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Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR

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Acta Metallurgica Sinica (English Letters) Aims and scope

Abstract

The effect of normal force on fretting wear behavior of zirconium alloy tube mated with grid dimple in simulated primary water of pressurized water reactor nuclear power plant was investigated. Results showed that the maximum wear depth, wear volume and wear coefficient of Zr alloy tube in simulated primary water at 315 °C gradually increased with increasing normal force, while the friction coefficient gradually decreased. Fretting process could be divided into four stages according to the variation of friction coefficient during test. When normal force exceeds 30 N, the fretting regime would transition from gross slip regime to partial slip regime after 3 × 107 cycles. Delamination was aggravated with increasing normal force, while abrasive wear became slighter. A thicker third-body layer with monoclinic ZrO2 was formed by the tribo-sintering mechanism under higher normal force. In addition, the schematic evolution processes of delamination and third-body layer formation were displayed according to morphology observation.

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Acknowledgements

This work is financially supported by the CNNC Science Fund for Talented Young Scholars, Youth Innovation Promotion Assessment CAS (2022187), the IMR Innovation Fund (No. 2021-PY10) 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) (No. 2020NMSAKF01). The authors are grateful for the help of 3D surface morphology analysis from Dr. Hui Feng at IMR, CAS.

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Authors and Affiliations

  1. School of Materials Science and Engineering, University of Science and Technology of China, Shenyang, 110016, China

    Yusheng Zhang & Hongliang Ming

  2. CAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang, 110016, China

    Yusheng Zhang, Hongliang Ming, Jianqiu Wang & En-Hou Han

  3. Nuclear Power Institute of China, Chengdu, 610213, China

    Jiang Lai & Lixia Gao

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  1. Yusheng Zhang
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Correspondence to Hongliang Ming or Jianqiu Wang.

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Zhang, Y., Lai, J., Ming, H. et al. Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR. Acta Metall. Sin. (Engl. Lett.) 36, 865–880 (2023). https://doi.org/10.1007/s40195-022-01496-2

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  • DOI: https://doi.org/10.1007/s40195-022-01496-2

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