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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.
Nojiri, Naoki; Fujimoto, Nozomu; Mori, Tomoaki; Obata, Hiroyuki*
JAERI-Data/Code 2004-012, 65 Pages, 2004/10
JAERI-Data-Code-2004-012.pdf:7.77MB
DELIGHT code is a fuel cell burnup analysis code which can produce the group constants necessary for High Temperature Gas-cooled Reactors (HTGR) core analyses. Collision probability method is used to the lattice calculation. The lattice calculation model is a cylinder type fuel or a ball type fuel of the HTGR. This code characterizes the burnup calculation considering the double heterogeneity caused by coated fuel particles of the HTGR fuel. DELIGHT code has updated its nuclear data library to the latest JENDL-3.3 data, and included new burnup chain models in order to calculate high burnup HTGR cores. The material regions of the periphery burnable poisons (BPs) were divided into details in order to improve calculation accuracy of the BP lattice calculation. This report presents the revised points of the DELIGHT-8 and can be used as user's manual.
U Doppler Effect using various samples in FCA XVII-1Ando, Masaki; Okajima, Shigeaki; Oigawa, Hiroyuki
JAERI-Research 2001-017, 20 Pages, 2001/03
JAERI-Research-2001-017.pdf:0.82MB
U Doppler effect measurements were carried out using 6 uranium samples with various composition or diameter varying self-shielding factors of U. Calculation accuracy of the standard analysis method for fast reactor cores at FCA was investigated.The Doppler effect were measured by the sample-heated and reactivity worth measurement method up to 800 degree in the FCA XVII-1 assembly, which simulated Na-cooled MOX fueled FBR. In the analysis, the Doppler effect was calculated using the effective cross sections obtained by the PEACO-X code. The calculated values based on the diffusion theory agreed well with the experiment for the U-metal and UO
samples. The calculation underestimated the experiment from 10% to 30% for the UO samples containing BeO. This underestimation was improved by the use of the transport calculation. The calculation, however, underestimated about 20% for the sample whose background cross section is greater than 300 barns.
Kugo, Teruhiko; Kaneko, Kunio*
Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, 2, p.2113 - 2122, 1999/09
no abstracts in English
U at FCA, II; Reaction rate measurement up to 2000
C with a foil heated by laser exposureOkajima, Shigeaki; Oigawa, Hiroyuki; Ando, Masaki; Mukaiyama, Takehiko
Journal of Nuclear Science and Technology, 34(1), p.13 - 20, 1997/01
Times Cited Count：2 Percentile：23.05(Nuclear Science & Technology)no abstracts in English
U at FCA, I; Reactivity worth measurement with a small heated sample up to 1500COkajima, Shigeaki; Oigawa, Hiroyuki; Mukaiyama, Takehiko; Ando, Masaki
Journal of Nuclear Science and Technology, 33(3), p.202 - 210, 1996/03
Times Cited Count：3 Percentile：32.66(Nuclear Science & Technology)no abstracts in English
C in the fast critical facility FCAOkajima, Shigeaki; Oigawa, Hiroyuki; Ando, Masaki; Mukaiyama, Takehiko
Proc. of 9th Int. Symp. on Reactor Dosimetry, 0, p.172 - 179, 1996/00
no abstracts in English
Okajima, Shigeaki; Oigawa, Hiroyuki; Mukaiyama, Takehiko
Journal of Nuclear Science and Technology, 31(10), p.1097 - 1104, 1994/10
Times Cited Count：7 Percentile：56.56(Nuclear Science & Technology)no abstracts in English
Okuno, Hiroshi; Naito, Yoshitaka; *
Journal of Nuclear Science and Technology, 31(9), p.986 - 995, 1994/09
Times Cited Count：2 Percentile：28.05(Nuclear Science & Technology)no abstracts in English
B.P.Kochurov*
JAERI-Review 94-002, 161 Pages, 1994/08
JAERI-Review-94-002.pdf:4.27MB
no abstracts in English
Naito, Yoshitaka; Okuno, Hiroshi; *
JAERI-M 93-180, 66 Pages, 1993/09
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
-fuel grain size on reactivity; Study by ultra-fine energy group calculations using the computer codes based on the collision probability methodOkuno, Hiroshi; *
JAERI-M 91-107, 49 Pages, 1991/08
no abstracts in English
Shindo, Ryuichi; Yamashita, Kiyonobu; Murata, Isao
JAERI-M 90-048, 225 Pages, 1990/03
no abstracts in English
; Akino, Fujiyoshi; ;
Journal of Nuclear Science and Technology, 24(6), p.431 - 441, 1987/06
Times Cited Count：2 Percentile：29.75(Nuclear Science & Technology)no abstracts in English
;
JAERI-M 85-163, 78 Pages, 1985/10
no abstracts in English
JAERI-M 85-034, 206 Pages, 1985/03
no abstracts in English
; *
Journal of Nuclear Science and Technology, 22(10), p.853 - 856, 1985/00
Times Cited Count：2 Percentile：40.2(Nuclear Science & Technology)no abstracts in English
; ; *
Journal of Nuclear Science and Technology, 22(1), p.16 - 27, 1985/00
Times Cited Count：11 Percentile：78.53(Nuclear Science & Technology)no abstracts in English
Nakagawa, Masayuki;
JAERI 1294, 82 Pages, 1984/12
no abstracts in English
