Recovery of uranium alloy
A method is described of recovery of uranium alloy from a mixture of uranium alloy with magnesium fluoride comprising: (a) pretreating uranium fluoride with magnesium at 400/sup 0/-1250/sup 0/C. to form a pretreated mixture of uranium and magnesium fluoride, (b) introducing the pretreated mixture into a molten-salt bath floating on a molten-uranium-alloy trap, (c) allowing the bath to transfer heat to the pretreated mixture to cause the magnesium fluoride to dissolve into the molten-salt bath and the uranium alloy to be molten, (d) allowing molten uranium alloy from the pretreated mixture in the bath to separate from the bath into the trap, (e) discharging separated molten-uranium alloy from the trap, and (f) discharging non-alloy components of the pretreated mixture along with excess molten salt from the bath.
- Assignee:
- NOV; EDB-87-045948; NOV-87-044067
- Patent Number(s):
- US 4636250
- OSTI ID:
- 6986694
- Country of Publication:
- United States
- Language:
- English
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INVESTIGATIONS ON THE REDUCTION OF URANIUM(IV) FLUORIDE BY LIQUID ALUMINUM IN MOLTEN SALT MIXTURES
Magnesium reduction of uranium fluoride in molten salts
Related Subjects
360101* -- Metals & Alloys-- Preparation & Fabrication
ACTINIDE ALLOYS
ACTINIDE COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
ALKALINE EARTH METALS
ALLOYS
DISPERSIONS
ELEMENTS
EXTRACTION
FLUORIDES
FLUORINE COMPOUNDS
HALIDES
HALOGEN COMPOUNDS
HIGH TEMPERATURE
MAGNESIUM
MAGNESIUM COMPOUNDS
MAGNESIUM FLUORIDES
METALS
MIXTURES
MOLTEN SALTS
SALTS
SEPARATION PROCESSES
SOLVENT EXTRACTION
URANIUM ALLOYS
URANIUM COMPOUNDS
URANIUM FLUORIDES
VERY HIGH TEMPERATURE