High confinement/high radiated power H-mode experiments in Alcator C-Mod and consequences for International Thermonuclear Experimental Reactor (ITER) QDT = 10 operation
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- A. Loarte
- ITER Organization, Route de Vinon sur Verdon 1 , 13115 Saint Paul Lez Durance, France
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- J. W. Hughes
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
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- M. L. Reinke
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
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- J. L. Terry
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
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- B. LaBombard
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
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- D. Brunner
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
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- M. Greenwald
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
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- B. Lipschultz
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
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- Y. Ma
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
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- S. Wukitch
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
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- S. Wolfe
- Plasma Science and Fusion Centre, Massachusetts Institute of Technology 2 , Cambridge, Massachusetts 02139, USA
説明
<jats:p>Experiments in Alcator C-Mod in (Enhanced D-alpha) EDA H-modes with extrinsic impurity seeding (N2, Ne, and Ar) have demonstrated a direct correlation between plasma energy confinement and edge power flow, achieving values of H98 ≥ 1 for edge power flows only marginally exceeding the scaled power for access to H-mode confinement in these conditions. For lower Z impurity seeding (N2 and Ne), plasmas with high energy confinement are obtained with a radiative power fraction of 85% or larger and a reduction of the peak heat flux at the divertor by more than a factor of 5 compared to similar attached conditions. The H-mode plasmas thus achieved in Alcator C-Mod meet or exceed the requirements both in terms of divertor heat flux handling and energy confinement for ITER QDT = 10 operation and with an edge power flow only marginally above the H-mode threshold power (by 1.0–1.4) as expected in ITER.</jats:p>
収録刊行物
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- Physics of Plasmas
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Physics of Plasmas 18 (5), 2011-04-22
AIP Publishing