Перегляд за автором "Tolstolutskaya, G.D."

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Application of hydrogen embritlement models to the blister growth behavior in 12Cr2MoNbVB steel and α -Fe exposed to low-energy D plasma

Nikitin, A.V.; Tolstolutskaya, G.D.; Ruzhytskiy, V.V.; Kopanets, I.E.; Karpov, S.A.; Vasilenko, R.L.; Rostova, G.Y.; Rybalchenko, N.D.; Sungurov, B.S. (Вопросы атомной науки и техники, 2017)

Processes of blisters and associated subsurface cracks nucleation during exposure of 12Cr2MoNbVB ferritic-martensitic steel and α-Fe under glow discharge hydrogen (deuterium) plasma with ion energies of ~ 1 keV and ion ...
Application of nanoindentation for investigation of radiation damage in SS316 stainless steel

Tolmachova, G.N.; Tolstolutskaya, G.D.; Karpov, S.A.; Sungurov, B.S.; Vasilenko, R.L. (Вопросы атомной науки и техники, 2015)

The possibility of application of nanoindentation technique for investigation of mechanical properties (hardness and modulus of elasticity) of SS316 steel irradiated with 1.4 MeV Ar⁺ ions to a dose of 1·10¹⁷ cm⁻² at 900 K ...
Blistering of W, Ta and W-Ta coatings under the influence of particles of low-energy hydrogen plazma

Tolstolutskaya, G.D.; Kuprin, A.S.; Voyevodin, V.N.; Nikitin, A.V.; Ovcharenko, V.D.; Belous, V.A.; Vasilenko, R.L.; Kopanets, I.E. (Вопросы атомной науки и техники, 2017)

The surface topography and deuterium retention in W, Ta and W-Ta coatings under the influence of low-energy deuterium plasma was studied. It was observed formation of blisters as dome and burst or delaminated structures. ...
Characterization of dislocation type defects formed at low-energy deuterium irradiation of SS316 stainless steel

Sungurov, B.S.; Tolstolutskaya, G.D.; Karpov, S.A.; Ruzhytskiy, V.V.; Voyevodin, V.N. (Вопросы атомной науки и техники, 2018)

The nature of small point defect clusters in SS316 austenitic stainless steel irradiated with deuterium ions at room temperature was identified from their behavior under annealing. In this analysis, the defect clusters ...
Comparative study of helium bubble formation in Cr-Fe-Ni-Mn high-entropy alloy and 18Cr10NiTi steel after irradiation and post-irradiation annealing

Kalchenko, А.S.; Karpov, S.A.; Kopanets, I.E.; Tikhonovsky, M.A.; Tolstolutskaya, G.D. (Вопросы атомной науки и техники, 2019)

High entropy alloys (HEAs) are considered for applications in nuclear reactors due to their promising mechanical properties, corrosion and radiation resistance. In order to understand the irradiation effects in HEAs and ...
Comparison of blistering of W bulk and coatings under H₂, D₂ and He plasma irradiation

Nikitin, A.V.; Kuprin, A.S.; Tolstolutskaya, G.D.; Vasilenko, R.L.; Ovcharenko, V.D.; Voyevodin, V.N. (Вопросы атомной науки и техники, 2018)

The surface topography of W bulk prepared by powder sintering (20 μm thickness) and W coatings deposited by cathodic arc evaporation and by argon ion sputtering was studied under the influence of low-energy hydrogen (deuterium) ...
Cooperative effect of displacement damage and inert gas impurities on deuterium retention in austenitic and ferritic-martensitic steels

Karpov, S.A.; Kopanets, I.E.; Ruzhytskyi, V.V.; Sungurov, B.S.; Tolstolutskaya, G.D. (Вопросы атомной науки и техники, 2014)

The behaviour of hydrogen (deuterium) in austenitic 18Cr10NiTi stainless steel and ferritic/martensitic steels EP-450 and EI-852 were investigated. Energetic heavy-ion irradiation has been used for modeling defect cluster ...
Deuterium trapping and sputtering of tungsten coatings exposed to low-energy deuterium plasma

Tolstolutskaya, G.D.; Kuprin, A.S.; Nikitin, A.V.; Kopanets, I.E.; Voyevodin, V.N.; Kolodiy, I.V.; Vasilenko, R.L.; Ilchenko, A.V. (Вопросы атомной науки и техники, 2020)

Processes of sputtering, surface modification and deuterium retention of tungsten coatings were studied under the influence of low-energy (500 eV) deuterium plasma with fluence (2·10²⁴D+/m²) at room temperature. The method ...
Effect of argon-ion irradiation on cavity formation and evolution in 18Cr10NiTi austenitic steel

Tolstolutskaya, G.D.; Karpov, S.A.; Kalchenko, A.S.; Kopanets, I.E.; Nikitin, A.V.; Voyevodin, V.N. (Вопросы атомной науки и техники, 2020)

The swelling behavior of 18Cr10NiTi austenitic stainless steel irradiated with energetic Ar-ions in the dose range of 40…105 displacements per atom (dpa) with simultaneously implanted argon to the levels of 0.08…6.3 at.% ...
Effect of argon-ion irradiation on cavity formation in 18Cr10NiTi austenitic steel and its strengthened version

Kolodiy, I.V.; Karpov, S.A.; Kalchenko, A.S.; Kopanets, I.E.; Tikhonovsky, M.A.; Tolstolutskaya, G.D.; Velikodnyi, A.N.; Voyevodin, V.N. (Вопросы атомной науки и техники, 2020)

The swelling behavior of 18Cr10NiTi austenitic stainless steel and its strengthened by Y₂O₃-ZrO₂ nanooxides version irradiated with 1.4 MeV Ar-ions up to dose 30 displacements per atom (dpa) with simultaneously implanted ...
Effect of argon ion irradiation on hardening and microstructure of ferritic-martensitic steel T91

Voyevodin, V.N.; Tolstolutskaya, G.D.; Karpov, S.A.; Tikhonovsky, M.A.; Tolmachova, G.N.; Kalchenko, A.S.; Vasilenko, R.L.; Kopanets, I.E. (Вопросы атомной науки и техники, 2019)

Ferritic-martensitic steel T91 was irradiated with 1.4 MeV Ar⁺ ions to doses from 0.5 to 7 displacements per atom (dpa) at room temperature. Microstructure characterization was performed using transmission electron microscopy ...
Effect of grain boundary on the cavity formation behavior in 1.4 MeV Ar⁺ irradiated 18Cr10NiTi-ODS steel

Tolstolutskaya, G.D.; Karpov, S.A.; Kalchenko, A.S.; Tikhonovsky, M.A. (Problems of Atomic Science and Technology, 2023)

The formation of cavity denuded zones (DZ) near grain boundary (GB) in 18Cr10NiTi-ODS steel with the addition of Y₂O₃-ZrO₂ nano-oxides irradiated with energetic Ar-ions in the dose range of 40…110 displacements per atom ...
Effect of severe plastic deformation on radiation hardening of T91 ferritic-martensitic steel

Voyevodin, V.N.; Tolstolutskaya, G.D.; Karpov, S.A.; Velikodnyi, A.N.; Tikhonovsky, M.A.; Kalchenko, A.S.; Tolmachova, G.N.; Vasilenko, R.L.; Kopanets, I.E. (Вопросы атомной науки и техники, 2021)

Effect of thermomechanical treatment on radiation hardening behavior in T91 ferritic-martensitic steel was evaluated. An applying of severe plastic deformation (SPD) by the “upsetting-extrusion” method and subsequent heat ...
Hardening of Cr-Fe-Ni-Mn high-entropy alloys caused by the irradiation with argon ions

Tolstolutskaya, G.D.; Rostova, G.Y.; Voyevodin, V.N.; Velikodnyi, A.N.; Tikhonovsky, M.A.; Tolmachova, G.N.; Kalchenko, A.S.; Vasilenko, R.L.; Kopanets, I.E. (Вопросы атомной науки и техники, 2017)

Nanoindentation was used to measure the ion irradiation effect on hardening of Cr-Fe-Ni-Mn high-entropy alloys with different composition. Alloys were irradiated with 1.4 MeV Ar ions at room temperatures and midrange doses ...
High-resolution transmission electron microscopy study of crystallography and morphology of TiC precipitates in argon-irradiated 18Cr10NiTi steel

Kalchenko, A.S.; Karpov, S.A.; Tolstolutskaya, G.D. (Вопросы атомной науки и техники, 2021)

This work encompasses identification of the crystal structure and analysis of the TiC precipitates in 18Cr-10Ni-Ti austenitic stainless steel under Ar-ions irradiation. High resolution transmission electron microscopy ...
Ion-implanted deuterium release behavior from Li-based advanced ceramics

Tolstolutskaya, G.D.; Karpov, S.A.; Ruzhytskiy, V.V.; Nikitin, A.V. (Problems of Atomic Science and Technology, 2022)

The behavior of ion-implanted deuterium in advanced lithium orthosilicate (Li₄SiO₄) pellets with addition of lithium metatitanate (Li₂TiO₃), and in reference Li₄SiO₄ pellets, has been studied. Thermal desorption spectroscopy ...
Kinetics of blisters growth in a deformed α-Fe at low-energy deuterium plasma exposure

Nikitin, A.V.; Tolstolutskaya, G.D.; Kopanets, I.E.; Karpov, S.A.; Ruzhytskiy, V.V. (Вопросы атомной науки и техники, 2018)

The results of the study of surface topography evolution and the features of deuterium interaction with α-Fe under glow discharge 1 keV deuterium ions bombardment at Troom up to ion fluence of 3.4·10²⁴ D/m² are ...
Mechanisms of radiation damage and development of structural materials for operating and advanced nuclear reactors

Voyevodin, V.N.; Tolstolutskaya, G.D.; Tikhonovsky, M.A.; Kuprin, A.S.; Kalchenko, A.S. (Вопросы атомной науки и техники, 2021)

Safety of nuclear reactor (NR) and economic of nuclear power are determined to high degree by structural materials. Study of reasons of change of physical-mechanical properties of materials and of their dimensional stability ...
Microstructure evolution and deuterium trapping in low-energy cascades after irradiation of SS316 stainless steel

Karpov, S.A.; Tolstolutskaya, G.D.; Sungurov, B.S.; Ruzhytskiy, V.V. (Вопросы атомной науки и техники, 2017)

The release profile of deuterium from SS316 austenitic steel irradiated with low-energy deuterium ions was studied using thermal desorption spectroscopy as well as steel microstructure evolution after deuterium implantation ...
Morphology and sputtering of tungsten nitrides coatings exposed to deuterium plasma

Tolstolutskaya, G.D.; Kuprin, A.S.; Nikitin, A.V.; Vasilenko, R.L. (Problems of Atomic Science and Technology, 2023)

Processes of sputtering, surface modification and change in the stoichiometric composition of W and WN coatings deposited on stainless steel by cathodic arc evaporation were studied under the influence of low-energy (500 ...

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