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Title: MIXING AND SETTLING SEPARATION PROCESS FOR URANIUM OR PLUTONIUM.

Inventors:
;
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4627689
Patent Number(s):
3677743
Assignee:
(to United States Atomic Energy Commission). TIC; NSA-26-058678
NSA Number:
NSA-26-058678
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-72
Country of Publication:
United States
Language:
English
Subject:
N40450* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing; FISSION PRODUCTS; LIQUID METALS; MIXER-SETTLERS; MOLTEN SALTS; PLUTONIUM; PLUTONIUM OXIDES; SOLVENT EXTRACTION; SPENT FUELS; URANIUM; URANIUM DIOXIDE; REACTOR FUELS/reprocessing of mixed oxide, by solvent extraction using liquid metals, molten salts, and mixer-settlers; URANIUM/ separation from spent oxide fuels by solvent extraction using liquid metals, molten salts, and mixer-settlers; FISSION PRODUCTS/separation from spent oxide fuels by solvent extraction using liquid metals, molten salts, and mixer-settlers; PLUTONIUM/separation from spent oxide fuels by solvent extraction using liquid metals, molten salts, and mixer-settlers

Citation Formats

Walsh, W.J., and Pierce, R.D. MIXING AND SETTLING SEPARATION PROCESS FOR URANIUM OR PLUTONIUM.. United States: N. p., 1972. Web.
Walsh, W.J., & Pierce, R.D. MIXING AND SETTLING SEPARATION PROCESS FOR URANIUM OR PLUTONIUM.. United States.
Walsh, W.J., and Pierce, R.D. Sat . "MIXING AND SETTLING SEPARATION PROCESS FOR URANIUM OR PLUTONIUM.". United States.
@article{osti_4627689,
title = {MIXING AND SETTLING SEPARATION PROCESS FOR URANIUM OR PLUTONIUM.},
author = {Walsh, W.J. and Pierce, R.D.},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1972},
month = {1}
}