Contamination of ITER core by impurities of tungsten and carbon

Abstract The ITER operation including ELMy H-mode is simulated with the code TOKES that considers processes among D-, T-, He-, C- and W-species and aims at fully integrated modelling in respect to the confined plasma and vessel wall. New features implemented for the scrape-off layer (SOL) and the MHD thermal transport in the confinement region are described. TOKES is now able to carry out self-consisted simulations with edge localized modes (ELMs) and with a tungsten wall. The impact of SOL plasma on the vessel surface is calculated based on random tests for gyrating particles with the trajectories calculated in the guiding centre approximation. A simple SOL model for the atoms, emitted due to sputtering and then ionized, is applied to account for the recycling and impurity densities at the separatrix. Benchmark results demonstrate the abilities of the code being under development. Plasma contamination in its dependence on the materials (C or W) for outer and inner divertor legs is examined. The operation deterioration caused by vaporization at tungsten divertor surfaces after ELMs is addressed.