A reliable calculation of neutron-induced activation of materials requires the inclusion of all kinematically allowed reactions and subsequent reaction chains. While neutron-induced reactions have been sufficiently covered in the past, sequential (x,n) reactions with charged particles x, produced in a first-step reaction, were neglected. To include this type of reaction three new libraries and a preparatory code were developed to produce pseudo cross sections for the European reference code FISPACT. Inventory calculations with the updated FISPACT code, done for all stable elements, showed for 30 elements an increase of at least one of the radiological quantities activity, dose rate and decay heat. Two types of candidate structural materials were investigated: Ferritic-martensitic steels and vanadium-based alloys. While V-Cr-Ti alloys without impurities are known to have far superior long-term activation properties, a realistic assumption of technically achievable amounts of tramp elements leads nearly to the same level of activation as for the optimized ferritic-martensitic steels.