Search Results - "DRAGUNOV, YU. G"

Space Nuclear Power by Dragunov, Yu. G.

“…Data on the development of nuclear power units for use in spacecraft—nuclear rocket engines and nuclear power units—are presented. Information on the creation…”
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Welding with Pressure for Making Nuclear Reactor Components by Dragunov, Yu. G., Evropin, S. V., Elkin, V. N., Korostelev, A. B., Romadova, E. L.

“…The principles of welding with pressure for making nuclear reactor components from refractory nickel alloys with limited weldability are presented. The main…”
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Approaches to Developing a Small Nuclear Power Plant Based on a Gas-Cooled Reactor by Dragunov, Yu. G., Kudinov, V. V., Kulikov, D. G.

“…The concept of a small gas-cooled reactor for the Brayton cycle using reactor technologies, design solutions, and existing experience of NIKIET is proposed…”
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Nikiet Activity in Space Nuclear Energy by Dragunov, Yu. G., Kaplienko, A. V., Romadova, E. L.

“…The operational features determining innovative approaches to the design of space nuclear energy installations are analyzed. It is shown that there is no…”
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Modeling of the Coolant Flow Distribution Over the Elements of a BREST-OD-300 Reactor Core by Dragunov, Yu. G., Lemekhov, V. V., Sapozhnikov, I. S., Solonin, V. I., Krapivtsev, V. G., Getya, S. I., Markov, P. V.

“…The lead-coolant flow in the core elements of the BREST-OD-300 reactor is formed at the ingress into the shank portion [lower-end caps] of the elements by a…”
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Conception of a Transportable Small Power Plant with a Fast Gas-Cooled Reactor by Dragunov, Yu. G., Dunaitsev, A. A., Kim, D. D., Kobzev, P. V., Kudinov, V. V., Kulikov, D. G.

“…The conception of a transportable small power plant based on a high-temperature gas-cooled nuclear reactor and a gas-turbine plant for supplying heat and…”
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Reactor Pressure Vessel Cooling Scheme: Selection and Validation for Small Nuclear Power Plants by Afremov, D. A., Dragunov, Yu. G., Koretskii, S. A., Kudinov, V. V., Kulikov, D. G.

“…An analysis of existing and possible designs of high-temperature gas-cooled reactor installations has shed light on the critical elements determining the…”
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Contact loss in the vicinity of cylindrical and spherical inclusions in a nanocomposite material by Vlasov, N. M., Dragunov, Yu. G.

“…The loss of contact in the vicinity of cylindrical and spherical inclusions in a nanocomposite material is studied. The physical basis of the process is…”
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Phase transformations in pentagonal nanocrystals by Vlasov, N. M., Dragunov, Yu. G.

“…The kinetics of phase transformations in pentagonal nanocrystals with a logarithmic coordinate dependence of the internal stress fields is considered. Such a…”
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Reactor unit for megawatt propulsion-power module by Dragunov, Yu. G.

“…The results of the first stage of work on the development of a reactor unit for a megawatt-class propulsionpower module for space exploration are presented…”
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Stress–Strain Kinetics in Calculations of High-Temperature Strength and Longevity of Reactor Structures by Dragunov, Yu. G., Evropin, S. V., Gadenin, M. M., Makhutov, N. A., Rebyakov, Yu. N., Chernyavskii, A. O., Chernyavskii, O. F.

“…The plastic properties of materials must be used more fully as working temperatures and temperature gradients increase. The results of tests performed on…”
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Modernization of the IBR-2 pulsed research reactor by Dragunov, Yu. G., Tretiyakov, I. T., Lopatkin, A. V., Romanova, N. V., Lukasevich, I. B., Ananyev, V. D., Vinogradov, A. V., Dolgikh, A. V., Yedunov, L. V., Pepelyshev, Yu. N., Rogov, A. D., Shabalin, E. P., Zaikin, A. A., Golovnin, I. S.

“…The structural design of the IBR-2 periodic-pulse reactor is described. The principal stages of the project in modernizing the reactor, the technical…”
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Technical solutions and development stages for the BREST-OD-300 reactor unit by Dragunov, Yu. G., Lemekhov, V. V., Smirnov, V. S., Chernetsov, N. G.

“…The safety and economy requirements for the large-scale nuclear power technology are examined. The design particularities are presented. It is shown that…”
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Service Life Restoration Technology for RBMK: Design, Implementation, and Assimilation Experience by Adamov, E. O., Dragunov, Yu. G., Slobodchikov, A. V., Mikhailov, M. N., Petrov, A. A., Ukharov, S. G., Burlakov, E. V., Asmolov, V. G., Chernikov, O. G., Bystrikov, A. A., Kudryavtsev, K. G., Lozhnikov, I. N., Kharakhnin, S. N.

“…The RBMK design-stage service life was assumed to be 30 years. Ten power-generating units have now exceeded this limit. Service life extension of nuclear power…”
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Experimental studies of the dynamical characteristics of fuel-element bundles of VVER fuel assemblies in turbulent coolant flow by Dragunov, Yu. G., Solonin, V. I., Perevezentsev, V. V., Petrov, I. V.

“…Studies of fuel-assembly vibrations pay special attention to pre-reactor bench tests with partial modeling of the reactor operating conditions [1]. Full-scale…”
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Conversion of research reactors to low-enrichment fuel by Dragunov, Yu. G., Cherepnin, Yu. S., Lukichev, V. A.

“…Work on lowering the enrichment of fuel for research reactors recently designed in Russia is reviewed in brief. It is noted that the conversion to low-enriched…”
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MBIR multipurpose fast reactor–innovative tool for the development of nuclear power technologies by Dragunov, Yu. G., Tretiyakov, I. T., Lopatkin, A. V., Romanova, N. V., Lukasevich, I. B.

“…The objective of implementing the MBIR liquid-metal cooled fast research reactor, which is supposed to come on line in 2019, is to provide the industry with…”
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Modernization and service-life extension of RBMK power units by Dragunov, Yu. G., Petrov, A. A., Ivanov, A. V., Rozhdestvensky, M. I., Slobodchikov, A. V., Umyarov, R. M.

“…The preparation of power units for service-life extension and aspects of determining the residual service life of critical irreplaceable elements of reactors –…”
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Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75/100 by Zrodnikov, A.V., Toshinsky, G.I., Komlev, O.G., Dragunov, Yu.G., Stepanov, V.S., Klimov, N.N., Kopytov, I.I., Krushelnitsky, V.N.

“…This article presents an innovative nuclear power technology, based on the use of modular type fast-neutron reactors SVBR-75/100 having heavy liquid-metal…”
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Vibrations of fuel-element bundles in VVER fuel assemblies excited by turbulent coolant flow by Dragunov, Yu. G., Solonin, V. I., Perevezentsev, V. V., Petrov, I. V.

“…Complex experimental studies of hydrodynamically excited vibrations of fuel-element bundles have been performed on full-scale models of VVER-440 fuel…”
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