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Nakai, Satoru; Nishio, Ryuichi; Uchihashi, Masaya; Kaneko, Yoshihisa; Yamashita, Hironobu*; Yamaguchi, Atsunori*; Aoki, Takayuki*
no journal, ,
A sodium cooled fast breeder reactor (FBR) has unique systems and components and different degradation mechanism from light water reactor (LWR) so that need to establish maintenance technology in accordance with its features. The examination of the FBR maintenance technology is carried out in the special committee for considering the maintenance for Monju established in the Japan Society of Maintenology (JSM). As a result of the study such as extraction of Monju maintenance feature, maintenance technology benchmark between Monju and LWR components and survey of LWR maintenance experience, it is clear that principles of maintenance are same as LWR, necessity of LWR maintenance experience reflection and points to be considered in Monju maintenance. The road map to establish a FBR maintenance technology in the technical aspect became clear and it is vital to acquire operation and maintenance experience of the plant to implement this road map, and to establish a fast reactor maintenance.
Demachi, Kazuyuki*; Dong, F.*; Abe, Toru*; Chen, S.*; Takaya, Shigeru; Seki, Akiyuki; Yoshikawa, Masanori; Miki, Daisuke*
no journal, ,
Takada, Tsuyoshi; Horiike, Hiroshi*; Miyano, Hiroshi*; Ebisawa, Katsumi*
no journal, ,
Trials related to seismic safety of nuclear power plants are being held in many places in Japan. Among many controversial issues, the study group on trials on nuclear power plants in JSM has studied the recent court decisions on nuclear safety against future earthquakes; that of the Osaka District Court, the Mito District Court, and the Sendai District Court. The concept of "substantial safety" and "procedural safety", along with the concept of "Defense in Depth (DiD)" proposed by International Atomic Energy Agency (IAEA), particularly the fifth protection level namely effective evacuation planning are discussed herein. Finally, the probabilistic risk assessment (PRA) study must be done to treat the substantial safety of nuclear power plants and to cover all levels of protection described in the DiD concept.