秦山核电二期工程反应堆堆内构件模型流致振动试验研究  

Experimental Study of Flow-induced Vibration of the Reactor Internal in Qinshan Phase II NPP Project

作　　者：喻丹萍[1] 胡永陶[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2003年第z1期109-113,共5页Nuclear Power Engineering

摘　　要：秦山核电二期工程是我国自行设计的第一个600MW级核电站,有必要进行反应堆堆内构件流致振动试验研究。本文介绍了按相似准则设计的实堆1:5的堆内构件试验模型,进行流致振动试验采用的试验方法,完成的试验内容以及试验数据的分析和处理。测得了吊篮结构在冷却剂流动冲刷下的脉动压力和各种响应参数。试验结果可用于秦山核电二期工程安全评审,并提供了吊篮流致振动响应计算的载荷谱和实堆振动监测、故障诊断的参考样本。Qinshan Phase Ⅱ NPP Project is the first 600MW PWR nuclear power plant designed by China. It is necessary to carry out the experimental study on the flow-induced vibration (FIV) of the reactor internal. This paper introduced the 1:5 experimental model, test method, test case, test data analysis and process. Fluctuating pressure force function that applies to the core barrel and a lot of response parameters of the internal structure were obtained. The result could be used in the safety evaluation for Qinshan Phase Ⅱ NPP Project.

关 键 词：堆内构件 试验模型 流致振动试验 

分 类 号：TL351+.1[核科学技术—核技术及应用] TL334