Identification and assessment of containment and release management strategies for a BWR Mark I containment
- Brookhaven National Lab., Upton, NY (United States)
This report identifies and assesses accident management strategies which could be important for preventing containment failure and/or mitigating the release of fission products during a severe accident in a BWR plant with a Mark 1 type of containment. Based on information available from probabilistic risk assessments and other existing severe accident research, and using simplified containment and release event trees, the report identifies the challenges a Mark 1 containment could face during the course of a severe accident, the mechanisms behind these challenges, and the strategies that could be used to mitigate the challenges. A safety objective tree is developed which provides the connection between the safety objectives, the safety functions, the challenges, and the strategies. The strategies were assessed by applying them to certain severe accident sequence categories which have one or more of the following characteristics: have high probability of core damage or high consequences, lead to a number of challenges, and involve the failure of multiple systems. 59 refs., 55 figs., 27 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5070180
- Report Number(s):
- NUREG/CR-5634; BNL-NUREG-52259; ON: TI92000521
- Country of Publication:
- United States
- Language:
- English
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BWR TYPE REACTORS
CONTAINMENT SYSTEMS
FISSION PRODUCT RELEASE
LOSS OF COOLANT
REACTOR CORE DISRUPTION
EMERGENCY PLANS
CONTAINMENT
FAILURE MODE ANALYSIS
FAILURES
HEAT TRANSFER
HYDRAULICS
MANAGEMENT
MITIGATION
PROBABILISTIC ESTIMATION
REACTOR SAFETY
RISK ASSESSMENT
SYSTEMS ANALYSIS
ACCIDENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
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POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
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220502* - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
220900 - Nuclear Reactor Technology- Reactor Safety
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