Sensitivity analysis of a nuclear reactor system finite element model

Gregory A. Banyay, Stephen D. Smith, Jason S. Young

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

    1 Scopus citations


    The structures associated with the nuclear steam supply system (NSSS) of a pressurized water reactor (PWR) warrant evaluation of various non-stationary loading conditions which could occur over the life of a nuclear power plant. These loading conditions include those associated with a loss of coolant accident and seismic event. The dynamic structural system is represented by a finite element model consisting of significant epistemic and aleatory uncertainties in the physical parameters. To provide an enhanced understanding of the influence of these uncertainties on model results, a sensitivity analysis is performed. This work demonstrates the construction of a computational design of experiment which runs the finite element model a sufficient number of times to train and verify a unique aggregate surrogate model. Adaptive sampling is employed in order to reduce the overall computational burden. The surrogate model is then used to perform both global and local sensitivity analyses.

    Original languageEnglish (US)
    Title of host publicationASME 2018 Verification and Validation Symposium, VVS 2018
    PublisherAmerican Society of Mechanical Engineers (ASME)
    ISBN (Electronic)9780791840795
    StatePublished - 2018
    EventASME 2018 Verification and Validation Symposium, VVS 2018 - Minneapolis, United States
    Duration: May 16 2018May 18 2018

    Publication series

    NameASME 2018 Verification and Validation Symposium, VVS 2018


    ConferenceASME 2018 Verification and Validation Symposium, VVS 2018
    Country/TerritoryUnited States

    All Science Journal Classification (ASJC) codes

    • Computational Theory and Mathematics
    • Information Systems and Management
    • Information Systems

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