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 |
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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 |
Funding
Manuscript received July 19, 2019; revised December 9, 2019; accepted January 3, 2020. Date of publication April 14, 2020; date of current version June 10, 2020. This work was supported by the U.S. Department of Energy under Contract DE-AC02-09CH11466, Contract DE-AC05-00OR22725, Contract DE-AC52-07NA27344, Contract DE-SC0019308, and Contract DE-SC0019239. This manuscript has been authored in part by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). The review of this article was arranged by Senior Editor G. H. Neilson. (Corresponding author: Drew Elliott.) Drew Elliott and Theodore M. Biewer are with the Oak Ridge National Laboratory, Oak Ridge, TN 37830 USA (e-mail: [email protected]).
Keywords
- Fusion
- LTX-beta
- Lithium Tokamak Experiment (LTX)
- lithium
- neutral beam injection (NBI)
- spherical toakamak
- tokamak