Flexible Electrode Made of Graphene and Few-Layer Graphite von Abdullin, Kh. A., Chikhray, E. V., Gabdullin, M. T., Ismailov, D. V.

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Hydrogen release of reactor irradiated RGT-graphite von Tazhibaeva, I.L., Klepikov, A.Kh, Shestakov, V.P., Romanenko, O.G., Chikhray, E.V., Kenzhin, E.A., Cherepnin, Yu.S., Tikhomirov, L.N., Zverev, V.A.

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Hydrogen release from irradiated vanadium alloy V–4Cr–4Ti von Klepikov, A.Kh, Romanenko, O.G, Chikhray, Y.V, Tazhibaeva, I.L, Shestakov, V.P, Longhurst, G.R

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Hydrogen permeability measurements of 08Cr18Ni10Ti stainless steel in fission reactor irradiation conditions von Tazhibaeva, I. L., Shestakov, V. P., Chikhray, E. V., Romanenko, O. G., Klepikov, A. Kh, Cherepnin, Yu. S., Tikhomirov, L. N., Kenzhin, E. A., Basov, A. V.

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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) von KULSARTOV, T. V, HAYASHI, K, NAKAMICHI, M, AFANASYEV, S. E, SHESTAKOV, V. P, CHIKHRAY, Y. V, KENZHIN, E. A, KOLBAENKOV, A. N

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In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 von NAKAMICHI, M, KULSANOV, T. V, HAYASHI, K, AFANASYEV, S. E, SHESTAKOV, V. P, CHIKHRAY, Y. V, KENZHIN, E. A, KOLBAENKOV, A. N

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Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation von Kulsartov, T., Tazhibayeva, I., Ponkratov, Yu, Gordienko, Yu, Zaurbekova, Zh, Baklanov, V., Chikhray, Ye, Skakov, M., Koyanbayev, Ye, Korovikov, A., Nesterov, E.

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Material science activities for fusion reactors in Kazakhstan von Tazhibayeva, I., Kenzhin, E., Shestakov, V., Chikhray, Y., Kulsartov, T., Azizov, E., Filatov, O., Chernov, V.

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Tritium accumulation and release from Li2TiО3 during long-term irradiation in the WWR-K reactor von Tazhibayeva, I., Beckman, I., Shestakov, V., Kulsartov, T., Chikhray, E., Kenzhin, E., Kiykabaeva, A., Kawamura, H., Tsuchiya, K.

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Tritium accumulation and release from Li sub(2Ti[ETH]) sub(3) during long-term irradiation in the WWR-K reactor von Tazhibayeva, I, Beckman, I, Shestakov, V, Kulsartov, T, Chikhray, E, Kenzhin, E, Kiykabaeva, A, Kawamura, H, Tsuchiya, K

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Hydrogen release from reactor-irradiated beryllium von Klepikov, A.Kh, Tazhibaeva, I.L., Shestakov, V.P., Romanenko, O.G., Chikhray, Y.V., Kenzhin, E.A., Cherepnin, Yu.S., Tikhomirov, L.N.

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Influence of loading method on hydrogen retention and release from beryllium von Klepikov, A.Kh, Tazhibaeva, I.L., Romanenko, O.G., Chikhray, Y.V., Shestakov, V.P., Kenzhin, E.A.

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Tritium accumulation and release from Li2TiO3 during long-term irradiation in the WWR-K reactor von TAZHIBAYEVA, I, BECKMAN, I, SHESTAKOV, V, KULSARTOV, T, CHIKHRAY, E, KENZHIN, E, KIYKABAEVA, A, KAWAMURA, H, TSUCHIYA, K

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Material science activities for fusion reactors in Kazakhstan von TAZHIBAYEVA, I, KENZHIN, E, SHESTAKOV, V, CHIKHRAY, Y, KULSARTOV, T, AZIZOV, E, FILATOV, O, CHERNOV, V

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Influence of loading method on hydrogen retention and release from beryllium von Klepikov, A K, Tazhibaeva, I L, Romanenko, O G, Chikhray, Y V, Shestakov, V P, Kenzhin, E A

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Some peculiarities of hydrogen interaction with beryllium during in-pile irradiation von Tazhibaeva, I. L., Klepikov, A. Kh, Shestakov, V. P., Romanenko, O. G., Chikhray, Y. V., Kenzhin, E. A., Cherepninand, Yu. S., Tikhomirov, L. N.

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Influence of loading method on hydrogen retention and release from beryllium von KLEPIKOV, A. K, TAZHIBAEVA, I. L, ROMANENKO, O. G, CHIKHRAY, Y. V, SHESTAKOV, V. P, KENZHIN, E. A

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