Published January 1996
| Version v1
Journal article
Generic validation of computer codes for safety analyses of CANDU power plants
- 1. Atomic Energy of Canada Ltd., Chalk River, ON (Canada)
- 2. Ontario Hydro, Toronto, ON (Canada)
- 3. Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.
- 4. Hydro-Quebec, Montreal, PQ (Canada)
- 5. New Brunswick Power (Canada). Point Lepreau Generating Station
Description
Since the 1960s, the CANDU industry has been developing and using scientific computer codes, validated according to the quality-assurance practices of the day, for designing and analyzing CANDU power plants. To provide a systematic framework for the validation work done to date and planned for the future, the industry has decided to adopt the methodology of validation matrices, similar to that developed by the Nuclear Energy Agency of the Organization for Economic Co-operation and Development for Light Water Reactors (LWR). Specialists in six scientific disciplines are developing the matrices for CANDU plants, and their progress to date is presented. (author) 1 ref., 5 tabs., 1 fig
Additional details
Publishing Information
- Journal Title
- Canadian Nuclear Society Bulletin
- Journal Volume
- 17
- Journal Issue
- 2
- Journal Page Range
- p. 23-29.
- ISSN
- 0714-7074
- CODEN
- BCSCEP
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 28005760
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTER CODES; MATRICES; SAFETY ANALYSIS; VALIDATION
- Descriptors DEC
- HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; TESTING; THERMAL REACTORS