Aspects of zircaloy core materials for advanced LWRs
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6883714
Zircaloy has been successfully used as the primary light water reactor (LWR) core structural material since its introduction in the early days of the US naval nuclear program. Its unique combination of low neutron absorption cross section, fabricability, mechanical strength, and corrosion resistance in high-temperature water has resulted in remarkable reliability of operation of pressurized and boiling water reactor (PWR, BWR) fuel through the years. Currently, BWRs use Zircaloy-2 for fuel cladding and Zircaloy-4 for channels and spacers, while PWRs use Zircaloy-4 for fuel cladding, spacer grids, and control rod guide tubes. As required fluences continue to increase and as a more statistically significant number of components reach ultra-high burnups, however, Zircaloy as a material is liable to be pushed to its operating limits. This paper discusses those areas to which fuel vendors are giving attention; e.g., microstructure, corrosion, irradiation growth and creep, and mechanical properties.
- OSTI ID:
- 6883714
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- 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
ALLOYS
BWR TYPE REACTORS
CORROSION RESISTANCE
CREEP
CRYSTAL STRUCTURE
DEFORMATION
FABRICATION
FUEL CANS
MATERIALS
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MICROSTRUCTURE
PERFORMANCE
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTORS
SUPPORTS
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
ALLOYS
BWR TYPE REACTORS
CORROSION RESISTANCE
CREEP
CRYSTAL STRUCTURE
DEFORMATION
FABRICATION
FUEL CANS
MATERIALS
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MICROSTRUCTURE
PERFORMANCE
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTORS
SUPPORTS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS