PRODUCTION OF REACTOR FUEL OXIDES FROM MOLTEN CHLORIDE SALT SOLUTIONS
Laboratory and engineering scale studies on the dissolution of irradiated oxide fuels in a molten chloride salt solution, and recovery of U, Th, and Pu as their oxides by appropriate electrochemical or chemical reactions are described. Exploratory studies on the preparation of PuC/sub 2/-UO/sub 2/, PuO/ sub 2/-- ThO/sub 2/, and UO/sub 2/-- ThO/sub 2/ solid solutions b y reaction in molten chloride salt solutions are also discussed. (P.C.H.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-17-026760
- OSTI ID:
- 4692951
- Report Number(s):
- HW-SA-2915
- Country of Publication:
- United States
- Language:
- English
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