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    Risk analysis with dynamic safety measure for pressurized water reactors with advanced safety features

    Author
    Shah, Asad Ullah Amin
    ORCID
    https://orcid.org/0000-0003-4929-3994
    View/Open
    Shah_rpi_0185E_12254.pdf (4.449Mb)
    Other Contributors
    Kang, Hyun Gook; Liu, Emily; shi, Shanbin; Julius, Anak Agung;
    Date Issued
    2023-08
    Subject
    Nuclear engineering
    Degree
    PhD;
    Terms of Use
    This electronic version is a licensed copy owned by Rensselaer Polytechnic Institute (RPI), Troy, NY. Copyright of original work retained by author.;
    Metadata
    Show full item record
    URI
    https://hdl.handle.net/20.500.13015/6739
    Abstract
    After the Fukushima Daiichi Accident, the US Department of Energy initiated the LightWater Sustainability Program to investigate safety options for existing nuclear fleets, such as accident-tolerant fuel and US diverse and flexible coping strategies. As these safety options are relatively new, developing a framework that can assess their risk and benefits effectively is essential. A dynamic probabilistic risk assessment framework is suggested to analyze the risk and safety of these options during abnormal deviations or accidents. The framework can explicitly highlight the risk and safety benefits of the existing and new safety systems, perform sensitivity analysis of physical parameters and optimize the value of design variables of the system and components. The risk and sensitivity analysis has been demonstrated by leveraging the suggested framework for analyzing two diverse accident scenarios: Station blackout and medium break loss of coolant accident. A CDF- based benefit index and included in the framework can assess the risk margin offered by the existing or the new safety options and provide a mathematical way of comparing those. Additionally, a new concept design for forced safety injection tanks has been suggested. The feasibility of this system has been demonstrated by modeling and integrating this new system into the nuclear power plant model and analyzing the risk benefits. The presented DPRA framework is further leveraged to optimize the FSIT's design parameters, such as actuation set-point or the delays between the series operation of FSITs. Since time is crucial during an accident evolution, a time-based dynamic event importance index is introduced that supports the operator in deciding how much resources he should invest for each component to recover the lost safety function. This measure provides reliability and timebased component importance and ranks them for the operator to allocate resources to restore those components. This measure is compared with the conventional measures. Then efforts are made to estimate the cost savings from re-categorizing the safety components from RISC1 and RISC2 safety classification to RISC3 and RISC4, respectively.;
    Description
    August2023; School of Engineering
    Department
    Dept. of Mechanical, Aerospace, and Nuclear Engineering;
    Publisher
    Rensselaer Polytechnic Institute, Troy, NY
    Relationships
    Rensselaer Theses and Dissertations Online Collection;
    Access
    Restricted to current Rensselaer faculty, staff and students in accordance with the Rensselaer Standard license. Access inquiries may be directed to the Rensselaer Libraries.;
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