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연구 분야
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논문
구성원
article|
인용수 16
·2024
Overview of the KSTAR experiments toward fusion reactor
W.H. Ko, S. W. Yoon, W. C. Kim, J.G. Kwak, K.L. Park, Y.U. Nam, S.J. Wang, June-Key Chung, B.H. Park, G. Y. Park, H.H. Lee, Hyunsun Han, M. Choi, Y.S. Na, Y. In, Chanyoung Lee, Minwoo Kim, G.S. Yun, Young-chul Ghim, Wonho Choe, J.M. Kwon, Jungpyo Lee, Woochang Lee, Y.M. Jeon, Kimin Kim, Jongha Lee, Giwook Shin, Junghee Kim, Jaehyun Lee, S.H. Hahn, Jeongwon Lee, Hyun-Seok Kim, J. G. Bak, S. G. Lee, Youngho Lee, Junhyung Jeong, M.H. Woo, Junghee Kim, J.-W. Juhn, J. Ko, C. Sung, H.W. Shin, Jongyoun Park, S.K. Kim, Jong-Kyu Park, N.C. Logan, S.M. Yang, Egemen Kolemen, Qiming Hu, Ricardo Shousha, J.L. Barr, C. Paz-Soldan, Y.S. Park, S.A. Sabbagh, K. Ida, S. Kim, A. Loarte, E.P. Gilson, D. Eldon, T. Nakano, T. Tala, KSTAR Team
IF 4Nuclear Fusion
초록

Abstract The Korean Superconducting Tokamak Advanced Research has been focused on exploring the key physics and engineering issues for future fusion reactors by demonstrating the long pulse operation of high beta steady-state discharge. Advanced scenarios are being developed with the goal for steady-state operation, and significant progress has been made in high ℓ i , hybrid and high beta scenarios with β N of 3. In the new operation scenario called fast ion regulated enhanced (FIRE), fast ions play an essential role in confinement enhancement. GK simulations show a significant reduction of the thermal energy flux when the thermal ion fraction decreases and the main ion density gradient is reversed by the fast ions in FIRE mode. Optimization of 3D magnetic field techniques, including adaptive control and real-time machine learning control algorithm, enabled long-pulse operation and high-performance ELM-suppressed discharge. Symmetric multiple shattered pellet injections (SPIs) and real-time disruption event characterization and forecasting are being performed to mitigate and avoid the disruptions associated with high-performance, long-pulse ITER-like scenarios. Finally, the near-term research plan will be addressed with the actively cooled tungsten divertor, a major upgrade of the NBI and helicon current drive heating, and transition to a full metallic wall.

키워드
DivertorNuclear engineeringKSTARASDEX UpgradeHeliconMaterials scienceTokamakPlasmaTransient (computer programming)Fusion power
타입
article
IF / 인용수
4 / 16
게재 연도
2024

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