Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1470547 | Corrosion Science | 2010 | 14 Pages |
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.
Related Topics
Physical Sciences and Engineering
Materials Science
Ceramics and Composites
Authors
Martin Bojinov, Vasil Karastoyanov, Petri Kinnunen, Timo Saario,