Abstract
Nickel-based alloys such as Alloy 600 have been used as structural materials in the nuclear island of pressurized water reactor (PWR) nuclear power plants. Stress corrosion cracking (SCC) of Alloy 600 and its weld metal in PWR primary water has been reported. There are several methods for evaluating SCC resistance or behavior of Nickel-based alloys in high temperature aqueous solutions, such as compact tension (CT) specimens for crack growth rate tests, slow strain rate tests (SSRT), U-bend or reverse U bend tests, C-ring tests. These methods have their own features and application scopes depending on the objective of evaluation. The results obtained by CT specimens or SSRT specimens for SCC behavior of Alloy 600 in simulated PWR primary water are compared and analyzed. The effects of some key parameters such as temperature, cold work and materials parameters on SCC are compared and analyzed, showing that the results from both CT specimens and SSRT specimens indicated the similar trend.
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