| Autor: |
Tada, Kenichi, Yamamoto, Akio, Kunieda, Satoshi, Konno, Chikara, Kondo, Ryoichi, Endo, Tomohiro, Chiba, Go, Ono, Michitaka, Tojo, Masayuki |
| Zdroj: |
Journal of Nuclear Science & Technology; Jun2024, Vol. 61 Issue 6, p830-839, 10p |
| Abstrakt: |
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. [ABSTRACT FROM AUTHOR] |
| Databáze: |
Supplemental Index |
| Externí odkaz: |
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