Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors
Patent
·
OSTI ID:563645
A method is described for purifying metallic alloys of uranium for use as nuclear reactor fuels in which the metal alloy is first converted to an oxide and then dissolved in nitric acid. Initial removal of metal oxide impurities not soluble in nitric acid is accomplished by filtration or other physical means. Further purification can be accomplished by carbonate leaching of uranyl ions from the partially purified solution or using traditional methods such as solvent extraction. 3 figs.
- Research Organization:
- University of California
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-48
- Assignee:
- Dept. of Energy, Washington, DC (United States)
- Patent Number(s):
- US 5,698,173/A/
- Application Number:
- PAN: 8-675,327
- OSTI ID:
- 563645
- Country of Publication:
- United States
- Language:
- English
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