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Extra resources for Corrosion Issues in Light Water Reactors: Stress Corrosion Cracking (EFC51)
Sample text
A. Gorman, ‘Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in Pressurized Water Reactors: Parts 1, 2 and 3’, Corrosion, 59 (2003) 931–994, 60 (2004) 5–63, and 60 (2004) 115–180. L. E. Thomas, V. Y. Gertzman, S. M. Bruemmer, ‘Crack-tip microstructures and impurities in stress-corrosion-cracked Alloy 600 from recirculating and once-through steam generators’ Proceedings of 10th Int. Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Lake Tahoe, NACE International (2001).
Nevertheless, the two are clearly closely related. IGA/IGSCC varies greatly with height of the tube support plate in recirculating steam generators, being much more prevalent at the lower levels where the temperature difference between the primary and secondary fluids is greatest. This is clearly strong evidence for the importance of impurity hideout, which increases as a function of the available superheat on the secondary side. Broached tube support plates minimize the extent of the narrow gap between the tube and its support plate and hence substantially reduce the tendency for impurity hideout in such locations.
Bruemmer, E. P. Simonen, P. M. Scott, P. L. Andresen, G. S. Was, J. L. Nelson, ‘Radiation-induced material changes and susceptibility to Intergranular failure of light-water-reactor core internals’, Journal of Nuclear Materials, 274 (1999) 299– 314. US NRC Information Notice, ‘Stress corrosion cracking of reactor coolant pump bolts’ 90 – 68 (1990) and supplement 1 (1994). J. B. Hall, S. Fyfitch, K. E. Moore, ‘Laboratory and operating experience with Alloy A286 and Alloy X750 RV internals bolting stress corrosion cracking’, Proceedings of 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Stevenson, Washington, American Nuclear Society (2003) 208–215.