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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:15.7(Nuclear Science & Technology)Fujimoto, Nozomu; Nojiri, Naoki; Yamashita, Kiyonobu*
Nuclear Engineering and Design, 233(1-3), p.155 - 162, 2004/10
Times Cited Count:2 Percentile:17.16(Nuclear Science & Technology)The HTTR uses low-enriched uranium fuel with burnable poison rod. For validation of the nuclear design code system for the HTTR, a critical assembly of VHTRC had been constructed. The calculation uncertainties of effective multiplication factor, neutron flux distribution, burnable poison reactivity worth, and control rod worth, temperature coefficients were evaluated. Calculation accuracy of a Monte Carlo code is also evaluated.
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:61.44(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
Komuro, Yuichi; Suzaki, Takenori; *; Sakurai, Kiyoshi; Horiki, Oichiro*
JAERI-Research 97-088, 19 Pages, 1997/11
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:47.9(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:0.01(Nuclear Science & Technology)no abstracts in English
Komuro, Yuichi; ; Sakurai, Kiyoshi; Yamamoto, Toshihiro; Suzaki, Takenori; Horiki, Oichiro*; Nitta, Kazuo*
PHYSOR 96: Int. Conf. on the Physics of Reactors, 1, p.L120 - L129, 1996/00
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:0.01(Nuclear Science & Technology)no abstracts in English
Obara, Toru*; Nakajima, Ken; *; Sekimoto, Hiroshi*; Suzaki, Takenori
JAERI-M 94-004, 40 Pages, 1994/02
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
JAERI-M 87-063, 133 Pages, 1987/04
no abstracts in English
; ; ; *
Journal of Nuclear Science and Technology, 22(5), p.358 - 370, 1985/05
Times Cited Count:13 Percentile:81.92(Nuclear Science & Technology)no abstracts in English
; ; ; ;
JAERI-M 85-047, 81 Pages, 1985/04
no abstracts in English