The rate of plasma current-quench during tokamak plasma disruptions determines the electromagnetic forces on the in-vessel components/vacuum vessel. Also halo currents and rapid changes of poloidal field due to the plasma vertical displacement contribute to loads on vessel and in-vessel components and hence needs to be studied thoroughly to safeguard these tokamak peripherals. The plasma current quench occurrence during the spontaneous major disruption has been investigated for a set of ADITYA tokamak disrupted discharges and average plasma current quench and instantaneous current quench rates have been estimated. The fastest area-normalized plasma current ( I P ) quench time is observed to be ∼5 ms m −2 . The estimated post disruption plasma electron temperatures (PDET) are observed to be ∼15–35 eV and proportional to area-normalized plasma current quench time. Further analysis of several disruptive discharges of ADITYA tokamak reveal that the current q...

中文翻译：

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ADITYA托卡马克破裂期间等离子体电流猝灭的表征

托卡马克等离子体破坏过程中的等离子体电流猝灭速率决定了血管内组件/真空容器上的电磁力。同样，由于等离子体的垂直位移，光晕电流和极向电场的快速变化也会增加血管和血管内组件的负荷，因此需要对它们进行彻底研究以保护这些托卡马克外围设备。对于一组ADITYA托卡马克中断的放电，已经研究了自发性重大破坏期间的等离子体电流猝灭发生，并估计了平均等离子体电流猝灭和瞬时电流猝灭速率。最快的区域归一化等离子体电流（IP）淬灭时间约为5 ms m -2。估计的破坏后等离子体电子温度（PDET）约为15–35 eV，与面积归一化的等离子体电流猝灭时间成比例。进一步分析ADITYA托卡马克的几种破坏性排放，可以发现当前的...