Behavior of four PWR rods subjected to a simulated loss-of-coolant accident in the power burst facility
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6525159
None
- Research Organization:
- EG and G Idaho, Idaho Falls
- OSTI ID:
- 6525159
- 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
Behavior of four PWR rods subjected to a simulated loss-of-coolant accient in the power burst facility
Effects of containment purge on the consequences of a loss-of-coolant accident. [PWR]
Frequency and consequences of small loss-of-coolant accidents. [PWR; BWR]
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6526054
Effects of containment purge on the consequences of a loss-of-coolant accident. [PWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6877322
Frequency and consequences of small loss-of-coolant accidents. [PWR; BWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6595382
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
DEFORMATION
FUEL CANS
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
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
DEFORMATION
FUEL CANS
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS