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Superconductors for the NET coils

N. Mitchell, L. Bottura1991年Fusion Engineering and DesignIF 1.7出版社

AbstractNext generation fusion reactors such as the Next European Tokamak (NET) and the International Thermonuclear Experimental Reactor (ITER) have design targets for the conductor performance in their superconducting coils. These coils require high fields and must tolerate both AC and DC conditions. There are a range of superconductor configurations (monolithic, cable in conduit) and materials (Nb3Sn, NbTi) that are candidates for the conductors. This report quantifies the performance of these candidates in the expected environment of the NET/ITER coils, and shows that Nb3Sn cable in conduit type conductors can be expected to satisfy the present design targets of NET/ITER.

日本語訳

次世代核融合炉、例えば次欧州トカマク(NET)や国際熱核融合実験炉(ITER)は、その超伝導コイルにおける導体性能に関して設計目標を有している。これらのコイルは高磁場を必要とし、交流および直流の両条件下に耐えなければならない。導体の候補となる構成(モノリシック型、ケーブル・イン・コンジット型)および材料(Nb₃Sn、NbTi)には様々なものがある。本報告書は、NET/ITERコイルの想定環境下におけるこれらの候補の性能を定量化し、Nb₃Snケーブル・イン・コンジット型導体が現在のNET/ITER設計目標を満たすことが期待できることを示すものである。

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iter低精度(概要文一致)

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Next European Torus
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