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Title: 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 DTIE; NSA-16-013164
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 = {1962},
month = {4}
}