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.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1998年第5期438-442,共5页
Nuclear Power Engineering
关键词
核电站
反应堆
堆内构件
流致振动
Qinshan 600MW nuclear power plant Reactor Internals Flow induced vibration Extreme value loads
