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Non-destructive and Failure Evaluation of Tubing from a Retired Steam Generator (NUREG/CR-6924)On this page: Download complete documentThe following links on this page are to documents in Adobe Portable Document Format (PDF). See our Plugins, Viewers, and Other Tools page for more information. For successful viewing of PDF documents on our site please be sure to use the latest version of Adobe. Publication InformationManuscript Completed: August 2006 Prepared by Argonne National Laboratory E. Reichelt, NRC Project Manager Prepared for AbstractStress corrosion cracks (SCC) in tubes removed from a nuclear reactor retired steam generator (SG) have been examined. Eddy current (EC) nondestructive evaluation (NDE), pressure testing, and metallurgical sectioning or fractography were carried out on six tube support plate SCCs and four tube sheet SCCs. The deposits on the top of the tube sheet in the vicinity of the cracking were analyzed. Failure pressures and leak rates for the tube support plate SCCs were evaluated using finite element analysis and were compared to experimental results. Crack profiles used in the analysis were estimated using eddy current examination and fractography results. The data obtained from the pressure tests were compared with the industry probability of leakage database and correlation. The results were generally consistent with the probability of leakage values presented by industry, i.e., tubes that would not be expected to leak based on measured eddy current voltages and the industry correlation did not leak. The best predictions of the SCC profile and crack depth were obtained from the use of a multiparameter algorithm applied to rotating pancake coil data. Very little correlation between +Point amplitude and maximum depth of SCC was found for the tubes that were examined. |
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