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Fretting Wear Damage of the Corroded Fuel Cladding Tubes for Nuclear Fuel Rod against Supporting Grids

机译:用于支撑栅格的核燃料杆的腐蚀燃料包层管的微动磨损

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Fuel cladding tubes in nuclear fuel assembly are held up by supporting grids because the tubes are long and slender. Fluid flows of high-pressure and high-temperature in the tubes cause oscillating motions between tubes and supports. This is called as FIV (flow induced vibration), which causes fretting wear in contact parts of tube-support. The fretting wear of tube-support can threaten the safety of nuclear power plant. Therefore, a research about the fretting wear characteristics of tube-support is required. The fretting wear tests were performed with supporting grids and cladding tubes, especially after corrosion treatment on tubes, in water. The tests were done using various applied loads with fixed amplitude. From the results of fretting tests, the wear amounts of tube materials can be predictable by obtaining the wear coefficient using the work rate model. Due to stick phenomena the wear depth was changed as increasing load and temperature. The maximum wear depth was decreased as increasing the water temperatures. At high temperatures there are the regions of some severe adhesion due to stick phenomena.
机译:核燃料组件中的燃料包覆管通过支撑栅格固定,因为管长而细长。管中高压和高温的流体流动导致管和支撑件之间的振动运动。这被称为FIV(流量诱导的振动),这导致管支撑件的接触部件中的微动磨损。管支撑的微动磨损可以威胁到核电站的安全性。因此,需要关于管支撑件的微动磨损特性的研究。通过支撑栅格和包层管进行微动磨损试验,尤其是在水中腐蚀处理后,在水中进行腐蚀处理。使用具有固定幅度的各种施加的载荷来完成测试。从烦恼测试的结果,通过使用工作速率模型获得磨损系数可以预测管材料的磨损量。由于粘性现象,磨损深度随着负载和温度的增加而变化。随着水温的增加,最大磨损深度降低。在高温下,由于棒状现象,存在一些严重粘附的区域。

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