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P: Fachverband Plasmaphysik
P 16: Poster Session Plasma Physics
P 16.20: Poster
Thursday, March 19, 2026, 13:45–15:45, Redoutensaal
Helium exhaust studies in ASDEX Upgrade — •Simon Krumm1, Athina Kappatou1, Antonello Zito1, Volker Rohde1, Gerd Schall1, Marco Wischmeier1, Rachael M. Mcdermott1, and the ASDEX Upgrade Team2 — 1Max-Planck-Institut für Plasmaphysik, 85748 Garching, Germany — 2see the author list of H. Zohm et al. 2024 NF 64 112001
Helium is one of the product of the fusion reaction used in future fusion power plants. Thermalised helium dilutes the fuel and has to be efficiently removed to sustain the fusion process. Recent work at ASDEX Upgrade (AUG) investigated the helium removal in Type-I ELMy H-modes both experimentally and numerically [A. Zito et al. 2023 Nucl.Fusion 63 096027 & 2025 Nucl.Fusion 65 046022]. Helium removal is hindered by its high wall retention in tungsten, as well as the inefficiency of active pumping in AUG. Most importantly, because of helium's high ionisation energy, its divertor retention is low compared to other impurities, leading to inefficient transport from the divertor to the pumping surfaces. The next step is to investigate reactor relevant scenarios - especially those compatible with power exhaust - to also assess their compatibility with helium exhaust. For this, neutral partial pressure measurements in the divertor are needed. We employ optical in-situ and ex-situ Penning gauges, as well as Threshold Ionization Mass Spectrometry in the pumping ducts. Additionally, utilising these diagnostics, the new activated charcoal cryopump [G. Schall et al. 2021 Fusion Eng. Des. 166 112316] recently installed on AUG can be characterised for its helium pumping capability.
Keywords: magnetic confinement; plasma diagnostic; Helium transport