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

Miller, Philip E

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

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Abstract

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.

Inventors:

McLean, II, William ^[1]; Miller, Philip E ^[2]

(Oakland, CA)
Livermore, CA

Issue Date:: 1997-01-01

Research Org.:: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

OSTI Identifier:: 871279

Patent Number(s):: 5698173

Assignee:: United States of America as represented by United States (Washington, DC)

Patent Classifications (CPCs):: C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F

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C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C01G43/00 - Compounds of uranium

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DOE Contract Number:: W-7405-ENG-48

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: 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/

Citation Formats


                    McLean, II, William, and Miller, Philip E. Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors.  United States: N. p., 1997. 
        Web.

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                    McLean, II, William, & Miller, Philip E. Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors.  United States.

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                    McLean, II, William, and Miller, Philip E. Wed .  
        "Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors".  United States.  https://www.osti.gov/servlets/purl/871279.

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@article{osti_871279,

  title        = {Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors},

  author       = {McLean, II, William and Miller, Philip E},

  abstractNote = {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.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1997},

  month        = {1}

}

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

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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.
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