| The steam generator in pressurized water reactors nuclear power plants consists mainly of a shell made of carbon steel and tubes made of Alloy 600. By exposure to high temperature water both materials suffer environmentally induced cracking. The intergranular stress corrosion cracking (IGSCC) susceptibility of Alloy 600 was investigated as a function of the level of applied stresses, temperature and primary water solution pH. Constant load tests were carried out with specimens prepared utilizing thin wall tubes and constant deformation tests were used in specimens prepared from plates. It was found that in the tubes exposed to primary water at 330... |
