The HTR-PM technology, developed by China, uses a spherical fuel element with all-ceramic coated particles, the outermost layer is a graphite layer, and the interior contains about 12,000 nuclear fuel particles uniformly dispersed in the matrix graphite powder. Due to its high temperature resistance, small neutron cross section and excellent heat transfer performance, graphite is selected as moderator and structural material in HTR-PM. However, during reactor operation, the movement of the component balls and their impact on each other can cause varying degrees of wear on the outermost graphite. In this paper, the effect of temperature on the wear performance of graphite balls was investigated by using the graphite ball wear experimental equipment. It is found that the friction coefficient of graphite ball decreases significantly with increasing temperature in the range of room temperature to 300 ℃. At room temperature, the wear is mainly abrasive wear, accompanied by a small amount of fatigue wear, and the wear surface at high temperature is smoother and denser than that at room temperature. In addition, the particle size of graphite dust produced by friction decreases with the increase of temperature, and there is no large abrasive dust. The amount of wear increases with the increase of temperature, while the wear rate decreases with the increase of time and eventually becomes stable. This study not only lays a foundation for the analysis of the deposition behavior of graphite dust, but also provides key data for pipeline cleaning and equipment maintenance of HTR-PM, which has great practical significance for ensuring the safe, economical and efficient operation of reactors.

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Experimental Study and Analysis of Wear Properties of Graphite Balls Used in HTR-PM at Different Temperatures

  • Hu Xiaomuzi,
  • Wang Xiujuan,
  • Zhang Haochun,
  • Cao Jian

摘要

The HTR-PM technology, developed by China, uses a spherical fuel element with all-ceramic coated particles, the outermost layer is a graphite layer, and the interior contains about 12,000 nuclear fuel particles uniformly dispersed in the matrix graphite powder. Due to its high temperature resistance, small neutron cross section and excellent heat transfer performance, graphite is selected as moderator and structural material in HTR-PM. However, during reactor operation, the movement of the component balls and their impact on each other can cause varying degrees of wear on the outermost graphite. In this paper, the effect of temperature on the wear performance of graphite balls was investigated by using the graphite ball wear experimental equipment. It is found that the friction coefficient of graphite ball decreases significantly with increasing temperature in the range of room temperature to 300 ℃. At room temperature, the wear is mainly abrasive wear, accompanied by a small amount of fatigue wear, and the wear surface at high temperature is smoother and denser than that at room temperature. In addition, the particle size of graphite dust produced by friction decreases with the increase of temperature, and there is no large abrasive dust. The amount of wear increases with the increase of temperature, while the wear rate decreases with the increase of time and eventually becomes stable. This study not only lays a foundation for the analysis of the deposition behavior of graphite dust, but also provides key data for pipeline cleaning and equipment maintenance of HTR-PM, which has great practical significance for ensuring the safe, economical and efficient operation of reactors.