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首页> 外文期刊>チタン >Development of Superconducting Test Coil using Titanium Pipe for the International Thermonuclear Engineering Reactor (ITER)
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Development of Superconducting Test Coil using Titanium Pipe for the International Thermonuclear Engineering Reactor (ITER)

机译:国际热核工程反应堆(ITER)的钛管超导测试线圈的开发

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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:俄罗斯联邦埃夫雷莫夫研究所在国际热核实验反应堆(ITER)的工程和设计活动中开发了使用纯钛管的超导测试线圈。该线圈还通过日本原子能研究院(JAERI)的超导线圈测试设备进行了测试,并达到了ITER要求,在额定电流46 kA时最大磁场强度为13T。线圈的一个特点是使用纯钛管作为超导体的护套,以防止由于护套和超导股线之间的热收缩差异导致的热应变而导致超导性能下降。与JAERI和新日铁公司合作,在开发过程中使用了氧气含量为0.106%的纯钛管,以找到在4 K时的最佳机械性能。

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