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Title: Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER

Here, the XGC1 edge gyrokinetic code is used to study the width of the heat-flux to divertor plates in attached plasma condition. The flux-driven simulation is performed until an approximate power balance is achieved between the heat-flux across the steep pedestal pressure gradient and the heat-flux on the divertor plates.
Authors:
 [1] ;  [1] ;  [2] ;  [3] ; ORCiD logo [4] ;  [3] ;  [1] ;  [5] ;  [6] ;  [7] ; ORCiD logo [7] ;  [8] ;  [9] ; ORCiD logo [7]
  1. Princeton Univ., Princeton, NJ (United States). Princeton Plasma Physics Lab.
  2. ITER Organization, St. Paul Lez Durance (France)
  3. Culham Centre for Fusion Energy, Abingdon (United Kingdom)
  4. Technische Univ. Wien, Vienna (Austria)
  5. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  6. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States
  7. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  8. General Atomics, San Diego, CA (United States)
  9. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Publication Date:
Grant/Contract Number:
AC02-09CH11466; AC05-00OR22725; FC02-04ER54698; FC02-99ER54512
Type:
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 57; Journal Issue: 11; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Research Org:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
OSTI Identifier:
1373693