Model of vertical plasma motion during the current quench
Tokamak disruptions impair plasma position control, which allows the plasma column to move and hit the wall. These detrimental events enhance thermal and mechanical loads due to halo currents and runaway electron losses. Their fundamental understanding and prevention is one of the high-priority items for ITER. As commonly observed in experiments (see e.g., Refs. 1 and 2), the disruptive plasma tends to move vertically, and the timescale of this motion is rather resistive than Alfvenic. These observations suggest that the plasma column is nearly force-free during its vertical motion. In fact, the force-free constraint is already implemented in disruption simulators (see Ref. 3). In this work, we consider a geometrically simple system that mimics the tokamak plasma surrounded by the conducting structures. Using this model, we highlight the underlying mechanism of the vertical displacement events during the current quench phase of plasma disruption. The same geometrical simplification was recently employed in Ref. 8 but without taking advantage of the force-free approximation. We find that the force-free ansatz makes the description more transparent by immediate elimination of the fast Alfvenic time-scale. This helps to reveal possible violation of ideal MHD stability during slow resistive motion of the plasma.