. Folding the specific 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 codes, such as ERANOS and OpenMC. However, because the...
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Dr Danila Roubtsov (Canadian Nuclear Laboratories (CNL))26/07/2022, 09:30
Among the photo-nuclear reactions of light nuclides, the photo-disintegration of deuterium, $^2{\mathrm H}(\gamma,{\mathrm n})^1{\mathrm H}$, is arguably the most important one for nuclear systems with heavy/light water. In multiplying/critical systems, this reaction is also a source of delayed neutrons due to the delayed gamma emission of certain fission products. Therefore, it is important...
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Luiz Leal (IRSN)26/07/2022, 09:54
Recent experimental data measurements, 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 measurement has been carried out at the GELINA facility at the Joint Research Center Geel from the energy threshold (2.354 MeV) to 9 MeV. Additionally,...
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Nicolas Dari Bako (IPHC/CNRS)26/07/2022, 10:06
For the improvement of Generation IV nuclear reactors simulation, accurate evaluated data are required. Among others, a reaction of interest is the neutron inelastic scattering as it modifies the energy distribution of neutrons. In the context of the innovated Th/U cycle and for a better knowledge of the neutron inelastic scattering on thorium 232, experiments have been performed at...
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Mrs Valentina Fabrizio26/07/2022, 10:18
The increasing interest worldwide in Lead-cooled Fast Reactors (LFRs) substantiates the need to validate the analytical codes and methods used to support their design. For neutronic analyses, this is chiefly reflected in assessing the impact of nuclear data uncertainties on the integral and local parameters resulting from such analyses. Besides this driving interest, the aim of refining...
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Dr Naohiko Otsuka (International Atomic Energy Agency), Dr Osamu Iwamoto (Japan Atomic Energy Agency)26/07/2022, 10:30
The fast neutron fission cross 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 and their ratios in the EXFOR library were reviewed with the source articles. Additionally, Poenitz’s data compiled in his GMA database were reviewed. We found about 160 datasets are archived with the...
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Yongli Xu26/07/2022, 10:42
In order to reduce the uncertainties in the design and operation of accelerator-driven systems (ADSs), high-precision 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...
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Pierre Leconte26/07/2022, 10:54
Delayed neutron data is essential in inherent reactor safety and in reactor control since it is used to estimate the reactivity. The quantities of interest related to delayed neutrons are the average delayed neutron yield, and the group constants that define the kinetics of delayed neutron emission.
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Discrepancies among the evaluated data as well as missing covariance in most of international... -
Dimitri Rochman (Paul Scherrer Institute)
The characterization of Spent Nuclear Fuel (SNF) is a crucial step towards safe and
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economical designs of transport casks, disposal canisters, and interim or long-term
storage facilities. A number of quantities are at the heart of such characterization:
isotopic compositions, decay heat, gamma/neutron emission for the SNF themselves,
and criticality for specific SNF configurations. For these... -
Preston Awedisean (LBL/UCB)
The Fast Loading User Facility for Fission Yields (FLUFFY) has been used to measured short-lived fission yields on 238U and 239Pu via cyclical neutron activation analysis. Sub-second transport times allow FLUFFY to observe gamma-ray signatures from fission products with half-lives of less than one second. This ability makes it possible to report multiple independent fission product yields...
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