Pellet-cladding interaction phenomena in unirradiated and irradiated PWR fuel rods
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5354626
None
- Research Organization:
- EG and G Idaho Co., Idaho Falls
- OSTI ID:
- 5354626
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 27
- Country of Publication:
- United States
- Language:
- English
Similar Records
Pellet-cladding interaction phenomenon. [BWR; PWR]
Observation of pellet/cladding interaction defects in Dresden-3 fuel rods
Procedure for estimating the effect of fuel-pellet chips on the promotion of localized stresses in fuel rod cladding. [PWR]
Conference
·
Sun Oct 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7328711
Observation of pellet/cladding interaction defects in Dresden-3 fuel rods
Conference
·
Thu Jun 01 00:00:00 EDT 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7041233
Procedure for estimating the effect of fuel-pellet chips on the promotion of localized stresses in fuel rod cladding. [PWR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5357866
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS