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Title: Turbulence driven widening of the near-SOL power width in ASDEX Upgrade H-Mode discharges

Abstract

Divertor heat flux data from infra red (IR) from various tokamaks in H-Mode regime show that the power width, $$\lambda_{q}$$, scales approximately like 1.6 $$(R/a) ρ_{s,pol}$$. However, the IR based scaling comes with the restriction that only discharges were considered with attached divertor conditions. Here we set up a new data base covering low edge density data but also including high density plasmas reaching the H-mode density limit. We use Thomson-scattering to measure the electron temperature decay length which will set the near-SOL power width through parallel heat conduction. We present scaling results for the density, temperature and pressure separatrix fall-off lengths. As the principal result we derive a generalized power width scaling which reads as $$\lambda_{q}\propto\,\rho_{s,pol}\cdot(1+2.1\alpha_{t}^{1.7})$$ where $$\alpha_{t}$$ describes a normalized collisionality ($$\alpha_{t} = 3\cdot\,10^{-18}\,R\,q^2\,n\,Z_{eff}T^{-2}$$). The parameter $$\alpha_{t}$$ describes the relative importance of the interchange effect on drift-wave turbulence as proposed by Scott and is found to be closely linked to the diamagnetic parameter αd introduced by Rogers, Drake and Zeiler (RDZ). The edge operational space for ASDEX Upgrade displays a boundary qualitatively in agreement with the region labelled as density limit in the edge plasma phase space proposed by RDZ. The data base shows in the limit of low edge densities ($$\alpha_{t}\simeq\,0.2$$) accurate agreement to the IR based power width scaling. At elevated separatrix densities ($$\alpha_{t}\simeq\,1$$) the power width is broadened by a factor of up to about three accompanied by a reduction of the $$\text{H}_{98,y2}$$ confinement factor. Finally, plasmas with higher triangularity show higher values for $$\text{H}_{98,y2}$$ in the same range of normalized collisionality.

Authors:
ORCiD logo [1];  [1]; ORCiD logo [2]; ORCiD logo [3];  [1]; ORCiD logo [1];  [1];  [1];  [1]
  1. Max Planck Society, Garching (Germany). Max Planck Institute for Plasma Physics
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  3. Ecole Polytechnique, Palaiseau (France)
Publication Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
USDOE; Euratom
OSTI Identifier:
1651136
Grant/Contract Number:  
AC02-09CH11466; 633053
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 60; Journal Issue: 5; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; power width; turbulence; density limit; H-Mode; tokamak; ASDEX Upgrade; SOL decay length

Citation Formats

Eich, T., Manz, P., Goldston, R. J., Hennequin, P., David, P., Faitsch, M., Kurzan, B., Sieglin, B., and Wolfrum, E. Turbulence driven widening of the near-SOL power width in ASDEX Upgrade H-Mode discharges. United States: N. p., 2020. Web. doi:10.1088/1741-4326/ab7a66.
Eich, T., Manz, P., Goldston, R. J., Hennequin, P., David, P., Faitsch, M., Kurzan, B., Sieglin, B., & Wolfrum, E. Turbulence driven widening of the near-SOL power width in ASDEX Upgrade H-Mode discharges. United States. https://doi.org/10.1088/1741-4326/ab7a66
Eich, T., Manz, P., Goldston, R. J., Hennequin, P., David, P., Faitsch, M., Kurzan, B., Sieglin, B., and Wolfrum, E. Thu . "Turbulence driven widening of the near-SOL power width in ASDEX Upgrade H-Mode discharges". United States. https://doi.org/10.1088/1741-4326/ab7a66. https://www.osti.gov/servlets/purl/1651136.
@article{osti_1651136,
title = {Turbulence driven widening of the near-SOL power width in ASDEX Upgrade H-Mode discharges},
author = {Eich, T. and Manz, P. and Goldston, R. J. and Hennequin, P. and David, P. and Faitsch, M. and Kurzan, B. and Sieglin, B. and Wolfrum, E.},
abstractNote = {Divertor heat flux data from infra red (IR) from various tokamaks in H-Mode regime show that the power width, $\lambda_{q}$, scales approximately like 1.6 $(R/a) ρ_{s,pol}$. However, the IR based scaling comes with the restriction that only discharges were considered with attached divertor conditions. Here we set up a new data base covering low edge density data but also including high density plasmas reaching the H-mode density limit. We use Thomson-scattering to measure the electron temperature decay length which will set the near-SOL power width through parallel heat conduction. We present scaling results for the density, temperature and pressure separatrix fall-off lengths. As the principal result we derive a generalized power width scaling which reads as $\lambda_{q}\propto\,\rho_{s,pol}\cdot(1+2.1\alpha_{t}^{1.7})$ where $\alpha_{t}$ describes a normalized collisionality ($\alpha_{t} = 3\cdot\,10^{-18}\,R\,q^2\,n\,Z_{eff}T^{-2}$). The parameter $\alpha_{t}$ describes the relative importance of the interchange effect on drift-wave turbulence as proposed by Scott and is found to be closely linked to the diamagnetic parameter αd introduced by Rogers, Drake and Zeiler (RDZ). The edge operational space for ASDEX Upgrade displays a boundary qualitatively in agreement with the region labelled as density limit in the edge plasma phase space proposed by RDZ. The data base shows in the limit of low edge densities ($\alpha_{t}\simeq\,0.2$) accurate agreement to the IR based power width scaling. At elevated separatrix densities ($\alpha_{t}\simeq\,1$) the power width is broadened by a factor of up to about three accompanied by a reduction of the $\text{H}_{98,y2}$ confinement factor. Finally, plasmas with higher triangularity show higher values for $\text{H}_{98,y2}$ in the same range of normalized collisionality.},
doi = {10.1088/1741-4326/ab7a66},
journal = {Nuclear Fusion},
number = 5,
volume = 60,
place = {United States},
year = {Thu Apr 09 00:00:00 EDT 2020},
month = {Thu Apr 09 00:00:00 EDT 2020}
}

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