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Modeling plasma toroidal flow profile control via NTV torque with n = 2 3D fields in MAST-U
Nuclear Fusion ( IF 3.5 ) Pub Date : 2020-08-13 , DOI: 10.1088/1741-4326/aba334
Yueqiang Liu 1 , A. Kirk 2 , B.C. Lyons 1 , S. Munarretto 1 , C. Paz-Soldan 1 , L. Piron 3, 4 , A.D. Turnbull 1
Affiliation  

Toroidal modeling utilizing the MARS-Q code (Liu et al 2013 Phys. Plasmas 20 042503) shows that large (compared to electromagnetic torque) neoclassical toroidal viscous (NTV) torque can be achieved in the plasma core region in reference MAST(-U) L-mode plasmas, by applying the n = 2 ( n is the toroidal mode number) 3D fields generated by the magnetic coils used for controlling the edge localized mode and/or by the error field correction coils. Large NTV torque, occurring at relatively slow plasma flow, in combination with strong variation of the torque amplitude versus the coil phasing of the 3D coils, offers a tool to control the plasma toroidal rotation profile in spherical tokamaks. To effectively employ the toroidal NTV torque, the potentially fast initial flow needs to first be damped by 3D fields. MARS-Q quasi-linear initial value simulations demonstrate that this is achievable in MAST-U, within the designed 3D coil current capability for ...

中文翻译:

在MAST-U中通过n = 2个3D场通过NTV转矩对等离子体环形流动轮廓控制进行建模

利用MARS-Q代码进行环形建模(Liu等人2013 Phys.Plasmas 20 042503)显示,在参考MAST(-U)的等离子体核心区域中可以实现大(与电磁转矩相比)新古典环形粘性(NTV)转矩通过施加n = 2(n是环形模数)的L模式等离子体,该3D磁场由用于控制边缘定位模式的电磁线圈和/或由误差场校正线圈产生。在相对缓慢的等离子流下发生的大NTV转矩,加上转矩幅度相对于3D线圈的线圈相位的强烈变化,提供了一种控制球形托卡马克中的等离子环形旋转轮廓的工具。为了有效地利用环形NTV扭矩,可能首先需要通过3D场来衰减潜在的快速初始流量。
更新日期:2020-08-14
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