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Title: FUSED SALT PROCESS FOR RECOVERY OF VALUES FROM USED NUCLEAR REACTOR FUELS

Abstract

A process is given for recovering plutonium from a neutron-irradiated uranium mass (oxide or alloy) by dissolving the mass in an about equimolar alkali metalaluminum double chloride, adding aluminum metal to the mixture obtained at a temperature of between 260 and 860 deg C, and separating a uranium-containing metal phase and a plutonium-chloride- and fission-product chloridecontaining salt phase. Dissolution can be expedited by passing carbon tetrachloride vapors through the double salt. Separation without reduction of plutonium from neutron- bombarded uranium and that of cerium from uranium are also discussed.

Inventors:
Issue Date:
OSTI Identifier:
4129122
Patent Number(s):
2948586
Assignee:
U.S. Atomic Energy Commission
Patent Classifications (CPCs):
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
NSA Number:
NSA-14-025580
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ALKALI METALS; ALUMINUM; ALUMINUM CHLORIDES; CERIUM; CHLORIDES; FISSION PRODUCTS; FUELS; FUSED SALTS; HALOGENATED HYDROCARBONS; METALS; PLUTONIUM; RECOVERY; REPROCESSING; TEMPERATURE; URANIUM ALLOYS; URANIUM OXIDES; VAPORS

Citation Formats

Moore, R H. FUSED SALT PROCESS FOR RECOVERY OF VALUES FROM USED NUCLEAR REACTOR FUELS. United States: N. p., 1960. Web.
Moore, R H. FUSED SALT PROCESS FOR RECOVERY OF VALUES FROM USED NUCLEAR REACTOR FUELS. United States.
Moore, R H. Mon . "FUSED SALT PROCESS FOR RECOVERY OF VALUES FROM USED NUCLEAR REACTOR FUELS". United States.
@article{osti_4129122,
title = {FUSED SALT PROCESS FOR RECOVERY OF VALUES FROM USED NUCLEAR REACTOR FUELS},
author = {Moore, R H},
abstractNote = {A process is given for recovering plutonium from a neutron-irradiated uranium mass (oxide or alloy) by dissolving the mass in an about equimolar alkali metalaluminum double chloride, adding aluminum metal to the mixture obtained at a temperature of between 260 and 860 deg C, and separating a uranium-containing metal phase and a plutonium-chloride- and fission-product chloridecontaining salt phase. Dissolution can be expedited by passing carbon tetrachloride vapors through the double salt. Separation without reduction of plutonium from neutron- bombarded uranium and that of cerium from uranium are also discussed.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {8}
}