Central investigations and evaluations of manufacturing and operational defects of pressurized components in nuclear power plants. Summary of technical reports 1.3, 2.6, 2.7, 3.1, 3.4

This report contains the content of five technical report. 1. Long term annealing reactor pressure vessel steels and their weld-simulated heat affected zones (22 NiMoCr 3 7 and 20 MnMoNi 5 5 steels); 2. Transmission electron microscopy investigations with regard to chromium depletion at grain boundaries in heat affected zones of austenitic weldments (X10 CrNiTi 18 9 steel = 1.4541); 3. On the influence of an inside grinding of weldments of material 1.4541 on the formation of intergranular cracks; 4. Investigations with respect to strain-induced corrosion cracking on specimens taken from a high-pressure preheater of a BWR plant; 5. Investigation of the crack growth zone from the austenitic cladding to the ferritic base material of a reactor pressure vessel