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EFFECT OF Ni2+ IN OCCLUDED VOLUME ON THE OXIDATION BEHAVIOR OF 304 STAINLESS STEEL IN HIGH TEMPERATURE WATER |
KUANG Wenjun, 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:
KUANG Wenjun WU Xinqiang HAN En-Hou. EFFECT OF Ni2+ IN OCCLUDED VOLUME ON THE OXIDATION BEHAVIOR OF 304 STAINLESS STEEL IN HIGH TEMPERATURE WATER. Acta Metall Sin, 2011, 47(7): 927-931.
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Abstract In the occluded volume of high temperature pressurized water loop in nuclear power plants, poor-controlled water chemistry due to sluggish flowage could induce accelerated degradation of structural materials. In this paper, an occluded volume shaped nuclear-grade 304 stainless steel sample was immersed in oxygenated high temperature water containing a certain concentration of Ni2+. It was found that from the outer to the inner side of the sample, the proportion of spinel in the oxide film decreased while that of hematite increased and Ni content in the outer oxide film decreased. It was thought that the concentration of Ni2+ could influence the oxidation behavior of material significantly. The occluded volume could impede the inward diffusion of Ni2+, causing a concentration gradient of Ni2+ along depth of the volume and gradual change of oxide film characteristic.
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Received: 23 March 2011
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Fund: Supported by National Natural Science Foundation of China (No.50871113), National Basic Research Program of China (No. 2011CB610506) and National Science and Technology Major Project (No.2011ZX06004-010) |
[1] Ford F P, Gordon B M, Horn R M. ASM Handbook. ASM International, 2006: 341[2] Scott P M, Combrade P. ASM Handbook. ASM International, 2006: 363[3] Kim Y J. Corrosion, 1999; 55: 81[4] Miyazawa T, Terachi T, Uchida S, Satoh T, Tsukada T, Satoh Y, Wada Y, Hosokawa H. J Nucl Sci Technol, 2006; 43: 884[5] Terachi T, Arioka K. NACE, Houston, TX, 2006, Paper No.06608[6] Kuang W J, Wu X Q, Han E H. Corros Sci, 2010; 52: 4081[7] Ziemniak S E, Hanson M. Corros Sci, 2002; 44: 2209[8] Kuang W J, Han E H, Wu X Q, Rao J C. Corros Sci, 2010; 52: 3654[9] Kuang W J, Wu X Q, Han E H, Ruan L Q. Corros Sci, 2011; 53: 1107[10] Kumai C S, Devine T M. Corrosion, 2007; 63: 1101[11] Thierry D, Persson D, Leygraf C, Boucherit N, Hugotlegoff A. Corros Sci, 1991; 32: 273[12] Oblonsky L J, Devine T M. Corros Sci, 1995; 37: 17[13] Maslar J E, Hurst W S, Bowers W J, Hendricks J H, Aquino M I. J Electrochem Soc, 2000; 147: 2532[14] Maslar J E, Hurst W S, Bowers W J, Hendricks J H. Corrosion, 2002; 58: 739[15] Stellwag B. Corros Sci, 1998; 40: 337[16] Kim Y J, Andresen P L. Corrosion, 2003; 59: 511[17] Kim U C, Kim K M, Kang J S, Lee E H, Kim H P. J Nucl Mater, 2002; 302: 104 |
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