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Local and integral disruption forces on the tokamak wall

机译：托卡马克墙上的本地和整体中断力量

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The disruption-induced forces on the tokamak wall are evaluated analytically within the standard large-aspect-ratio model that implies axisymmetry, circular plasma and wall, and absence of halo currents. Additionally, the ideal-wall reaction is assumed. The disruptions are modelled as rapid changes in the plasma pressure (thermal quench (TQ)) and net current (current quench (CQ)). The force distribution over the poloidal angle is found as a function of these inputs. The derived formulas allow comparison of the TQ- and CQ-produced forces calculated differently, with and without account of the poloidal current induced in the wall. The latter variant represents the inherent property of the codes treating the wall as a set of toroidal filaments. It is proved here that such a simplification leads to unacceptably large errors in the simulated forces for both TQs and CQs. It is also shown that the TQ part of the force must prevail over that due to CQ in the high-beta scenarios developed for JT-60SA and ITER.
机译：在标准的大宽高比模型内分析地评估Tokamak壁上的破坏力，暗示轴对称，圆形等离子体和壁，并且没有晕圈电流。另外，假设理想壁反应。破坏被建模为等离子体压力（热骤冷（TQ））和净电流（电流骤冷（CQ））的快速变化。以这些输入的函数发现对面角的力分布。衍生的公式允许比较不同地计算的TQ和CQ产生的力，随着壁中诱导的单极电流而没有叙述。后一种变体代表将墙壁视为一组环形细丝的守则的固有特性。这里证明，这种简化导致TQS和CQs模拟力中的不可接受的大误差。还表明，由于为JT-60SA和ITER开发的高β场景中的CQ而必须占用的TQ部分。

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