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Кулешова, Евгения Анатольевна

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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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Кулешова

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Евгения Анатольевна

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Теперь показываю 1 - 10 из 20

Только метаданные
Grain Boundary Embrittlement of Steels of Vver-1000 Reactor Vessels Under Long-Term Operation
(2019) Mal'tsev, D. A.; Fedotova, S. V.; Kuleshova, E. A.; Кулешова, Евгения Анатольевна
© 2019, Springer Science+Business Media, LLC, part of Springer Nature.Results of fractographic analysis and Auger electron spectroscopy of materials of vessels of VVER-1000 reactors obtained at the “Kurchatov Institute” Research Center are systematized. Comparative analysis of the effect of the operating factors on the level of grain boundary embrittlement in the matrix metal and welded joints is performed. The contribution of grain boundary embrittlement into the total radiation-induced embrittlement of the weld metal of the vessels is determined.
Только метаданные
Radiation-Induced Phase Formation in Steels of VVER Reactor Pressure Vessels Containing ~0.3–1.3 wt % Nickel
(2019) Frolov, A. S.; Zhuchkov, G. M.; Fedotov, I. V.; Kuleshova, E. A.; Кулешова, Евгения Анатольевна
© 2019, Pleiades Publishing, Ltd.Abstract: The radiation-induced structural elements in the materials of water-moderated water-cooled reactor pressure vessels have been studied by TEM and atomic probe tomography at the National Research Center Kurchatov Institute. The effect of Ni concentration in the range from 0.34 to 1.28 wt % on the formation of phases under fast neutron irradiation has been analyzed. The volume density of radiation-induced phases has been shown to depend on the Ni concentration in steel; the phase sizes and compositions remain almost the same. The volume density of these precipitations affects the radiation hardening, one of the radiation embrittlement mechanisms. The quantitative parameters of radiation-induced phases have been shown to control the service life growth, the enhancement of the thermal stability, and the melting technology of reactor vessel steels bearing nickel in the 0.3–0.7 wt % range.
Только метаданные
Annealing as a Technique for Estimating the Structural Elements Contribution to NPP Materials Service Properties
(2019) Fedotov, I. V.; Kuleshova, E. A.; Кулешова, Евгения Анатольевна
© 2019, Pleiades Publishing, Ltd.Abstract: The annealing technique is used to estimate the effect of radiation-induced structural elements on the service properties of the materials used in nuclear power plants: reactor pressure vessel (RPV) and in-vessel internals steels. The WWER-1000 RPV weld seam is affected by a hardening mechanism, the contribution of which is 60–65%, and a nonhardening mechanism resulting in grain-boundary segregation, the contribution of which is 30–35%. Radiation defects 40–45% and G-phase precipitates 35–40% are mainly responsible for the radiation-induced hardening of WWER-1000 internals materials. Radiation-induced structural changes should be eliminated for these materials to be reused.
Только метаданные
Degradation of Fuel Cladding Materials Based on Zirconium after Operation in VVER-Type Reactors
(2019) Frolov, A. S.; Gurovich, B. A.; Maltsev, D. A.; Safonov, D. V.; Kuleshova, E. A.; Кулешова, Евгения Анатольевна
© 2019, Pleiades Publishing, Ltd.Abstract: The paper presents microstructural studies of specimens cut from fuel elements made of E110 spongy zirconium-based alloy after operation in a VVER-1000 before reaching the burnup of ~35 MWd/kg U. As a result of exposure to high temperatures and neutron irradiation, significant changes in the phase composition of fuel cladding materials appear: change in the size, density, and composition of β-Nb particles; change in the composition of the Laves phase; formation of dislocation loops of α type, as well as δ and γ hydrides. The main structural elements determining the degradation of the mechanical properties of the E110 alloy under irradiation are dislocation loops and fine-phase precipitates owing to their relatively large density. The data obtained can be used to construct dose dependences of microstructural changes with the aim of predicting the residual life of claddings and fuel assemblies as a whole.
Только метаданные
Structural evolution features of the 42XNM alloy during neutron irradiation under VVER conditions
(2021) Gurovich, B. A.; Frolov, A. S.; Maltsev, D. A.; Safonov, D. V.; Kuleshova, E. A.; Кулешова, Евгения Анатольевна
© 2020The paper presents the results of microstructural studies by transmission electron microscopy and atom probe tomography of the Ni-Cr-Mo (42XNM) alloy in the initial state, as well as after neutron irradiation, in the range of fast neutron fluence (0.9–1.5)•1026n•m−2 (E>0.1 MeV) (5–12 dpa) at ~ 300°C. It was shown that during neutron irradiation, various defects were formed – dislocation loops and pores, the bulk density and size of the second phase precipitates (TiN and α-Cr) remained stable. Quantitative analysis of chemical composition for regions near the boundaries of austenitic grains was made, which showed typical effects for materials with an FCC lattice (which contains Ni and Cr) after neutron irradiation – nickel depletion of grain boundaries and enrichment in chromium. Similar studies were carried out for segregation processes on the Frank loop edges.
Только метаданные
Development of Software for Determining the Parameters of Pores and Segregations of Alloying Elements in Austenitic Steels after Ion Irradiation
(2021) Frolov, A. S.; Alekseeva, E. V.; Kuleshova, E. A.; Кулешова, Евгения Анатольевна
© 2021, Pleiades Publishing, Inc.Abstract: SwellingProfile and ElementProfile software packages were developed to construct swelling profiles when processing cross-cut images obtained using scanning transmission electron microscopy (STEM). These packages also make it possible to calculate the distribution profiles of chemical elements near the boundaries of vacancy pores and along the ion-beam path in materials irradiated to relatively large damaging doses. They were applied to analyze the vacancy swelling in 08Kh18N10T steel irradiated with nickel ions (with preliminary helium implantation) at a temperature of 625°C up to the peak damaging doses of ~300 dpa. Two maxima are revealed in the plotted swelling profile, which are due to the formation of two systems of pores of different sizes. A comparative analysis showed that the implanted-nickel profile correlates well with the calculations performed within SRIM-2008.
Только метаданные
Application of the EBSD Method to Study the Fracture Mechanisms of Reactor Pressure Vessels Steels under Operational Factors
(2021) Maltsev, D. A.; Fedotova, S. V.; Saltykov, M. A.; Stepanov, N. V.; Kuleshova, E. A.; Кулешова, Евгения Анатольевна
© 2021, Pleiades Publishing, Inc.Abstract: The mechanisms of degradation of the structure and properties of steels of pressure vessels of pressurized water reactors (PWRs) have been analyzed using еlectron backscatter diffraction (EBSD) method, whose possibilities are demonstrated by an example of materials of the pressure vessels of the VVER-440 reactors after 45 years of operation. It is shown that the long-term use of the materials of a VVER-440 pressure vessel at elevated operating temperatures (~270°C) induces the occurrence of portions with intercrystallite fracture, which was not observed previously. Fracture occurs at the boundaries of primary austenitic grains along the ferrite–bainite interface.
Только метаданные
Радиационно-индуцированная деградация структуры конструкционных материалов водо-водяных реакторов
(НИЦ "Курчатовский институт", 2022) Кулешова, Е. А.; Гурович, С. В.; Федотова, С. В.; Фролов, А. С.; Мальцев, Д. А.; Кулешова, Евгения Анатольевна
Монография предназначена для широкого круга научных сотрудников, специалистов и аспирантов, интересующихся перспективными направлениями развития атомной энергетики и реакторного материаловедения, а также студентов кафедр, обучающихся по специальности "Ядерные реакторы и материалы". В монографии представлены как литературные, так и оригинальные данные, полученные в НИЦ "Курчатовский институт". Исследования облученных реакторных материалов в СССР были впервые начаты в НИЦ "Курчатовский институт" в 1951 году и охватили практически все материалы активных зон реакторов на тепловых нейтронах: материалы корпусов реакторов, оболочек тепловыделяющих элементов и топлива, материалы канальных труб, реакторных графитов и т.п. Эти работы включали исследования как структуры, так и свойств материалов. При этом был накоплен уникальный опыт выявления факторов и механизмов, определяющих поведение и ресурс материалов и элементов активных зон под воздействием нейтронного облучения в ядерных реакторах.
Только метаданные
Structural features ensuring the increase of service characteristics of high-nickel steels for pressure vessels of prospective energy-generation reactors
(2022) Kuleshova, E. A.; Isaenkova, M. G.; Krymskaya, O. A.; Minushkin, R. A.; Кулешова, Евгения Анатольевна; Исаенкова, Маргарита Геннадьевна; Крымская, Ольга Александровна; Минушкин, Роман Александрович
Complex structure studies and mechanical tests of low carbon Ni–Cr–Mo–V steels with low and high nickel content (low-Ni and high-Ni steels) were performed. Mechanical tests showed that high-Ni steels in initial state are characterized by higher strength properties and lower values of critical temperature of brittleness in comparison with low-Ni steels. Estimation of input of various structural elements in ensuring yield strength and brittle fracture stress (which is connected with critical temperature of brittleness) was performed. It was shown that increased strength characteristics of high-Ni steels are determined mostly by higher density of nanoscale carbide precipitations and dislocations. It was also shown that lower critical temperature of brittleness of high-Ni steels is associated with lower width of substructural blocks and, consequently, with higher number of barriers to brittle transcrystalline crack propagation. © 2022
Только метаданные
THE ROLE OF NICKEL IN FORMING A STRUCTURE PROVIDING INCREASED SERVICE PROPERTIES OF REACTOR STRUCTURAL MATERIALS РОЛЬ НИКЕЛЯ В ФОРМИРОВАНИИ СТРУКТУРЫ, ОБЕСПЕЧИВАЮЩЕИ ПОВЫШЕННЫЕ СЛУЖЕБНЫЕ ХАРАКТЕРИСТИКИ РЕАКТОРНЫХ КОНСТРУКЦИОННЫХ МАТЕРИАЛОВ
(2022) Kuleshova, E. A.; Fedotov, I. V.; Stepanov, N. V.; Frolov, A. S.; Maltsev, D. A.; Safonov, D. V.; Кулешова, Евгения Анатольевна