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Title: Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak

Journal Article · · Nuclear Fusion
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  1. Chinese Academy of Sciences (CAS), Hefei (China). Institute of Plasma Physics
  2. General Atomics, San Diego, CA (United States)
  3. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  4. Alternative Energies and Atomic Energy Commission (CEA), Saint Paul-lez-Durance (France)
  5. 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
Citation Metrics:
Cited by: 48 works
Citation information provided by
Web of Science

References (12)

Suppression of tungsten accumulation during ELMy H-mode by lower hybrid wave heating in the EAST tokamak journal August 2017
SOL effects on the pedestal structure in DIII-D discharges journal May 2017
Realization of minute-long steady-state H-mode discharges on EAST journal February 2017
A digital long pulse integrator for EAST Tokamak journal May 2014
Separation of β̄ p and ℓ i in tokamaks of non-circular cross-section journal October 1985
Comparison between gas puffing and supersonic molecular beam injection in plasma density feedback experiments in EAST journal October 2013
Present Status of the EAST Diagnostics journal February 2011
Progress of the CFETR design journal June 2019
Confinement improvement in the high poloidal beta regime on DIII-D and application to steady-state H-mode on EAST journal May 2017
Transport of fast electrons during LHCD in TS, JET, and ASDEX journal December 1993
Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR journal November 2017
Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST journal June 2017

Cited By (2)


Figures / Tables (11)


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