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

Patent · Wed Jan 01 00:00:00 EST 1997

OSTI ID:871279

Miller, Philip E ^[1]

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1. Livermore, CA

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.

• Research Organization: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
• DOE Contract Number: W-7405-ENG-48
• Assignee: United States of America as represented by United States (Washington, DC)
• Patent Number(s): US 5698173
• OSTI ID: 871279
• Country of Publication: United States
• Language: English

Related Subjects

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/