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Journal Articles

Development of FRENDY nuclear data processing code; Generation capability of multi-group cross sections from ACE file

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.

JAEA Reports

JAEA Reports

One-, tow-, three-dimensional transport codes using multi-group double-differential form cross sections

Mori, Takamasa; Nakakawa, Masayuki; *

JAERI 1314, 151 Pages, 1988/11

JAERI-1314.pdf:4.5MB

no abstracts in English

JAEA Reports

ANISN-DD; One-dimensional Sn transport code using multi-group double-differential form cross sections

Mori, Takamasa; *; Nakakawa, Masayuki

JAERI-M 87-123, 55 Pages, 1987/08

JAERI-M-87-123.pdf:1.21MB

no abstracts in English

JAEA Reports

JAEA Reports

JSD 1000:Multi-Group Cross Section Sets for Shielding Materials

JAERI-M 84-038, 116 Pages, 1984/03

JAERI-M-84-038.pdf:3.34MB

no abstracts in English

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