A model is formulated to make a first estimate of the maximum tolerable power of liquid lithium (Li) divertor targets, and to gain insight into their behaviour in terms of Li loss rate and surface temperature. The model, formulated as a simple analytical expression, states that the incoming power is balanced by heat conduction through the target and by the Li which dissipates energy via evaporation, radiation and ion-neutral friction. A target is considered to fail when the net Li loss flux from the surface exceeds the available supply. The model is evaluated over a range of input parameters: Li supply rate, surface layer thickness, redeposition coefficient, and dissipated energy per Li particle lost to the plasma. Based on the results, fir...
Considering that solutions for the steady-state power exhaust problem in future fusion reactors (e.g...
Liquid metal walls have the potential to solve first-wall problems for fusion reactors, such as heat...
Fusion power plants are likely to require near complete detachment of the divertor plasma from the d...
A model is formulated to make a first estimate of the maximum tolerable power of liquid lithium dive...
To develop realistic liquid lithium divertors for future fusion reactors, this paper aims to improve...
An 0D model is proposed that makes it possible to estimate the limiting stationary heat loads to the...
Developing a reactor compatible divertor has been identified as a particularly challenging technolog...
Liquid lithium (Li) can partly ameliorate lifetime and power-exhaust issues of plasma facing compone...
In this work, a conceptual design for a pre-filled liquid lithium divertor target for the National S...
The Liquid Lithium Divertor (LLD) on NSTX will be the first test of a fully-toroidal liquid lithium ...
In a tokamak a part of the energy is deposited as heat in the region called divertor. Liquid metal ...
A fusion reactor divertor must withstand heat flux densities <10 MW m-2. Additionally, it may hav...
The use of low atomic number liquid metals has been shown to have the potential to solve many of the...
Considering that solutions for the steady-state power exhaust problem in future fusion reactors (e.g...
Liquid metal walls have the potential to solve first-wall problems for fusion reactors, such as heat...
Fusion power plants are likely to require near complete detachment of the divertor plasma from the d...
A model is formulated to make a first estimate of the maximum tolerable power of liquid lithium dive...
To develop realistic liquid lithium divertors for future fusion reactors, this paper aims to improve...
An 0D model is proposed that makes it possible to estimate the limiting stationary heat loads to the...
Developing a reactor compatible divertor has been identified as a particularly challenging technolog...
Liquid lithium (Li) can partly ameliorate lifetime and power-exhaust issues of plasma facing compone...
In this work, a conceptual design for a pre-filled liquid lithium divertor target for the National S...
The Liquid Lithium Divertor (LLD) on NSTX will be the first test of a fully-toroidal liquid lithium ...
In a tokamak a part of the energy is deposited as heat in the region called divertor. Liquid metal ...
A fusion reactor divertor must withstand heat flux densities <10 MW m-2. Additionally, it may hav...
The use of low atomic number liquid metals has been shown to have the potential to solve many of the...
Considering that solutions for the steady-state power exhaust problem in future fusion reactors (e.g...
Liquid metal walls have the potential to solve first-wall problems for fusion reactors, such as heat...
Fusion power plants are likely to require near complete detachment of the divertor plasma from the d...