The diverter area of future fusion reactors will have to withstand extremely challenging conditions in terms of heat flux, particle flux, thermal cycling, and a nuclear environment. For example, the diverter of ITER is expected to need replacing every two years. Understanding the effects different plasma conditions can have on a divertor technology is crucial to ensuring reasonable lifespan of this component.
The envisioned material for most divertor technologies, including that of ITER, is tungsten. Recent experiments have published seemingly contradictory results when exploring the effects of plasma conditions on this material's recrystallization dynamics. This thesis aims to further explore this question in order to clarify these effects.
The question this research wants to answer is, what influence H plasma has on the recrystallization behavior of W compared to a different plasma, more specifically He (Helium) plasma and, if possible, Ar (Argon) plasma under the same thermal conditions.