Chang, Chih-Cheng

Gaganidze, Ermile

Terentyev, Dmitry

Van Eyken, Jelle

Zinovev, Aleksandr

English

KITopen

Science Talks 6 (2023) 100214Contents lists available at ScienceDirectScience Talksj ourna l homepage: www.e lsev ie r .es /scta lkEffect of neutron irradiation to 0.7 and 1.4 dpa on the tensile mechanicalproperties and microstructure of EUROFER97 steelAleksandr Zinovev a,⁎, Chih-Cheng Chang a,b, Jelle Van Eyken a, Ermile Gaganidze c, Dmitry Terentyev aa Institute for Nuclear Materials Science, Belgian Nuclear Research Centre (SCK CEN), Boeretang 200, 2400 Mol, Belgiumb Institute of Mechanics, Materials and Civil Engineering (iMMC), Université catholique de Louvain (UCLouvain), Av. Georges Lemaître 4, 1348 Louvain-la-Neuve, Belgiumc Karlsruhe Institute of Technology, Institute for Applied Materials, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany⁎ Corresponding author.E-mail address: aleksandr.zinovev@sckcen.be (A. Zinovehttp://dx.doi.org/10.1016/j.sctalk.2023.100214Received 9 March 2023; Received in revised form 102772-5693/© 2023 The Authors. Published by ElseviA B S T R A C TA R T I C L E I N F OKeywords:Reduced-activation materialFerritic-martensitic steelIrradiation hardeningFusionStrengthDuctilitySeveral grades of reduced-activation ferritic-martensitic (RAFM) steels have been proposed for fusion applications(e.g., blanket first wall) since the 1990s all over the world. Four batches of the European reference RAFM steelEUROFER97 have been produced since 1998. The RCC-MRx design code, developed, among others, for fusion reac-tors, currently contains a provisional section dedicated to EUROFER97, encompassing properties of the first twobatches, whereas minimum three batches are required for a full qualification and final inclusion of a material intoRCC-MRx. The EUROfusion project coordinates efforts to broaden the knowledge of EUROFER97 properties relevantfor fusion reactors ITER and DEMO, preparing them for closing the database gaps in RCC-MRx and aggregating them inthe DEMO material property handbook (MPH). Its purpose is to provide average and minimum curves of requiredproperties according to the DEMO engineering design and manufacturing needs.The present work reports mechanical properties and fractographic analysis of batch 4 of neutron-irradiatedEUROFER97 for the first time. The measured strength and ductility are in line with the data already aggregated inthe MPH. SEM investigation confirms that the dimple fracture is retained in the material after neutron irradiationup to 1.4 dpa in the temperature range 25…550 °C.Video and Transcript to this article can be found online at https://doi.org/10.1016/j.sctalk.2023.100214.v).April 2023; Accepted 13 April 2023er Ltd. This is an open access article under the CC BY license (http://creativecommons.org/licenses/by/4.0/).A. Zinovev et al. Science Talks 6 (2023) 100214Figures and tablesFig. 1. (a) A cut of the 3D model of ITER, the world's largest fusion reactor under construction in France [iter.org]. (b) Design of the water cooled lithium‑lead (WCLL) testblanket module (TBM) for ITER, which will be made of EUROFER97 [1].Fig. 2. Example and dimensions of the tensile specimens used in the present research (left) and a drawing of their positioning in irradiation capsules for the BR-2 reactor(center and right).2Fig. 3. Top view of the irradiation channels of the BR-2 material test reactor at SCK CEN (Belgium) [sckcen.be].A. Zinovev et al. Science Talks 6 (2023) 1002143Fig. 4. Yield stress (mean) of EUROFER97 batch 4 before and after neutron irradiation compared to the reference data [2,3].A. Zinovev et al. Science Talks 6 (2023) 1002144Fig. 5. Uniform elongation (mean) of EUROFER97 batch 4 before and after neutron irradiation compared to the reference data [3].A. Zinovev et al. Science Talks 6 (2023) 1002145Fig. 6. Fracture surface of tested tensile specimens of EUROFER97 batch 4 tested at room temperature. Left panels – general view of the specimen cross-section. Right panels –high magnification images taken from the area marked on the left images. (a, b) Nonirradiated. (c, d) Irradiated to 1.4 dpa at 300 °C. (e, f) Irradiated to 0.7 dpa at 550 °C.A. Zinovev et al. Science Talks 6 (2023) 100214CRediT authorship contribution statementAleksandr Zinovev: Investigation, Visualization, Writing – originaldraft, Writing – review & editing. Chih-Cheng Chang: Investigation.Jelle VanEyken: Investigation, Visualization. Ermile Gaganidze:Concep-tualization, Methodology, Validation, Resources, Writing – review &editing. Dmitry Terentyev: Supervision, Project administration, Fundingacquisition.Data availabilityData will be made available on request.AcknowledgmentsThis work has been carried out within the framework of theEUROfusion Consortium, funded by the European Union via the Euratom6Research and Training Programme (Grant Agreement No 101052200 —EUROfusion). Views and opinions expressed are however those of the au-thor(s) only and do not necessarily reflect those of the European Union orthe European Commission. Neither the European Union nor the EuropeanCommission can be held responsible for them.Declaration of interestsThe authors declare that they have no known competing financial inter-ests or personal relationships that could have appeared to influence thework reported in this paper.References[1] J. Aubert, G. Aiello, D. Alonso, T. Batal, R. Boullon, S. Burles, B. Cantone, F. Cismondi, A.Del Nevo, L. Maqueda, A. Morin, E. Rodríguez, F. Rueda, M. Soldaini, J. Vallory, Designand preliminary analyses of the new water cooled Lithium lead TBM for ITER, FusionEng. Des. 160 (2020), 111921, https://doi.org/10.1016/j.fusengdes.2020.111921.A. Zinovev et al.[2] E. Gaganidze, F. Gillemot, I. Szenthe, M. Gorley, M. Rieth, E. Diegele, Development ofEUROFER97 database and material property handbook, Fusion Eng. Des. 135 (2018)9–14, https://doi.org/10.1016/j.fusengdes.2018.06.027.[3] DEMO Material Properties Handbook: EUROFER97. EUROfusion, 2018.Further reading[4] M. Rieth, M. Dürrschnabel, S. Bonk, U. Jäntsch, T. Bergfeldt, J. Hoffmann, S. Antusch, E.Simondon, M. Klimenkov, C. Bonnekoh, B.-E. Ghidersa, H. Neuberger, J. Rey, C. Zeile, G.Pintsuk, G. Aiello, Technological processes for steel applications in nuclear fusion, Appl.Sci. 11 (2021) 11653, https://doi.org/10.3390/app112411653.[5] RCC-MRx, AFCEN Edition, Design and Construction Rules for Mechanical Components ofNuclear Installation, 2018.Aleksandr Zinovev is a researcher at Belgian Nuclear ResearchCentre (SCK CEN) who is active in Materials Science for fusionapplications. He graduated from Ufa State Aviation TechnicalUniversity in 2012 and received a Ph.D. degree from Universitécatholique de Louvain in a joint project with SCK CEN in 2019.Currently he takes part in the characterisation of in-vessel struc-tural materials for fusion reactors ITER and DEMO within theEUROfusion project, contributing to the evaluation and selec-tion of engineering options allowing for their safe and reliableoperation.Chih-Cheng Chang is a PhD student enrolled in the Institute ofMechanics, Materials and Civil Engineering at UCLouvain andBelgian Nuclear Research Centre (SCK CEN). His PhD topic con-cerns the assessment of mechanical properties of fusion mate-rials by micro-mechanical testing. He is currently in the lastyear of the PhD project focusing on the finite element methodvalidation of application of miniaturized specimens for fracturetoughness tests.7Jelle Van Eyken graduated in the field of nuclear physics atK.U. Leuven university. Currently active in the non-destructiveandmicrostructural research department of the Belgian NuclearResearch Center (SCK CEN) since 2011. Main focus in the fieldelectron microscopy (SEM-EDS-WDS-EBSD).Science Talks 6 (2023) 100214Ermile Gaganidze received his Diploma in Physics from IvaneJavakhishvili Tbilisi State University. He earned his PhD degreefrom the University of Bayreuth. He worked as a scientist at In-stitute of Physics of the Georgian Academy of Sciences, Univer-sity of Bayreuth and University of Leipzig. In 1998 he joined theKarlsruhe Institute of Technology (KIT). Currently he is a seniorscientist at KIT at the Institute for AppliedMaterials –Mechanicsof Materials and Interfaces leading a group investigating theneutron irradiation induced damage in the structural materialsfor fusion application.Dmitry Terentyev has obtainedmaster degree inNuclear Phys-ics in 2002 at Saint Petersburg Polytechnic University, followedby the PhD degree in 2006 issued at Université Libre de Bru-xelles. Since 2014, Dr. Dmitry Terentyev leads the Fusion Re-search Programme at Belgian Nuclear Research Center (SCKCEN,Mol). Scientific expertise of Dr. Terentyev coversmaterialsscience, neutronic physics and computational materials model-ling. Specific focus of research is made on irradiation effects innuclear materials.

Effect of neutron irradiation to 0.7 dpa and 1.4 dpa on the tensile properties and fracture surface of EUROFER97 steel

https://publikationen.bibliothek.kit.edu/1000162589/151400669

Effect of neutron irradiation to 0.7 dpa and 1.4 dpa on the tensile properties and fracture surface of EUROFER97 steel

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