Avoiding excessive structure heat loads in future fusion tokamaks is regarded as one of the greatest design challenges. In this paper, we aim at developing a tool to study how the severe divertor heat loads can be mitigated by reconfiguring the magnetic confinement. For this purpose, a free boundary equilibrium code is integrated with a plasma edge transport code to work in an automated fashion. Next, a practical and efficient adjoint based sensitivity calculation is proposed to evaluate the sensitivities of the integrated code. The sensitivity calculation is finally applied to a realistic test case and compared with finite difference sensitivity calculations.