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Accident Progression and Source Term Analyses for LWR Severe Accidents - Japanese Activities and Progress -

DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.420

M. Kajimoto
Institute of Nuclear Safety (INS), Nuclear Power Engineering Corporation (NUPEC), Fujita Kanko Toranomon Bldg. 7F, Toranomon 3-17-1, Minato-ku, Tokyo, 105 Japan

N. Tanaka
Institute of Nuclear Safety (INS), Nuclear Power Engineering Corporation (NUPEC), Fujita Kanko Toranomon Bldg. 7F, Toranomon 3-17-1, Minato-ku, Tokyo, 105 Japan

O. Furukawa
Institute of Nuclear Safety (INS), Nuclear Power Engineering Corporation (NUPEC), Fujita Kanko Toranomon Bldg. 7F, Toranomon 3-17-1, Minato-ku, Tokyo, 105 Japan

Y. Takechi
Institute of Nuclear Safety (INS), Nuclear Power Engineering Corporation (NUPEC), Fujita Kanko Toranomon Bldg. 7F, Toranomon 3-17-1, Minato-ku, Tokyo, 105 Japan

M. Hirano
Institute of Nuclear Safety (INS), Nuclear Power Engineering Corporation (NUPEC), Fujita Kanko Toranomon Bldg. 7F, Toranomon 3-17-1, Minato-ku, Tokyo, 105 Japan

Resumo

Since the TMI-2 accident, experimental and analytical researches for LWR severe accidents have been carried out in Japan by the Nuclear Power Engineering Corporation (NUPEC), the Japan Atomic Energy Research Institute (JAERI) and industries. In 1980s, significant researches on severe accidents were performed by the organizations as a part of developing PSA methodology. In 1994, the industries set forth PSA-based individual plant examination (IPE) programs, and have selected viable measures of accident managements. The present paper describes Japanese activities and progress of the severe accident analyses. STCP and MELCOR were introduced to the Institute of Nuclear Safety (INS/NUPEC) and widely used to perform PSA for typical domestic LWRs. Various accident management measures and their effectiveness/viability were also discussed based on the MELCOR analyses. At JAERI, THALES/ART and an updated version THALES-2 that were developed by JAERI, were intensively used to identify important parameters that control accident progression and source term. In the IPE program performed by the industries, MAAP was used as a primary tool to quantify containment event trees and accident management procedures. These results have been reviewed by the INS through comparison with the information obtained from the MELCOR analyses. A comparative study among severe accident codes was endeavored by a cooperation work among INS, JAERI and industries. This study identified many important factors that may affect severe accident progression and source term behaviors. Analytical researches on severe accidents in Japan have been done with both introduced and originally developed codes. There still remain some differences between the predicted results among the codes resulted from phenomenological uncertainties, but common and qualitative understandings of severe accident phenomena have been established and utilized in performing level 2 PSA and discussing accident managements by taking account of experimental results.

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