TY - GEN
T1 - Predictive modeling of baffle-former bolt failures in pressurized water reactors
AU - Banyay, Gregory A.
AU - Kelley, Matthew H.
AU - McKinley, Joshua K.
AU - Palamara, Matthew J.
AU - Sidener, Scott E.
AU - Worrell, Clarence L.
N1 - Publisher Copyright:
© 2019, The Minerals, Metals & Materials Society.
PY - 2019
Y1 - 2019
N2 - 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.
AB - 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.
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U2 - 10.1007/978-3-030-04639-2_105
DO - 10.1007/978-3-030-04639-2_105
M3 - Conference contribution
AN - SCOPUS:85064061778
SN - 9783030046385
SN - 9783030046392
SN - 9783319515403
SN - 9783319651354
SN - 9783319728520
SN - 9783319950211
T3 - Minerals, Metals and Materials Series
SP - 1573
EP - 1588
BT - Minerals, Metals and Materials Series
PB - Springer International Publishing
T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
Y2 - 18 August 2019 through 22 August 2019
ER -