奥氏体不锈钢AL-6XN在超临界水中的腐蚀
Corrosion Behavior of Austenitic AL-6XN Stainless Steel in Supercritical Water
摘 要
研究了奥氏体不锈钢AL-6XN在550 ℃,600 ℃和650 ℃超临界水中的腐蚀行为.采用扫描电镜、X射线能谱仪和X射线衍射仪观察氧化膜的腐蚀形貌、组织结构及元素成分分布.结果表明,AL-6XN不锈钢在超临界水中氧化膜的生长服从固态生长机制,600 ℃时的腐蚀增重量约为550 ℃时的3倍,而650 ℃时其腐蚀增重出现了大幅下降.试样表层形成了富Fe的磁晶石结构腐蚀产物颗粒,其氧化膜呈现双层结构,外层为Fe3O4结构,内层为FeCr2O4和(Ni,Fe)Fe2O4混合尖晶石结构.
超临界水
腐蚀性能
氧化膜
austenitic stainless steel
supercritical water
corrosion property
oxide film
Abstract
The corrosion behavior of AL-6XN stainless steel in supercritical water at 550 ℃,600 ℃ and 650 ℃ was investigated.Morphology,structure and elemental distribution of the oxide film were investigated by SEM,EDS and XRD.The results show that the oxide growth of AL-6XN stainless steel in supercritical water is believed to follow the solid-state growth mechanism,and the weight gained at 600 ℃ were approximately three times of that at 550 ℃,while the weight gained at 650 ℃ reduced drastically.Granular corrosion products with Fe-rich magnetite structure were observed on the surface,and the oxide scale exhibited a dual-layer structure and mainly consisted of an outer Fe3O4 structure and an inner FeCr2O4/(Ni,Fe)Fe2O4 mixed spinel structure.
中图分类号 TG172.8
所属栏目 试验研究
基金项目 国家“973”重点基础研究发展计划项目(2007CB209802)
收稿日期 2009/8/20
修改稿日期 2009/10/4
网络出版日期
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引用该论文: ZHU Fa-wen,ZHANG Le-fu,TANG Rui,QIAO Pei-peng,BAO Yi-chen. Corrosion Behavior of Austenitic AL-6XN Stainless Steel in Supercritical Water[J]. Corrosion & Protection, 2010, 31(8): 595～599
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参考文献
【1】A technology roadmap for generation Ⅳ nuclear energy systems[C]//US DOE Nuclear Energy Research Advisory Committee and the Generation Ⅳ International Forum,GIF-002-00,2002.
【2】Pantip Ampornrat,Gary S Was.Oxidation of ferritic-martensitic alloys T91,HCM12A and HT-9 in supercritical water[J].Journal of Nuclear Materials,2007,371(1/3):1-17.
【3】Chen Y,Sridharan K,Allen T R.Corrosion of candidate austenitic stainless steels for supercritical water reactors[C]//Paper 07408,Corrosion 2007.
【4】Tan L,Ren X,Sridharan K,et al.Corrosion behavior of Ni-base alloys for advanced high temperature water-cooled nuclear plants[J].Corrosion Science,2008,50:3056-3062.
【5】Cho H S,Kimura A,Ukai S,et al.Corrosion properties of oxide dispersion strengthened steels in super-critical water environment[J].Journal of Nuclear Materials,2004,329-333:387-391.
【6】Stellwag B.The mechanism of oxide film formation on austenitic stainless steels in high temperature water[J].Corrosion Science,1998,40:337-370.
【7】Gao X,Wu X Q,Zhang Z E,et al.Characterization of oxide films grown on 316L stainless steel exposed to H2O2-containing supercritical water[J].Journal of Supercritical Fluids,2007,42:157-163.
【8】Zhang Q,Tang R,Yin K J,et al.Corrosion behavior of Hastelloy C-276 in supercritical water[J].Corrosion Science,2009,51(9):2092-2097.
【9】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 vapor at 600 ℃[J].Corrosion Science,2006,48(8):2014-2035.
【10】Essuman E,Meier G H,Zurek J,et al.The effect of water vapor on selective oxidation of Fe-Cr alloys[J].Oxidation of Metals,2008,69:143-162.
【11】Elizabeth J Opila.Volatility of common protective oxides in high-temperature water vapor:current understanding and unanswered questions[C]//Mater Sci.Forum 2004:765-774.
【12】L Z W,H Y D,G W.Use of a solid-state oxygen pump to study oxidation kinetics of Cr and Mo[J].Oxidation of Metals,2000,53:577-596.
【13】Stearns C A,Kohl F J,Fryburg G C.Oxidative vaporization kinetics of Cr2O3 in oxygen from 1000 ℃ to 1300 ℃[J].J Electrochem Soc,1974,121:945-951.
【14】Solak N,Ustel F,Urgen M,et al.Oxidation behavior of molybdenum nitride coatings[J].Surface and Coating Technology,2003,174-175:713-719.
【2】Pantip Ampornrat,Gary S Was.Oxidation of ferritic-martensitic alloys T91,HCM12A and HT-9 in supercritical water[J].Journal of Nuclear Materials,2007,371(1/3):1-17.
【3】Chen Y,Sridharan K,Allen T R.Corrosion of candidate austenitic stainless steels for supercritical water reactors[C]//Paper 07408,Corrosion 2007.
【4】Tan L,Ren X,Sridharan K,et al.Corrosion behavior of Ni-base alloys for advanced high temperature water-cooled nuclear plants[J].Corrosion Science,2008,50:3056-3062.
【5】Cho H S,Kimura A,Ukai S,et al.Corrosion properties of oxide dispersion strengthened steels in super-critical water environment[J].Journal of Nuclear Materials,2004,329-333:387-391.
【6】Stellwag B.The mechanism of oxide film formation on austenitic stainless steels in high temperature water[J].Corrosion Science,1998,40:337-370.
【7】Gao X,Wu X Q,Zhang Z E,et al.Characterization of oxide films grown on 316L stainless steel exposed to H2O2-containing supercritical water[J].Journal of Supercritical Fluids,2007,42:157-163.
【8】Zhang Q,Tang R,Yin K J,et al.Corrosion behavior of Hastelloy C-276 in supercritical water[J].Corrosion Science,2009,51(9):2092-2097.
【9】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 vapor at 600 ℃[J].Corrosion Science,2006,48(8):2014-2035.
【10】Essuman E,Meier G H,Zurek J,et al.The effect of water vapor on selective oxidation of Fe-Cr alloys[J].Oxidation of Metals,2008,69:143-162.
【11】Elizabeth J Opila.Volatility of common protective oxides in high-temperature water vapor:current understanding and unanswered questions[C]//Mater Sci.Forum 2004:765-774.
【12】L Z W,H Y D,G W.Use of a solid-state oxygen pump to study oxidation kinetics of Cr and Mo[J].Oxidation of Metals,2000,53:577-596.
【13】Stearns C A,Kohl F J,Fryburg G C.Oxidative vaporization kinetics of Cr2O3 in oxygen from 1000 ℃ to 1300 ℃[J].J Electrochem Soc,1974,121:945-951.
【14】Solak N,Ustel F,Urgen M,et al.Oxidation behavior of molybdenum nitride coatings[J].Surface and Coating Technology,2003,174-175:713-719.
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