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  4. Full wave simulations of fast wave efficiency and power losses in the scrape-off layer of tokamak plasmas in mid/high harmonic and minority heating regimes

Full wave simulations of fast wave efficiency and power losses in the scrape-off layer of tokamak plasmas in mid/high harmonic and minority heating regimes

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Author(s)
Bertelli, N.
•
Jaeger, E.F.
•
Hosea, J.C.
•
Phillips, C.K.
•
Berry, L.
•
Gerhardt, S.P.
•
Green, D.
•
LeBlanc, B.
•
Perkins, R.J.
•
Qin, C.M.
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Date Issued
December 2015
Journal
Nuclear Fusion
Publisher
IOP Publishing
Citation
Bertelli, N. et al. “Full Wave Simulations of Fast Wave Efficiency and Power Losses in the Scrape-Off Layer of Tokamak Plasmas in Mid/high Harmonic and Minority Heating Regimes.” Nuclear Fusion 56, 1 (December 2015): 016019 © 2016 U.S. Department of Energy
Version
Author's final manuscript
Abstract
Several experiments on different machines and in different fast wave (FW) heating regimes, such as hydrogen minority heating and high harmonic fast waves (HHFW), have found strong interaction between radio-frequency (RF) waves and the scrape-off layer (SOL) region. This paper examines the propagation and the power loss in the SOL by using the full wave code AORSA, in which the edge plasma beyond the last closed flux surface (LCFS) is included in the solution domain and a collisional damping parameter is used as a proxy to represent the real, and most likely nonlinear, damping processes. 2D and 3D AORSA results for the National Spherical Torus eXperiment (NSTX) have shown a strong transition to higher SOL power losses (driven by the RF field) when the FW cut-off is removed from in front of the antenna by increasing the edge density. Here, full wave simulations have been extended for 'conventional' tokamaks with higher aspect ratios, such as the DIII-D, Alcator C-Mod, and EAST devices. DIII-D results in HHFW regime show similar behavior found in NSTX and NSTX-U, consistent with previous DIII-D experimental observations. In contrast, a different behavior has been found for C-Mod and EAST, which operate in the minority heating regime.
MIT Department
Massachusetts Institute of Technology. Plasma Science and Fusion Center
Terms of Use
Article is made available in accordance with the publisher's policy and may be subject to US copyright law. Please refer to the publisher's site for terms of use.
Persistent DSpace Link
http://hdl.handle.net/1721.1/113082
DOI of Published Version
https://doi.org/10.1088/0029-5515/56/1/016019
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