Identification and assessment of containment and release management strategies for a BWR Mark I containment
Creators
- 1. Brookhaven National Lab., Upton, NY (United States)
Description
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
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI92000521; NTIS; INIS; GPO.Files
23011299.pdf
Files
(15.4 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 208 p.
- Report number
- NUREG/CR--5634
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23011299
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT; CONTAINMENT SYSTEMS; EMERGENCY PLANS; FAILURE MODE ANALYSIS; FAILURES; FISSION PRODUCT RELEASE; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MANAGEMENT; MITIGATION; PROBABILISTIC ESTIMATION; REACTOR CORE DISRUPTION; REACTOR SAFETY; RISK ASSESSMENT; SYSTEMS ANALYSIS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC02-76CH00016
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- BNL-NUREG--52259.