Results from core-edge experiments in high Power, high performance plasmas on DIII-D

Significant challenges to reducing divertor heat flux in highly powered near-double null divertor (DND) hybrid plasmas, while still maintaining both high performance metrics and low enough density for application of RF heating, are identified. For these DNDs on DIII-D, the scaling of the peak heat f...

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Main Authors: T.W. Petrie, M.E. Fenstermacher, C.T. Holcomb, T.H. Osborne, S.L. Allen, J.R. Ferron, H.Y. Guo, C.J. Lasnier, A.W. Leonard, T.C. Luce, M.A. Makowski, A.G. McLean, D.C. Pace, W.M. Solomon, F. Turco, M.A. VanZeeland, J.G. Watkins
Format: Article
Language:English
Published: Elsevier 2017-08-01
Series:Nuclear Materials and Energy
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179116302526
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author T.W. Petrie
M.E. Fenstermacher
C.T. Holcomb
T.H. Osborne
S.L. Allen
J.R. Ferron
H.Y. Guo
C.J. Lasnier
A.W. Leonard
T.C. Luce
M.A. Makowski
A.G. McLean
D.C. Pace
W.M. Solomon
F. Turco
M.A. VanZeeland
J.G. Watkins
author_facet T.W. Petrie
M.E. Fenstermacher
C.T. Holcomb
T.H. Osborne
S.L. Allen
J.R. Ferron
H.Y. Guo
C.J. Lasnier
A.W. Leonard
T.C. Luce
M.A. Makowski
A.G. McLean
D.C. Pace
W.M. Solomon
F. Turco
M.A. VanZeeland
J.G. Watkins
author_sort T.W. Petrie
collection DOAJ
description Significant challenges to reducing divertor heat flux in highly powered near-double null divertor (DND) hybrid plasmas, while still maintaining both high performance metrics and low enough density for application of RF heating, are identified. For these DNDs on DIII-D, the scaling of the peak heat flux at the outer target (q⊥P) ∝ [PSOL x IP] 0.92 for PSOL= 8−19MW and IP= 1.0–1.4MA, and is consistent with standard ITPA scaling for single-null H-mode plasmas. Two divertor heat flux reduction methods were tested. First, applying the puff-and-pump radiating divertor to DIII-D plasmas may be problematical at high power and H98 (≥ 1.5) due to improvement in confinement time with deuterium gas puffing which can lead to unacceptably high core density under certain conditions. Second, q⊥P for these high performance DNDs was reduced by ≈35% when an open divertor is closed on the common flux side of the outer divertor target (“semi-slot”) but also that heating near the slot opening is a significant source for impurity contamination of the core. PSI-22 keywords: DIII-D, Divertor geometry, Gas injection and fueling, Impurity sources, Power deposition
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spelling doaj.art-41f3c34d12f0415fa90c73c675955ca42022-12-21T17:58:50ZengElsevierNuclear Materials and Energy2352-17912017-08-011211411145Results from core-edge experiments in high Power, high performance plasmas on DIII-DT.W. Petrie0M.E. Fenstermacher1C.T. Holcomb2T.H. Osborne3S.L. Allen4J.R. Ferron5H.Y. Guo6C.J. Lasnier7A.W. Leonard8T.C. Luce9M.A. Makowski10A.G. McLean11D.C. Pace12W.M. Solomon13F. Turco14M.A. VanZeeland15J.G. Watkins16General Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USA; Corresponding author.Lawrence Livermore National Laboratory, Livermore, CA, USALawrence Livermore National Laboratory, Livermore, CA, USAGeneral Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USALawrence Livermore National Laboratory, Livermore, CA, USAGeneral Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USAGeneral Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USALawrence Livermore National Laboratory, Livermore, CA, USAGeneral Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USAGeneral Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USALawrence Livermore National Laboratory, Livermore, CA, USALawrence Livermore National Laboratory, Livermore, CA, USAGeneral Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USAGeneral Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USAColumbia University, New York, NY, USAGeneral Atomics, P.O. Box 85608, San Diego, CA 92186-5608, USASandia National Laboratories, Albuquerque, NM, USASignificant challenges to reducing divertor heat flux in highly powered near-double null divertor (DND) hybrid plasmas, while still maintaining both high performance metrics and low enough density for application of RF heating, are identified. For these DNDs on DIII-D, the scaling of the peak heat flux at the outer target (q⊥P) ∝ [PSOL x IP] 0.92 for PSOL= 8−19MW and IP= 1.0–1.4MA, and is consistent with standard ITPA scaling for single-null H-mode plasmas. Two divertor heat flux reduction methods were tested. First, applying the puff-and-pump radiating divertor to DIII-D plasmas may be problematical at high power and H98 (≥ 1.5) due to improvement in confinement time with deuterium gas puffing which can lead to unacceptably high core density under certain conditions. Second, q⊥P for these high performance DNDs was reduced by ≈35% when an open divertor is closed on the common flux side of the outer divertor target (“semi-slot”) but also that heating near the slot opening is a significant source for impurity contamination of the core. PSI-22 keywords: DIII-D, Divertor geometry, Gas injection and fueling, Impurity sources, Power depositionhttp://www.sciencedirect.com/science/article/pii/S2352179116302526
spellingShingle T.W. Petrie
M.E. Fenstermacher
C.T. Holcomb
T.H. Osborne
S.L. Allen
J.R. Ferron
H.Y. Guo
C.J. Lasnier
A.W. Leonard
T.C. Luce
M.A. Makowski
A.G. McLean
D.C. Pace
W.M. Solomon
F. Turco
M.A. VanZeeland
J.G. Watkins
Results from core-edge experiments in high Power, high performance plasmas on DIII-D
Nuclear Materials and Energy
title Results from core-edge experiments in high Power, high performance plasmas on DIII-D
title_full Results from core-edge experiments in high Power, high performance plasmas on DIII-D
title_fullStr Results from core-edge experiments in high Power, high performance plasmas on DIII-D
title_full_unstemmed Results from core-edge experiments in high Power, high performance plasmas on DIII-D
title_short Results from core-edge experiments in high Power, high performance plasmas on DIII-D
title_sort results from core edge experiments in high power high performance plasmas on diii d
url http://www.sciencedirect.com/science/article/pii/S2352179116302526
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