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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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A component test facility based on the spherical tokamak
Recent experiments (Synakowski et al 2004 Nucl. Fusion 43 1648, Lloyd et al 2004 Plasma Phys. Control. Fusion 46 B477) on the Spherical Tokamak (or Spherical Torus, ST) (Peng 2000 Phys. Plasmas 7Expand
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Worldwide collaborative efforts in plasma control software development
This presentation will describe the DIII-D collaborations with various tokamak experiments throughout the world which have adapted custom versions of the plasma control system (PCS) software for their own use. Expand
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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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Neoclassical islands on COMPASS-D
Neoclassical magnetic islands are observed to limit the achievable beta in COMPASS-D low collisionality single null divertor tokamak plasmas with ITER-like geometry (R0=0.56 m, B0=1.2 T, Ip=120-180Expand
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H-modes on COMPASS-D with high-power ECRH
Recent high-power electron-cyclotron resonance heating (ECRH) H-mode experiments on COMPASS-D have used fundamental high-power ECRH to access high densities. Within the operating range set by theExpand
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Overview of L–H power threshold studies in NSTX
A summary of results from recent L–H power threshold (PLH) experiments in the National Spherical Torus Experiment is presented. First PLH (normalized linearly by plasma density) was found to be aExpand
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Overview of the physics and engineering design of NSTX upgrade
The spherical tokamak (ST) is a leading candidate for a Fusion Nuclear Science Facility (FNSF) due to its compact size and modular configuration. The National Spherical Torus eXperiment (NSTX) is aExpand
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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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Active stabilization of the resistive-wall mode in high-beta, low-rotation plasmas.
The resistive-wall mode is actively stabilized in the National Spherical Torus Experiment in high-beta plasmas rotating significantly below the critical rotation speed for passive stability and inExpand
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