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超级奥氏体不锈钢AL-6XN在超临界水中的腐蚀行为

CORROSION BEHAVIOR OF SUPER-AUSTENITIC STAINLESS STEEL AL-6XN IN SUPERCRITICAL WATER
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摘要 研究了超级奥氏体不锈钢AL-6XN在500℃,550℃和600℃/25 MPa超临界水中的腐蚀行为,通过扫描电镜-电子能谱(SEM-EDX)、X射线衍射(XRD)和X射线光电子能谱(XPS)分析了氧化膜的显微形貌、组织结构与成分分布。结果表明,氧化膜为双层结构,氧化膜中含Fe_3O_4,Cr_2O_3,Fe_2O_3和FeCr_2O_4相。AL-6XN在超临界水中氧化膜存在脱落现象,脱落程度随温度升高而加剧。 The corrosion behavior of super-austenitic stainless steel AL-6XN exposed to supercritical wa- ter (SCW) at 500℃, 550 ℃, 600 ℃/25 MPa respectively was investigated by means of mass loss method, scanning electron microscope/energy dispersive X-ray spectroscopy, X-ray diffraction and X-ray photoelectron spectroscopy. A dual-layered oxide scale formed on AL-6XN, which was mainly composed of Fe3O4, Cr2O3, Fe2O3 and FeCr2O4. The oxide scale had a tendency to spall, which increased with the increase of exposure temperature.
出处 《中国腐蚀与防护学报》 CAS CSCD 北大核心 2012年第5期375-380,共6页 Journal of Chinese Society For Corrosion and Protection
基金 核能开发项目国家重点基础研究发展规划项目(2007CB209800)资助
关键词 超级奥氏体不锈钢AL-6XN 超临界水 氧化 氧化膜脱落 super-austenitic stainless steel AL-6XN, supercritical water, oxidation, oxide scale spalling
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参考文献9

  • 1Was G S, Ampornrat P, Gupta G, et al. Corrosion and stress corrosion cracking in supercritical water [J]. Nucl. Mater., 2007, 371 (1-3): 176-201.
  • 2Li H, Nishimura A, Yang W, et al. Low Activation Fer- ritic/Martensitic Steel, Potential Core Structure Mate- rial of Supercritical Water Cooled Reactor [A]. The 3rd International Symposium on Supercritical Water-cooled Reactors-Design and Technology[C]. Shanghai: 2007.
  • 3尹开锯,邱绍宇,唐睿,张强,张乐福,刘鸿.铁素体-马氏体钢P91和P92在超临界水中腐蚀后氧化膜多孔性分析[J].中国腐蚀与防护学报,2010,30(1):1-5. 被引量:16
  • 4Abed H F, Voyiadjis Z G. Plastic deformation modeling of AL-6XN stainless steel at low and high strain rates and temperatures using a combination of bcc and fcc mecha- nisms of metals [J]. J. Plasticity, 2005, 21:1618-1639.
  • 5Wright I G, Tortorelli P F. Oxide growth and exfoliation on alloys exposed to steam[A]. Program on Technology In- novation [C]. Palo Alto: 2007.
  • 6Zielinsky W, Kurzylowski K J. TEM study of the oxide scales formed on type 316 SS during annealing at 600 X2 in a vacuum and air [J]. Scr. Mater., 2000, 43:33-37.
  • 7Zhang Q, Tang R, Yin K J, et al. Corrosion behavior of hastelloy C-276 in supercritical water [J]. Corros. Sci., 2009, 51:2092-2097.
  • 8Bradford S A. Fundamentals of Corrosion in Gases, Met- Ms[M]. OH: ASM International, 1987.
  • 9Graham M J, Hussey R J. Transport in Growing Oxide Films, Oxidation of Metals and Associated Mass Trans- port[M]. Warrendale: The Metallurgical Society Inc, 1987.

二级参考文献16

  • 1高欣,吴欣强,关辉,韩恩厚.高温高压水环境中腐蚀产物膜的研究现状[J].腐蚀科学与防护技术,2007,19(2):110-113. 被引量:15
  • 2K. Kataoka, S. Shiga, K. Moriya, Y. Oka, S. Yoshida, H. Takahashi, Proceedings of ICAPP’03, Cordoba Spain, May 4–7, 2003, Paper No. 3258.
  • 3S. Teysseyre, J. McKinley, G.S. Was, D.B. Mitton, H. Kim, J.-K. Kim, R.M. Latanision, Proceedings of the 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems- Water Reactors, Stevenson, Washington, August 10–14, 2004, pp. 63–72.
  • 4Pantip Ampornrat, Gary S. Was. Oxidation of ferritic–martensitic alloys P91, HCM12A and HT-9 in supercritical water. Journal of Nuclear Materials 371 (2007) 1–17.
  • 5R. L. Klueh, D. R. Harries, Development of high (7-12%) chromium martensitic steels. High-Chromium Ferritic and Martensitic Steels for Nuclear Applications, SATM International, 2001.
  • 6F. Abe, M. Taneike, K. Sawada. Alloy design of creep resistant 9Cr steel using a dispersion of nano-sized carbonitrides, International Journal of Pressure Vessels and Piping 84 (2007) 3–12.
  • 7Bumjoon Kim, Chanseo Jeong, Byeongsoo Lim, Creep behavior and microstructural damage of martensitic P92 steel weldment, Materials Science and Engineering A 483–484 (2008) 544–546.
  • 8L. Tan, Y. Yang, T.R. Allen. Oxidation behavior of iron-based alloy HCM12A exposed in supercritical water, Corrosion Science 48(2006) 3123-3138.
  • 9G.S. Was, P. Ampornrat, G. Gupta. Corrosion and stress corrosion cracking in supercritical water. Journal of Nuclear Materials 371(2007)176-201.
  • 10A. Fry, S. Osgerby, M. Wright, Oxidation of Alloys in Steam Environments – A Review, National Physical Laboratory (NPL) Report MATC(A)90, September, 2002.

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