Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors
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:
-
- (Oakland, CA)
- Livermore, CA
- Issue Date:
- Research Org.:
- Lawrence Livermore National Laboratory (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
- 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.
McLean, II, William, & Miller, Philip E. Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors. United States.
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.
@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 = {Wed Jan 01 00:00:00 EST 1997},
month = {Wed Jan 01 00:00:00 EST 1997}
}
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