Fabrication and Qualification Testing of Plasma Facing Components for the Nuclear Fusion Research

ITER divertor should remove the extreme heat flux up to 10 MW/m2 (and 20 MW/m2 in the transient condition) and various type of divertor have been developed for enhancing the heat transfer. For the limitation of mechanical machining, 3D metal printing technology is selected to fabricate the multi-layer cooling devices for the development of fusion divertor research, Thermo-hydraulic testing was performed in Korean heat load test facility using an electron beam (KoHLT-EB). Tungsten-armored mockups were fabricated by the HIP between W and FMS (Ferritic-Martensitic Steel), W coating in FMS. 3D printed mockup was designed and fabricated based on the optimization of the 3D cooling structure. KoHLT-EB was used to evaluate the thermos-hydraulic enhancement. Present results will contribute to the development of a Korean fusion research and DEMO reactor. Plasma facing components for the high heat flux testing were fabricated and thermo-hydraulic and lifetime testing was performed as selected for the development of fusion divertor and blanket first wall in KoHLT-EB high heat flux test facility. The various cooling mockups for ITER, DEMO, and fusion research have been fabricated, such as HIP bonding, VPS coating, and 3D metal printing. 3D printed mockups were fabricated based on the optimization of cooling structure. Thermo-hydraulic testing for the fabricated mockups was performed in KoHLT-EB. These results will contribute the development of fusion research and DEMO concept.