Erlangen 2026 – scientific programme
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P: Fachverband Plasmaphysik
P 16: Poster Session Plasma Physics
P 16.34: Poster
Thursday, March 19, 2026, 13:45–15:45, Redoutensaal
EMC3-EIRENE predictions of radiative detachment scenarios in W7-X equipped with a tungsten based divertor — •Daniil Ryndyk1, Derek Harting1, Shuai Xu1, Yuhe Feng4, Florian Effenberg3, Heinke Frerichs2, Sebastijan Brezinsek1, and W7-X team4 — 1FZJ GmbH, IFN-1, Jülich, Germany — 2University of Wisconsin-Madison, Madison, WI, USA — 3PPPL, Princeton, NJ, USA — 4MPG IPP, Greifswald, Germany
The nuclear fusion experiment Wendelstein 7-X (W7-X) currently operates with carbon-fiber composite (CFC) plasma-facing components (PFC) forming the island divertor used for particle and power exhaust. In a future fusion reactor, carbon-based PFCs are not tolerable due to unacceptably high fuel retention. An alternative PFC material for a fusion reactor is tungsten (W), which shows in general low sputtering, low fuel retention, and good thermomechanical properties.
As a first systematic approach to study the impact of potential W PFCs in W7-X, we use EMC3-EIRENE as plasma boundary simulation code for 3D magnetic configurations. We investigate detachment scenarios with the standard magnetic configuration of W7-X equipped with a W divertor based on the current divertor geometry and analyze the dependence of detachment relevant parameters (e.g. target heat loads) on operation conditions (e.g. plasma density). In a comparison with the detachment behavior of the current C divertor, we discuss the accessibility of similar, impurity radiation determined detachment and the relevance of volume recombination processes.
Keywords: EMC3-EIRERE; W7-X; Detachment; Tungsten