| 引用本文: | 郑会,庄文华,杨双亮,郭相龙,张乐福.高温高压水环境下位移幅值对690合金传热管切向微动磨损的影响[J].中国表面工程,2022,35(4):57~64 |
| Zheng Hui,Zhuang Wenhua,Yang Shuangliang,Guo Xianglong,Zhang Lefu.Effect of Displacement Amplitude on Tangential Fretting Wear of Alloy 690 Tube in High Temperature and High Pressure Water[J].China Surface Engineering,2022,35(4):57~64 |
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| 摘要: |
| 由于试验装置的限制，在模拟工程服役环境的高温高压水环境下对三代核电用 690 合金管 / 405 不锈钢抗振条(AVB) 的高频微动磨损研究存在不足，影响了对核电厂蒸汽发生器传热管结构完整性评价的有效性。在模拟压水堆核电厂二回路高温高压水环境下，以 690 合金传热管为研究对象，开展高频切向微动磨损试验。试验研究不同位移幅值(D=20、30、40、80、 120 μm)对 690 合金管微动磨损行为的影响。试验结束后，借助扫描电子显微镜、能谱仪和三维形貌仪对磨损区域进行形貌表征、能谱分析和磨损体积计算。试验结果表明：随着位移幅值的增加，磨损接触面积增大，磨损深度和磨损体积均增加， 磨损加剧。当位移幅值较小时(D=20、30、40 μm)，磨屑不易排出接触面，多黏着在磨痕中心，磨损机制主要是黏着磨损； 当位移幅值增加至 80、120 μm 时，磨屑分布均匀，磨损机制向剥层磨损转变。随着磨损机制的转变，磨损率呈现先增加后降低的趋势，在 D=80 μm 时，磨损率最大。通过更符合工程实际的高温高压水环境试验，对比了不同位移幅值下的传热管微动磨损性能，给出了磨损率随位移幅值变化的趋势，初步阐明了磨损机制，有利于核电装备的摩擦学性能提升，对核电厂 690 传热管的结构完整性评价有较好的指导作用。 |
| 关键词: 位移幅值 690 合金管 微动磨损 高温高压水 |
| DOI：10.11933/j.issn.1007-9289.20211009002 |
| 分类号:TG178 |
| 基金项目:国家重点研发计划(2019YFB1900904)和国家科技重大专项(2018ZX06002008)资助项目 |
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| Effect of Displacement Amplitude on Tangential Fretting Wear of Alloy 690 Tube in High Temperature and High Pressure Water |
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Zheng Hui1, Zhuang Wenhua2, Yang Shuangliang1, Guo Xianglong2, Zhang Lefu2
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1.State Nuclear Power Plant Service Company, Shanghai 200233 , China;2.School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240 , China
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| Abstract: |
| Due to the limitation of the test equipment, the research on the high-frequency fretting wear tests of the alloy 690 tube / 405 stainless steel anti-vibration bar (AVB) for the third generation nuclear power plants in the high temperature and high pressure water environment that simulates the service environment is insufficient, which affects the effectiveness of the structural integrity assessment of the steam generator in the nuclear power plant. Hence, high-frequency tangential fretting wear tests of alloy 690 tubes are carried out in high temperature high pressure water which simulates the secondary side environment of PWR. The effects of displacement amplitudes (D=20, 30, 40, 80 and 120 μm) on fretting wear characteristics of alloy 690 tubes is investigated. After tests, the worn surfaces are examined through SEM, EDS and 3D profiler to acquire the wear morphology, wear products composition and wear volume. The results show that the contact area, the wear depth and the wear volume increase with the enlargement of the displacement amplitudes. When the displacement amplitudes are small (D=20, 30 and 40 μm), the wear mechanism mainly is adhesive wear, so that the wear products tend to stuck to the center of the contact surfaces. When the displacement amplitudes increase to 80 μm and 120 μm, the wear mechanism changes into delamination in which the wear products distribute uniformly on the surfaces. With the change of the wear mechanism, the wear rate shows a trend of first increasing and then decreasing, and reaches the maximum at D=80 μm. Through tests in the high temperature and high pressure water environment, which is more in accordance with the actual engineering environment, the fretting wear properties of the heat transfer tubes under different displacement amplitudes are compared. The trend of the wear rates changing with the displacement amplitudes is given, and the wear mechanisms are preliminarily clarified, which is beneficial to the improvements of the tribological property of nuclear power equipment and the directive function for the structural integrity assessments of the 690 heat transfer tubes in nuclear power plants. |
| Key words: displacement amplitude alloy 690 tube fretting wear high temperature and high pressure water |
