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Ishida, Michihiko; Hayashi, Yoshiaki*; Ueda, Yoshinori*; Yoshida, Kazuo
Nihon Genshiryoku Gakkai Wabun Rombunshi, 9(1), p.71 - 81, 2010/03
A special committee of "Research on the analysis methods for accident consequence of nuclear fuel cycle facilities (NFCF)" was organized by the Atomic Energy Society of Japan (AESJ) under the entrustment of Japan Atomic Energy Agency (JAEA) for a research on the state-of-the-art of consequence analysis method for Probabilistic Safety Assessment (PSA) of NFCF such as fuel reprocessing and fuel fabrication facilities. The objectives of this research is to obtain the basic useful information related for establishing the quantitative performance requirement and for risk-informed regulation through qualifying issues needed to be resolved for applying PSA to NFCF. In this technical report, it was summarized that the research result about basic experimental data related to the consequence of the radiolytically generated hydrogen gas explosion postulated in the radioactive solution reserve tank caused by the loss of dilution air supply.
Abe, Hitoshi; Tashiro, Shinsuke; Ueda, Yoshinori*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 9(1), p.82 - 95, 2010/03
A special committee of "Research on the analysis methods for accident consequence of nuclear fuel facilities (NFF)" was organized by the Atomic Energy Society of Japan under the entrustment of JAEA. The committee aims to research on the state-of-the-art of consequence analysis method for Probabilistic Safety Assessment (PSA) of NFF such as fuel reprocessing and fuel fabrication facilities. The objective is to obtain the useful information related to establishing quantitative performance objectives and to risk-informed regulation through qualifying issues needed to be resolved for applying PSA to NFF. The research activities of the committee were mainly focused on the analysis method of consequences for postulated accidents with potentially large consequence in NFF resulting in release of radio active material to the environment. In this technical report, the research results about basic experimental data and method for safety evaluation for fire and explosion incidents were summarized.
Kase, Takeshi; ; Fujita, Yuji; Ueda, Yoshinori
Saikuru Kiko Giho, (4), 27-35 Pages, 1999/00
None
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Proceedings of 5th International Conference on Recycling, Conditioning and Disposal (RECOD '98), Vol.3, p.798 - 805, 1998/00
None
; ; ; Koyama, Tomozo; Ojima, Hisao; Shikakura, Sakae
Proceedings of 2nd International Symposium on Global Environment and Nuclear Energy Systems (GENES-2), 0 Pages, 1996/10
None
; ; ; Koyama, Tomozo; Ojima, Hisao; Shikakura, Sakae
Proceedings of 2nd International Symposium on Global Environment and Nuclear Energy Systems (GENES-2), 0 Pages, 1996/00
None
Ozawa, Masaki; Ueda, Yoshinori; Yasu, Takami; Goto, Minoru; Washiya, Tadahiro; Shimizu, Ryo; Torata, Shinichiro; Myochin, Munetaka
PNC TN8450 90-008, 202 Pages, 1990/07
None
Ishida, Michihiko; Suto, Toshiyuki; Inano, Masatoshi; Aoshima, Atsushi; Muramatsu, Ken; Ueda, Yoshinori*
no journal, ,
A study to evaluate component failure rates for a reprocessing plant has started at the Japan Atomic Energy Agency (JAEA). The study is sponsored by the Japan Nuclear Energy Safety Organization (JNES) as a contract research. The Tokai Reprocessing plant(TRP) has been operating over 30 years since 1977. Maintenance records of plant components have been accumulated and compiled in the Tokai Reprocessing Plant Maintenance Support System (TORMASS). Since the TORMASS was thought to be an effective source to pick up component failure information, the evaluation work of component failure rates started at 2005 based on the maintenance records in the TORMASS. By the end of 2006, failure rates for 17 types of 392 components had been evaluated. This result is expected to contribute to building up generic database for reprocessing plant component failure rates in order to promote the utilization of the risk information for reprocessing plants in Japan.
Tamaki, Hitoshi; Yoshida, Kazuo; Ueda, Yoshinori*
no journal, ,
A risk-informed regulation will be applied to not only nuclear power plants but also nuclear fuel facilities in Japan. It is important for risk-informed regulation to assure the results of PSA. Component failure rates used in the frequency evaluation play an important role to assure the quality of PSA. Reprocessing plants are recognized as having higher risk than that of other nuclear fuel facilities. However, accident frequencies happened in reprocessing plants are evaluated almost using component failure rates estimated from operation experiences of nuclear power plants because those parameters estimated from experiences of reprocessing plants are limited. In order to improve the quality of results of accident frequencies in reprocessing plants, a project was launched in 2005 at JAEA. This project is consisted of two activities and is performed under entrustment from JNES. One is the estimation of component failure rates based on maintenance data from Tokai Reprocessing plant which has been operating since 1977 in Japan. The other is the preparation of component failure rates for frequency evaluation of accidents in reprocessing plants. This presentation will introduce the second activity.
Ishida, Michihiko; Inano, Masatoshi; Aoshima, Atsushi; Suto, Toshiyuki; Muramatsu, Ken; Ueda, Yoshinori*
no journal, ,
Component failure rates are one of the most important inputs for PSA. Although there are many component failure rates databases for NPPs, there are few for a reprocessing plant. Therefore, in order to perform reliable PSA of a reprocessing plant, it is important to establish the failure rate database based on the actual plant maintenance data. The Tokai Reprocessing Plant (TRP) has been operating over 30 years since 1977. Maintenance records of plant components have been accumulated and compiled in the Tokai Reprocessing Plant Maintenance Support System (TORMASS). A basic study has started in the JAEA from 2005 by using the TORMASS data to contribute the development of reliable component failure rates. The outlines of the component failure estimation are summarized.
Tamaki, Hitoshi; Yoshida, Kazuo; Ishida, Michihiko; Muramatsu, Ken; Ueda, Yoshinori*
no journal, ,
no abstracts in English
Ueda, Yoshinori*; Ishida, Michihiko; Tamaki, Hitoshi; Muramatsu, Ken
no journal, ,
no abstracts in English
