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

Patent · Mon Aug 01 00:00:00 EDT 1960

OSTI ID:4129122

Moore, R H

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.

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-14-025580
• Assignee: U.S. Atomic Energy Commission
• Patent Number(s): US 2948586
• OSTI ID: 4129122
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-60
• Country of Publication: United States
• Language: English

Related Subjects

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