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Impurity reduction and remote radiative cooling with single-null poloidal divertor in Doublet-III

M. Shimada, M. Nagami, K. Ioki, S. Izumi, M. Maeno, H. Yokomizo, K. Shinya, H. Yoshida, N.H. Brooks, C.L. Hsieh1982年被引用 72Nuclear FusionIF 3出版社

The successful operation of a single-null poloidal divertor in Doublet-III has demonstrated several new advantages of a diverted tokamak in addition to the suppression of impurity influx as demonstrated in DIVA: 1) The impurity contamination and radiation loss of the main plasma has been reduced by an open divertor geometry, i.e. without a divertor chamber; 2) The radiative cooling and formation of a dense and cold (ne≥5 × l013 cm−3, Te≤7 eV, torr) divertor plasma have been observed. – Up to 50% of the Ohmic input power is radiated in the divertor region, thus cooling the plasma in front of the divertor plate down to several eV. This remote radiative cooling greatly reduces the heat load on the divertor plate without cooling the main plasma. – The feasibility of remote radiative cooling in INTOR was studied by use of a volume integration technique of the radiation power along the field line.

日本語訳

単一零次ポロイダルダイバータのダブルトIIIにおける成功した運転は、DIVAで実証された不純物流入の抑制に加えて、ダイバータ付きトカマクのいくつかの新しい利点を実証した:1) ダイバータチャンバーを有さない開放型ダイバータ形状により、主プラズマの不純物汚染および放射損失が低減された;2) 高密度かつ低温の(ne≥5×l013 cm−3、Te≤7 eV、トル)ダイバータプラズマの形成および放射冷却が観察された。– オーミック入力電力の最大50%がダイバータ領域で放射され、これによりダイバータ板前方のプラズマが数eVまで冷却された。この遠隔放射冷却は、主プラズマを冷却することなく、ダイバータ板への熱負荷を大幅に低減する。– INTORにおける遠隔放射冷却の実現可能性は、磁力線に沿った放射パワーの体積積分手法を用いて検討された。

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