DSTAR: A COMPREHENSIVE TOKAMAK RESISTIVE DISRUPTION MODEL FOR VACUUM VESSEL COMPONENTS.

A computer code, DSTAR, has recently been developed to quantify the surface erosion and induced forces than can occur during major tokamak plasma disruptions. A disruption analysis has been performed for the TFCX fusion device. The limiters and inboard first wall were assumed to be clad with beryllium. Disruption simulations were performed with and without these structures present, to determine their electromagnetic influence. The results with structure show that the ablated wall material is transported poloidally, as well as radially, in the plasma causing the outermost regions of the plasma to cool. The plasma moves downward and deforms while maintaining contact with the lower limits. The conclusion is drawn that disruption simulations that do not include both the thermal and electromagnetic response of the vacuum vessel will not result in an accurate prediction.