THE PROCESSING OF IRRADIATED URANIUM RESULTS OF THE OPERATION OF THE FONTENAY-aux-ROSES PILOT PLANT

Technical Report · Sat Oct 31 04:00:00 EST 1959

OSTI ID:4269306

Regnaut, P; Faugeras, P; Brut, A; Helou, R; Redon, A

The pilot plant at Fontenay-aux-Roses for the processing of irradiated uranium was put in operation in 1954. The results of four years' experience in the operation of this plant are described in detail. The method used is based on the preferential extraction of the nitrates of heavy metals by tributyl phosphate diluted in a paraffin hydrocarbon. The steps of the process include removal of the cladding, dissolution of the uranium bars, extractions, concentration of the fission product solution prior to storage, concentration of the plutonium solutions, second cycle of plutonium purification, and preparation of plutonium fluoride. The conclusions drawn from this operating experience are discussed. Laboratory investigations on the chemical removal of the cladding, dissolution of the uranium, equipment for solvent extraction, concentration of plutonium solutions, and recovery of metal from slag are also reported. (J.S.R.)

• Research Organization: Commissariat a l'Energie Atomique, Paris
• NSA Number: NSA-13-006447
• OSTI ID: 4269306
• Report Number(s): A/CONF.15/P/1172
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BUTYL PHOSPHATES
CHEMISTRY
ENRICHMENT
FISSION PRODUCTS
FRANCE
FUEL CANS
FUEL ELEMENTS
OPERATION
PARAFFIN
PERFORMANCE
PLUTONIUM FLUORIDES
PLUTONIUM NITRATES
RECOVERY
REPROCESSING
SOLUTIONS
SOLVENT EXTRACTION
STORAGE
URANYL NITRATES
WATER