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Predictive Modeling of Baffle-Former Bolt Failures in Pressurized Water Reactors

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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.

18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems.

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Correspondence to Matthew J. Palamara .

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© 2019 The Minerals, Metals & Materials Society

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Banyay, G.A., Kelley, M.H., McKinley, J.K., Palamara, M.J., Sidener, S.E., Worrell, C.L. (2019). Predictive Modeling of Baffle-Former Bolt Failures in Pressurized Water Reactors. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_105

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