ITER高温超导电流引线测试杜瓦设计与分析  

ITER poloidal field high temperature superconducting current lead test dewar design and analysis

作　　者：韩全 陆坤 刘辰 刘承连 丁开忠[1] 宋云涛[1] Han Quan;Lu Kun;Liu Chen;Liu Chenglian;Ding Kaizhong;Song Yuntao(Institute of Plasma Physics,Chinese Academy of Sciences,Hefei 230031,China)

机构地区：[1]中国科学院等离子体物理研究所,合肥230031

出　　处：《低温工程》2018年第5期50-54,共5页Cryogenics

基　　金：国家ITER Feeder采购包项目(项目编号:Y15QT12561)

摘　　要：为了满足国际热核聚变反应堆计划(ITER)高温超导电流引线测试需要的低温及真空工作环境,根据杜瓦设计的各项技术指标要求,设计了ITER高温超导电流引线的测试杜瓦结构。通过对外筒体进行了结构强度校核分析,确定了外筒体的结构设计方案。对冷屏及其冷却管进行了设计、选型及压差计算,确定了冷屏设计方案。通过对冷屏绝热支撑结构设计及热负荷计算,确定了冷屏的各项热负荷情况。各项计算结果均满足要求,同时并对该ITER高温超导电流引线测试杜瓦成功进行了制造和测试。In order to meet the requirements of low temperature and high vacuum working conditions for international thermonuclear experimental reactor（ ITER） high temperature superconducting current lead test,a test dewar of ITER high temperature superconducting current lead was designed according to the dewar design requirements. The outer shell structure was established based on the engineering analysis. The pressure drop of thermal shield and its pipes were calculated to determine the structures. Based on the heat load analysis,thermal shield support structure was designed. All the calculation and analysis results meet the requirements. A test dewar was manufactured,and the ITER high-temperature superconducting current lead was successfully tested in it.

关 键 词：ITER 高温超导电流引线 测试杜瓦 设计 分析 

分 类 号：TB69[一般工业技术—制冷工程]