Response of NSTX liquid lithium divertor to high heat loads

ELM induced divertor heat loads on TCV

Results are presented for heat loads at the TCV outer divertor target during ELMing H-mode using a fast IR camera. Benefitting from a recent surface cleaning of the entire first wall graphite armour, a comparison of the transient thermal response of freshly cleaned and untreated tile surfaces (coated with thick codeposited layers) has been performed. The latter routinely exhibit temperature tra...

Integrated models to study the impact of ELMs and disruptions on lithium in the NSTX divertor

Lithium as a potential plasma-facing material has many attractive features including a reduction in recycling of hydrogenic species and ability to withstand high heat and neutron fluxes in fusion reactors. Recent analysis of the National Spherical Torus eXperiment (NSTX) device has shown significant and recurring benefits of lithium coatings on plasma-facing components performance. To self-cons...

"Snowflake" divertor configuration in NSTX

National Spherical Torus Experiment Liquid Lithium Divertor

Recent NSTX high power divertor experiments have shown significant and recurring benefits of solid lithium coatings on PFC’s to the performance of divertor plasmas in both Land Hmode confinement regimes heated by high-power neutral beams. The next step in this work is installation of a liquid lithium divertor (LLD) to achieve density control for inductionless current drive capability (e.g., abo...

Analysis of sweeping heat loads on divertor plate materials

The heat flux on the divertor plate of a fusion reactor is probably one of the most limiting constraints on its lifetime. The current heat flux profile on the outer divertor plate of a device like the International Thermonuclear Experimental Reactor (ITER) is highly peaked with narrow profile. The peak heat flux can be as high as 30-40 MW/m 2 with full width at half maximum (FWHM) of the order ...