HYDROFLUORIC ACID DECLADDING OF ZIRCONIUM-CLAD POWER REACTOR FUEL ELEMENTS

Technical Report · Sat Nov 01 04:00:00 EST 1958

DOI:https://doi.org/10.2172/4300381· OSTI ID:4300381

Clark, W. E.; Kibbey, A. H.

ABS>A detailed flowsheet is presented for the removal of Zircaloy-2 cladding from a UO/sub 2/ core (as in the Commonwealth Edison fuel) by dissolution in hydrofluoric acid to give a F/Zr ratio of 4.5/l in the solution. The core is dissolved in 8 M HNO/sub 3/ for subsequent removal of fission products by solvent extraction. In tests on unirradiated prototypes, uranium loss to the fluoride solution was as little as 0.16%. Dissolution data on uranium metal and U-10% Mo alloy indicate that these cores can be declad similarly. U-Zr alloys cannot be so stripped while U-Nb is somewhat doubtful. It appears that pure zirconium cladding can be removed about as easily as Zircaloy-2. One container constructed of Carpenter 20 (niobium stabilized) stainless steel can probably be used for both dissolution steps. (auth)

• Research Organization: Oak Ridge National Lab., Tenn.
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-13-001120
• OSTI ID: 4300381
• Report Number(s): ORNL-2460
• Country of Publication: United States
• Language: English

Related Subjects

ACIDITY
CARPENTER
CHEMICAL REACTIONS
CHEMISTRY
CORROSION
DIAGRAMS
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
FUELS
HYDROFLUORIC ACID
IRRADIATION
LOSSES
MATERIALS TESTING
MEASURED VALUES
MOLYBDENUM ALLOYS
NIOBIUM ALLOYS
NITRIC ACID
PERFORMANCE
QUANTITY RATIO
REACTOR CORE
REPROCESSING
SEPARATION PROCESSES
SOLUTIONS
SOLVENT EXTRACTION
STAINLESS STEELS
TESTING
URANIUM ALLOYS
URANIUM DIOXIDE
ZIRCALOY
ZIRCONIUM
ZIRCONIUM ALLOYS