Published April 2023 | Version v1
Journal article Metadata-only

JENDL-5 benchmarking for fission reactor applications

Creators

  • 1. Japan Atomic Energy Agency, Nuclear Science and Engineering Center, Tokai, Ibaraki (Japan)
  • 2. Japan Atomic Energy Agency, Fast Reactor Cycle System Research and Development Center, Oarai, Ibaraki (Japan)
  • 3. Japan Atomic Energy Agency, HTGR Research and Development Center, Oarai, Ibaraki (Japan)

Description

The new version of the Japanese evaluated nuclear data library, JENDL-5, was released in December 2021. This paper demonstrates the validation of JENDL-5 for fission reactor applications. Benchmark calculations are performed with the continuous-energy Monte Carlo codes MVP3 and MCNP6.2 and the deterministic code system MARBLE. The benchmark calculation results indicate that the performance of JENDL-5 for fission reactor applications is better than that of the former library JENDL-4.0. (author)

Availability note (English)

Available from DOI: https://doi.org/10.1080/00223131.2023.2197439

Additional details

Identifiers

DOI
10.1080/00223131.2023.2197439;

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo) (Online)
Journal Volume
61
Journal Issue
1
Journal Page Range
p. 2-22
ISSN
1881-1248

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
56002752
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CRITICALITY; ENRICHED URANIUM; FISSILE MATERIALS; M CODES; MONTE CARLO METHOD; NEUTRON TRANSPORT THEORY; NUCLEAR DATA COLLECTIONS; POST-IRRADIATION EXAMINATION; REACTIVITY; REACTOR CORES; SENSITIVITY ANALYSIS
Descriptors DEC
ACTINIDES; CALCULATION METHODS; COMPUTER CODES; ELEMENTS; FISSIONABLE MATERIALS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; REACTOR COMPONENTS; TRANSPORT THEORY; URANIUM

Optional Information

Notes
63 refs., 25 figs., 8 tabs.