The lithium tokamak experiment #2;LTX#3; is a modest-sized spherical tokamak #2;R0=0.4 m and a =0.26 m#3; designed to investigate the low-recycling lithium wall operating regime for magnetically confined plasmas. LTX will reach this regime through a lithium-coated shell internal to the vacuum vessel, conformal to the plasma last-closed-flux surface, and heated to 300-400 oC. This structure is highly conductive and not axisymmetric. The three-dimensional nature of the shell causes the eddy currents and magnetic fields to be three-dimensional as well. In order to analyze the plasma equilibrium in the presence of three-dimensional eddy currents, an extensive array of unique magnetic diagnostics has been implemented. Sensors are designed to sur...
Abstract. Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relat...
The Liquid Lithium Divertor (LLD) on NSTX will be the first test of a fully-toroidal liquid lithium ...
The current drive experiment-upgrade (CDX-U) device at the Princeton Plasma Physics Laboratory (PPPL...
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ∼ 3.4kG, ...
Liquid metal walls have the potential to solve first-wall problems for fusion reactors, such as heat...
The Lithium Tokamak Experiment (LTX) is a spherical tokamak designed to study the low-recycling regi...
The Lithium Tokamak Experiment (LTX) is a spherical tokamak designed to study the lowrecycling regim...
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ~ 3.4kG, ...
Abstract. The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R 0 = 0.4m, a = 0.26m, B ...
The Lithium Tokamak eXperiment (LTX) is a small, low aspect ratio tokamak, which is fitted with a st...
Liquid metal walls have been proposed to address the first wall challenge for fusion reactors. The L...
A flowing liquid lithium first wall or diverter target could virtually eliminate the concerns with p...
The COMPASS tokamak has been re-installed in IPP Prague after its transport from Culham in UK. A Dia...
The principal of the measurement of the radial current distribution in a Tokamak plasma, using a lit...
The doctoral thesis presents the diagnostic neutral lithium beam on the COMPASS tokamak in Prague. T...
Abstract. Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relat...
The Liquid Lithium Divertor (LLD) on NSTX will be the first test of a fully-toroidal liquid lithium ...
The current drive experiment-upgrade (CDX-U) device at the Princeton Plasma Physics Laboratory (PPPL...
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ∼ 3.4kG, ...
Liquid metal walls have the potential to solve first-wall problems for fusion reactors, such as heat...
The Lithium Tokamak Experiment (LTX) is a spherical tokamak designed to study the low-recycling regi...
The Lithium Tokamak Experiment (LTX) is a spherical tokamak designed to study the lowrecycling regim...
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R0 = 0.4m, a = 0.26m, BTF ~ 3.4kG, ...
Abstract. The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with R 0 = 0.4m, a = 0.26m, B ...
The Lithium Tokamak eXperiment (LTX) is a small, low aspect ratio tokamak, which is fitted with a st...
Liquid metal walls have been proposed to address the first wall challenge for fusion reactors. The L...
A flowing liquid lithium first wall or diverter target could virtually eliminate the concerns with p...
The COMPASS tokamak has been re-installed in IPP Prague after its transport from Culham in UK. A Dia...
The principal of the measurement of the radial current distribution in a Tokamak plasma, using a lit...
The doctoral thesis presents the diagnostic neutral lithium beam on the COMPASS tokamak in Prague. T...
Abstract. Use of a large-area liquid lithium limiter in the CDX-U tokamak produced the largest relat...
The Liquid Lithium Divertor (LLD) on NSTX will be the first test of a fully-toroidal liquid lithium ...
The current drive experiment-upgrade (CDX-U) device at the Princeton Plasma Physics Laboratory (PPPL...