Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0

The WIMSD-5B transport code is a deterministic tool for nuclear reactor core design and fuel management. It can efficiently handle pin-cell and supercell models and calculate homogenized cross sections, which are essential for reactor physics calculations. It is used by core design packages such as the CORD-2 package, developed at the Jožef Stefan Institute, and SEANAP developed by Universidad Politécnica de Madrid (UPM). The WLUP update project https://www-nds.iaea.org/wimsd demonstrated the way to update the WIMS-D libraries with different evaluated nuclear data libraries, including ENDF libraries up to version ENDF/B-VII.1. Using an updated version of the procedure, a new WIMS-D library based on the ENDF/B-VIII.0 data was developed to improve the accuracy of core design calculations. Several improvements to the library were made and the effects of each individual improvement was demonstrated using a 3×3 supercell benchmark model that is representative of a typical pressurized water reactor. Finally, the performance of the library over a diverse set of neutron transport problems was tested for, to ensure no regressions were introduced. • New nuclear data library for deterministic calculations. • Library validation with WIMS-D benchmark suite and pincell burnup benchmark. • Revision of decay and burnup chains in the nuclear data library. • Analysis of the impact of decay chains on burnup-dependent isotope concentrations.

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Publication Details

Journal
Annals of Nuclear Energy
Published
2024-10-23
DOI
https://doi.org/10.1016/j.anucene.2024.110989
Citations
1
Primary Topic
Nuclear Physics and Applications
Type
article
Field-Weighted Citation Impact
0.61
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article

Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0

Jan Malec, Andrej Trkov, Oscar Cabellos, Marjan Kromar
1 citations
Annals of Nuclear Energy
Nuclear Physics and Applications
0.61
article

Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0

Jan Malec, Andrej Trkov, Oscar Cabellos, Marjan Kromar
article en
1 citations

Abstract

The WIMSD-5B transport code is a deterministic tool for nuclear reactor core design and fuel management. It can efficiently handle pin-cell and supercell models and calculate homogenized cross sections, which are essential for reactor physics calculations. It is used by core design packages such as the CORD-2 package, developed at the Jožef Stefan Institute, and SEANAP developed by Universidad Politécnica de Madrid (UPM). The WLUP update project https://www-nds.iaea.org/wimsd demonstrated the way to update the WIMS-D libraries with different evaluated nuclear data libraries, including ENDF libraries up to version ENDF/B-VII.1. Using an updated version of the procedure, a new WIMS-D library based on the ENDF/B-VIII.0 data was developed to improve the accuracy of core design calculations. Several improvements to the library were made and the effects of each individual improvement was demonstrated using a 3×3 supercell benchmark model that is representative of a typical pressurized water reactor. Finally, the performance of the library over a diverse set of neutron transport problems was tested for, to ensure no regressions were introduced. • New nuclear data library for deterministic calculations. • Library validation with WIMS-D benchmark suite and pincell burnup benchmark. • Revision of decay and burnup chains in the nuclear data library. • Analysis of the impact of decay chains on burnup-dependent isotope concentrations.

Annals of Nuclear EnergyVol. 211
University of Ljubljana (SI), Jožef Stefan Institute (SI), Universidad Politécnica de Madrid (ES)
Openalex Percentile: Top 30%
Nuclear Physics and Applications
0.61
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Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0 — Jan Malec, Andrej Trkov, et al. · Annals of Nuclear Energy (2024) | TGRS Research Map | TGRS