Complex Equipments or Systems

Impact Fretting Wear Behavior of Alloy 690 Tubes in Dry and Deionized Water Conditions

  • Zhen-Bing Cai ,
  • Jin-Fang Peng ,
  • Hao Qian ,
  • Li-Chen Tang ,
  • Min-Hao Zhu
展开
  • 1. Traction Power State Laboratory, Southwest Jiaotong University, Chengdu 610031, China;
    2. Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China

收稿日期: 2015-11-29

  修回日期: 2017-04-13

  网络出版日期: 2019-07-22

基金资助

Supported by National Natural Science Foundation of China (Grant Nos. 51375407, U1530136, 51627806), Shanghai Municipal Science and Technology Talent Program of China (Grant No. 14R21421500), and Young Scientific Innovation Team of Science and Technology of Sichuan (Grant No. 2017TD0017)

Impact Fretting Wear Behavior of Alloy 690 Tubes in Dry and Deionized Water Conditions

  • Zhen-Bing Cai ,
  • Jin-Fang Peng ,
  • Hao Qian ,
  • Li-Chen Tang ,
  • Min-Hao Zhu
Expand
  • 1. Traction Power State Laboratory, Southwest Jiaotong University, Chengdu 610031, China;
    2. Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China

Received date: 2015-11-29

  Revised date: 2017-04-13

  Online published: 2019-07-22

Supported by

Supported by National Natural Science Foundation of China (Grant Nos. 51375407, U1530136, 51627806), Shanghai Municipal Science and Technology Talent Program of China (Grant No. 14R21421500), and Young Scientific Innovation Team of Science and Technology of Sichuan (Grant No. 2017TD0017)

摘要

The impact fretting wear has largely occurred at nuclear power device induced by the flow-induced vibration, and it will take potential hazards to the service of the equipment. However, the present study focuses on the tangential fretting wear of alloy 690 tubes. Research on impact fretting wear of alloy 690 tubes is limited and the related research is imminent. Therefore, impact fretting wear behavior of alloy 690 tubes against 304 stainless steels is investigated. Deionized water is used to simulate the flow environment of the equipment, and the dry environment is used for comparison. Varied analytical techniques are employed to characterize the wear and tribochemical behavior during impact fretting wear. Characterization results indicate that cracks occur at high impact load in both water and dry equipment; however, the water as a medium can significantly delay the cracking time. The crack propagation behavior shows a jagged shape in the water, but crack extended disorderly in dry equipment because the water changed the stress distribution and retarded the friction heat during the wear process. The SEM and XPS analysis shows that the main failure mechanisms of the tube under impact fretting are fatigue wear and friction oxidation. The effect of medium(water) on fretting wear is revealed, which plays a potential and promising role in the service of nuclear power device and other flow equipments.

本文引用格式

Zhen-Bing Cai , Jin-Fang Peng , Hao Qian , Li-Chen Tang , Min-Hao Zhu . Impact Fretting Wear Behavior of Alloy 690 Tubes in Dry and Deionized Water Conditions[J]. Chinese Journal of Mechanical Engineering, 2017 , 30(4) : 819 -828 . DOI: 10.1007/s10033-017-0147-8

Abstract

The impact fretting wear has largely occurred at nuclear power device induced by the flow-induced vibration, and it will take potential hazards to the service of the equipment. However, the present study focuses on the tangential fretting wear of alloy 690 tubes. Research on impact fretting wear of alloy 690 tubes is limited and the related research is imminent. Therefore, impact fretting wear behavior of alloy 690 tubes against 304 stainless steels is investigated. Deionized water is used to simulate the flow environment of the equipment, and the dry environment is used for comparison. Varied analytical techniques are employed to characterize the wear and tribochemical behavior during impact fretting wear. Characterization results indicate that cracks occur at high impact load in both water and dry equipment; however, the water as a medium can significantly delay the cracking time. The crack propagation behavior shows a jagged shape in the water, but crack extended disorderly in dry equipment because the water changed the stress distribution and retarded the friction heat during the wear process. The SEM and XPS analysis shows that the main failure mechanisms of the tube under impact fretting are fatigue wear and friction oxidation. The effect of medium(water) on fretting wear is revealed, which plays a potential and promising role in the service of nuclear power device and other flow equipments.

参考文献

[1] A Ramalho, A Mertallinger, A Cavaleiro. Fretting behaviors of W-Si coated steels in vacuum environment. Wear, 2006, 261(1): 79-85.
[2] Z B Cai, M H Zhu, Z R Zhou. An experimental study of torsional fretting behavior of LZ50 steel. Tribology International, 2010, 43(1): 361-369.
[3] Z B Cai, G Zhang, Y Zhu, et al. Torsional fretting wear of nitrogen ion implantation biomedical Ti6Al7Nb alloy under bovine serum. Tribology International, 2013, 59: 312-320.
[4] L Zhao, J Hu, Z Wu, et al. Investigation on flow accelerated corrosion mitigation for secondary circuit piping of the third Qinshan nuclear power plant. Chinese Journal of Mechanical Engineering, 2011, 24(2): 214-219.
[5] L Xin, B Yang, Z Wang, et al. Microstructural evolution of subsurface on Inconel 690TT alloy subjected to fretting wear at elevated temperature. Materials & Design, 2016, 104: 152-161.
[6] Y Sato, A Iwabuchi, M Uchidate, et al. Dynamic corrosion properties of impact-fretting wear in high -temperature pure water. Wear, 2015, 330: 182-192.
[7] H Tang. Fretting damage one of worldwide difficulties in the field of nuclear power equipment and structures for a long term. Nuclear Power Engineering, 2000, 21(3): 222-231.
[8] L Yang, M Zhou, Z Tian. Heat transfer enhancement with mixing vane spacers using the field synergy principle. Chinese Journal of Mechanical Engineering, 2016, 30(1): 127-134.
[9] Y Zhong, C Zhou, S Chen, et al. Effects of temperature and pressure on stress corrosion cracking behavior of 310S stainless steel in chloride solution. Chinese Journal of Mechanical Engineering, 2016, 30(1): 200-206.
[10] H Jiang, J Qu, R Y Lu, et al. Grid-to-rod flow-induced impact study for PWR fuel in reactor. Progress in Nuclear Energy, 2016, 91: 355-361.
[11] K Fujta. Flow -induced vibration and fluid -structure interaction in nuclear power plant components. Journal of Wind Engineering and Industrial Aerodynamics, 1990, 33(1-2): 405-418.
[12] J Luo, Z B Cai, J L Mo, et al. Friction and wear properties of high-velocity oxygen fuel sprayed WC-17Co coating under rotational fretting conditions. Chinese Journal of Mechanical Engineering, 2016, 29(3): 515-521.
[13] H G D Goyder. Flow -induced vibration in heat exchangers. Chemical Engineering Research and Design, 2002, 80(3): 226-232.
[14] P Ko, A Lina, A Ambard. A review of wear scar patterns of nuclear power plant components. ASME 2003 Pressure Vessels and Piping Conference, USA, 2003: 97-106.
[15] L Guo, S Yang, H Jiao. Behavior of thin-walled circular hollow section tubes subjected to bending. Thin-Walled Structures, 2013, 73: 281-289.
[16] F M Gueout, N Fisher. Steam generator fretting -wear damage: A summary of recent findings. Journal of Pressure Vessel Technology, 1999, 121(3): 304-310.
[17] S Jeong, C Cho, Y Lee. Friction and wear of Inconel 690 for steam generator tube in elevated temperature water under fretting condition. Tribology International, 2005, 38(3): 283-288.
[18] I Chung, M Lee. An experimental study on fretting wear behavior of cross -contacting Inconel 690 tubes. Nuclear Engineering and Design, 2011, 241(10): 4103 -4110.
[19] J Li, Y Lu, H Zhang, et al. Effect of grain size and hardness on fretting wear behavior of Inconel 600 alloys. Tribology International, 2015, 81: 215-222.
[20] T Wang, S Shen. Experimental studies of fretting wear in heat exchanger tubes. Nuclear Power Engineering, 1990, 11(6): 338-443.
[21] B Payne, M Biesinger, N Mcintyre. X-ray photoelectron spectroscopy studies of reactions on chromium metal and chromium oxide surfaces. Journal of Electron Spectroscopy and Related Phenomena, 2011, 184(1): 29 -37.
[22] A Grosvenor, M Biesinger, R Smart, et al. New interpretations of XPS spectra of nickel metal and oxides. Surface Science, 2006, 600(9): 1771 -1779.
[23] Y Toru, H Petr. Analysis of XPS spectra of Fe2+ and Fe3+ ions in oxide materials. Applied Surface Science, 2008, 254(8):2441 -2449.
[24] Q P Zhong, Z H Zhao. Fractography. Beijing: Higher Education Press, 2006.
[25] W Kilian, P W Magdalena, G Sergo, et al. Sequence of deformation and cracking behaviours of Gallium-Arsenide during nano-scratching. Materials Chemistry and Physics, 2013, 138(1):38-48.
[26] F Meng, J Wang. Scratch-induced stress corrosion cracking for steam generator tubings. Corrosion & Protection, 2013, 12(5):2114 -2125.
文章导航

/