Blanket design and neutronics analysis for compact tokamak test reactor

Using Monte Carlo particle transport code MCNP, the 3D neutronics analysis as well as TBR calculation for high power compact tokamak (CT) test reactor were done. The structure design for helium cooling ceramic breeder (HCCB) blanket was carried out with Li₄SiO₄, Be and the low activated ferrite steel as the tritium breeder, neutron multiplier and structural material respectively. The variation of TBR vs the breeding unit thickness was simulated, under different breeding unit with different structure arrangement. The preliminary optimum design of blanket with tritium self-sufficiency was obtained. The related characteristics of neutron wall loading, energy deposit and power density was given, as supplies data support for the thermal hydraulics and related design and analysis in next step. (authors)