Is Mark I shell failure really important? Pt. 2
Creators
- 1. New York Power Authority, White Plains, NY (USA)
- 2. Risk Management Associates, Albuquerque, NM (USA)
Description
This second part of a two part paper provides specific analyses performed on the reactor safety study's reference BWR, the Peach Bottom Plant. Source terms are provided for a series of station blackout accident sequences. In the base case, failure of the drywell is calculated to occur shortly after reactor vessel failure. The source terms associated with this sequence are in the few percent range for iodine, cesium, and tellurium. Because the containment failure occurs upon reactor vessel failure, this source term is expected to be equal to or larger than the source term that would be associated with shell failure. A sensitivity analysis was also performed to evaluate the benefits of extended use of the automatic depressurization system in station blackout sequences. Among the benefits of extended ADS operation are reduced source terms and a decreased probability of prompt containment failure when the reactor vessel fails. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 121
- Journal Issue
- 3
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 447-458
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- 16. water reactor safety information meeting (WRSM-16).
- Dates
- 24-28 Oct 1988.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 22009767
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUTOMATION; BWR TYPE REACTORS; CONTAINMENT BUILDINGS; DEPRESSURIZATION SYSTEMS; FAILURES; FISSION PRODUCT RELEASE; MELTDOWN; OUTAGES; PEACH BOTTOM-1 REACTOR; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; SOURCE TERMS
- Descriptors DEC
- ACCIDENTS; BUILDINGS; CONTAINMENT; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS