Water Chemistry Parameters as Factors Influencing the Reliability of RBMK-1000 Reactor Fuel Assemblies

摘要

A model is presented for describing the combined effect on the corrosion of the zirconium alloy of fuel-rod claddings of the physical and chemical factors typical for the operating conditions of light-water reactors. The model describes the corrosion of zirconium alloy throughout the entire fuel cycle at a nuclear power station during normal operation of fuel assemblies in the reactor core and during the storage of spent fuel assemblies in fuel pools; this model can be used for predicting the effect on corrosion of changes in the quality of water chemistry. The model was verified on the basis of experimental and operational data on the corrosion of the zirconium fuel-rod claddings used in test loops and at nuclear power stations.