[3L01-07] Fusion Instrument Engineering

[3L01] Investigation of liquid test blanket module for DEMO reactor

(1)Design investigation of self-cooled LiPb module

*Teruya Tanaka¹, Masatoshi Kondo², Yoji Someya³, Shinji Ebara⁴, Takehiko YokomineYokomine⁵, Kazunari Katayama⁶, Ryuta Kasada⁴, Ryoji Hiwatari³, Yoshiteru Sakamoto³, Takashi Nozawa³ (1. NIFS, 2. Tokyo Tech, 3. QST, 4. Tohoku Univ., 5. Kyoto Univ., 6. Kyushu Univ.)

Keywords:DEMO reactor, test blanket module, liquid blanket, LiPb, self-cooled

In the action plan toward a DEMO reactor, install of a test blanket module (DEMO TBM) with a liquid metal or molten salt tritium breeder in the latter period of the reactor operation is proposed to confirm the feasibility of the liquid blanket concept. A self-cooled LiPb blanket concept has been selected to start the investigation of the DEMO TBM designs from the viewpoint of the simple module structure. Based on analysis results of three-dimensional magnetic field distributions in a DEMO reactor, evaluation of magnitudes of MHD pressure drop in the blanket area, proposal of flow channel configuration in the TBM module, investigation of a flow condition of LiPb for the first wall cooling, etc. have been performed by numerical calculations. In addition to the present investigation results, issues in the future study such as material corrosion, etc. will be discussed.