Plasma detachment in divertor tokamaks
Plasma detachment in divertor tokamaks
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DOI：
10.1088/1361-6587/aaa7a9
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发表时间：
2018-04-01
影响因子：
2.2
通讯作者：
Leonard, A. W.
中科院分区：
文献类型：
--
作者：
Leonard, A. W.
本文评述了托卡马克装置偏滤器等离子体分离的观测结果。等离子体分离的特点是传输和耗散的功率，动量和粒子通量沿着从中平面到偏滤器的开放场线。内侧偏滤器等离子体和外侧偏滤器等离子体之间的分离起始和其他特性的不对称性被发现主要是由右箭头X上的等离子体（E）（B）和右箭头漂移驱动的。总结了偏滤器板的几何形状和磁场位形对偏滤器分离的影响。偏滤器分离的控制已经随着许多诊断的发展而取得进展，以实时表征分离状态。最后考察了分离偏滤器运行与高性能堆芯等离子体的兼容性。
Observations of divertor plasma detachment in tokamaks are reviewed. Plasma detachment is characterized in terms of transport and dissipation of power, momentum and particle flux along the open field lines from the midplane to the divertor. Asymmetries in detachment onset and other characteristics between the inboard and outboard divertor plasmas is found to be primarily driven by plasma (E) over right arrow X (B) over right arrow drifts. The effect of divertor plate geometry and magnetic configuration on divertor detachment is summarized. Control of divertor detachment has progressed with a development of a number of diagnostics to characterize the detached state in real-time. Finally the compatibility of detached divertor operation with high performance core plasmas is examined.