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Tada, Kenichi; Yamamoto, Akio*; Kunieda, Satoshi; Konno, Chikara; Kondo, Ryoichi; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*
Journal of Nuclear Science and Technology, 10 Pages, 2023/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Nuclear data processing code 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, consideration of the resonance upscattering, ACE file perturbation, 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.
Tada, Kenichi; Yamamoto, Akio*; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*
Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022) (Internet), 10 Pages, 2022/05
Nuclear data processing is an important interface between an evaluated nuclear data library and nuclear transport calculation codes. JAEA has developed a new nuclear data processing code FRENDY from 2013. FRENDY version 1 generates ACE files which are used for the continuous-energy Monte Carlo codes including PHITS, Serpent, and MCNP; it was released as an open-source software under the 2-clause BSD license in 2019. After FRENDY version 1 was released, many functions are developed: the multi-group neutron cross-section library generation, the statistical uncertainty quantification for the probability tables for unresolved resonance cross-section, the perturbation of the ACE file, and the modification of the ENDF-6 formatted nuclear data file, etc. We released FRENDY version 2 including these functions. This presentation explains the overview of FRENDY and features of the new functions implemented in FRENDY version 2.
Ogata, Atsushi*; Okamoto, Hiromi*; Kusano, Kanya*; Endo, Ichita*; Nishida, Yasushi*; Sakae, Takeji*; Arai, Masatoshi*; Nakanishi, Hiroshi*; Kondo, Kiminori*
JAERI-Tech 2002-007, 28 Pages, 2002/03
JAERI-Tech-2002-007.pdf:1.34MB
no abstracts in English
Tada, Kenichi; Yamamoto, Akio*; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*
no journal, ,
FRENDY (From Evaluated Nuclear Data library to any application) is a nuclear data processing code for the evaluated nuclear data libraries JENDL, ENDF/B, JEFF, TENDL, and so on. The first version of FRENDY was released in 2019 as an open-source software under the 2-clause BSD license. FRENDY Ver. 1 generates ACE files which is used for the continuous energy Monte Carlo codes such as PHITS, Serpent, and MCNP. Many new modules, e.g., the multi-group neutron cross-section generation from the ACE file, are implemented in FRENDY Ver. 2. This presentation explains the characteristics of FRENDY and new capabilities implemented in FRENDY Ver. 2.
Tada, Kenichi; Yamamoto, Akio*; Endo, Tomohiro*; Chiba, Go*; Ono, Michitaka*; Tojo, Masayuki*
no journal, ,
JAEA released the nuclear data processing code FRENDY version 2 in January 2022. This presentation explains the overview of new functions implemented in FRENDY version 2, e.g., multi-group cross section generation, uncertainty quantification for probability tables, perturbation of ACE file, and modification of evaluated nuclear data file.
Po-gross alpha countsYamada, Ryohei; Hashimoto, Hiroki*; Tamakuma, Yuki*; Omori, Yasutaka*; Hosoda, Masahiro*; Akata, Naofumi*; Uchiyama, Rei; Nakada, Akira; Endo, Michitaka*; Imajo, Yusuke*; et al.
no journal, ,
no abstracts in English
