Published 1982
| Version v1
Book
A probabilistic analysis of LWR steam explosions
Description
In this paper, we present a probabilistic assessment of containment failure due to an in-vessel explosion following a core melt accident in a Light Water Reactor. We limit our assumptions to the most basic physical parameters of the core melt accident and describe these parameters with frequency distributions. A Monte Carlo solution technique is used to calculate output frequency distributions for steam explosion energy, reactor vessel response, and resulting missile velocities. Based on current results, we estimate the probability of containment failure due solely to an in-vessel steam explosion to be one to two orders of magnitude smaller than the probability calculated in the Reactor Safety Study (WASH-1400)
Additional details
Publishing Information
- Publisher
- American Nuclear Society, Inc.
- Imprint Place
- La Grange Park, IL
- Imprint Title
- Probabilistic risk assessment
- Journal Page Range
- p. 293-302.
Conference
- Title
- ANS/ENS topical meeting on probabilistic risk assessment.
- Dates
- 20-24 Sep 1981.
- Place
- Port Chester, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14783487
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; FAILURES; MATHEMATICAL MODELS; MELTDOWN; MONTE CARLO METHOD; PRESSURE GRADIENTS; PROBABILITY; PWR TYPE REACTORS; REACTOR SAFETY; REACTOR VESSELS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTAINMENT; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS