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Виктор Владимирович Бакланов

Observed names: Baklanov V., Baklanov, V, Baklanov, Viktor, V V Baklanov, V. Baklanov, V. V. Baklanov, V.V. Baklanov, Viktor Baklanov, Viktor V. BAKLANOV, Viktor V. Baklanov, В. В. Бакланов
ORCID: 0000-0001-7627-8752
Observed ORCID: 0000-0001-7627-8752
OpenAlex ID: A5036730304
Study of properties of tungsten irradiated in hydrogen atmosphere
2017 · I. Tazhibayeva, M. Skakov, et al. · Nuclear Fusion · 24
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Interaction of tritium and helium with lead–lithium eutectic under reactor irradiation
2014 · Irina Tazhibayeva, Timur Kulsartov, et al. · Fusion Engineering and Design · 23
The BN-350 Reactor Decommissioning: Quantitative Analysis and Prospects for Solid Radioactive Waste Management
2025 · Nurzhan Mukhamedov, Viktor Baklanov, et al. · Energies · 16
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Influence of the Carbidized Tungsten Surface on the Processes of Interaction with Helium Plasma
2022 · Mazhyn Skakov, Arman Miniyazov, et al. · Materials · 16
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Zirconium carbide coating for corium experiments related to water-cooled and sodium-cooled reactors
2011 · K. Plevacova, C. Journeau, et al. · Journal of Nuclear Materials · 15
Artificial radionuclides in the plant cover around nuclear fuel cycle facilities
2024 · Natalya Larionova, Anna Toporova, et al. · PLoS ONE · 12
Investigation of the interaction of liquid tin-lithium alloy with austenitic stainless steel at high temperatures
2023 · Yu.V. Ponkratov, K.K. Samarkhanov, et al. · Fusion Engineering and Design · 12
La-Cu Electrode Material For Low Temperature Solid Oxide Fuel Cells
2023 · Mazhyn K. Skakov, Sana K. Kabdrakhmanova, et al. · ES Materials & Manufacturing · 11
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Influence of temperature on tungsten carbide formation in a beam plasma discharge
2021 · G K Zhanbolatova, V V Baklanov, et al. · Journal of Physics Conference Series · 10
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Investigation of hydrogen isotopes interaction processes with lithium under neutron irradiation
2016 · Zhanna Zaurbekova, Mazhyn Skakov, et al. · Fusion Engineering and Design · 9
Determination of tritium generation and release parameters at lithium CPS under neutron irradiation
2016 · Yuriy Ponkratov, Viktor Baklanov, et al. · Fusion Engineering and Design · 9
Severe accident research in the core degradation area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center
2012 · D. Bottomley, J. Stuckert, et al. · Nuclear Engineering and Design · 9
On the Possibility of Forming a Corium Pool by Induction Heating in a Melt Trap of the Lava-B Facility
2023 · Mazhyn Skakov, Viktor Baklanov, et al. · Applied Sciences · 8
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Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation
2017 · T. Kulsartov, I. Tazhibayeva, et al. · Fusion Engineering and Design · 8
High-temperature test of tin-lithium CPS under deuterium plasma irradiation conditions
2023 · Yu.V. Ponkratov, K.K. Samarkhanov, et al. · Journal of Nuclear Materials · 7
Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor
2023 · A. V. Kaplienko, V. V. Lemekhov, et al. · Atomic Energy · 7
Structural and Phase Transformations in Alloys during Spark Plasma Sintering of Ti + 23.5 at % Al + 21 at % Nb Powder Mixtures
2018 · B. K. Karakozov, M. K. Skakov, et al. · Inorganic Materials · 7
Method of out-of-pile high-temperature tests of low-melting materials in conditions of modeling a severe nuclear reactor accident
2024 · Kuanyshbek Toleubekov, Mazhyn Skakov, et al. · International Journal of Advanced Nuclear Reactor Design and Technology · 6
Effect of spark plasma sintering temperature on structure and phase composition of Ti-Al-Nb-based alloys
2017 · Sherzod Kurbanbekov, Mazhyn Skakov, et al. · Materials Testing · 6
Investigation of tritium and helium generation and release from tin-lithium alloy under neutron irradiation
2025 · Yu. Ponkratov, Yu. Gordienko, et al. · Journal of Nuclear Materials · 5
Investigation of the interaction between corium and metal-coolers at the VCG-135 test bench in the conditions of a severe accident
2024 · Mazhyn Skakov, Viktor Baklanov, et al. · Nuclear Engineering and Design · 5
Experiment and new analysis model simulating in-place cooling of a degraded core in severe accidents of sodium-cooled fast reactors
2023 · Yuya Imaizumi, Mitsuhiro Aoyagi, et al. · Annals of Nuclear Energy · 5
Experimental Simulation of Decay Heat of Corium at the Lava-B Test-Bench
2023 · M. K. Bekmuldin, М. K. Skakov, et al. · Nuclear Technology · 5
Development of Evaluation Method for In-place Cooling of Residual Core Materials in Core Disruptive Accidents of Sfrs
2019 · Yuya Imaizumi, Mitsuhiro Aoyagi, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 5
Changes in mechanical properties and structure of electrolytic plasma treated × 12 CrNi 18 10 Ti stainless steel
2017 · Sherzod Kurbanbekov, Mazhyn Skakov, et al. · Materials Testing · 5
Works count: 81
Citation count: 311
H-index: 9
I10-index: 9
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