Barsebäck as a Research and Development Platform, Extraction and Analysis of Service-aged and Irradiated Reactor Pressure Vessel Material
Activity Acronym:
BREDA RPV
Authors:
Pål Efsing, Magnus Boåsen, Daniela Klein, Ulla Ehrnstén, Pentti Arffman, Noora Hytönen, Jari Lydman, Sebastian Lindqvist, Mattias Thuvander, Kristina Lindgren, Jenny Roudén,
Abstract:
As part of the NKS-R program, VTT, Chalmers University of Technology and KTH has continued the mechanical and microstructural testing in or-der to analyze the as-aged material properties of the retired reactor pres-sure vessel, RPV, and reactor pressure vessel head, RPVH from Barsebäck unit 2. The current phase included Impact testing of material from the reactor pressure vessel head and microstructural characteriza-tion of the weld metal using LOM, SEM and APT. Due to the nature of the work, the NKS-project is connected to a number of adjacent activities, including support from the Finnish Nuclear Safety Program, the SAFIR-program, the Swedish Radiation Safety Authority SSM and Swedish Cen-tre for Nuclear Technology, SKC and Energiforsk.
Magnus Boåsen, KTH and Sebastian Lindqvist, VTT/Altoo University both successfully presented and defended their Ph.D. theses partially per-formed with-in the scope of the project during the fall of 2020.
Keywords:
Low alloy steel, Long Term Operation, irradiation effects, fracture tough-ness, ductile to brittle transition temperature, constraint effects, high reso-lution microscopy, microstructural characterization
NKS Reports 
