Search Results - "STREBKOV, Yu. S"

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

“…The role and place of NIKIET, as one of the leading design organizations in the nuclear industry, in the joint implementation of the large-scale international…”
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Design, Manufacture, and Experimental Serviceability Validation of ITER Blanket Components by Leshukov, A. Yu, Strebkov, Yu. S., Sviridenko, M. N., Safronov, V. M., Putrik, A. B.

“…In 2014, the Russian Federation and the ITER International Organization signed two Procurement Arrangements (PAs) for ITER blanket components: 1.6.P1ARF.01…”
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Analyses results of the EHF FW Panel with welded fingers by 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.

“…•The design of FW panel with welded fingers has been developed.•The FW panel with welded fingers has been analyzed.•The pressure drop in FW panel coolant path…”
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Design development and analytical assessment of LLCB TBM in Russian Federation during 2012–2013 by 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.

“…•The detailed design of LLCB TBM has been developed.•The neutronic calculations demonstrate the feasibility of the LLCB concept for applying tritium…”
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Assessment of critical level of shear stresses in tribocouples of Аl2O3 and metal details of ITER blanket modules by Zaitsev, A. N., Strebkov, Yu. S., Leshukov, A. Yu, Ivanov, V. M., Kuksenova, L. I., Sachek, B. Ya, Mezrin, A. M., Aleksandrova, Yu. P.

“…The shear strength of plasma-sprayed electroinsulating Аl 2 O 3 coating has been determined for blanket modules of a thermonuclear reactor in a friction couple…”
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Comparative Evaluations of Nuclear Fuel Breeding Rate in Hybrid Fission-Fusion Reactor with U and Th by Leshukov, A. Yu, Lopatkin, A. V., Lukasevich, I. B., Razmerov, A. V., Strebkov, Yu. S., Sysoev, A. G.

“…A nuclear fuel-breeding blanket of a hybrid fission-fusion reactor is considered in this work. The blanket design uses the tight layout of cylindrical…”
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Development of fabrication technology and investigation of properties of steel-to-bronze joints suggested for ITER HHF components by Kalinin, G.M., Abramov, V.Ya, Gervash, A.A., Zolotarev, V.B., Krestnikov, N.S., Mazul, I.V., Strebkov, Yu.S., Fabritsiev, S.A.

“…When developing fabrication process for ITER High Heat Flux components, special attention shall be paid to the production of reliable joints between heat sink…”
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Russian concept for a DEMO-S demonstration fusion power reactor by 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.

“…Conceptual design studies for a tokamak-based demonstration fusion reactor have been carried out in Russia since 1991. The preferred concept was a steady-state…”
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Irradiation behavior of Ti–4Al–2V (ΠT-3B) alloy for ITER blanket modules flexible attachment by Rodchenkov, B.S., Kozlov, A.V., Kuznetsov, Yu.G., Kalinin, G.M., Strebkov, Yu.S.

“…Titanium alloys are recommended as a material to manufacture flexible attachments of the shield blanket modules in the ITER reactor owing to their advantageous…”
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Design and Analysis of Solid Blanket Concept for Hybrid Fusion-Fission Facility by 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.

“…The article discusses the results of conceptual design and analysis for solid blanket of a hybrid fusion-fission facility based on a tokamak-type fusion…”
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The technological features of manufacturing process for RF CHC TBM by Sviridenko, M.N., Kapyshev, V.K., Kovalenko, V.G., Makarov, S.A., Leshukov, A.Yu, Razmerov, A.V., Strebkov, Yu.S.

“…The development of manufacturing technology for the ceramic helium-cooled test blanket module (CHC TBM) is performed in the framework of the concept for RF…”
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The modified RF concept of CHC experimental module for testing on H–H iter phase by Leshukov, A.Yu, Kapyshev, V.K., Kovalenko, V.G., Makarov, S.A., Razmerov, A.V., Sviridenko, M.N., Strebkov, Yu.S.

“…The development of ceramic helium-cooled experimental module (CHC EM) is a part of RF concept for the Federal Government program to master the fusion nuclear…”
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Microstructure investigation of bronze/steel brazed joints proposed for HHF components of ITER manufacturing by Kalinin, G.M., Krestnikov, N.S., Jarovinskiy, Yu.L., Makhin, I.D., Nikolaev, V.V., Skladnov, K.S., Strebkov, Yu.S., Zolotarev, V.B.

“…Brazing is considered as one of the perspective option of high heat flux components of ITER manufacturing. CuCrZr bronze, austenitic steel AISI 321-type and…”
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Progress in design development and research activity on LLCB TBM in Russian Federation by 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.

“…•Progress in RF LLCB TBM design and supporting R&D since conceptual design activity is presented.•Hydrodynamic, transient thermal and structural analysis of…”
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Overview of JSC “NIKIET” activity on ITER Procurement Arrangements by 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.

“…The two following ITER blanket-relevant Procurement Arrangements (PA) were signed by Russian Federation and ITER Organization in 2014: 1)1.6.P1ARF.01 “Blanket…”
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The effect of irradiation on tensile properties and fracture toughness of CuCrZr and CuCrNiSi alloys by Kalinin, G.M., Artyugin, A.S., Yvseev, M.V., Shushlebin, V.V., Sinelnikov, L.P., Strebkov, Yu.S.

“…This paper deals with the effect of irradiation on tensile properties and fracture toughness of CuCrZr and CuCrNiSi alloys, considered for use in some…”
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Properties of unirradiated and irradiated Ti–6Al–4V alloy for ITER flexible connectors by Rodchenkov, B.S., Evseev, M.V., Strebkov, Yu.S., Sinelnikov, L.P., Shushlebin, V.V.

“…The high strength (α+β) Ti–6Al–4V alloy was selected as the material for flexible attachments of the shield blanket modules in the ITER reactor. The different…”
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Fourth International Scientific and Technical Conference on Innovative Projects and Technologies of Nuclear Power (MNTK NIKIET-2016) by 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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Overview of Russian Federation activity on the LLCB TBM design and analysis by 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.

“…► The preliminary design of TBM elements has been developed. ► Neutronic calculations demonstrate the feasibility of LLCB concept for tritium breeding…”
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Strength analysis results for the RF “modified” option of the shielding block for ITER blanket module by Sviridenko, M.N., Leshukov, A.Yu, Razmerov, A.V., Strebkov, Yu.S.

“…In accordance with the combined analysis of “reference” shield block (SB) design option the RF specialist have adopted the decision to develop the “modified”…”
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