Analysis of cladding deformation over plenum axial gaps in Zircaloy-clad fuel rods. LWBR Development Program
An analytical model has been developed to predict deformation of unirradiated Zircaloy cladding over axial gaps in plenum regions of fuel rods. This model uses the ACCEPT finite element computer program to calculate the elastic-plastic deformation of cladding due to net external pressure. Progressive increase in gap length (from elongation of cladding below the gap due to Zircaloy growth and pellet-cladding interaction induced creep and from fuel stack shrinkage due to densification of fuel pellets) and deformations of fuel pellets and support sleeve which bound the axial gap in LWBR type blanket fuel rods are included in the model. The thermal creep representation used is based on data from uniaxial creep testing of fuel rod tubing.
- Research Organization:
- Bettis Atomic Power Lab., West Mifflin, PA (USA)
- DOE Contract Number:
- AC11-76PN00014
- OSTI ID:
- 6504041
- Report Number(s):
- WAPD-TM-1339; ON: DE83006717
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210500* -- Power Reactors
Breeding
ALLOYS
BREEDER REACTORS
COMPUTER CALCULATIONS
CREEP
DEFORMATION
DYNAMIC LOADS
FUEL CANS
FUEL ELEMENTS
FUEL RODS
LWBR TYPE REACTORS
MECHANICAL PROPERTIES
REACTOR COMPONENTS
REACTORS
STRESSES
THERMAL REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS