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Title: METHOD OF DISSOLVING REFRACTORY ALLOYS

Abstract

This patent relates to the dissolution of alloys of uranium with zirconium, thorium, molybdenum, or niobium. The alloy is contacted with an anhydrous solution of mercuric chloride in a low-molecular-weight monohydric alcohol to produce a mercury-containing alcohol slurry. The slurry is then converted to an aqueous system by adding water and driving off the alcohol. The resulting aqueous slurry is electrolyzed in the presence of a mercury cathode to remove the mercury and produce a uranium-bearing aqueous solution. This process is useful for dissolving irradiated nuclear reactor fuels for radiochemical reprocessing by solvent extraction. In addition, zirconium-alloy cladding is selectively removed from uranium dioxide fuel compacts by this means. (AEC)

Inventors:
;
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4742971
Patent Number(s):
3086926
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-17-018214
NSA Number:
NSA-17-018214
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ALCOHOLS; CATHODES; ELECTROLYSIS; FUEL CANS; MERCURY; MERCURY CHLORIDES; MOLYBDENUM ALLOYS; NIOBIUM ALLOYS; REPROCESSING; SEPARATION PROCESSES; SLURRIES; SOLUTIONS; SOLVENT EXTRACTION; THORIUM ALLOYS; URANIUM ALLOYS; URANIUM COMPOUNDS; URANIUM DIOXIDE; WATER; ZIRCONIUM ALLOYS

Citation Formats

Helton, D.M., and Savolainen, J.K. METHOD OF DISSOLVING REFRACTORY ALLOYS. United States: N. p., 1963. Web.
Helton, D.M., & Savolainen, J.K. METHOD OF DISSOLVING REFRACTORY ALLOYS. United States.
Helton, D.M., and Savolainen, J.K. Tue . "METHOD OF DISSOLVING REFRACTORY ALLOYS". United States.
@article{osti_4742971,
title = {METHOD OF DISSOLVING REFRACTORY ALLOYS},
author = {Helton, D.M. and Savolainen, J.K.},
abstractNote = {This patent relates to the dissolution of alloys of uranium with zirconium, thorium, molybdenum, or niobium. The alloy is contacted with an anhydrous solution of mercuric chloride in a low-molecular-weight monohydric alcohol to produce a mercury-containing alcohol slurry. The slurry is then converted to an aqueous system by adding water and driving off the alcohol. The resulting aqueous slurry is electrolyzed in the presence of a mercury cathode to remove the mercury and produce a uranium-bearing aqueous solution. This process is useful for dissolving irradiated nuclear reactor fuels for radiochemical reprocessing by solvent extraction. In addition, zirconium-alloy cladding is selectively removed from uranium dioxide fuel compacts by this means. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {4}
}