Achievements of actively controlled divertor detachment compatible with sustained high confinement core in DIII-D and EAST

作者：Liang Wang, Huiqian Wang, D. Eldon, Qiping Yuan, S. Ding, Kedong Li, A. M. Garofalo, Xianzu Gong, Guosheng Xu, Heng Guo, Kai Wu, L.Y. Meng, J.C. Xu, J.B. Liu, Mingwei Chen, Bin Zhang, Yanmin Duan, F. Ding, Zengyin Yang, Jing Qian, J. Huang, Qilong Ren, A.W. Leonard, M.E. Fenstermacher, C.J. Lasnier, J.G. Watkins, M.W. Shafer, J.L. Barr, David B. Weisberg, J. McClenaghan, J.M. Hanson, A.W. Hyatt, Tom Osborne, Deepa Thomas, D.A. Humphreys, R. J. Buttery, Guang–Nan Luo, Bingjia Xiao, Baonian Wan, J.G. Li · 发表于：Nuclear Fusion · 年份：2021 · DOI：10.1088/1741-4326/ac4774 · 被引用次数：25 · 研究领域：Magnetic confinement fusion research、Fusion materials and technologies、Laser-Plasma Interactions and Diagnostics

Abstract The compatibility of efficient divertor detachment with high-performance core plasma is vital to the development of magnetically controlled fusion energy. The joint research on the EAST and DIII-D tokamaks demonstrates successful integration of divertor detachment with excellent core plasma confinement quality, a milestone towards solving the critical plasma–wall-interaction (PWI) issue and core-edge integration for ITER and future reactors. In EAST, actively controlled partial detachment with T et,div ∼ 5 eV around the strike point and H 98 > 1 in different H-mode scenarios including the high β P H-mode scenario have been achieved with ITER-like tungsten divertor, by optimizing the detachment access condition and performing detailed experiments for core-edge integration. For active long-pulse detachment feedback control, a 30 s H-mode operation with detachment-control duration being 25 s has been successfully achieved in EAST. DIII-D has achieved actively controlled fully detached divertor with low plasma electron temperature ( T et,div ⩽ 5 eV across the entire divertor target) and low particle flux (degree of detachment, DoD > 3), simultaneously with very high core performance ( β N ∼3, β P > 2 and H 98 ∼ 1.5) in the high β P scenario being developed for ITER and future reactors. The high- β P high confinement scenario is characterized by an internal transport barrier (ITB) at large radius and a weak edge transport barrier (ETB, or pedestal), which are syn...