检索规则说明:AND代表“并且”;OR代表“或者”;NOT代表“不包含”;(注意必须大写,运算符两边需空一格)
检 索 范 例 :范例一: (K=图书馆学 OR K=情报学) AND A=范并思 范例二:J=计算机应用与软件 AND (U=C++ OR U=Basic) NOT M=Visual
作 者:黄茜[1] 张毅雄[1] 沈平川[1] 余晓菲[1] 吴万军[1]
机构地区:[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610041
出 处:《核动力工程》2016年第5期19-23,共5页Nuclear Power Engineering
摘 要:建立反应堆结构三维非线性有限元模型,采用总体瑞利阻尼、局部材料阻尼和弹簧单元阻尼相结合的方法解决部件间的阻尼差异问题,导出燃料组件的等效间隙与等效刚度计算公式并真实地模拟了带间隙的同心圆部件间的接触、动态变化的预紧力和摩擦效应。随后,以同时满足响应谱和功率谱包络性要求的非平稳地震位移时程作输入,开展反应堆结构的非线性地震分析,得到结构在安全停堆地震(SSE)下的地震响应,为反应堆结构的三维非线性抗震研究提供借鉴。A three-dimensional nonlinear FEM model of reactor equipment and system was built. In the model, global Rayleigh damping, local material damping and element damping were used simultaneously to deal with the damping difference of different structures, and the method of equivalent stiffness and equivalent gap between fuel assemblies and the core shroud was proposed. Meanwhile, the contact effect with a positive gap between two concentric cylinders and the dynamic friction effect with variational pre-tightening force was simulated. Subsequently, seismic time history inputs compatible with both response spectrum and power spectrum density(PSD) was introduced as the analysis input, and a nonlinear 3D reactor equipment and system seismic analysis was carried out. Finally, seismic responses were obtained for SSE event. The research in this paper provides a guidance and reference for the future 3D nonlinear seismic analysis of reactor equipment and system.
分 类 号:TL371[核科学技术—核技术及应用]
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在链接到云南高校图书馆文献保障联盟下载...
云南高校图书馆联盟文献共享服务平台 版权所有©
您的IP:216.73.216.15