Bruchmechanische Untersuchungen an bestrahltem Reaktordruckbehälterstahl der stillgelegten Reaktoren des KKW Greifswald

The paper presents initial results of the post mortem investigations performed on the reactor pres-sure vessels (RPV) of 1st generation WWER-440/V-230 reactors. Trepans were taken from the beltline weld and the base metal of the units 1, 2 and 4 RPVs, which represent different material conditions (irradiated, annealed and re-irradiated. From the trepans were manufactured standard SE(B) and Charpy V-notch specimens and investigated by Master Curve (MC) and Charpy V-notch testing. Specimens from defined locations through the thickness of the welding seam and the base metal ring were tested. The reference temperature T0 was calculated using the measured fracture toughness values KJc at brittle failure of the specimen. In addition Charpy V-notch specimens were tested in order to determine the Charpy-V ductile-to brittle transition temperatures.