AbstractA scoping neutronics study has been carried out for an engineering test fusion breeder. Several fast fission blanket schemes have been studied for different tritium breeders, such as Li, LiPb, FliBe and Li2O. The variation of neutronics performance with the accumulation of fission fuel has also been studied for tritium breeding, fission fuel breeding and energy deposition. The study has been made to enhance the fissile fuel production while breaking even in tritium. To alleviate the critical problem of MHD pressure drop and to simplify the reactor structure, fission material is placed only in the outboard blanket. After optimization, calculation results based on a one-dimensional model show that the required performance can be achieved for Li, LiPb and Li2O blankets, while the performance is far from satisfactory for FLiBe. Finally, multi-dimensional calculations were performed for a liquid Li blanket.