Key features in the operation of KSTAR

J. Kwak, Y. Oh, K. Kim, S. W. Kim, S. H. Hong, W. Chu, H. J. Lee, Y.O. Kim, J. Kim, S. Park, S. Hahn, M. K. Park, H. K. Kim, J. Bak, Y. Bae, W. Ko, S.G. Lee, J.H. Lee, J. Jung, K.D. Lee, Y. Nam, Y. Jeon, S. Yoon, A. England, W. C. Kim, K. Park, H. Na, H. Yang, M. Kwon
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引用次数: 6

Abstract

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 Nb3Sn, 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 BT=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
KSTAR运行的主要特点
韩国超导托卡马克先进研究(KSTAR)装置旨在进行先进托卡马克(at)研究。自2008年首次获得等离子体以来,已经过去了三年。由于它是超导机器,并且正在进行AT研究,因此在机器工程和操作方面具有独特的特点。环形磁场(TF)磁体线圈由Nb3Sn制成,可提供高达3.5 T的高环形磁场,并已经过充分测试。由Nb3Sn和NbTi组成的极向磁场(PF)磁铁线圈,其设计的最大电流为25 kA,测试了高达15 kA的电流。对PF磁铁线圈的运行进行了热液压分析。所有面向等离子体的组件(pfc)都配备了水冷石墨瓦,并具有高达350°C的烘烤能力。在过去两年的可靠运行中,开发了一种启动方案,该方案考虑了磁性线圈中电缆导管导体(CICC)护套中的铁磁性材料的影响,以及低温恒温器结构中的非铁磁性上下不对称。被动稳定器和船内控制线圈(IVCC)是KSTAR实现AT运行的关键部件。2010年,将分段IVCC线圈连接成圆形线圈进行内部垂直控制,获得了高伸长率(κ ~ 1.8, δ>0.6)的分流等离子体。为满足KSTAR的长脉冲要求,研制了一种2 MW、300 s /离子源的中性束注入系统。一个100千伏功率为1.7兆瓦的NBI离子源已经投入使用。最后,在2010年,在0.6 MA的等离子体电流下,以1.3 MW的NBI功率成功生产了ELMy h模。KSTAR的第一次h模式放电(#4200)比官方计划提前一年完成,在pfc上硼化后,在BT=2.0 T, Ip=0.6 MA的良好平衡双零配置下完成。KSTAR早期的成功运行包括h模式实验显示了先进和稳态运行的能力,这对国际热核实验反应堆(ITER)和未来的聚变反应堆至关重要
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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