The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D

This paper presents experimental measurements of the location of the impurity flow stagnation point in the scrape-off-layer (SOL) of a tokamak plasma. Coherence imaging of carbon-2+ emission (465 nm) is used to track the main-chamber impurity velocity of DIII-D L-mode plasmas with B×∇B out of the di...

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Main Authors: M.G. Burke, F. Scotti, S.L. Allen, W.H. Meyer, A. Holm, M. Zhao, A.G. McLean, M. Fenstermacher, H.Q. Wang, R. Wilcox
Format: Article
Language:English
Published: Elsevier 2025-03-01
Series:Nuclear Materials and Energy
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Online Access:http://www.sciencedirect.com/science/article/pii/S2352179125000286
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author M.G. Burke
F. Scotti
S.L. Allen
W.H. Meyer
A. Holm
M. Zhao
A.G. McLean
M. Fenstermacher
H.Q. Wang
R. Wilcox
author_facet M.G. Burke
F. Scotti
S.L. Allen
W.H. Meyer
A. Holm
M. Zhao
A.G. McLean
M. Fenstermacher
H.Q. Wang
R. Wilcox
author_sort M.G. Burke
collection DOAJ
description This paper presents experimental measurements of the location of the impurity flow stagnation point in the scrape-off-layer (SOL) of a tokamak plasma. Coherence imaging of carbon-2+ emission (465 nm) is used to track the main-chamber impurity velocity of DIII-D L-mode plasmas with B×∇B out of the divertor. The C2+ flow stagnates near the top or crown of the plasma when an open divertor (no baffling) is used. In contrast, with matched conditions and using a divertor with baffling, the C2+ flow stagnates near the outer divertor leg (X-point). The C2+ poloidal emission is hollow, peaking near the divertor legs, in the open configuration. In contrast, in the closed configuration, the C2+ emission is flat through most of the main-chamber SOL. Changing divertor dissipation from attached to detached conditions had only a minor effect on the main-chamber midplane impurity velocity. Numerical simulations using the multi-fluid edge transport code UEDGE including cross-field drifts show qualitative agreement with the open divertor experimental result.
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spelling doaj-art-08765e71a3c844e3865d5df8c82e34262025-08-20T02:47:37ZengElsevierNuclear Materials and Energy2352-17912025-03-014210188810.1016/j.nme.2025.101888The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-DM.G. Burke0F. Scotti1S.L. Allen2W.H. Meyer3A. Holm4M. Zhao5A.G. McLean6M. Fenstermacher7H.Q. Wang8R. Wilcox9Lawrence Livermore National Laboratory, Livermore, CA, USA; Corresponding author.Lawrence Livermore National Laboratory, Livermore, CA, USALawrence Livermore National Laboratory, Livermore, CA, USALawrence Livermore National Laboratory, Livermore, CA, USALawrence Livermore National Laboratory, Livermore, CA, USALawrence Livermore National Laboratory, Livermore, CA, USALawrence Livermore National Laboratory, Livermore, CA, USALawrence Livermore National Laboratory, Livermore, CA, USAGeneral Atomics, San Diego, CA, USAOak Ridge National Laboratory, Oak Ridge, TN, USAThis paper presents experimental measurements of the location of the impurity flow stagnation point in the scrape-off-layer (SOL) of a tokamak plasma. Coherence imaging of carbon-2+ emission (465 nm) is used to track the main-chamber impurity velocity of DIII-D L-mode plasmas with B×∇B out of the divertor. The C2+ flow stagnates near the top or crown of the plasma when an open divertor (no baffling) is used. In contrast, with matched conditions and using a divertor with baffling, the C2+ flow stagnates near the outer divertor leg (X-point). The C2+ poloidal emission is hollow, peaking near the divertor legs, in the open configuration. In contrast, in the closed configuration, the C2+ emission is flat through most of the main-chamber SOL. Changing divertor dissipation from attached to detached conditions had only a minor effect on the main-chamber midplane impurity velocity. Numerical simulations using the multi-fluid edge transport code UEDGE including cross-field drifts show qualitative agreement with the open divertor experimental result.http://www.sciencedirect.com/science/article/pii/S2352179125000286TokamakDivertor
spellingShingle M.G. Burke
F. Scotti
S.L. Allen
W.H. Meyer
A. Holm
M. Zhao
A.G. McLean
M. Fenstermacher
H.Q. Wang
R. Wilcox
The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D
Nuclear Materials and Energy
Tokamak
Divertor
title The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D
title_full The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D
title_fullStr The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D
title_full_unstemmed The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D
title_short The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D
title_sort effect of divertor closure on the impurity stagnation point in detached l mode discharges on diii d
topic Tokamak
Divertor
url http://www.sciencedirect.com/science/article/pii/S2352179125000286
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