核2级调节阀的抗震分析及试验研究
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摘要
基于ANSYS有限元分析软件,在模态分析基础上,采用等效静力法对调节阀的抗震性能进行分析,分析了调节阀在开启和关闭状态下对SL1(运行安全地震动)的应力响应,并分析了调节阀在开启状态下对SL2(安全停堆地震动)的应力响应,分析得知支架拐角、阀盖-中法兰连接的弯角处和阀体中腔为薄弱部位,其最大应力值均小于许用应力。对调节阀分别进行两次SL1地震和一次SL2地震试验,测定调节阀的自振频率、阻尼等振动参数和加速度、应力等地震响应参数,试验结果表明调节阀具有足够的刚度和强度,满足抗震设计强度要求。试验结果与有限元分析结果对比,误差小于10%。
By using finite element analysis software ANSYS,modal analysis of a control valve is carried out,and on the base of modal analysis results,the seismic response analysis of the controled valve in opening and closing states under SL1(operating basis earthquake)and that of the contral valve is opening state under SL2(sate shutdown eathquake) are carried out by the equivalent static method.The analysis results show that the corner bracket,the corner of valve cover-flange connection and the valve body are weak parts,and their maximum stress values are less than allowable stress.Two times SL1 and one time SL2 seismic experiments on the control vavle were performed in each composite direction to determine its natural frequency,damping and other parameters.The experiment results show that the valve has sufficient stiffness and strength to meet the seismic design strength requirment.Comparing the experiment results with analysis results,the largest error is less than 10%.
引文
[1]中国核工业总公司.EJ/T531-2001,核电厂专用起重机设计准则[S],2001.Chin Nuclear Industry Corporation.EJ/T 531-2001,Nuclear Power Plant Special Crane Design Criteria[S],2001.
    [2]法国核岛设备设计制造规则协会.RCC-M压水堆核岛机械设备设计和建造规则:第I卷A和Z篇[S],2000.French pressure shell equipment design and manufacture rules association.RCC-M PWR Pressure Shell of Mechanical Equipment Design and BuildRules[S],2000.
    [3]王炯,吴天行.核电站环形吊车抗震计算分析李增光[J].核动力工程,2008,(1):46-49.WANG Jiong,WU Tianxing.Analysis of seismic response of a polar crane in nuclear power plant[J].Nuclear Power Engineering,2008(01):46-49.
    [4]张征明,何树延,李仲三.核反应堆贮液容器的抗震分析[J].核动力工程,2001,(4):314-316.ZHANG Zhengming,HE Shuyan,LI Zhongsan.Seismic analysis of liquid storage container in nuclear reactors[J].Nuclear Power Engineering,2001,(4):314-316.
    [5]朱林剑,孙守林.130/10t核级专用桥式起重机抗震分析[J].起重运输机械,1997,(7):7-10.ZHU Linjian,SUN Shoulin.Analysis of seismic response 130/10t nuclear class specialised overhead travelling crane[J].Hoisting and ConveyingMachinery,1997(7):7-10.
    [6]张征明,吴莘馨,何树延.核安全级阀门的结构力学分析[J].阀门,2004,(4):1-4.ZHANG Zhengming,WU Xinxin,HE Shuyan.Structural mechanical analysis of the nuclear safety-related valve[J].Valve,2004,(4):1-4.
    [7]张征明,吴莘馨.核安全一级阀门的力学分析[J].阀门,2007,(2):18-22.ZHANG Zhengming,WU Xinxin.Mechanical analysis of the nuclear safety class 1 valve Institute of Nuclear and new Energy Technology,TsinghuaUniversity,Beijing 100084,China
    [8]孙英学.核电站稳压器阀门接管应力分析[J].核动力工程,2000,(2):112-116.SUN Yingxue.Stress analysis of valve nozzle of pressurizer in NPP[J].Nuclear Power Engineeing,2000,(2):112-116.
    [9]JIANG Zhengfeng,Zhou Chao,Ding Yufeng.Dynamics analysis of engine valves based on ANSYS[J].Lubrication Engineering,2006,(4):106-108.
    [10]周长城,胡仁喜,熊文波.Ansys11.0基础与典型范例[M].电子工业出版社,2007.ZHOU Changcheng,HU Renxi,XIONG Wenbo.Ansys11.0.O foundation and typical examples[M].Electronic Idustry Rress,2007.
    [11]Fanous F,Greimann L,Rogers J.ANSYS3-Danalysisofnuclearsteelcontainment[C]//4th IntANSYSConfExhib1989 Part2,1989:10.20-10.32.

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