THE SALT CYCLE PROCESS

Technical Report · Mon Aug 01 04:00:00 EDT 1960

DOI:https://doi.org/10.2172/4769449· OSTI ID:4769449

Benedict, G. E.; Lyon, W. L.; Mudge, L. K.; Swanson, J. L.; Walling, Jr., M. T.

The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact facilities located at the reactor sites. Irradiated UO/sub 2/ fuels would be processed through a brief sequence of steps and partially purified UO/sub 2/ or UO/sub 2/--PuO/sub 2/ powders recovered, suitable for refabrication into fuel elements. The major steps of the process are the dissolution of uranium oxides in molten NaCl--KCl eutectic by chlorination to form soluble uranyl chloride and the reduction of uranyl chloride to UO/sub 2/, which separates as a solid. The preferred method of reduction is the electrolytic method, which yields UO/sub 2/ as a conveniently handled, adherent deposit on the cathode. Means are described for separation of Pu from U and for co-deposition of the Uo. Also included are discussions of the probable nature of the U and Pu species present in the molten salt, side reactions in which uranyl chloride may participate, and the influence of certain variables on the properties of the UO/sub 2/ produced. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• Sponsoring Organization: USDOE
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-16-030491
• OSTI ID: 4769449
• Report Number(s): HW-SA-1936
• Country of Publication: United States
• Language: English

Related Subjects

ADHESION
BURNUP
CATHODES
CHEMISTRY
CHLORIDES
CHLORINATION
ELECTRODEPOSITION
ELECTROLYSIS
EUTECTICS
FUELS
FUSED SALTS
PLUTONIUM
PLUTONIUM OXIDES
POTASSIUM CHLORIDES
POWDERS
REACTION KINETICS
REDUCTION
REPROCESSING
SEPARATION PROCESSES
SODIUM CHLORIDES
SOLIDS
SOLUTIONS
THERMODYNAMICS
URANIUM
URANIUM DIOXIDE
URANYL COMPOUNDS