Chen J, Brower D L, Benedett T
University of California Los Angeles, Los Angeles, California 90095, USA.
Rev Sci Instrum. 2022 Aug 1;93(8):083515. doi: 10.1063/5.0101550.
Toroidal current profile measurements in the tokamak plasma edge are critical for fusion plasma physics research and model validation. A three-wave Faraday-effect polarimeter-interferometer with a sub-centimeter spatial resolution is proposed on the DIII-D tokamak to determine the edge current profile via Abel inversion. By using probe beams with 316 µm wavelength, a low-field-side, vertical-view, single-pass optical layout covering the plasma edge region (R = 2.15-2.27 m) is assessed. Measurements with no greater than 0.1° polarimetric systematic uncertainty, no greater than 0.01° polarimetric root-mean-square noise (1 kHz bandwidth), and a 0.8 cm radial chord spacing are considered feasible based on the achieved performance of existing systems using similar wavelengths on fusion devices. Synthetic diagnostic calculations taking various factors into account, such as diagnostic uncertainty and quality of magnetic flux surfaces, find that the edge current profile can be determined with up to 0.12 MA/m uncertainty, or about 10% of the peak current density in the pedestal of an investigated high-confinement plasma.
托卡马克等离子体边缘的环形电流分布测量对于聚变等离子体物理研究和模型验证至关重要。在DIII-D托卡马克上提出了一种具有亚厘米空间分辨率的三波法拉第效应偏振计-干涉仪,以通过阿贝尔反演确定边缘电流分布。通过使用波长为316 µm的探测光束,评估了一种覆盖等离子体边缘区域(R = 2.15-2.27 m)的低场侧、垂直视图、单程光学布局。基于在聚变装置上使用类似波长的现有系统所达到的性能,测量具有不大于0.1°的偏振系统不确定性、不大于0.01°的偏振均方根噪声(1 kHz带宽)以及0.8 cm的径向弦间距被认为是可行的。考虑到各种因素(如诊断不确定性和磁通量表面质量)的综合诊断计算表明,边缘电流分布可以在不确定性高达0.12 MA/m的情况下确定,约为所研究的高约束等离子体基座中峰值电流密度的10%。