横向流动中直立圆管的流致振动分析
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- 英文论文题名：Flow-induced vibration analysis on vertical tube in cross flow
- 论文作者：张国欣 ; 赵民富 ; 薛松龄
- 英文论文作者：ZHANG Guo-xin ; ZHAO Min-fu ; XUE Song-ling ; China Institute of Atomic Energy
- 年：2015
- 作者机构：中国原子能科学研究院;
- 论文关键词：中国实验快堆 ; 流致振动 ; 流固耦合 ; 数值模拟
- 英文论文关键词：china experiment fast reactor ; flow-induced vibration ; fluid-structure coupling ; numerical Simulation
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第3册（核能动力分卷（下））
- 语种：中文
- 分类号：TL433
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：4
- 文件大小：259k
- 原文格式：O
- 会议级别：全国
摘要
中国实验快堆堆芯中心测量柱热电偶护管工作于横向流动的液态钠之中,可能存在涡致振动、湍流激振等流致振动现象。针对此类横向流动中的细长结构,本文建立了一个直立圆管模型,采用计算流体力学软件CFX与力学分析软件ANSYS相耦合的方法对其进行了模拟计算,并选取多种工况进行了敏感性分析,得出了横向流动中直立圆管流致振动的响应规律。计算结果表明,中国实验快堆堆芯中心测量柱热电偶护管不会发生共振,是安全的。
The thermocouple well,which located in centre measuring column of China Experiment Fast Reactor(CEFR) core,lies in cross flow of liquid sodium.It may exist flow-induced vibration、turbulence excitation and such as flow-induced vibration phenomena.The vertical tube model has been established,aiming to simulate such slender structure in cross flow,and the coupling method of CFX and ANSYS is used to simulate the model.The response regular of vertical tube in cross flow is obtained through sensitivity analyses beyond many cases.The results indicate that the thermocouple well,located in centre measuring column of CEFR core,won't resonate,which is safe.
The thermocouple well,which located in centre measuring column of China Experiment Fast Reactor(CEFR) core,lies in cross flow of liquid sodium.It may exist flow-induced vibration、turbulence excitation and such as flow-induced vibration phenomena.The vertical tube model has been established,aiming to simulate such slender structure in cross flow,and the coupling method of CFX and ANSYS is used to simulate the model.The response regular of vertical tube in cross flow is obtained through sensitivity analyses beyond many cases.The results indicate that the thermocouple well,located in centre measuring column of CEFR core,won't resonate,which is safe.
引文
[1]徐銤.我国快堆技术发展现状与前景[A].见:中国核学会核能动力学会反应堆热工流体专业委员会,第十届全国反应堆热工流体力学会议论文集,第十届全国反应堆热工流体力学会议,北京,2007.10,北京,原子能科学技术出版社,2007:1-4.
[2]Laurent Borsoi,Flow-Induced Vibration Of Nuclear Components:Future R&D Perspective Derived form the French Experience[A].Transactions,SMiRT 16,Washington DC,2001.8:1460-1471.
[3]S.Patil,A.Murthy,Y.Dagba,Coupled structure(FE)and fluid flower(FV)analysis for vortex induced vibrations[A].Transactions,SMiRT 16,Washington DC,2001.8:2010-2016.
[4]Masaya KONDO,Yoshinari ANODA,Water flow simulation test on flow induced oscillation of thermowell in prototype fast breeder reactor MONJU[J].JSME International Journal,2001,44(4):688-694.
[5]赵民富,张国欣,陈玉宙.竖直圆管内超临界水传热特性数值模拟[J].原子能科学技术,2011.2,45(2):146-149.
[6]Robert D.Blevin Ph.D,Formulas For Natural Frequency and Mode Shape[M].Van Nostrand Reinhold Company,New York,1979:108-109.
[7]Shoei-Sheng Chen,Flow-Induced Vibration Of Circular Cylindrical Structures[M].Hemisphere Publishing Corporation,New York,1987:248-271.
[2]Laurent Borsoi,Flow-Induced Vibration Of Nuclear Components:Future R&D Perspective Derived form the French Experience[A].Transactions,SMiRT 16,Washington DC,2001.8:1460-1471.
[3]S.Patil,A.Murthy,Y.Dagba,Coupled structure(FE)and fluid flower(FV)analysis for vortex induced vibrations[A].Transactions,SMiRT 16,Washington DC,2001.8:2010-2016.
[4]Masaya KONDO,Yoshinari ANODA,Water flow simulation test on flow induced oscillation of thermowell in prototype fast breeder reactor MONJU[J].JSME International Journal,2001,44(4):688-694.
[5]赵民富,张国欣,陈玉宙.竖直圆管内超临界水传热特性数值模拟[J].原子能科学技术,2011.2,45(2):146-149.
[6]Robert D.Blevin Ph.D,Formulas For Natural Frequency and Mode Shape[M].Van Nostrand Reinhold Company,New York,1979:108-109.
[7]Shoei-Sheng Chen,Flow-Induced Vibration Of Circular Cylindrical Structures[M].Hemisphere Publishing Corporation,New York,1987:248-271.