The Lithium Tokamak eXperiment (LTX) is a small, low aspect ratio tokamak, which is fitted with a stainless steel-clad copper liner, conformal to the last closed flux surface. The liner can be heated to 350{degree}C. Several gas fueling systems, including supersonic gas injection, and molecular cluster injection have been studied, and produce fueling efficiencies up to 35%. Discharges are strongly affected by wall conditioning. Discharges without lithium wall coatings are limited to plasma currents of order 10 kA, and discharge durations of order 5 msec. With solid lithium coatings discharge currents exceed 70 kA, and discharge durations exceed 30 msec. Heating the lithium wall coating, however, results in a prompt degradation of the discha...
The Lithium Tokamak Experiment (LTX) is a spherical tokamak designed to study the lowrecycling regim...
Liquid metal walls have the potential to solve first-wall problems for fusion reactors, such as heat...
Use of a large-area liquid lithium surface as a first wall has significantly improved the plasma per...
Lithium plasma facing components reduce the flux of “recycled ” particles entering the plasma edge f...
Liquid metal walls have been proposed to address the first wall challenge for fusion reactors. The L...
The use of flowing liquid lithium as a first wall for a reactor has potentially attractive physics a...
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ∼ 3.4kG, ...
Part of the development of liquid metals as a first wall or divertor for reactor applications must i...
Abstract. CDX-U has been operated with the vacuum vessel wall and limiter surfaces nearly completely...
Abstract. Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relat...
Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relative increa...
Recent experiments in the Current Drive Experiment-Upgrade provide a first-ever test of large area l...
The use of low atomic number liquid metals has been shown to have the potential to solve many of the...
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ~ 3.4kG, ...
Abstract. Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relat...
The Lithium Tokamak Experiment (LTX) is a spherical tokamak designed to study the lowrecycling regim...
Liquid metal walls have the potential to solve first-wall problems for fusion reactors, such as heat...
Use of a large-area liquid lithium surface as a first wall has significantly improved the plasma per...
Lithium plasma facing components reduce the flux of “recycled ” particles entering the plasma edge f...
Liquid metal walls have been proposed to address the first wall challenge for fusion reactors. The L...
The use of flowing liquid lithium as a first wall for a reactor has potentially attractive physics a...
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ∼ 3.4kG, ...
Part of the development of liquid metals as a first wall or divertor for reactor applications must i...
Abstract. CDX-U has been operated with the vacuum vessel wall and limiter surfaces nearly completely...
Abstract. Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relat...
Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relative increa...
Recent experiments in the Current Drive Experiment-Upgrade provide a first-ever test of large area l...
The use of low atomic number liquid metals has been shown to have the potential to solve many of the...
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ~ 3.4kG, ...
Abstract. Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relat...
The Lithium Tokamak Experiment (LTX) is a spherical tokamak designed to study the lowrecycling regim...
Liquid metal walls have the potential to solve first-wall problems for fusion reactors, such as heat...
Use of a large-area liquid lithium surface as a first wall has significantly improved the plasma per...