Study of the beltline weld and base metal of WWER-440 first generation reactor pressure vessel

Abstract

We present experimental results of the circumferential core weld SN0.1.4 and the base metal ring 0.3.1 of the reactor pressure vessel from the Unit 1 of the Greifswald WWER-440/230. The investigated trepans represent the irradiated-annealed-reirradiated (IAI) condition. The working program is focused on the characterization of the reactor pressure vessel steels through the reactor pressure vessel wall. The key part of the testing is aimed at the determination of the reference temperature T 0 following the ASTM Test Standard E1921 to determine the fracture toughness in different thickness locations.

Uncertainties in activity calculations of different nuclides in reactor steels by neutron irradiation

“…Material probes from the pressure vessels were gained in the frame of the ongoing decommissioning procedure. The investigation of this material is described in [3].…”