Sequential ion irradiations on Fe-Cr and ODS Fe-Cr alloys

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dc.contributor.author Scepanovic, Masa
dc.contributor.author Leguey Galán, Teresa
dc.contributor.author Garcia-Cortes, I.
dc.contributor.author Sanchez, Fernando Jose
dc.contributor.author Hugenschmidt, C.
dc.contributor.author Auger Martínez, María Angustias
dc.contributor.author Castro Bernal, María Vanessa de
dc.date.accessioned 2021-03-24T10:34:42Z
dc.date.available 2021-03-24T10:34:42Z
dc.date.issued 2020-12
dc.identifier.bibliographicCitation Šćepanović, M., Leguey, T., García-Cortés, I., Sánchez, F. J., Hugenschmidt, C., Auger, M. A. & de Castro, V. (2020). Sequential ion irradiations on Fe-Cr and ODS Fe-Cr alloys. Nuclear Materials and Energy, 25, 100790.
dc.identifier.issn 2352-1791
dc.identifier.uri http://hdl.handle.net/10016/32212
dc.description.abstract Oxide dispersion strengthened steels are candidate materials for nuclear reactor applications due to a powerful combination of properties, such as reduced activation, high-temperature strength and increased creep resistance. The dispersion of nanometric oxide particles in the steel matrix may also enhance radiation resistance by acting as trapping sites for irradiation induced defects. In this work, an Fe-14Cr-2 W-0.3-Ti-0.3Y2O3 (wt%) steel and a model Fe-14Cr (wt%) alloy were sequentially irradiated with He+ and Fe+ ions up to 15 dpa and 8000 appm to simulate fusion radiation damage. Their microstructural stability was investigated by positron annihilation spectroscopy and transmission electron microscopy. Transmission electron microscopy studies show that under these irradiation conditions there are no significant changes in the mean size, qualitative chemical composition and number density of nanoparticles, although the irradiation appears to induce a slight coarsening of the smaller nanoparticles. Both materials exhibit very small (<2 nm) irradiation-induced bubbles, with similar sizes but lower number density in the ODS steel. Positron annihilation spectroscopy results show the presence of irradiation induced open volume defects, much more noticeable in the model alloy. In both alloys, helium appears to associate with the newly formed vacancy-type defects introduced by the subsequent Fe+ irradiation.
dc.format.extent 11
dc.language.iso eng
dc.publisher Elsevier
dc.rights © 2020 The Authors.
dc.rights Atribución-NoComercial-SinDerivadas 3.0 España
dc.rights.uri http://creativecommons.org/licenses/by-nc-nd/3.0/es/
dc.subject.other Fecr alloys
dc.subject.other Ods steelsion irradiation
dc.subject.other Radiation damage
dc.subject.other Transmission electron microscopy
dc.subject.other Positron annihilation spectroscopy
dc.title Sequential ion irradiations on Fe-Cr and ODS Fe-Cr alloys
dc.type article
dc.subject.eciencia Física
dc.identifier.doi https://doi.org/10.1016/j.nme.2020.100790
dc.rights.accessRights openAccess
dc.relation.projectID Gobierno de España. ENE2015-70300-C3-2-R
dc.relation.projectID Comunidad de Madrid. S2018/EMT-4437
dc.relation.projectID Comunidad de Madrid. 2017-T1/IND-5439
dc.relation.projectID Gobierno de España. ENE2016-76755-R
dc.type.version publishedVersion
dc.identifier.publicationfirstpage 1
dc.identifier.publicationissue 100790
dc.identifier.publicationlastpage 11
dc.identifier.publicationtitle Nuclear Materials and Energy
dc.identifier.publicationvolume 25
dc.identifier.uxxi AR/0000026463
dc.contributor.funder Ministerio de Economía y Competitividad (España)
dc.contributor.funder Comunidad de Madrid
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