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 (Li4SiO4, Li2TiO3 and Li 2ZrO3) and Be multipliers (Be and Be12Ti). Based on a neutronics-heat coupled analysis, the tritium breeding ratio was evaluated so as to satisfy constraints of the operating temperature of ≤900°C for Li ceramics and Be12Ti, and ≤600°C for Be. Cooling water condition was assumed to be 23MPa and 290-360°C. The result indicates that surplus tritium production in lower neutron wall load (P n) blanket compensates a shortfall in higher Pn blanket and thus the overall tritium production can marginally satisfy fuel self-sufficiency.
- Solid breeder
ASJC Scopus subject areas
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering