Seal loss-of-coolant accident and recovery actions following loss of component cooling water
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5986073
A model for the potential reactor coolant pump seal loss-of-coolant accident in a Westinghouse Electric Corporation pressurized water reactor following a loss of component cooling water (CCW) is developed based on state-of-the-art knowledge. The potential operator recovery actions in coping with a loss-of-CCW event are investigated, and an event tree is constructed to describe the possible core melt sequences. The sequence frequencies are plant specific; however, evaluations (of the sequence frequencies) demonstrate that an emergency operating procedure that clearly identifies possible recovery actions can reduce the core melt probability by two orders of magnitude.
- Research Organization:
- Atomic Energy Council, Taipei (TW)
- OSTI ID:
- 5986073
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 84:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
COOLANT LOOPS
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LOSS OF COOLANT
PWR TYPE REACTORS
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REACTOR COMPONENTS
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WATER MODERATED REACTORS