Speaker
Zaixin Li
(Center For Fusion Science)
Description
Chinese Fusion Engineering Testing Reactor (CFETR) is aimed to obtain the technologies to fill the gaps between ITER and DEMO. The helium cooled ceramic breeder (HCCB) blanket is one of the candidates for CFETR. Ceramics Li4SiO4, beryllium and helium of 8 MPa were selected as tritium breeding material, neutron multiplication and coolant, respectively. CLF steel developed in SWIP, one of reduced activation ferritic/martensitic (RAFM) steels, was applied as structural materials of blanket. Neutron and gamma transport was simulated. Activation calculation was performed with FISPACT-2007 code and EAF-2007 activation file. In this study, neutronics characteristic of HCCB blanket such as tritium breeding ratio (TBR), nuclear heating distribution and shielding were assessed. The arrangement of Be, Li4SiO4and cooling plate in blanket module was optimized to improve TBR. The sensitive study for First Wall on TBR was also performed. The radioactivity inventories of HCCB blanket were estimated. The dominant radionuclides in structural materials, Li4SiO4 and Beryllium were discussed, respectively. The damage of plasma facing components such as First Wall anddivertor due to DT neutron irradiation was analyzed in terms of DPA values.
Co-authors
Fengchao Zhao
(Center For Fusion Science, Southwestern Institute of Physics (SWIP), Chengdu, Sichuan, China)
Kaiming Feng
(Center For Fusion Science, Southwestern Institute of Physics (SWIP), Chengdu, Sichuan, China)
Zaixin Li
(Center For Fusion Science, Southwestern Institute of Physics (SWIP), Chengdu, Sichuan, China)
Zhou Zhao
(Center For Fusion Science, Southwestern Institute of Physics (SWIP), Chengdu, Sichuan, China)
