부산대학교 도서관

The Korean Superconducting Tokamak Advanced Research (KSTAR) device is aimed at advanced tokamak (AT) research. Three years have passed since it achieved its first plasma in 2008. Because it is a superconducting machine and is pursuing AT research, it has unique features in terms of the machine engineering and operation. The toroidal field (TF) magnet coils are made of Nb 3 Sn, which provide high toroidal fields up to 3.5 T, and have been fully tested. The poloidal field (PF) magnet coils, consisting of both Nb3Sn and NbTi, which have a maximum current of 25 kA in their design, were tested up to 15 kA. A thermal hydraulic analysis is being conducted for PF magnet coil operation. All plasma facing components (PFCs) are equipped with water cooled graphite tiles and have the capability of being baked up to 350 °C. A startup scenario, which considered both the effect of the ferromagnetic material in the cable in conduit conductor (CICC) jacket in the magnet coils as well as a non-ferromagnetic up-down asymmetry in the cryostat structure, was developed and demonstrated its effectiveness by the last two year's reliable operations. Passive stabilizers and In-Vessel Control Coils (IVCC) are key components to realize AT Operation in KSTAR. The segmented IVCC coils were connected to form circular coils for internal vertical control in 2010 and diverted plasmas with high elongation (κ∼1.8, δ>0.6) were achieved. A neutral beam injection (NBI) system was developed aiming at 2 MW, 300 s per ion source which meets the long-pulse requirement of KSTAR. An NBI ion source with a power of 1.7 MW at 100 kV has been commissioned. Finally, ELMy H-modes were successfully produced with 1.3 MW NBI power at a plasma current of 0.6 MA in the 2010 campaign. The first H-mode discharge (#4200) in KSTAR was achieved one year earlier than officially planned and it was done at B T =2.0 T with Ip=0.6 MA in a well-balanced double null configuration after boronization on the PFC. Successful operations in the early days of KSTAR including H-mode experiments revealed the capability of advanced and steady-state operation which is essential for the International Thermonuclear Experimental Reactor (ITER) and future fusion reactors