Thorium conversion optimization in two-fluid molten-salt reactor

Molten-Salt Reactors (MSR) are an attractive reactor system for various purposes. They can be designed to be operated in a fast neutron spectrum for spent fuel transmutation or in a thermal spectrum. Thermal MSRs provide an ideal platform for conversion of thorium to ²³³U. Flowing salt can be continuously reprocessed to minimize neutron losses due to neutron absorption in fission products. This study deals with a static neutronic optimization of a Two-Fluid MSR concept. Such a reactor features two separated molten-salt streams in the reactor core. One salt contains fissile material ²³³U, the other thorium. Separation of these streams improves the conversion capabilities of MSRs. Such a design was analysed for Molten-Salt Breeder Reactor (MSBR) development. This reactor was not realized, but it is used as a reference for this study. Monte-Carlo code MCNP5 was used to model a simplified MSBR core and for calculation of the breeding capabilities of this design. Several basic geometric parameters were selected for evaluation of their effect on characteristics of the reactor. Based on this analysis, an improved designed was prepared with shorter fissile material doubling time. The whole analysis was carried out for fresh fuel composition. It is possible to expect that on-line fuel reprocessing will limit fuel composition changes during reactor operation. Only effect of ²³³Pa accumulation on the thorium conversion was studied for several fuel reprocessing rates. (author)