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View document| NKS Programme Area: | NKS-R | | Research Area: | Plant life management and extension | | Report Number: | NKS-486 | | Report Title: | Barsebäck as a Research and Development Platform, Extraction and Analysis of Service-aged and Irradiated Reactor Pressure Vessel Material | | Activity Acronym: | BREDA 2023 | | Authors: | Pål Efsing, Jonas Faleskog, Daniela Klein, Noora Hytönen, Jari Lydman, Sebastian Lindqvist, Mattias Thuvander, Jenny Roudén, | | Abstract: | As part of the NKS-R program, VTT, Chalmers University of
Technology and KTH have extended the assessment of micro-structural and mechanical property evolution during irradiation to analyze the as-aged material properties of the retired reactor pressure vessel, RPV, from Barsebäck unit 2. The testing included impact and fracture mechanical testing of material, and microstructural characterization of the weld metal from the reactor pressure vessel using LOM, SEM and APT. Due to the nature of the work, the NKS-project is connected to several 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, and SKC. | | Keywords: | Low alloy steel, irradiation effects, fracture toughness, ductile to brittle transition temperature, constraint effects, high resolution microscopy, microstructural characterization | | Publication date: | 21 Mar 2024 | | ISBN: | 978-87-7893-582-3 | | Number of downloads: | 438 | | Download: |  NKS-486.pdf |
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