Managing Material Degradation in Nuclear Power Plants

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Mike Montazer
Danyal Montazer

Abstract

The demanding environments of an operating nuclear reactor may impact the ability of a broad range of materials to perform their intended function over extended service periods. Identifying materials and components where degradation may occur is an important aspect of safe and secure operation of a nuclear power plant.“The average operating time of a CANDU power plant is 30 years,” “However, many nuclear power plants would be able to operate safely beyond their initial design life”.To achieve this, each utility has to demonstrate that high levels of safety and security will be upheld for the extended service period by applying advanced ageing management techniques. Thus it is essential to understand the mechanisms of Material Degradation and radiation damage to the “system structure and components (SSCs) and possible mitigation approaches.Canadian Nuclear Power Services Ltd. (CNPS) is primarily established for refurbishment of nuclear power plants, and all aspects of material degradation can be looked into by walkdowns.This paper elaborates Managing Material Degradation in Nuclear Power Plants.Estimating the actual minimum wall thickness of a feeder pipe is subject to uncertainties associated with the inspection data. The main objective of this study is to quantify the coverage error intrinsic to the 6-probe and 14-probe feeder inspection tools, based on the analysis of over 4,400 inspection scans from Darlington and Pickering reactors. To increase confidence in the results, a smaller subset of well characterized wall thickness profiles was selected as a reference for a simulation approach. The distribution of maximum probe coverage error was estimated in terms of numerous simulated probe passes over the reference profiles. The results of the simulation study show that the maximum probe coverage error ranges from 0 mm to over 0.2 mm in some cases, with the average errors equal to 0.042 mm and 0.065 mm for the 6-probe and 14- probe, respectively. The high variation in the results was due to a strong linear correlation of coverage error with the pattern of wall thinning, with lower values associated with general thinning and higher values applicable to more localized thinning profiles. The thinning patterns were characterized quantitatively using a patch area method, which allows the results to be used for uncertainty analysis and prediction of the actual minimum thickness in a general setting.

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