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首页> 外文期刊>Plasma physics and controlled fusion >Plasma response to lithium-coated plasma-facing components in the National Spherical Torus Experiment
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Plasma response to lithium-coated plasma-facing components in the National Spherical Torus Experiment

机译：在国家球形圆环实验中，等离子体对锂涂层等离子体组件的等离子体响应

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Experiments in the National Spherical Torus Experiment (NSTX) have shown beneficial effects on the performance of divertor plasmas as a result of applying lithium coatings on the graphite and carbon-fiber-composite plasma-facing components. These coatings have mostly been applied by a pair of lithium evaporators mounted at the top of the vacuum vessel which inject collimated streams of lithium vapor toward the lower divertor. In neutral beam injection (NBI)-heated deuterium H-mode plasmas run immediately after the application of lithium, performance modifications included decreases in the plasma density, particularly in the edge, and inductive flux consumption, and increases in the electron and ion temperatures and the energy confinement time. Reductions in the number and amplitude of edge-localized modes (ELMs) were observed, including complete ELM suppression for periods of up to 1.2 s, apparently as a result of altering the stability of the edge. However, in the plasmas where ELMs were suppressed, there was a significant secular increase in the effective ion charge Zeff and the radiated power as a result of increases in the carbon and medium-Z metallic impurities, although not of lithium itself which remained at a very low level in the plasma core, <0.1%. The impurity buildup could be inhibited by repetitively triggering ELMs with the application of brief pulses of an n = 3 radial field perturbation. The reduction in the edge density by lithium also inhibited parasitic losses through the scrape-off-layer of ICRF power coupled to the plasma, enabling the waves to heat electrons in the core of H-mode plasmas produced by NBI. Lithium has also been introduced by injecting a stream of chemically stabilized, fine lithium powder directly into the scrape-off-layer of NBI-heated plasmas. The lithium was ionized in the SOL and appeared to flow along the magnetic field to the divertor plates. This method of coating produced similar effects to the evaporated lithium but at lower amounts.
机译：美国国家球形圆环实验（NSTX）中的实验表明，由于在石墨和碳纤维复合等离子表面组件上涂了锂涂层，对偏滤器等离子的性能产生了有益的影响。这些涂层大部分是通过安装在真空容器顶部的一对锂蒸发器来施加的，这些蒸发器将准直的锂蒸汽流注入下分流器。在中子束注入（NBI）加热的氘H型等离子体在施加锂之后立即运行，其性能改进包括降低等离子体密度（特别是边缘）和感应通量，并降低电子和离子温度，以及能量约束时间。观察到边缘局部模式（ELM）的数量和幅度减小，包括完全ELM抑制长达1.2 s的时间，显然是由于改变了边缘的稳定性。但是，在抑制了ELM的等离子体中，由于碳和中Z金属杂质的增加，有效离子电荷Zeff和辐射功率的长期增长显着，尽管锂本身并没有保持在血浆核心中非常低的水平，<0.1％。通过使用n = 3径向场扰动的短脉冲重复触发ELM，可以抑制杂质的积累。锂引起的边缘密度降低还抑制了通过与等离子体耦合的ICRF功率刮除层产生的寄生损耗，从而使波能够加热NBI产生的H型等离子体核心中的电子。还可以通过将化学稳定的细锂粉流直接注入NBI加热的等离子的刮除层中来引入锂。锂在SOL中被离子化，并似乎沿着磁场流向分流板。这种涂覆方法产生与蒸发的锂相似的效果，但用量较少。

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