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Effect of the Microstructure of Inconel 600 HTMA on Susceptibility to Stress Corrosion Cracking on the Simulated Nuclear Power Plant Operating Condition
Joung-Soo Kim, Jung-Ho Han, Hong-Pyo Kim, Yun-Soo Lim, Deok-Hyun Lee, Seong-Sik Hwang, Do-Haeng Hur
Keywords: steam generator, alloy 600, stress corrosion cracking, pressurized water reactor, primary water stress corrosion cracking, high temperature mill annealing