Long pulse advanced tokamak discharges in the DIII-D tokamak

摘要

One of the main goals for the DIII-D research programme is to establish an advanced tokamak (AT) plasma with high bootstrap current fraction that can be sustained in-principle steady-state. Substantial progress has been made in several areas during the last year. The resistive wall model (RWM) stabilization has been done with spinning plasmas in which the plasma pressure has been extended well above the no-wall beta limit. The 3/2 neoclassical tearing mode (NTM) has been stabilized by electron cyclotron heating (ECH) of the magnetic islands, which drives current to substitute the missing bootstrap current. In these experiments either the plasma was moved or the toroidal field was changed to overlap the ECH resonance with the location of the NTMs. Effective disruption mitigation has been obtained yb massive noble gas injection into shots where disruptions were deliberately triggered. The massive gas puff causes a fast and clean current quench with essentially all the plasma energy radiated fairly uniformly to the vessel walls. The run-away electrons that are normally seen accompanying disruptions are suppressed by the large density of electrons still bound on the impurity nuclei. Major elements required to establish integrated, long pulse, AT operations have been achieved in DIII-D: β_T = 4.2%, β_P = 2, f_(BS) = 65%, and β_NH_(89P) = 10 for 600 ms (～4τE). The next challenge is to integrate the different elements, which will be the goal for the next five years when additional control will be available. Twelve RWM coils are scheduled to be installed in DIII-D during the summer of 2003. Future plans include upgrading the tokamak pulse length capability and increasing the ECH power, to control the current profile evolution.