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Maruyama, Yu; Yamano, Norihiro; Kudo, Tamotsu; Moriyama, Kiyofumi; Sugimoto, Jun
JAERI-memo 08-127, p.269 - 275, 1996/06
no abstracts in English
Maruyama, Yu; Yamano, N.; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Sugimoto, Jun
Proc. of Int. Topical Meeting on Probabilistic Safety Assessment (PSA96), 3, p.1367 - 1374, 1996/00
no abstracts in English
Ishigami, Tsutomu
Journal of Nuclear Science and Technology, 32(7), p.691 - 701, 1995/07
Times Cited Count：2 Percentile：28.65(Nuclear Science & Technology)no abstracts in English
Maruyama, Yu; Yamano, N.; Kudo, Tamotsu; Moriyama, Kiyofumi; Sugimoto, Jun
Proc., Seminar on the Vapor Explosions in Nuclear Power Safety,Kanzanji 1995, 0, p.54 - 69, 1995/00
no abstracts in English
JAERI-M 93-111, 464 Pages, 1993/06
no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 33(12), p.1112 - 1120, 1991/12
no abstracts in English
Soda, Kunihisa
Journal of Nuclear Science and Technology, 19(10), p.813 - 820, 1982/00
Times Cited Count：4 Percentile：47.6(Nuclear Science & Technology)no abstracts in English
JAERI-M 8373, 143 Pages, 1979/05
no abstracts in English
Matsumura, Tatsuro; Iijima, Takahiko; Ishii, Sho; Takano, Masahide; Onozawa, Atsushi
no journal, ,
no abstracts in English
Tonoike, Kotaro; Yamane, Yuichi
no journal, ,
It is conceivable that a large amount of fuel debris has been produced in the reactors of Fukushima Daiichi Nuclear Power Station (1FNPS) due to the severe core damage and melting. The amount is far beyond minimum critical mass, and essentially subject to criticality control. This presentation will outline the criticality control of fuel debris in the Three Mile Island Nuclear Station, Unit 2 reactor (TMI-2). Then, criticality control problems of fuel debris during the 1FNPS decommissioning will be described contrasting with the TMI-2 case. Finally, technical expectations and research activities of the fuel debris criticality control for the 1FNPS will be presented. It is possible that the fuel debris will be retrieved under nonborated water at the risk of criticality. In this scenario, the risk control, mitigation measures in case of criticality, would be a key factor in safety of the decommissioning.
Takano, Masahide; Onozawa, Atsushi; Suzuki, Miho; Obata, Hiroki
no journal, ,
no abstracts in English
Matsumura, Taichi; Nagaishi, Ryuji; Katakura, Junichi*; Suzuki, Masahide*
no journal, ,
no abstracts in English
Takano, Masahide; Onozawa, Atsushi; Suzuki, Miho; Obata, Hiroki
no journal, ,
For the decommissioning of damaged cores of Fukushima Daiichi NPS, the retrieval operation of solidified core melt (corium) and its safe management are essential tasks. To understand characteristics of corium specific to the 1F cores, we have prepared and analyzed various types of simulated corium specimens in laboratory scale. To verify the effect of cooling condition found on the simulated corium, we revisit the actual corium specimens collected from the TMI-2 accident core, which have been stored at the Reactor Fuel Examination Facility (RFEF) in JAEA Tokai since 1991. Comparing the phases and microstructure, rapid-cooled specimens have dense microstructure and consist of single phase of cubic structure. On the other hand, the slow-cooled specimens consist of U-rich cubic and Zr-rich tetragonal phases distributed minutely. From these observations we have confirmed the similar dependence of microstructure and mechanical property on the cooling condition.
