Plasma detachment in tokamaks is useful for reducing heat flux to the target. It involves interactions of the plasma with impurities and
neutral particles, leading to significant losses of plasma power, momentum, and particles. Accurate mapping of plasma emissivity
in the divertor and X-point region is essential for assessing the rel…
Accurate quantification of the power loss channels and overall power balance of the plasma is essential for the safe operation of current and future fusion devices. The relative magnitudes of core radiation, SOL radiation and divertor target heat loading are determining factors in both PFC design and plasma scenario design in the successful real…
The design and understanding of alternative divertor configurations may be crucial for achieving acceptable steady-state heat and particle material loads for magnetic confinement fusion reactors. Multiple x-point alternative divertor geometries such as Snowflakes and Xpoint targets have great potential in reducing power loads, but have not yet b…
