Published February 1985 | Version v1
Report

Containment performance for core melt accidents in BWRs with Mark I and Mark II containments

  • 1. Brookhaven National Lab., Upton, NY

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).