Erosion of PFC in DEMO due to ELM impact

The transient events could pose a severe tread causing a melting and erosion of plasma facing components in the fusion power plant DEMO. Here we analyze the impact of the edge localized modes (ELMs) on the divertor target and the first wall surface. The expected ELMs characteristics in DEMO are derived by extrapolating predictions made for ITER and by using the scaling arguments found from existing experiments. The tungsten armor damage and effect of melt layer motion due to the repetitive ELM loads is numerically investigated by using the MEMOS code (Bazylev, 2002). It is shown that due to the ELMs repetitive impact the divertor plate melts and the total tungsten surface roughness on the divertor plate considerably grows. The ELMs heat impact on the DEMO first wall does not cause melting of the W armor. It is proven that for controlled (like in ITER) ELMs a pure W divertor module with water coolant tolerates energy loads even in the case of advanced version of DEMO.