Zircaloy-4 cladding deformation during power reactor irradiation
Conference
·
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
OSTI ID:6461018
Axial elongation, circumferential creep, ovalization and ridging in Zircaloy fuel cladding were investigated for fuel irradiated in four modern PWR's. For fueled rods, only fluence and stress were found to influence elongation, while for nonfueled rods the texture was also important. Time and flux had weaker than linear influence on circumferential creep strain in nonfueled rods, while the influence of the stress was stronger than linear. The strain rate was almost athermal. The creep strain clearly increased with preirradiation yield strength. The creep rate decreased with an increase in the angle between the basal poles and the radial direction. Ovalization of fueled and nonfueled rods was observed. Clad ridging developed in fueled rods, usually in a time period between one and two reactor cycles and almost always after three cycles. 29 refs.
- Research Organization:
- EPRI, Palo Alto, CA, USA
- OSTI ID:
- 6461018
- Report Number(s):
- CONF-800834-
- Conference Information:
- Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
- Country of Publication:
- United States
- Language:
- English
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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
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
BWR TYPE REACTORS
CREEP
DEFORMATION
FUEL CANS
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
MATHEMATICS
MECHANICAL PROPERTIES
PELLETS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
REGRESSION ANALYSIS
STATISTICS
STRAINS
TIN ALLOYS
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
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
BWR TYPE REACTORS
CREEP
DEFORMATION
FUEL CANS
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
MATHEMATICS
MECHANICAL PROPERTIES
PELLETS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
REGRESSION ANALYSIS
STATISTICS
STRAINS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS