Interim report on whole rod testing
Work has only been conducted on a limited inventory of irradiated rods made by Westinghouse for the Turkey Point Unit 3. The measured cladding strain was sufficiently large so that failure mechanism verification by inducing breaches in intact unmodified fuel rods at elevated temperatures in short periods of time does not appear to be practical. While stress-rupture has not been completely eliminated as a failure mechanism, for temperatures where the irradiation damage is annealed, Blackburn's recipe appears to give a very conservative estimate of breach times. The fuel apparently exhibited no additional gas release or axial fission product migration at 900/sup 0/F. The NDE gave no indication of deterioration of the fuel rod condition. 5 figures.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC14-76FF02170
- OSTI ID:
- 6781154
- Report Number(s):
- HEDL-6776
- 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
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HIGH TEMPERATURE
INSPECTION
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SPENT FUEL ELEMENTS
STRAINS
TESTING
THERMAL REACTORS
TURKEY POINT-3 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HIGH TEMPERATURE
INSPECTION
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SPENT FUEL ELEMENTS
STRAINS
TESTING
THERMAL REACTORS
TURKEY POINT-3 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS