Results of simulated abnormal heating events for full-length nuclear fuel rods
Full-length nuclear fuel rods were tested in a furnace to simulate the slow heating rates postulated for commercial pressurized water reactor fuel rods exposed to an overheating event in a storage cask. Fuel rod temperatures and internal gas pressures were monitored during the test and are presented along with mensural data for cladding. Metallography of the cladding provided data on grain growth, hydriding, oxidation, cladding stresses, and the general nature of the failures.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6400890
- Report Number(s):
- PNL-4555; ON: DE83007866
- Resource Relation:
- Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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FUEL RODS
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TEMPERATURE EFFECTS
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EXPERIMENTAL DATA
FIRES
METALLOGRAPHY
PWR TYPE REACTORS
SPENT FUEL CASKS
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL RODS
FAILURES
TEMPERATURE EFFECTS
DEFORMATION
EXPERIMENTAL DATA
FIRES
METALLOGRAPHY
PWR TYPE REACTORS
SPENT FUEL CASKS
SPENT FUEL STORAGE
CASKS
CONTAINERS
DATA
FUEL ELEMENTS
INFORMATION
NUMERICAL DATA
REACTOR COMPONENTS
REACTORS
STORAGE
WATER COOLED REACTORS
WATER MODERATED REACTORS
050900* - Nuclear Fuels- Transport
Handling
& Storage
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
054000 - Nuclear Fuels- Health & Safety