反应堆用国产石墨的摩擦表面形貌分析  

Friction Surface Analysis on Chinese Graphite Used in Nuclear Reactor

作　　者：盛选禹[1] 于溯源[1] 雒晓卫[1] 何树延[1] 张振声[1] 

机构地区：[1]清华大学核能技术设计研究院,北京100084

出　　处：《核动力工程》2001年第5期401-405,455,共6页Nuclear Power Engineering

基　　金：清华大学骨干人才支持计划;清华大学核能技术设计研究院基础研究基金9850403联合资助

摘　　要：为探讨石墨材料在氦气和高温条件下的摩擦机理,利用扫描电子显微镜对国产细颗粒石墨和粗颗粒石墨摩擦试验后的表面进行了观察。结果表明,两种石墨在不同试验条件下的摩擦机理不完全相同。但无论那种石墨,只要摩擦表面出现塑性变形,则材料的摩擦系数较大;摩擦表面出现塑性变形和摩擦系数之间存在对应关系,但是否出现塑性变形与氦气和高温条件没有直接关系。The friction surfaces of Chinese large grain and fine grain graphite are analyzed under a Scanning Electron Microscope to investigate the friction mechanism of graphite in high temperature helium. The friction mechanisms for the different test conditions with the two kinds of graphite were not same. When the friction surface has plastic deformation, the friction coefficient was great regardless of the type of graphite or test conditions. The friction coefficient was related to the plastic deformation which was not directly related to the helium or the high temperatures.

关 键 词：石墨 摩擦 塑性变形 核反应堆 材料 表面形貌 摩擦系数 

分 类 号：TL342[核科学技术—核技术及应用]