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Скуратов, Владимир Алексеевич

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Институт ядерной физики и технологий
Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.
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Владимир Алексеевич
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20211
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Автор: Alekseeva, L. S. × Тема: Конференции НИЯУ МИФИ ×

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    TEM STUDY OF Y-Ti-O AND Y-Al-O IN ODS ALLOYS IRRADIATED WITH SWIFT HEAVY IONS
    (НИЯУ МИФИ, 2021) Korneeva, Е. А.; Ibrayeva, A.; O’Connell, J.; Mutali, A.; Sohatsky, A. S.; Vershinina, T. N.; Skuratov, V. A.; Zdorovets, М.; Alekseeva, L. S.; Nokhrin, A. V.; Скуратов, Владимир Алексеевич
    In recent years, nuclear industry development must be response to new requirements of safety, sustainability and effectiveness. The operating conditions of nuclear reactors of new design would tend to more damage operation mode, in particular, high temperature and high dozes. Oxide dispersion strengthened (ODS) alloys now have been widely investigated as perspective constructive materials for fuel claddings in Generation IV nuclear reactors due to their high values of high temperature creep resistance and resistance to irradiation swelling [1- 3]. High operation properties of ODS alloys are due to nanosized dielectric particles based mainly on yttrium oxides embedded in the metallic matrix. These thermostable nanosized particles are responsible for resistance to dislocation motion that regulate high-temperature creep resistance and tensile properties at high temperatures as well as provide swelling resistance while acting as sinks for radiation defects. Nowadays most literature data are devoted to study structure stability of ODS alloys under neutron and low-energy ion irradiation that didn’t show any significant effect on the ODS structure [4,5]. At the same time apart from neutron irradiation cladding materials in reactor core will contact with fission fragments (FF) that can dramatically affect the structure of dielectric materials even down to complete amorphization due to high levels of electronic excitation [6]. Therefore, studying the structure behavior of oxide nanoparticles in metallic matrix under FF impact can broaden the idea of operational limits and conditions of ODS steels for new reactors. The aim of present study is the complex investigation of radiation stability of nanostructured Y-Ti-O and Y-Al-O compounds embedded in metallic matrix and as separate oxides at a broad range of electronic stopping power and ion fluences.