Search for reality of solid breeder blanket for DEMO

For a tokamak fusion DEMO reactor with the fusion output of 2.95 GW, neutronic and thermal design of blanket is under way to find a feasible blanket concept. For the continuity with the Japanese ITER-TBM options, this study considered water-cooled blanket with solid breeding materials of Li ceramics (Li(4)SiO(4), Li(2)TiO(3) and Li(2)ZrO(3)) and Be multipliers (Be and Be(12)Ti). Based on a neutronics-heat coupled analysis, the tritium breeding ratio was evaluated so as to satisfy constraints of the operating temperature of <= 900 degrees C for Li ceramics and Be12Ti, and <= 600 degrees C for Be. Cooling water condition was assumed to be 23 MPa and 290-360 degrees C. The result indicates that surplus tritium production in lower neutron wall load (P(n)) blanket compensates a shortfall in higher P(n) blanket and thus the overall tritium production can marginally satisfy fuel self-sufficiency. (c) 2010 Elsevier B.V. All rights reserved.