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Wu, P.*; Murai, Naoki; Li, T.*; Kajimoto, Ryoichi; Nakamura, Mitsutaka; Kofu, Maiko; Nakajima, Kenji; Xia, K.*; Peng, K.*; Zhang, Y.*; et al.
New Journal of Physics (Internet), 25(1), p.013032_1 - 013032_11, 2023/01
Times Cited Count：0 Percentile：0(Physics, Multidisciplinary)Okumura, Keisuke
JAEA-Data/Code 2015-015, 162 Pages, 2015/10
JAEA-Data-Code-2015-015.pdf:3.99MB
JAEA-Data-Code-2015-015-appendix(CD-ROM).zip:3.38MB
MOSRA-SRAC is a lattice calculation module of the Modular code System for nuclear Reactor Analyses (MOSRA). This module performs the neutron transport calculation for various types of fuel elements including existing light water reactors, research reactors, etc. based on the collision probability method with a set of the 200-group cross-sections generated from the Japanese Evaluated Nuclear Data Library JENDL-4.0. It has also a function of the isotope generation and depletion calculation for up to 234 nuclides in each fuel material in the lattice. In these ways, MOSRA-SRAC prepares the burn-up dependent effective microscopic and macroscopic cross-section data to be used in core calculations.
*; ; Yokokawa, Mitsuo
JAERI-Data/Code 96-013, 25 Pages, 1996/03
JAERI-Data-Code-96-013.pdf:1.04MB
no abstracts in English
latticesNakajima, Ken;
Nuclear Technology, 113, p.375 - 379, 1996/03
Times Cited Count：5 Percentile：45.07(Nuclear Science & Technology)no abstracts in English
Annals of Nuclear Energy, 18(12), p.705 - 722, 1991/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
C-J.Jeong*; Okumura, Keisuke; ; Tanaka, Kenichi*
Journal of Nuclear Science and Technology, 27(6), p.515 - 523, 1990/06
no abstracts in English
; Iijima, Tsutomu
Journal of Nuclear Science and Technology, 15(8), p.553 - 567, 1978/08
Times Cited Count：0no abstracts in English
