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Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER
A multi-machine database for the H-mode scrape-off layer power fall-off length, λq in JET, DIII-D, ASDEX Upgrade, C-Mod, NSTX and MAST has been assembled under the auspices of the InternationalExpand
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Exploration of spherical torus physics in the NSTX device
The National Spherical Torus Experiment (NSTX) is being built at the Princeton Plasma Physics Laboratory to test the fusion physics principles for the Spherical Torus (ST) concept at the MA level.Expand
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A long-pulse high-confinement plasma regime in the Experimental Advanced Superconducting Tokamak
A high-confinement plasma that is potentially useful for controlled fusion has now been sustained for over 30 s. The Experimental Advanced Superconducting Tokamak in Hefei, China, achieved thisExpand
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Pedestal stability comparison and ITER pedestal prediction
The pressure at the top of the edge transport barrier (or 'pedestal height') strongly impacts fusion performance, while large edge localized modes (ELMs), driven by the free energy in the pedestalExpand
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Analysis of a multi-machine database on divertor heat fluxesa)
A coordinated effort to measure divertor heat flux characteristics in fully attached, similarly shaped H-mode plasmas on C-Mod, DIII-D, and NSTX was carried out in 2010 in order to construct aExpand
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Equilibrium properties of spherical torus plasmas in NSTX
Research in NSTX has been conducted to establish spherical torus plasmas to be used for high ?, auxiliary heated experiments. This device has a major radius R0 = 0.86?m and a midplane halfwidth ofExpand
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Fusion nuclear science facilities and pilot plants based on the spherical tokamak
A fusion nuclear science facility (FNSF) could play an important role in the development of fusion energy by providing the nuclear environment needed to develop fusion materials and components. TheExpand
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H-mode pedestal, ELM and power threshold studies in NSTX
H-mode operation plays a crucial role in National Spherical Torus Experiment (NSTX) research, allowing higher beta limits due to reduced plasma pressure peaking, and long pulse operation due to highExpand
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The effect of lithium surface coatings on plasma performance in the National Spherical Torus Experiment
National Spherical Torus Experiment [which M. Ono et al., Nucl. Fusion 40, 557 (2000)] high-power divertor plasma experiments have shown, for the first time, that benefits from lithium coatingsExpand
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Edge localized modes: recent experimental findings and related issues
Edge localized mode (ELM) measurements in many tokamaks, including ASDEX-Upgrade, DIII-D, JET, JT-60U and MAST, are reviewed, which includes progress in experimental observations at the plasma edgeExpand
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