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Development of Superconducting Test Coil using Titanium Pipe for the International Thermonuclear Engineering Reactor (ITER)

机译:使用钛管用于国际热核工程反应器(ITER)的超导试验线圈的开发

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摘要

A superconducting test coil using pure titanium pipe was developed by Efremov Institute of Russian Federation during the Engineering and Design Activity for the International Thermonuclear Experimental Reactor (ITER). The coil was also tested with the superconducting coil test facility of Japan Atomic Energy Research Institute (JAERI) and achieved the ITER requirement, maximum magnetic field of 13 T at rated current of 46 kA. A feature of the coil is use of pure titanium pipe as a jacket of the superconductor to prevent degradation of superconducting performance due to thermal strain caused by a difference of thermal contraction between the jacket and superconducting strands. The pure titanium pipe having 0.106 percent oxygen content was used based on the development to find optimum mechanical properties at 4 K, which was performed in collaboration with JAERI and Nippon Steel Corporation.
机译:使用纯钛管的超导试验线圈由俄罗斯联邦EFREMOV研究所开发,在工程和设计活动中,为国际热核实验反应器(磨料)。 该线圈也用日本原子能研究所(JAERI)的超导线圈测试设施进行了测试,并达到了46ka额定电流的最大磁场,最大磁场13t。 线圈的特征是使用纯钛管作为超导体的护套,以防止由于夹克和超导股之间的热收缩差异引起的热应变导致的超导性能的降低。 基于显影使用具有0.106%的氧含量的纯钛管,以找到4 k的最佳机械性能,其与Jaeri和Nippon Steel Corporation合作进行。

著录项

  • 来源
    《チタン》 |2002年第2期|共4页
  • 作者

    NAKAJIMA Hideo;

  • 作者单位

    Japan Atomic Energy Research Institute 801-1 Mukoyama Naka-machi Naka-gun Ibaraki 311-0193;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 jpn
  • 中图分类 金属材料;
  • 关键词

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