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Articles: plasma detachment in jet mark I divertor experiments

机译:文章:喷射标记I偏滤器实验中的等离子体分离

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The experimental characteristics of divertor detachment in the JET tokamak with the Mark I pumped divertor are presented for ohmic, L mode and ELMy H mode experiments with the main emphasis on discharges with deuterium fuelling only. The range over which diver- tor detachment is observed for the various regimes, as well as the influence of divertor configuration, direction of the toroidal field, divertor target material and active pumping on detachment, will be described. The observed detachment characteristics, such as the existence of a considerable elec- tron pressure drop along the field lines in the scrape-off layer(SOL), and the compatibility of the decrease in plasma flux to the divertor plate with the observed increase of neutral pressure and D_αemission from the divertor region, will be examined in the light of existing results from ana- Lytical and numerical models for plasma detachment.
机译:提出了带有Mark I抽水式偏滤器的JET托卡马克中偏滤器脱离的实验特性,用于欧姆,L模式和ELMy H模式实验,主要侧重于仅使用氘燃料进行放电。将描述在各种情况下观察到的分流器分离的范围,以及分流器配置,环形场的方向,分流器目标材料和主动泵送对分离的影响。观察到的分离特性,例如沿刮除层(SOL)沿磁力线存在相当大的电子压降,以及等离子体通量向分流板的减少与所观察到的中性增加的相容性来自偏滤器区域的压力和D_α排放将根据血浆分离的解析模型和数值模型的现有结果进行检查。

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