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| CORROSION BEHAVIORS OF NUCLEAR-GRADE STAINLESS STEEL AND FERRITIC-MARTENSITIC STEEL IN SUPERCRITICAL WATER |
| ZHONG Xiangyu, WU Xinqiang, HAN En-Hou |
1) State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016
2) Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016 |
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Cite this article:
ZHONG Xiangyu WU Xinqiang HAN En-Hou. CORROSION BEHAVIORS OF NUCLEAR-GRADE STAINLESS STEEL AND FERRITIC-MARTENSITIC STEEL IN SUPERCRITICAL WATER. Acta Metall Sin, 2011, 47(7): 932-938.
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Abstract The corrosion behaviors of nuclear-grade 304 stainless steel (304SS) and ferritic-martensitic steel P92 exposed to 400℃/25 MPa supercritical water were investigated. The exposed specimens were characterized by weight gain measurement, XRD, Raman spectroscopy and SEM. It is found that both materials show general corrosion and exponential kinetics in mass gain, and the mass gain of 304SS is approximately an order of magnitude less than that of steel P92. The oxide film on 304SS is rather thin and composed of Cr2O3, α-Fe2O3, Fe3O4 and spinel, some nodules were observed on the surface. While the oxide film on steel P92 consists of α-Fe2O3, Fe3O4 and spinel, more α-Fe2O3 exist in the outer surface of the oxide film. The surface morphology of oxide film on steel P92 changes from dense particles to porous network structure with increasing exposure time, which may be relative to the dissolution of oxide.
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Received: 23 March 2011
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| Fund: Supported by National Basic Research Program of China (No.2011CB610501) and National Science and Technology Major Project (No.2011ZX06004-009}) |
| [1] A Technology Roadmap for Generation IV Nuclear Energy Systems. U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, 2002: 45[2] Was G S, Teysseyre S. In: Allen T R, King P J, Nelson L, eds., Proc 12th Int Conf Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Salt Lake City: TMS, 2005: 1343[3] Chen Y, Sridharan K, Allen T R. Corrosion 2007. Nashville, Tennessee: NACE, 2002: No.07408[4] Gao X,Wu X Q, Zhang Z E, Guan H, Han E H. J Supercrit Fluids, 2007; 42: 157[5] Sun M C, Wu X Q, Zhang Z E, Han E H. Corro Sci, 2009; 51: 1069[6] Was G S, Ampornrat P, Gupta G, Teysseyre S, West E A, Allen T R, Sridharan K, Tan L, Chen Y, Ren X, Pister C. J Nucl Mater, 2007; 371: 176[7] Was G S, Allen T R. American Nuclear Society–Int Congress on Advances in Nuclear Power Plants 2005, ICAPP’05, Seoul: American Nuclear Society, 2005: 3460[8] Tan L, Ren X, Allen T R. Corros Sci, 2010; 52: 1520[9] Tan L, Yang Y, Allen T R. Corros Sci, 2006; 48: 3123[10] Yin K, Qiu S, Tang R, Zhang Q, Zhang L. J Supercrit Fluids, 2009; 50: 235[11] Chen Y, Sridharan K, Allen T R. Corros Sci, 2006; 48: 2843[12] Robertson J. Corros Sci, 1991; 32: 443[13] Ziemniak S E. J Solution Chem, 1992; 21: 745[14] Lister D H, Davidson R D, Mcalpine E. Corros Sci, 1987; 27: 113[15] Kim J H, Hwang I S. Nucl Eng Des, 2005; 235: 1029[16] Maslar J E, Hurst W S, Bowers W J, Hendricks J H, Aquino M I. J Electrochem Soc, 2000; 147: 2532[17] Maslar J E, Hurst W S, Bowers W J, Hendricks J H, Aquino M I, Levin I. Appl Surf Sci, 2001; 180: 102[18] Miyazawa T, Terachi T, Uchida S, Satoh T, Tsukada T, Satoh Y, Wada Y, Hosokawa H. J Nucl Sci Technol, 2006; 43: 884[19] Halvarsson M, Tang J E, Asteman H, Sevensson J E, Johansson L G. Corros Sci, 2006; 48: 2014[20] Han E H, Wang J Q, Wu X Q, Ke W. Acta Metall Sin, 2010; 46: 1379(韩恩厚, 王俭秋, 吴欣强, 柯伟. 金属学报, 2010; 46: 1379)[21] Li M S. The Oxidation of Metals. Beijing: Metallurgy Industry Press, 2001: 37(李美栓. 金属的高温腐蚀, 北京: 冶金工业出版社, 2001: 37)[22] Ampornrat P, Was G S. J Nucl Mater, 2007; 371: 1[23] Kritzer P, Boukis N, Dinjus E. J Supercrit Fluids, 1999; 15: 205[24] Sue K, Tsujinaka N, Adschiri T, Arai K. Ind Eng Chem Res, 2002; 41: 3298[25] Sue K, Tsujinaka N, Adschiri T, Arai K, Watanabe Y. Corrosion 2002. Denver, Colorado: NACE, 2002: No.02354 |
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