采用专用往复滑动摩擦试验机及工装, 通过台架试验模拟核电服役条件, 测试了压力容器支座用高强石墨镶嵌减摩板的滑动摩擦磨损性能, 并用扫描电子显微镜观察了石墨磨损形貌。结果表明: 减摩板试验件在垂直载荷42.53 MPa(承载3 603 kN)和99 MPa(承载8 386 kN)作用下经800次循环摩擦试验的平均摩擦因数分别为0.12和0.11, 满足核电设计技术要求; 镶嵌于减摩板的高强石墨在干摩擦条件下的磨损机制以磨粒磨损为主, 伴有疲劳磨损。

With the special reciprocating sliding friction testing machine and tooling, the sliding friction and wear properties of the antifriction plate inlaid with high strength graphite for support of reactor pressure vessel (RPV) were tested under the simulated service condition of nuclear power by the bench test, and the worn surface of graphite was investigated by scanning electronic microscope (SEM). The results show that the average friction coefficient of antifriction plate samples was 0.12 and 0.11 under vertical load of 42.53 MPa (bearing load 3 603 N) and 99 MPa (bearing load 8 386 N) after friction test for 800 cycles. It met the technical requirements of nuclear power design. The dry friction wear mechanism of high strength graphite inlaid in the antifriction plate was abrasive wear, accompanied by fatigue wear.