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Yanagisawa, Hiroshi; Umeda, Miki; Motome, Yuiko; Murao, Hiroyuki
Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet), 10 Pages, 2023/10
The benchmark analyses on the TRIGA reactor of the IEU-COMP-THERM-013 (ICT-013) in the ICSBEP handbook using the MVP version 3 code were carried out with the Japanese, US and European nuclear data libraries, including JENDL-5. The analyses on effective neutron multiplication factors (k's) were also performed for another TRIGA reactor defined in the ICT-003 as well as the ICT-013. As a result, it is confirmed that the calculated k
's vary in the range of 0.8% with the libraries. The results also suggest that there might be unknown bias in the ICT-013 for the calculated k
's. For the analyses on the control rod worths of the ICT-013, it is confirmed that differences in the worths among the libraries become smaller than those in k
's. Most of the errors involved in k
's are considered to be cancelled in the calculation of the worths since the worths are obtained by subtraction of the reciprocals of two sorts of k
's. The differences in the worths by between the benchmark and alternative methods defined in the ICT-013 were tried to be examined from the aspect of the differences in horizontal flux distributions by between those methods. It is confirmed that the differences in the worths for two shim control rods, which are fully withdrawn at a delayed critical state, are well understood by that attempt, but on the other hand the differences are not sufficiently explained for a regulating control rod, which is partially inserted to attain delayed criticality.
Yanagisawa, Hiroshi; Umeda, Miki; Motome, Yuiko; Murao, Hiroyuki
JAEA-Technology 2022-030, 80 Pages, 2023/02
Nuclear criticality benchmark analyses were carried out for TRIGA-type reactor systems in which uranium-zirconium hydride fuel rods are loaded by using the continuous-energy Monte Carlo code MVP with the evaluated nuclear data library JENDL-5. The analyses cover two sorts of benchmark data, the IEU-COMP-THERM-003 and IEU-COMP-THERM-013 in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook, and effective neutron multiplication factors, reactivity worths for control rods etc. were calculated by JENDL-5 in comparison with those by the previous version of JENDL. As the results, it was confirmed that the effective neutron multiplication factors obtained by JENDL-5 were 0.4 to 0.6% greater than those by JENDL-4.0, and that there were no significant differences in the calculated reactivity worths by between JENDL-5 and JENDL-4.0. Those results are considered to be helpful for the confirmation of calculation accuracy in the analyses on NSRR control rod worths, which are planned in the future.
Takino, Kazuo; Sugino, Kazuteru; Oki, Shigeo
Annals of Nuclear Energy, 162, p.108454_1 - 108454_7, 2021/11
Times Cited Count:1 Percentile:11.39(Nuclear Science & Technology)Nojiri, Naoki; Shimakawa, Satoshi; Fujimoto, Nozomu; Goto, Minoru
Nuclear Engineering and Design, 233(1-3), p.283 - 290, 2004/10
Times Cited Count:12 Percentile:60.80(Nuclear Science & Technology)This paper describes the results of core physics test in start-up and power-up of the HTTR. The tests were conducted in order to ensure performance and safety of the high temperature gas cooled reactor, and was carried out to measure the critical approach, the excess reactivity, the shutdown margin, the control rod worth, the reactivity coefficient, the neutron flux distribution and the power distribution. The expected core performance and the required reactor safety characteristics were verified from the results of measurements and calculations.
Fujimoto, Nozomu; Nojiri, Naoki; Nakano, Masaaki*; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu
JAERI-Tech 98-021, 66 Pages, 1998/06
no abstracts in English
Akino, Fujiyoshi; Yamane, Tsuyoshi
Nihon Genshiryoku Gakkai-Shi, 40(4), p.262 - 264, 1998/00
no abstracts in English
Ando, Masaki; ; Nishina, Kojiro*;
Journal of Nuclear Science and Technology, 34(5), p.445 - 453, 1997/05
Times Cited Count:6 Percentile:47.54(Nuclear Science & Technology)no abstracts in English
Akino, Fujiyoshi; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko
Journal of Nuclear Science and Technology, 34(2), p.185 - 192, 1997/02
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)no abstracts in English
Yamashita, Kiyonobu; Murata, Isao; Shindo, Ryuichi; ; H.Werner*
Journal of Nuclear Science and Technology, 31(5), p.470 - 478, 1994/05
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)no abstracts in English
Nagaoka, Yoshiharu; Saito, Minoru;
Transactions of the American Nuclear Society, 66, p.454 - 455, 1992/11
no abstracts in English
; Miyoshi, Yoshinori; ; ; ;
Proc. of the Int. Conf. on Nuclear Power Plant Operations; Ready for 2000, p.435 - 441, 1992/00
no abstracts in English
Oigawa, Hiroyuki; Osugi, Toshitaka; Ono, Akio; ;
JAERI-M 91-096, 39 Pages, 1991/06
no abstracts in English
Okajima, Shigeaki; Osugi, Toshitaka; Sakurai, Takeshi;
Journal of Nuclear Science and Technology, 27(10), p.950 - 959, 1990/10
no abstracts in English
Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao
The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.350 - 358, 1990/09
no abstracts in English
Arigane, Kenji
JAERI-M 87-063, 133 Pages, 1987/04
no abstracts in English
; ; ; ;
JAERI-M 85-047, 81 Pages, 1985/04
no abstracts in English
; ; ;
JAERI-M 9911, 32 Pages, 1982/02
no abstracts in English
Omura, Hiroshi*
JAERI-M 9433, 109 Pages, 1981/04
no abstracts in English
; ; ;
JAERI-M 8553, 52 Pages, 1979/11
no abstracts in English
; ; ; ; ;
JAERI-M 8293, 101 Pages, 1979/06
no abstracts in English