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

54 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 languageEnglish
Pages (from-to)54-67
Number of pages14
JournalCorrosion Science
Volume52
Issue number1
DOIs
Publication statusPublished - 2010
MoE publication typeA1 Journal article-refereed

Fingerprint

Niobium alloys
Zirconium alloys
Light water reactors
Coolants
Corrosion
Electrochemical impedance spectroscopy
Oxidation
Water
Alkalies
Oxygen vacancies
Fluorides
Kinetic parameters
Nuclear power plants
Transfer functions
Rate constants
Dissolution

Cite this

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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.",
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Influence of water chemistry on the corrosion mechanism of a zirconium-niobium alloy in simulated light water reactor coolant conditions. / Bojinov, Martin (Corresponding Author); Karastoyanov, Vasil; Kinnunen, Petri; Saario, Timo.

In: Corrosion Science, Vol. 52, No. 1, 2010, p. 54-67.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

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

VL - 52

SP - 54

EP - 67

JO - Corrosion Science

JF - Corrosion Science

SN - 0010-938X

IS - 1

ER -