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Hidaka, Akihide; Asaka, Hideaki; Ueno, Shingo*; Yoshino, T.*; Sugimoto, Jun
JAERI-Research 99-067, p.55 - 0, 1999/12
JAERI-Research-99-067.pdf:2.51MB
no abstracts in English
Sobajima, Makoto
IAEA-TECDOC-1002, p.27 - 36, 1998/03
no abstracts in English
Sobajima, Makoto
Nihon Genshiryoku Gakkai-Shi, 40(5), p.372 - 374, 1998/00
no abstracts in English
Yamano, N.; Maruyama, Yu; Moriyama, Kiyofumi; Sugimoto, Jun
NEA/CSNI/R(96)24, 0, p.1 - 49, 1996/00
no abstracts in English
Hidaka, Akihide; Ezzidi, A.*; Sugimoto, Jun
PSA 96: Int. Topical Meeting on Probabilistic Safety Assessment, 3, p.1548 - 1556, 1996/00
no abstracts in English
Yamano, N.; Maruyama, Yu; Moriyama, Kiyofumi; Kudo, Tamotsu; H.S.Park*; Sugimoto, Jun
Proc. of 11th KAIF/KNS Annual Conf., 0, p.827 - 838, 1996/00
no abstracts in English
Abe, Kiyoharu; Muramatsu, Ken
Transactions of the 13th Int. Conf. on Structural Mechanics in Reactor Technology (SMiRT),Vol. 4, 0, p.647 - 652, 1995/00
no abstracts in English
Sugimoto, Jun; *; Yamano, N.
Proc. of the Seminar on the Vapor Explosions in Nuclear Power Safety,Tateshina 1994, 0, p.33 - 66, 1994/00
no abstracts in English
Watanabe, Norio
JAERI-M 93-164, 155 Pages, 1993/09
no abstracts in English
Soda, Kunihisa; Hidaka, Akihide; Hashimoto, Kazuichiro
JAERI-M 92-061, 40 Pages, 1992/05
no abstracts in English
Soda, Kunihisa
Proc. of the Int. Conf. on Design and Safety of Advanced Nuclear Power Plants,Vol. 3, p.23.1-1 - 23.1-5, 1992/00
no abstracts in English
Hidaka, Akihide; Sugimoto, Jun; *; Soda, Kunihisa
JAERI-M 91-175, 65 Pages, 1991/10
no abstracts in English
Soda, Kunihisa
2nd Int. Conf. on Containment Design and Operation, 14 Pages, 1991/00
no abstracts in English
Ikegawa, Tomohiko*; Ishibashi, Ryo*; Sakamoto, Kan*; Yamashita, Shinichiro
no journal, ,
Zircaloy (Zry) is used in LWRs generally. When steam and Zry reacted under the high temperature environment, hydrogen and heat of reaction generated. Those have an influence on a presence of core damage at an accident. The effect of the accident tolerant fuel was quantitatively investigated in the study when the accident management (depressurization of RPV and water pouring by firefighting car) was carried out in the severe accident.
Suzuki, Minoru*; Sakai, Takaaki*; Takata, Takashi; Doda, Norihiro
no journal, ,
With an aim to establish a quantitative risk assessment of accident managements (AMs) for various external hazards, the plant dynamics analyses with Continuous Markov Chain Monte Carlo (CMMC) method were carried out to assess repeatedly occurred multi-failures by volcano ash in volcanic eruption event. AM repetition of the filter exchange to recover the cooling function of the air coolers (ACs) of auxiliary cooling system (ACS) were considered. The uncertainty of AM measure was set as a parameter. The results showed that extending the endurance time of ACS-AC filter was effective as AM measure against volcanic ash hazard.
Suzuki, Minoru*; Kawashima, Masato*; Sakai, Takaaki*; Doda, Norihiro; Tanaka, Masaaki
no journal, ,
With an aim to establish a quantitative risk assessment of accident managements (AMs) for various external hazards, the plant dynamics analyses with Continuous Markov Chain Monte Carlo (CMMC) method were carried out for AM in cases of the filter exchange to recover the cooling function of the air coolers from soot and smoke and the firefighting from ambient temperature rise in forest fire event. The results indicated that this method can use for evaluation of effectiveness of AM measures repeatedly performed against forest fire events with respect to time progress and the AM measures against rising ambient temperature is important for fast reactors using air-cooling system.
Koike, Akari*; Sakai, Takaaki*; Doda, Norihiro; Tanaka, Masaaki
no journal, ,
To evaluate the effect of the operator's recognition of the accident management (AM) necessity on plant safety, the operator's recognition of the AM necessity was modeled as a function of time-dependent success probability, and dynamic PRA analyses using the Continuous Markov chain Monte Carlo method (CMMC) were performed for a sodium-cooled fast reactor during abnormal snowfall event. The analysis results showed that AM was effective in delaying the core damage and that the recognition timing by the operator was an important factor in avoiding the core damage after the accident.