期刊文献+

AP1000核岛结构基础隔震设计与参数影响分析 被引量:3

Seismic Isolation Design and Parameter Effect Analysis of AP1000 Nuclear Island Structure
原文传递
导出
摘要 基于ANSYS和Midas Gen软件建立AP1000核岛结构有限元模型,通过非线性时程分析方法模拟核岛结构的三维地震响应,对核岛结构在安全停堆地震作用下的响应规律及隔震控制进行研究。选取隔震周期、刚度比和屈重比为控制参数,分析不同隔震层参数对核岛结构地震响应的影响。研究表明:引入基础隔震技术,能有效降低核岛结构的地震响应;核岛结构随隔震周期的延长,顶点水平加速度和隔震层剪力均呈现明显减小趋势,屈重比和屈服前后刚度比随隔震周期的延长,对隔震核岛结构的地震响应影响越小。 The finite element model of AP1000 nuclear island structure was built by ANSYS and Midas Gen software platform, and its three-dimensional seismic response was analyzed through nonlinear time history method. The seismic response and seismic isolation control of the nuclear island structure under safe shutdown earthquake is investigated. In addition, the isolation period, stiffness ratio and flexion weight ratio is selected as the control parameters of the seismic isolation layer, to analyze the seismic isolation layer and superstructure seismic response with different seismic isolation layer parameters. The results show that, the base seismic isolation can significantly reduce the seismic response of the nuclear island structure. The superstructure top horizontal acceleration and shear of seismic isolation layer remarkably decreases with the increasing of the isolation period. Besides, the effect of flexion weight ratio and stiffness ratio on the seismic response of isolated nuclear island structure declines with the increasing of the isolation period.
出处 《核动力工程》 EI CAS CSCD 北大核心 2016年第6期45-49,共5页 Nuclear Power Engineering
基金 国家自然科学基金项目(51378135 51408140) 广东省优秀青年教师(Yq201402) 教育部博士点新教师基金项目(20134410120003) 广州市科技计划项目(201510010291)
关键词 核岛结构 安全停堆地震 隔震层参数 地震响应 基础隔震 Nuclear island structure, Safe shutdown earthquake, Seismic isolation layer parameters, Seismic response, Base seismic isolation
  • 相关文献

参考文献9

二级参考文献55

  • 1汪训流,叶列平,陆新征.往复荷载下预应力混凝土结构的数值模拟[J].工程抗震与加固改造,2006,28(6):25-29. 被引量:11
  • 2钱稼茹,赵作周,段安,夏祖讽,王明弹.CNP1000核电厂安全壳1:10模型拟动力试验[J].土木工程学报,2007,40(6):7-13. 被引量:16
  • 3MSC. Software. MSC. Marc2005 (Volume A): Theory and user information [CP]. MSC. Marc Finite Element Program Documents, 2005.
  • 4Basha S M, Singh R K, Patnaik R. Predictions of ultimate load capacity for pre-stressed concrete containment vessel model with BARC finite element code ULCA [J]. Annals of Nuclear Energy, 2003, 30: 437-471.
  • 5夏祖讽.先进核电厂安全壳概念设计.上海核工程研究设计院,1999.
  • 6GB50011-2010,建筑抗震设计规范[S].
  • 7大崎顺彦,渡部丹监修.原子炉施设の耐震设计[M].日本产业出版社.1986.
  • 8JEAG4601-2008原子力发电所耐震设计技术指针[S].
  • 9JEAC4601-2008原子力发电所耐震设计技术规程[s].
  • 10刘耿.《幸福有多》[J].望东方周刊,2011,.

共引文献98

同被引文献25

引证文献3

二级引证文献6

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部