Activities of the safety and operation project for the international research and development of the sodium-cooled fast reactor in the Generation IV international forum

第4世代原子力システムに関する国際フォーラムでのナトリウム冷却高速炉の研究開発における安全&運転プロジェクトの活動について

堺 公明; Ren, L.*; Tsige-Tamirat, H.*; Vasile, A.*; Kang, S.-H.*; Ashurko, Y.*; Fanning, T.*

Sakai, Takaaki; Ren, L.*; Tsige-Tamirat, H.*; Vasile, A.*; Kang, S.-H.*; Ashurko, Y.*; Fanning, T.*

The Generation IV (GEN-IV) international forum is a framework for international cooperation in research and development for the next generation of nuclear energy systems. The SFR Safety and Operation (SO) project addresses the area of the safety technology and the reactor operation technology developments. The aim of the SO project includes (1) analyses and experiments that support establishing safety approaches and validating performance of specific safety features, (2) development and verification of computational tools and validation of models employed in safety assessment and facility licensing, and (3) acquisition of reactor operation technology, as determined largely from experience and testing in operating SFR plants. In this paper, recent activities in the SO project are described.