Enhancement of JSFR safety design and criteria for Gen.IV reactor

JSFR安全設計と第4世代炉クライテリアの強化

青砥 紀身 ; 近澤 佳隆  ; 大久保 努; 岡田 敬三*; 伊藤 隆哉*

Aoto, Kazumi; Chikazawa, Yoshitaka; Okubo, Tsutomu; Okada, Keizo*; Ito, Takaya*

JSFR開発の現状と東京電力の福島第一原子力発電所事故からの教訓をまとめる。JSFRは次世代炉として期待されている。JSFRの安全設計はシビアアクシデントや受動炉停止系、自然循環崩壊熱除去系を2010年の設計案で既に考慮しているが、福島第一の事故を受けてシビアアクシデント及び外部事象に対する重要性の認識が高まってきた。近年の活動では外部ハザード評価や上記事故の教訓を活かした設計強化があげられる。本書では安全設計方策の世界的な安全設計クライテリアと国際研究開発協力の重要性も示す。

Overview of Japan Sodium-cooled Fast Reactor (JSFR) development status and reflection of lessons learned from the TEPCO's Fukushima Dai-ichi Nuclear Power Plant (1F) accident have been summarized. JSFR was recognized as a promising next generation nuclear reactor. Even though the JSFR safety design already took into account measures against severe accident situations and passive safety features such as passive shutdown system and natural convection decay heat removal systems in the 2010 design version, it is become aware of importance of design measures against severe accidents and extreme external events by the 1F accident. As recent activities, external hazard evaluations and design improvements reflecting lessons learned from 1F accident have been conducted. This paper also discusses importance of development of global safety design criteria and international Research and Development cooperation on safety design measures.