Zr-1Nb-<ITALIC>x</ITALIC>Ge合金在400 ℃过热蒸汽中耐腐蚀性能的研究

doi:10.11902/1005.4537.2013.084

中国腐蚀与防护学报

2014, Vol. 34

Issue (2): 171-177 DOI: 10.11902/1005.4537.2013.084

研究报告

本期目录 | 过刊浏览

Zr-1Nb-xGe合金在400 ℃过热蒸汽中耐腐蚀性能的研究

张金龙¹,², 屠礼明¹,², 谢兴飞¹,², 姚美意¹,², 周邦新¹,²

1. 上海大学微结构重点实验室上海 200444;
2. 上海大学材料研究所上海 200072

Corrosion Resistance of Zr-1Nb-xGe Alloys in Superheated Steam at 400 ℃

ZHANG Jinlong¹, ², TU Liming¹, ², XIE Xingfei¹, ², YAO Meiyi¹, ², ZHOU Bangxin¹, ²

1. Laboratory for Microstructures, Shanghai University, Shanghai 200444, China;
2. Institute of Materials, Shanghai University, Shanghai 200072, China

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摘要:

利用高压釜腐蚀实验研究了Zr-1Nb-xGe (x=0，0.05，0.1，0.2，质量分数，%) 合金在400 ℃，10.3 MPa过热蒸汽中的耐腐蚀性能；利用SEM和TEM分别观察了合金和氧化膜的显微组织。结果表明：添加Ge可以改善Zr-1Nb合金的耐腐蚀性能，当Ge含量为0.05%时效果最佳。在Zr-1Nb-xGe合金中存在4种第二相，分别是β-Nb，Zr(Nb，Fe，Cr)₂，Zr(Nb，Fe，Cr，Ge)₂和尺寸较大的Zr₃Ge。Ge在Zr-1Nb合金α-Zr基体中的最大固溶含量在0.05%~0.1%之间，固溶的Ge可以有效延缓氧化膜中显微组织的演化，从而改善合金的耐腐蚀性能；当Ge含量超过合金的固溶含量时，会形成Zr(Nb，Fe，Cr，Ge)₂以及尺寸较大的Zr₃Ge第二相，Zr₃Ge会使耐腐蚀性能降低。

关键词 ： Zr-1Nb合金, Ge, 耐腐蚀性能, 显微组织

Abstract：The corrosion resistance of Zr-1Nb-xGe(x=0, 0.05, 0.1, 0.2, mass fraction, %) alloys was investigated in superheated steam at 400 ℃, 10.3 MPa by autoclave tests. The microstructures of the alloys and oxide scales on the corroded specimens were observed by SEM and TEM. The results show that the corrosion resistance of the Zr-1Nb alloy in superheated steam at 400 ℃, 10.3 MPa may be enhanced by Ge addition. The alloy with 0.05% Ge shows the best corrosion resistance. In Zr-1Nb-xGe alloys, there are four types of second phase particles (SPPs), including β-Nb, Zr(Nb,Fe,Cr)₂, Zr(Nb,Fe,Cr,Ge)₂ and coarse Zr₃Ge SPPs, and the maximum solid solubility of Ge in the α-Zr matrix of Zr-1Nb alloy is 0.05%~0.1%. It is noted that the Ge solid soluted in the α-Zr matrix can effectively slow down the microstructural evolution of oxide scale, thereby enhancing the corrosion resistance of the alloy. When the Ge content exceeds its solid solubility, Ge was precipitated as Zr(Nb,Fe,Cr,Ge)₂ and Zr₃Ge SPPs. The coarse Zr₃Ge SPPs will decrease the corrosion resistance of the alloys.

Key words： Zr-1Nb alloy Ge corrosion resistance microstructure

收稿日期: 2013-05-21

ZTFLH:

TG174.3

基金资助:国家自然科学基金项目(50971084) 和国家先进压水堆重大专项 (2011ZX06004-023) 资助

通讯作者: jlzhang@shu.edu.cn

作者简介: 张金龙，男，1964年生，副研究员，研究方向为核材料

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引用本文:

张金龙, 屠礼明, 谢兴飞, 姚美意, 周邦新. Zr-1Nb-xGe合金在400 ℃过热蒸汽中耐腐蚀性能的研究[J]. 中国腐蚀与防护学报, 2014, 34(2): 171-177.
ZHANG Jinlong, TU Liming, XIE Xingfei, YAO Meiyi, ZHOU Bangxin. Corrosion Resistance of Zr-1Nb-xGe Alloys in Superheated Steam at 400 ℃. Journal of Chinese Society for Corrosion and protection, 2014, 34(2): 171-177.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2013.084 或 https://www.jcscp.org/CN/Y2014/V34/I2/171

[1] Liu J Z. Structure Nuclear Materials [M]. Beijing: Chemical Industry Press, 2007
(刘建章. 核结构材料 [M]. 北京: 化学工业出版社, 2007)
[2] Zhao W J, Zhou B X, Miao Z, et al. The development of high-performance zirconium alloy in China [J]. Atom. Energ. Sci. Technol., 2005, 39(suppl.): 1-9
(赵文金, 周邦新, 苗志等. 我国高性能锆合金的发展 [J]. 原子能科学技术, 2005, 39(增刊): 1-9)
[3] Sabol G P. An alloy development success [A]. Zirconium in the Nuclear Industry: Fourteenth International Symposium. ASTM STP 1467 [C]. Stockholm: ASTM International, 2004: 3-24
[4] Nikulina A V, Markelov V A, Peregud M M. Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores [A]. Zirconium in the Nuclear Industry: Eleventh International Symposium. ASTM STP 1295 [C]. Garmisch-Partenkirchen: ASTM International, 1996: 785-804
[5] Zhou B X, Zhao W J, Mao Z, et al. New Zirconium Alloy Research [M]. Beijing: Chemical Industry Press, 1997
(周邦新, 赵文金, 苗志等. 新锆合金的研究 [M]. 北京: 化学工业出版社, 1997)
[6] Zhao W J. The research of high-performance zirconium alloy in nuclear industry [J]. Rare Met. Lett., 2004, 23(5): 15-20
(赵文金. 核工业用高性能锆合金的研究 [J]. 稀有金属快报, 2004, 23(5): 15-20)
[7] Park J Y, Choi B K, Yoo S J, et al. Corrosion behavior and oxide properties of Zr-1.1 wt% Nb-0.05 wt% Cu alloy [J]. J. Nucl. Mater., 2006, 359: 59-68
[8] Yao M Y, Zou L H, Xie X F, et al. Effect of Bi addition on the corrosion resistance of Zr-4 in superheated steam at 400 ℃/10.3 MPa [J]. Acta Metall. Sin., 2012, 48: 1097-1102
(姚美意, 邹玲红, 谢兴飞等. 添加Bi对Zr-4合金在400 ℃/10.3 MPa过热蒸汽中耐腐蚀性能的影响 [J]. 金属学报, 2012, 48: 1097-1102)
[9] Zhu L, Yao M Y, Sun G C, et al. Effect of Bi addition on the corrosion resistance of Zr-1Nb alloy in deionized water at 360 ℃ and 18.6 MPa [J]. Acta Metall. Sin., 2013, 49: 51-57
(朱莉, 姚美意, 孙国成等. 添加Bi对Zr-1Nb合金在360 ℃和18.6 MPa去离子水中耐腐蚀性能的影响 [J]. 金属学报, 2013, 49: 51-57)
[10] Xie X F, Zhang J L, Zhu L, et al. Study on the corrosion resistance of Zr-0.7Sn-0.35Nb-0.3Fe-xGe alloy in lithiated water at high temperature under high pressure [J]. Acta Metall. Sin., 2012, 48(12): 1487-1494
(谢兴飞, 张金龙, 朱莉等. Zr-0.7Sn-0.35Nb-0.3Fe-xGe 合金在高温高压LiOH水溶液中耐腐蚀性能的研究 [J]. 金属学报, 2012, 48(12): 1487-1494)
[11] Li S L, Yao M Y, Zhang X, et al. Effect of Cu addition on the corrosion resistance of M5 alloy in superheated steam at 500 ℃ [J]. Acta Metall. Sin., 2011, 47:163-168
(李士炉, 姚美意, 张欣等. 添加Cu对M5合金在500 ℃过热蒸汽中耐腐蚀性能的影响 [J]. 金属学报, 2011, 47: 163-168)
[12] Charquet D, Hahn R, Ortlib E, et al. Solubility limits and for mation of intermetallic precipitates in ZrSnFeCr alloys [A]. Zircorium in the Nuclear Industry: 8th International Symposium. ASTM STP 1023 [C]. Philadelphia: ASTM International, 1989: 405-422
[13] Anada H, Herb B J, Nomoto K, et al. Effect of annealing temperature on corrosion behavior and ZrO₂ microstructure of zircaloy-4 cladding tube [A]. Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295 [C]. Garmisch-Partenkirchen Germany: ASTM International, 1996: 74-93
[14] Yao M Y, Zhou B X, Li Q, et al. A superior corrosion behavior of Zircaloy-4 in lithiated water at 360 ℃/18.6 MPa by β-quenching [J]. J. Nucl. Mater., 2008, 374: 197-203
[15] Jeong Y H, Kim H G, Kim T H. Effect of β phase, precipitates and Nb-concentaration in matrix on corrosion and oxide characterstics of Zr-xNb alloys [J]. J. Nucl. Mater., 2003, 317: 1-12
[16] Rudling P, Wikmark G. A unified model of Zircaloy BWR corrosion and hydriding mechanisms [J]. J. Nucl. Mater., 1999, 265: 44-59
[17] Comstock R J, Schoenberger G, Sable G P. Influence of processing variables and alloy chemistry on the corrosion behavior of ZIRLO nuclear fuel cladding [A]. Zirconium in the Nuclear Industry: Eleventh International Symposium. ASTM STP 1295 [C]. Garmisch-Partenkirchen Germany: 1996: 710-725
[18] Zhou B X, Li Q, Yao M Y, et al. Effect of water chemistry and composition on microstructural evolution of oxide on Zr alloys [A]. Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505 [C]. Sunriver Oregon: ASTM International, 2008: 360-380
[19] Zhou B X, Li Q, Yao M Y, et al. Study on the microstructure of Zr-4 alloy oxide film [J]. Corros. Prot., 2009, 30: 589-594
(周邦新, 李强, 姚美意等. Zr-4合金氧化膜的显微组织研究 [J]. 腐蚀与防护, 2009, 30: 589-594)
[20] Zhou B X, Li Q, Liu W Q, et al. The effects of water chemistry and composition on the microstructure evolution of oxide films on zirconium alloys during autoclave tests [J]. Rare Met., 2006, 35: 1009-1016
(周邦新, 李强, 刘文庆等. 水化学及合金成分对锆合金腐蚀时氧化膜显微组织演化的影响 [J]. 稀有金属材料与工程, 2006, 35: 1009-1016)
[21] Wang J K. Modern Ge Metallurgy [M]. Beijing: Metallurgy Industry Press, 2005
(王吉坤. 现代锗冶金 [M]. 北京: 冶金工业出版社, 2005)
[22] Li T F. Metal High Temperature Oxidation and Thermal Corrosion [M]. Beijing: Chemical Industry Press, 2003
(李铁藩. 金属高温氧化和热处理 [M]. 北京: 化学工业出版社, 2003)
[23] Weidinger H G, Ruhmann H, Cheliotis G, et al. Corrosion-electrochemical properties of zirconium intermetallics [A]. Zirconium in the Nuclear Industry: 9th International Symposium, ASTM STP 1132 [C]. Kobe Japan: ASTM International, 1991: 499-535
[24] Toffolon-Masclet C, Brachet J C, Jago G. Studies of second phase particles in different zirconium alloys using extractive carbon replica and an electrolytic anodic dissolution procedure [J]. J. Nucl. Mater., 2002, 305: 224-231
[25] Cao X X, Yao M Y, Peng J C, et al. Corrosion behaviour of Zr(Fe_x,Cr_1-_x)₂ alloys in 400 ℃ superheated steam [J]. Acta Metall. Sin., 2011, 47: 882-886
(曹潇潇, 姚美意, 彭剑超等. Zr(Fe_x, Cr_1-_x)₂合金在 400 ℃过热蒸汽中的腐蚀行为 [J]. 金属学报, 2011, 47: 882-886)

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