Model of zirconium alloy corrosion in the VVER coolant under normal operating conditions
The paper presents results of model calculation of the effect of zirconium alloy composition on the alloy corrosion in VVER normal operating conditions. The model is based on the thermodynamic approach to analysis of equations describing the high-temperature oxidation of zirconium cladding alloys. The oxidation kinetics of the sponge-based E110 and E635 alloys is calculated. Prediction of the E110 alloy corrosion in the VVER.1200 reactor is obtained. The model can serve as a basis for computer codes that are used to predict corrosion behavior of different alloys in nuclear reactors.