METHOD FOR SEPARATING URANIUM, PROTACTINIUM, AND RARE EARTH FISSION PRODUCTS FROM SPENT MOLTEN FLUORIDE SALTS REACTOR FUELS.

Patent · Fri Jan 01 00:00:00 EST 1971

OSTI ID:4019960

Shaffer, J H; Moulton, D M; Grimes, W R

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-25-041903
• Assignee: (to United States Atomic Energy Commission).
• Patent Number(s): US 3577225 .
• OSTI ID: 4019960
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-71
• Country of Publication: United States
• Language: English

Related Subjects

N20510* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing
BISMUTH
FISSION PRODUCTS
FUELS
MELTING
MOLTEN SALT REACTORS
PROTACTINIUM
REDUCTION
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION URANIUM
BISMUTH/solvent properties of molten, for fission products, protactinium, and uranium from spent molten salt reactor fuels
PROTACTINIUM/separation from spent molten salt reactor fuels by selective reduction and extraction using molten bismuth
URANIUM/separation from spent molten salt reactor fuels by selective reduction and extraction using molten bismuth
FISSION PRODUCTS/separation from spent molten salt reactor fuels by selective reduction and extraction using molten bismuth
REACTOR FUELS/ reprocessing of molten salt
by selective reduction and extraction using molten bismuth