Coupled Finite Element Thermal-Mechanical Analysis of Gravity Support System of International Thermonuclear Experimental Reactor
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摘要: 根据热核实验反应堆重力支撑系统的结构特点,提出了重力支撑系统的有限元模型建模方法.应用ANSYS软件,采用单元网格划分法,建立了该重力支撑系统整体三维有限元模型,通过热-力耦合分析,得出热核实验反应堆重力支撑系统在静载荷、热负荷、电磁力和地震载荷同时作用下各零件的最大Tresca应力及其所在位置.零件的强度分析表明:支撑系统各零件的最大应力均小于其相应的许用应力,满足ASME压力容器规范.
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关键词:
- ITER重力支撑系统 /
- 有限元法 /
- 热-力耦合分析
Abstract: A method for building the finite element model of the gravity support system of the international thermonuclear experimental reactor (ITER) was put forward according to the structure characteristics of the gravity support system.By this method,a 3D finite element model of the gravity support system was built with ANSYS software using a mesh generation method of high precision and with an acceptable calculation scale.Then,a coupled thermal-mechanical analysis of the gravity support system was carried out,and the maximum Tresca stress and its position in every part of the system were obtained under the combined action of dead weight,thermal load,electromagnetic forces and seismic load.The stress analysis results show that the maximum stresses in all parts of the system are smaller than their respective allowable stress limits,and that the parts have enough mechanical strength to meet the requirements of ASME Pressure Vessel Code-III NF. -
赵君煜.国际热核聚变实验堆(ITER)计划[J].物理,2004,33 (4):257-260.ZHAO Junyu.The international thermonuclear experimental reactor program[J].Physics,2004,33(4):257-260.[2] LIBEYRE P,DOLGETTA N,DECOOL P,et al.Mechanical tests of the ITER toroidal field model coil[J].IEEE Trans.Appl.Supercond,2004,14(2):1382-1387.[3] 张亚欧,谷志飞,宋勇.ANSYS7.0有限元分析实用教程[M].北京:清华大学出版社,2004:276-300.[4] MYATT R L,Finite element analysis of the TPX toroidal field coil system[J].IEEE Trans.Appl.Mag.,1994,30(4):2082-2085.[5] 程亚丽,鲍立曼,宋云涛,等.EAST超导托卡马克核聚变实验装置真空室窗口烘烤及热应力分析[J].原子能科学技术,2006,40(5):595-598.CHENG Yali,BAO Liman,SONG Yuntao,et al.Baking system for ports of experimental advanced super-conducting tokamk vacuum vessel and thermal stress analysis[J].Atomic Energy Science and Technology,2006,40(5):595-598.[6] 李明海,史光梅,王晓宇,等.核冷却试验包层模块的热-力耦合分析[J].核动力工程,2007,28(1):32-35.LI Minghai,SHI Guangmei,WANG Xiaoyu,et al.Thermal-mechanical analyses of helium-cooled test blanket module[J].Nuclear Power Engineering,2007,28(1):32-35.[7] 刘常乐,郁杰,武松涛.ITER真空室中子屏蔽组件的热-静力学有限元分析[J].机械强度,2007,29(1):67-71.LIU Changle,YU Jie,WU Songtao.Thermo-static fem analysis for neutron shielding component of iter vacuum vessel[J].Journal of Mechanical Strength,2007,29(1):67-71.[8] ASME锅炉及压力容器委员会压力容器分委员会.ASME 锅炉压力容器规范:第Ⅷ卷,第三册高压容器建造规则[S].北京:中国石化出版社,2005. -
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