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.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3595-2
PROCEEDINGS PAPER
U.S. Operating Experience With Thermally Treated Alloy 600 Steam Generator Tubes
April Smith,
April Smith
U.S. Nuclear Regulatory Commission, Washington, D.C.
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Kenneth J. Karwoski
Kenneth J. Karwoski
U.S. Nuclear Regulatory Commission, Washington, D.C.
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April Smith
U.S. Nuclear Regulatory Commission, Washington, D.C.
Kenneth J. Karwoski
U.S. Nuclear Regulatory Commission, Washington, D.C.
Paper No:
ICONE10-22139, pp. 217-225; 9 pages
Published Online:
March 4, 2009
Citation
Smith, A, & Karwoski, KJ. "U.S. Operating Experience With Thermally Treated Alloy 600 Steam Generator Tubes." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 1. Arlington, Virginia, USA. April 14–18, 2002. pp. 217-225. ASME. https://doi.org/10.1115/ICONE10-22139
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