Published 1997 | Version v1
Book

Results of the AP600 advanced plant probabilistic risk assessment

  • 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.