A multi-layer breeding blanket concept for CFETR based on PWR condition

A breeding blanket concept with the multi-layer structure based on the PWR water-cooled condition was presented for CFETR. To explore the feasibility of the blanket scheme, the neutronics and hydraulics programs were carried out. It was found when the P_n is less than 3MW/m², the local TBR (tritium breeding ratio) would be in range of 1.46-1.7. Thus, the net TBR would be more than 1.05, which meets the tritium self-sustaining requirement for the fusion reactor. Especially, the local TBR is 1.66 at a neutron wall load (P_n) of 0.5 MW/m² and the corresponding net TBR is 1.21. On the other hand, it also clarified a pipe bore with 7-8 mm at an inlet velocity of 3-4 m/s would be suitable for the heat removal of the blanket module. In addition, the total pressure drop would be under 0.2 MPa in the cooling system. It was concluded that the blanket concept would be more effective and benefit to CFETR in view of its neutron wall load level and the tritium self-sustaining efficiency.