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3. G.M. Gordon and K.S. Brown, “Dependence of Creviced BWR Component IGSCC Behavior on Coolant Chemistry,” Proceedings of the Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors (Houston, TX: NACE, 1990), pp. 14-46 to 14-62.
4. K.S. Brown and G.M. Gordon, “Effects of BWR Coolant Chemistry on the Propensity for IGSCC Initiation and Growth in Creviced Reactor Internals Components,” Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors (Warrendale, PA: TMS, 1987), pp. 243–248.
5. P.M. Scott et al., “Irradiation Assisted Stress Corrosion of Fuel Element Components of a Steam Generating Heavy Water Reactor” (Paper presented at the NEA/UNIPEDE Specialists Meeting on Life Limiting and Regulatory Aspects of Core Internals and Pressure Vessels, Stockholm, Sweden, 14–16 October 1987).