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Timur Kulsartov
Timur Kulsartov
National Nuclear Center of the Republic of Kazakhstan
Verified email at physics.kz
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Cited by
Year
Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3–SiO2 including CrPO4 (out-of-pile tests)
TV Kulsartov, K Hayashi, M Nakamichi, SE Afanasyev, VP Shestakov, ...
Fusion engineering and design 81 (1-7), 701-705, 2006
592006
In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3–SiO2 including CrPO4
M Nakamichi, TV Kulsartov, K Hayashi, SE Afanasyev, VP Shestakov, ...
Fusion engineering and design 82 (15-24), 2246-2251, 2007
372007
Status of design and experimental activity on module of lithium divertor for KTM tokamak
IE Lyublinski, AV Vertkov, MY Zharkov, VV Semenov, SV Mirnov, ...
Fusion engineering and design 88 (9-10), 1862-1865, 2013
352013
Tritium migration in the materials proposed for fusion reactors: Li2TiO3 and beryllium
TV Kulsartov, YN Gordienko, IL Tazhibayeva, EA Kenzhin, NI Barsukov, ...
Journal of Nuclear Materials 442 (1-3), S740-S745, 2013
332013
Radiation resistance of single-mode optical fibres with view to in-reactor applications
PF Kashaykin, AL Tomashuk, SA Vasiliev, AD Ignatyev, ...
Nuclear Materials and Energy 27, 100981, 2021
292021
Research of reactor radiation influence upon processes of hydrogen isotopes interaction with materials of the fusion facility
AO Sadvakassova, IL Tazhibayeva, EA Kenzhin, ZA Zaurbekova, ...
Fusion Science and Technology 60 (1T), 9-15, 2011
282011
Surface effects in diffusion measurements: deuterium permeation through martensitic steel
A Pisarev, V Shestakov, S Kulsartov, A Vaitonene
Physica Scripta 2001 (T94), 121, 2001
282001
Study of Li2TiO3+ 5 mol% TiO2 lithium ceramics after long-term neutron irradiation
Y Chikhray, V Shestakov, O Maksimkin, L Turubarova, I Osipov, ...
Journal of nuclear materials 386, 286-289, 2009
252009
Hydrogen recycling at plasma facing materials
CH Wu
Springer Science & Business Media, 2000
242000
Results of neutron irradiation of liquid lithium saturated with deuterium
I Tazhibayeva, Y Ponkratov, T Kulsartov, Y Gordienko, M Skakov, ...
Fusion Engineering and Design 117, 194-198, 2017
232017
Tritium accumulation and release from Li2TiО3 during long-term irradiation in the WWR-K reactor
I Tazhibayeva, I Beckman, V Shestakov, T Kulsartov, E Chikhray, ...
Journal of nuclear materials 417 (1-3), 748-752, 2011
232011
Material science activities for fusion reactors in Kazakhstan
I Tazhibayeva, E Kenzhin, V Shestakov, Y Chikhray, T Kulsartov, E Azizov, ...
Journal of nuclear materials 386, 15-18, 2009
232009
Interaction of tritium and helium with lead–lithium eutectic under reactor irradiation
I Tazhibayeva, T Kulsartov, N Barsukov, Y Gordienko, Y Ponkratov, ...
Fusion Engineering and Design 89 (7-8), 1486-1490, 2014
212014
Studies of two-phase lithium ceramics Li4SiO4-Li2TiO3 under conditions of neutron irradiation
T Kulsartov, Z Zaurbekova, R Knitter, A Shaimerdenov, Y Chikhray, ...
Nuclear Materials and Energy 30, 101129, 2022
202022
Experiments on tritium generation and yield from lithium ceramics during neutron irradiation
P Blynskiy, Y Chikhray, T Kulsartov, M Gabdullin, Z Zaurbekova, G Kizane, ...
International Journal of Hydrogen Energy 46 (13), 9186-9192, 2021
202021
Gas driven deuterium permeation through F82H martensitic steel
V Shestakov, A Pisarev, V Sobolev, S Kulsartov, I Tazhibaeva
Journal of nuclear materials 307, 1494-1497, 2002
202002
Radiation Resistance of Single-Mode Optical Fibers at λ = 1.55 μm Under Irradiation at IVG.1M Nuclear Reactor
PF Kashaykin, AL Tomashuk, SA Vasiliev, VA Britskiy, AD Ignatyev, ...
IEEE Transactions on Nuclear Science 67 (10), 2162-2171, 2020
182020
Study of properties of tungsten irradiated in hydrogen atmosphere
I Tazhibayeva, M Skakov, V Baklanov, E Koyanbayev, A Miniyazov, ...
Nuclear Fusion 57 (12), 126062, 2017
182017
Study of tritium and helium generation and release from lead-lithium eutectics Li15. 7Pb under neutron irradiation
T Kulsartov, Z Zaurbekova, I Tazhibayeva, Y Ponkratov, V Gnyrya, ...
Fusion Engineering and Design 146, 1317-1320, 2019
162019
Study of Tritium and Helium Release from Irradiated Lithium Ceramics Li2TiO3
T Kulsartov, I Tazhibayeva, Y Gordienko, E Chikhray, K Tsuchiya, ...
Fusion Science and Technology 60 (3), 1139-1142, 2011
162011
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