scholarly journals CANDU FIRE PROBABILISTIC RISK ASSESSMENT (PRA) MODEL

2019 ◽  
Vol 8 (2) ◽  
pp. 97-108
Author(s):  
Hossam Shalabi ◽  
George Hadjisophocleous

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(s):  
Qiu Yanfei

The motivation for exploring the potential development of accident tolerant fuels in PWR to replace existing Zr alloy clad monolithic oxide fuel is outlined. The assessment includes a brief review of core degradation processes under transient conditions and introduces the enhancement of the accident tolerance of PWR by the development of fuels/cladding that can tolerate loss of active cooling in the core and loss of coolant water for a considerably longer time period while maintaining or improving the fuel performance during accident conditions. probabilistic risk assessment are presented that illustrate the impact of these new candidate fuel/cladding materials on the reduction of core damage frequence.


Author(s):  
Sai Zhang ◽  
Zhegang Ma

Abstract The catastrophic Fukushima nuclear accident reminded the nuclear community about potential extreme accident scenarios, including those involving multiple reactor units on the same site. In response to the Fukushima accident, the nuclear power industry developed and implemented a series of strategies, including Diverse and Flexible Coping Strategies (FLEX), to enhance the capacities of nuclear power plants (NPPs) to cope with extreme accidents. This study examines the impact of FLEX strategies on the overall risk from all reactor units located at the same NPP site, including risks from accidents involving either a single unit or multiple units. The fundamental, methodological element of this study is Multi-Unit Probabilistic Risk Assessment (MUPRA) requiring a shift in Probabilistic Risk Assessment (PRA) from a one-reactor-at-a-time mindset to a consideration of all reactors sharing a site. An integrated modeling approach for multi-unit event sequence development is leveraged to develop the MUPRA model and address intra-unit and inter-unit dependencies. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), a PRA software developed and maintained by Idaho National Laboratory for the United States (U.S.) Nuclear Regulatory Commission, serves as the platform for MUPRA modeling. This study selects loss of offsite power (LOOP) as a representative initiating event potentially occurring on a generic two-unit NPP site and impacting both reactor units. First, an MUPRA model, including multi-unit event trees, is developed to obtain single-unit and multi-unit accident scenarios. Next, different FLEX strategies are assumed; for example, whether FLEX equipment for multiple units can be used in a cross-connected manner. Lastly, the effectiveness of each postulated FLEX strategy is evaluated by incorporating the corresponding FLEX equipment and deployment logic into the MUPRA model.


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