Neutronics Study for a Tokamak Commercial Breeder

A conceptual design for a liquid lithium self-cooled tokamak commercial breeder, TCB, has been performed. Fission-suppressed blanket is adopted to maximize fuel production and alleviate safety problem. U-Pu cycle is chosen owing to its available technology. The difficulty of suppressing fission in a uranium system is partly overcome by using depleted uranium. The toroidal effect and self-shielding effect have been taken into account. The effects of neutron source density distribution on the blanket neutronics performance and poloidal variation of the neutron wall loading are also studied.