This paper describes industry programs to manage structural degradation and to justify continued operation of nuclear components when unexpected degradation has been encountered due to design materials and/or operational problems. Other issues have been related to operation of components beyond their original design life in cases where there is no evidence of fatigue crack initiation or other forms of structural degradation. Data from plant operating experience have been applied in combination with inservice inspections and degradation management programs to ensure that the degradation mechanisms do not adversely impact plant safety. Probabilistic fracture mechanics calculations are presented to demonstrate how component failure probabilities can be managed through augmented inservice inspection programs.
Life Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation
Contributed by the Pressure Vessels and Piping Division for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received by the PVP Division, January 2000; revised manuscript received October 23, 2000. Editor: S. Y. Zamrik.
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Simonen, F. A., and Gosselin, S. R. (October 23, 2000). "Life Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation ." ASME. J. Pressure Vessel Technol. February 2001; 123(1): 58–64. https://doi.org/10.1115/1.1344237
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