PLUTONIUM RECOVERY FROM NEUTRON-BOMBARDED URANIUM FUEL
Abstract
A process of recovering plutonium from neutronbombarded uranium fuel by dissolving the fuel in equimolar aluminum chloride-potassium chloride; heating the mass to above 700 deg C for decomposition of plutonium tetrachloride to the trichloride; extracting the plutonium trichloride into a molten salt containing from 40 to 60 mole % of lithium chloride, from 15 to 40 mole % of sodium chloride, and from 0 to 40 mole % of potassium chloride or calcium chloride; and separating the layer of equimolar chlorides containing the uranium from the layer formed of the plutonium-containing salt is described. (AEC)
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4796850
- Patent Number(s):
- 3029130
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
- NSA Number:
- NSA-16-013164
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; CALCIUM CHLORIDES; DECOMPOSITION; FUELS; FUSED SALTS; HEATING; HIGH TEMPERATURE; IRRADIATION; LAYERS; LITHIUM CHLORIDES; MASS; NEUTRON BEAMS; PLUTONIUM; PLUTONIUM CHLORIDES; POTASSIUM CHLORIDES; RECOVERY; SEPARATION PROCESSES; SODIUM CHLORIDES; SOLUBILITY; URANIUM
Citation Formats
Moore, R H. PLUTONIUM RECOVERY FROM NEUTRON-BOMBARDED URANIUM FUEL. United States: N. p., 1962.
Web.
Moore, R H. PLUTONIUM RECOVERY FROM NEUTRON-BOMBARDED URANIUM FUEL. United States.
Moore, R H. Tue .
"PLUTONIUM RECOVERY FROM NEUTRON-BOMBARDED URANIUM FUEL". United States.
@article{osti_4796850,
title = {PLUTONIUM RECOVERY FROM NEUTRON-BOMBARDED URANIUM FUEL},
author = {Moore, R H},
abstractNote = {A process of recovering plutonium from neutronbombarded uranium fuel by dissolving the fuel in equimolar aluminum chloride-potassium chloride; heating the mass to above 700 deg C for decomposition of plutonium tetrachloride to the trichloride; extracting the plutonium trichloride into a molten salt containing from 40 to 60 mole % of lithium chloride, from 15 to 40 mole % of sodium chloride, and from 0 to 40 mole % of potassium chloride or calcium chloride; and separating the layer of equimolar chlorides containing the uranium from the layer formed of the plutonium-containing salt is described. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Apr 10 00:00:00 EST 1962},
month = {Tue Apr 10 00:00:00 EST 1962}
}
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