Plasma Exposure of Ceramic and Pre-Irradiated Materials in DiMES
2025 Research Campaign, Thrust: FPP Candidate Wall Materials
Purpose of Experiment
Novel and/or advanced plasma-facing materials must be investigated for use in next-generation fusion devices. This experiment in DIII-D aims to characterize the plasma-material interaction (PMI) response of fusion pilot-plant relevant material candidates by exposing them to tokamak plasma using the Divertor Materials Evaluation System (DiMES) test-stand. Materials to-be exposed are silicon carbide fiber composites (SiCf/SiC), pristine and neutron irradiated monolithic silicon carbide (SiC), boron carbide (B4C), silicon nitride (Si3N4), pristine and neutron irradiated titanium diboride (TiB2), pristine and neutron irradiated titanium carbide (TiC), pristine and neutron irradiated tungsten (W), and pristine and neutron irradiated tungsten doped with potassium ions (K-doped W). SiCf/SiC, B4C, Si3N4, and SiC samples will be exposed to H-mode plasma with a strike point swept across and back the DiMES surface. H-mode plasma exposures will induce intense steady-state and transient heat and particle fluxes on the materials; by comparing post-exposure material surface morphology and erosion, conclusions can be made on material suitability for fusion plasma-facing applications. TiB2, TiC, W, and K-doped W samples will be exposed to L-mode plasma in order to characterize how neutron damage influences plasma-induced defect evolution and deuterium capture and retention behavior in the materials. This experiment includes first-of-its-kind DIII-D plasma exposures to samples pre-irradiated with neutrons and is highly relevant for both near-term ITER-like devices as well as fusion pilot-plant type facilities where neutron degradation is unavoidable.