Flow accelerated corrosion (FAC) is a serious form of degradation in primary heat transport piping system (PHTS) of the nuclear reactor. Pipes transporting hot coolant from the reactor to steam generators are particularly vulnerable to FAC degradation, such as tight radius pipe bends with high flow velocity. FAC is a life limiting factor, as excessive degradation can result in the loss of structural integrity of the pipe. To prevent this, engineering codes and regulations have specified minimum wall thickness requirements to ensure fitness for service of the piping system. Nuclear utilities have implemented periodic wall thickness inspection programs and carried out replacement of pipes prior to reaching an unsafe state. To optimize the life-cycle management of PHTS, accurate prediction of time of replacement or “end of life” of pipe sections is important. Since FAC is a time-dependent process of uncertain nature, this paper presents two probabilistic models for predicting the end of life. This paper illustrates that the modeling assumptions have a significant impact on the predicted number of replacements and life-cycle management of the nuclear piping system. A practical case study is presented using wall thickness inspection data collected from Canadian nuclear plants.
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January 2011
Research Papers
The Impact of Probabilistic Modeling in Life-Cycle Management of Nuclear Piping Systems
M. D. Pandey,
M. D. Pandey
Department of Civil and Environmental Engineering,
University of Waterloo
, Waterloo, ON, N2L 3G1, Canada
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D. Lu,
D. Lu
Department of Civil and Environmental Engineering,
University of Waterloo
, Waterloo, ON, N2L 3G1, Canada
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D. Komljenovic
D. Komljenovic
Nuclear Generating Station Gentilly-2,
Hydro-Quebec 75
, Boulevard Rene-Levesque, West Montreal, QC, H2Z 1A4, Canada
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M. D. Pandey
Department of Civil and Environmental Engineering,
University of Waterloo
, Waterloo, ON, N2L 3G1, Canada
D. Lu
Department of Civil and Environmental Engineering,
University of Waterloo
, Waterloo, ON, N2L 3G1, Canada
D. Komljenovic
Nuclear Generating Station Gentilly-2,
Hydro-Quebec 75
, Boulevard Rene-Levesque, West Montreal, QC, H2Z 1A4, CanadaJ. Eng. Gas Turbines Power. Jan 2011, 133(1): 012901 (7 pages)
Published Online: September 24, 2010
Article history
Received:
August 10, 2009
Revised:
August 28, 2009
Online:
September 24, 2010
Published:
September 24, 2010
Citation
Pandey, M. D., Lu, D., and Komljenovic, D. (September 24, 2010). "The Impact of Probabilistic Modeling in Life-Cycle Management of Nuclear Piping Systems." ASME. J. Eng. Gas Turbines Power. January 2011; 133(1): 012901. https://doi.org/10.1115/1.4000897
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