EFFECT OF Bi ADDITION ON THE CORROSION RESISTANCE OF Zr-1Nb ALLOY IN DEIONIZED WATER AT 360 ℃ AND 18.6 MPa

ZHU Li; YAO Meiyi; SUN Guocheng; CHEN Wenjue; ZHANG Jinlong; ZHOU Bangxin

doi:10.3724/SP.J.1037.2012.00378

Acta Metall Sin >

2013 , Vol. 49 >Issue 1: 51 - 57

DOI: https://doi.org/10.3724/SP.J.1037.2012.00378

EFFECT OF Bi ADDITION ON THE CORROSION RESISTANCE OF Zr-1Nb ALLOY IN DEIONIZED WATER AT 360 ℃ AND 18.6 MPa

ZHU Li ,
YAO Meiyi ,
SUN Guocheng ,
CHEN Wenjue ,
ZHANG Jinlong ,
ZHOU Bangxin

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

Received date: 2012-06-27

Revised date: 2012-10-11

Online published: 2013-01-11

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Abstract

The effect of Bi contents on the corrosion resistance of Zr-1Nb-xBi (x=0.05-0.3, mass fraction, %) was investigated in deionized water at 360 ℃ and 18.6 MPa by autoclave tests. The results show that the corrosion resistance of Zr-1Nb alloy can be improved by adding Bi,and the more the Bi content is, the better the corrosion resistance is.TEM and EDS analyses on the microstructures of the alloys show that there are two types of second phase particles (SPPs), including ZrNbFe and β-Nb. The Bi contents have little effect on the type, size and amount of SPPs, 0.3%Bi can be completely dissolved in α-Zr matrix and has no influence on the solution content of Nb inα-Zr matrix. From the fracture and inner surface morphology of oxide films observed by SEM, it can be seen that the Bi dissolved in theα-Zr could noticeably slow down the microstructural evolution of oxide film, including the propagation of micro--cracks and the transformation from columnar grains to equiaxed grains in the oxide film.

Key words：

Zr-1Nb alloy

; Bi; corrosion resistance; microstructure

Cite this article

ZHU Li , YAO Meiyi , SUN Guocheng , CHEN Wenjue , ZHANG Jinlong , ZHOU Bangxin . 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(1) : 51 -57 . DOI: 10.3724/SP.J.1037.2012.00378

References

[1] Motta A T, Yilmazbayhan A, Gomes da Silva M J, Comstock R J, Was G S, Busby J T, Gartner E, Peng Q J,Jeong Y H, Park J Y. J Nucl Mater, 2007; 371: 61

[2] Cox B. J Nucl Mater, 2005; 336: 331

[3] Billot P, Yagnik S, Ramasubramanian N, Peybernes J,Pecheur D. In: Moan G D, Rudling P eds., Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423,Annecy: ASTM International, 2002: 169

[4] Mardon J P, Charquet D, Senevat J. In: Sabol G P, Moan G D eds., Zirconium in the Nuclear Industry: 12th International Symposium, ASTM STP 1354, Toronto: ASTM International, 2000: 505

[5] Park J Y, Yoo S J, Choi B K, Jeong Y H. J Nucl Mater,2008; 374: 343

[6] Hong H S, Moon J S, Kim S J, Lee K S. J Nucl Mater, 2001; 297: 113

[7] 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

(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)

[8] Li S L, Yao M Y, Zhang X, Geng J Q, Peng J C, Zhou B X. Acta Metall Sin, 2011; 47: 163

(李士炉, 姚美意, 张欣, 耿建桥, 彭剑超, 周邦新. 金属学报, 2011; 47: 163)

[9] Chen H M, Ma C L, Bai X D. The Corrosion and Protection of Nuclear Materials. Beijing: Atomic Energy Press, 1984: 1

(陈鹤鸣, 马春来, 白新德编著. 核反应堆材料腐蚀及其防护.北京: 原子能出版社, 1984: 1)

[10] Li P Z, Li Z K, Xue X Y, Liu J Z. Rare Met Mater Eng,

1998; 27: 356

(李佩志, 李中奎, 薛祥义, 刘建章. 稀有金属材料与工程, 1998; 27: 356)

[11] Yao M Y, Zou L H, Xie X F, Zhang J L, Peng J C, Zhou B X.

Acta Metall Sin, 2012; 48: 1098

(姚美意, 邹玲红, 谢兴飞, 张金龙, 彭剑超, 周邦新. 金属学报, 2012; 48: 1098)

[12] Yao M Y, Zhou B X, Li Q, Liu W Q, Geng X, Lu Y P. J Nucl Mater,2008; 374: 197

[13] Kim Y S, Kim S K, Bang J G, Jung Y H. J Nucl Mater,2000; 279: 335

[14] Comstock R J, Schoenberger G, Sabol G P. In: Bradley E R,Sabol G P eds., Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, Garmisch--Partenkirchen: ASTM International, 1996: 710

[15] Park J Y, Choi B K, Yoo S J, Jeong Y H. J Nucl Mater,2006; 359: 59

[16] Anada H, Takeda K. In: Bradley E R, Sabol G P eds., Zirconium in

the Nuclear Industry: 11th International Symposium, ASTM STP 1295,

Garmisch--Partenkirchen: ASTM International, 1996: 35

[17] Wadman B, Lai Z, Andren H O, Nystrom A L, Rudling P, Pettersson H I.In: Garde A M, Bradley E R eds., Zirconium in the Nuclear Industry: 10th International Symposium, ASTM STP 1245, Baltimore M D: ASTM International, 1994: 579

[18] Zhou B X, Li Q, Yao M Y, Liu W Q. Nucl Power Eng, 2005; 26: 364

(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, 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. 稀有金属材料工程, 2006; 35: 1009)

[20] 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, Sunriver Oregon: ASTM International, 2008: 371

[21] Zhou B X, Li Q, Huang Q, Miao Z, Zhao W J, Li C. Nucl Power Eng, 2000; 21: 339

(周邦新, 李强, 黄强, 苗志, 赵文金, 李聪.核动力工程, 2000; 21: 339)

[22] 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)

[23] Zhou B X, Peng J C, Yao M Y, Li Q, Xia S, Du C X, Xu G. In: Limback M,Barberis P eds., Zirconium in the Nuclear Industry: 16th International Symposium, ASTM STP 1529, Chengdu: ASTM International, 2010: 620

[24] Zhong X Y, Yang B, Li M C, Yao M Y, Zhou B X, Shen J N. Rare Met

Mater Eng, 2010; 39: 2167

(钟祥玉, 杨波, 李谋成, 姚美意, 周邦新. 沈嘉年. 稀有金属材料工程,

2010; 39: 2167)

[25] Weidinger H G, Ruhmann H, Cheliotis G, Maguire M, Yau T L.In: Eucken C M, Garde A M eds., Zirconium in the Nuclear Industry:9th International Symposium, ASTM STP 1132, Kobe: ASTM International,1991: 499

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