PRELIMINARY SPENT FUEL WASTE EVALUATION AND MANAGEMENT FOR SMALL MODULAR REACTORS

Abstract

Three Small Modular Reactor (SMR) concepts, micro-scale High Temperature Gas Cooled Reactor (mHTGR), small modular Chloride Salt-based Molten Salt Reactor (CMSR), and the small modular Fluoride Salt-based Molten Salt Reactor (FMSR), are designed to employ different moderators, coolants and fuels than CANDU® reactors. The use of graphite moderator, novel reactor coolant, and different uranium ceramic or salt fuel will make SMR fuel-waste management requirements different from CANDU® reactor spent fuel. This paper provides estimates of potential SMR spent fuel waste and a review of technologies for conditioning the waste to facilitate disposal with CANDU® fuel waste. Estimated SMR spent fuel waste is similar in the quantities of uranium, plutonium, minor actinides, and fission products for equivalent energy generation and similar enrichment, but differs in volume and chemical composition. Large volumes of graphite, fluorides, and chlorides will be found in the HTGR and MSR fuel waste, respectively. Separation of uranium compounds from graphite and salt matrix is necessary to reduce the waste volume and facilitate waste disposal.