Best-judgment analysis of emergency core cooling system performance. [PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7353696
None
- Research Organization:
- Combustion Engineering, Inc., Windsor, CT
- OSTI ID:
- 7353696
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 23
- Country of Publication:
- United States
- Language:
- English
Similar Records
Best-judgment analysis of emergency core cooling system performance. [PWR]
An analysis of a feed-and-bleed mode of PWR emergency core cooling
General Electric's realistic approach for emergency core cooling system analysis
Journal Article
·
Fri Jul 01 00:00:00 EDT 1977
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·
OSTI ID:7306554
An analysis of a feed-and-bleed mode of PWR emergency core cooling
Conference
·
Sat Oct 01 00:00:00 EDT 1983
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5094589
General Electric's realistic approach for emergency core cooling system analysis
Conference
·
Thu Dec 31 23:00:00 EST 1981
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5952846
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
ECCS
ENGINEERED SAFETY SYSTEMS
LOSS OF COOLANT
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
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
ECCS
ENGINEERED SAFETY SYSTEMS
LOSS OF COOLANT
PERFORMANCE
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS