Abstract: Noora Hytönen: Effect of Microstructure on Brittle Fracture Initiation in a Reactor Pressure Vessel Weld Metal Master of Science Thesis Tampere University Materials Science November 2019 The weld can be the most life-limiting part in a reactor pressure vessel (RPV). During operation, the pressure vessel components are subjected to high temperature and neutron irradiation induced ageing, which cause embrittlement. The RPV head is only subjected to thermal ageing. Submerged arc welding method is commonly used in the construction of reactor pressure vessels. Welding is a complex process that often introduces inclusions and other second-phase particles in the weld, which play a role in brittle fracture. Non-metallic inclusions, such as oxides, are brittle particles that may initiate a cleavage fracture when the loading stress exceeds the critical stress at the crack front. Knowledge on ductile-to-brittle transition and all factors affecting that are a critical safety matter, and therefore understanding the fracture mechanics of an RPV is important. A ferritic steel weld experiences a ductile-to-brittle transition, causing the metal to act brittle at low temperatures and ductile at elevated temperatures. Severe ageing is known to shift the transition temperature towards higher temperatures due to embrittlement. The brittle fracture must be avoided by securing that the weld metal remains ductile in all situations. Factors affecting the brittle fracture in RPVs have been researched, but more detailed knowledge on weld embrittlement in needed in order to increase the understanding of affecting parameters, and eventually increase the RPV life time and prevent the formation of brittle fracture. This thesis is part of the BRUTE (Barsebäck RPV material used for true evaluation of embrittlement) project at VTT Technical Research Centre of Finland Ltd. The project belongs to the SAFIR2022 programme (The Finnish Research Programme on Nuclear Power Plant Safety 20192022). The aim of the thesis is to increase the understanding of factors affecting brittle fracture initiation in the RPV weld metal. The investigated material is from a decommissioned Swedish nuclear power plant reactor pressure vessel, Barsebäck Unit 2, which had been in effective operation for 23 years. The base material consists of standard bainitic pressure vessel steel and the weld metal is high in Ni and Mn. All the experiments were performed at VTT Centre for Nuclear Safety (CNS), pioneering the new laboratory facilities. The experiments in this thesis concentrated on two main subjects, i.e., weld microstructure characterisation and brittle fracture mechanics. The general microstructural characterisation concluded that the weld is a high-quality weld throughout the wall thickness. The heat-affected zone (HAZ) consisted of fine-grained and coarse-grained regions. The solidification structure consisted of a typical multipass weld with as-welded and reheated regions. Acicular ferrite dominated the as-welded microstructure with some grain boundary ferrite between the columnar grains. Polygonal ferrite dominated the reheated microstructure with some grain boundary ferrite and acicular ferrite. The macroand microhardness measurements of the weld showed homogeneous weld and the macrohardness profiles were plotted from the base material to the HAZ and to the weld metal. The transition temperature and ageing effect were determined by Charpy V-notch impact toughness test. The testing gave a transition temperature of -75 ◦C. In this thesis, the investigated fracture specimens were tested at low temperatures, i.e., in the brittle fracture regime. On all investigated brittle specimens the cleavage fracture initiated at a particle rich in Mn, Al, Si, and O, and the particle was always the largest at the area of a maximum crack driving force. No severe thermal ageing effect has been observed.