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NKS Programme Area:NKS-R
Research Area:Plant life management and extension
Report Number:NKS-431
Report Title:Barsebäck as a Research and Development Platform, Extraction and Analysis of Service-aged and Irradiated Reactor Pressure Vessel Material; Summary of 2019 activities
Activity Acronym:BREDA-RPV
Authors:Pål Efsing, Magnus Boåsen, Ulla Ehrnstén, 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 order to analyze the as-aged material properties of the retired reactor pressure vessel, RPV, from Barsebäck unit 2. The current phase included Impact testing of material from the reactor pressure vessel head and microstructural characterization 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 Centre for Nuclear Technology, SKC and Energiforsk. Noora Hytönen, Tampere University successfully presented and defended her M..Sc. thesis performed with-in the scope of the project in November 2019.
Keywords:Low alloy steel, irradiation effects, fracture toughness, ductile to brittle transition temperature, constraint effects, high resolution microscopy, microstructural characterization
Publication date:11 Febr 2020
ISBN:ISBN 978-87-7893-521-2
Number of downloads:1437
Download:pdf NKS-431.pdf
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