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高温气冷堆石墨材料的疲劳裂纹扩展综述
引用本文:常华键 荒进长利. 高温气冷堆石墨材料的疲劳裂纹扩展综述[J]. 核动力工程, 1999, 20(3): 232-235
作者姓名:常华键 荒进长利
作者单位:清华大学核能技术设计研究院(常华健),日本原子力研究所核热利用部高温照射研究室(荒井长利)
摘    要:迄今为止,各国的高温气冷堆均采用石墨作为其堆芯活性区及反射层的主要结构材料。由于堆内的高温高辐照环境,石墨构件一般承受较高的热应力及辐照应力,这些应力的循环变化将引起疲劳载荷。

关 键 词:高温气冷堆 石墨 疲劳裂纹扩展 研究综述

Summarization on Fatigue Grack Growth of Graphites in HTGR
Chang Huajian Taketoshi Arai. Summarization on Fatigue Grack Growth of Graphites in HTGR[J]. Nuclear Power Engineering, 1999, 20(3): 232-235
Authors:Chang Huajian Taketoshi Arai
Abstract:Up to now,the high temperature gas cooled reactors (HTGR) in various countries use graphite as their main structural materials such as moderators and reflectors.In these applications,graphite components are subjected to combined loading resulting from thermal stresses and stresses caused by neutron irradiation induced dimensional changes.Fatigue loading,which is caused either by the stresses mentioned above or by seismic and static forces,is an important factor to caused failure of components.Some researchers in several countries have carried out a lot of investigations into the fatigue endurance of various graphites.This paper presents some experimentally results for fatigue crack growth rates in some typical graphites.These results obtained from different researchers are not well comparable.However,they can be taken as references for understanding of fatigue behavior in similar materials and for further studies.
Keywords:High temperature gas cooled reactor(HTGR) Graphite Fatigue crack growth  
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