At present, several plasma boundary codes exist that attempt to describe the complex interactions in the divertor SOL (Scrape-Off Layer). The predictive capability of these edge codes is still very limited. Yet, in parallel to major efforts to mature edge codes, we face the design challenges for next step fusion devices. One of them is the design of the helium and heat exhaust system. In past automated design studies, results indicated large potential reductions in peak heat load by an increased magnetic flux divergence towards the target structures. In the present study, a free boundary magnetic equilibrium solver is included into the simulation chain to verify these tendencies. Additionally, we expanded the applicability of the automated design method by introducing advanced “adjoint” sensitivity computations. This method, inherited from airfoil shape optimization in aerodynamics, allows for a large number of design variables at no additional computational cost. Results are shown for a design application of the new WEST divertor.