Abstract
A 0D circuit model for predicting Ip(t) in Local Helicity Injection (LHI) discharges is developed. Analytic formulas for estimating the surface ?ux of fnite-A plasmas developed by Hirshman and Neilson (1986 Phys. Fluids 29 790) are modifed and expanded to treat highly shaped, ultralow-A tokamak geometry using a database of representative equilibria. Model predictions are compared to sample LHI discharges in the A ∼ 1 Pegasus spherical tokamak, and are found to agree within 15% of experimental Ip(t). High performance LHI discharges are found to follow the Taylor relaxation current limit for approximately the frst half of the current ramp, or Ip ≲ 75 kA. The second half of the current ramp follows a limit imposed by power-balance as plasmas expand from high-A to ultralow-A. This shape evolution generates a signifcant drop in external plasma inductance, effectively using the plasma's initially high inductance to drive the current ramp and provide >70% of the current drive V-s. Projections using this model indicate the relative in?uences of higher helicity input rate and injector current on the attainable total plasma current.
Original language | English |
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Article number | 076011 |
Journal | Nuclear Fusion |
Volume | 58 |
Issue number | 7 |
DOIs | |
State | Published - May 15 2018 |
Funding
The authors thank: B.A. Kujak-Ford, B.T. Lewicki, and G.R. Winz for their technical assistance; D.J. Schlossberg, G.M. Bodner, T.M. Townsend, and D.M. Kreite for their support in experimental operations; and C.J. Everson and K.E. Thome for their work supporting the development and verification of the ShapeFIT boundary reconstruction code. This material is based upon work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, under Award Numbers DE-FG02-96ER54375 and DE-SC0006928.
Keywords
- Plasma startup
- Taylor relaxation
- current drive
- helicity injection
- spherical tokamaks
- tokamaks