Abstract This paper systematically studies the friction and wear properties between the friction plates and the support platform of the marine nuclear power plant reactor. The friction performance between SA508 steel and three different kinds of graphite is studied with a commercial reciprocating sliding friction and wear tester. The variation of friction coefficient of materials under different temperature and load is analyzed, and the wear mechanism is analyzed to decide whether these graphite materials can be applied to marine nuclear power station. The results show that in this experiment, the change trend of friction coefficient with time is increasing at first, then decreasing and finally increasing slowly; and the higher the temperature, the larger the friction coefficient; the larger the load, the smaller the friction coefficient. The wear rate of graphite materials increases with temperature and load. The wear mechanism of the material under low temperature and low load is mainly adhesion wear, accompanied by a small amount of abrasive wear, and as the temperature increases and the load increases, the abrasive wear will increase. The friction coefficient of the material exceeds the predetermined value under a certain temperature or load, so it cannot be applied to a marine nuclear power plant.

中文翻译：

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反应堆压力容器滑动轴承座摩擦磨损性能

摘要 本文系统地研究了船用核电站反应堆摩擦片与支撑平台之间的摩擦磨损特性。用商用往复滑动摩擦磨损试验机研究了SA508钢与三种不同石墨之间的摩擦性能。分析了材料在不同温度和载荷下摩擦系数的变化，分析了磨损机理，以决定这些石墨材料是否可以应用于船用核电站。结果表明，在本试验中，摩擦系数随时间的变化趋势为先增大后减小，最后缓慢增大；温度越高，摩擦系数越大；载荷越大，摩擦系数越小。石墨材料的磨损率随着温度和载荷的增加而增加。材料在低温低负荷下的磨损机理主要是粘附磨损，并伴有少量磨粒磨损，随着温度的升高和负荷的增加，磨粒磨损会增加。材料在一定温度或载荷下摩擦系数超过规定值，不能应用于船用核电站。