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首页> 外文会议>Topical Conference on Radio Frequency Power in Plasmas >Current Generation by Helicons and LH Waves in Modern Tokamaks and Reactors FNSF-AT, ITER and DEMO. Scenarios, Modeling and Antennae
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Current Generation by Helicons and LH Waves in Modern Tokamaks and Reactors FNSF-AT, ITER and DEMO. Scenarios, Modeling and Antennae

机译：目前的直升机和LH波在现代Tokamaks和Reactors FNSF-AT，ITER和演示中。场景，建模和天线

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The Innovative concept and 3D full wave code modeling Off-axis current drive by RF waves in large scale tokamaks, reactors FNSF-AT,ITER and DEMO for steady state operation with high efficiency was proposed [1] to overcome problems well known for LH method [2]. The scheme uses the helicons radiation (fast magnetosonic waves at high (20-40) IC frequency harmonics) at frequencies of 500-1000 MHz, propagating in the outer regions of the plasmas with a rotational transform. It is expected that the current generated by Helicons will help to have regimes with negative magnetic shear and internal transport barrier to ensure stability at high normalized plasma pressure β_N>3 (the so-called Advanced scenarios) of interest for FNSF and the commercial reactor. Modeling with full wave three-dimensional codes PSTELION and STELEC2 showed flexible control of the current profile in the reactor plasmas of ITER, FNSF-AT and DEMO [2,3], using multiple frequencies, the positions of the antennae and toroidal waves slow down. Also presented are the results of simulations of current generation by helicons in tokamaks DIII-D, T-15MD and JT-60SA [3]. In DEMO and Power Plant antenna is strongly simplified, being some analoge of mirrors based ECRF launcher, as will be shown. For spherical tokamaks the Helicons excitation scheme does not provide efficient Off-axis CD profile flexibility due to strong coupling of helicons with O-mode, also through the boundary conditions in low aspect machines, and intrinsic large amount of trapped electrons, as is shown by STELION modeling for the NSTX tokamak. Brief history of Helicons experimental and modeling exploration in straight plasmas, tokamaks and tokamak based fusion Reactors projects is given, including planned joint DIII-D-Kurchatov Institute experiment on helicons CD [1].
机译：提出了创新的概念和3D全波代码通过RF波在大规模的Tokamak中进行了轴电流驱动器，反应堆FNSF-AT，迭代和演示，用于高效率的稳态操作，以克服LH方法众所周知的问题[2]。该方案在500-1000 MHz的频率下使用螺旋辐射（高（20-40）IC频率谐波的快速磁性波），在等离子体的外部区域中具有旋转变换。预计由赫索斯产生的电流将有助于具有负磁性剪切和内部运输屏障的制度，以确保FNSF和商业反应堆感兴趣的高标准化等离子体压力β_N> 3（所谓的高级方案）处的稳定性。用全波三维代码建模PSTelion和Stelec2显示了使用多个频率的磨损器，FNSF-AT和演示[2,3]反应器等离子体中电流配置轮廓的灵活控制，使用多个频率，天线和环形波的位置减速。还提出是托卡马克斯DIII-D，T-15MD和JT-60SA的直升机模拟当前生成的结果[3]。在演示和发电厂天线强烈简化，是基于ECRF发射器的镜子的一些分析，如图所示。对于球形TOKAMAKS，直升机激励方案由于Helicons与O模式的强耦合，并且通过低方面机的边界条件以及固有的大量被捕获的电子，并且如图所示NSTX Tokamak的硬盘建模。提出了直升离等离子体，托卡马克和托卡马克的融合反应堆项目的实验和建模勘探的简史，包括计划联合Dii-D-Kurchatov研究所在Helicons CD [1]。

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