Pitting corrosion is a serious form of degradation in steam generator (SG) tubing of some nuclear generating stations. The nature and extent of the pitting process is assessed through inspection programs, typically using eddy current probes. Although the data can be used in a probabilistic framework to predict the probability of a tube leak in future time intervals, the consideration of uncertainties associated with inspection tools is extremely important. The paper shows that the defect size data collected through inspections are significantly contaminated by probability of detection and measurement error such that the data present an incomplete picture of the defect population. The use of inspection data without accounting for inspection uncertainties in the analysis results in highly biased estimates of the leak probability. The paper presents a statistically correct likelihood method to account for inspection uncertainties and demonstrates its effectiveness through examples.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4814-0
PROCEEDINGS PAPER
The Effect of Inspection Uncertainties in Predicting the Probability of Leak of Steam Generator Tubing Due to Pitting Available to Purchase
M. D. Pandey,
M. D. Pandey
University of Waterloo, Waterloo, ON, Canada
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S. V. Datta,
S. V. Datta
University of Waterloo, Waterloo, ON, Canada
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D. Komljenovic
D. Komljenovic
Hydro-Quebec, Becancour, QC, Canada
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M. D. Pandey
University of Waterloo, Waterloo, ON, Canada
S. V. Datta
University of Waterloo, Waterloo, ON, Canada
D. Komljenovic
Hydro-Quebec, Becancour, QC, Canada
Paper No:
ICONE16-48729, pp. 685-693; 9 pages
Published Online:
June 24, 2009
Citation
Pandey, MD, Datta, SV, & Komljenovic, D. "The Effect of Inspection Uncertainties in Predicting the Probability of Leak of Steam Generator Tubing Due to Pitting." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues. Orlando, Florida, USA. May 11–15, 2008. pp. 685-693. ASME. https://doi.org/10.1115/ICONE16-48729
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