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CORROSION RESISTANCE OF Zr-0.72Sn-0.32Fe- 0.14Cr-xNb ALLOYS IN 500 ℃ SUPERHEATED STEAM |
Boyang WANG1,Bangxin ZHOU1,2(),Zhen WANG1,Jiao HUANG1,Meiyi YAO1,2,Jun ZHOU3 |
1 Institute of Materials, Shanghai University, Shanghai 200072 2 Laboratory for Microstructures, Shanghai University, Shanghai 200444 3 Western Energy Material Technologies Co. Ltd., Xi'an 710016 |
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Cite this article:
Boyang WANG,Bangxin ZHOU,Zhen WANG,Jiao HUANG,Meiyi YAO,Jun ZHOU. CORROSION RESISTANCE OF Zr-0.72Sn-0.32Fe- 0.14Cr-xNb ALLOYS IN 500 ℃ SUPERHEATED STEAM. Acta Metall Sin, 2015, 51(12): 1545-1552.
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Abstract Zirconium alloys with low alloying content are mainly used in the nuclear industry as structural materials because of their superior properties in terms of thermal neutron transparency, mechanical strength and corrosion resistance. They are used for fuel cladding tubes and channels. The reaction between zirconium and water at high temperature forms oxide film on the surfaces. In order to further improve the corrosion resistance of Zr-based cladding tubes, research has continued on developing new zirconium alloys. The corrosion resistance of Zr-0.72Sn-0.32Fe-0.14Cr-xNb alloys (x=0, 0.12, 0.28, 0.48, 0.97, mass fraction, %) was investigated in a superheated steam at 500 ℃ and 10.3 MPa by autoclave tests. All the plate specimens of zirconium alloys with thickness of 2.8 mm have a similar texture. The microstructure of alloys and oxide films on the corroded specimens were observed by TEM and SEM. The results showed that no nodular corrosion appeared on these alloys for 500 h exposure. The thickness of oxide layers developed on the rolling surface (SN), the surface perpendicular to the rolling direction (SR) and the surface perpendicular to the transversal direction (ST) after 500 h exposure was close to each other. There was no anisotropic corrosion resistance for these alloys. The corrosion rate of the alloys increased with the increase of Nb content after 250 h exposure when the Nb content exceeded 0.28%. In the alloy with low Nb content, the fcc-Zr(Fe, Cr)2 or fcc-Zr(Fe, Cr, Nb)2 precipitate was mainly formed, while the hcp-Zr(Fe, Cr, Nb)2 precipitate was frequently observed in the alloy with high Nb content. The corrosion resistance of Zr-0.72Sn-0.32Fe-0.14Cr-xNb alloys was improved by decreasing the Nb/Fe ratio. From a point of view for the improving corrosion resistance, the addition of Nb no more than 0.3% is recommended.
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Fund: Supported by National Natural Science Foundation of China (No.51471102) |
[1] | Zhao W J, Zhou B X, Miao Z, Peng Q, Jiang Y R, Jiang H M, Pang H. Atom Energy Sci Technol, 2005; 39(suppl): 1 | [1] | (赵文金, 周邦新, 苗 志, 彭 倩, 蒋有荣, 蒋宏曼, 庞 华. 原子能科学技术, 2005; 39(增刊): 1) | [2] | Cox B. J Nucl Mater, 2005; 336: 331 | [3] | Sabol G P. In: Rudling P, Kammenzind B eds., Zirconium in the Nuclear Industry: Fourteenth International Symposium, ASTM STP 1467, Stockholm: ASTM, 2004: 3 | [4] | Sabol G P, Comstock R J, Weiner R A. In: Garde A M, Bradley E R eds., Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, Baltimore, MD: ASTM, 1994: 724 | [5] | Nikulina A V, Markelov V A, Peregud M M. In: Bradley E R, Sabol G P eds., Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, Garmisch-Partenkirchen, Germany: ASTM, 1996: 785 | [6] | Zhao W J. Rare Met Lett, 2004; 23(5): 15 | [6] | (赵文金. 稀有金属快报, 2004; 23(5): 15) | [7] | Zhou B X. J Met Heat Treat, 1997; 18(3): 8 | [7] | (周邦新. 金属热处理学报, 1997; 18(3): 8) | [8] | Liu W Q, Zhu X Y, Wang X J, Li Q, Yao M Y, Zhou B X. Atom Energy Sci Technol, 2010; 44: 1477 | [8] | (刘文庆, 朱晓勇, 王晓姣, 李 强, 姚美意, 周邦新. 原子能科学技术, 2010; 44: 1477) | [9] | Yao M Y, Zhou B X, Li Q, Xia S, Liu W Q. Shanghai Met, 2008; 30(6): 1 | [9] | (姚美意, 周邦新,李 强, 夏 爽, 刘文庆. 上海金属, 2008; 30(6): 1) | [10] | Zhao W J, Miao Z, Jiang H M, Yu X W, Li W J, Li C, Zhou B X. J Chin Soc Corros Prot, 2002; 22: 124 | [10] | (赵文金, 苗 志, 蒋宏曼, 于晓卫, 李卫军, 李 聪, 周邦新. 中国腐蚀与防护学报, 2002; 22: 124) | [11] | Zhou B X, Peng J C, Yao M Y, Li Q, Xia S, Du C X, Xu G. In: Limb?ck M, Barbéris P eds., Zirconium in the Nuclear Industry: Sixteenth International Symposium, ASTM STP 1529, Bridgeport: ASTM, 2011: 620 | [12] | Sun G C, Zhou B X, Yao M Y, Xie S J, Li Q. Acta Metall Sin, 2012; 48: 1103 | [12] | (孙国成, 周邦新, 姚美意, 谢世敬, 李 强. 金属学报, 2012; 48: 1103) | [13] | Yao M Y, Li S L, Zhang X, Peng J C, Zhou B X, Zhao X S, Shen J Y. Acta Metall Sin, 2011; 47: 865 | [13] | (姚美意, 李士炉, 张 欣, 彭剑超, 周邦新, 赵旭山, 沈剑韵. 金属学报, 2011; 47: 865) | [14] | Toffolon C, Brachet J C, Servant C, Legras L, Charquet D, Barberis P, Mardon J P. In: Moan G D, Rudling P eds., Zirconium in the Nuclear Industry: Thirteenth International Symposium, ASTM STP 1423, West Conshohochen: ASTM, 2002: 361 | [15] | Takeda K, Anada H. In: Sabol G P, Moan G D eds., Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, West Conshohochen: ASTM, 2000: 592 | [16] | Broy Y, Garzarolli F, Seibold A, van Swam L F. In: Sabol G P, Moan G D eds., Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, West Conshohochen: ASTM, 2000: 609 | [17] | Zhou B X, Li Q, Yao M Y, Liu W Q, Chu Y L. J ASTM Int, 2008; 5: 360 | [18] | Zhou B X, Li Q, Yao M Y, Liu W Q. Nucl Power Eng, 2005; 26: 364 | [18] | (周邦新, 李 强, 姚美意, 刘文庆. 核动力工程, 2005; 26: 364) | [19] | Zhou B X, Li Q, Huang Q, Miao Z, Zhao W J, Li C. Nucl Power Eng, 2000; 21: 339 | [19] | (周邦新, 李 强, 黄 强, 苗 志, 赵文金, 李 聪. 核动力工程, 2000; 21: 339) | [20] | Liu W Q, Li Q, Zhou B X, Yan Q S, Yao M Y. Nucl Power Eng, 2005; 26: 249 | [20] | (刘文庆, 李 强, 周邦新, 严青松, 姚美意. 核动力工程, 2005; 26: 249) | [21] | Zhou B X, Li Q, Liu W Q, Yao M Y, Chu Y L. Rare Met Mater Eng, 2006; 35: 1009 | [21] | (周邦新, 李 强, 刘文庆, 姚美意, 褚于良. 稀有金属材料与工程, 2006; 35: 1009) | [22] | Zhou B X, Li Q, Yao M Y, Xia S, Liu W Q, Chu Y L. Rare Met Mater Eng, 2007; 36: 1129 | [22] | (周邦新, 李 强, 姚美意, 夏 爽, 刘文庆, 褚于良. 稀有金属材料与工程, 2007; 36: 1129) | [23] | Zhou B X, Yao M Y, Li Q, Xia S, Liu W Q, Chu Y L. Rare Met Mater Eng, 2007; 36: 1317 | [23] | (周邦新, 姚美意, 李 强, 夏 爽, 刘文庆, 褚于良. 稀有金属材料与工程, 2007; 36: 1317) | [24] | Sun G C. Master Thesis, Shanghai University, 2012 | [24] | (孙国成. 上海大学硕士学位论文, 2012) | [25] | Woo O T, Griffiths M. J Nucl Mater, 2009; 384: 77 | [26] | Kim H G, Park J Y, Jeong Y H. J Nucl Mater, 2005; 345: 1 |
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