Comparative Evaluations of Nuclear Fuel Breeding Rate in Hybrid Fission-Fusion Reactor with U and Th von Leshukov, A. Yu, Lopatkin, A. V., Lukasevich, I. B., Razmerov, A. V., Strebkov, Yu. S., Sysoev, A. G.

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Design and Analysis of Solid Blanket Concept for Hybrid Fusion-Fission Facility von Strebkov, Yu. S., Afremov, D. A., Arhipov, O. P., Vershinin, I. V., Danilov, I. V., Ivanov, V. O., Kozlov, S. A., Korostelev, A. B., Larionov, I. A., Leshukov, A. Yu, Loginov, D. Yu, Lopatkin, A. V., Lukasevich, I. B., Mezhina, E. R., Poddubnyi, I. I., Pulinets, A. A., Razmerov, A. V., Sviridenko, M. N., Sysoev, A. G., Cherepnin, Yu. S.

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ITER Vessel Internals: Origination and Development von Kaplienko, A. V., Strebkov, Yu. S., Danilov, I. V., Korostelev, A. B., Solov’ev, O. V., Sviridenko, M. N., Poddubnyi, I. I.

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Design, Manufacture, and Experimental Serviceability Validation of ITER Blanket Components von Leshukov, A. Yu, Strebkov, Yu. S., Sviridenko, M. N., Safronov, V. M., Putrik, A. B.

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Optimization and adjustment of impact set-up for testing of insulated pads of ITER blanket module connectors and first wall von Kolganov, V., Poddubnyi, I., Timofeev, S., Sviridenko, M., Razmerov, A., Strebkov, Yu, Danilov, I., Khomiakov, S., Parshutin, E., Malyshev, A., Tagiev, R., Putrik, A., Safronov, V., Egorov, K., Eaton, R., Raffray, R.

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Analyses results of the EHF FW Panel with welded fingers von Sviridenko, M.N., Leshukov, A.Yu, Razmerov, A.V., Tomilov, S.N., Danilov, I.V., Strebkov, Yu.S., Mazul, I.V., Labusov, A., Gervash, A.A., Belov, A.V., Semichev, D.

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Design development and analytical assessment of LLCB TBM in Russian Federation during 2012–2013 von Leshukov, A.Yu, Kapyshev, V.K., Kartashev, I.A., Kovalenko, V.G., Razmerov, A.V., Sviridenko, M.N., Strebkov, Yu.S., Kirillov, I.R., Obukhov, D.M., Vitkovskiy, I.V., Pertsev, D.A.

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Assessment of critical level of shear stresses in tribocouples of Аl2O3 and metal details of ITER blanket modules von Zaitsev, A. N., Strebkov, Yu. S., Leshukov, A. Yu, Ivanov, V. M., Kuksenova, L. I., Sachek, B. Ya, Mezrin, A. M., Aleksandrova, Yu. P.

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Overview of JSC “NIKIET” activity on ITER Procurement Arrangements von Leshukov, A.Yu, Dragunov, Yu. G., Strebkov, Yu. S., Kirillov, S.Yu, Makarov, S.V., Trofimovich, P.D., Dubinin, G.V., Maksimov, V.A., Sviridenko, M.N., Razmerov, A.V., Parshutin, E.V., Khomyakov, S.E., Kolganov, V.Yu, Zhmakin, A.V., Belyakov, V.A., Mazul, I.V., Gervash, A.A., Safronov, V.M., Romannikov, A.N., Eaton, R., Egorov, K.

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Progress in design development and research activity on LLCB TBM in Russian Federation von Kovalenko, V.G., Leshukov, A.Yu, Tomilov, S.N., Razmerov, A.V., Strebkov, Yu. S., Sviridenko, M.N., Kirillov, I.R., Obukhov, D.M., Pertsev, D.A., Vitkovsky, I.V.

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The effect of irradiation on tensile properties and fracture toughness of CuCrZr and CuCrNiSi alloys von Kalinin, G.M., Artyugin, A.S., Yvseev, M.V., Shushlebin, V.V., Sinelnikov, L.P., Strebkov, Yu.S.

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Development of fabrication technology and investigation of properties of steel-to-bronze joints suggested for ITER HHF components von Kalinin, G.M., Abramov, V.Ya, Gervash, A.A., Zolotarev, V.B., Krestnikov, N.S., Mazul, I.V., Strebkov, Yu.S., Fabritsiev, S.A.

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Properties of unirradiated and irradiated Ti–6Al–4V alloy for ITER flexible connectors von Rodchenkov, B.S., Evseev, M.V., Strebkov, Yu.S., Sinelnikov, L.P., Shushlebin, V.V.

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Russian concept for a DEMO-S demonstration fusion power reactor von Kolbasov, B.N., Belyakov, V.A., Bondarchuk, E.N., Borisov, A.A., Kirillov, I.R., Leonov, V.M., Shatalov, G.E., Sokolov, Yu.A., Strebkov, Yu.S., Vasiliev, N.N.

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Fourth International Scientific and Technical Conference on Innovative Projects and Technologies of Nuclear Power (MNTK NIKIET-2016) von Dragunov, Yu. G., Gabaraev, B. A., Dzhalavyan, A. V., Lopatkin, A. V., Pimenov, A. O., Strebkov, Yu. S., Lemekhov, V. V., Moiseev, A. V., Cherepnin, Yu. S., Arkhipov, O. P., Evropin, S. V., Ryasnyanskii, S. G., Kulikov, D. G., Afremov, D. A., Danilov, I. V.

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Irradiation behavior of Ti–4Al–2V (ΠT-3B) alloy for ITER blanket modules flexible attachment von Rodchenkov, B.S., Kozlov, A.V., Kuznetsov, Yu.G., Kalinin, G.M., Strebkov, Yu.S.

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Thermal mechanical analysis of the Enhanced Heat Flux First Wall panel von Sviridenko, M.N., Leshukov, A.Yu, Razmerov, A.V., Danilov, I.V., Strebkov, Yu.S., Mazul, I.V., Alekseev, A.B.

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Overview of Russian Federation activity on the LLCB TBM design and analysis von Leshukov, A. Yu, Kapyshev, V.K., Kartashev, I.A., Kovalenko, V.G., Razmerov, A.V., Sviridenko, M.N., Strebkov, Yu. S., Kirillov, I.R., Obukhov, D.M., Vitovskiy, I.V., Pertsev, D.A.

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Strength analysis results for the RF “modified” option of the shielding block for ITER blanket module von Sviridenko, M.N., Leshukov, A.Yu, Razmerov, A.V., Strebkov, Yu.S.

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The technological features of manufacturing process for RF CHC TBM von Sviridenko, M.N., Kapyshev, V.K., Kovalenko, V.G., Makarov, S.A., Leshukov, A.Yu, Razmerov, A.V., Strebkov, Yu.S.

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