SMuK 2023 – scientific programme
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P: Fachverband Plasmaphysik
P 11: Poster I
P 11.42: Poster
Wednesday, March 22, 2023, 14:00–15:30, HSZ EG
Engineering tool for the robust optimization of a full-W divertor in W7-X — •Antara Menzel-Barbara1,2, Joris Fellinger1, Rudolf Neu2,3, Dirk Naujoks1, and Thomas Pedersen1 — 1Max Planck Institute for Plasma Physics, 17491 Greifswald, Germany — 2Technische Universität München, 85748 Garching, Germany — 3Max Planck Institute for Plasma Physics, 85748 Garching, Germany
High levels of fuel retention due to co-deposition make C-based materials such as CFC, currently used on the W7-X divertor, incompatible for a fusion reactor. As part of an ongoing investigation into a W-based divertor for W7-X, an engineering tool for the robust optimization of leading edges is being developed. Leading edges, resulting from assembly tolerances and deformation during operation, lead to very high incidence angles and to strongly increased heat fluxes. Compared to a C-based divertor, leading edges in a W design are more problematic because of W melting. Since manufacturing and assembly tolerances are major cost drivers, relaxing them is another priority for a new divertor. Because particles in W7-X can come from opposite directions on the target surface in different magnetic configurations, the usual strategy of entirely shadowing divertor plates to avoid leading edges is not possible. Instead, a more refined approach that optimizes the divertor surface while considering all major magnetic configurations simultaneously is necessary. A variety of tools, including the code EMC3-Lite and Ansys, is used to rapidly evaluate a modified surface, and identify the problematic areas. Strategies to effectively explore the design space of geometric modifications are currently being investigated.