Lead P.I. - Dr. Lance Snead and Dr. David Sprouster 

Plasma facing materials for fusion reactors have transitioned from the graphite of early machines, to carbon-fiber-composites, to beryllium, to the tungsten of current machines such as the International Thermonuclear Experimental Reactor.  While the high-atomic number of tungsten proves a difficult atom for the fusion reactors to erode and poison the plasma, its irradiation effects significantly limit its useful lifetime.  Ultra-high temperature ceramics are considered higher-operating temperature long-lived alternatives to tungsten.  Ongoing research included fabrication of low-activation and irradiation stable UHTC’s with high fracture toughness.  Intrinsic toughening is sought through multicomponent carbide system while classic compositing is being pursued for extrinsic toughening.