Safety

[2C-03-01] A Safety Enhanced Core Concept for Metal-Fuel Sodium-Cooled Fast Reactors

*Sho Fuchita¹, Koji Fujimura¹, Kazuhiro Fujimata¹, Tomoki Mishima¹, Hirotaka Nakahara¹, Satoshi Takeda², Hirokazu Ohta³ (1. Hitachi-GE Nuclear Energy, Ltd. (Japan), 2. Osaka University (Japan), 3. Central Research Institute of Electric Power Industry (Japan))

キーワード：sodium-cooled fast reactor, metal fuel core, anticipated transient without scram, gas expansion module, self-actuated shutdown system, reactor vessel auxiliary cooling system