1. Optimization of Metallurgical Variables to Improve the Stress Corrosion Resistance of Alloy 600, EPRI Report NP-3051 (Palo Alto, CA: EPRI, June 1983).
2. Corrosion Evaluation of Thermally Treated Alloy 600 Tubing in Primary and Faulted Secondary Water Environments. EPRI NP-6721 (Palo Alto, CA: EPRI, June 1990).
3. K. Smith et al., “Inconel 690: A Material with Improved Corrosion Resistance for PWR Steam Generator Tubes,” Proc. Second Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors (La Grange Park, IL: ANS, 1985), pp. 319–328.
4. See technical papers in the series of Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, published every other year since 1983. See also papers published in the international symposia held in Fontevraud, France on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors; held in 1985, 1990, 1994, and 1998.
5. This comparison table was developed by A.R. McIlree of EPRI, with review and revision by Westinghouse.