Published 1998 | Version v1
Book

Severe core damage frequency and insights from CANDU 6 level 1 probabilistic safety assessment

  • 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, Canada
Part of:
Proceedings of the 11th Pacific Basin Nuclear Conference

Additional 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)

Optional Information

Notes
5 refs.,3 tabs.,3 figs.