Abstract
The oxidation of the zirconium alloy E110 inf simulated nuclear power plant coolant at 310 °C is characterised using in situ Electrochemical Impedance Spectroscopy (EIS) and ex-situ microscopic observations. EIS data have been fitted to a transfer function derived from the Mixed Conduction Model. The kinetic parameters characterising the oxidation process – interfacial rate constant of oxidation, diffusion coefficient of oxygen vacancies, and field strength in the inner layer – have been estimated. The dependence of their values on LiOH/KOH/NaF content are discussed in terms of an enhanced rate of dissolution of the barrier layer at higher level of alkali and fluoride.
Original language | English |
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Pages (from-to) | 54-67 |
Number of pages | 14 |
Journal | Corrosion Science |
Volume | 52 |
Issue number | 1 |
DOIs | |
Publication status | Published - 2010 |
MoE publication type | A1 Journal article-refereed |