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Improvement of confinement and remote radiative cooling of beam heated plasmas in IT-60 with ion Del B drift towards the X-point

S. Tsuji, N. Nosogane, K. Itami, H. Kubo, T. Nishitani, M. Shimada, Y. Koide, N. Nishino, T. Sugie, K. Nagashima1992年被引用 7Nuclear FusionIF 3出版社

Improvement of both energy and particle confinement was observed in beam heated hydrogen plasmas in JT-60 when the heating power and the line averaged density exceeded thresholds. The radiation power from the divertor plasma increased to as much as 50% of the heating power. This regime was termed improved divertor confinement (IDC). The discharges with improvement of the energy confinement by up to 20% and enhanced divertor radiation lasted for several seconds in a quasi-steady state without significant impurity accumulation in the core. The threshold line averaged electron density for the IDC regime increased linearly with power and dropped with increasing safety factor. The improvement was observed only when the ion Del B drift was towards the X-point. The behaviour of light impurities and in-out asymmetries in particle recycling changed with reversal of the toroidal magnetic field. These findings are consistent with the theoretical model in which collisional transport near the separatrix is connected with the onset of the IDC regime

日本語訳

JT-60におけるビーム加熱水素プラズマにおいて、加熱パワーと線平均密度が閾値を超えると、エネルギー閉じ込めと粒子閉じ込めの両方の改善が観測された。ダイバータプラズマからの放射損失は加熱パワーの50%にまで増加した。この領域は改善閉じ込め(IDC)と名付けられた。エネルギー閉じ込めが最大20%改善し、ダイバータ放射が増強された放電は、コア部への顕著な不純物蓄積を伴わずに、準定常状態で数秒間持続した。IDC領域の閾値線平均密度はパワーとともに線形に増加し、安全係数が増加すると低下した。この改善は、イオン∇BドリフトがX点方向を向いている場合にのみ観測された。トロイダル磁場の方向を反転させると、粒子リサイクリングにおける軽不純物の挙動と内外非対称性が変化した。これらの結果は、セパラトリクス近傍の衝突輸送がIDC領域の発現と関連しているという理論モデルと一致している。

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jt-60sa中精度(概要文一致)

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Neutral beam injectionX-point
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