Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI

RE Nygren, FL Tabarés - Nuclear Materials and Energy, 2016 - Elsevier
This review of the potential of robust plasma facing components (PFCs) with liquid surfaces
for applications in future D/T fusion device summarizes the critical issues for liquid surfaces …

A long-pulse high-confinement plasma regime in the Experimental Advanced Superconducting Tokamak

J Li, HY Guo, BN Wan, XZ Gong, YF Liang, GS Xu… - Nature physics, 2013 - nature.com
High-performance and long-pulse operation is a crucial goal of current magnetic fusion
research. Here, we demonstrate a high-confinement plasma regime known as an H-mode …

An overview of lithium experiments on HT-7 and EAST during 2012

JS Hu, J Ren, Z Sun, GZ Zuo, QX Yang, JG Li… - Fusion Engineering and …, 2014 - Elsevier
In 2012, lithium coating with an upgraded system on EAST, the first application of lithium
granules injection for ELMs pacing on EAST, and the first flowing lithium limiter experiments …

Enhanced H-mode pedestals with lithium injection in DIII-D

TH Osborne, GL Jackson, Z Yan, R Maingi… - Nuclear …, 2015 - iopscience.iop.org
Periods of edge localized mode (ELM)-free H-mode with increased pedestal pressure and
width were observed in the DIII-D tokamak when density fluctuations localized to the region …

Current drive at plasma densities required for thermonuclear reactors

R Cesario, L Amicucci, A Cardinali, C Castaldo… - Nature …, 2010 - nature.com
Progress in thermonuclear fusion energy research based on deuterium plasmas
magnetically confined in toroidal tokamak devices requires the development of efficient …

First results of the use of a continuously flowing lithium limiter in high performance discharges in the EAST device

JS Hu, GZ Zuo, J Ren, QX Yang, ZX Chen, H Xu… - Nuclear …, 2016 - iopscience.iop.org
As an alternative choice of solid plasma facing components (PFCs), flowing liquid lithium
can serve as a limiter or divertor PFC and offers a self-healing surface with acceptable heat …

The effect of progressively increasing lithium coatings on plasma discharge characteristics, transport, edge profiles and ELM stability in the National Spherical Torus …

R Maingi, DP Boyle, JM Canik, SM Kaye… - Nuclear …, 2012 - iopscience.iop.org
Lithium wall coatings have been shown to reduce recycling, suppress edge-localized modes
(ELMs), and improve energy confinement in the National Spherical Torus Experiment …

Plasma response to lithium-coated plasma-facing components in the National Spherical Torus Experiment

MG Bell, HW Kugel, R Kaita, LE Zakharov… - Plasma Physics and …, 2009 - iopscience.iop.org
Abstract Experiments in the National Spherical Torus Experiment (NSTX) have shown
beneficial effects on the performance of divertor plasmas as a result of applying lithium …

Lithium, a path to make fusion energy affordable

A De Castro, C Moynihan, S Stemmley, M Szott… - Physics of …, 2021 - pubs.aip.org
In this tutorial article, we review the technological, physics, and economic basis for a
magnetic fusion device utilizing a flowing liquid lithium divertor (molten metal velocity in the …

Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas

MA Jaworski, T Abrams, JP Allain, MG Bell… - Nuclear …, 2013 - iopscience.iop.org
Liquid metal plasma-facing components (PFCs) have been proposed as a means of solving
several problems facing the creation of economically viable fusion power reactors. To date …