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Acta Metallurgica Sinica (English Letters)

, Volume 32, Issue 12, pp 1437–1448 | Cite as

Effects of Temperature on Fretting Corrosion Between Alloy 690TT and 405 Stainless Steel in Pure Water

  • Xing-Chen Liu
  • Hong-Liang MingEmail author
  • Zhi-Ming Zhang
  • Jian-Qiu Wang
  • Li-Chen Tang
  • Hao Qian
  • Yong-Cheng Xie
  • En-Hou Han
Article
  • 73 Downloads

Abstract

In pressurized water reactor, fretting corrosion has become the main reason for the failure of 690TT heat exchanger tubes. The effect of temperature on the fretting corrosion behavior between 690TT tube and 405 stainless steel (SS) bar has been studied during 106 fretting cycles. The overall average coefficient of friction (COF) values descends with an increase in test temperature, while the width of worn scar becomes wider. The severest fretting corrosion happens when the test temperature is at 100 °C. The wear mechanism differs at different test temperatures, from adhesive wear at room temperature to abrasive wear and delamination at 100 °C, to abrasive wear at 200 °C. Deformation slips, high residual strain concentration, and micro-cracks are found which are disadvantageous for the further service performance of the tubes.

Keywords

Alloy 690TT 405 SS Fretting corrosion Temperature 

Notes

Acknowledgements

This work is supported by the National Natural Science Foundation of China (No. 51771211), the Large-scale advanced PWR major projects (No. 2017ZX06002006), the Liaoning Provincial Natural Science Foundation of China (No. 20180540076), and the open-ended fund of the CAS Key laboratory of Nuclear Materials and Safety Assessment (Institute of Metal Research, Chinese Academy of Sciences, China) (Nos. 2019NMSAKF02 and 2017NMSAKF04). The authors are grateful for the help of 3D surface morphology analysis from Dr. Hui Feng at IMR, CAS.

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Copyright information

© The Chinese Society for Metals (CSM) and Springer-Verlag GmbH Germany, part of Springer Nature 2019

Authors and Affiliations

  • Xing-Chen Liu
    • 1
    • 2
  • Hong-Liang Ming
    • 1
    Email author
  • Zhi-Ming Zhang
    • 1
  • Jian-Qiu Wang
    • 1
  • Li-Chen Tang
    • 3
  • Hao Qian
    • 3
  • Yong-Cheng Xie
    • 3
  • En-Hou Han
    • 1
  1. 1.CAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal ResearchChinese Academy of SciencesShenyangChina
  2. 2.School of Materials Science and EngineeringUniversity of Science and Technology of ChinaShenyangChina
  3. 3.Shanghai Nuclear Engineering Research and Design Institute Ltd. Co.ShanghaiChina

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