CANDU Fire Probabilistic Risk Assessment (PRA) Model
Description
Fire Probabilistic Risk Assessment (PRA) is being introduced to the fire protection engineering practice both locally and worldwide. The commercial nuclear power industry has also experiencing the impact of this new approach. This paper examines the work performed to assess the relative accuracy of fire models for CANDU nuclear power plant (NPP) applications. The Canadian NPP uses some portions of NUREG/CR-6850 in performing fire PRA. Canadian fire ignition frequencies have been provided by International Fire Data Exchange Project. The CANDU Fire PRA Model can quantitatively evaluate plant damage states and core damage frequencies. This model will assist fire engineers in performing CANDU Fire PRA analysis, by recognizing vulnerabilities related to fire events and will contribute to further improvement of the Canadian NPPs' safety. (author)
Availability note (English)
Available from DOI: https://doi.org/10.12943/CNR.2017.00020Additional details
Identifiers
Publishing Information
- Journal Title
- CNL Nuclear Review (Online)
- Journal Volume
- 8
- Journal Issue
- 2
- Journal Page Range
- p. 97-108
- ISSN
- 2369-6931
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 52064772
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CANDU TYPE REACTORS; FIRE HAZARDS; FIRE PREVENTION; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; SIMULATION
- Descriptors DEC
- CALCULATION METHODS; HAZARDS; HEAVY WATER MODERATED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS
Optional Information
- Notes
- 28 refs., 2 tabs., 7 figs.