Abstract
LTX-β, the upgraded Lithium Tokamak Experiment, recently began its first campaign with a goal to study the transport properties of gradient-free electron temperature profile equilibria with increased toroidal field and neutral beam injection. The temperature-gradient-free equilibria in LTX were enabled by the lithium plasma-facing surface. To make the lithium surface conditions more consistent for LTX-β, a new, faster lithium evaporator system has been developed. The toroidal magnetic field has been nearly doubled to ≥0.3 T. Auxiliary heating and fueling with a high flux (35 A, 20 kV) neutral beam has begun. The beam provides core fueling without cold edge neutrals, to test whether flat temperature profiles can be sustained, and makes possible core ion temperature measurements via charge exchange recombination spectroscopy. Neutral beam fueling has been demonstrated with increases in line-integrated density. The coupling of the beam matches well with NUBEAM predictions for shine through. Improved performance has been observed following lithium evaporative coatings and an increase in field strength.
Original language | English (US) |
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Article number | 9067051 |
Pages (from-to) | 1382-1387 |
Number of pages | 6 |
Journal | IEEE Transactions on Plasma Science |
Volume | 48 |
Issue number | 6 |
DOIs | |
State | Published - Jun 2020 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Condensed Matter Physics
Keywords
- Fusion
- LTX-beta
- Lithium Tokamak Experiment (LTX)
- lithium
- neutral beam injection (NBI)
- spherical toakamak
- tokamak