A magnetic field configuration affecting the edge of the confinement region, designed to divert impurities and helium ash to a target chamber. Often this chamber is also called ‘divertor’.
Handling the heat fluxes at the divertor of fusion power plants is one focus of fusion research. It is tackled by developing more resistant materials and by developing magnetic configurations (e.g., snowflake and Super-x divertor) that reduce the heat load at the divertor.
The snowflake divertor employs a more advanced magnetic field configuration which flares the hot plasma at the divertor surface and reduces the residual heat flux per wall area. The technique has the potential to create heat loads that can be tolerated by existing materials.
A divertor design in which the power per unit area striking material surfaces is reduced greatly. It requires a set of divertor coils that extends and controls a long plume of exhaust plasma. The length of the plume allows high radiative cooling before the plasma reaches the target.