NEUP CINR-18-15307: A novel and flexible approach for converting LWR UNF fuel into forms that can be used to fuel a variety of Gen-IV reactors

We propose to investigate both the chemical decladding and the digestion of entire LWR fuel assemblies using thionyl chloride and surrogate materials (unirradiated cladding and natural or depleted UO2 pellets). We will attempt to develop strategies to recover zirconium and a selectable fraction of the uranium as highly purified chlorides separated from the transuranics and fission products for use in various Gen-IV reactor designs.

Additional Info

Field	Value
Awarded Institution	University of Tennessee at Knoxville
PI	Craig Barnes