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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
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
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
ALPHA-PARTICLE-DRIVEN TOROIDAL ALFVEN EIGENMODES IN THE TOKAMAK FUSION TEST REACTOR
- R. Nazikian, G. Fu, +26 authors D. Spong
- Physics
- 1 April 1997
Alpha-particle-driven toroidal Alfven eigenmodes (TAEs) have been observed for the first time in deuterium-tritium (D-T) plasmas on the tokamak fusion test reactor (TFTR). These modes are observed… Expand
Advances in global MHD mode stabilization research on NSTX
- S. Sabbagh, J. Berkery, +12 authors H. Yuh
- Physics
- 1 February 2010
Stabilizing modes that limit plasma beta and reduce their deleterious effect on plasma rotation are key goals for the efficient operation of a fusion reactor. Passive stabilization and active control… Expand
NSTX plasma operation with a Liquid Lithium Divertor
- H. Kugel, J. Allain, +27 authors L. Zakharov
- Materials Science
- 1 October 2012
Abstract NSTX 2010 experiments were conducted using a molybdenum Liquid Lithium Divertor (LLD) surface installed on the outer part of the lower divertor. This tested the effectiveness of maintaining… Expand
Overview of results from the National Spherical Torus Experiment (NSTX)
The mission of the National Spherical Torus Experiment (NSTX) is the demonstration of the physics basis required to extrapolate to the next steps for the spherical torus (ST), such as a plasma facing… Expand
Progress toward commissioning and plasma operation in NSTX-U
- M. Ono, J. Chrzanowski, +39 authors A. Zolfaghari
- Physics, Environmental Science
- 5 June 2015
The National Spherical Torus Experiment-Upgrade (NSTX-U) is the most powerful spherical torus facility at PPPL, Princeton USA. The major mission of NSTX-U is to develop the physics basis for an… Expand
Electromagnetic transport from microtearing mode turbulence.
- W. Guttenfelder, J. Candy, +7 authors H. Yuh
- Physics, Medicine
- Physical review letters
- 14 April 2011
This Letter presents nonlinear gyrokinetic simulations of microtearing mode turbulence. The simulations include collisional and electromagnetic effects and use experimental parameters from a high-β… Expand
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