TAILIEUCHUNG - A systematic approach to identify initiating events and its relationship to Probabilistic Risk Assessment: Demonstrated on the Molten salt reactor experiment

One of the first steps in developing a risk assessment model is an exhaustive search for initiating events, which is a systematic and comprehensive starting point to answer the question “what can go wrong?” for a given system design. | Progress in Nuclear Energy 129 2020 103507 Contents lists available at ScienceDirect Progress in Nuclear Energy journal homepage http locate pnucene A systematic approach to identify initiating events and its relationship to Probabilistic Risk Assessment Demonstrated on the Molten Salt Reactor Experiment Brandon M. Chisholm a Steven L. Krahn a Karl N. Fleming b a Vanderbilt University Dept. of Civil and Environmental Engineering PMB 351831 2301 Vanderbilt Place 37235 Nashville TN USA b KNF Consulting Services LLC 816 West Francis Ave Spokane WA 99205 USA A R T I C L E I N F O A B S T R A C T Keywords One of the first steps in developing a risk assessment model is an exhaustive search for initiating events which is Molten salt reactor a systematic and comprehensive starting point to answer the question what can go wrong for a given system Initiating events design. Identifying Postulated Initiating Events PIEs for a reactor design that is at a conceptual or preliminary Safety stage facilitates the incorporation of risk insights into the next iteration of the design process and allows for the Risk assessment Process hazards analysis early establishment of more quantifiable risk assessment models such as event sequence diagrams and event tree Master logic diagram analysis. Liquid-Fueled Molten Salt Reactors LF-MSRs are an example of an advanced reactor technology that does not benefit from having a wealth of operating experience or prior risk-informed safety assessment efforts. Furthermore design details such as normal operating conditions and the composition of radioactive material inventories can deviate substantially from those in other reactors such that a systematic and comprehensive approach to identifying PIEs for an LF-MSR may highlight accident initiators that have not previously been identified. In the present work the Master Logic Diagram MLD and Hazards and Operability HAZOP study approaches were used together to identify and consider PIEs

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