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
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