Containment performance for core melt accidents in BWRs with Mark I and Mark II containments
Description
Most previous risk assessment studies have assumed catastrophic failure of containments for severe accidents which are predicted to exceed the containment yield stress. This investigation analyzes the progression of a severe accident in order to develop realistic containment temperature and pressure loading, utilizes models for containment leakage estimates for the various loading histories, and assesses the expected failure modes and timing of releases for core melt accidents in Boiling Water Reactors (BWRs) with Mark I and Mark II containments. The results of the investigation indicate that leakage through the seal on the drywell head may be sufficient to prevent catastrophic failure of the containments for a wide range of hypothetical core melt scenarios. In addition, the investigation had indicated the potential for a previously unidentified failure mode (containment liner melt through) for Mark I containments in which a large fraction of the core is released from the vessel in a molten state
Additional details
Publishing Information
- Imprint Title
- International topical meeting on probabilistic safety methods and applications: proceedings. Volume 2. Sessions 9-16
- Journal Page Range
- p. 119.1-119.12.
- Report number
- EPRI-NP--3912-SR-Vol.2
Conference
- Title
- International ANS/ENS topical meeting on probabilistic safety methods and applications.
- Dates
- 24 Feb - 1 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023391
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; CORIUM; FAILURES; FISSION PRODUCT RELEASE; LINERS; LOSS OF COOLANT; MELTDOWN; PERFORMANCE; PRESSURE VESSELS; PRESSURIZATION; PROBABILITY; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR SAFETY; RISK ASSESSMENT; SEALS; SENSITIVITY ANALYSIS; THERMAL STRESSES; US NRC
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTAINMENT; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; STRESSES; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS