...
  • 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>Diffusion and Defect Data. Solid State Data, Part B. Solid State Phenomena >Wear Characteristics of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions
【24h】

Wear Characteristics of Tube-Support Components for a Nuclear Steam Generator under Fretting Conditions

机译：微动条件下核蒸汽发生器管支撑部件的磨损特性

获取原文
获取原文并翻译 | 示例
           
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

Tubes in nuclear steam generators are held up by supports because the tubes are long and slender. Fluid flows of high-pressure and high-temperature flows in the tubes cause oscillating motions between tubes and supports. This is called as FIV (flow induced vibration) which cause fretting wear in contact part of tube-support. The reduction of tube thickness due to fretting wear of tube-support can threaten the safety of nuclear power plant. Therefore, a research on the fretting wear characteristics of tube-support is required. This work is focused on investigations of fretting wear characteristics and wear mechanisms of tube-support. Results show that the wear rate of tube is proportional to that of support and that with increasing the water temperature the wear volume of tube-support decreases because the oxidation rate decreases due to reduction of the oxygen concentration in contact surfaces. Also, the wear mechanisms of tube-support are abrasive and oxidational wear.
机译：核蒸汽发生器中的管子长而细，因此被支撑物支撑着。管中高压和高温的流体流动会引起管和支撑件之间的振荡运动。这称为FIV（流动引起的振动），会引起管支架接触部分的微动磨损。由于管支架的微动磨损而导致的管厚度减小会威胁到核电站的安全。因此，需要对管支架的微动磨损特性进行研究。这项工作的重点是研究微动磨损特性和管支架的磨损机理。结果表明，管的磨损率与支架的磨损率成正比，并且随着水温的升高，管支架的磨损量减小，这是因为氧化速率由于接触表面中氧浓度的降低而降低。而且，管支撑件的磨损机制是磨料磨损和氧化磨损。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱：kefu@zhangqiaokeyan.com

京公网安备：11010802029741号 ICP备案号：京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有

  • 客服微信

  • 服务号