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View document| NKS Programme Area: | NKS-R | | Research Area: | Plant life management and extension | | Report Number: | NKS-443 | | Report Title: | 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 | | Publication date: | 23 Febr 2021 | | ISBN: | 978-87-7893-535-9 | | Number of downloads: | 1454 | | Download: |  NKS-443.pdf |
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