Pellet-cladding interaction phenomenon. [BWR; PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7328711
- Electric Power Research Inst., Palo Alto, CA
None
- OSTI ID:
- 7328711
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 24
- Country of Publication:
- United States
- Language:
- English
Similar Records
Theoretical analysis of pellet--cladding mechanical interaction. [PWR; BWR]
Pellet-cladding interaction phenomena in unirradiated and irradiated PWR fuel rods
Effects of annealing on irradiated spent-fuel cladding. [BWR; PWR]
Conference
·
Sat Dec 31 23:00:00 EST 1977
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6529565
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)
·
OSTI ID:5354626
Effects of annealing on irradiated spent-fuel cladding. [BWR; PWR]
Conference
·
Sat Dec 31 23:00:00 EST 1977
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6528714
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
BWR TYPE REACTORS
FUEL ELEMENT FAILURE
FUEL-CLADDING INTERACTIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
FUEL ELEMENT FAILURE
FUEL-CLADDING INTERACTIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS