A METHOD OF PREPARING URANIUM DIOXIDE

Patent · Tue Dec 17 00:00:00 EST 1963

OSTI ID:4130008

Scott, F A; Mudge, L K

A process of purifying raw, in particular plutonium- and fission- products-containing, uranium dioxide is described. The uranium dioxide is dissolved in a molten chloride mixture containing potassium chloride plus sodium, lithium, magnesium, or lead chloride under anhydrous conditions; an electric current and a chlorinating gas are passed through the mixture whereby pure uranium dioxide is deposited on and at the same time partially redissolved from the cathode. (AEC)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-18-003919
• Assignee: U.S. Atomic Energy Commission
• Patent Number(s): US 3114682
• OSTI ID: 4130008
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-64
• Country of Publication: United States
• Language: English

Related Subjects

CHEMISTRY
CATHODES
CHLORINATION
ELECTRODEPOSITION
FISSION PRODUCTS
FUSED SALTS
LEAD CHLORIDES
LITHIUM CHLORIDES
MAGNESIUM CHLORIDES
MIXING
PATENT
PLUTONIUM COMPOUNDS
POTASSIUM CHLORIDES
PREPARATION
REPROCESSING
SODIUM CHLORIDES
SOLUTIONS
URANIUM DIOXIDE