Research Papers: Nuclear Power

Residual Life Assessment of Steam Generators With Alloy 600 TT Tubing: Methods and Application

[+] Author and Article Information
Ian de Curieres1

 AREVA-NP, Paris, La Défense 92084, Franceian.decurieres@areva.com

Marie-Christine Meunier, Pierre Joly

 AREVA-NP, Paris, La Défense 92084, France


Corresponding author.

J. Eng. Gas Turbines Power 132(10), 102902 (Jun 30, 2010) (6 pages) doi:10.1115/1.4000340 History: Received July 20, 2009; Revised August 06, 2009; Published June 30, 2010; Online June 30, 2010

The aim of the paper is to introduce methods to estimate the residual life of steam generators with alloy 600 thermally treated (TT) tubing, taking into account primary water stress corrosion cracking (PWSCC) as the main contributor damage. The methods take into account both initiation and propagation of PWSCC cracks in the expansion transition zone of steam generator tubes, as well as the current damage status (cracking and plugging) of the tube bundle, known from inspection results. A probabilistic model is used to treat initiation, while the propagation stage is treated in a deterministic way based on inspection data. After introducing the methods used to assess the residual life, a brief parametric study will be shown to illustrate the effects of initiation versus propagation. Eventually, the cases of a few actual steam generators with tubing made of alloy 600 TT showing different situations of present damage and damage evolution rates will be presented.

Copyright © 2010 by American Society of Mechanical Engineers
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Figure 1

Estimate of the evolution of PWSCC initiation thanks to a Weibull modeling (from Ref. 4)

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Figure 2

Schematic representation of the indices model and the distributions of parameters (from Ref. 5). The “t” value indicated is the minimum time to failure.

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Figure 3

Use of a probabilistic index model to predict the initiation behavior of steam generator tubes (from Ref. 8). The concerned steam generator has tubes made of alloy 600 MA.

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Figure 4

Examples of crack length distribution. The evolution from the distribution of outage 1 to outage 2 enables to obtain a CGR field.

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Figure 5

Evolution of the PWSCC initiation in a steam generator with tubes in alloy 600 TT in the roll transition zone. Comparison between the model and the ISI data.

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Figure 6

CGRs for two studied steam generators as obtained in the algorithm

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Figure 7

Example of stresses in the rolled transition zone for the kiss-rolled tubes (from Ref. 9)




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