低温工学
Online ISSN : 1880-0408
Print ISSN : 0389-2441
ISSN-L : 0389-2441
核融合装置用大電流超電導導体の性能評価試験装置
高橋 良和押切 雅幸河野 勝己塙 博美今橋 浩一関 秀一大都 起一若林 宏高野 克敏宇野 康弘辻 博史
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1998 年 33 巻 5 号 p. 323-333

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The superconducting performance test facility for the 50-kA conductor of a fusion machine was completed at the Japan Atomic Energy Research Institute (JAERI). This facility consists of a 5-kW refrigeration system, 60-kA DC power-supply system, a liquid-helium dewar, and vacuum evacuation and data acquisition systems. The full-size conductor and joint sample for the ITER central solenoid (CS) model coils will be tested in this facility. The samples are cooled by a supercritical helium of from 5 to 16K and tested for an external field of up to 11 T and a 60kA current. According to these results, the operation limits of the model coil will be estimated and the fabrication technique of large coils verified. This facility has completed preliminary tests and its designed performance confirmed.

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