Development of safety design criteria for the Generation-IV Sodium-cooled Fast Reactor

第4世代ナトリウム冷却高速炉の安全設計クライテリアの開発

中井 良大 ; 岡野 靖; 久保 重信 

Nakai, Ryodai; Okano, Yasushi; Kubo, Shigenobu

The Generation-IV International Forum (GIF) is a cooperative international framework to carry out the research and development needed to establish the feasibility and performance capabilities of the next generation nuclear energy systems. In the framework of the GIF, an effort on development of the "Safety Design Criteria (SDC)" for the Sodium-cooled Fast Reactor (SFR) was initiated in 2011 with the intent of completion of two years. The objectives of the SDC are to provide the reference criteria of the safety designs of structures, systems and components of the SFR system, where the criteria are clarified systematically and comprehensively, consistent with the GIF's basic safety approach and with the aim of achieving the safety and reliability goals defined in the GIF Roadmap. The SDC will be disseminated for taking reviews by all the technical entities related to the safety of nuclear systems, and will be utilized for SFR designs at international level.