Effect of temperature nonuniformity on the diametral expansion of internally pressurized Zircaloy-4 cladding during transient heating in steam. [BWR, PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5289403
None
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 5289403
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 27
- Country of Publication:
- United States
- Language:
- English
Similar Records
Effects of stress biaxiality on ballooning behavior of Zircaloy cladding. [PWR, BWR]
The steam oxidation of Zircaloy-4 during temperature transients
Prediction of critical heat flux during flow transients. [PWR; BWR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5287552
The steam oxidation of Zircaloy-4 during temperature transients
Conference
·
· TMS (The Metallurgical Society) Paper Selection; (USA)
·
OSTI ID:5365208
Prediction of critical heat flux during flow transients. [PWR; BWR]
Conference
·
Sun Dec 31 23:00:00 EST 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5284519
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
ALLOYS
BWR TYPE REACTORS
DEFORMATION
ELASTICITY
EXPANSION
FUEL CANS
MECHANICAL PROPERTIES
PWR TYPE REACTORS
REACTORS
STEAM
STRAINS
STRESSES
TEMPERATURE DEPENDENCE
TEMPERATURE GRADIENTS
TENSILE PROPERTIES
THERMAL STRESSES
THERMOELASTICITY
TIN ALLOYS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
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
ALLOYS
BWR TYPE REACTORS
DEFORMATION
ELASTICITY
EXPANSION
FUEL CANS
MECHANICAL PROPERTIES
PWR TYPE REACTORS
REACTORS
STEAM
STRAINS
STRESSES
TEMPERATURE DEPENDENCE
TEMPERATURE GRADIENTS
TENSILE PROPERTIES
THERMAL STRESSES
THERMOELASTICITY
TIN ALLOYS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS