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Superconducting test facility of NIFS for the Large Helical Device

J. Yamamoto, T. Mito, K. Takahata, S. Yamada, O. Motojima1993年Fusion Engineering and DesignIF 1.7出版社

AbstractFor development of superconducting conductors and coils, the National Institute for Fusion Science prepared a new superconducting test facility which is a combination of an electro-mechanical testing device and a large cryogenic cooling system at the new Cryogenics and Superconductivity Building at the Toki site. The cryogenic cooling system has a capacity of 250 liters of liquid helium per hour or 500 W at 4.5 K, and can also supply supercritical helium up to 50 g/s. A dc power supply generates 75 kA current at 21 V. A split-type superconducting coil generates a magnetic field of 9 T of 100 mm in width. The mechanical testing machine has a capacity of 10 MN at liquid-helium temperature. The following R & D experiments for the Large Helical Device have been done using the facility: critical current and stability measurement of helical coil conductors of which the nominal current is 21 kA at 7 T, an elasticity measurement of a helical coil, and stability measurement of a cable-in-conduit conductor.

日本語訳

Abstract超伝導導体および超伝導コイルの開発を目的として,核融合科学研究所は,新しい超伝導試験施設を建設した。本施設は,新設された極低温・超伝導研究棟に設置された,電気機械試験装置と大型極低温冷却システムを組み合わせたものである。極低温冷却システムは,液体ヘリウム250リットル毎時または4.5Kにおいて500Wの冷却能力を有し,さらに超臨界ヘリウムを毎秒50グラムまで供給することができる。直流電源は,21Vにおいて75kAの電流を発生する。分割型超伝導コイルは,100mm幅の領域において9Tの磁界を発生する。電気機械試験装置は,液体ヘリウム温度において10MNの能力を有する。本施設を用いて,大型ヘリカル装置のための以下の研究開発実験が実施された:公称電流21kA,磁界7Tにおけるヘリカルコイル導体の臨界電流および安定性測定,ヘリカルコイルの弾性測定,およびケーブル・イン・コンジット導体の安定性測定。

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