Taming the plasma–material interface with the ‘snowflake’ divertor in NSTX
Taming the plasma–material interface with the ‘snowflake’ divertor in NSTX
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DOI：
10.1088/0029-5515/51/1/012001
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发表时间：
2015-04
期刊：
影响因子：
3.3
通讯作者：
V. Soukhanovskii;J. Ahn;R. Bell;D. Gates;S. Gerhardt;R. Kaita;E. Kolemen;B. LeBlanc;R. Maingi;M. Makowski;R. Maqueda;A. Mclean;J. Menard;D. Mueller;S. Paul;R. Raman;A. Roquemore;D. Ryutov;S. Sabbagh;H. Scott
中科院分区：
文献类型：
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作者：
V. Soukhanovskii;J. Ahn;R. Bell;D. Gates;S. Gerhardt;R. Kaita;E. Kolemen;B. LeBlanc;R. Maingi;M. Makowski;R. Maqueda;A. Mclean;J. Menard;D. Mueller;S. Paul;R. Raman;A. Roquemore;D. Ryutov;S. Sabbagh;H. Scott
偏滤器热通量的稳态处理是ITER和未来具有紧凑型高功率密度偏滤器的常规和球形托卡马克的关键问题。一种新型的“雪花”偏滤器（SFD）的配置，理论上预测有显着的磁几何偏滤器热通量缓解的好处，如增加等离子体润湿面积和更高的偏滤器体积可用于体积功率和动量损失过程，与标准偏滤器相比。一个显着的偏滤器峰值热通量的减少和杂质屏蔽已同时实现与核心H-模式限制在放电与SFD只使用极向场线圈的最小集合。
Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high-power density divertors. A novel ‘snowflake’ divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry benefits for divertor heat flux mitigation, such as an increased plasma-wetted area and a higher divertor volume available for volumetric power and momentum loss processes, as compared with the standard divertor. Both a significant divertor peak heat flux reduction and impurity screening have been achieved simultaneously with core H-mode confinement in discharges with the SFD using only a minimal set of poloidal field coils.