Recovery of protactinium from molten fluoride nuclear fuel compositions
Patent
·
OSTI ID:4346688
A method is provided for separating protactinium from a molten fluonlde salt composition consisting essentially of at least one alkali and alkaline earth metal fluoride and at least one soluble fluoride of uranium or thorium which comprises oxidizing the protactinium in said composition to the + 5 oxidation state and contacting said composition with an oxide selected from the group consisting of an alkali metal oxide, an alkaline earth oxide, thorium oxide, and uranium oxide, and thereafter isolating the resultant insoluble protactinium oxide product from said composition. (Official Gazette)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-29-026773
- Assignee:
- to United States Atomic Energy Commission
- Patent Number(s):
- US 3781403
- OSTI ID:
- 4346688
- Resource Relation:
- Patent File Date: 1971 Nov 30; Other Information: C01g57/00. Orig. Receipt Date: 30-JUN-74
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
N40450* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing
N40430 -Chemistry-Radiochemistry & Nuclear Chemistry-Radioactive Waste Treatment
*PROTACTINIUM- SEPARATION PROCESSES
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
FLUORIDES
MOLTEN SALT FUELS
OXIDES
PROTACTINIUM OXIDES
THORIUM FLUORIDES
THORIUM OXIDES
URANIUM FLUORIDES
URANIUM OXIDES
N40430 -Chemistry-Radiochemistry & Nuclear Chemistry-Radioactive Waste Treatment
*PROTACTINIUM- SEPARATION PROCESSES
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
FLUORIDES
MOLTEN SALT FUELS
OXIDES
PROTACTINIUM OXIDES
THORIUM FLUORIDES
THORIUM OXIDES
URANIUM FLUORIDES
URANIUM OXIDES