Search for reality of solid breeder blanket for DEMO

Tobita, Kenji; Uto, Hiroyasu; Liu, C.; Tanigawa, Hisashi; Tsuru, Daigo; Enoeda, Mikio; Yoshida, Toru; Asakura, Nobuyuki

For a tokamak fusion DEMO reactor with the fusion output of 2.95 GW, neutronics and thermal design was carried out to find a blanket concept with reality. For the continuity with the Japanese ITER-TBM options, this study considered water-cooled blanket with solid breeding materials of Li ceramics and Be multipliers. A neutronics-heat coupled analysis determined an optimal arrangement of blanket interior under the constraints of the operating temperature of breeding materials and multipliers. When the cooling water is used under 23 MPa and 290-360 C, the overall tritium sufficiency is marginally satisfied although blankets with high neutron wall load ( = 5 MW/m) around the mid-plane do not meet the required local TBR. Based on the results, possible directions for further research are presented.