金属燃料ナトリウム冷却高速炉の安全解析に関する研究; プロジェクト全体概要

Study on safety analyses for metal-fueled sodium-cooled fast reactors; Project overview

山野 秀将   ; 二神 敏  ; 堂田 哲広  ; 田上 浩孝 ; 内堀 昭寛 ; 尾形 孝成*; 太田 宏一*

Yamano, Hidemasa; Futagami, Satoshi; Doda, Norihiro; Tagami, Hirotaka; Uchibori, Akihiro; Ogata, Takanari*; Ota, Hirokazu*

Japan Atomic Energy Agency and Central Research Institute of Electric Power Industry have been conducting a project to develop safety analysis methodologies on metal fuel sodium-cooled fast reactors in the area of advanced reactors under the framework of the U.S.-Japan bilateral commission on civil nuclear cooperation since 2018. The project encompasses analysis methodology development and experiment on core bowing reactivity analysis, core damage accident analysis, and mechanistic source-term analysis. This report describes the project overview and the outcomes of five-year activities in Phase 1: 2018-2022.