Severe core damage frequency and insights from CANDU 6 level 1 probabilistic safety assessment
Creators
- 1. Atomic Energy of Canada Limited (Canada)
- 2. Spectrum Consulting Inc. (Canada)
Description
An internal events Level 1 probabilistic safety assessment (PSA) of a CANDU 6 nuclear power plant (NPP) was conducted by AECL and KAERI, with Wolsong NPP 2/3/4 in Korea taken as the reference plant. Wolsong NPP 2/3/4 is an enhanced design of Wolsong NPP Unit 1, which has been operating successfully since 1983. The reference plant has a number of safety and design improvements compared to Wolsong NPP 1. Based on the PSA, the summed severe core damage frequency for Wolsong NPP 2/3/4 is estimated to be 6.1E-6 events per year for internal events. Initiating events that dominate the severe core damage frequency are loss of Class 1V electrical power, dual digital computer control failure, loss of end shield cooling and loss of service water. They contribute 24%, 17%, 16% and 12% respectively to the summed severe core damage frequency. The results of this PSA confirm a low severe core damage frequency. (author)
Availability note (English)
Available from Canadian Nuclear Society, 144 Front Street, Suite 475, Toronto, ON M5J 2L7, CanadaAdditional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, ON (Canada)
- ISBN
- 0-919784-57-7
- Imprint Title
- Proceedings of the 11th Pacific Basin Nuclear Conference
- Imprint Pagination
- 2 v.
- Journal Page Range
- v. 2 p. 1051-1059
Conference
- Title
- 11. Pacific Basin Nuclear Conference. International Co-operation in the Pacific Rim for the 21st Century
- Dates
- 3-7 May 1998
- Place
- Banff, Alberta (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 32000316
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATOMIC ENERGY OF CANADA LTD; CANDU TYPE REACTORS; FAILURE MODE ANALYSIS; INTERNATIONAL COOPERATION; KAERI; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; CANADIAN ORGANIZATIONS; COOPERATION; HEAVY WATER MODERATED REACTORS; KOREAN ORGANIZATIONS; NATIONAL ORGANIZATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS
Optional Information
- Notes
- 5 refs.,3 tabs.,3 figs.