奥氏体不锈钢AL-6XN在超临界水中的腐蚀行为
Corrosion Behavior of Austenitic Stainless Steel AL-6XN in Supercritical Water Environment
摘 要
采用增重法对奥氏体不锈钢AL-6XN在500 ℃/25 MPa超临界水(SCW)中的腐蚀行为进行试验研究, 利用SEM和XRD对表面氧化膜的成分和结构进行了分析。结果表明, AL-6XN在SCW中的腐蚀动力学遵循抛物线规律, 局部表面发生了点蚀; 氧化膜为双层结构, 内层为致密的Cr2O3和FeCr2O4混合物, 外层为较疏松的Fe3O4且分布着氧化物颗粒。
超临界水
腐蚀
氧化膜结构
austenite stainless steel AL-6XN
supercritical water
corrosion
oxide scale structure
Abstract
Corrosion behavior of AL-6XN exposed in supercritical water (SCW) at 500 ℃/25 MPa was investigated by means of gravimetry, and the structure and chemical composition of the oxide films were examined by scanning electron microscopy (SEM) equipped with an energy-dispersive X-ray spectrometer (EDS) and X-ray diffraction (XRD). The results show that AL-6XN approximately followed parabolic oxidation kinetics the SCW conditions. Pits can be observed on AL-6XN samples exposed in SCW. Duplex layer oxide structures under conposing of a compact inner Cr2O3/FeCr2O4 mixture layer and porous Fe3O4 outer layer developed on all samples exposed to SCW, oxide particles can be observed on sample surface.
中图分类号 TG174.3
所属栏目 试验研究
基金项目 江苏省自然科学基金(BK2011317); 中国广东核电集团项目(CGNPC2010S096-09)
收稿日期 2011/12/6
修改稿日期
网络出版日期
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备注乔岩欣, 工程师, 博士,
引用该论文: QIAO Yan-xin,REN Ai,LIU Fei-hua,ZHENG Yu-gui,TANG Rui,GUO Li-ping. Corrosion Behavior of Austenitic Stainless Steel AL-6XN in Supercritical Water Environment[J]. Corrosion & Protection, 2012, 33(11): 960
被引情况:
【1】程从前,刘宜萱,赵杰, "几种耐热钢在超(超)临界水中抗氧化性能的比较",机械工程材料 38, 55-58(2014)
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参考文献
【1】Totemeier T C, Clark D E. Effect of transient thermal cycles in a supercritical water-cooled reactor on the microstructure and properties of ferritic-martensitic steels[J]. J Nucl Mater, 2006, 355:104-113.
【2】朱发文, 张乐福, 唐睿, 等. 奥氏体304NG不锈钢在550 ℃/25 MPa超临界水中的腐蚀行为[J]. 原子能科学技术, 2009, 46(9):1093-1098.
【3】姜峨, 文燕, 刘然超, 等. 304NG不锈钢均匀腐蚀性能研究[J]. 核动力工程, 2005, 26(4):390-392.
【4】张丽, 韩恩厚, 张召恩, 等. 不锈钢及镍基合金在亚临界水环境中的腐蚀[J]. 金属学报, 2003, 39:649-654.
【5】Kriksunov L B, MacDonald D D. Potential-pH diagrams for iron in supercritical water[J]. Corrosion, 1997, 53:605-611.
【6】Tan L, Ren X, Sridharan K, et al. Corrosion behavior of Ni-base alloys for advanced high temperature water-cooled nuclear plants[J]. Corros Sci, 2008, 50:3056-3062.
【7】Lin L F, Cragnolino G, Szklarska-smialowska Z, et al. Stress corrosion cracking of sensitized type 304 stainless steel in high temperature chloride solutions[J]. Corrosion, 1981, 37:616-625.
【8】Zurek J, Wessel E, Niewolak L, et al. Anomalous temperature dependence of oxidation kinetics during steam oxidation of ferritic steels in the temperature range 550~650 ℃[J]. Corros Sci, 2004, 46:2301-2317.
【9】Sun M C, Wu X Q, Zhang Z E, et al. Oxidation of 316 stainless steel in supercritical water[J]. Corros Sci, 2009, 51:1069-1072.
【10】Was G S, Teysseyre S, Jiao Z. Corrosion of austenitic alloys in supercritical water[J]. Corrosion, 2006, 62:989-1005.
【11】Panter J, Viguier B, Cloue J M, et al. Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600[J]. J Nucl Mater, 2006, 348:213-221.
【12】李美栓. 金属的高温腐蚀[M]. 北京:冶金工业出版社, 2001.
【13】Oxide Growth and Exfoliation on Alloy Exposed to Steam[R]. EPRI, Palo Alto CA:2007, 1013666.
【14】Bradford S A. Fundamentals of Corrosion in Gases in Metals Handbook[M]. Ninth Ed. volume 13, Corrosion, ASM International, Metals Park, OH 1987, 13:68.
【15】尹开锯, 邱绍宇, 唐睿, 等. 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, 30:1-5.
【16】Halvarsson M, Tang J E, Asteman H, et al. Microstructural investigation of the breakdown of the protective oxide scale on a 304 steel in the presence of oxygen and water vapour at 600 ℃[J]. Corros Sci, 2006, 48:2014.
【2】朱发文, 张乐福, 唐睿, 等. 奥氏体304NG不锈钢在550 ℃/25 MPa超临界水中的腐蚀行为[J]. 原子能科学技术, 2009, 46(9):1093-1098.
【3】姜峨, 文燕, 刘然超, 等. 304NG不锈钢均匀腐蚀性能研究[J]. 核动力工程, 2005, 26(4):390-392.
【4】张丽, 韩恩厚, 张召恩, 等. 不锈钢及镍基合金在亚临界水环境中的腐蚀[J]. 金属学报, 2003, 39:649-654.
【5】Kriksunov L B, MacDonald D D. Potential-pH diagrams for iron in supercritical water[J]. Corrosion, 1997, 53:605-611.
【6】Tan L, Ren X, Sridharan K, et al. Corrosion behavior of Ni-base alloys for advanced high temperature water-cooled nuclear plants[J]. Corros Sci, 2008, 50:3056-3062.
【7】Lin L F, Cragnolino G, Szklarska-smialowska Z, et al. Stress corrosion cracking of sensitized type 304 stainless steel in high temperature chloride solutions[J]. Corrosion, 1981, 37:616-625.
【8】Zurek J, Wessel E, Niewolak L, et al. Anomalous temperature dependence of oxidation kinetics during steam oxidation of ferritic steels in the temperature range 550~650 ℃[J]. Corros Sci, 2004, 46:2301-2317.
【9】Sun M C, Wu X Q, Zhang Z E, et al. Oxidation of 316 stainless steel in supercritical water[J]. Corros Sci, 2009, 51:1069-1072.
【10】Was G S, Teysseyre S, Jiao Z. Corrosion of austenitic alloys in supercritical water[J]. Corrosion, 2006, 62:989-1005.
【11】Panter J, Viguier B, Cloue J M, et al. Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600[J]. J Nucl Mater, 2006, 348:213-221.
【12】李美栓. 金属的高温腐蚀[M]. 北京:冶金工业出版社, 2001.
【13】Oxide Growth and Exfoliation on Alloy Exposed to Steam[R]. EPRI, Palo Alto CA:2007, 1013666.
【14】Bradford S A. Fundamentals of Corrosion in Gases in Metals Handbook[M]. Ninth Ed. volume 13, Corrosion, ASM International, Metals Park, OH 1987, 13:68.
【15】尹开锯, 邱绍宇, 唐睿, 等. 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, 30:1-5.
【16】Halvarsson M, Tang J E, Asteman H, et al. Microstructural investigation of the breakdown of the protective oxide scale on a 304 steel in the presence of oxygen and water vapour at 600 ℃[J]. Corros Sci, 2006, 48:2014.
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