Nuclear fusion is considered as a future source of sustainable energy supply. Since the H-mode
discovery in ASDEX experiment Divertor I in 1982 the divertor has been an integral part of all
modern tokamaks and stellarators. The major goal of this thesis is to develop a feasible
divertor design for a fusion power plant to be built after ITER. The thesis describes the
approach in the conceptual development of a helium-cooled divertor and the methods of
verification and validation of the design.
