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Tobita, Yoshiharu; Tagami, Hirotaka; Ishida, Shinya; Onoda, Yuichi; Sogabe, Joji; Okano, Yasushi
IAEA-TECDOC-2079, p.72 - 84, 2025/00
Since the fast reactor core is not in the maximum reactivity configuration, a hypothetical core disruptive accident could lead to the prompt criticality due to a change in the core material configuration, and the resulting energy generation has been one of the issues in fast reactor safety, and therefore appropriate measures are needed to mitigate and contain the effect of energy generated in the accident. In order to assess the effectiveness of these mitigative measures, a set of computer codes to analyze the event progressions and energy generation behavior in the ATWS of fast reactors have been developed, maintained, and improved under international collaboration in JAEA. Since the important physical phenomena, which govern the event progression, vary along with the progression of the accident, the whole accident process is divided into several phases in the analysis of accident, and dedicated analysis methods for each phase are provided to analyze the event progression in each phase. The organization and overview of these analysis methods are described in this paper. As a representative example of the validation approaches in applying these analysis methods to the reactor safety assessment in licensing procedure in Japan, the validation studies to confirm the applicability to reactor analysis of the SIMMER code for analyzing core material movement and reactor power, which is important to analyze the energy generation in the accident, are presented in the paper. The validation studies of the SIMMER code confirmed the applicability of SIMMER to the reactor analysis, while the critical phenomena that the effect of their uncertainty in the reactor analysis should be checked were also recognized.
Nakamura, Hideo
Proceedings of ANS International Conference on Best Estimate Plus Uncertainties Methods (BEPU 2018) (USB Flash Drive), 8 Pages, 2018/00
no abstracts in English
Nakamura, Hideo
Proceedings of Seminar on the Transfer of Competence, Knowledge and Experience gained through CSNI Activities in the Field of Thermal-Hydraulics (THICKET 2016) (CD-ROM), 29 Pages, 2016/06
no abstracts in English
Takamatsu, Kuniyoshi; Katanishi, Shoji; Nakagawa, Shigeaki; Kunitomi, Kazuhiko
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(1), p.76 - 87, 2004/03
The Gas Turbine High Temperature Reactor 300 (GTHTR300) composed of an inherent safe 600MWt reactor and a closed gas turbine power conversion system is a high efficient and economically competitive HTGR to be deployed in 2010s. To analyze the plant dynamics and the thermal hydraulics of the GTHTR300, a new analytical code (Conan-GTHTR) based on 'RELAP5/MOD3' has been developed and applied to heat transfer calculations of the High Temperature Engineering Test Reactor (HTTR) for its verification. The results proved that the new code was available for transient simulations in Higt Temperature Gas-Cooled Reactor systems.
Takeda, Takeshi; Tachibana, Yukio; Kunitomi, Kazuhiko; Itakura, Hirofumi*
JAERI-Data/Code 96-032, 147 Pages, 1996/11
JAERI-Data-Code-96-032.pdf:4.58MB
no abstracts in English
Araya, Fumimasa; Murao, Yoshio; Iwamura, Takamichi
Journal of Nuclear Science and Technology, 32(10), p.1039 - 1046, 1995/10
Times Cited Count：5 Percentile：48.96(Nuclear Science & Technology)no abstracts in English
Araya, Fumimasa; Murao, Yoshio
Journal of Nuclear Science and Technology, 32(4), p.339 - 350, 1995/04
Times Cited Count：3 Percentile：36.32(Nuclear Science & Technology)no abstracts in English
Onuki, Akira; ; Murao, Yoshio
JAERI-M 94-026, 60 Pages, 1994/03
no abstracts in English
W.Nixon*; P.J.Cooper*; C.M.Bone*; S.Acharya*; U.Baeverstam*; J.Ehrhardt*; I.Hasemann*; Steinhauer, C.*; E.G.Diaz*; J.C.Glynn*; et al.
EUR-15109, 0, 338 Pages, 1994/00
no abstracts in English
Homma, Toshimitsu;
JAERI-M 93-207, 36 Pages, 1993/10
no abstracts in English
Araya, Fumimasa; Iwamura, Takamichi; Okubo, Tsutomu; ; Murao, Yoshio
Nihon Genshiryoku Gakkai-Shi, 34(8), p.776 - 786, 1992/08
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
Iwamura, Takamichi; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio
Subchannel Analysis in Nuclear Reactors, p.281 - 301, 1992/00
no abstracts in English
; Kukita, Yutaka; Anoda, Yoshinari; Nakamura, Hideo; Tasaka, Kanji
Journal of Nuclear Science and Technology, 28(1), p.33 - 44, 1991/01
no abstracts in English
Iwamura, Takamichi; Okubo, Tsutomu; Murao, Yoshio; ;
Journal of Nuclear Science and Technology, 28(1), p.45 - 58, 1991/01
no abstracts in English
1.0m, P/D: 1.1261.2, number of rods: 47Iwamura, Takamichi; Okubo, Tsutomu; ; ; Murao, Yoshio
JAERI-M 90-044, 158 Pages, 1990/03
no abstracts in English
Iwamura, Takamichi; ; Okubo, Tsutomu; ; Murao, Yoshio
JAERI-M 90-043, 70 Pages, 1990/03
no abstracts in English
Iwamura, Takamichi; Okubo, Tsutomu; Murao, Yoshio;
Thermal Hydraulics of Advanced Nuclear Reactors, p.31 - 38, 1990/00
no abstracts in English
Tasaka, Kanji; Koizumi, Yasuo; Suzuki, Mitsuhiro; Anoda, Yoshinari; Kukita, Yutaka; Kumamaru, Hiroshige; Nakamura, Hideo; Yonomoto, Taisuke; Kawaji, Masahiro; Murata, Hideo
JAERI 1307, 379 Pages, 1987/11
no abstracts in English
Koizumi, Yasuo; ; ; Tasaka, Kanji
Nucl.Eng.Des., 99, p.157 - 165, 1987/00
Times Cited Count：12 Percentile：74.55(Nuclear Science & Technology)no abstracts in English
Nomura, Yasushi; Katakura, Junichi; Naito, Yoshitaka; Komuro, Yuichi; Okuno, Hiroshi
JAERI 1303, 152 Pages, 1986/11
no abstracts in English
