Abstract
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 (FW) surface. The expected ELMs characteristics in DEMO are derived by extrapolating predictions made for ITER and using the scaling arguments found from existing experiments. The tungsten armor damage and effect of melt layer motion owing to the repetitive ELM loads are numerically investigated. The detailed description of the model for simulation of the melt motion (used in the melt motion at surfaces code) is described. It is shown that due to the unmitigated repetitive ELM impact, the divertor plate melts whereas FW does not. The divertor surface of monoblock W divertor module with water coolant tolerates the mitigated ELMs with 33 times (like in ITER) does not melt even in the case of advanced version of DEMO loads.
Sign-in/Register to access full text options 
Free) 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a call
