Plasma Exposure of 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 (FPP) relevant material candidates by exposing them to tokamak plasma using the Divertor Materials Evaluation System (DiMES). Materials to be exposed are pristine and neutron irradiated monolithic silicon carbide (SiC), titanium diboride (TiB2), titanium carbide (TiC), tungsten (W), and potassium doped tungsten (K-doped W). These samples will be exposed to L-mode plasma to characterize how neutron damage influences plasma-induced defect evolution and hydrogen isotope retention in the materials. In most FPP magnetically confined fusion device concepts, material degradation from neutron is inevitable; it is vital to characterize how neutron damage impact plasma response of fusion first wall materials.