A METHOD OF PROCESSING FUEL MATERIAL OF NUCLEAR REACTORS
A method is given for processing reactor fuel materials for separation and recovery of Pu in concentrated form. The method comprises dissolution of a U or Pu oxidic or alloy mass in an alkali metal-alunninum double chloride by heating to 260 to 800 deg C; a metal phase containing U metal and a salt phase containing Pu in the chloride form are formed. The Pu may be obtained as the metal by adding Ca and/or Mg to the separated salt phase. The formation of A1/ sub 2/0/sub 3/, which hinders dissolution of reactor fuel alloys, may be prevented or reduced by sparging the double chloride melt with CCl/sub 4/ vapors in an inert gas. The method is also applicable to the separation of a rare earth, alkaline earth, alkali metal, or thorium from uranium. (D.L.C.)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-15-026123
- OSTI ID:
- 4007132
- Report Number(s):
- GB 870691
- Country of Publication:
- United Kingdom
- Language:
- English
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