Consequences of resistive disruptions on vacuum vessel components

A computer code, DSTAR, has recently been developed to quantitify the surface erosion and induced forces that can occur during major tokamak plasma disruptions. A disruption analysis has been performed with DSTAR for the Tokamak Fusion Core Experiment (TFCX) 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 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 erosion prediction.