Journal
COMPUTER PHYSICS COMMUNICATIONS
Volume 228, Issue -, Pages 69-82Publisher
ELSEVIER SCIENCE BV
DOI: 10.1016/j.cpc.2018.03.003
Keywords
Radial electric field; Tokamak boundary plasma transport; BOUT plus
Funding
- CSC [201606060097]
- U.S. Department of Energy by Lawrence Livermore National Laboratory [DE-AC52-07NA27344]
- U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences [DE-FG02-97ER54392]
- China National Natural Science Foundation of China [11575039, 11505236, 11575055, LLNL-JRNL-737785]
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The steady state radial electric field (Er) is calculated by coupling a plasma transport model with the quasi-neutrality constraint and the vorticity equation within the BOUT++ framework. Based on the experimentally measured plasma density and temperature profiles in Alcator C-Mod discharges, the effective radial particle and heat diffusivities are inferred from the set of plasma transport equations. The effective diffusivities are then extended into the scrape-off layer (SOL) to calculate the plasma density, temperature and flow profiles across the separatrix into the SOL with the electrostatic sheath boundary conditions (SBC) applied on the divertor plates. Given these diffusivities, the electric field can be calculated self-consistently across the separatrix from the vorticity equation with SBC coupled to the plasma transport equations. The sheath boundary conditions act to generate a large and positive Er in the SOL, which is consistent with experimental measurements. The effect of magnetic particle drifts is shown to play a significant role on local particle transport and Er by inducing a net particle flow in both the edge and SOL regions. (C) 2018 Elsevier B.V. All rights reserved.
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