Comparison of dimensional changes in fuel rods with predictions under cyclic conditions of power and system pressure (LWBR Development Program)
Technical Report
·
OSTI ID:6742153
The various additions to the CYGRO fuel rod analysis technique in order to calculate ratchetting effects are described. These effects include fuel cracking, clad collapse, friction between fuel and clad, clad anisotropy, and effects of neutron flux on clad creep. By reasonable choice of parameters good agreement can be obtained with tests on axial elongations of non-free-standing fuel rods. There is a pronounced sensitivity of these predictions to the value of creep enhancement as a result of neutron flux. Predictions of diameter changes are believed to be inherently less accurate because of the masking effects of ridging, wrinkling, and clad collapse. (NSA 24: 21446)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AT(11-1)-GEN-14
- OSTI ID:
- 6742153
- Report Number(s):
- WAPD-TM-940
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CREEP
DEFORMATION
FUEL ELEMENTS
FUEL RODS
LWBR TYPE REACTORS
MECHANICAL PROPERTIES
PERFORMANCE
PRESSURE GRADIENTS
RATCHETING
REACTOR COMPONENTS
REACTORS
STRESSES
THERMAL REACTORS
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CREEP
DEFORMATION
FUEL ELEMENTS
FUEL RODS
LWBR TYPE REACTORS
MECHANICAL PROPERTIES
PERFORMANCE
PRESSURE GRADIENTS
RATCHETING
REACTOR COMPONENTS
REACTORS
STRESSES
THERMAL REACTORS
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS