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NSTX

Spherical Tokamak

Associated Organization:

Princeton Plasma Physics Laboratory

Publications

Modeling temperature profiles in the pedestal of NSTX with reduced models

Nuclear Fusion, 2026

Fast-ion enhanced modeling of neoclassical tearing modes at NSTX and DIII-D

Plasma Physics and Controlled Fusion, 2026

Electron-Scale-Driven Turbulence by Negative-Density-Gradient in NSTX

arXiv (physics.plasm-ph), 2026

Interpretation of high-harmonic fast-wave propagation in the scrape-off layer of NSTX-U as a geometrically bounded-waveguide mode

Journal of Plasma Physics, 2026

The impact of kinetic and global effects on ideal ballooning 2nd stable pedestals of conventional and low aspect-ratio tokamaks

Nuclear Fusion, 2026

Transition to ELM-free improved H-mode by lithium deposition on NSTX graphite divertor surfaces

Journal of Nuclear Materials, 2009

Overview of the Initial NSTX Experimental Results

Years Operated

1999 - 2012

The National Spherical Torus Experiment (NSTX) was a spherical tokamak built at PPPL. It began operations in February of 1999. The NSTX device was built with the objective of studying the behavior of the spherical tokamak configuration in the mega ampere regime. It was designed to work with a confinement magnetic field of 0.55 T and to reach a central temperature between 1 to 3 keV. In 2012, NSTX ended operations to undergo a mayor upgrade. Once this upgrade was finished, the device became NSTX-U.

  • NSTX image 1

Publications

Modeling temperature profiles in the pedestal of NSTX with reduced models

Nuclear Fusion, 2026

Fast-ion enhanced modeling of neoclassical tearing modes at NSTX and DIII-D

Plasma Physics and Controlled Fusion, 2026

Electron-Scale-Driven Turbulence by Negative-Density-Gradient in NSTX

arXiv (physics.plasm-ph), 2026

Interpretation of high-harmonic fast-wave propagation in the scrape-off layer of NSTX-U as a geometrically bounded-waveguide mode

Journal of Plasma Physics, 2026

The impact of kinetic and global effects on ideal ballooning 2nd stable pedestals of conventional and low aspect-ratio tokamaks

Nuclear Fusion, 2026

Transition to ELM-free improved H-mode by lithium deposition on NSTX graphite divertor surfaces

Journal of Nuclear Materials, 2009

Overview of the Initial NSTX Experimental Results

Years Operated

1999 - 2012

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