High-temperature deformation and burst characteristics of recrystallized Zircaloy-4 tubing (LWBR Development Program)
Technical Report
·
OSTI ID:7010646
Internal pressure burst tests of unirradiated, recrystallized Zircaloy-4 tubing were performed at isothermal temperatures ranging from 80/sup 0/ to approximately 1900/sup 0/F to assess deformation characteristics before fracture. It was concluded that significant local deformation (bulging) could occur. It is also shown that a reasonable estimate of flow stress under combined stress loading can be obtained from uniaxial tensile data and a strain parameter (R) measured from the contractile strains observed in tensile tests. (NSA 24: 17261)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AT(11-1)-GEN-14
- OSTI ID:
- 7010646
- Report Number(s):
- WAPD-TM-900
- Country of Publication:
- United States
- Language:
- English
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THERMAL REACTORS
THERMAL STRESSES
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WATER COOLED REACTORS
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