[en] The protection of the first wall by ceramic coatings against melting by plasma disruptions, was studied by computational heat transfer analysis. The compilation of a European Fusion File of nuclear data in its first version is presented. A specific contribution is the revision of the lead cross sections for (n,n¹), (n,2n) and (n,3n) reactions. The activations of neutron flux monitors for the JET neutron diagnostics system were recalculated using a 3D model of the torus and its D-shaped plasma. Calculations of nuclear heating and radiation damage parameters were performed for the lithium-lead blanket concept in the NET-II torus geometry, using a simplified blanket model. Results of low cycle fatigue and tensile testing of the reference heat of stainless steel 316 L is reported. The latter including the effect of a HFR-irradiation to 5 dpa and 40 appm helium. The design of a 12 Tesla niobium-tin insert coil for the SULTAN test facility is presented, including the start of its conductor development. The next step will be the development of a 32 kA (11 Tesla) conductor for the toroidal field coils of NET, as regulated under magnet system studies. The results are presented of two EXOTIC experiments: irradiation of ceramic lithium compounds for tritium breeding. (Auth.)