Search Results - "Kuleshova, A. E."
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1
Reorientation of Hydrides in Unirradiated Clad Tubes Made of Alloy E110 under Conditions Simulating Long-Term Dry Storage of Spent Nuclear Fuel
Published in Physics of metals and metallography (01-09-2021)“…Reorientation of hydrides in the course of dry storage of spent nuclear fuel is a possible mechanism for the degradation of the properties of fuel claddings…”
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2
Grain Boundary Embrittlement of Steels of Vver-1000 Reactor Vessels Under Long-Term Operation
Published in Metal science and heat treatment (01-11-2019)“…Results of fractographic analysis and Auger electron spectroscopy of materials of vessels of VVER-1000 reactors obtained at the “Kurchatov Institute” Research…”
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3
Radiation-Induced Phase Formation in Steels of VVER Reactor Pressure Vessels Containing ~0.3–1.3 wt % Nickel
Published in Physics of metals and metallography (01-05-2019)“…The radiation-induced structural elements in the materials of water-moderated water-cooled reactor pressure vessels have been studied by TEM and atomic probe…”
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4
Specific Features of Structural-Phase State and Properties of Reactor Pressure Vessel Steel at Elevated Irradiation Temperature
Published in Science and technology of nuclear installations (01-01-2017)“…This paper considers influence of elevated irradiation temperature on structure and properties of 15Kh2NMFAA reactor pressure vessel (RPV) steel. The steel is…”
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5
Precipitation kinetics of radiation-induced Ni-Mn-Si phases in VVER-1000 reactor pressure vessel steels under low and high flux irradiation
Published in Journal of nuclear materials (01-09-2021)“…•VVER-1000 RPV steels after low and high flux irradiation are studied by APT, TEM.•Number density of NMS phases increases with irradiation dose and Ni+Mn…”
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6
Development of Software for Determining the Parameters of Pores and Segregations of Alloying Elements in Austenitic Steels after Ion Irradiation
Published in Crystallography reports (01-11-2021)“…SwellingProfile and ElementProfile software packages were developed to construct swelling profiles when processing cross-cut images obtained using scanning…”
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7
Annealing as a Technique for Estimating the Structural Elements Contribution to NPP Materials Service Properties
Published in Physics of metals and metallography (01-08-2019)“…The annealing technique is used to estimate the effect of radiation-induced structural elements on the service properties of the materials used in nuclear…”
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8
Comparison of microstructural features of radiation embrittlement of VVER-440 and VVER-1000 reactor pressure vessel steels
Published in Journal of nuclear materials (01-02-2002)“…Comparative microstructural studies of both surveillance specimens and reactor pressure vessel (RPV) materials of VVER-440 and VVER-1000 light water reactor…”
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9
Assessment of segregation kinetics in water-moderated reactors pressure vessel steels under long-term operation
Published in Journal of nuclear materials (15-08-2016)“…In reactor pressure vessel (RPV) bcc-lattice steels temper embrittlement is developed under the influence of both operating temperature of ∼300 °C and neutron…”
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10
Creation of Digital Opportunities for the Participation of Residents in the Region Development as a Factor of the Government Efficiency
Published in Upravlencheskoe konsulʹtirovanie (23-10-2020)“…No one better than people living in the region can know what is required for the development of the region. The modern government, oriented towards the…”
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11
Milk exosomes as delivery agents for therapy of cancer diseases
Published in Uspehi molekulârnoj onkologii (24-06-2022)“…Exosomes are natural nanovesicles with a diameter of 40–100 nm, which are actively involved in the transfer of biologically active substances and participate…”
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12
Application of the EBSD Method to Study the Fracture Mechanisms of Reactor Pressure Vessels Steels under Operational Factors
Published in Crystallography reports (01-07-2021)“…The mechanisms of degradation of the structure and properties of steels of pressure vessels of pressurized water reactors (PWRs) have been analyzed using…”
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13
Microstructural behavior of VVER-440 reactor pressure vessel steels under irradiation to neutron fluences beyond the design operation period
Published in Journal of nuclear materials (30-06-2005)“…Electron-microscopy and fractographic studies of the surveillance specimens from base and weld metals of VVER-440/213 reactor pressure vessel (RPV) in the…”
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14
Complex study of grain boundary segregation in long-term irradiated reactor pressure vessel steels
Published in Journal of nuclear materials (01-01-2020)“…Grain boundary (GB) embrittlement of reactor pressure vessel steel occurs at the long-term operation through the radiation-enhanced segregation of impurities…”
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15
Experimental assessment of the effectiveness of recovery annealing of VVER-1000 vessels
Published in Atomic energy (New York, N.Y.) (01-02-2011)“…An experimental assessment of the effectiveness of recovery annealing of VVER-1000 vessels on the basis of mechanical tests and structural studies of control…”
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16
Effect of Ni content on thermal and radiation resistance of VVER RPV steel
Published in Journal of nuclear materials (01-06-2015)“…In this paper thermal stability and radiation resistance of VVER-type RPV steels for pressure vessels of advanced reactors with different nickel content were…”
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17
Degradation of RPV steel structure after 45 years of operation in the VVER-440 reactor
Published in Journal of nuclear materials (01-11-2020)“…This paper presents the results of the complex structural studies of RPV steels (weld and base metal from both beltline and nozzle regions) from the…”
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18
Chemical composition effect on VVER-1000 RPV weld metal thermal aging
Published in Journal of nuclear materials (01-10-2015)“…Temperature and fast neutron flux simultaneously affect the material of welded joints of reactor pressure vessels under irradiation. Understanding thermal…”
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19
Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels
Published in Journal of nuclear materials (01-10-2015)“…A complex study of structural state and properties of 18Cr–10Ni–Ti austenitic stainless steel after irradiation in BOR-60 fast research reactor (in the…”
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20
Microstructural evolution of the 42XNM alloy during a severe accident (LOCA)
Published in Journal of nuclear materials (01-04-2022)“…•42XNM alloy (after neutron irradiation and short heat treatment corresponding to LOCA) was studied by TEM and APT.•The grain structure does not undergo…”
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