Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors
Abstract
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.
- Inventors:
- Issue Date:
- Research Org.:
- Univ. of California (United States)
- Sponsoring Org.:
- USDOE, Washington, DC (United States)
- OSTI Identifier:
- 563645
- Patent Number(s):
- 5698173
- Application Number:
- PAN: 8-675,327; TRN: 98:002117
- Assignee:
- Dept. of Energy, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-48
- Resource Type:
- Patent
- Resource Relation:
- Other Information: PBD: 16 Dec 1997
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 05 NUCLEAR FUELS; URANIUM ALLOYS; REFINING; URANIUM OXIDES; DISSOLUTION; FILTRATION; URANYL COMPOUNDS; LEACHING; SOLVENT EXTRACTION; NUCLEAR FUELS
Citation Formats
McLean, W II, and Miller, P E. Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors. United States: N. p., 1997.
Web.
McLean, W II, & Miller, P E. Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors. United States.
McLean, W II, and Miller, P E. Tue .
"Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors". United States.
@article{osti_563645,
title = {Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors},
author = {McLean, W II and Miller, P E},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1997},
month = {12}
}
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