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Title: 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.:
University of California
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
563645
Patent Number(s):
5,698,173
Application Number:
PAN: 8-675,327; TRN: 98:002117
Assignee:
Dept. of Energy, Washington, DC (United States) PTO; SCA: 050700; PA: EDB-98:013351; SN: 98001896309
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}
}