核电厂大型组合结构的有限元抗震分析方法研究
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摘要
在现代核电站抗震设计中,有限元法是各类相关设备抗震分析与评价的重要数值仿真工具。对于形状复杂、部件众多的大型组合结构,采用整体三维建模的有限元模型通常需要很大的存储和计算规模,超出现有的计算条件。因此需要首先研究组合结构各个部件的动力学特性,从而建立合理的三维简化力学模型,并以该模型为基础进行有限元数值仿真。本文以某地车-吊车组合结构为例,给出此类大型组合结构的抗震分析方法,并将等效静力法与反应谱法相结合,对该结构进行分析,最后根据相关法规对各子结构进行评价,以确保总体组合结构在极限安全地震条件下能够保持结构完整性。
In design of modern nuclear power plants,the finite element method is regarded as an important numerical simulation tool for seismic analysis and evaluation of all kinds of equipment.For those large,complicated joint structures with considerable equipment,a total three-dimensional finite element model requires huge computer resources,beyond the abilities of most currently used computers.Therefore,it is required to study dynamic characteristics of each sub-structure and to establish appropriately simplified three-dimensional mechanical models which can be used for finite element simulation.In this paper,the seismic analysis method for large joint structures is given to deal with a crane-joint structure.The equivalent static method and response spectra method are used to analyze such structure.Finally,these sub-structures are evaluated based the regulations of nuclear codes to ensure the structure integrity of the crane-joint structure when subjected to the ultimate safety ground motions.
In design of modern nuclear power plants,the finite element method is regarded as an important numerical simulation tool for seismic analysis and evaluation of all kinds of equipment.For those large,complicated joint structures with considerable equipment,a total three-dimensional finite element model requires huge computer resources,beyond the abilities of most currently used computers.Therefore,it is required to study dynamic characteristics of each sub-structure and to establish appropriately simplified three-dimensional mechanical models which can be used for finite element simulation.In this paper,the seismic analysis method for large joint structures is given to deal with a crane-joint structure.The equivalent static method and response spectra method are used to analyze such structure.Finally,these sub-structures are evaluated based the regulations of nuclear codes to ensure the structure integrity of the crane-joint structure when subjected to the ultimate safety ground motions.
引文
[1]核电厂抗震设计规范GB50267-97[S].北京:中国标准出版社,1997.
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[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,2005,5:471-474.
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[2]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,2001,4:26-30.
[3]万力,傅激扬,吴莘馨,等.中国先进研究堆备用柴油发电机组的抗震动力学分析[J].高技术通讯,2005,2:62-66.
[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,2005,5:471-474.
[5]朱镜清.结构抗震分析原理[M].北京:地震出版社,2001.
[6]马爱军,周传月.Patran和Nastran有限元分析专业教程[M].北京:清华大学出版社,2005.
[7]美国机械工程师学会.ASME-Ⅲ核动力装置设备,第三册,NC分卷,二级设备[S].合肥:中国机械工程学会,1989.
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