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Fujita, Tatsuya; Yamamoto, Akio*
Journal of Nuclear Science and Technology, 18 Pages, 2024/00
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)This study newly established a direct coupling code system consisting of the nuclear data processing code FRENDY version 2, and the three-dimensional heterogeneous transport code GENESIS (FRENDY-V2/GENESIS) for easy implementation of the random-sampling-based uncertainty quantification considering the implicit effect due to nuclear cross-section (XS) perturbations. The multi-group macroscopic XSs prepared for GENESIS were generated by FRENDY version 2, where the Dancoff factor was calculated by the neutron current method. Then the background XSs were evaluated based on the Carlvik two-term rational approximation. The infinite multiplication factor (k-infinity) and the fission reaction rate distribution in UO
and MOX lattice geometries were compared with MVP3 to verify the calculation accuracy of FRENDY-V2/GENESIS. The sensitivity analyses on the discretization conditions such as the ray tracing of the method of characteristics were also carried out. Through several comparisons between FRENDY-V2/GENESIS and MVP3, FRENDY-V2/GENESIS with the SHEM 361-group structure calculates the k-infinity within approximately 50 pcm and the fission reaction rate distribution within approximately 0.1% by the root mean square, respectively. Consequently, the applicability of FRENDY-V2/GENESIS was verified, and FRENDY-V2/GENESIS can be used to discuss the implicit effect due to multi-group XS perturbations.
Yamamoto, Akio*; Endo, Tomohiro*; Tada, Kenichi
Transactions of the American Nuclear Society, 122(1), p.714 - 717, 2020/06
A generation capability of multi-group cross sections from point-wise cross sections in ACE files is being developed as a function of the nuclear data processing code FRENDY. This presentation describes features of this function and comparison of the processing results between this function and GROUPR module in NJOY.
Nakagawa, Masayuki; Mori, Takamasa;
JAERI-M 90-097, 95 Pages, 1990/06
no abstracts in English
Mori, Takamasa; Nakagawa, Masayuki;
JAERI 1314, 151 Pages, 1988/11
no abstracts in English
Mori, Takamasa; ; Nakagawa, Masayuki
JAERI-M 87-123, 55 Pages, 1987/08
no abstracts in English
JAERI-M 84-053, 301 Pages, 1984/03
no abstracts in English
JAERI-M 84-038, 116 Pages, 1984/03
no abstracts in English
Tada, Kenichi
no journal, ,
This presentation explains the recent development work of the nuclear data processing code FRENDY. This presentation shows the major new functions in FRENDY version 2 which was released in Jan. 2022 and the overview of the new functions implemented in the revised version which was released in Nov. 2022.
