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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.
U, 
U and 
Pu by using results of in-pile measurements of effective delayed neutron fractionSakurai, Takeshi; Okajima, Shigeaki
Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 12 Pages, 2002/10
The cross section adjustment method was applied to total delayed neutron yields of U, U and Pu of the JENDL-3.2 file by using experimental results of effective delayed neutron fraction 
at six cores built in two fast critical facilities of the MASURCA and FCA and a thermal critical facility of the TCA to improve these yields. The adjustment was carried out on the yields given at several incident neutron energy points in the file. Furthermore, to validate these adjusted delayed neutron yields, analyses were performed for the experiments at ZPR fast critical facility. These adjusted yields brought a reduction of uncertainty of calculated and an improvement in agreement of between experiment and calculation.
U, U and Pu in JENDL-3.2 using benchmark experiments on effective delayed neutron fraction Sakurai, Takeshi; Okajima, Shigeaki
Journal of Nuclear Science and Technology, 39(1), p.19 - 30, 2002/01
Times Cited Count：6 Percentile：39.48(Nuclear Science & Technology)The cross section adjustment method was applied to total delayed neutron yields of U, U and Pu of the JENDL-3.2 file by using experimental results of effective delayed neutron fraction at six cores built in two fast critical facilities of the MASURCA and FCA and a thermal critical facility of the TCA to improve these yields. The adjustment was carried out on the yields given at several incident neutron energy points in the file. After the adjustment, the yield of U was almost uniformly decreased by about 3% below 7 MeV. The yield of Pu was increased by 2.6% and that of U was decreased by 0.9% at the thermal energy point, while the change of yield was less than 0.3% at the other energy points for these nuclides. By using these adjusted yields, the uncertainty of calculated was reduced and the agreement of between experiment and calculation was improved.
Fujimoto, Nozomu; Yamashita, Kiyonobu; Akino, Fujiyoshi
JAERI-Research 99-052, p.51 - 0, 1999/09
JAERI-Research-99-052.pdf:2.05MB
no abstracts in English
C at FCA, 3; Development of a cell code, PEACO-X, with ultra-fine group structureOkajima, Shigeaki; Oigawa, Hiroyuki; Mukaiyama, Takehiko
JAERI-M 92-185, 42 Pages, 1992/11
no abstracts in English
JAERI-M 6491, 19 Pages, 1976/03
no abstracts in English
Nuclear Science and Engineering, 55(3), p.349 - 351, 1974/03
Times Cited Count：1no abstracts in English
