反应堆堆芯围筒结构热流固耦合热变形分析  

Thermal deformation analysis on thermal-fluid-structure coupling of reactor core shroud

作　　者：赵飞云[1] 朱焜[1] 李源[1] 于浩[1] 翁羽[1] 张明[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《计算机辅助工程》2012年第4期43-46,共4页Computer Aided Engineering

摘　　要：针对反应堆堆芯围筒热流固耦合问题,采用三维有限元法研究堆芯围筒的热变形.考察ANSYS的三维实体热单元SOLID 70,三维实体单元SOLID 45,三维表面热效应单元SURF 152和三维热-流耦合管单元FLUID 116等单元类型的特点和实用性.建立堆芯围筒、吊篮和冷却剂的温度分析有限元模型:堆芯围筒和吊篮采用SOLID 70,结构表面与冷却剂的对流传热表面采用SURF152,堆芯围筒与吊篮之间冷却剂采用FLUID 116.采用SOLID 45建立堆芯围筒有限元模型,根据得到的堆芯围筒、吊篮和冷却剂的温度场结果分析堆芯围筒热变形.结果表明,在考虑堆芯围筒及吊篮固体和流体的交叉耦合的基础上,采用三维有限元法能比较客观地模拟反应堆堆芯处的复杂运行环境.As to the thermal-fluid-structure coupling issue of reactor core shroud, the thermal deformation of core shroud is researched by 3D finite element method. The characteristics and practicability are researched for ANSYS element types including 3D solid thermal element SOLID 70,3D solid element SOLID 45,3D surface thermal effect element SURF 152 and 3D thermal-fluid coupling pipe element FLUID 116. The finite element models of thermal analysis are built for reactor core shroud, barrel and coolant. For the models, the core shroud and barrel are modeled by SOLID 70; the structure surface and convective heat transfer surface of coolant are modeled by SURF 152; the coolant between core shroud and barrel is modeled by FLUID 116. The finite element model of thermal deformation analysis is built for core shroud by SOLID 45, and the thermal deformation of core shroud is analyzed according to the temperature field results of core shroud, barrel and coolant. The results indicate that, considering the thermal-fluid-structure coupling among core shroud, barrel and coolant, the complex running environment of reactor core shroud can be simulated objectively by 3D finite element method.

关 键 词：反应堆 堆芯围筒 热变形分析 热流固耦合 冷却剂 ANSYS 

分 类 号：TL351.1[核科学技术—核技术及应用]