Disruption and their consequences have long been an active area in tokamak research and the active control of disruption avoidance is very important for large tokamak devices like ITER. Well known reasons of disruption are the operation limits associated with the plasma density, pressure and plasma current. For high current operation, there is a hard limit imposed by ideal kink modes which are unstable for qedge<2 . In the experiment, the disruption behavior associated with kink or tearing mode instabilities could be observed in the low-q plasma. While the additional rotational transform given by external coils could have an impact on the magnetohydrodynamics (MHD) equilibrium and instabilities for the advanced tokamak operation, which could be helpful to the disruption avoidance [1]. In this work, based on the J-TEXT configuration a new three dimensional (3D) helical-like coil is designed for the addition of rotational transform. The equilibrium and the share of rotational transform with 3D external coil superposed are solved by the nonlinear resistive 3D HINT code [2]. In addition, the properties of MHD instabilities with turning of the rotational transform are analyzed by 3D nonlinear MHD Infrastructure for Plasma Simulation (MIPS) code [3] to investigate what extent strong additional rotational transform with ιcoil/ι0~5% (ι=2π/q) can be used for the MHD instabilities suppression at low-q or high current operation, which could be helpful to active control of the disruption avoidance. These results can make contributions to J-TEXT upgrade aiming at advanced tokamak operation in the future.
[1] Pandya M. D. et al 2015 Phys. Plasmas, 22 110702
[2] Yasuhiro Suzuki 2017 Plasma Phys. Control. Fusion 59 054008
[3] Todo Y. et al. 2010 Plasma Fusion Res., 5 S2062