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

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.
 [1];  [2]
  1. (Oakland, CA)
  2. (Livermore, CA)
Issue Date:
OSTI Identifier:
United States of America as represented by United States (Washington, DC) LLNL
Patent Number(s):
US 5698173
Contract Number:
Research Org:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Country of Publication:
United States
purification; uranium; alloys; differential; solubility; oxides; production; purified; fuel; precursors; method; purifying; metallic; nuclear; reactor; fuels; metal; alloy; converted; oxide; dissolved; nitric; acid; initial; removal; impurities; soluble; accomplished; filtration; physical; means; carbonate; leaching; uranyl; partially; solution; traditional; methods; solvent; extraction; metallic alloys; metallic alloy; uranium alloy; solvent extraction; nitric acid; nuclear reactor; metal oxide; metal alloy; reactor fuel; uranium alloys; oxide impurities; reactor fuels; solvent extract; /423/252/264/