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

Martin Bojinov; Vasil Karastoyanov; Petri Kinnunen; Timo Saario

doi:10.1016/j.corsci.2009.08.045

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

Martin Bojinov^*
, Vasil Karastoyanov
, Petri Kinnunen
, Timo Saario

^*Corresponding author for this work

Research output: Contribution to journal › Article › Scientific › peer-review

87 Citations (Scopus)

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
Pages (from-to)	54-67
Journal	Corrosion Science
Volume	52
Issue number	1
DOIs	https://doi.org/10.1016/j.corsci.2009.08.045
Publication status	Published - 2010
MoE publication type	A1 Journal article-refereed

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

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.",

author = "Martin Bojinov and Vasil Karastoyanov and Petri Kinnunen and Timo Saario",

year = "2010",

doi = "10.1016/j.corsci.2009.08.045",

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pages = "54--67",

journal = "Corrosion Science",

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T1 - Influence of water chemistry on the corrosion mechanism of a zirconium-niobium alloy in simulated light water reactor coolant conditions

AU - Bojinov, Martin

AU - Karastoyanov, Vasil

AU - Kinnunen, Petri

AU - Saario, Timo

PY - 2010

Y1 - 2010

N2 - 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.

AB - 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.

U2 - 10.1016/j.corsci.2009.08.045

DO - 10.1016/j.corsci.2009.08.045

M3 - Article

SN - 0010-938X

VL - 52

SP - 54

EP - 67

JO - Corrosion Science

JF - Corrosion Science

IS - 1

ER -

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

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