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Title: 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:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4043048
Patent Number(s):
2992886
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-15-022383
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}
}