Preliminary Calculation And Analysis Of Activation For CFETR Blanket

China Fusion Engineering Test Reactor (CFETR) which is based on the tokamak approach is currently undergoing the engineering conceptual design by the China National Integration. The main objective of CFETR is to demonstrate and realize tritium self-sufficiency breeding. Neutronics analysis and activation calculation and analysis for CFETR Blanket are pretty important. According to recently completed preliminary design of CFETR, we established a simplified two-dimensional model of tritium self-sufficiency breeding blanket in the MCNPX program for neutronics analysis. With zone homogenization adopted, the entire model comes out with partial elliptical cross section torus structure and stratified homogeneous DT fusion Gaussian spectrum neutron source. We adopted nuclear data library FENDL2.0 for neutron transport, low Activation Ferrite Steel as structural materials, Li4SiO4 and high-pressure helium as tritium breeder and coolant respectively. Using MCNPX and an activation calculation code FISPACT-2007, TBR, neutron transport, nuclear heart, radioactivity, shutdown dose rate and shielding effect for China fusion engineering test reactor (CFETR) have been calculated basing on the model of blanket. The calculation results show that the total radioactivity is 2.34×1019Bq at shutdown after one year operation and the total radioactivity is 7.98×1018Bq which is 12.1% of the original radioactivity. Until the cooling time reaches 2.6 years,25.2 years and 46.4 years, respectively, tritium breeding material, neutron multiplier material and structural material can be remotely operated. The results show that there isn’t serious environmental issue. Taking the preliminary effect of shielding layer simulation into consideration, the design of inner breeding blanket structure needs to be adjusted, and further optimization of the shielding layer for neutron shielding design should be adopted. This work will be useful in the protection of maintenance staff and suggestion on optimization of shielding facility.