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Impact of ideal MHD stability limits on high-beta hybrid operation

机译：理想MHD稳定性限制对高β混合动力运算的影响

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摘要

The hybrid scenario is a candidate for stationary high-fusion gain tokamak operation in ITER and DEMO. To obtain such performance, the energy confinement and the normalized pressure beta(N) must be maximized, which requires operating near or above ideal MHD no-wall limits. New experimental findings show how these limits can affect hybrid operation. Even if hybrids are mainly limited by tearing modes, proximity to the no-wall limit leads to 3D field amplification that affects plasma profiles, e.g. rotation braking is observed in ASDEX Upgrade throughout the plasma and peaks in the core. As a result, even the small ASDEX Upgrade error fields are amplified and their effects become visible. To quantify such effects, ASDEX Upgrade measured the response to 3D fields applied by 8x2 non-axisymmetric coils as beta(N) approaches the no-wall limit. The full n = 1 response profile and poloidal structure were measured by a suite of diagnostics and compared with linear MHD simulations, revealing a characteristic feature of hybrids: the n = 1 response is due to a global, marginally-stable n = 1 kink characterized by a large m = 1, n = 1 core harmonic due to q(min) being just above 1. A helical core distortion of a few cm forms and affects various core quantities, including plasma rotation, electron and ion temperature, and intrinsic W density. In similar experiments, DIII-D also measured the effect of this helical core on the internal current profile, providing information useful to understanding of the physics of magnetic flux pumping, i.e. anomalous current redistribution by MHD modes that keeps q(min) > 1. Thanks to flux pumping, a broad current profile is maintained in DIII-D even with large on-axis current drive, enabling fully non-inductive operation at high beta(N) up to 3.5-4.
机译：混合方案是inter和演示中的静止高融合增益Tokamak操作的候选者。为了获得这种性能，必须最大化能量限制和归一化压力β（n），这需要在理想的MHD无墙限制附近或高于理想的无墙限制。新的实验结果显示这些限制如何影响混合动力操作。即使杂交种主要受撕裂模式的限制，接近无壁限制也会导致3D场放大，从而影响等离子体型材，例如，影响等离子体型材。在整个等离子体升级中观察到旋转制动，并在核心中的峰值升级。结果，即使是放大了小的ASDEX升级错误字段，它们的效果也变得可见。为了量化此类效果，ASDEX升级测量了对8x2非轴对称线圈施加的3D字段的响应，因为Beta（n）接近无墙限制。通过套件诊断测量全n = 1响应曲线和针状体结构，并与线性MHD模拟进行比较，揭示杂交种的特征：n = 1响应是由于全局，边缘稳定的n = 1扭结所表征大M = 1，n = 1核谐波由于Q（min）在于高于1.呈少厘米的螺旋核心变形，形成各种核心量，包括等离子体旋转，电子和离子温度，以及内在的W.密度。在类似的实验中，DIII-D还测量了该螺旋芯对内部电流配置轮廓的影响，提供了对理解磁通量泵送物理学的信息，即通过保持Q（min）> 1的MHD模式的异常电流再分配。由于焊剂泵送，即使具有大的轴电流驱动，宽电流曲线也保持在DIII-D中，使高β（n）高达3.5-4的完全非感应操作。

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