[3L10-12] Blanket Materials

[3L12] Study on electrically insulated flow channels of self-cooled liquid metal blanket system under condition of helical reactor FFHR-d1

*Teruya Tanaka¹, Satoshi Ito², Takumi Chikada³, Yukinori Hamaji¹, Takehiko Yokomine⁴, Takeo Muroga¹ (1. NIFS, 2. Tohoku Univ., 3. Shizuoka Univ., 4. Kyoto Univ.)

Keywords:Liquid metal blanket, Thermo fluid calculation, MHD pressure drop, Electrical insulating material

Study of a self-cooled liquid metal blanket system (LiPb, etc.) by using the thermo-fluid calculation code STREAM have been conducted for the blanket configuration, magnetic field distribution and heat load distribution considered in the design of the helical reactor FFHR-d1. The required coolant circulation rate, flow velocity for first wall cooling, magnitude of MHD pressure drop and cooling channel configuration obtained for the maximum magnetic field of ~7.5 T, maximum neutron wall loading of 2.0 MW/m² and heat load of 0.1 MW/m² on the first wall will be presented. The presentation also includes required performances of electrically insulated flow channels, investigation of candidate insulating materials and startup of fabrication studies of the flow channels.