A small number of cracking incidents have occurred in carbon steel outlet feeders of a CANDU® reactor. The cracks were initiated from both the inside and the outside surfaces of tight-radius cold bends. All cracks were intergranular. One plausible explanation for the inside surface initiated cracking is that it is caused by oxidizing water stress corrosion cracking. This mechanism has been studied extensively under boiling water reactor water chemistry (at neutral pH) conditions and the crack path for this kind of SCC is transgranular. It is not known whether the elevated pH in CANDU® primary water chemistry affects cracking behaviour, particularly electrochemical potential thresholds and crack path. Also, the possible effects of cold work have been investigated in the context of SCC of carbon steel in high temperature water. The pronounced cold work in the feeder bends has been identified as the main variable likely to affect the crack path. Based on the understanding of the feeder cracking incidents, an experimental program was carried out to address the effects of coolant pH, and cold work from feeder bending process during fabrication, on the SCC behaviour of carbon steels in the context of an oxidizing water SCC mechanism.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4351-2
PROCEEDINGS PAPER
Effect of Environmental and Material Conditions on SCC of Carbon Steels in High Temperature Water
Sue Liu,
Sue Liu
Canadian Nuclear Safety Commission, Ottawa, ON, Canada
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Michael D. Wright
Michael D. Wright
Atomic Energy of Canada Limited, Chalk River, ON, Canada
Search for other works by this author on:
Sue Liu
Canadian Nuclear Safety Commission, Ottawa, ON, Canada
Michael D. Wright
Atomic Energy of Canada Limited, Chalk River, ON, Canada
Paper No:
ICONE17-75206, pp. 337-349; 13 pages
Published Online:
February 25, 2010
Citation
Liu, S, & Wright, MD. "Effect of Environmental and Material Conditions on SCC of Carbon Steels in High Temperature Water." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 337-349. ASME. https://doi.org/10.1115/ICONE17-75206
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