Divertor
A component in a fusion tokamak that uses magnetic null points (X-points) to extract helium ash and heat exhaust from the plasma edge.
Governing formula
Magnetic X-point Separatrix Boundary Geometry
SI unit
MW/m² (Heat Flux Capacity)
In depth
Divertor field coils create a magnetic separatrix boundary, directing scrape-off layer (SOL) plasma away from main chamber walls onto armored target plates (tungsten or carbon).
Examples in the real world
ITER's full-tungsten armored divertor target designed to withstand steady heat loads up to 10 MW/m².