Advances in the long-pulse steady-state high beta H-mode scenario with active controls of divertor heat and particle fluxes in EAST

Wan, Baonian; Gong, Xianzu; Liang, Yunfeng; Xiang, Nong; Xu, Guo Sheng; Sun, Youwen; Wang, Liang; Qian, Jinping; Liu, Haiqing; Zhang, Bin; Xia, T. Y.; Huang, Juan; Ding, Rui; Zhang, Tao; Zuo, Guizhong; Sun, Zhen; Zeng, Long; Zhang, Xinjun; Zang, Qing; Lyu, Bo; Garofalo, Andrea M.; Li, Guoqiang; Li, Kedong; Yang, Qingquan

doi:10.1088/1741-4326/ac2993

Title: Advances in the long-pulse steady-state high beta H-mode scenario with active controls of divertor heat and particle fluxes in EAST

Journal Article · Mon Feb 07 00:00:00 EST 2022 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/ac2993· OSTI ID:1821925

Wan, Baonian ^[1]; Gong, Xianzu ^[1]; Liang, Yunfeng ^[2]; Xiang, Nong ^[1];

^[1];

^[1]; Qian, Jinping ^[1];

^[1];

^[1]; Xia, T. Y. ^[1]; Huang, Juan ^[1];

^[1];

^[1]; Zuo, Guizhong ^[1]; Sun, Zhen ^[3];

^[1]; Zhang, Xinjun ^[1]; Zang, Qing ^[1];

^[1] more »

Chinese Academy of Sciences (CAS), Beijing (China)
Chinese Academy of Sciences (CAS), Beijing (China); Forschungszentrum Juelich (Germany)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
General Atomics, San Diego, CA (United States)

Since the last IAEA-Fusion Energy Conference, the Experimental Advanced Superconducting Tokamak (EAST) research program has been, in support of ITER and CFETR, focused on development in terms of the long-pulse steady-state (fully noninductive) high beta H-mode scenario with active controls of the stationary and transient divertor heat and particle fluxes. The operational domain of the steady-state H-mode plasma scenario has been significantly extended with ITER-like tungsten mono-block divertor, plasma control and heating schemes. EAST has achieved several important milestones in the development of high β_p H-mode scenario and its key physics and technologies. A 60 s-scale long-pulse steady-state high β_p H-mode discharge with the major normalized plasma parameters similar to the designed performance of the CFETR 1GW fusion power operation scenario has been successfully established and sustained by pure RF heating and current drive. Several feedback control schemes have been developed for a sustained detachment with good core confinement. This includes control of the total radiation power, target electron temperature, and particle flux measured using divertor Langmuir probes or a combination of the control of target electron temperature and AXUV radiation near the X point. The detachment feedback control schemes have been integrated with small-ELM regimes and high β_p scenario via neon seeding, enabling a core and edge compatible integrated high-beta scenario applicable to long-pulse operations. ELM suppression has been achieved using various methods, including resonant magnetic perturbations and impurity seeding. Full suppression of ELMs by using n=4 RMPs has been demonstrated for ITER for the first time in low input torque plasmas in EAST. Finally, EAST has been operated with helium to support the ITER research requirements for the first time. For a long-pulse, high bootstrap current fraction operation, a new lower tungsten divertor with active water-cooling has been installed, along with improvements in the heating and current drive capability.

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Research Organization:: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Sponsoring Organization:: USDOE; National Key Research and Development Program of China; National Magnetic Confinement Fusion Energy R&D Program

Grant/Contract Number:: AC02-09CH11466; 2017YFE0301100; 2017YFE0301300; 2017YFE301205; 2018YFE0303104; 2019YFE0303000; 2019YFE0304000; 2019YFE0307000; 2019YFE03010002; 2109YFE03020004; 2017YFA0402500

OSTI ID:: 1821925

Journal Information:: Nuclear Fusion, Vol. 62, Issue 4; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

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