Risk impact of two accident management strategies
Conference
·
OSTI ID:10121407
This report probabilistic Risk Assessment is used to evaluate two accident management strategies: intentionally depressurizing the reactor coolant system of a pressurized water reactor to prevent containment-pressurization during high pressure melt ejection, and flooding the containment of a boiling water reactor to prevent or delay vessel breach. Sensitivity studies indicated that intentional depressurization would not provide a significant risk reduction at Surry. A preliminary evaluation of the containment flooding strategy indicated that it might prove beneficial for some plants, but that further strategy development would be needed to fully evaluate the strategy-
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 10121407
- Report Number(s):
- SAND--92-1808C; CONF-921007--15; ON: DE93005376
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
CONTAINMENT
DEPRESSURIZATION
HEAT TRANSFER
HYDRAULICS
MANAGEMENT
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
RISK ASSESSMENT
SENSITIVITY ANALYSIS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
CONTAINMENT
DEPRESSURIZATION
HEAT TRANSFER
HYDRAULICS
MANAGEMENT
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
RISK ASSESSMENT
SENSITIVITY ANALYSIS