[en] ASDEX Upgrade, presently under construction at IPP Garching, is a divertor tokamak allowing experiments with elongated plasmas of Single and Double Null shapes. For this tokamak, we have performed a series of dynamical simulations during the start up, the flat top and the shut down phase, using the Princeton Tokamak Simulation Code (TSC). In the simulations, we have included all coil groups, i.e. the ohmic heating system, the poloidal field coils external to the TF magnets, the inner control coils as well as passive structures such as passive conductors and the vacuum vessel. The feedback control of the plasma position by the inner control coils and the external poloidal field coils, both during regular shot scenarios and for disruption simulations under realistic power supply constraints, is studied. In the following we describe in somewhat more detail two applications, the simulation of a complete discharge including the start up phase and a plasma disruption. Although in both cases of the simulation, model assumptions are required for the thermal energy transport, the emphasis is here on the aspects of plasma position and shape control and the electrodynamics of the poloidal field circuits. (author) 2 refs., 3 figs