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Title: Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST

Recent experiments on EAST have achieved the first long pulse H-mode (61 s) with zero loop voltage and an ITER-like tungsten divertor, and have demonstrated access to broad plasma current profiles by increasing the density in fully-noninductive lower hybrid current-driven discharges. These long pulse discharges reach wall thermal and particle balance, exhibit stationary good confinement (H 98y2~1.1) with low core electron transport, and are only possible with optimal active cooling of the tungsten armors. In separate experiments, the electron density was systematically varied in order to study its effect on the deposition profile of the external lower hybrid current drive (LHCD), while keeping the plasma in fully-noninductive conditions and with divertor strike points on the tungsten divertor. A broadening of the current profile is found, as indicated by lower values of the internal inductance at higher density. A broad current profile is attractive because, among other reasons, it enables internal transport barriers at large minor radius, leading to improved confinement as shown in companion DIII-D experiments. These experiments strengthen the physics basis for achieving high performance, steady state discharges in future burning plasmas.
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  1. General Atomics, San Diego, CA (United States)
  2. Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics
  3. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
  4. Univ. of California, Los Angeles, CA (United States). Dept. of Physics and Astronomy
  5. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  6. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  7. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  8. Alternative Energies and Atomic Energy Commission (CEA), Saint-Paul-Les-Durance Cedex (France). Inst. de Recherche sur la Fusion par confinement Magnetique (IRFM)
Publication Date:
Grant/Contract Number:
FC02-04ER54698; SC0010685; SC0010492; FG02-01ER54615; AC02-09CH11466; AC52-07NA27344
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 57; Journal Issue: 7; Journal ID: ISSN 0029-5515
IOP Science
Research Org:
General Atomics, San Diego, CA (United States)
Sponsoring Org:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
Country of Publication:
United States
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; magnetic fusion; steady-state tokamak; current profile control; lower hybrid
OSTI Identifier: