Analysis of the transient capability of rod-type fuel elements (LWBR Development Program)
Technical Report
·
OSTI ID:6742118
The capability of a bulk-oxide, rod-type fuel element to sustain a series of up-power transients that induces high strain rate in the cladding has been evaluated by comparing peak clad stresses and strains calculated by the CYGRO computer program with a set of stress-strain limits used for this evaluation. The generalized data of depletion capability developed therein are useful in determining fuel rod performance capability for a wide range of geometries and operating conditions, without having to run specific CYGRO calculations for each fuel element. (NSA 25: 11534)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AT(11-1)-GEN-14
- OSTI ID:
- 6742118
- Report Number(s):
- WAPD-TM-979
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
LWBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE
REACTOR COMPONENTS
REACTORS
STRESS ANALYSIS
THERMAL REACTORS
TRANSIENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500* -- Power Reactors
Breeding
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
LWBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE
REACTOR COMPONENTS
REACTORS
STRESS ANALYSIS
THERMAL REACTORS
TRANSIENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS