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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; Iwamoto, Osamu
Proceedings of 2019 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC 2019), Vol.2, p.1622 - 1624, 2020/08
Times Cited Count：0 Percentile：0.08(Nuclear Science & Technology)JAEA has published the evaluated nuclear data library JENDL to improve the prediction accuracy of nuclear calculations. JENDL is now one of the most famous evaluated nuclear data libraries in the world. This presentation explains the recent activity of the JENDL project and overview of the next version of general-purpose file JENDL-5. Nuclear calculation codes cannot treat the evaluated nuclear data library. This presentation also explains the nuclear data processing system FRENDY which is used to generate cross section library for a nuclear calculation code.
Kondo, Ryoichi*; Endo, Tomohiro*; Yamamoto, Akio*; Tada, Kenichi
Proceedings of International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering (M&C 2019) (CD-ROM), p.1493 - 1502, 2019/00
A perturbation capability of ACE formatted cross section files was developed using the modules of FRENDY. Uncertainty quantification using MCNP was carried out for the Godiva critical experiment by the RS method. We verified the results of the RS method by comparing with those obtained by the conventional sensitivity analyses. Moreover, uncertainty reduction using the bias factor method with the RS technique was applied to kinetic parameter, i.e., neutron generation time.
Tada, Kenichi
no journal, ,
The nuclear data processing is very important process to connect the evaluated nuclear data file and nuclear transport calculation code. Because the nuclear data processing is carried out only when new or modified nuclear data file were released, it is difficult to cultivate the specialist of the nuclear data processing. To enhance understanding of the evaluated nuclear data file and nuclear data processing, this lecture explains the overview of them.
Fujita, Tatsuya
no journal, ,
Based on publicly available information, recent discussions on the nuclear regulation and future outlook are presented. In addition, the following issues are raised for motivating the advancement of domestic nuclear data libraries. (1) Is there a formal documents including useful information and data for helping licensees holding their application accountable?, (2) Is there extensive support for nuclear constant libraries?, (3) What would be beneficial from verification and validation, and quality assurance perspective for licensess to adopt a new nuclear data library?, (4) What nuclear data of nuclides/reactions will we be working on? (What are the needs of the licensees?), (5) What future efforts are needed to quantify uncertainties caused by nuclear data libraries?
