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Control of Edge Transport Barrier relaxations using Resonant Magnetic Perturbations

机译:使用谐振磁性扰动控制边缘传输屏障弛豫

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In divertor tokamak plasmas, an Edge Transport Barrier forms during the L-H transition. A poloidal shear flow has been shown to play a crucial role in the barrier sustainement. The H regime, obtained for a critical value of the heating power, is promising for the next generation of tokamak experiments such as ITER. However, an instability known as Edge Localized Mode (ELM) develops as the power is increased further. ELMs are characterized by intermittent bursts in the radial heat flux, therefore causing the transport barrier to relax quasi-periodically. Over the last decade, the possibility of controlling ELMs has become more and more plausible, as recent experiments were carried out on DIII-D using I-coils, on JET using error field correction coils, and on TEXTOR using an ergodic divertor. These experimental studies demonstrate a qualitative control over the ELMs by imposing a magnetostatic perturbation at the plasma edge. However, in order to get any quantitative result, much work has to be done in the understanding of ELM dynamics. In this work, we present results from numerical simulations of Resistive Ballooning Mode (RBM) turbulence reproducing the stabilization of barrier relaxations by a static magnetic perturbation. We focus our study on the edge region around the resonant surface q = 3. We use the TEXTOR tokamak geometry, and plasma parameters close to those used in typical experiments on this machine.
机译:在Vertiver Tokamak等离子体中,L-H过渡期间的边缘传输屏障形式。已经显示了面色剪切流动在屏障可持续发展中发挥着至关重要的作用。为加热功率的临界值获得的H制度是对下一代Tokamak实验(例如ITER)有希望。然而,已知为边缘定位模式(ELM)的不稳定性进一步增加,因为进一步增加。 ELMS的特征在于径向热通量中的间歇突发,因此导致传输屏障周期性地松弛。在过去的十年中,控制ELMS的可能性越来越合理,因为最近的实验在DIII-D上使用I-圈子进行了使用误差场校正线圈,以及使用ergodic Devertor的刷子上的仪器进行。这些实验研究通过在等离子体边缘施加静静压扰动来证明对榆树的定性控制。然而,为了获得任何定量结果,必须在理解榆树动态方面做出很多工作。在这项工作中,我们通过静态磁性扰动来呈现电阻膨胀模式(RBM)湍流的数值模拟的结果,再现静态磁性扰动的屏障弛豫的稳定。我们将研究集中在谐振表面周围的边缘区域Q = 3.我们使用Textor Tokamak几何形状,以及接近本机典型实验中使用的等离子参数。

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