[en] The STARFIRE/DEMO Project has performed a conceptual design study of the demonstration fusion power reactor to follow the FED/INTOR class of experimental tokamaks. This paper discusses thermo-structural and thermal-hydraulic aspects of two fundamentally different first wall and tritium breeding blanket concepts for STARFIRE/DEMO. The first concept uses solid lithium oxide (Li₂O) as the tritium breeder in a modular blanket. The first wall is a flat corrugated panel. Both first wall and blanket are constructed of titanium-modified austenitic stainless steel and are cooled with pressurized high-temperature water. The second concept features a liquid metal, 17Li-83Pb, as tritium breeder and coolant. The blanket module's two semi-cylindrical front walls form the first wall, the back faces of which are cooled by flowing liquid metal. Ferritic steel and vanadium alloy are the candidate structural materials