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Title: URANIUM SEPARATION PROCESS

Abstract

A method of separating uranium oxides from PuO/sub 2/, ThO/sub 2/, and other actinide oxides is described. The oxide mixture is suspended in a fused salt melt and a chlorinating agent such as chlorine gas or phosgene is sparged through the suspension. Uranium oxides are selectively chlorinated and dissolve in the melt, which may then be filtered to remove the unchlorinated oxides of the other actinides. (AEC)

Inventors:
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4796849
Patent Number(s):
3030176
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-16-013166
NSA Number:
NSA-16-013166
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ACTINIDES; CARBONYLS; CHLORIDES; CHLORINATION; CHLORINE; FILTERS; GASES; MELTING; MIXING; OXIDES; PHOSGENE; PLUTONIUM OXIDES; SEPARATION PROCESSES; SOLUBILITY; SUSPENSIONS; THORIUM OXIDES; URANIUM; URANIUM OXIDES

Citation Formats

Lyon, W.L. URANIUM SEPARATION PROCESS. United States: N. p., 1962. Web.
Lyon, W.L. URANIUM SEPARATION PROCESS. United States.
Lyon, W.L. Tue . "URANIUM SEPARATION PROCESS". United States.
@article{osti_4796849,
title = {URANIUM SEPARATION PROCESS},
author = {Lyon, W.L.},
abstractNote = {A method of separating uranium oxides from PuO/sub 2/, ThO/sub 2/, and other actinide oxides is described. The oxide mixture is suspended in a fused salt melt and a chlorinating agent such as chlorine gas or phosgene is sparged through the suspension. Uranium oxides are selectively chlorinated and dissolve in the melt, which may then be filtered to remove the unchlorinated oxides of the other actinides. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1962},
month = {4}
}