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.

Generation and verification of the multigroup constants library MGCL-J3 for nuclear criticality calculations

Komuro, Yuichi; Okuno, Hiroshi; Naito, Yoshitaka; *; Nagai, Masakatsu*; *; *; *

JAERI-M 93-190, 94 Pages, 1993/10

JAERI-M-93-190.pdf:1.86MB

no abstracts in English

Measurement of Doppler effect up to 2000C at FCA, 3; Development of a cell code, PEACO-X, with ultra-fine group structure

Okajima, Shigeaki; Oigawa, Hiroyuki; Mukaiyama, Takehiko

JAERI-M 92-185, 42 Pages, 1992/11

JAERI-M-92-185.pdf:1.02MB

no abstracts in English

MAIL 3.0; A Computer program calculating cross sections for SIMCRI, ANISN, KENO-IV, MULTI-KENO and MULTI-KENO-II

Komuro, Yuichi; Okuno, Hiroshi; Naito, Yoshitaka; *; *; *

JAERI-M 90-126, 125 Pages, 1990/08

JAERI-M-90-126.pdf:2.18MB

no abstracts in English

Spectrum-averaged one-group cross sections of actnides based on JENDL-3

Masukawa, Fumihiro; Nakagawa, Tsuneo; Iijima, Shungo*

Journal of Nuclear Science and Technology, 27(6), p.572 - 576, 1990/06

https://doi.org/10.3327/jnst.27.572

no abstracts in English

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

Evaluation of neutron nuclear data of natural nickel and its isotopes

Kikuchi, Yasuyuki; *

Journal of Nuclear Science and Technology, 22(5), p.337 - 357, 1985/00

https://doi.org/10.3327/jnst.22.337

no abstracts in English

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

ORIGEN-JR: A Computer Code for Calculating Radiation Sources and Analyzing Nuclide Transmutations

; ;

JAERI-M 8229, 62 Pages, 1979/05

JAERI-M-8229.pdf:1.51MB

no abstracts in English

ESELEM 4: A Code for calculating fine neutron spectrum and multi-group cross sections in plate lattice

Nakagawa, Masayuki; Katsuragi, Satoru; *

JAERI 1245, 46 Pages, 1976/07

JAERI-1245.pdf:2.29MB

no abstracts in English