Analysis of design changes and modifications to enhance safety margins at KANUPP - a PAEC/NSS team effort
Creators
- 1. Pakistan Atomic Energy Commission, Islamabad (Pakistan)
- 2. Nuclear Safety Solutions Ltd., Toronto, Ontario (Canada)
Description
Accident analysis for revision of the Karachi Nuclear Power Plant Final Safety Analysis Report has been completed by a cooperative effort between the Pakistan Atomic Energy Commission and Nuclear Safety Solutions. The revision was created to assess design changes and modifications which had been implemented in the plant to support life extension and enhance safety margins. The enhancements were primarily related to safety system response following loss of coolant accident scenarios. In addition, the revision of the safety report included updates to two dual failure accident sections, loss of coolant coincident with loss of emergency injection water, and loss of reactivity control coincident with loss of protection, which had been a part of the original safety report. The paper provides an overview of the design changes which have been implemented and a summary of the updated safety analysis. The new analysis supports full power operation. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-88-7
- Imprint Title
- Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference
- Imprint Pagination
- 303 Megabytes
- Journal Page Range
- [20 p.]
Conference
- Title
- Canada's nuclear renewal and growth
- Acronym
- 28. Annual conference of the Canadian Nuclear Society and 31. CNS/CNA student conference on embracing the future
- Dates
- 3-6 Jun 2007
- Place
- Saint John, New Brunswick (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 38107404
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- KANUPP REACTOR; LIFETIME EXTENSION; LOSS OF COOLANT; REACTOR SAFETY; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; CANDU TYPE REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; LIFETIME; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SERVICE LIFE; THERMAL REACTORS
Optional Information
- Notes
- Paper T1008; 3 tabs., 4 figs.