Corrosion Behavior of BWR Plant Components and Countermeasures

摘要

Environmentally assisted cracking (EAC), such as SCC and corrosion fatigue, is one of the most important of the phenomena that govern the life expectancy of the structural components of nuclear power plants. The parameters that control it are sensitization of materials, water chemistry, and stress/strain.This paper examines the EAC behavior of the materials used as structural components of boiling water reactors, such as low-alloy steel, carbon steel, stainless steel, and Ni-base alloy, and also treats irradiation-assisted SCC (IASCC) of stainless steel. The mechanisms of EAC and various countermeasures are discussed in terms of the controlling parameters mentioned above.