A team from NC State, ORNL, and JEOL used a large JEOL electron beam powder bed fusion (EB-PBF) system (JAM-5200EBM) to print full-size tungsten tiles measuring approximately 140 x 130 mm, which were installed in the lower divertor of the DIII-D tokamak in July 2026. During the DIII-D tile test campaign, the tungsten tiles were exposed to three days of direct plasma irradiation, including 74 medium- and high-power high-confinement (H-mode) discharges, and were retrieved intact with no damage. Previously, in 2025, small samples in the DiMES device withstood heat fluxes of nearly 20 MW/m2 (with peaks exceeding 35 MW/m2) with minimal surface damage. DIII-D is a national fusion research facility operated by General Atomics in the United States (San Diego). ORNL is the U.S. Department of Energy's largest science and energy laboratory and is responsible for manufacturing research on additive manufacturing and nuclear materials. JEOL's JAM-5200EBM uses a high-power electron beam, making it suitable for high-melting-point refractory materials such as tungsten. Michael Kirka of ORNL commented that the ability to insert printed tungsten tiles into an operating tokamak and retrieve them intact marks a shift for additive manufacturing in fusion from "promising" to "proven." Tungsten is the primary candidate material for plasma-facing components such as fusion reactor divertors and first walls. Tungsten parts with complex cooling channels are almost impossible to machine by conventional methods, making EB-PBF the only viable route. This in-machine discharge validation closes the final gap in engineering credibility. The demand for tungsten components in fusion and nuclear energy equipment will drive the development of supply chains for refractory metal powders and the EB-PBF process. Qualification cycles are long and first-mover advantages are significant, so suppliers with tungsten powder and printing capabilities should begin qualification work early.