1999 Volume 48 Issue 12 Pages 753-762
EAC (Environmental assisted cracking) such as SCC and corrosion fatigue is one of the most important phenomena to control the total life time of structural components of nuclear power plants. As has been well recognized, they are controlled by many parameters as sensitization of materials, water chemistry and stress/strain.
In this paper, EAC behavior of the materials used as BWR structural components such as Low alloy steel, carbon steel, stainless steel and Ni base alloy as well as IASCC (Irradiation Assisted SCC) of stainless steel are widely discussed. In addition, their mechanisms and various kinds of countermeasures are also summarized in terms of their controlling parameters mentioned above.