Measurement of the oxidation of spent fuel between 140/degree/ and 225/degree/C by thermogravimetric analysis
A series of PWR spent fuel samples from Turkey Point Unit 3 have been oxidized at temperatures between 140/degree/ and 225/degree/C in air atmospheres with dew points between 14.5/degree/ and /minus/70/degree/C, using a thermogravimetric analysis system (TGA). Tests lasted between 400 and 2100 hours. At the conclusion of a test, the atmosphere was sampled to determine the release of fission gas during testing, and the fuel samples were analyzed for microstructural changes. It appears that the mechanism for oxidation of spent fuel to U/sub 3/O/sub 7/ takes place in two steps that occur somewhat simultaneously. Oxygen migrates along the grain boundaries, which are oxidized and enlarged. The grains oxidize by the inward progression of a layer of U/sub 4/O/sub 9/ saturated with oxygen. A simplified model of the mechanism, which considers oxygen diffusion through the product layer as the rate-controlling step, yields an activation energy of 27 /plus minus/ 4 kcal/mol. Moisture, between dew points of /minus/70/degree/ to +14.5/degree/C, i.e., water vapor partial pressures varying over four orders of magnitude, had no significant effect on the oxidation rate. 34 refs., 12 figs., 6 tabs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 6676540
- Report Number(s):
- WHC-EP-0107; ON: DE89003016
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Oxidation of spent fuel in air at 175 degree to 195 degree C
Oxidation of spent fuel in air at 175{degree} to 195{degree}C
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
OXIDATION
THERMAL GRAVIMETRIC ANALYSIS
RADIOACTIVE WASTE STORAGE
SPENT FUELS
TURKEY POINT-3 REACTOR
CHEMICAL REACTION KINETICS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
GRAIN BOUNDARIES
MEASURING METHODS
MICROSTRUCTURE
PWR TYPE REACTORS
REGULATIONS
TEMPERATURE EFFECTS
TESTING
URANIUM OXIDES
ACTINIDE COMPOUNDS
CHALCOGENIDES
CHEMICAL ANALYSIS
CHEMICAL REACTIONS
CRYSTAL STRUCTURE
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUELS
GRAVIMETRIC ANALYSIS
KINETICS
MANAGEMENT
MATERIALS
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
POWER REACTORS
QUANTITATIVE CHEMICAL ANALYSIS
REACTION KINETICS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
STORAGE
THERMAL ANALYSIS
THERMAL REACTORS
URANIUM COMPOUNDS
WASTE MANAGEMENT
WASTE STORAGE
WATER COOLED REACTORS
WATER MODERATED REACTORS
052002* - Nuclear Fuels- Waste Disposal & Storage
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
400700 - Radiochemistry & Nuclear Chemistry