PLUTONIUM RECOVERY FROM NEUTRON-BOMBARDED URANIUM FUEL
Patent
·
OSTI ID:4117235
A process of recovering plutonium from fuel by dissolution in molten KAlCl/sub 4/ double salt is described. Molten lithium chloride plus stannous chloride is added to reduce plutonium tetrachloride to the trichloride, which is dissolved in a lithium chloride phase while the uranium, as the tetrachloride, is dissolved in a double-salt phase. Separation of the two phases is discussed. (AEC)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-18-012279
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 3126251
- OSTI ID:
- 4117235
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALUMINUM CHLORIDES
CHEMICAL REACTIONS
CHEMISTRY
FUELS
FUSED SALTS
IRRADIATION
LITHIUM CHLORIDES
MIXING
NEUTRON BEAMS
NEUTRONS
OPERATION
PATENT
PLUTONIUM
PLUTONIUM CHLORIDES
POTASSIUM CHLORIDES
RADIOCHEMISTRY
RECOVERY
REDUCTION
REPROCESSING
SEPARATION PROCESSES
SOLUTIONS
TIN CHLORIDES
URANIUM
URANIUM CHLORIDES
CHEMICAL REACTIONS
CHEMISTRY
FUELS
FUSED SALTS
IRRADIATION
LITHIUM CHLORIDES
MIXING
NEUTRON BEAMS
NEUTRONS
OPERATION
PATENT
PLUTONIUM
PLUTONIUM CHLORIDES
POTASSIUM CHLORIDES
RADIOCHEMISTRY
RECOVERY
REDUCTION
REPROCESSING
SEPARATION PROCESSES
SOLUTIONS
TIN CHLORIDES
URANIUM
URANIUM CHLORIDES