Influence of water chemistry on the corrosion mechanism of a zirconium-niobium alloy in simulated light water reactor coolant conditions

Martin Bojinov (Corresponding Author), Vasil Karastoyanov, Petri Kinnunen, Timo Saario

    Research output: Contribution to journalArticleScientificpeer-review

    57 Citations (Scopus)


    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 languageEnglish
    Pages (from-to)54-67
    Number of pages14
    JournalCorrosion Science
    Issue number1
    Publication statusPublished - 2010
    MoE publication typeA1 Journal article-refereed


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