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Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors

United States Patent

*** EXPIRED ***
December 16, 1997
View the Complete Patent at the US Patent & Trademark Office
Lawrence Livermore National Laboratory - Visit the Industrial Partnerships Office Website
A method 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.
McLean, II; William (Oakland, CA), Miller; Philip E. (Livermore, CA)
The United States of America as represented by the United States (Washington, DC)
08/ 675,327
June 21, 1996
STATEMENT OF GOVERNMENT INTEREST The U.S. Government has certain rights to this invention under Contract No. W-7405-ENG-48 between the University of California and the U.S. Department of Energy.