Analysis of cladding deformation over plenum axial gaps in Zircaloy-clad fuel rods. LWBR Development Program

Technical Report · Wed Dec 01 04:00:00 EST 1982

OSTI ID:6504041

Gorscak, D A; Pfennigwerth, P L

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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BREEDER REACTORS
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DEFORMATION
DYNAMIC LOADS
FUEL CANS
FUEL ELEMENTS
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MECHANICAL PROPERTIES
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