Results of the AP600 advanced plant probabilistic risk assessment
Creators
- 1. Westinghouse Electric Corp., Monroeville, PA (United States)
Description
The AP600 Probabilistic Risk Assessment (PRA) includes detailed models of the plant systems, including the containment and containment systems that would be used to mitigate the consequences of a severe accident. The AP600 PRA includes a level 1 analysis (core damage frequency), and a level 2 analysis (environmental consequences), an assessment of the plant vulnerability to accidents caused by fire or floods, and a seismic margins analysis. Numerous sensitivities are included in the AP600 PRA including one that assumes no credit for non-safety plant systems. The core damage frequency for the AP600 of 1.7E-07/year is small compared with other PRAs performed in the nuclear industry. The AP600 large release frequency of 1.8E-08/year is also small and shows the ability of the containment systems to prevent a large release should a severe accident occur. Analyses of potential consequences to the environment from a severe accident show that a release would be small, and that containment still provides significant protection 24 hours after an assumed accident. Sensitivity analyses show that plant risk (as measured by core damage frequency and large release frequency) is not sensitive to the reliability of operator actions. 6 refs., 1 fig., 1 tab
Additional details
Publishing Information
- Publisher
- American Nuclear Society, Inc.
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Title
- Proceedings of the international topical meeting on advanced reactors safety: Volume 2
- Imprint Pagination
- 715 p.
- Journal Page Range
- p. 838-845.
Conference
- Title
- American Nuclear Society (ANS) international meeting on advanced reactors safety.
- Acronym
- ARS '97
- Dates
- 1-5 Jun 1997.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29021560
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- REACTOR ACCIDENTS; RISK ASSESSMENT; SENSITIVITY ANALYSIS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; REACTORS
Optional Information
- Secondary number(s)
- CONF-970607--Vol.2.