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Nagaishi, Ryuji; Morita, Keisuke; Yamagishi, Isao; Hino, Ryutaro; Ogawa, Toru
Proceedings of 2014 Nuclear Plant Chemistry Conference (NPC 2014) (USB Flash Drive), 9 Pages, 2014/10
Two years after Three Mile Island Unit 2 (TMI-2) loss-of-coolant accident, radioactive contaminated water has been processed by Submerged Demineralizer System (SDS) with two types of zeolite adsorbents to remove radioactive nuclides. During and after the process, adsorption amount and distribution of nuclides on the zeolites, residual water content and thermal conductivity in the SDS vessels have been measured or estimated for verification of safety in the process, subsequent transportation and disposal. Hydrogen generation has been also evaluated mainly by direct monitoring in the large-scale of vessel after the process. In this work, the revaluation of hydrogen generation was demonstrated on the basis of the open information of vessel, and the latest experimental data obtained in adsorption and radiolysis occurring in small-scale of zeolite-water mixtures. As a result, the evaluated data was found to be comparable with the reported data obtained in the large-scale of real vessel.
Washiya, Tadahiro; Yano, Kimihiko; Ikeuchi, Hirotomo; Kaji, Naoya; Takano, Masahide; Morimoto, Kyoichi
Proceedings of 2014 Water Reactor Fuel Performance Meeting/ Top Fuel/ LWR Fuel Performance Meeting (WRFPM 2014) (CD-ROM), 6 Pages, 2014/09
On March 11, 2011, the Great East Japan Earthquake caused the severe accident at Fukushima Daiichi NPS (F1). In the reactors of unit 1-3, large amount of fuel debris was generated. Thermodynamic equilibrium (TDE) calculations based on results of MAAP code analysis was carried out and typical debris phases were predicted. Experimental studies were also carried out using simulated fuel debris, and verify the expected properties. The F1 accident differs from the past severe accidents. Specific factors in the F1 accident to be considered in this study are fuel assembly and control rod materials, core configuration and accident sequence. Further specific factors are high zirconium and iron contents, B
C and sea water effects and molten core concrete interaction (MCCI). Mechanical properties were identified as important properties. Mechanical properties have been obtained experimentally using simulated debris as based on (U,Zr)O
and (U,Zr,Fe)O materials.
Uetsuka, Hiroshi
Saishin Kaku Nenryo Kogaku; Kodoka No Genjo To Tembo, p.156 - 162, 2001/06
no abstracts in English
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
Uetsuka, Hiroshi; Nagase, Fumihisa;
JAERI-Research 95-084, 36 Pages, 1995/11
JAERI-Research-95-084.pdf:1.32MB
no abstracts in English
Ishigami, Tsutomu
Journal of Nuclear Science and Technology, 32(7), p.691 - 701, 1995/07
Times Cited Count：2 Percentile：27.03(Nuclear Science & Technology)no abstracts in English
Onizawa, Kunio; Hashimoto, Kazuichiro
OECD Documents, Three Mile Island Reactor Pressure Vessel Investigation Project; Achievements and, 0, p.322 - 334, 1995/00
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
Uetsuka, Hiroshi; Nagase, Fumihisa
Proceedings of Three Mile Island Reactor Pressure Vessel Investigation Project Open Forum, p.269 - 280, 1994/00
no abstracts in English
Tsukada, Takashi; Suzuki, Masahide; Kawasaki, Satoru
Proceedings of Three Mile Island Reactor Pressure Vessel Investigation Project Open Forum, p.151 - 163, 1994/00
no abstracts in English
JAERI-M 93-111, 464 Pages, 1993/06
no abstracts in English
Furuta, Teruo
Kaku Nenryo, (17), p.17_44 - 17_45, 1992/06
no abstracts in English
Hidaka, Akihide; Sugimoto, Jun; Soda, Kunihisa
EUR-14039-EN, p.28 - 36, 1992/00
no abstracts in English
Hashimoto, Kazuichiro; Onizawa, Kunio; Kurihara, Ryoichi; Kawasaki, Satoru; Soda, Kunihisa
Int. J. Press. Vessels Piping, 52, p.25 - 40, 1992/00
Times Cited Count：3 Percentile：53.24(Engineering, Multidisciplinary)no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 33(12), p.1112 - 1120, 1991/12
no abstracts in English
Hashimoto, Kazuichiro; Soda, Kunihisa
JAERI-M 91-193, 21 Pages, 1991/10
no abstracts in English
Hashimoto, Kazuichiro; Onizawa, Kunio; Kurihara, Ryoichi; Kawasaki, Satoru; Soda, Kunihisa;
Transactions of the 11th Int. Conf. on Structural Mechanics in Reactor Technology,Vol. F, p.123 - 128, 1991/08
no abstracts in English
Hidaka, Akihide; Sugimoto, Jun; ; Soda, Kunihisa
JAERI-M 89-213, 87 Pages, 1989/12
no abstracts in English
Hashimoto, Kazuichiro; Soda, Kunihisa;
Nuclear Technology, 87, p.1058 - 1066, 1989/12
no abstracts in English
