Development of nuclear data processing code FRENDY version 2

Nuclear data processing is important to connect evaluated nuclear data libraries and radiation transport codes. The nuclear data processing code FRENDY version 1 was released in 2019 to generate ACE-formatted cross section files with simple input data. After we released FRENDY version 1, many functi...

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Bibliographic Details
Published in:Journal of nuclear science and technology 2024-06, Vol.61 (6), p.830-839
Main Authors: Tada, Kenichi, Yamamoto, Akio, Kunieda, Satoshi, Konno, Chikara, Kondo, Ryoichi, Endo, Tomohiro, Chiba, Go, Ono, Michitaka, Tojo, Masayuki
Format: Article
Language:English
Subjects:
Cross-sections
Data processing
Nuclides
Radiation transport
Resonance
Statistical analysis
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Summary:Nuclear data processing is important to connect evaluated nuclear data libraries and radiation transport codes. The nuclear data processing code FRENDY version 1 was released in 2019 to generate ACE-formatted cross section files with simple input data. After we released FRENDY version 1, many functions were developed, e.g. neutron multi-group cross section generation, explicit consideration of the resonance interference effect among different nuclides in a material, adaptive setting of the background cross sections, consideration of the resonance upscattering, ACE file perturbation, statistical uncertainty quantification of probability table, and modification of ENDF-6-formatted file. FRENDY version 2 was released including these new functions. It generates GENDF- and MATXS-formatted neutron multi-group cross section files from an ACE-formatted cross section file or an evaluated nuclear data file. This paper explains the features of the new functions implemented in FRENDY version 2 and the verification of the neutron multigroup cross section generation function of this code.
ISSN:0022-3131
1881-1248
DOI:10.1080/00223131.2023.2278600