核电站石墨密封垫片的试验研究  

Experiment Research of Graphite Sealing Gaskets for Nuclear Power Plant

作　　者：励行根 励勇 励洁 宋炜 蔡仁良[2] 

机构地区：[1]宁波天生密封件有限公司,浙江宁波315302 [2]华东理工大学,上海200237

出　　处：《液压气动与密封》2010年第11期29-32,共4页Hydraulics Pneumatics & Seals

摘　　要：基于金属与金属接触的密封原理,对核电站用石墨密封垫片的基本参数和主要性能进行了试验研究。研究结果表明,石墨环的密度、容积、压缩厚度等是影响垫片压缩回弹率、应力松弛率和泄漏率的重要因素,并获得了它们之间的相互关系和内在规律。Based upon the sealing mechanism of MMC, basic parameters and main behaviors for graphite sealing gaskets has experimentally researched. The results show that density and volume of graphite, compress thickness are important factors, which effects compressibility, recovery, relaxation and sealability of gasket, as well as obtain the relations between these factors and their laws.

关 键 词：垫片 密封 核电 法兰接头 柔性石墨 

分 类 号：TB42[一般工业技术]