Interim results from UO/sub 2/ fuel oxidation tests in air
An experimental program is being conducted at Pacific Northwest Laboratory (PNL) to extend the characterization of spent fuel oxidation in air. To characterize oxidation behavior of irradiated UO/sub 2/, fuel oxidation tests were performed on declad light-water reactor spent fuel and nonirradited UO/sub 2/ pellets in the temperature range of 135 to 250/sup 0/C. These tests were designed to determine the important independent variables that might affect spent fuel oxidation behavior. The data from this program, when combined with the test results from other programs, will be used to develop recommended spent fuel dry-storage temperature limits in air. This report describes interim test results. The initial PNL investigations of nonirradiated and spent fuels identified the important testing variables as temperature, fuel burnup, radiolysis of the air, fuel microstructure, and moisture in the air. Based on these initial results, a more extensive statistically designed test matrix was developed to study the effects of temperature, burnup, and moisture on the oxidation behavior of spent fuel. Oxidation tests were initiated using both boiling-water reactor and pressurized-water reactor fuels from several different reactors with burnups from 8 to 34 GWd/MTU. A 10/sup 5/ R/h gamma field was applied to the test ovens to simulate dry storage cask conditions. Nonirradiated fuel was included as a control. This report describes experimental results from the initial tests on both the spent and nonirradiated fuels and results to date on the tests in a 10/sup 5/ R/h gamma field. 33 refs., 51 figs., 6 tabs.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6153707
- Report Number(s):
- PNL-6201; ON: DE88000250
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
AIR
BURNUP
BWR TYPE REACTORS
CHALCOGENIDES
CHEMICAL REACTIONS
DATA
DRY STORAGE
ENERGY SOURCES
EXPERIMENTAL DATA
FLUIDS
FUELS
GASES
HIGH TEMPERATURE
INFORMATION
MATERIALS
MOISTURE
NUCLEAR FUELS
NUMERICAL DATA
OXIDATION
OXIDES
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
RECOMMENDATIONS
SPENT FUEL STORAGE
SPENT FUELS
STORAGE
TEMPERATURE EFFECTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
AIR
BURNUP
BWR TYPE REACTORS
CHALCOGENIDES
CHEMICAL REACTIONS
DATA
DRY STORAGE
ENERGY SOURCES
EXPERIMENTAL DATA
FLUIDS
FUELS
GASES
HIGH TEMPERATURE
INFORMATION
MATERIALS
MOISTURE
NUCLEAR FUELS
NUMERICAL DATA
OXIDATION
OXIDES
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
RECOMMENDATIONS
SPENT FUEL STORAGE
SPENT FUELS
STORAGE
TEMPERATURE EFFECTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS