Abstract
A simulation of J-TEXT ohmic disruptive discharge has been achieved by using of the Tokamak Simulation Code (TSC) model. TSC is a numerical model of an axisymmetric free-boundary tokamak plasma and the associated control systems. The anomalous transport coefficient of disruption was adjusted according to heat transport across large magnetic island to mimic a sudden disruption. The simulation result of plasma current, electron temperature, loop voltage, and the disruption is compared with J-TEXT experimental disruptive discharge data. According to the simulation result, the dynamic response of one test plasma-facing module was calculated; the numerical results show that the maximum stress of the test module is in safety range.
Published Version
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