Conceptual Design and Analysis of Cold Mass Support of the CS3U Feeder for the ITER

被引:0
作者
朱银锋 [1 ,2 ]
宋云涛 [1 ]
张远斌 [1 ,3 ]
王忠伟 [1 ]
机构
[1] Tokamak Design Division,Institute of Plasma Physics,Chinese Academy of Sciences
[2] School of Mechanical and Electrical Engineering,Anhui University of Architecture
[3] Mechanical Engineering Department,Hefei University
关键词
cold mass support; CS feeder; ITER; coupling analysis;
D O I
暂无
中图分类号
TL64 [热核反应堆(聚变堆)];
学科分类号
082701 ;
摘要
In the International Thermonuclear Experimental Reactor(ITER) project,the feeders are one of the most important and critical systems.To convey the power supply and the coolant for the central solenoid(CS) magnet,6 sets of CS feeders are employed,which consist mainly of an in-cryostat feeder(ICF),a cryostat feed-through(CFT),an S-bend box(SBB),and a coil terminal box(CTB).To compensate the displacements of the internal components of the CS feeders during operation,sliding cold mass supports consisting of a sled plate,a cylindrical support,a thermal shield,and an external ring are developed.To check the strength of the developed cold mass supports of the CS3U feeder,electromagnetic analysis of the two superconducting busbars is performed by using the CATIA V5 and ANSYS codes based on parametric technology.Furthermore, the thermal-structural coupling analysis is performed based on the obtained results,except for the stress concentration,and the max.stress intensity is lower than the allowable stress of the selected material.It is found that the conceptual design of the cold mass support can satisfy the required functions under the worst case of normal working conditions.All these performed activities will provide a firm technical basis for the engineering design and development of cold mass supports.
引用
收藏
页码:599 / 604
页数:6
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共 6 条
  • [1] Development of Experimental Superconducting Magnet for the Collector Ring of FAIR Project[J]. 朱银锋,吴维越,武松涛,徐厚昌,刘常乐.Plasma Science and Technology. 2010(02)
  • [2] ITER超导纵场线圈内馈线系统传热分析
    李长春
    宋云涛
    武松涛
    陈永华
    [J]. 低温与超导, 2009, 37 (11) : 21 - 25
  • [3] ITER PF导体铠甲低温力学性能研究
    刘华军
    武玉
    韩奇阳
    任志斌
    李来风
    [J]. 低温与超导, 2009, 37 (09) : 31 - 33
  • [4] Structural Analysis of the ITER VV Lower Port Region[J]. 蔡影祥,武松涛,郁杰.Plasma Science and Technology. 2007(04)
  • [5] Structural Analysis of ITER Lower In-Vessel-Viewing Port[J]. 蔡影祥,武松涛,郁杰,刘常乐.Plasma Science and Technology. 2006(06)
  • [6] Preliminary Engineering Design of Toroidal Field Magnet System for Superconducting Tokamak HT-7U
    潘引年
    翁佩德
    陈灼民
    李保增
    武松涛
    吴维越
    高秉钧
    郁杰
    吴镝
    吴雪冰
    陈强
    陈文革
    [J]. Plasma Science & Technology, 2000, (02) : 235 - 243