Effects of stress biaxiality on ballooning behavior of Zircaloy cladding. [PWR, BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5287552
None
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 5287552
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 27
- Country of Publication:
- United States
- Language:
- English
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Sun Dec 31 23:00:00 EST 1978
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·
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
DEFORMATION
ELASTICITY
FUEL CANS
FUEL ELEMENT FAILURE
MECHANICAL PROPERTIES
PRESSURE DEPENDENCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRAINS
STRESSES
TENSILE PROPERTIES
THERMOELASTICITY
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
DEFORMATION
ELASTICITY
FUEL CANS
FUEL ELEMENT FAILURE
MECHANICAL PROPERTIES
PRESSURE DEPENDENCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRAINS
STRESSES
TENSILE PROPERTIES
THERMOELASTICITY
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS