反应堆堆内构件流致振动试验的极值载荷分析  

Analysis of Extreme Value Loads on the Flow induced Vibration Testing for Internals

作　　者：梁志坚[1] 胡永陶[1] 

机构地区：[1]中国核动力研究设计院

出　　处：《核动力工程》1998年第5期438-442,共5页Nuclear Power Engineering

摘　　要：应用极值载荷分布法分析了秦山６００ＭＷ核电站反应堆堆内构件流致振动试验的实测载荷，得出在设计寿命期４０年内，流致振动对堆内构件疲劳寿命的影响可以忽略不计。同时为堆内构件流致振动试验时间的确定，提供了有价值的参考数据。The testing loads of Qinshan 600MW nuclear reactor internals is analyzed by the extreme value loads distribution method.It comes to the conclusion that the effect of the flow induced vibration on the fatigue life of the reactor internals during the design service life can be ignored and the valuable data for determinaton of the minimum record duration of reactor internals flow induced vibration testing are given.

关 键 词：核电站 反应堆 堆内构件 流致振动 

分 类 号：TL339[核科学技术—核技术及应用]