Browse > Article
http://dx.doi.org/10.4191/KCERS.2006.43.11.724

Experimental Verification of a Kinetic Model of Zr-Oxidation  

Yoo, Han-Ill (Solid State Ionics Research Lab., School of Materials Science and Engineering, Seoul National University)
Park, Sang-Hyun (Solid State Ionics Research Lab., School of Materials Science and Engineering, Seoul National University)
Publication Information
Abstract
It has long been known that the oxidation kinetics of Zr-based alloys undergoes a crossover from parabolic to cubic in the pretransition period (before breakaway of the oxide scale). This kinetic crossover, however, is not fully understood yet. We have earlier proposed a model for the Zr-oxidation kinetics, in a closed form for the first time, by taking into account a compressive strain energy gradient as a diffusional driving force in addition to a chemical potential gradient of component oxygen across the ZrO$_2$ scale upon Zr [J. Nucl. Mater., 299 (2001) 235]. In this paper, we experimentally reconfirm the validity of the proposed model by using the thermogravimetric data on mass gain of Zr in a plate and wire form, respectively, in air atmosphere at different temperatures in the range of 500$^{\circ}$ to 800$^{\circ}C$, and subsequently report on the numerical values for oxygen chemical diffusivity and strain energy gradient across the oxide scale.
Keywords
Oxidation kinetics; Zr-based alloys; ZrO$_2$; Oxygen chemical diffusivity; Strain energy;
Citations & Related Records
연도 인용수 순위
  • Reference
1 S. P. Timoshenko and J. N. Goodier, Theory of Elasticity, 3rd Ed.; p. 247, McGraw-Hill, Inc., 1970
2 L.B.Pankratz, Thermodynamic Properties of Elements and Oxides, PB83-174052, US Bureau of Mines, Albany, OR, 1983
3 H.-I. Yoo, B.-J. Koo, J.-O. Hong, I.-S. Hwang, and Y.-H. Jeong, 'A Working Hypothesis on Oxidation Kinetics of Zircaloy,' J. Nucl. Mater., 299 235-41 (2001)   DOI   ScienceOn
4 J. Favergeon, T. Montesin, and G. Bertrand, 'Mechano- Chemical Aspects of High Temperature Oxidation: A Mesoscopic Model Applied to Zirconium Alloys,' Oxid. Met., 64 253-79 (2005)   DOI
5 T. Ahmed and L. H. Keys, 'The Breakaway Oxidation of Zirconium and Its Alloys. A Review,' J. Less-Common Met., 39 99-107 (1975)   DOI   ScienceOn
6 E. Hillner, 'Corrosion of Zirconium-Base Alloys-An Overview'; pp. 211-35 in: Zirconium in the Nuclear Industry: Third International Symposium, ASTM STP, vol. 633, 1977
7 J. Godlewski, 'How the Tetragonal Zirconia is Stabilized in the Oxide Scale that is Formed on a Zirconium Alloy Corroded at 400oC in Steam'; pp. 663-83 in: Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, 1994
8 J. Godlewski, J. P. Gros, M. Lambertin, J. F. Wadier, and H. Weidinger, 'Raman Spectroscopy Study of the Tetragonal- to-Monoclinic Transition in Zirconium Oxide Scales and Determination of Overall Oxygen Diffusion by Nuclear Microanalysis of $O^{18}$'; pp. 416-36 in: Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, 1991
9 J. Godlewski, P. Bouvier, G. Lucazeau, and L. Fayette, 'Stress Distribution Measured by Raman Spectroscopy in Zirconia Films Formed by Oxidation of Zr-Based Alloys'; p. 877-900 in: Zirconium in the Nuclear Industry, Twelfth International Symposium (ASTM special technical publication), 2000
10 H. Schmalzried, 'Chemical Kinetics of Solids', pp. 331-54, VCH, Weinheim, Chap. 14, 1995
11 M. Martin, N. Lakshmi, U. Koops, and H.-I. Yoo, 'In situ Investigations on the Oxidation of Metals,' Proc. 16th Ikedani Conference, Electrochemistry and Thermodynamics on Materials Processing for Sustainable Production: Masuko Symposium, Nov. 12-16, 2006, Tokyo, Japan
12 M. Barsoum, Fundamentals of Ceramics; p. 401, McGraw- Hill, Inc., 1997
13 F. Garzarolli, H. Seidel, R. Tricot, and J. P. Gros, 'Oxide Growth Mechanism on Zirconium Alloys'; pp. 395-415 in: Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, 1991
14 H.-J. Beie, A. Mitwalsky, F. Garzarolli, H. Ruhmann, and H.- J. Sell, 'Examinations of the Corrosion Mechanism of Zirconium Alloys'; pp. 615-43 in: Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, 1994