Abstract: For meeting the application requirements of China Fusion Engineering Test Reactor (CFETR) blanket, the helium cooled ceramic breeder (HCCB) blanket concept was proposed in this paper. In order to verify the rationality and feasibility of HCCB blanket scheme, the neutronics characteristics including tritium breeding ratio, neutron wall loading, neutron flux density, nuclear power and irradiation damage were calculated with the three-dimensional Monte Carlo particle transport code MCNP. The results show that the HCCB blanket scheme satisfies the requirements of tritium selfsustaining, its neutron flux density and nuclear power distributions are reasonable, and the shield meets the design requirements well.