Progress towards high performance plasmas in the National Spherical Torus Experiment (NSTX)

Journal Article · Sat Jan 01 00:00:00 EST 2005 · Nuclear Fusion

DOI:https://doi.org/10.1088/0029-5515/45/10/S14· OSTI ID:1081826

Kaye, S. ^[1]; Peng, Yueng Kay Martin ^[2]

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1. Princeton Plasma Physics Laboratory (PPPL)
2. ORNL

The major objective of the National Spherical Torus Experiment (NSTX) is to understand basic toroidal confinement physics at low aspect ratio and high T in order to advance the spherical torus (ST) concept. In order to do this, NSTX utilizes up to 7.5MW of neutral beam injection, up to 6MW of high harmonic fast waves (HHFWs), and it operates with plasma currents up to 1.5MA and elongations of up to 2.6 at a toroidal field up to 0.45 T. New facility, and diagnostic and modelling capabilities developed over the past two years have enabled the NSTX research team to make significant progress towards establishing this physics basis for future ST devices. Improvements in plasma control have led to more routine operation at high elongation and high T (up to 40%) lasting for many energy confinement times. T can be limited by either internal or external modes. The installation of an active error field (EF) correction coil pair has expanded the operating regime at low density and has allowed for initial resonant EF amplification experiments. The determination of the confinement and transport properties of NSTX plasmas has benefitted greatly from the implementation of higher spatial resolution kinetic diagnostics. The parametric variation of confinement is similar to that at conventional aspect ratio but with values enhanced relative to those determined from conventional aspect ratio scalings and with a BT dependence. The transport is highly dependent on details of both the flow and magnetic shear. Core turbulence was measured for the first time in an ST through correlation reflectometry. Non-inductive start-up has been explored using PF-only and transient co-axial helicity injection techniques, resulting in up to 140 kA of toroidal current generated by the latter technique. Calculated bootstrap and beam-driven currents have sustained up to 60% of the flat-top plasma current in NBI discharges. Studies of HHFW absorption have indicated parametric decay of the wave and associated edge thermal ion heating. Energetic particle modes, most notably toroidal Alfv en eigenmodes and fishbone-like modes result in fast particle losses, and these instabilities may affect fast ion confinement on devices such as ITER. Finally, a variety of techniques has been developed for fuelling and power and particle control.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1081826
• Journal Information: Nuclear Fusion, Vol. 45, Issue 10; ISSN 0029--5515
• Country of Publication: United States
• Language: English