Modelling of zirconium alloys corrosion in LWR's

A number of models have been developed for in-reactor corrosion of zirconium alloys. The models accurately take the influence of coolant temperature, heat and neutron flux, coolant vapour content, deposition of corrosion products, water radiolysis and etc. into account. The concept of oxide formation on the metal/oxide interface under the influence of chemical activity of alloying components and coolant chemistry was used as the physicochemical base of the models. The models describe the different corrosion behaviour of alloys E-110, E-635, zircaloys and other alloys in deionised water: under ammonia-potassium and lithium chemistry regimes on natural way.