Preliminary Neutronics And Activation Analysis Of The WCSB Blanket For CFETR

China Fusion Engineering Test Reactor (CFETR) is a fusion superconducting tokamak reactor. The purpose of it is to verify the specific techniques of the fusion reactor. The blanket is one of key components of the CFETR, which will be used to test the tritium self-sufficiency technology and convert the energy from fusion into the available power during reactor operation. The neutronics and activation analysis of the blanket is preliminary validated the rationality and correctness of the design parameters. It is the key step in the engineering design and test. Many activity materials can be produced when the neutron multiplier, structure material and tritium breeder have serious activation reaction under high energy neutron field. Accordingly, it is required to ensure radiation safety of staff at the time of replacement and maintenance.The three-dimensional Monte Carlo Neutron-Photon Transport Code MCNP/4C and the Fusion Evaluated Nuclear Data Library (FENDL/2) which released by IAEA are used in the neutronics performance calculations for water cooling solid breeder blanket (WCSB) of CFETR. The neutronics performance calculation and analysis include tritium breeder ratio, neutron wall loading and nuclear heat. The TBR of the three dimensional geometrical model is more than1.20, which meets the design requirement of CFETR. The results show that the distribution of the source region and the blanket design are the main factors affect the neutronics performance of blanket.Furthermore, the activation calculation is performed by using FISPACT-2007with the EAF-2007library, and the activation characteristics include activity, afterheat and contact dose rate. It is performed assuming an intermittent irradiation over one year at full fusion power (200MW), and the duty cycle time is0.4. The results show that wait times are required in the order102years for the remote handling recycling option. Meanwhile, the impurity of the blanket, such as93Nb and59Co and94Mo must be confined in reasonable scope. The results can provide significant theory reference base for the optimization and next plan of the blanket.