THE PREPARATION OF URANIUM METAL BY THE ELECTROLYTIC REDUCTION OF ITS OXIDES

Journal Article · Sun Jun 01 04:00:00 EDT 1958 · Journal of the Electrochemical Society (U.S.) Absorbed Electrochem. Technol.

DOI:https://doi.org/10.1149/1.2428843· OSTI ID:4345049

Niedrach, L W; Dearing, B E

The background work is described for a new continuous process for the production of uranium by electrolytic reduction of its oxides in fused salt electrolytes. Unlike past electrolytic processes for uranium production, the present one is operated at temperatures which are above the melting point of the metal. The effect of current, salt bath composition, and other variables on efficiency and cell operation are discussed. An electrolysis bath containing 20 mole % UF/sub 4/ diluted with a 50:50 mole% mixture of BaF/sub 2/ and MgF/sub 2/ was found to be satisfactory. With this bath anode current densities as high as 3.6 amp/cm/sup 2/ are feasible without encountering anode effect.'' Any of the oxides of uranium can be used as the feed, but UO/sub 3/ appears to be preferable. The advantages of the new process are outlined, and the areas requiring additional development work are indicated. (auth)

• Research Organization: General Electric Co., Schenectady, N.Y.
• Sponsoring Organization: USDOE
• NSA Number: NSA-12-009769
• OSTI ID: 4345049
• Journal Information: Journal of the Electrochemical Society (U.S.) Absorbed Electrochem. Technol., Journal Name: Journal of the Electrochemical Society (U.S.) Absorbed Electrochem. Technol. Vol. Vol: 105; ISSN JESOA
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ANODES
BARIUM FLUORIDES
CHEMICAL REACTIONS
CHEMISTRY
CURRENTS
EFFICIENCY
ELECTROLYSIS
ELECTROLYTIC CELLS
FUSED SALTS
MAGNESIUM FLUORIDES
MELTING POINTS
METALS
PREPARATION
QUANTITY RATIO
REDUCTION
TEMPERATURE
URANIUM
URANIUM OXIDES
URANIUM TETRAFLUORIDE
URANIUM TRIOXIDE