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NSTX-U

Spherical Tokamak

Associated Organization:

Princeton Plasma Physics Laboratory

Publications

Modeling of divertor heat flux limits and lithium vapor shielding in NSTX-U using UEDGE code

Nuclear Fusion, 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

Current ramp-up studies for NSTX-U in support of the development of non-inductive current ramp-up scenarios in STs

Nuclear Fusion, 2026

Development of flash lithium evaporators for NSTX-U

arXiv (physics.plasm-ph), 2026

Variations in lithium vapor cave performance predictions due to radial transport and recycling assumptions

Nuclear Fusion, 2026

Overview of the physics and engineering design of NSTX upgrade

2011 IEEE/NPSS 24th Symposium on Fusion Engineering, 2011

Years Operated

2016 - Present

The National Spherical Torus Experiment Upgrade (NSTX-U) is the name which NSTX, located at PPPL, is known after a major upgrade that began in 2012. The main upgrades made were a larger centerstack to improve the magnetic confinement, an additional neutral beam injector to improve heating and structural enhancements to adapt the coils and vacuum vessel to the new working conditions. NSTX-U was operational for 10 weeks in 2016 but a failure in one poloidal coil forced the device to shut down and undergo a major repair process. It is expected that NSTX-U will resume operations in 2021.

  • NSTX-U image 1
  • NSTX-U image 2
  • NSTX-U image 3
  • NSTX-U image 1
  • NSTX-U image 2
  • NSTX-U image 3

Publications

Modeling of divertor heat flux limits and lithium vapor shielding in NSTX-U using UEDGE code

Nuclear Fusion, 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

Current ramp-up studies for NSTX-U in support of the development of non-inductive current ramp-up scenarios in STs

Nuclear Fusion, 2026

Development of flash lithium evaporators for NSTX-U

arXiv (physics.plasm-ph), 2026

Variations in lithium vapor cave performance predictions due to radial transport and recycling assumptions

Nuclear Fusion, 2026

Overview of the physics and engineering design of NSTX upgrade

2011 IEEE/NPSS 24th Symposium on Fusion Engineering, 2011

Years Operated

2016 - Present

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