分流器中性压力对 ASDEX 升级版先进托卡马克方案约束退化的影响

D. Silvagni, M. Dunne, T. Luda, A. Bock, A. Burckhart, R. Fischer, M. Griener, R. M. McDermott, U. Plank, T. Pütterich, M. Reisner, J. Stober, B. Tal, G. Tardini, H. Zohm
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摘要

在以往的活动中,ASDEX 升级版全钨壁托卡马克已经开展了一项针对先进托卡马克(AT)方案的密集实验计划。这些放电是在第一壁硼化后不久进行的,目的是降低密度和杂质流入。研究发现,即使在工程参数相似(甚至不完全相同)的情况下进行放电,这种 AT 放电的约束水平也会有很大差异。这项工作研究了造成这种约束变化的原因。在分析的所有等离子体量中,AT 方案的束缚质量与分流器中性压力的相关性最好,突出了边缘和刮除层物理在决定全局等离子体束缚中的关键作用。特别是,研究发现,约束性下降的主要原因是基座稳定性的降低,而基座稳定性的降低又是由最大密度梯度位置的外移造成的,而最大密度梯度位置的外移通常是在分流器中性压力增加时观察到的。由于所分析的 AT 放电密度较低,最大密度梯度位置的移动可能完全是由壁面氘排出量的变化引起的,而氘排出量受沉积在面向等离子体部件上的硼层和壁面氘存量的影响很大。最后,利用综合模型 IMEP [Luda 等人,Nucl. Fusion 60, 036023 (2020)]对约束质量的预测能力在这些放电中进行了测试,结果很有希望。
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Impact of divertor neutral pressure on confinement degradation of advanced tokamak scenarios at ASDEX Upgrade
Over previous campaigns, an intense experimental program on advanced tokamak (AT) scenarios, has been carried out at the ASDEX Upgrade tokamak with full-tungsten wall. These discharges have been executed shortly after the boronization of the first wall to reduce the density and the impurity influx. The confinement level of such AT discharges was found to vary considerably, even when discharges with similar, if not identical, engineering parameters were carried out. This work investigates the causes of such confinement variations. Among all plasma quantities analyzed, confinement quality of AT scenarios correlates best with divertor neutral pressure, highlighting the key role of edge and scrape-off layer physics in determining global plasma confinement. In particular, it is found that the main cause of confinement degradation is the reduction of pedestal stability, which is in turn caused by the outward shift of the maximum density gradient position typically observed when the divertor neutral pressure increases. Owing to the low density of AT discharges under analysis, the movement of the maximum density gradient position can be caused entirely by changes in deuterium outgassing from the wall, which is strongly influenced by the boron layer deposited on the plasma-facing components and by the deuterium wall inventory. Finally, the predictive capability of confinement quality with the integrated model IMEP [Luda et al., Nucl. Fusion 60, 036023 (2020)] is tested on these discharges and shows promising results.
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