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 |
| Number of pages | 14 |
| Journal | Corrosion Science |
| Volume | 52 |
| Issue number | 1 |
| DOIs | |
| Publication status | Published - 2010 |
| MoE publication type | A1 Journal article-refereed |
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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 journal › Article › Scientific › peer-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 -