
CANDU FIRE PROBABILISTIC RISK ASSESSMENT (PRA) MODEL
Author(s) -
Hossam Shalabi,
George Hadjisophocleous
Publication year - 2019
Publication title -
cnl nuclear review
Language(s) - English
Resource type - Journals
eISSN - 2369-6931
pISSN - 2369-6923
DOI - 10.12943/cnr.2017.00020
Subject(s) - nuclear power plant , probabilistic risk assessment , firefighting , probabilistic logic , engineering , risk assessment , nuclear power , fire protection , fire safety , work (physics) , environmental science , forensic engineering , nuclear engineering , computer science , civil engineering , computer security , mechanical engineering , nuclear physics , chemistry , physics , organic chemistry , artificial intelligence
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.