An 0D model is proposed that makes it possible to estimate the limiting stationary heat loads to the targets covered with liquid lithium (LL) layer, taking into account the effects of vapor shielding by sputtered and evaporated LL and hydrogen recycling. Several models of cooled target substrates are considered in which the LL layer facing the plasma is placed. For the considered substrate models, a parametric analysis of the tolerable stationary heat loads to the target on the substrate thickness, the effective cooling energy per particle of sputtered lithium, and the lithium prompt redeposition factor was carried out. It is shown that, at a small substrate thickness, the choice of the substrate model has a significant impact on the tolera...
Samples of the NSTX Liquid Lithium Divertor (LLD) with and without an evaporative Li coating were di...
Considering that solutions for the steady-state power exhaust problem in future fusion reactors (e.g...
The behaviour of the scrape-off plasma of the European tokamak DEMO (DEMOnstration tokamak of the ec...
To develop realistic liquid lithium divertors for future fusion reactors, this paper aims to improve...
A model is formulated to make a first estimate of the maximum tolerable power of liquid lithium dive...
In this work, a conceptual design for a pre-filled liquid lithium divertor target for the National S...
In a tokamak a part of the energy is deposited as heat in the region called divertor. Liquid metal ...
Two small liquid metal targets based on the capillary porous structure were exposed to the divertor ...
Developing a reactor compatible divertor has been identified as a particularly challenging technolog...
The Liquid Lithium Divertor (LLD) on NSTX will be the first test of a fully-toroidal liquid lithium ...
Solutions for the steady-state power exhaust problem in future fusion reactors (e.g. DEMO) are not a...
The use of low atomic number liquid metals has been shown to have the potential to solve many of the...
Samples of the NSTX Liquid Lithium Divertor (LLD) with and without an evaporative Li coating were di...
Considering that solutions for the steady-state power exhaust problem in future fusion reactors (e.g...
The behaviour of the scrape-off plasma of the European tokamak DEMO (DEMOnstration tokamak of the ec...
To develop realistic liquid lithium divertors for future fusion reactors, this paper aims to improve...
A model is formulated to make a first estimate of the maximum tolerable power of liquid lithium dive...
In this work, a conceptual design for a pre-filled liquid lithium divertor target for the National S...
In a tokamak a part of the energy is deposited as heat in the region called divertor. Liquid metal ...
Two small liquid metal targets based on the capillary porous structure were exposed to the divertor ...
Developing a reactor compatible divertor has been identified as a particularly challenging technolog...
The Liquid Lithium Divertor (LLD) on NSTX will be the first test of a fully-toroidal liquid lithium ...
Solutions for the steady-state power exhaust problem in future fusion reactors (e.g. DEMO) are not a...
The use of low atomic number liquid metals has been shown to have the potential to solve many of the...
Samples of the NSTX Liquid Lithium Divertor (LLD) with and without an evaporative Li coating were di...
Considering that solutions for the steady-state power exhaust problem in future fusion reactors (e.g...
The behaviour of the scrape-off plasma of the European tokamak DEMO (DEMOnstration tokamak of the ec...