Particle control and plasma performance in the Lithium Tokamak eXperiment
The Lithium Tokamak eXperiment is a small, low aspect ratio tokamak [Majeski et al., Nucl.
Fusion 49, 055014 (2009)], which is fitted with a stainless steel-clad copper liner, conformal …
Fusion 49, 055014 (2009)], which is fitted with a stainless steel-clad copper liner, conformal …
Results and future plans of the Lithium Tokamak eXperiment (LTX)
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with the unique capability of
studying the low-recycling regime by coating nearly 90% of the first wall with lithium in either …
studying the low-recycling regime by coating nearly 90% of the first wall with lithium in either …
[HTML][HTML] High performance discharges in the Lithium Tokamak eXperiment with liquid lithium walls
JC Schmitt, RE Bell, DP Boyle, B Esposti, R Kaita… - Physics of …, 2015 - pubs.aip.org
The first-ever successful operation of a tokamak with a large area (40% of the total plasma
surface area) liquid lithium wall has been achieved in the Lithium Tokamak eXperiment …
surface area) liquid lithium wall has been achieved in the Lithium Tokamak eXperiment …
Improved neutral and plasma density control with increasing lithium wall coatings in the Lithium Tokamak Experiment-β (LTX-β)
A comparison of three sets of Lithium Tokamak Experiment-β (LTX-β) discharges is
presented, each with progressively more lithium evaporatively deposited on the stainless …
presented, each with progressively more lithium evaporatively deposited on the stainless …
The impact of lithium wall coatings on NSTX discharges and the engineering of the Lithium Tokamak eXperiment (LTX)
R Majeski, H Kugel, R Kaita, S Avasarala… - Fusion engineering and …, 2010 - Elsevier
Recent experiments on the National Spherical Torus eXperiment (NSTX) have shown the
benefits of solid lithium coatings on carbon PFC's to diverted plasma performance, in both L …
benefits of solid lithium coatings on carbon PFC's to diverted plasma performance, in both L …
[HTML][HTML] Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment
High edge electron temperatures (200 eV or greater) have been measured at the wall-
limited plasma boundary in the Lithium Tokamak Experiment (LTX). Flat electron …
limited plasma boundary in the Lithium Tokamak Experiment (LTX). Flat electron …
Low recycling and high power density handling physics in the Current Drive Experiment-Upgrade with lithium plasma-facing components
The Current Drive Experiment-Upgrade [T. Munsat, PC Efthimion, B. Jones, R. Kaita, R.
Majeski, D. Stutman, and G. Taylor, Phys. Plasmas 9, 480 (2002)] spherical tokamak …
Majeski, D. Stutman, and G. Taylor, Phys. Plasmas 9, 480 (2002)] spherical tokamak …
Experiments with liquid metal walls: Status of the lithium tokamak experiment
Liquid metal walls have been proposed to address the first wall challenge for fusion
reactors. The lithium tokamak experiment (LTX) at the Princeton Plasma Physics Laboratory …
reactors. The lithium tokamak experiment (LTX) at the Princeton Plasma Physics Laboratory …
Observation of flat electron temperature profiles in the lithium tokamak experiment
It has been predicted for over a decade that low-recycling plasma-facing components in
fusion devices would allow high edge temperatures and flat or nearly flat temperature …
fusion devices would allow high edge temperatures and flat or nearly flat temperature …
Liquid lithium surface control and its effect on plasma performance in the HT-7 tokamak
Experiments with liquid lithium limiters (LLLs) have been successfully performed in HT-7
since 2009 and the effects of different limiter surface structures on the ejection of Li droplets …
since 2009 and the effects of different limiter surface structures on the ejection of Li droplets …