[en] For the water-cooled liquid lithium INTOR/NET blanket concept, a computational analysis was made of the shock wave loading and the dynamic response of the canister type module after sudden rupture of an internal coolant tube. A start was made, by definition of format and contents, for the compilation of an 'European Fusion File', as a basic tool for neutronics calculations on fusion reactor concepts and plasma physics experiments. To enable a better modelling of the JET torus in the calculations performed for neutron diagnostics, the code system FURNACE has been extended to handle three dimensional geometries. Tensile specimens of V-5%Ti alloy were exposed to liquid sodium during a five month period at 487, 572 and 664 deg C, in parallel to a 5 dpa irradiation also in liquid sodium in the HFR reactor. Tensile testing indicated a slight increase in UTS and yield strength and a lower ductility for the 664 deg C exposure. The radiation damage studies on the reference heat of ss 316L for the European fusion programme are extended towards weldings. In a preparative step, the microstructure of laser beam weldings in 6 mm plate was analysed. Progress on the feasibility study for an in-pile crack growth measurement rig is reported. A subsized prototype forced flow cooled niobium-tin superconductor for a 12 Tesla insert coil for the SULTAN test facility at Villigen was manufactured and tested. A study on upscaling towards the requirements of the NET toroidal field coils commenced. Progress towards a first irradiation experiment on tritium extraction from ceramic breeder material (lithium-aluminate and lithium-silicate) for the joint ECN/SCK/SNL project is reported