ITER极向场线圈过渡馈线冷屏的结构优化与传热耦合分析  

Design Considerations of Thermal Shield of Cryostat Feed-Through of Poloidal Coil for International Thermonuclear Experimental Reactor

作　　者：董标[1] 韩曼芬[1] 王开松[1] 宋云涛[2] 王忠伟[2] 程勇[2] 吕佳佳[1] 邵珠振[1] 冯昌乐[1] 徐杨[1] 

机构地区：[1]安徽理工大学机械工程学院,淮南232001 [2]中国科学院等离子体物理研究所,合肥230031

出　　处：《真空科学与技术学报》2011年第5期612-616,共5页Chinese Journal of Vacuum Science and Technology

基　　金：国家重点基础研究发展计划(973计划)项目"ITER高温超导超大电流引线型超导传输线的研究2008CB717900";ITER计划(1TER大型超导磁体系统馈线研究2008GB102000)专项支持项目;安徽理工大学博士基金项目

摘　　要：国际热核聚变实验堆磁体馈线系统是连接杜瓦内部的磁体线圈和杜瓦外部之间的冷源、电源以及控制系统的重要通道,其主要作用是为磁体线圈供电、冷却和测量控制诊断。本文通过理论传热计算、利用有限元分析软件ANSYS进行热分析和温度-结构耦合分析,对处于特殊低温与真空环境的辐射冷屏进行了结构优化,保证了系统的安全运行,为降低冷屏热应力和4.5 K温区的热负荷、减小整个系统的热漏指明了方向,为下一轮冷屏结构设计提供了可靠的依据。The thermal shield of the cryostat feed-through was designed,constructed,and installed in the poloidal coil system for the international thermonuclear experimental reactor（ITER）.The heat transport and the coupling of the structures and the temperature field were calculated in finite element method by means of a software package,ANSYS,for the purpose of the design optimization of the radioactive thermal shield,used in low temperature and high vacuum environment.The preliminary results show that the optimized structure of the thermal shield,on the basis of the calculation,is capable of reducing the heat stress and the heat loads and the heat leak of the thermal shield operating at 4.5 K.Possible improvement of the design was also discussed.

关 键 词：国际热核聚变实验堆 极向场 过渡馈线 冷屏 传热分析 

分 类 号：TL626[核科学技术—核技术及应用]