论文

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

  • 朱莉 ,
  • 姚美意 ,
  • 孙国成 ,
  • 陈文觉 ,
  • 张金龙 ,
  • 周邦新
展开
  • 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
朱莉, 女, 1988年生, 硕士生

收稿日期: 2012-06-27

  修回日期: 2012-10-11

  网络出版日期: 2013-01-11

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项目2011ZX06004--023资助

 

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
Expand
  • 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

摘要

利用高压釜腐蚀实验研究了Zr-1Nb-xBi(x=0.05-0.3, 质量分数, %)合金在360 ℃和18.6 MPa去离子水中的耐腐蚀性能. 结果表明, 在Zr--1Nb合金的基础上添加Bi能明显改善其耐腐蚀性能, 且随着Bi含量的增加, 合金的耐腐蚀性能进一步提高.合金显微组织的TEM观察和EDS分析表明, 合金中存在ZrNbFe型和β-Nb第二相,Bi含量对第二相的种类、尺寸和数量没有明显的影响; 0.3%的Bi可全部固溶在α-Zr基体中, 且不影响Nb的固溶含量. 氧化膜断口和内表面形貌的SEM观察表明,固溶在α-Zr基体中的Bi能够明显延缓氧化膜显微组织的演化, 包括孔隙发展成为微裂纹的过程和柱状晶向等轴晶的转变.

本文引用格式

朱莉 , 姚美意 , 孙国成 , 陈文觉 , 张金龙 , 周邦新 . 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(1) : 51 -57 . DOI: 10.3724/SP.J.1037.2012.00378

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.

参考文献

 


[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
文章导航

/