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Title: RECOVERY OF URANIUM FROM ZIRCONIUM-URANIUM NUCLEAR FUELS

Abstract

An improvement was made in a process of recovering uranium from a uranium-zirconium composition which was hydrochlorinated with gsseous hydrogen chloride at a temperature of from 350 to 800 deg C resulting in volatilization of the zirconium, as zirconium tetrachloride, and the formation of a uranium containing nitric acid insoluble residue. The improvement consists of reacting the nitric acid insoluble hydrochlorination residue with gaseous carbon tetrachloride at a temperature in the range 550 to 600 deg C, and thereafter recovering the resulting uranium chloride vapors. (AEC)

Inventors:
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4802608
Patent Number(s):
3043653
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-16-027114
NSA Number:
NSA-16-027114
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; CARBON TETRACHLORIDE; CHEMICAL REACTIONS; CHLORINATION; EVAPORATION; GASES; HIGH TEMPERATURE; HYDROCHLORIC ACID; NITRIC ACID; RADIOCHEMISTRY; RECOVERY; REPROCESSING; RESIDUES; SOLUBILITY; TEMPERATURE; URANIUM; URANIUM ALLOYS; URANIUM CHLORIDES; URANIUM COMPOUNDS; VAPORS; WASTE PROCESSING; ZIRCONIUM; ZIRCONIUM ALLOYS; ZIRCONIUM CHLORIDES

Citation Formats

Gens, T.A. RECOVERY OF URANIUM FROM ZIRCONIUM-URANIUM NUCLEAR FUELS. United States: N. p., 1962. Web.
Gens, T.A. RECOVERY OF URANIUM FROM ZIRCONIUM-URANIUM NUCLEAR FUELS. United States.
Gens, T.A. Tue . "RECOVERY OF URANIUM FROM ZIRCONIUM-URANIUM NUCLEAR FUELS". United States.
@article{osti_4802608,
title = {RECOVERY OF URANIUM FROM ZIRCONIUM-URANIUM NUCLEAR FUELS},
author = {Gens, T.A.},
abstractNote = {An improvement was made in a process of recovering uranium from a uranium-zirconium composition which was hydrochlorinated with gsseous hydrogen chloride at a temperature of from 350 to 800 deg C resulting in volatilization of the zirconium, as zirconium tetrachloride, and the formation of a uranium containing nitric acid insoluble residue. The improvement consists of reacting the nitric acid insoluble hydrochlorination residue with gaseous carbon tetrachloride at a temperature in the range 550 to 600 deg C, and thereafter recovering the resulting uranium chloride vapors. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1962},
month = {7}
}