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

https://doi.org/10.13182/T122-32047

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.

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

Graphs of Neutron Cross Sections in JSD 1000 for Radiation Shielding Safety Analysis

JAERI-M 84-053, 301 Pages, 1984/03

JAERI-M-84-053.pdf:6.05MB

no abstracts in English

Recent development of FRENDY

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.