接触分析在反应堆结构设计中的应用  

Application of Contact Analysis in Nuclear Reactor Structural Design

作　　者：王亚曦[1] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计重点实验室,成都610041

出　　处：《核动力工程》2013年第S1期164-167,共4页Nuclear Power Engineering

摘　　要：核反应堆结构中板和壳之间存在较多的接触问题。正确模拟接触物体间的刚度特性是建立反应堆动力分析模型的关键。本研究采用数值计算的方法,通过与试验数据比较,合理地选取接触算法和接触参数,研究核反应堆结构间接触物体的非线性刚度,完善数值计算方法。研究结果证明:采用增广拉格朗日(Lagrange)乘子法和平面应力模型分析板和壳之间的接触刚度能够较好地反映试验结果。The contact problems between the plate and shell often exist in nuclear reactor structure.In order to develop appropriately the reactor structure dynamic finite element model,it is important to correctly stimulate the stiffness characteristics between contact pairs.This paper focuses on the numerical calculation methods and the selection of reasonable contact arithmetic and parameter by comparing with experimental data.The nonlinear contact stiffness between contact objects in reactor structure is studied,and the numerical calculation methods are consummated.The study results verify that it can represent experimental behaviors by adopting Augmented Lagrange Multiplier method and plane stress model to analyze the contact stiffness between the plate and shell.

关 键 词：接触 反应堆结构 静压刚度 

分 类 号：TL371[核科学技术—核技术及应用]