华龙一号吊篮1:5模型试验流致振动响应计算分析

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英文篇名：Calculation Analysis of Response of Flow-Induced Vibration in Core Barrel for 1:5 Scale Model Test of HPR1000 作者：席志德 ; 杨杰 ; 马建中 英文作者：Xi Zhide;Yang Jie;Ma Jianzhong;Mechanical Laboratory for Reactor Structure of Nuclear Power Institute of China; 关键词：华龙一号(HPR1000) ; 堆内构件 ; 吊篮 ; 流致振动 英文关键词：HPR1000;;Nuclear internals;;Core barrel;;Flow induced vibration 中文刊名：HDLG 英文刊名：Nuclear Power Engineering 机构：中国核动力研究设计院核反应堆结构力学室; 出版日期：2019-06-30 出版单位：核动力工程 年：2019 期：v.40 语种：中文; 页：HDLG2019S1017 页数：4 CN：S1 ISSN：51-1158/TL 分类号：74-77

摘要

秦山核电厂二期堆内构件1:5模型试验的流致振动分析是利用试验数据外推得到的,目的是获得响应最大值。华龙一号(HPR1000)堆内构件1:5模型试验吊篮的流致振动响应分析采用了相类似的分析方法,最终获得了吊篮的位移和应变响应值。该方法首先进行HPR1000吊篮有限元模型建模,幵通过模态分析获得了各阶模态的响应最大点的值与测量点的模态频率下响应值的比例关系,用该比例关系获得了吊篮的最大响应值。
        The analysis of the flow-induced vibration of internals for 1:5 scale model test of the Qinshan Nuclear Power Plant phase Ⅱ was conducted by extrapolating from experimental data, to obtain the maximal response. The same method is used to get the response of the flow-induced vibration of core barrel for 1:5 scale model test of HPR1000. Firstly, the finite element model is established, and the proportion about the maximal response and the experimental data is obtained. Based on those proportions, the response can be achieved.

引文

[1]毛庆,张景绘.反应堆吊篮流致振动响应分析中的理论研究[J].核动力工程,2004,25(3):198-202.
    [2]YANG M A,HCONNELLY W.Computerized Method Flow-Induced Random Vibration Analysis of Nuclear Reactor Internals[J].Nuclear Engineering and Design,1977,42:257-263.
    [3]席志德,陈炳德,李朋洲,等.输送流体的同心圆筒结构动力特性研究[J].工程力学,2008,25(11):218-222.