论文

打磨态690TT合金经不同时间浸泡后表面氧化膜结构分析

  • 王俭秋 ,
  • 张志明
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  • 中国科学院金属研究所金属腐蚀与防护国家重点实验室, 沈阳 110016
张志明, 男, 1983年生, 博士生

收稿日期: 2011-04-06

  修回日期: 2011-04-16

  网络出版日期: 2011-07-11

基金资助

国家重点基础研究发展计划项目2011CB610502和国家自然科学基金项目51025104资助

ANALYSES OF SURFACE OXIDE FILMS ON GROUND ALLOY 690TT AFTER IMMERSION FOR DIFFERENT TIMES

  • YU Jian-Qiu ,
  • ZHANG Zhi-Meng
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  • State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016

Received date: 2011-04-06

  Revised date: 2011-04-16

  Online published: 2011-07-11

Supported by

Supported by National Basic Research Program of China (No.2011CB610502) and National Natural Science Foundation of China (No.51025104)

摘要

利用多种分析手段深入分析了打磨处理的690TT合金在模拟压水堆一回路高温高压水环境中经不同时间浸泡后表面生长的氧化膜的微观结构. 结果表明, 从短期氧化到长期氧化, 氧化膜表面形貌变化不明显; 氧化膜主要由尖晶石结构的氧化物和单质Ni构成. 浸泡96和1440 h后, 氧化膜主要由富含Cr的氧化物构成. 浸泡720, 1440和2160 h后, 氧化膜均由外层、中间层和内层构成: 外层是分散的富含Ni和Fe的尖晶石结构的大颗粒氧化物; 中间层是致密的富含Cr的尖晶石结构的小颗粒氧化物; 内层是均匀连续的富含Cr的氧化物. 中间层和内层氧化物能对基体起到良好的保护作用; 随着氧化时间的延长, 保护层的平均生长速率逐渐降低. 打磨处理促进了690TT合金表面保护性氧化膜的生长.

本文引用格式

王俭秋 , 张志明 . 打磨态690TT合金经不同时间浸泡后表面氧化膜结构分析[J]. 金属学报, 2011 , 47(7) : 823 -830 . DOI: 10.3724/SP.J.1037.2011.00206

Abstract

The morphologies and structures of surface oxide films grown on ground Ni base alloy 690TT after immersion in the simulated hydrogenated primary water of pressured water reactors (PWRs) for different times were analyzed by various methods. After immersion for 35 h,\linebreak the ground alloy 690TT was covered with compact oxide particles. With the increase of the immersion time, the sample surfaces were covered with scattered big oxide particles and compact small oxide particles. Regardless of the immersion time, the grown oxide films are composed of spinel oxides and metallic Ni. After immersion for 720, 1440 and 2160 h, the oxide films are composed of three layers: the outmost layer is the separated big oxide particles which are rich in Fe and Ni; the intermediate layer is the compact small oxide particles rich in Cr, Fe and Ni; the inner layer is the continuous Cr oxides. The peak decompositions of the XPS results revealed that the Cr oxides in the inner layer are probably Cr2O3. The intermediate and inner layers in the oxide films could restrain the outward diffusion of metal atoms and also the inward diffusion of the oxygen atoms and then protect the matrix from further corrosion well. The average corrosion rate of the intermediate and inner layer decreased gradually with the immersion time increasing. Grinding treatment accelerated the growth of protective oxide film on alloy 690TT in the studied solution.

参考文献

[1] Han E H, Wang J Q, Wu X Q, Ke W. Acta Metall Sin, 2010; 46: 1379

(韩恩厚, 王俭秋, 吴欣强, 柯伟, 金属学报, 2010; 46: 1379)

[2] Zhou B X, Han E H. The Invited Lecture at the 30th annual Celebration Meeting for the Foundation of Chinese Society for Corrosion and Protection and the 5th National Conference for Corrosion and Protection, Beijing, Sept 14–16, 2009

[3] Staehle R W, Gorman J A. Corrosion, 2003; 59: 931

[4] Staehle R W. International Seminar on Materials Problems in Light Water Nuclear Power Plants: Status, Mitigation, Future Problems, Suzhou: Institute of Metal Research, CAS, Suzhou Nuclear Power Research Institute, the Second Research and Design Institute of Nuclear Industry, Feb 20–23, 2005

[5] Warzee M, Hennaut J, Maurice M, Sonnen C, Waty J, Berge P. J Electrochem Soc, 1964; 112: 670

[6] Ostwald C, Grabke H J. Corros Sci, 2004; 46: 1113

[7] Scenini F, Newman R C, Cottis R A, Jacko R J. Corrosion, 2008; 64: 824

[8] Scenini F, Newman R C, Cottis R A, Jacko R J. Corrosion 2007, Nashville, Tennessee, March 11—15, Paper No.07611

[9] Tan L, Ren X, Sridharan K, Allen T R. Corros Sci, 2008; 50: 2040

[10] Ding X S. Nucl Power Eng Technol, 2000; 13(4): 37

(丁训慎. 核电工程与技术, 2000; 13(4): 37)

[11] Terachi T, Totsuka N, Yamada T, Nakagawa T, Deguchi H, Horiuchi M, Oshitani M. J Nucl Sci Technol, 2003; 40: 509

[12] Ziemniak S E, Hanson M. Corros Sci, 2006; 48: 498

[13] Ziemniak S E, Hanson M. Corros Sci, 2002; 44: 2209

[14] Nakagawa T, Totsuka N, Terachi T, Nakajima N. J Nucl Sci Technol, 2003; 40: 39

[15] Ziemniak S E, Hanson M. Corros Sci, 2006; 48: 498

[16] Hermas A A. Corros Sci, 2008; 50: 2498

[17] Stefanov P, Stoychev D, Stoycheva M, Marinova T. Mater Chem Phys, 2000; 65: 212

[18] Sun H, Wu X Q, Han E H. Corros Sci, 2009; 51: 2840

[19] McIntype N S, Rummery T E, Cook M G, Owen D. J Electrochem Soc, 1976; 123: 1164

[20] Machet A, Galtayries A, Zanna S, Klein L, Maurice V, Jolivet P, Foucault M, Combrade P, Scott P, Marcus P. Electrochim Acta, 2004; 49: 3957

[21] McIntype N S, Zetaruk D G, Owen D. J Electrochem Soc, 1979; 126: 750

[22] Carette F, Lafont M C, Chatainier G, Guinard L, Pieraggi B. Surf Interface Anal, 2002; 34: 135

[23] Machet A, Galtayries A, Marcus P, Combrade P, Jolivet P, Scott P. Surf Interface Anal, 2002; 34: 197

[24] Sun M C, Wu X Q, Zhang Z E, Han E H. J Supercrit Fluids, 2008; 47: 309

[25] Panter J, Viguier B, Clou´e J M, Foucault M, Combrade P, Andrieu E. J Nucl Mater, 2006; 348: 213

[26] Zhang Z M, Wang J Q, Han E H, Ke W. Corros Sci, 2011, submitted

[27] Li M S. High Temperature Corrosion of Metals. Beijing: Metallurgical Industry Press, 2001: 162

(李美栓. 金属的高温腐蚀. 北京: 机械工业出版社, 2001: 162)

[28] Marchetti L, Perrin S, Raquet O, Pijolat M. Mater Sci Forum, 2008; 595–598: 529

[29] Lister D H, Davidson R D, Mcalpine E. Corros Sci, 1987; 27: 113

[30] Zhang Z M, Wang J Q, Han E H, Ke W. J Mater Sci Technol, 2011, accepted

[31] Ziemniak S E, Hanson M, Sander P C. Corros Sci, 2008; 50: 2465

[32] Zhang Z M, Wang J Q, Han E H, Ke W. Acta Metall Sin, 2011; 47: 831

(张志明, 王俭秋, 韩恩厚, 柯伟. 金属学报, 2011; 47: 831)
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