STUDY ON THE CORROSION RESISTANCE OF Zr–0.7Sn–0.35Nb–0.3Fe–xGe ALLOY IN LITHIATEDWATER AT HIGH TEMPERATURE UNDER HIGH PRESSURE

  • XIE Xingfei ZHANG Jinlong ZHU Li YAO Meiyi ZHOU Bangxin PENG Jianchao
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  • 1. Laboratory for Microstructures, Shanghai University, Shanghai 200444
    2. Institute of Materials, Shanghai University, Shanghai 200072

Received date: 2012-07-19

  Revised date: 2012-09-18

  Online published: 2012-12-11

Supported by

Supported by National Natural Science Foundation of China (No.50971084) and National Advanced Pressurized Water Reactor Project of China (No.2011ZX06004–023)

Abstract

The corrosion resistance of Zr–0.7Sn–0.35Nb–0.3Fe–xGe (x=0.05, 0.1, 0.2, mass fraction, %) alloys was investigated in lithiated water with 0.01 mol/L LiOH at 360 /18.6 MPa by autoclave tests. The microstructures of the alloys and oxide films on the corroded specimens were observed by TEM and SEM. The results show that the corrosion resistance of the Zr–0.7Sn–0.35Nb–0.3Fe alloys in lithiated water at high temperature under high pressure is markedly improved by Ge addition. The alloy with 0.1%Ge shows the best corrosion resistance. In Zr–0.7Sn–0.35Nb–0.3Fe–xGe alloys, there exists fine Zr(Fe, Cr, Nb)2 and Zr(Fe, Cr, Nb, Ge)2 second phase particles (SPPs) with a close–packed hexagonal crystal structure (hcp) and coarse Zr3Ge SPPs with a tetragonal crystal structure (TET). The oxide films formed on the Zr–0.7Sn–0.35Nb–0.3Fe–0.1Ge alloys corroded for 220 d are compact and thin. The micro–pores and micro–cracks are hardly detected and many ZrO2 columnar grains exist in the oxide films formed on the Zr–0.7Sn–0.35Nb–0.3Fe–0.1Ge alloys. This indicates that the suitable amount of Ge could not only delay the process that the vacancies diffuse to form micro–pores and micro–pores develop to form micro–cracks, but also could retard the evolution from ZrO2 columnar grains to ZrO2 equiaxed grains.

Cite this article

XIE Xingfei ZHANG Jinlong ZHU Li YAO Meiyi ZHOU Bangxin PENG Jianchao . STUDY ON THE CORROSION RESISTANCE OF Zr–0.7Sn–0.35Nb–0.3Fe–xGe ALLOY IN LITHIATEDWATER AT HIGH TEMPERATURE UNDER HIGH PRESSURE[J]. Acta Metall Sin, 2012 , 48(12) : 1487 -1494 . DOI: 10.3724/SP.J.1037.2012.00434

References

[1] Liu J Z. Structure Nuclear Materials. Beijing: Chemical Industry Press, 2007: 19

(刘建章. 核结构材料. 北京: 化学工业出版社, 2007: 19)

[2] Zhao W J, Zhou B X, Miao Z, Peng Q, Jiang Y R, Jiang H M, Pang H. Atom Energ Sci Technol, 2005; 39(suppl):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)

[3] Nikulina A V, Markelov V A. In: Bradley E R, Sabol G P eds., Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, Garmisch

Partenkirchen Germany: ASTM International, 1996: 785

[4] Sabol G P, Comstock R J. In: Garde A M, Bradley E R eds., Zirconium in the Nuclear Industry: 10th International Symposium, ASTM STP 1245, Baltimore, MD:

ASTM International, 1994: 724

[5] Jung Y I, Lee M H, Kim H G, Park J Y, Jeong Y H. J Alloys Compd, 2009; 479: 423

[6] Yang W D. Reactor Materials Science. 2nd Ed., Beijing: Atomic Energy Press, 2006: 260

(杨文斗. 反应堆材料学. 第二版, 北京: 原子能出版社, 2006: 260)

[7] Liu W Q, Zhu X Y, Wang X J, Li Q, Yao M Y, Zhou B X. Atom Energ Sci Technol, 2010; 44: 1477

(刘文庆, 朱晓勇, 王晓娇, 李强, 姚美意, 周邦新. 原子能科学技术, 2010; 44: 1477)

[8] Kim J M, Jeong Y H, Kim I S. J Nucl Mater, 2000; 280: 235

[9] Liu W Q, Li Q, Zhou B X, Yao M Y. Nucl Power Eng, 2003; 24(1): 33

(刘文庆, 李强, 周邦新, 姚美意. 核动力工程, 2003; 24(1): 33)

[10] Wang J K. Modern Ge Metallurgy. Beijing: Metallurgy Industry Press, 2005: 58

(王吉坤. 现代锗冶金. 北京: 冶金工业出版社, 2005: 58)

[11] Zhou B X, Li Q, Yao M Y, Liu W Q, Chu Y L. In: Kammenzind B, Limback M eds., Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505,

West Conshohochen: American Society for Testing and Materials, 2009: 360

[12] Schaffer M, Schaffer B, Ramasse Q. Ultramicroscopy, 2012; 114: 62

[13] Zhou B X, Yao M Y, Li Q, Xia S, Liu W Q, Chu Y L. Rare Met Mater Eng, 2007; 36: 1317

(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)

[14] Charquet D, Hahn R, Ortlib E. In: Van Swam L F P, Eucken C M eds., Zircorium in the Nuclear Industry: 8th International Symposium, ASTM STP 1023, Philadelphia:

ASTM International, 1989: 405

[15] Anada H, Takeda K. In: Sabol G P, Bradley E R eds., Zircorium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, Ann Arbor: ASTM International,

1996: 35

[16] Wadman B, Lai Z, Andren H O, Nystrom A L, Rudling P, Pettersson H. In: Garde A M, Bradley E R eds., Zirconium in the Nuclear Industry: 10th International Symposium

ASTM STP 1245, Ann Arbor: ASTM International, 1994: 579

[17] Zhou B X, Peng J C, Yao M Y, Li Q, Xia S, Du C X, Xu G. In: Limback M, Barb´eris P eds., Zirconium in the Nuclear Industry: 16th International Symposium, ASTM

STP 1529, Bridgeport: ASTM International, 2011: 620

[18] Zhang X, Yao M Y, Li S L, Zhou B X. Acta Metall Sin, 2011; 47: 1112

(张欣, 姚美意, 李士炉, 周邦新. 金属学报, 2011; 47: 1112)

[19] Zhou B X, Li Q, Liu W Q, Yao M Y, Chu Y L. Rare Met Mater Eng, 2006; 35: 1009

(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)

[20] Zhou B X, Li Q, Yao M Y, Liu W Q, Chu Y L. Corros Prot, 2009; 30: 589

(周邦新, 李强, 姚美意, 刘文庆, 褚于良. 腐蚀与防护, 2009; 30: 589)

[21] Li T F. Metal High Temperature Oxidation and Thermal Corrosion. Beijing: Chemical Industry Press, 2003: 51

(李铁藩. 金属高温氧化和热处理. 北京: 化学工业出版社, 2003: 51)

[22] Yang X L, Zhou B X, Jiang Y R, Li C. Nucl Power Eng, 1994; 15(1): 79

(杨晓林, 周邦新, 蒋有荣, 李聪. 核动力工程, 1994; 15(1): 79)

[23] Toffolon–Masclet C, Brachet J C, Jago G. J Nucl Mater, 2002; 305: 224

[24] Cao X X, Yao M Y, Peng J C, Zhou B X. Acta Metall Sin, 2011; 47: 882

(曹潇潇, 姚美意, 彭剑超, 周邦新. 金属学报, 2011; 47: 882)

[25] Yilmazbayhan A, Breval E. J Nucl Mater, 2006; 349: 265

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