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控制棒驱动机构与反应堆堆顶组合模型的抗震分析
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  • 英文篇名:Seismic Analysis of Assembled Model of Control Rod Drive Mechanism and Reactor Head Package
  • 作者:鲁治诚 ; 尚尔涛 ; 伍时建 ; 聂照宇 ; 陈永超
  • 英文作者:LU Zhi-cheng;SHANG Er-tao;WU Shi-jian;NIE Zhao-yu;CHEN Yong-chao;State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment;China Nuclear Power Design Co.,Ltd;Shanghai Branch,China Nuclear Power Design Co.,Ltd;
  • 关键词:控制棒驱动机构 ; 反应堆堆顶 ; 抗震分析
  • 英文关键词:control rod drive mechanism;;reactor head package;;seismic analysis
  • 中文刊名:JSCX
  • 英文刊名:Equipment Environmental Engineering
  • 机构:核电安全监控技术与装备国家重点实验室;深圳中广核工程设计有限公司;深圳中广核工程设计有限公司上海分公司;
  • 出版日期:2019-02-25
  • 出版单位:装备环境工程
  • 年:2019
  • 期:v.16
  • 语种:中文;
  • 页:JSCX201902013
  • 页数:5
  • CN:02
  • ISSN:50-1170/X
  • 分类号:72-76
摘要
目的获得控制棒驱动机构(CRDM)和反应堆堆顶组件(RHP)在地震作用下的动力学响应。方法建立控制棒驱动机构与反应堆堆顶组件的有限元组合模型,采用ANSYS软件对模型开展三维非线性抗震分析。分析模型中分别用梁单元、杆单元和弹簧单元等模拟堆顶的各个部件,考虑控制棒驱动机构抗震支承板之间、抗震支承板与抗震支承环之间的相互碰撞作用。此外,将电缆托架和电缆桥组件的梁模型也加入到组合模型,而不是简单地将其简化为集中质量,可减小该部分质量分配不真实对抗震分析结果带来的误差。结果利用ANSYS软件时程法中的直接积分法完成了组合模型的抗震分析,提取了控制棒驱动机构和反应堆堆顶组件各部位应力评定所需的载荷。结论较为准确地模拟了抗震板之间的碰撞作用,得到了各截面的载荷,可为设备应力分析提供输入。
        Objective To obtain the dynamic response of control rod drive mechanism(CRDM) and reactor head package(RHP) under earthquake conditions.Methods The assembled finite element model for CRDM and RHP was established.Three-dimensional nonlinear seismic analysis was performed with software ANSYS.Beam,link,and spring elements in software ANSYS were used for modeling components of CRDM and RHP,and the collision effects among seismic support plates and between seismic ring and seismic support plates were considered.Furthermore,the beam model of cable frame and cable-bridge was also assembled in the model instead of simplifying to quality point,which can reduce the error of seismic analysis caused by untruthful mass distribution.Results The seismic analysis and calculation of assembled model were conducted by the direct integral calculus method with software ANSYS,and the section loads of CRDM and RHP which was required in stress analysis were extracted.Conclusion The seismic plate collision between the load of each section is simulated accurately and the load of each section is obtained.It can provide input for stress analysis of equipment.
引文
[1]RCC-M-2012,Design and Construction Rules for Mechanical Components of Power Nuclear Islands[S].
    [2]ASME-2013,ASME Boiler and Pressure Vessel Code[S].
    [3]ANSYS Inc.ANSYS User′s Manual for Revision[K].Pittsburgh:ANSYS Inc,2009.
    [4]NUREG-0800,Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants:LWREdition[S].

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