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 (doi:10.7910/DVN/VBDX3H)

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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

doi:10.7910/DVN/VBDX3H

Harvard Dataverse

2019-01-10

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N. Bertelli, E.F. Jaeger, J.C. Hosea, C.K. Phillips, L. Berry, P.T. Bonoli, S.P. Gerhardt, D. Green, B. LeBlanc, R.J. Perkins, C.M. Qin, R.I. Pinsker, R. Prater, P.M. Ryan, G. Taylor, E.J. Valeo, J.R. Wilson, J.C. Wright, X.J. Zhang, 2019, "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", https://doi.org/10.7910/DVN/VBDX3H, Harvard Dataverse, V1

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

doi:10.7910/DVN/VBDX3H

N. Bertelli, E.F. Jaeger, J.C. Hosea, C.K. Phillips, L. Berry, P.T. Bonoli, S.P. Gerhardt, D. Green, B. LeBlanc, R.J. Perkins, C.M. Qin, R.I. Pinsker, R. Prater, P.M. Ryan, G. Taylor, E.J. Valeo, J.R. Wilson, J.C. Wright, X.J. Zhang

Harvard Dataverse

https://doi.org/10.7910/DVN/VBDX3H

Physics, Alcator C-Mod, computer simulations, ion cyclotron heating, NSTX, scrape off layer

Several experiments on different machines and in different fast wave (FW) heating regimes, such as hydrogen minority heating and high harmonic fast waves, 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. 3D AORSA results for National Spherical Torus eXperiment (NSTX), where a full antenna spectrum is reconstructed, are shown confirming the same behavior found for a single toroidal mode results in Bertelli et al Nucl. Fusion, 54 083004, 2014, namely, a strong transition to higher SOL power losses (driven by the RF field) has been found when the FW cut-off is removed from in front of the antenna by increasing the edge density. Additionally, 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 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 unlike NSTX/NSTX-U and DIII-D, which operate in the mid/high harmonic regime.

<a href="http://library.psfc.mit.edu/catalog/reports/2010/15ja/15ja086/abstract.php">PSFC REPORT PSFC/JA-15-86</a><br /><br />This work was supported in part under DoE Contract No. DE-FC02-01ER54648.

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