PLUTONIUM RECOVERY FROM NEUTRON-BOMBARDED URANIUM FUEL
Patent
·
OSTI ID:4796850
A process of recovering plutonium from neutronbombarded uranium fuel by dissolving the fuel in equimolar aluminum chloride-potassium chloride; heating the mass to above 700 deg C for decomposition of plutonium tetrachloride to the trichloride; extracting the plutonium trichloride into a molten salt containing from 40 to 60 mole % of lithium chloride, from 15 to 40 mole % of sodium chloride, and from 0 to 40 mole % of potassium chloride or calcium chloride; and separating the layer of equimolar chlorides containing the uranium from the layer formed of the plutonium-containing salt is described. (AEC)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-16-013164
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 3029130
- OSTI ID:
- 4796850
- Country of Publication:
- United States
- Language:
- English
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