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Extra resources for Corrosion Issues in Light Water Reactors: Stress Corrosion Cracking (EFC51)
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. US NRC Information Notice, ‘Valve stem corrosion failures’, 85–59, (1985).
Scott, P. Combrade, ‘On the mechanism of stress corrosion crack initiation and growth in Alloy 600 exposed to PWR primary water’, Proceedings of 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Stevenson, Washington, American Nuclear Society (2003) 29–35. 7. R. W. Staehle, J. A. Gorman, K. D. Stavropoulos, C. S. Welty, ‘Application of statistical distributions to characterizing and predicting corrosion of tubing in steam generators of Pressurized Water Reactors’, Proceedings of Life Prediction of Corrodible Structures, ed.
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). R. M. Horn, G. M. Gordon, F. P. Ford, R. L. Cowan, ‘Experience and assessment of stress corrosion cracking in L-grade stainless steel in BWR internals’, Nuclear Engineering and Design, 174 (1997) 313–325.