Search Results - "Kulsartov, T."

Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation by Kulsartov, T., Kenzhina, I., Chikhray, Ye, Zaurbekova, Zh, Kenzhin, Ye, Aitkulov, M., Gizatullin, Sh, Dyussambayev, D.

“…In this work, the analysis of experimental results on the irradiation of lithium ceramics Li2TiO3 is presented. Lithium ceramics samples were irradiated at the…”
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Modeling of hydrogen isotopes release from lithium ceramics Li2TiO3 during in-situ experiments using vacuum extraction method by Kulsartov, T., Kenzhina, I., Tolenova, A., Kenzhin, Ye, Shaimerdenov, A., Nesterov, Ye, Gizatulin, Sh, Chikhray, Ye, Gluchshenko, A.

“…Lithium ceramics Li2TiO3 in spherical granules (pebbles) is one of the most promising functional material for use in breeder blankets of a fusion reactor. In…”
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Radiation Resistance of Single-Mode Optical Fibers at λ = 1.55 μm Under Irradiation at IVG.1M Nuclear Reactor by Kashaykin, P. F., Tomashuk, A. L., Vasiliev, S. A., Britskiy, V. A., Ignatyev, A. D., Ponkratov, Yu. V., Kulsartov, T. V., Samarkhanov, K. K., Gnyrya, V. S., Zarenbin, A. V., Semjonov, S. L.

“…Radiation-induced attenuation (RIA) at a wavelength of <inline-formula> <tex-math notation="LaTeX">\lambda = 1.55\,\,\mu \text{m} </tex-math></inline-formula>…”
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Radiation Resistance of Fiber Bragg Gratings under Intense Reactor Irradiation by Kashaykin, P. F., Vasiliev, S. A., Tomashuk, A. L., Ignatyev, A. D., Britskii, V. A., Shaimerdenov, A. A., Akhanov, A. M., Silnyagin, P. P., Kulsartov, T. V.

“…Radiation-induced attenuation (RIA) of light and radiation-induced shift (RIS) of the resonant wavelength in fiber Bragg gratings (FBGs) during reactor…”
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Effect of low-temperature neutron irradiation on the properties of titanium beryllide by Shaimerdenov, A., Akhanov, A., Gizatulin, Sh, Nessipbay, A., Shakirov, B., Askerbekov, S., Kulsartov, T., Kenzhina, I., Larionov, A., Akayev, S., Udartsev, S.

“…•The influence of low-temperature neutron irradiation on the properties of titanium beryllide produced by the industrial method is shown.•Samples of titanium…”
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Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation by Kulsartov, T., Tazhibayeva, I., Ponkratov, Yu, Gordienko, Yu, Zaurbekova, Zh, Baklanov, V., Chikhray, Ye, Skakov, M., Koyanbayev, Ye, Korovikov, A., Nesterov, E.

“…•The results of a study of tritium generation and release from the lithium CPS under neutron irradiation are described.•The distribution of free tritium atoms…”
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Radiation resistance of single-mode optical fibres with view to in-reactor applications by Kashaykin, P.F., Tomashuk, A.L., Vasiliev, S.A., Ignatyev, A.D., Shaimerdenov, A.A., Ponkratov, Yu.V., Kulsartov, T.V., Kenzhin, Y.A., Kh. Gizatulin, Sh, Zholdybayev, T.K., Chikhray, Y.V., Semjonov, S.L.

“…•Reliability of single-mode fibres is tested with view to the whole ITER lifetime.•Polyimide-coated fibres fail mechanically during ITER-relevant…”
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Tritium migration in the materials proposed for fusion reactors: Li2TiO3 and beryllium by Kulsartov, T.V., Gordienko, Yu.N., Tazhibayeva, I.L., Kenzhin, E.A., Barsukov, N.I., Sadvakasova, A.O., Kulsartova, A.V., Zaurbekova, Zh.A.

“…The results of tritium and helium gas release from lithium ceramics samples Li2TiO3 irradiated at the WWR-K reactor (Almaty, Kazakhstan) and from beryllium…”
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Reactor studies of tritium release from lead-lithium eutectic Li15.7Pb with deuterium over the sample by Tazhibayeva, I.L., Kulsartov, T.V., Baklanova, Yu.Yu, Zaurbekova, Zh.A., Gordienko, Yu, Ponkratov, Yu.V.

“…•Studies of tritium generation and release from Li15.7Pb eutectic under various temperatures.•Experiments on the release of tritium in the presence and absence…”
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Study of Li2TiO3 + 5 mol% TiO2 lithium ceramics after long-term neutron irradiation by CHIKHRAY, Y, SHESTAKOV, V, MAKSIMKIN, O, TURUBAROVA, L, OSIPOV, I, KULSARTOV, T, KUYKABAYEBA, A, TAZHIBAYEVA, I, KAWAMURA, H, TSUCHIYA, K

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Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 (out-of-pile tests) by KULSARTOV, T. V, HAYASHI, K, NAKAMICHI, M, AFANASYEV, S. E, SHESTAKOV, V. P, CHIKHRAY, Y. V, KENZHIN, E. A, KOLBAENKOV, A. N

“…Ceramic coating on structural materials has been considered to be used as a tritium permeation barrier for fusion power plants. In the present study, a series…”
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Tritium accumulation and release from Li2TiО3 during long-term irradiation in the WWR-K reactor by Tazhibayeva, I., Beckman, I., Shestakov, V., Kulsartov, T., Chikhray, E., Kenzhin, E., Kiykabaeva, A., Kawamura, H., Tsuchiya, K.

“…Proposed mathematical and software analysis of reactor experiments allowed interpretation of the experimental results of a tritium release study. Tritium was…”
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Studies of reactor irradiation effect on hydrogen isotope release from vanadium alloy V4Cr4Ti by Kulsartov, T., Shestakov, V., Chikhray, Y., Kenzhin, Y., Kolbayenkov, A., Tazhibayeva, I.

“…Vanadium alloys are most promising materials being considered for lithium blanket-breeder in future fusion reactors. The primary reason for these stems from…”
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Material science activities for fusion reactors in Kazakhstan by Tazhibayeva, I., Kenzhin, E., Shestakov, V., Chikhray, Y., Kulsartov, T., Azizov, E., Filatov, O., Chernov, V.

“…The paper describes the results of fusion reactor materials R&D activities in the Republic of Kazakhstan in the framework of the fusion material national…”
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Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor by CHIKHRAY, Y, SHESTAKOV, V, KULSARTOV, T, TAZHIBAYEVA, I, KAWAMURA, H, KUYKABAEVA, A

“…A 220-day irradiation of Li2TiO3 ceramics with 96% enrichment of isotope 6Li was carried out at WWRK reactor. One of the study goals was to examine tritium…”
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Development of the reactor lithium ampoule device for research of spectral-luminescent characteristics of nuclear-excited plasma by Batyrbekov, E.G., Gordienko, Yu. N., Ponkratov, Yu. V., Khasenov, M.U., Tazhibayeva, I.L., Barsukov, N.I., Kulsartov, T.V., Zaurbekova, Zh. A., Tulubayev, Ye. Yu, Skakov, M.K.

“…•The development procedure of the ampoule device for experiments with nuclear-excited plasma under neutron irradiation is described.•The methods of nuclear…”
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In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 by NAKAMICHI, M, KULSANOV, T. V, HAYASHI, K, AFANASYEV, S. E, SHESTAKOV, V. P, CHIKHRAY, Y. V, KENZHIN, E. A, KOLBAENKOV, A. N

“…In-pile experiments on tritium permeation were conducted for ferritic steel (F82H) with and without a ceramic coating of Cr2O3-SiO2 including CrPO4, using a…”
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Experiments on tritium generation and yield from lithium ceramics during neutron irradiation by Blynskiy, P., Chikhray, Ye, Kulsartov, T., Gabdullin, M., Zaurbekova, Zh, Kizane, G., Kenzhin, Ye, Tolenova, A., Nesterov, E., Shaimerdenov, A.

“…The vacuum extraction method with a mass spectrometry registration of tritium is presented in paper. It can provide a full-range analysis of gas phase…”
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Reactor experiments on irradiation of two-phase lithium ceramics Li2TiO3/Li4SiO4 of various ratios by Kulsartov, T., Zaurbekova, Zh, Knitter, R., Chikhray, Ye, Kenzhina, I., Askerbekov, S., Shaimerdenov, A., Kizane, G.

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Analysis of reactor experiments to study the transfer processes of generated tritium in lithium cps (capillary-porous system) by Askerbekov, S., Kenzhina, I., Kulsartov, T., Chikhray, Ye, Tazhibayeva, I., Ponkratov, Yu, Gordienko, Yu, Zaurbekova, Zh, Gabdullin, M., Kadyrzhanov, K., Nesterov, E.

“…To date, there have been many studies on the possibility of using lithium CPS as a plasma-facing material in fusion reactors. For use such liquid-lithium…”
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