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Dissolution mechanisms for UO/sub 2/ and spent fuel

Conference ·
OSTI ID:6893594
;
The probable dissolution mechanisms for UO/sub 2/ and spent fuel were studied based on accelerating oxidation and dissolutions in autoclave and electrochemical experiments. The dissolution of UO/sub 2/ is primarily due to oxidation of U/sup +4/ (solid) to U/sup +6/ (liquid). The U/sup +6/(liquid) is initially in dissolved uranyl ions, UO/sub 2//sup +2/, but subsequent hydrolysis reactions lead to the formation of solid uranyl hydrates (or related complex compounds) that deposit onto the surfaces of UO/sub 2/ and container walls as thin or thick coatings, depending on the temperature, pH, and time. Therefore, the dissolution rate of UO/sub 2/ cannot be simply determined from the uranium content of the solution. Moreover, the dissolution rate is not limited by the solubility of the uranyl ions. Electrochemical dissolution of spent fuel shows that the initial dissolution and leaching behavior is similar to that of UO/sub 2/ surfaces.
Research Organization:
Pacific Northwest Lab., Richland, WA (USA)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
6893594
Report Number(s):
PNL-SA-8933; CONF-801206-15; ON: DE83003656
Country of Publication:
United States
Language:
English

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Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
053000 -- Nuclear Fuels-- Environmental Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
400702 -- Radiochemistry & Nuclear Chemistry-- Properties of Radioactive Materials
ACTINIDE COMPOUNDS
CATIONS
CHALCOGENIDES
CHARGED PARTICLES
CHEMICAL REACTION KINETICS
CHEMICAL REACTIONS
DISSOLUTION
ENERGY SOURCES
FUELS
IONS
KINETICS
LEACHING
MATERIALS
NUCLEAR FUELS
OXIDATION
OXIDES
OXYGEN COMPOUNDS
REACTION KINETICS
REACTOR MATERIALS
SEPARATION PROCESSES
SPENT FUELS
STABILITY
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES