@inproceedings{e6ea0c232f7a4e548b47fdf96e763907,
title = "Mechanisms of oxidation of fuel cladding alloys revealed by high resolution APT, TEM and SIMS analysis",
abstract = "Aqueous corrosion of zirconium alloys has become the major factor limiting prolonged fuel campaigns in nuclear plant. Studies using SEM, TEM and electrochemical impedance measurements have been interpreted as showing a dense inner-most oxide layer, and an increased thickness of the layer has been correlated to a better corrosion resistance. Many authors have reported that an 'intermediate layer' at the metal oxide interface has a complex structure or/and stochiometry different to that of both the bulk oxide and bulk metal, sometimes claimed to be a suboxide phase. Diffraction evidence has suggested the presence of both cubic ZrO and rhombohedral Zr 3O phases, and compositional analysis has revealed similar variations in local oxygen stoichiometry. We have carried out a systematic investigation of the structure and chemistry of the metal/oxide interface in samples of commercial ZIRLO corroded for times up to 180 days. We have developed new experimental techniques for the study of these interfaces both by Electron Energy Loss Spectroscopy (EELS) analysis in the Transmission Electron Microscope (TEM) and by Atom Probe Tomography (APT), and exactly the same samples have been investigated by both techniques. Our results show the development of a clearly defined suboxide layer of stoichiometry close to ZrO, and the subsequent disappearance of this layer at the first of the characteristic 'breakaway' transitions in the oxidation kinetics. We can correlate this behaviour with changes in the structure of the oxide layer, and particularly the development of interconnected porosity that links the corroding interface with the aqueous environment. Using high resolution SIMS analysis of isotopically spiked samples we demonstrate the penetration of the oxidising species through these porous outer oxide layers. {\textcopyright} 2012 Materials Research Society.",
keywords = "Aqueous corrosion, Aqueous environment, Atom-probe tomography, Bulk metals, Bulk oxides, Complex structure, Compositional analysis, Electrochemical impedance measurements, Experimental techniques, Fuel cladding, High resolution, Interconnected porosity, Intermediate layers, Major factors, Metal oxide interface, Nuclear plant, Oxidation kinetics, Oxide layer, Oxygen stoichiometry, Spiked samples, Stochiometry, Systematic investigations, Transmission electron microscope, Corrosion resistance, Metallic compounds, Stoichiometry, Transmission electron microscopy, Zirconium, Zirconium alloys, Electron energy loss spectroscopy",
author = "Grovenor, {C R M} and N Ni and D Hudson and Yardley, {S S} and Moore, {K L} and Smith, {G D W} and S Lozano-Perez and Sykes, {J M}",
note = "Conference code: 91734 Export Date: 26 January 2015 CODEN: MRSPD Correspondence Address: Grovenor, C.R.M.; Department of Materials, Oxford University, Parks Road, Oxford, OX1 3PH, United Kingdom References: Sabol, G.P., ZIRLO{\texttrademark} - An Alloy Development Success (2005) Zirconium in the Nuclear Industry: Fourteenth International Symposium, pp. 2-24. , ed. P. Rudling and B. Kammenzind American Society for Testing and Materials, Sweden; Cox, B., (2005) Journal of Nuclear Materials, 336, p. 331; Pickman, D.O., Zirconium Alloy Performance in Light Water Reactors: A Review of UK and Scandinavian Experience (1994) Zirconium in the Nuclear Industry: Tenth International Symposium, pp. 19-32. , ed. A.M. Garde and E.R. Bradley ASTM STP 1245, American Society for Testing and Materials; Nikulina, A.V., (2003) Metal Science and Heal Treatment, 45, p. 287; Lustman, B., Kerze, F., (1955) The Metallurgy of Zirconium, , McGraw-Hill Book Company, Michigan; Beie, H.-J., Mitwalsky, A., Garzarolli, F., Ruhmann, H., Sell, H.-J., Examinations of the Corrosion Mechanism of Zirconium Alloys (1993) Zirconium in the Nuclear Industry: Tenth International Symposium, pp. 615-643. , ed. A.M. Garde and E.R. Bradley ASTM International. Baltimore, MD; Lemaignan, C., Corrosion of Zirconium Alloy Components in Light Water Reactors (2006) ASM Handbook. 13C Corrosion: Environments and Industries, pp. 415-420; Ahmed, T., Keys, L.H., (1975) Journal of the Less-Common Metals, 39, p. 99; Park, D.J., Park, J.Y., Jeong, Y.H., Lee, J.Y., (2010) Journal of Nuclear Materials, 399, p. 208; Ploc, R.A., (1980) Journal of Nuclear Materials, 91, p. 322; Maroto, A.J.G., Bordoni, R., Villegas, M., Olmedo, A.M., Blesa, M.A., Iglesias, A., Koenig, P., (1996) Journal of Nuclear Materials, 229, p. 79; Bossis, P., Leli{\`e}vre, G., Barberis, P., Illis, X., Lefebvre, F., Thomas, L., Maguire, M., Multi-scale characterization of the metal-oxide interface of zirconium alloys (2000) Zirconium in the Nuclear Industry: Twelfth International Symposium, pp. 918-945. , ed. G. P. Sabol and G. D. Moan ASTM International; Kubo, T., Uno, M., Precipitate Behavior in Zircaloy-2 Oxide-Films and Its Relevance to Corrosion-Resistance (1990) Zirconium in the Nuclear Industry: Ninth International Symposium, pp. 476-496. , ed. C. M. Eucken and A. M. Garde ASTM International; Ni, N., Lozano-Perez, S., Jenkins, M.L., English, C., Smith, G.D.W., Sykes, J.M., Grovenor, C.R.M., (2010) Scripta Materialia, 62, p. 564; Wadman, B., Lai, Z., Nystrom, H.-O., Nystr{\"o}m, L.-A., Rudling, P., Pettersson, H., Microstructure of Oxide Layers Formed during Autoclave Testing of Zirconium Alloys (1993) Zirconium in the Nuclear Industry: Tenth International Symposium, pp. 579-598. , ed. A. M. Garde and E. R. Bradley ASTM International, Baltimore, MD; Wikmark, G., Rudling, P., Lehtinen, B., Hutchinson, B., Oscarsson, A., Ahlberg, E., The Importance of Oxide Morphology for the Oxidation Rate of Zirconium Alloys (1996) Zirconium in the Nuclear Industry: Eleventh International Symposium, pp. 55-73. , ed. E.R. Bradley and O.P. Sabol ASTM STP 1295; Yilmazbayhan, A., Breval, E., Motta, A.T., Comstock, R.J., (2006) Journal of Nuclear Materials, 349, p. 265; Iltis, X., Michel, H., (1991) Journal of Alloys and Compounds, 177, p. 71; Abolhassani, S., Barta, G., Jakobb, A., (2010) Journal of Nuclear Materials, 399, p. 1; Foord, D.T., Newcomb, S.B., Instabilities in the Oxidation Behaviour of Zircaloy-4 (1993) Microscopy of Oxidation-2, pp. 374-386. , ed. S. B. Newcomb and M. J. Bennett The institute of Materials; Furuta, T., Motohashi, H., (1980) Journal of Nuclear Materials, 95, p. 303; Anada, H., Takeda, K., Microstructure of Oxides on Zircaloy-4, 1.0Nb Zircaloy-4, and Zircaloy-2 Formed in 10.3-MPa Steam at 673 K (1995) Zirconium in the Nuclear Industry: Eleventh International Symposium, pp. 35-54. , ed. E. R. Bradley and G. P. Sabol American Society for Testing and Materials, Garmisch-Partenkirchen, Germany; Lozano-Perez, S., (2008) Micron, 39, p. 320; Ni, N., Lozano-Perez, S., Sykes, J., Grovenor, C., (2010) Ultramicroscopy, 111, p. 123; Miller, M.K., Russell, K.F., Thompson, G.B., (2005) Ultramicroscopy, 102, p. 287; Banerjee, S., Mukhopadhyay, P., (2007) Phase Transformations: Examples from Titanium and Zirconium Alloys, , Pergamon, Oxford; Ishii, Y., Sykes, J.M., (2000) Materials at High Temperatures, 17, p. 23; Foord, D.T., Newcomb, S.B., The Microstructural Characterization of Factors Which Determine the Degradation Behaviour of Zircaloy-4 (1996) Microscopy of Oxidation, 3, pp. 488-498. , ed. S.B. Newcomb and J.A. Little Henry Ling Ltd. Dorset, UK; 2011 MRS Fall Meeting ; Conference date: 01-01-1824",
year = "2012",
doi = "10.1557/opl.2012.521",
language = "English",
volume = "1383",
pages = "101--112",
booktitle = "host publication",
url = "http://www.scopus.com/inward/record.url?eid=2-s2.0-84864885184&partnerID=40&md5=b4b4fca561581c35b8178849f9067285",
}