ABSTRACT
Corrosion of passive components has become a major source of deterioration because those components are exposed to slow increasing degradation which can cause very serious damage. The Stress Corrosion Cracking (SCC) is a problem of some importance in pressurized water reactors (PWR) since many difierent components are concerned (Stutzmann and Nordmann 1996). This phenomenon appears from the combined infiuence of tensile stress and corrosive environment. Boursier et. al (Boursier, Desjardins, and Vaillant 1995) analyzed Alloy 600 for steam generator tubings in pressurized water reactors and they described the difierent stages of the cracking.
