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

  title={Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER},
  author={C.S. Chang and S. Ku and Alberto Loarte and Vassili Parail and F. K{\"o}chl and Michele Romanelli and Rajesh Maingi and J-W. Ahn and T. K. Gray and J. Hughes and B. LaBombard and T. Leonard and M. A. Makowski and J. L. Terry},
  journal={Nuclear Fusion},
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. The simulation results compare well against the empirical scaling λ q ∝ 1/ BPγ obtained from present tokamak devices, where λ q is the divertor heat-flux width mapped to the… 

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A multi-machine database for the H-mode scrape-off layer power fall-off length, λq in JET, DIII-D, ASDEX Upgrade, C-Mod, NSTX and MAST has been assembled under the auspices of the International

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A heuristic model for the plasma scrape-off width in low-gas-puff tokamak H-mode plasmas is introduced. Grad B and curv B drifts into the scrape-off layer (SOL) are balanced against near-sonic

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