| Project Detail |
The U.S. has accumulated approximately 86,000 metric tons of used nuclear fuel (UNF) from light-water reactors (LWRs), a value that increases by approximately 2,000 tons per year. This UNF is destined for permanent disposal even though more than 90% of its energy remains. Innovative technologies that enable the secure, economical reprocessing of the nation’s LWR UNF could substantially reduce the volume, heat load, and radiotoxicity of waste requiring permanent disposal while providing a valuable and sustainable fuel feedstock for advanced fast reactors. CURIE seeks to research innovative separations technologies, material accountancy, and online monitoring technologies, as well as designs for a reprocessing facility that will enable group recovery of actinides for advanced reactor (AR) feedstocks, incorporate in situ process monitoring, minimize waste volumes, enable a 1¢/kilowatt-hour (kWh) fuel cost for AR fuels, and maintain disposal costs in the range of 0.1¢/kWh.
Project Innovation + Advantages:
The University of Utah will research a pyrochemical process for efficiently converting UNF to a uranium/transuranic (U/TRU) product suitable for sodium-cooled fast reactors or molten-salt fueled reactors. This process is based on two key separations steps that can occur in a single reaction vessel: dissolution of oxide UNF in molten lithium chloride (LiCl)-potassium chloride (KCl) salt and electrochemical recovery of U/TRU metal on a cathode. Overall, this technology should result in less material handling and lower space requirements than conventional pyroprocessing technology via elimination of fuel baskets, consolidation of processing units, and use of a single solvent salt (i.e., LiCl-KCl). If successful, the proposed process would open the pathway for high throughput, economical pyrochemical processing of UNF that does not generate pure plutonium streams. |
