论文

Cu对Zr-2.5Nb合金在500 ℃/10.3 MPa过热蒸汽中腐蚀行为的影响

  • 李强 ,
  • 梁雪 ,
  • 彭剑超 ,
  • 余康 ,
  • 姚美意 ,
  • 周邦新
展开
  • 上海大学微结构重点实验室, 上海 200444
李强, 男, 1967年生, 副研究员

收稿日期: 2011-04-29

  网络出版日期: 2011-07-11

基金资助

国家自然科学基金项目50871064和50971084, 国家高技术研究发展计划项目2008AA031701, 上海市自然科学基金项目09ZR1411700及上海市重点学科建设项目S30107资助

EFFECT OF Cu-ADDITION ON THE CORROSION BEHAVIOR OF Zr-2.5Nb ALLOYS IN 500 ℃/10.3 MPa SUPERHEATED STEAM

  • LI Jiang ,
  • LIANG Xue ,
  • PENG Jian-Tiao ,
  • YU Kang ,
  • YAO Mei-Yi ,
  • ZHOU Bang-Xin
Expand
  • Laboratory for Microstructures, Shanghai University, Shanghai 200444

Received date: 2011-04-29

  Online published: 2011-07-11

Supported by

Supported by National Natural Science Foundation of China (Nos.50871064 and 50971084), National High Technology Research and Development Program of China (No.2008AA031701), Natural Science Foundation of Shanghai (No.09ZR1411700) and Shanghai Leading Academic Discipline Project (No.S30107)

摘要

添加微量合金元素Cu的Zr-2.5Nb-xCu (x=0.2, 0.5, 质量分数, %)合金样品, 经β相水淬、冷轧变形及580 ℃, 50 h和620 ℃, 2 h退火处理, 在静态高压釜中进行500 ℃/10.3 MPa的过热蒸汽腐蚀实验. 利用SEM和TEM研究了氧化膜截面的显微组织. 结果表明, 添加少量Cu可以提高Zr-2.5Nb合金的耐腐蚀性能; 合金的耐腐蚀性能与氧化膜中的柱状晶的生长及形态有关, 添加合金元素Cu有利于提高锆合金氧化膜中柱状晶比例, 并使柱状晶尺寸增大且排列有序, 从而提高锆合金的耐腐蚀性能.

本文引用格式

李强 , 梁雪 , 彭剑超 , 余康 , 姚美意 , 周邦新 . Cu对Zr-2.5Nb合金在500 ℃/10.3 MPa过热蒸汽中腐蚀行为的影响[J]. 金属学报, 2011 , 47(7) : 877 -881 . DOI: 10.3724/SP.J.1037.2011.00275

Abstract

Zr-2.5Nb-xCu (x=0.2, 0.5, mass fraction, %) specimens were annealed at 580 ℃ for 50 h and 620 ℃ for 2 h after β-quenching and cold rolling, and then corroded in autoclave with 500 ℃/10.3 MPa superheated steam. SEM and TEM equipped with EDS were employed to investigate their corrosion behaviors through analyzing the microstructures of the fracture surface of the oxide layers or of the cross-section of oxide layers. It was found that the addition of copper can improve the corrosion resistance of Zr-2.5Nb alloy, which is closely related to the increases in the fraction and size of columnar grains in the oxide film.

参考文献

[1] Garzarolli F, Seidel H, Tricot R, Gros J P. In: Eucken C M, Garde A M, eds., Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, Philadelphia: American Society for Testing and Materials, 1991: 395

[2] Takeda K, Anada H. In: Sabol G P, Moan G D, eds., Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, West Conshohocken, PA: American Society for Testing and Materials, 2000: 592

[3] Bouvier P, Godlewski J, Lucazeau G. J Nucl Mater, 2002; 300: 118

[4] Jeong Y H, Kim H G, Kim T H. J Nucl Mater, 2003; 317: 1

[5] Sabol G P. J ASTM Int, 2005; 2: 3

[6] Bossis P, Pˆecheur D, Hanifi K, Thomazet J, Blat M. J ASTM Int, 2006; 3: 494

[7] Kim H G, Jeong Y H, Kim T H. J Nucl Mater, 2004; 326: 125

[8] Jeong Y H, Lee K O, Kim H G. J Nucl Mater, 2002; 302: 9

[9] Park J Y, Choi B K, Jeong Y H, Jung Y H. J Nucl Mater, 2005; 340: 237

[10] Park J Y, Choi B K, Jeong Y H, Kim K T, Jung Y H. Proc of 2005 Water Reactor Fuel Performance Meeting, Kyoto, Japan, 2005: 188

[11] Li Q. PhD Thesis, Shanghai University, 2008

(李强. 上海大学博士论文, 2008)

[12] Zhou B X, Li Q, Yao M Y, Liu WQ, Chu Y L. Nucl Power Eng, 2005; 26: 364

(周邦新, 李强, 姚美意, 刘文庆, 褚玉良. 核动力工程, 2005; 26: 364)

[13] 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, 褚玉良. 稀有金属材料与工程, 2006; 35: 1009)

[14] Yao M Y. PhD Thesis, Shanghai University, 2007

(姚美意. 上海大学博士论文, 2007)
文章导航

/