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Ishikawa, Jun; Muramatsu, Ken; Sakamoto, Toru*
JAERI-Research 2005-021, 133 Pages, 2005/09
JAERI-Research-2005-021.pdf:7.58MB
The THALES-2 code is an integrated severe accident analysis code in order to simulate the accident progression and transport of radioactive material for probabilistic safety assessment (PSA) of a nuclear power plant, a part of a level 3 PSA being performed at JAERI for a 1,100MWe BWR-5 with a Mark-II containment. Results and insights from the analyses were that (1) the calculated release fractions of CsI and CsOH to the environment were in the range of 0.01 to 0.1 for late containment overpressure failure cases, and the release fractions for the containment venting case were one order of magnitude smaller than that of over-pressure case and those for drywell spray recovery cases where no containment failure occurred were two orders of magnitude smaller than the containment venting cases, (2) the governing factors for source terms of Iodine and Cesium are different depending on whether the containment fails before core melt or not, (3) the containment venting, which is one of the accident management measures, can be expected to reduce source terms if suppression pool bypass is avoided.
Tamai, Hiroshi; Matsukawa, Makoto; Kurita, Genichi; Hayashi, Nobuhiko; Urata, Kazuhiro*; Miura, Yushi; Kizu, Kaname; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Kudo, Yusuke; et al.
Plasma Science and Technology, 6(1), p.2141 - 2150, 2004/02
Times Cited Count：2 Percentile：6.49(Physics, Fluids & Plasmas)The dominant issue for the the modification program of JT-60 (JT-60SC) is to demonstrate the steady state reactor relevant plasma operation. Physics design on plasma parameters, operation scenarios, and the plasma control method are investigated for the achievement of high-
. Engineering design and the R&D on the superconducting magnet coils, radiation shield, and vacuum vessel are performed. Recent progress in such physics and technology developments is presented.
Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Chujo, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.
Nuclear Fusion, 43(7), p.606 - 613, 2003/07
no abstracts in English
Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Cho, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.
Nuclear Fusion, 43(7), p.606 - 613, 2003/07
Times Cited Count：33 Percentile：69.03(Physics, Fluids & Plasmas)no abstracts in English
Ishikawa, Jun; Muramatsu, Ken; Sakamoto, Toru*
Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 8 Pages, 2002/00
no abstracts in English
*; Muramatsu, Ken; *; Sakamoto, Toru*
ANS Proc. of the 1992 National Heat Transfer Conf., p.386 - 400, 1993/00
no abstracts in English
Hidaka, Akihide; *; Soda, Kunihisa; Muramatsu, Ken; Sakamoto, Toru*
ANS Proc. of the 1992 National Heat Transfer Conf., p.408 - 416, 1993/00
no abstracts in English
Ishigami, Tsutomu; Sakamoto, Toru*; Kobayashi, Kensuke; *
JAERI-M 88-093, 89 Pages, 1988/05
no abstracts in English
Kobayashi, Kensuke; Ishigami, Tsutomu; Sakamoto, Toru*; Fujiki, Kazuo
Severe accidents in Nuclear Power Plants,Vol. 1, p.323 - 329, 1988/00
no abstracts in English
Abe, Kiyoharu; Watanabe, Norio; Ida, Mitsuo; Sakamoto, Toru; Ishigami, Tsutomu; Harami, Taikan
Proc.on Probabilistic Safety Assessment and Risk Management PSA87, Vol.3, p.945 - 950, 1987/00
no abstracts in English
Ishikawa, Jun; Sakamoto, Toru*; Moriyama, Kiyofumi; Nakamura, Hideo; Nakamura, Koichi*
no journal, ,
no abstracts in English
Yamashita, Shinichiro; Abe, Hiroaki*; Sato, Daiki*; Owaki, Masao*; Sakamoto, Kan*; Kusagaya, Kazuyuki*; Tsuchiya, Akiyuki*
no journal, ,
The ATF Working Group (ATF-WG), which started its activities in July 2017, has been considering safety requirements for the introduction of ATF while incorporating overseas knowledge of the United States, which is ahead of ATF development. In the ATF-WG activities, based on the safety design of the core and fuel of LWRs for power generation, we organized the concept of extracting the evaluation items necessary for ATF safety design and the importance of ATF safety. The way of thinking organized here can also be used for the research and development of ATF that are currently underway, and we are going to summarize it in a report in the future.
