Predictive modeling of baffle-former bolt failures in pressurized water reactors

Gregory A. Banyay, Matthew H. Kelley, Joshua K. McKinley, Matthew J. Palamara, Scott E. Sidener, Clarence L. Worrell

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

    2 Scopus citations

    Abstract

    Baffle-former bolt failures have been observed in recent inspections of pressurized water reactors (PWRs). These failures are understood to be primarily caused by irradiation-assisted stress corrosion cracking (IASCC). A prognostic method has been developed for simulating the degradation of baffle-former bolts due to IASCC. The method characterizes the evolution of stress in a reactor environment, as well as the redistribution of stress amidst neighboring bolt failures. Empirically-validated Weibull parameters are utilized in a stochastic framework, and the model is exercised as a Monte Carlo simulation to evaluate a range of plausible scenarios from which trends of bolt failure rates and patterns can be determined. This semi-empirical methodology is informed by both operating experience and a more detailed, predictive finite element analysis model that encompasses the full range of phenomenological effects common to the operating environment within a PWR.

    Original languageEnglish (US)
    Title of host publicationMinerals, Metals and Materials Series
    PublisherSpringer International Publishing
    Pages1573-1588
    Number of pages16
    ISBN (Print)9783030046385, 9783030046392, 9783319515403, 9783319651354, 9783319728520, 9783319950211
    DOIs
    StatePublished - 2019
    Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States
    Duration: Aug 18 2019Aug 22 2019

    Publication series

    NameMinerals, Metals and Materials Series
    ISSN (Print)2367-1181
    ISSN (Electronic)2367-1696

    Conference

    Conference18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
    Country/TerritoryUnited States
    CityBoston
    Period8/18/198/22/19

    All Science Journal Classification (ASJC) codes

    • Electronic, Optical and Magnetic Materials
    • Energy Engineering and Power Technology
    • Mechanics of Materials
    • Metals and Alloys
    • Materials Chemistry

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