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P: Fachverband Plasmaphysik
P 17: Plasma Wall Interaction II
P 17.5: Vortrag
Donnerstag, 19. März 2026, 18:00–18:15, KH 02.016
Developing Tritium Diffusion Barrier Materials for Plasma-Facing Components in Fusion Reactors — •Markus Hermanski1,3, Liang Gao1, Arkadi Kreter1, Jan Willem Coenen1, Rongxing Yi1, Sebastijan Brezinsek1,2, and Christian Linsmeier1,2 — 1Forschungszentrum Jülich GmbH, Institute of Fusion Energy and Nuclear Waste Management — Plasmaphysics (IFN-1), Jülich 52425, Germany — 2Ruhr-Universität Bochum, Faculty of Physics and Astronomy, Bochum 44801, Germany — 3RWTH Aachen University, Faculty of Georesources and Materials Engineering, Aachen 52072, Germany
Fuel permeation and retention in wall materials of fusion reactors, especially Tritium (T), are important aspects to be prevented to achieve commercial viability of fusion power in the future. For this reason, T diffusion barrier materials have been developed, however, focusing on applications at the coolant side. Preventing T permeation into the coolant, they cannot address the degradation of wall materials induced by H isotopes from plasma. Here, a diffusion barrier made of tungsten carbides (WxC) is proposed and will be developed for applications at plasma-facing surfaces.
WxC coatings will be fabricated via field assisted sintering technique (FAST) on W and G91 steel substrates, followed by deuterium (D) plasma exposure, where laser induced breakdown spectroscopy (LIBS), nuclear reaction analysis (NRA) and thermal desorption spectroscopy (TDS) measurements will be employed to measure the D depth profile after plasma exposure.
Keywords: WxC coatings; Diffusion Barrier; Deuterium exposition