Advanced high-temperature superconducting magnet for fusion reactors: Segment fabrication and joint technique
Advanced high-temperature superconducting magnet for fusion reactors: Segment fabrication and joint technique
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DOI：
10.1016/j.fusengdes.2018.01.072
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发表时间：
2018-11-01
影响因子：
1.7
通讯作者：
Tamura, Hitoshi
中科院分区：
文献类型：
--
作者：
Ito, Satoshi;Hashizume, Hidetoshi;Tamura, Hitoshi
超导磁体可能会变得更大，更复杂，用于未来的演示和商业聚变反应堆。对于这种情况下，创新的设计概念，可拆卸（或可拆卸）的高温超导（FITS）磁体已被提出用于托卡马克和螺旋反应堆，使用高温超导材料的高热稳定性和低温功率的特点。在日本，已经提出了HTS线圈的联合绕组的衍生概念，其中线圈通过连接短导体段来缠绕。本文首先简要总结了接头设计中的重要技术的设计历史和研究开发现状，然后报道了插入铟箔的机械搭接接头的最新研究进展。根据接头电阻随温度、外加磁场和导体中高温超导带材层数和行数的变化规律，对100 kA级高温超导导体接头进行低温热处理，接头电阻可降低到初始值的1/3。这些接头的机械行为表明，铟的应力松弛不影响制造时间，并且在高电磁力下，含有铟的机械接头比钎焊接头更优选。
Superconducting magnets may potentially become larger and more complex for use in future demonstration and commercial fusion reactors. For such situations, the innovative design concept of remountable (or demountable) high-temperature superconducting (FITS) magnets has been proposed for both tokamak and helical reactors that uses the HTS material features of high thermal stability and low cryogenic power. In Japan, the derived concept of joint-winding of HTS coils has been proposed, in which the coils are wound by connecting short conductor segments. This paper first briefly summarizes the design proposal history and current research and development (R&D) status of the important technologies for joint design, and then reports recent R&D progress in mechanical lap joints with inserted indium foils. Based on the joint resistance as a function of temperature, the applied magnetic field and the numbers of layers and rows of HTS tapes in the conductor, the joint resistance of a 100 kA-class HTS conductor joint can be reduced to one third of its initial value by low-temperature heat treatment. Mechanical behavior of these joints indicates that stress relaxation of indium does not affect the fabrication time and that mechanical joints containing indium are preferable to soldered joints under high electromagnetic forces.