Abstract

After modification of the ASDEX Upgrade divertor, i.e., installation of the `LYRA'-divertor, extensive helium exhaust and transport studies have been performed to investigate two different aspects important for the development of a steady-state fusion device: (1) helium transport in the scrape-off layer (SOL) and divertor with a divertor geometry similar to the one foreseen for ITER, and (2) helium transport in the plasma core with internal transport barriers (ITBs). In ohmic and H-mode discharges larger compression ratios and enrichment factors as compared to divertor I have been found. With the new divertor configuration both quantities depend on the heating power and deteriorate with divertor detachment. In ITB-discharges with an H-mode edge, helium exhaust is rather slow – as expected for such low density scenarios – but not hindered by the transport barrier.

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