核电站燃料厂房辅助吊车抗震计算
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摘要
为实现核电站燃料厂房辅助吊车抗震计算,将结构的各阶固有模态用SRSS方法组合,并将多种地震波放大系数组成的包络线作为输入地震载荷,按SSE地震载荷楼层反应谱,X和Y方向加速度均取0.15g,Z方向加速度取0.10g,阻尼比取2%。计算结果表明,辅助吊车的基频为9.285Hz,远小于33Hz,整体为挠性结构;第一阶振型沿水平方向,显示地震作用下的位移响应以水平方向为主;位移响应幅值均小于跨度的1/1000(即14.3mm),满足规范要求。
Each order of structural intrinsic modes was combined by SRSS methods in order,to achieve the seismic cakulation of auxiliary crane in feul factor nuclear power station. The envelopes,which were composed by amplification factor of many seismic waves,were used as input earthquake load. When the accelerations were 0. 15g in X and Y directions,0. 10g in Z direction respectively,and the damping ratio was 2% ,the SSE were used for the floor response spectrum of seismic load,As the calculated results,the base band of auxiliary crane was 9. 285Hz,which was much less than 33Hz,so the whole structure it was flexible. Based on the direction of first-order vibration mode,the displacement response under earthquake was mainly on the horizontal direction. The amplitude of displacement response was less than on thousandth of span (for 14. 3 mm),it satisfied he requirement of specification.
Each order of structural intrinsic modes was combined by SRSS methods in order,to achieve the seismic cakulation of auxiliary crane in feul factor nuclear power station. The envelopes,which were composed by amplification factor of many seismic waves,were used as input earthquake load. When the accelerations were 0. 15g in X and Y directions,0. 10g in Z direction respectively,and the damping ratio was 2% ,the SSE were used for the floor response spectrum of seismic load,As the calculated results,the base band of auxiliary crane was 9. 285Hz,which was much less than 33Hz,so the whole structure it was flexible. Based on the direction of first-order vibration mode,the displacement response under earthquake was mainly on the horizontal direction. The amplitude of displacement response was less than on thousandth of span (for 14. 3 mm),it satisfied he requirement of specification.
引文
[1]Kei Kobayashi.Aseismic evaluation for aging degradation of nuclear power plant components[J].Nuclear Engineering and Design,2002,214(1):57～71.
[2]孙柏涛,刘永昌,高登琛,等.巴基斯坦恰希玛核电站用P300工程核级离心通风机抗震性能计算及试验研究[J].地震工程与工程振动,1997,17(1):89～94.
[3]I Micheli,S Cardini,A Colaiuda,et al.Investiga-tion upon the dynamic structural response of a nuclear plant on aseismic isolating devices[J].Nuclear Engineering and Design,2004,228(2):319～343.
[4]盛选禹,雒晓卫,傅激扬.反应堆主泵抗震强度的三维实体模型计算[J].核动力工程,2005,26(5):471～474.
[5]Zhang Zhengming,He Shuyan,Xu Ming.Seismic analysis of liquid storage container in nuclear reactors[J].Nuclear Engineering and Design,2007,237(12):1325～1331.
[6]朱林剑,孙守林,梁丰,等.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.
[7]李增光,雒王炯,吴天行.核电站环形吊车抗震计算分析[J].核动力工程,2008,29(1):46～49.
[8]国家地震局.GB50267-97核电厂抗震设计规范[S].北京:中国计划出版社,1998.
[2]孙柏涛,刘永昌,高登琛,等.巴基斯坦恰希玛核电站用P300工程核级离心通风机抗震性能计算及试验研究[J].地震工程与工程振动,1997,17(1):89～94.
[3]I Micheli,S Cardini,A Colaiuda,et al.Investiga-tion upon the dynamic structural response of a nuclear plant on aseismic isolating devices[J].Nuclear Engineering and Design,2004,228(2):319～343.
[4]盛选禹,雒晓卫,傅激扬.反应堆主泵抗震强度的三维实体模型计算[J].核动力工程,2005,26(5):471～474.
[5]Zhang Zhengming,He Shuyan,Xu Ming.Seismic analysis of liquid storage container in nuclear reactors[J].Nuclear Engineering and Design,2007,237(12):1325～1331.
[6]朱林剑,孙守林,梁丰,等.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.
[7]李增光,雒王炯,吴天行.核电站环形吊车抗震计算分析[J].核动力工程,2008,29(1):46～49.
[8]国家地震局.GB50267-97核电厂抗震设计规范[S].北京:中国计划出版社,1998.
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