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

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

论文摘要

In pressurized water reactor,fretting corrosion has become the main reason for the failure of 690 TT heat exchanger tubes.The effect of temperature on the fretting corrosion behavior between 690 TT 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℃.The wear mechanism differs at different test temperatures,from adhesive wear at room temperature to abrasive wear and delamination at 100℃,to abrasive wear at 200℃.Deformation slips,high residual strain concentration,and micro-cracks are found which are disadvantageous for the further service performance of the tubes.

论文目录

  • 1 Introduction
  • 2 Experimental
  •   2.1 Preparation of Materials
  •   2.2 Fretting Corrosion Tests and Analysis
  • 3 Results and Discussion
  •   3.1 Microstructures and Hardness of 690TT and 405SS
  •   3.2 Evolution of Friction Coef f i cient
  •   3.3 Surface and Sectional Characterization of the Worn Scars
  •   3.4 Profi le Lines,Wear Volumes and Maximum Wear Depths of the Worn Scars
  • 4 Discussion
  •   4.1 Eff ects of Temperature on Fretting Corrosion
  •   4.2 Potential Eff ects of Wear Damage on Further Performance of the Tubes
  • 5 Conclusions
  • 文章来源

    类型: 期刊论文

    作者: Xing-Chen Liu,Hong-Liang Ming,Zhi-Ming Zhang,Jian-Qiu Wang,Li-Chen Tang,Hao Qian,Yong-Cheng Xie,En-Hou Han

    来源: Acta Metallurgica Sinica(English Letters) 2019年12期

    年度: 2019

    分类: 工程科技Ⅰ辑,工程科技Ⅱ辑

    专业: 核科学技术,电力工业

    单位: CAS Key Laboratory of Nuclear Materials and Safety Assessment,Institute of Metal Research,Chinese Academy of Sciences,School of Materials Science and Engineering,University of Science and Technology of China,Shanghai Nuclear Engineering Research and Design Institute Ltd.Co.

    基金: 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),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)

    分类号: TM623

    页码: 1437-1448

    总页数: 12

    文件大小: 13772K

    下载量: 15

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