Conveners
Integral Measurements: I
- Marie-Anne Descalle (LLNL)
Integral Measurements: II
- John Bess
Integral Measurements: III
- Boris Pritychenko (BNL)
-
Ivan Alexander Kodeli (CCFE/UKAEA Abingdon)27/07/2022, 06:00
Working Party on International Nuclear Data Evaluation Co-operation Subgroup 47 (WPEC SG47) entitled "Use of Shielding Integral Benchmark Archive and Database for Nuclear Data Validation" was started in June 2019 with the objectives to promote a more systematic and wider use of shielding benchmark experiments in nuclear data and transport code validation and development, to provide feedback on...
Go to contribution page -
Jesson Hutchinson (LANL)27/07/2022, 06:24
\documentclass{style/nseJournal}
\usepackage{enumitem}
\usepackage{xcolor}
\usepackage{hyperref}
\usepackage{cleveref}
\usepackage{graphicx}
\usepackage{rotating}
\usepackage{ulem}\newcommand{\beff}{$\beta_\mathrm{eff} $}
\newcommand{\keff}{$k_\mathrm{eff}$}\begin{document}
\title{EUCLID: A New Approach to Improve Nuclear Data Coupling Optimized Experiments with Validation using Machine...
Go to contribution page -
Dr Bohumil Jansky (Research Centre Rez)27/07/2022, 06:36
Abstract
Go to contribution page
The leakage neutron spectra measurements have been done on benchmark spherical assembly-nickel sphere with diameter of 50 cm and copper cube with an edge of 48.4 cm. The Cf-252 neutron source was placed into the centre of nickel sphere and copper cube. The proton recoil method was used for neutron spectra measurement using spherical hydrogen proportional detectors (HPD) with pressure... -
Noah Kleedtke (LANL)27/07/2022, 06:48
LA-UR-21-29561
Abstract
Go to contribution pageHigh-fidelity simulation of nuclear systems are paramount to the operational success and safety of many nuclear applications. Simulations rely on quality nuclear data. The nuclear data input for these simulations is continuously being reassessed by nuclear data evaluators. One way to support this ongoing evaluation is to present the evaluators with detailed analysis... -
Cecile Toccoli27/07/2022, 07:00
Verification and validation are essential components of the nuclear data development process, since only those data that have been demonstrated to accurately simulate real-life applications can be relied upon for those applications. While most nuclear data work relies on so-called 'differential' measurements, the validation of this work requires data from full systems also called Integral...
Go to contribution page -
Catherine Percher (Lawrence Livermore National Laboratory)27/07/2022, 07:45
The goal of the U.S. Nuclear Criticality Safety Program’s (NCSP) Thermal/Epithermal eXperiments (TEX) is to design and conduct new critical experiments to address high priority nuclear data needs from the nuclear criticality safety and nuclear data communities. The first set of five TEX experiments, using layers of plutonium-aluminum Zero Power Physics Reactor (ZPPR) plates stacked with...
Go to contribution page -
Mr Nicolas Leclaire27/07/2022, 08:09
The development of bias estimation methodologies has been a great tool for data uncertainty assessments. In particular, keff data and their uncertainties are becoming paramount for criticality-safety and reactor physics assessment. Moreover, the adjustment of cross sections implemented to match experimental keff within their uncertainty margins is important to produce the requested bias and...
Go to contribution page -
Mr Tomas Czakoj (Centrum Vyzkumu Rez ltd.)27/07/2022, 08:21
A new setup is being prepared in Centrum Výzkumu Řež for the measurement of prompt capture and inelastic gammas coming from neutron interactions. These gammas are important for safety during reactor operations (worker’s protection or radiation damage) or have applications in many areas like element identification in soil and space.
Go to contribution page
The setup consists of an aluminum sphere with a 50 cm diameter... -
Marie-Anne Descalle (LLNL)27/07/2022, 08:33
The 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 specifications 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...
Go to contribution page -
Dr Romain BOFFY (CEA Cadarache)27/07/2022, 08:45
The transfer function of a zero-power thermal reactor was successfully measured by means of a pile noise experiment at low frequency. During a month-long experimental campaign, neutron fluctuations were acquired using excore 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...
Go to contribution page -
Wim Haeck (LANL)27/07/2022, 08:57
A set of Python tools useful for benchmarking, benchmark selection, nuclear data validation, and nuclear data evaluation support called Faust is currently under development at Los Alamos National Laboratory. The goals and objectives for Faust are to:
Go to contribution page
- Provide input and output processing for different calculation codes
- Allow for exchanging results between different applications and... -
Dr John Bess (JFoster & Associates, LLC)27/07/2022, 11:00
The status of the two neutronics international benchmark projects sanctioned by the Organisation 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 Project (IRPhEP), was last directly discussed with the international nuclear data...
Go to contribution page -
Mr Takashi Kanda (Kindai University)27/07/2022, 11:24
A small modular reactor (SMR) employing calcium hydride (CaH2) as a moderator have attracted attention to the passive safety and economic efficiency. Some integral experiments should be carried out to validate nuclear data of CaH2, however, no integral experiment by reactor for the validation have been reported. As the first integral experiment by reactor, a series of...
Go to contribution page -
Dr Chikara Konno (Japan Atomic Energy Agency)27/07/2022, 11:36
For the JENDL development we analyzed the iron in-situ experiment at the DT neutron 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 investigate this issue.
The...
Go to contribution page -
Alexander Clark (LANL)27/07/2022, 11:48
\noindent Los Alamos National Laboratory\
Go to contribution page
P.O. Box 1663, MS A143\
Los Alamos, New Mexico 87545\
Email: \url{arclark@lanl.gov}\
LA-UR-21-29584\ \
Nuclear data are widely used by the international community for a variety of applications, including criticality safety, reactor performance, and material safeguards. Despite the breadth of use-cases, critical benchmarks are primarily used for... -
Peter Schillebeeckx (EC - JRC-Geel)
Characterisation of spent nuclear fuel (SNF) is required to ensure the safe operation of the different facilities involved in Spent Fuel management – for handling, storage, conditioning, reprocessing or final disposal – as well as for transport activities between those facilities. Several quantities are of importance: neutron and γ-ray emission rates and spectra, decay heat and the inventory...
Go to contribution page -
Raphaelle Ichou (IRSN)
Depletion codes such as VESTA 2.2 [1] are used to calculate the time evolution of a material subjected to radiation for a wide variety of applications in the fields of nuclear safety, radiation protection and environmental health safety. For these applications, experimental validation is paramount. VESTA 2.2, which allows coupling both MCNP6 [2] and/or MORET 5 [3] Monte Carlo codes to a...
Go to contribution page -
Dr Mitja Majerle (Nuclear Physics Institute of the CAS, Czechia)
The Nuclear Physics Institute of the Czech Academy of Sciences operates several fast neutron generators. The generators are based on the reaction of accelerated protons (U120M cyclotron, energy of protons up to 35 MeV) with the lithium and beryllium targets. The produced quasi-monoenergetic and continuous neutron spectra with energies up to 33 MeV have been well characterized.
Go to contribution page
The neutron... -
Anatoly Kochetkov (SCK-CEN)
The need for accurate knowledge of neutron data in materials as Pb and Bi has increased recently due to the Accelerator Driven System (ADS) and new generation of fast reactor designs with lead or lead-bismuth coolant. The Belgian Nuclear Research Centre (SCK CEN) develops the Multi-purpose hYbrid Research Reactor for High-tech Applications (MYRRHA) that will have a fast sub-critical core...
Go to contribution page -
Johannes Ekman (Uppsala University, Sweden)
A characterisation of spent nuclear fuel (SNF) is essential for a safe, secure, ecologic and economic handling, transport, interim storage and final disposal of SNF assemblies. Several quantities are of importance: neutron and γ-ray emission rates and spectra, decay heat and the inventory of fissile nuclides. These sources can only be obtained by theoretical calculations. Evidently, the...
Go to contribution page