（1. School of Materials Science and Engineering, Shanghai University, Shanghai 200072，China） （2. State Key Laboratory of Advanced Special Steels, Shanghai University, Shanghai 200444, China)
Stress corrosion cracking (SCC) of structural materials in high temperature water in nuclear power plants is one of the important factors for the safety operation. In this paper, the effects of alloy composition, loading and environmental factors on SCC growth of austenitic alloys in high temperature water environments are reviewed. Some available SCC mechanisms are briefly introduced. The element processes involved in SCC are categorized, and the physical degradation and physicalchemical degradation modes due to loading on the interfacial reactions in high temprature water are proposed. The deformation/oxidation interaction model for SCC growth rate is developed, based on the combination of the crack tip continuum mechanics and the oxidation kinetics. The fittness for the adopted oxidation kinetics and the crack tip asymptotic field in the SCC growth rate model is checked. It is found that the effects of temperature, material composition and water chemistry on oxidation kinetics correspond well to their effects on SCC growth rate. The compatibility of the adopted crack tip mechanical field is also confirmed. The calculated results with the developed SCC growth rate model based on deformation/oxidation interaction are found to be consistent with the reported experimental SCC growth rates and plant data.