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Title: Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years

Journal Article · · Journal of Fusion Energy
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  1. Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics
  2. General Atomics, San Diego, CA (United States)
  3. Forschungszentrum Juelich (Germany). Institut für Energie–und Klimaforschung-Plasmaphysik
  4. Dalian Univ. of Technology (China)
  5. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  6. Alternative Energies and Atomic Energy Commission (CEA), Saint-Paul-lez-Durance (France). Institute for Magnetic Fusion Research (IRFM)
  7. Southwestern Institute of Physics, Chengdu (China)

Active control of the excessively high heat and particle fluxes on the divertor target plates is of fundamental importance to the steady state operation of tokamaks, especially for fusion reactors. A series of experiments have been carried out on this critical issue to relieve the plasma-wall interactions in the experimental advanced superconducting tokamak (EAST) in the last ten years, not only contributing to the long pulse operation of EAST itself, but also providing physical understandings and potential techniques to the next-generation devices like ITER. Here we have characterized the power deposition pattern and broadened the divertor footprint width effectively. The plasma-wetted area is actively handled using either 3-dimentional edge magnetic topology or advanced plasma equilibrium, thereby peak heat flux around the strike point is reduced. Active control of detachment or radiation compatible with core plasma performance has progressed significantly in very recent years, with a series of active feedback control modules developed and utilized successfully, based on the divertor physics advances with both experiments and simulation. The upper divertor of EAST was upgraded from graphite to active water-cooling ITER-like tungsten in 2014, exhibiting much enhanced heat removal capability. As for the particle exhaust including both fueling and impurity particles, in addition to wall conditioning and impurity source control, the efficiency of particle flux exhaust is optimized by making full use of the divertor closure and the plasma drifts in both scrape-off layer and divertor volume. These heat and particle exhaust advances contribute greatly to a series of EAST achievements like H-mode operation over 100 s. A brief near-term plan on the integrated control of divertor plasma-wall interactions in long-time scale will also be introduced, aiming to provide favorable divertor operation solution for ITER and CFETR.

Research Organization:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE; National Key R & D Program of China; Hefei Comprehensive National Science Center; National Natural Science Foundation of China (NSFC); Chinese Academy of Sciences; K. C. Wong Education Foundation
Grant/Contract Number:
2017YFE0301300; 2017YFA0402500; 2019YFE03030000; GXXT-2020-004; 11922513; U19A20113; 11905255; QYZDBSSW-SLH001; 1808085J07; 2018HSC-UE008
OSTI ID:
1818378
Journal Information:
Journal of Fusion Energy, Vol. 40, Issue 1; ISSN 0164-0313
Publisher:
SpringerCopyright Statement
Country of Publication:
United States
Language:
English

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