Evaluation of core damage sequences initiated by loss of reactor coolant pump seal cooling
This report is concerned with core damage accident sequences initiated by loss of component cooling water, leading to loss of reactor coolant pump seal cooling, subsequent primary coolant leakage, and failure to make up the coolant loss. Three plants are considered: Indian Point Unit 3, Midland Unit 2, and Calvert Cliffs Unit 1. It is shown that design differences in the overall seal cooling support systems are responsible for considerable variation in the likelihood of, and plant response to, loss of component cooling.
- Research Organization:
- Impell Corp., Melville, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5407931
- Report Number(s):
- NUREG/CR-4643; BNL-NUREG-52003; ON: TI86015186
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
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REACTOR OPERATION
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ACCIDENTS
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DAMAGE
ENERGY SYSTEMS
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ENRICHED URANIUM REACTORS
EVALUATION
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INDIAN POINT-3 REACTOR
LOSS OF COOLANT
MECHANICS
MIDLAND-2 REACTOR
OPERATION
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PROCESS HEAT REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTOR OPERATION
REACTORS
SEALS
WATER COOLED REACTORS
WATER MODERATED REACTORS