Blanket design

Application of self-cooling liquid blanket system to FFHR-d1 has been studied. The method for breeding blanket , investigation by neutronics, support of reactor core internal structure and modularization of blanket, problem of first wall of blanket, and tritium control are reported. The outline figure of self-cooling liquid blanket structure, simple torus calculation system for investigation of neutronics design of FFHR-d1, arrangement of radiation shielding materials of breeding blanket, comparison of fully covered TBR calculated by simple torus calculation system for FFHR-d1, comparison of fast neutron flux at SCM in self-cooling liquid blanket, three-dimension neutron and gamma-ray transport calculation system for FFHR-d1, calculation results of fast neutron flux distribution, relation between thickness of the first wall and stress by thermal and internal pressure at 800K, experimental results of plasma driven permeation obtained by VEHICLE-1, change of melting point of LiF + BeF2 mixed salt, and tritium radioactivity from Flibe are illustrated. (S.Y.)