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Development program of a 60 kA high temperature superconductor current lead for the ITER toroidal field coils

R Heller, G Friesinger, A.M Fuchs, P Komarek, M Vogel2001年Fusion Engineering and DesignIF 1.7出版社

AbstractA high temperature superconducting current lead for application in fusion magnets was developed in collaboration of three laboratories. Bi-2223 Ag/Au tapes were selected to be used in the current lead and two industrial fabricated 10 kA modules were extensively tested. Both modules were used in the 20 kA current lead which was successfully tested in continous operation at 20 kA and over short time up to 40 kA.

日本語訳

高温超電導電流リードは、3つの研究所の協力により核融合磁石用に開発された。Bi-2223 Ag/Auテープが電流リードに選定され、2つの工業製造された10 kAモジュールが広範囲に試験された。両モジュールは20 kA電流リードに使用され、20 kAでの連続運転および40 kAまでの短時間運転に成功した。

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ITERHigh-temperature superconductorToroidal field coils
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