Effect of delayed reactor coolant pump trip during small-break LOCAs. [PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6595123
None
- Research Organization:
- W-NES, Pittsburgh, PA
- OSTI ID:
- 6595123
- Report Number(s):
- CONF-800607-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 34
- Country of Publication:
- United States
- Language:
- English
Similar Records
RC pump trip and small-break LOCA
Small-break LOCA studies of a PWR
Numerical simulation of PWR response to a small break LOCA (loss-of-coolant accident) with reactor coolant pumps operating
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6612589
Small-break LOCA studies of a PWR
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6661295
Numerical simulation of PWR response to a small break LOCA (loss-of-coolant accident) with reactor coolant pumps operating
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:6839251
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FLOW RATE
FLUID MECHANICS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PERFORMANCE
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PWR TYPE REACTORS
REACTOR ACCIDENTS
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
FLOW RATE
FLUID MECHANICS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PERFORMANCE
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS