The first CANDU (CANadian Deuterium Uranium) pressurized heavy water reactor (PHWR) went into operation in July 1971. Today, there are several units in operation at the Pickering, Bruce, and Darlington sites in Ontario, Canada. The steam generator tubing materials were manufactured from Monel 400, Inconel 600, and Incoloy 800 for the Pickering, Bruce, and Darlington respectively and are subjected to different operating conditions. This paper presents a review of some of the various types of degradation mechanisms that have been observed on these tubing materials over the operating period of the respective plants. The results presented are based on the metallurgical examination of removed tubes. The mechanisms that have been observed include pitting, stress corrosion cracking, intergranular attack, fretting, and erosion corrosion. The nature of the flaws and causative factors (if known) are discussed.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4242-8
PROCEEDINGS PAPER
A Review of Some Degradation Mechanisms in CANDU Steam Generator Tubing
G. Ogundele,
G. Ogundele
Kinectrics, Inc., Toronto, ON, Canada
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G. Goszczynski,
G. Goszczynski
Kinectrics, Inc., Toronto, ON, Canada
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S. Pagan,
S. Pagan
Ontario Power Generation, Pickering, ON, Canada
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P. King
P. King
Babcock & Wilcox Canada, Cambridge, ON, Canada
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G. Ogundele
Kinectrics, Inc., Toronto, ON, Canada
M. Clark
Kinectrics, Inc., Toronto, ON, Canada
G. Goszczynski
Kinectrics, Inc., Toronto, ON, Canada
A. Lloyd
Kinectrics, Inc., Toronto, ON, Canada
S. Pagan
Ontario Power Generation, Pickering, ON, Canada
K. Sedman
Bruce Power, Tiverton, ON, Canada
P. King
Babcock & Wilcox Canada, Cambridge, ON, Canada
Paper No:
ICONE14-89859, pp. 701-708; 8 pages
Published Online:
September 17, 2008
Citation
Ogundele, G, Clark, M, Goszczynski, G, Lloyd, A, Pagan, S, Sedman, K, & King, P. "A Review of Some Degradation Mechanisms in CANDU Steam Generator Tubing." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management. Miami, Florida, USA. July 17–20, 2006. pp. 701-708. ASME. https://doi.org/10.1115/ICONE14-89859
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