A Probabilistic Environmentally Assisted Cracking Model for Steam Generator Tubes

2014 ◽  
Vol 137 (2) ◽  
Author(s):  
Tae Hyun Lee ◽  
Jae Young Yoon ◽  
Hyo On Nam ◽  
Il Soon Hwang

A probabilistic environmentally assisted cracking (PEAC) model was developed to describe the propagation of primary water stress corrosion cracking for Alloy 600 in roll-transition region of steam generator (SG), a severe environmentally assisted cracking problem in pressurized water reactors (PWRs). In the PEAC model, crack growth rate (CGR) and probability of failure (POF) were obtained by adopting a Bayesian inference that decreases the uncertainties of unknown parameters and their distributions in theoretical equations. The CGR is mainly dependent on three factors: probability of detection (POD), initial crack size distribution, and stress distribution. The POD, which is a logistic link was updated with Bayesian inference based on SG inspection data. The crack size distribution, which is relative to initiation time expressed by a Weibull function, was also updated with Bayesian inference using POD. The stress distribution caused by mechanical rolling is considered to be a major contributing factor along the SG tube. It based on finite element analysis is deterministic model unlike POD and initial crack distribution. According to this model, the uncertainty of hyperparameters in the CGR which are parameters of a prior distribution was reduced, and the appropriate level of confidence was achieved by utilizing the available data. Moreover, a benchmark study for the SG tube was performed to evaluate reliability of Alloy 600 SG components in nuclear power plants. The POF was estimated from the developed PEAC model and failure criteria by taking into account the effects of inspection and repair of defective tubes. The results from this study are applied to demonstrate risk reduction in PWRs by adopting risk-informed in-service inspection.

Author(s):  
April Smith ◽  
Kenneth J. Karwoski

Steam generators placed in service in the 1960s and 1970s were primarily fabricated from mill-annealed Alloy 600. Over time, this material proved to be susceptible to stress corrosion cracking in the highly pure primary and secondary water chemistry environments of pressurized-water reactors. The corrosion ultimately led to the replacement of steam generators at numerous facilities, the first U.S. replacement occurring in 1980. Many of the steam generators placed into service in the 1980s used tubes fabricated from thermally treated Alloy 600. This tube material was thought to be less susceptible to corrosion. Because of the safety significance of steam generator tube integrity, this paper evaluates the operating experience of thermally treated Alloy 600 by looking at the extent to which it is used and recent results from steam generator tube examinations.


Author(s):  
Omesh K. Chopra ◽  
Bogdan Alexandreanu ◽  
William J. Shack

Reactor–vessel internal components made of nickel–base alloys are susceptible to environmentally assisted cracking. A better understanding of the causes and mechanisms of this cracking may permit less conservative estimates of damage accumulation and requirements on inspection intervals of pressurized water reactors (PWRs). This paper presents crack growth rate (CGR) results for Alloy 600 removed from nozzle#3 of the Davis–Besse (D-B) control rod drive mechanism (CRDM). The tests were conducted on 1/4-T or 1/2-T compact tension specimens in simulated PWR environment, and crack extensions were determined by DC potential drop measurements. The experimental CGRs under cyclic and constant load are compared with the existing CGR data for Alloy 600 to determine the relative susceptibility of the D-B CRDM nozzle alloy to environmentally enhanced cracking. The CGRs under constant load for the nozzle material are higher than those predicted by the best-fit curve for Alloy 600 at 316 °C. The results also indicate significant enhancement of CGRs under cyclic loading in the PWR environment. Characterization of the material microstructure and tensile properties is described.


1991 ◽  
Vol 113 (4) ◽  
pp. 719-724 ◽  
Author(s):  
J. W. Blake ◽  
H. S. Cheng

A predictive pitting model for estimating failure probabilities and service lives has been developed. This paper presents the failure probability analysis and a discussion of the model’s application to spur gears. Probability estimates are based on an initial crack size distribution and on possible interaction between cracks and inclusions. Plots of the fraction of components experiencing pitting (percent) versus life show less spread than would be expected. However, trends predicted based on parametric variation are consistent with service behavior. The model is applied by linking the pitting model with a spur gear performance code. Results are compared with AGMA standards.


Author(s):  
T. H. Lee ◽  
Y. J. Oh ◽  
I. S. Hwang ◽  
H. S. Chung ◽  
J. Y. Park

For the aging management and safety assurance of an operating pressurized water reactor (PWR), the integrity of steam generator (SG) tubes receives increasing attention. Non-destructive examination by eddy current technique (ECT), leak rate measurement and burst pressure evaluation constitute key elements. SG tubes containing cracks with physical and microstructural characteristics similar to those of field-aged tubes are needed for the effort. We explored a radial dent loading method to introduce axial intergranular cracks using sensitized alloy 600 tubes in laboratories as a procedure to generate a library of laboratory degraded tubes (LDT) for ECT qualification. Based on three-dimensional finite element analysis and preliminary experimental work that the method is shown to be more useful than the internal pressurization method for the production of cracks with high aspect ratio. In addition, direct current potential drop (DCPD) method applied with array probes has been developed for use in accurate monitoring and control of crack size and shape. In order to minimize plastic deformation of region containing cracks, it is desired to use the radial dent loading only for shallow crack initiation. Then, subsequent growth of crack depth can be made by internal pressurization method.


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