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2. Alloy 690 SCC growth rate testing;Paraventi;Procedings-2007 AECL/COG/EPRI Workshop on Cold Work Iron- and Nickel-Based Alloy Exposed to High-Temperature Water Environments, Toronto, Canada,2007
3. PWSCC of alloy 690, 52 and 152;Andresen;13th International Conference Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Whistler, British Columbia (Canada), Canadian Nuclear Society,2007
4. Crack growth response of alloy 690 in simulated PWR primary Water;Toloczko;14th International Conference Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Virginia Beach, VA (USA), American Nuclear Society,2009
5. Dependence of stress corrosion cracking of Alloy 690 on temperature, cold work, and carbide precipitation - Role of diffusion of vacancies at crack tips;Arioka;Corrosion,2011