Персона: Кулешова, Евгения Анатольевна
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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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Кулешова
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Евгения Анатольевна
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- ПубликацияТолько метаданныеGrain 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.
- ПубликацияТолько метаданныеRadiation-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.
- ПубликацияТолько метаданныеAnnealing 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.
- ПубликацияТолько метаданныеDegradation 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.
- ПубликацияТолько метаданныеTEM-studies of the dislocation loops and niobium-based precipitates in E110 alloy after operation in VVER-type reactor conditions(2019) Gurovich, B. A.; Frolov, A. S.; Maltsev, D. A.; Safonov, D. V.; Kuleshova, E. A.; Кулешова, Евгения Анатольевна© 2019 Elsevier Inc.Microstructural studies of fuel cladding (made of E110 alloy based on sponge zirconium) after operation in VVER-1000 conditions (up to ~13 dpa) were carried out. The essential microstructural elements, which are responsible for the degradation of this material under the influence of operational factors, are established. It is known that in the process of irradiation, beta‑niobium needle-shaped precipitates are formed (in addition to the dislocation structures), which, upon reaching a specific fluence of fast neutrons, form periodic structures (with a bulk density of ~2–3∙1022 m−3). However, for the first time in this work, it was shown that relatively low doses of irradiation (~1.5 dpa) are characterized by the formation of needle-like phases with the high bulk density of ~4∙1022 m−3, which decreases with increasing of irradiation dose. This indicates the coagulation process of these particles during further operation of the fuel rods as a part of the VVER-1000 Fuel Assembly (FA). It is also shown in this work that the threshold dose for the formation of -type dislocation loops in alloy E110 (under the specified irradiation conditions) does not exceed 5.6 dpa.