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Effect of dissolved oxygen on corrosion behavior of Zr–0.85Sn–0.16Nb–0.37Fe–0.18Cr alloy in 500 °C and 10.3 MPa super-heated steam
Affiliation:1. Institute of Materials, Shanghai University, Shanghai 200072, China;2. Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China;1. Materials Performance Centre, University of Manchester, Grosvenor Street, Manchester, M17HS, UK;2. Westinghouse Electric Company, 1332 Beulah Road, Pittsburgh, PA 15235, USA;1. Department of Materials and Centre for Nuclear Engineering, Imperial College, London SW7 2AZ, UK;2. Department of Engineering, Engineering Building, Lancaster University, Lancaster LA1 4YW, UK;1. State Key Laboratory of Metal Matrix Composites, School of Material Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, PR China;2. School of Materials Engineering, Shanghai University of Engineering Science, Shanghai, 201620, PR China;1. National Nuclear Laboratory, Building D5, First Floor, Culham Science Centre, Abingdon, Oxfordshire, OX14 3DB, UK;2. National Nuclear Laboratory, Central Laboratory, Seascale, Cumbria, CA20 1PG, UK;3. University of Oxford, Department of Materials, Parks Road, Oxford, 3PH, UK;1. Department of Materials and Centre for Nuclear Engineering, Imperial College, London SW7 2AZ, UK;2. Department of Physics and Astronomy, University College London, Gower Street, London WC1E 6BT, UK;3. School of EE&T, University of New South Wales, Sydney, NSW 2052, Australia;4. Westinghouse Electric Company, Pittsburgh, PA 15235, USA;1. DEN-Service d’Etudes des Matériaux Irradiés, CEA, Université Paris-Saclay, F-91191, Gif-sur-Yvette, France;2. DEN-Service de la Corrosion et du Comportement des Matériaux dans leur Environnement, CEA, Université Paris-Saclay, F-91191, Gif-sur-Yvette Cedex, France;3. CNRS/CEA UMR 8587, CEA Saclay, F-91191, Gif-sur-Yvette, France;4. CNRS UMR 8635, GEMaC, 92195 Meudon Cedex, France;5. NIMBE, CEA, CNRS, Université Paris-Saclay, CEA Saclay, 91191 Gif sur Yvette Cedex, France;6. DEN-Service d’Etudes Mécanique et Thermique, CEA, Université Paris-Saclay, CEA Saclay, F-91191 Gif-sur-Yvette Cedex, France;7. IMMCL Chevreul, Université Lille 1 Science et Technologie, 59655 Villeneuve d’Ascq Cedex, France
Abstract:To better understand the role of dissolved oxygen (DO) in affecting corrosion behavior of zirconium alloys, the Zr–0.85Sn–0.16Nb–0.37Fe–0.18Cr (wt.%) alloy was corroded in super-heated steam at 500 °C and 10.3 MPa under 1×10?6 DO and deaeration conditions. The microstructure of the alloy and oxide films was investigated by SEM, TEM, EDS and EBSD. Results show that the corrosion is aggravated under 1×10?6 DO. Compared with the deaeration condition, the oxide film is looser, and has more micro-cracks and more uneven inner surface under DO condition. For the oxide film forming under deaeration condition, the selected area diffraction (SAED) spots of planes (002)m, and (101)t are strong, while those of the (001)m and are weak. However, for the oxide film forming under DO condition, the SAED spots of planes (111)m, (200)m and (101)t are strong, while those of the (100)m and (110)m are weak. The higher DO content in super-heated steam accelerates the growth of oxide films, thus decreasing the corrosion resistance of zirconium alloys.
Keywords:zirconium alloy  dissolved oxygen  corrosion  microstructure  oxide film  super-heated steam
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