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- Publications
- Influence
Equilibrium properties of spherical torus plasmas in NSTX
- S. Sabbagh, S. Kaye, +22 authors W. Zhu
- Physics
- 1 November 2001
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 of… Expand
A component test facility based on the spherical tokamak
- Y. K. M. Peng, P. Fogarty, +20 authors Y. Takase
- Physics
- 7 November 2005
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 7… Expand
Worldwide collaborative efforts in plasma control software development
- B. Penaflor, J. R. Ferron, +7 authors D. Gates
- Computer Science
- 1 April 2008
TLDR
H-mode pedestal, ELM and power threshold studies in NSTX
- R. Maingi, C. Bush, +24 authors D. Stutman
- Physics
- 1 September 2005
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 high… Expand
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=120-180… Expand
H-modes on COMPASS-D with high-power ECRH
- S. J. Fielding, M. Valovic, +5 authors Ecrh Teams
- Physics
- 1 May 1998
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 the… Expand
Overview of L–H power threshold studies in NSTX
- R. Maingi, S. Kaye, +13 authors J. R. Wilson
- Materials Science
- 28 May 2010
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 a… Expand
Overview of the physics and engineering design of NSTX upgrade
- J. Menard, S. Gerhardt, +43 authors A. Zolfaghari
- Physics
- 1 August 2012
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 a… Expand
The effect of lithium surface coatings on plasma performance in the National Spherical Torus Experiment
- H. Kugel, M. Bell, +27 authors L. Zakharov
- Physics
- 2 May 2008
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 coatings… Expand
Active stabilization of the resistive-wall mode in high-beta, low-rotation plasmas.
- S. Sabbagh, R. Bell, +7 authors H. Yuh
- Physics, Medicine
- Physical review letters
- 28 July 2006
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 in… Expand