Analyses of precooling parameters for water reactor emergency core cooling
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7351849
- Brookhaven National Lab., Upton, NY
- OSTI ID:
- 7351849
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 23; Conference: Transactions of the American Nuclear Society 1976 annual meeting, Toronto, Canada, 13 Jun 1976
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CORE FLOODING SYSTEMS
HEAT TRANSFER
PWR TYPE REACTORS
ECCS
FLUID FLOW
LOSS OF FLOW
ACCIDENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
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Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CORE FLOODING SYSTEMS
HEAT TRANSFER
PWR TYPE REACTORS
ECCS
FLUID FLOW
LOSS OF FLOW
ACCIDENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled