Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak
- Chinese Academy of Sciences (CAS), Hefei (China). Institute of Plasma Physics
- General Atomics, San Diego, CA (United States)
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Alternative Energies and Atomic Energy Commission (CEA), Saint Paul-lez-Durance (France)
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Recent Experimental Advanced Superconducting Tokamak (EAST) experiments have successfully demonstrated a long-pulse steady-state scenario with improved plasma performance through integrated operation since the last IAEA FEC in 2016. A discharge with a duration over 100 s using pure radio frequency (RF) power heating and current drive has been obtained with the required characteristics for future long-pulse tokamak reactors such as good energy confinement quality (H98y2 ~ 1.1) with electron internal transport barrier inside ρ < 0.4, small ELMs (frequency ~100–200 Hz), and good control of impurity and heat exhaust with the tungsten divertor. The optimization of X-point, plasma shape, the outer gap and local gas puffing near the low hybrid wave (LHW) antenna were integrated with global parameters of BT and line-averaged electron density for higher current drive efficiency of LHW and on-axis deposition of electron cyclotron heating in the long-pulse operation. More recently, a high βP RF-only discharge (βP ~ 1.9 and βN ~ 1.5, $$\langle$$ne$$\rangle$$/nGW ~ 0.80, fbs ~ 45% at q95 ~ 6.8) was successfully maintained over 24 s with improved hardware capabilities, demonstrating performance levels needed for the China Fusion Engineering Test Reactor steady-state operation. In this work, a higher energy confinement is observed at higher βP and with favorable toroidal field direction. Towards the next goal (≥400 s long-pulse H-mode operations with ~50% bootstrap current fraction) on EAST, an integrated control of the current density profile, pressure profile and radiated divertor will be addressed in the near future.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA); National Magnetic Confinement Fusion Program of China; Chinese Academy of Sciences (CAS); National Key Research and Development Program of China; National Natural Science Foundation of China (NSFC); National Nature Science Foundation of China
- Contributing Organization:
- EAST Team
- Grant/Contract Number:
- AC52-07NA27344
- OSTI ID:
- 1798017
- Alternate ID(s):
- OSTI ID: 1511460
- Report Number(s):
- LLNL-JRNL-777065; 966470; TRN: US2210645
- Journal Information:
- Nuclear Fusion, Vol. 59, Issue 8; ISSN 0029-5515
- Publisher:
- IOP ScienceCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Web of Science
27th IAEA Fusion Energy Conference: summary of sessions EX/C, EX/S and PPC
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journal | January 2020 |
Improved high-performance fully non-inductive discharge by optimizing the fast-ion confinement on EAST
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journal | October 2019 |
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