[en] Application of reduced activation ferritic/martensitic (RAFM) steels as the structural material in future fusion reactors requires the knowledge of their mechanical properties under relevant operational conditions i.e. temperatures and irradiation by fast neutrons. Execution of the neutron irradiation and post irradiation examination is expensive and lengthy, therefore experimental and computational solutions to ease the characterization of as-irradiated materials are in the scope of interests of nuclear materials scientific community. Moreover, ion irradiation is considered as one possible way to surrogate high flux neutron irradiation damage. The extraction of the mechanical properties after ion irradiation primarily relies on the nanoindentation techniques and its subsequent post processing to extract engineering relevant information, although some innovative techniques such as compression micropillars and micro-tensile testing also exist. In this work, we have performed nanoindentation on BCC iron, as the basis material for ferritic steels, by using a new Bruker stage developed for high temperature operation. The obtained results were analyzed by means of crystal plasticity finite element method (CPFEM), whereas the constitutive laws of the material were derived and established by using tensile deformation data, thus providing an interconnection of material’s behavior under compressive and tensile deformations. The microstructural features such as indentation pile-up formation or dislocation density evolution were obtained by using transmission and scanning electron microscopy, and were compared with the predictions derived by the developed CPFEM model. It is demonstrated that a good agreement between the CPFEM and experimental data set, including tensile and compressive load
Research center :
A&M - Aérospatiale et Mécanique - ULiège
Disciplines :
Materials science & engineering Mechanical engineering Energy
Author, co-author :
Khvan, Tymofii ; Université de Liège - ULiège > Aérospatiale et Mécanique (A&M)
Noels, Ludovic ; Université de Liège - ULiège > Aérospatiale et Mécanique (A&M) ; Université de Liège - ULiège > Département d'aérospatiale et mécanique > Computational & Multiscale Mechanics of Materials (CM3)
Terentyev, Dmitry; SCK CEN - Belgian Nuclear Research Centre [BE]
Dencker, F; Leibniz University Hannover
Stauffer, D; Bruker Inc
Hanger, UD; Bruker Nano GmbH
Van Renterghem, Wouter; SCK CEN - Belgian Nuclear Research Centre [BE]
Cheng, C; SCK CEN - Belgian Nuclear Research Centre [BE]
Zinovev, Aleksandr; SCK CEN - Belgian Nuclear Research Centre [BE]
Language :
English
Title :
High temperature nanoindentation of iron: experimental and computational study
Publication date :
15 August 2022
Journal title :
Journal of Nuclear Materials
ISSN :
0022-3115
Publisher :
Elsevier, Netherlands
Volume :
567
Pages :
153815
Peer reviewed :
Peer Reviewed verified by ORBi
European Projects :
H2020 - 633053 - EUROfusion - Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium
Name of the research project :
EUROfusion
Funders :
EC - European Commission [BE] Union Européenne [BE]
Funding number :
101052200
Funding text :
This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 — EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor the European Commission can be held responsible for them.
Commentary :
NOTICE: this is the author’s version of a work that was accepted for publication in Journal of Nuclear Materials. Changes resulting from the publishing process, such as peer review, editing, corrections, structural formatting, and other quality control mechanisms may not be reflected in this document. Changes may have been made to this work since it was submitted for publication. A definitive version was subsequently published in Journal of Nuclear Materials 567 (2022) 153815, DOI: 10.1016/j.jnucmat.2022.153815
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