Theoretical analysis of pellet--cladding mechanical interaction. [PWR; BWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6529565
- Argonne National Lab., IL
None
- OSTI ID:
- 6529565
- Report Number(s):
- CONF-7811109-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 30
- Country of Publication:
- United States
- Language:
- English
Similar Records
Pellet-cladding interaction phenomenon. [BWR; PWR]
Mechanical analysis of the dilatation-induced pellet-cladding interaction
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Sun Oct 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
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OSTI ID:7328711
Mechanical analysis of the dilatation-induced pellet-cladding interaction
Conference
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Wed Jun 01 00:00:00 EDT 1977
· Trans. Am. Nucl. Soc.; (United States)
·
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Pellet-cladding interaction phenomena in unirradiated and irradiated PWR fuel rods
Conference
·
Fri Dec 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
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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
BWR TYPE REACTORS
FUEL CANS
FUEL PELLETS
FUEL-CLADDING INTERACTIONS
PELLETS
PWR TYPE REACTORS
REACTORS
STRAINS
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
FUEL CANS
FUEL PELLETS
FUEL-CLADDING INTERACTIONS
PELLETS
PWR TYPE REACTORS
REACTORS
STRAINS
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS