Abstract
Helium-cooled ceramic reflector (HCCR) blanket concept was proposed as a DEMO breeding blanket in Korea. It adopted lithium ceramic breeder, graphite reflector to reduce the beryllium multiplier, reduced activation ferritic-martensitic steel as a structural material, and high pressure/temperature helium as a coolant. As a pre-conceptual design study, neutronic assessment of the HCCR blanket was carried out by inserting the newly developed model into the K-DEMO three-dimensional neutronic calculation model. As results, the peak neutron wall load of 4.06 MW/m2 was obtained at the outboard midplane blanket first wall for the fusion power of 3 GW. The overall tritium breeding ratio (TBR) was estimated as 1.10. And the poloidal mean global TBR distribution at the blankets were calculated.
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