METHOD FOR DISSOLVING ZIRCONIUM-URANIUM COMPOSITIONS
Abstract
A method is descrioed for treating a zirconium-- uranium composition to form a stable solution from which uranium and other values may be extracted by contacting the composition with at least a 4 molar aqueous solution of ammonium fluoride at a temperature of about 100 deg C, adding a peroxide, in incremental amounts, to the heated solution throughout the period of dissolution until all of the uranium is converted to soluble uranyl salt, adding nitric acid to the resultant solution to form a solvent extraction feed solution to convert the uranyl salt to a solvent extractable state, and thereafter recovering the uranium and other desired values from the feed solution by solvent extraction.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4043048
- Patent Number(s):
- 2992886
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- NSA Number:
- NSA-15-022383
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; AMMONIUM COMPOUNDS; FLUORIDES; HYDROGEN PEROXIDES; NITRIC ACID; RECOVERY; SOLUTIONS; SOLVENT EXTRACTION; TEMPERATURE; URANIUM; URANIUM ALLOYS; URANYL COMPOUNDS; WATER; ZIRCONIUM ALLOYS
Citation Formats
Gens, T A. METHOD FOR DISSOLVING ZIRCONIUM-URANIUM COMPOSITIONS. United States: N. p., 1961.
Web.
Gens, T A. METHOD FOR DISSOLVING ZIRCONIUM-URANIUM COMPOSITIONS. United States.
Gens, T A. Tue .
"METHOD FOR DISSOLVING ZIRCONIUM-URANIUM COMPOSITIONS". United States.
@article{osti_4043048,
title = {METHOD FOR DISSOLVING ZIRCONIUM-URANIUM COMPOSITIONS},
author = {Gens, T A},
abstractNote = {A method is descrioed for treating a zirconium-- uranium composition to form a stable solution from which uranium and other values may be extracted by contacting the composition with at least a 4 molar aqueous solution of ammonium fluoride at a temperature of about 100 deg C, adding a peroxide, in incremental amounts, to the heated solution throughout the period of dissolution until all of the uranium is converted to soluble uranyl salt, adding nitric acid to the resultant solution to form a solvent extraction feed solution to convert the uranyl salt to a solvent extractable state, and thereafter recovering the uranium and other desired values from the feed solution by solvent extraction.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {7}
}
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