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Development of remountable joints and heat removable techniques for high- temperature superconducting magnets

机译：开发用于高温超导磁体的可重新安装的接头和可热移除的技术

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摘要

Segment fabrication is now a candidate for the design of superconducting helical magnets in the helical fusion reactor FFHR-dl, which adopts the joint winding of high-temperature superconducting (HTS) helical coils as a primary option and the 'remountable' HTS helical coil as an advanced option. This paper reports on recent progress in two key technologies: the mechanical joints (remountable joints) of the HTS conductors and the metal porous media inserted into the cooling channel for segment fabrication. Through our research activities it has been revealed that heat treatment during fabrication of the joint can reduce joint resistance and its dispersion, which can shorten the fabrication process and be applied to bent conductor joints. Also, heat transfer correlations of the cooling channel were established to evaluate heat transfer performance with various cryogenic coolants based on the correlations to analyze the thermal stability of the joint.
机译：分段制造现在是螺旋聚变反应堆FFHR-dl中超导螺旋磁体设计的候选方案，该模型采用高温超导（HTS）螺旋线圈的联合绕组作为主要选择，而“可重装” HTS螺旋线圈作为主要选择高级选项。本文报告了两项关键技术的最新进展：HTS导体的机械接头（可重装接头）和插入到冷却通道中用于分段制造的金属多孔介质。通过我们的研究活动，我们发现，在接头制造过程中进行热处理可以降低接头电阻及其分散，从而可以缩短制造过程，并应用于弯曲导体接头。此外，建立了冷却通道的传热相关性，以基于各种低温制冷剂的相关性来分析接头的热稳定性，从而评估传热性能。

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  • 来源
    《Nuclear fusion》 |2018年第2期|326014.1-326014.8|共8页
  • 作者

    H. Hashizume; S. Ito; N. Yanagi; H. Tamura; A. Sagara;

  • 作者单位

    Department of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, 6-6-01-2, Aramaki-Aza-Aoba, Aoba-ku, Sendai, Miyagi, 980-8579, Japan;

    Department of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, 6-6-01-2, Aramaki-Aza-Aoba, Aoba-ku, Sendai, Miyagi, 980-8579, Japan;

    National Institute for Fusion Science, 322-6, Oroshi-cho, Toki, Gifu 509-5292, Japan;

    National Institute for Fusion Science, 322-6, Oroshi-cho, Toki, Gifu 509-5292, Japan;

    National Institute for Fusion Science, 322-6, Oroshi-cho, Toki, Gifu 509-5292, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    high-temperature superconductor; helical fusion reactor; remountable HTS magnet; joint-winding; mechanical joint; porous media; heat transfer correlation;

    机译：高温超导体螺旋聚变反应堆可重装的HTS磁铁;联合绕组机械接头多孔介质传热相关;

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