AC impedance characteristics of oxide film on zirconium

J. Y. Lim, B. C. Han, I. S. Hwang

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The electrochemical impedance spectroscopy was employed primarily to explore its potential as an in situ monitor of film thickness and microstructure during the oxide formation and growth on a pure zirconium in water. The oxide film growth was accelerated by anodization of zirconium metal in a buffered alkaline solution at room temperature. AC impedance was measured at corrosion potential at various cumulative anodic charges. The impedance data suggests that the oxide film can be modeled adequately by a parallel RC circuit with the concept of a constant phase element. The oxide thickness estimated from the AC impedance was observed to increase linearly with the cumulative anodic charge indicating that the current efficiency for oxide growth is only about 6 percent under the condition. The oxide thickness analyzed by Auger Electron Spectroscopy (AES) corresponded with that predicted from the anodic charge. Hence it is suggested that the AC impedance techniques can be used to monitor the inner imprevious layer of the Zr oxide.

Original languageEnglish
Title of host publicationProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
EditorsS. Bruemmer, P. Ford, G. Was
PublisherMinerals, Metals and Materials Society
Pages1145-1151
Number of pages7
ISBN (Print)0873394755, 9780873394758
DOIs
Publication statusPublished - 1999
EventProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - - New Portbeach, CA, United States
Duration: 1999 Aug 11999 Aug 5

Publication series

NameProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Other

OtherProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
Country/TerritoryUnited States
CityNew Portbeach, CA
Period99/8/199/8/5

All Science Journal Classification (ASJC) codes

  • Engineering(all)

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