Nuclear fusion power represents a possible secure and carbon-free energy source, offering a sustainable solution to future global energy demands. As of today, magnetic confinement fusion (MCF) is the most promising and investigated approach to employ thermonuclear fusion for large-scale energy production. Within this context, three-dimensional, non-axisymmetric magnetic devices called stellarators represent a promising pathway for steady-state reactor operation. In these devices, managing the high particle and energy fluxes that exit the confined plasma and enter the boundary region, the so-called Scrape-Off Layer (SOL), remains a critical challenge to ensure the integrity of plasma-facing components. The island divertor is a leading power exhaust concept for stellarators, utilizing intrinsic magnetic islands to safely channel power and particles in the SOL to a localized surface, the divertor target plates.