Deformation and collapse of fuel rod cladding due to external pressure (LWBR Development Program)

Technical Report · Sun Jan 01 04:00:00 EST 1967

OSTI ID:7098779

Griffin, D S

Approximate methods are given for analyzing the effects of external pressure on Zircaloy fuel rod cladding. The structural behavior of the clad is idealized to be independent of the behavior of the fuel. Phenomena considered include inelastic and creep collapse, inelastic deformation (ovality), diametral shrinkage, dimpling, and axial wrinkling. Comparisons with experimental results are given where available. (NSA 21: 28761)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 7098779
• Report Number(s): WAPD-TM-591
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ALLOYS
BREEDER REACTORS
CREEP
DEFORMATION
FUEL CANS
LWBR TYPE REACTORS
MECHANICAL PROPERTIES
PRESSURE GRADIENTS
REACTORS
THERMAL REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS