Modelling the exhaust power in future Tokamak reactors remains an open issue in fusion research, as the change in scale from ITER to power plants suggest that heat fluxes in the latter could exceed manageable material limits on the target plates. A potential solution to the exhaust problem is the development of so-called “alternative divertors configurations”, whose aim is to widen the plasma- wetted area to reduce the heat load at the targets by altering the magnetic geometry in the divertor area. This is achieved by increasing the flux expansion (X-divertor), sometimes in combination of placing the outer strike point at a larger radial location (super-X divertor), or increasing the number of strike points.