Search Results - "KULAKOV, G. V"

Fuel cycles with advanced dispersion fuel elements of high uranium density by Savchenko, A. M., Karpyuk, L. A., Dergunova, E. A., Konovalov, Yu. V., Kulakov, G. V., Maranchak, S. V., Ershov, S. A., Kupenko, V. I., Mainikov, E. V.

“…The paper considers the possibility of replacing container fuel elements of thermal reactors with uranium dioxide or mixed oxide uranium-plutonium fuel with…”
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Monitoring of the Phytosanitary Status of the Hispid Starburr in Primorsky Krai by Sukholozova, E. A., Orlova, J. V., Kulakova, Yu. Yu, Kulakov, V. G., Horina, N. A., Yazykova, G. I., Sukholozov, E. A.

“…The results of monitoring of undesirable South American weed Acanthospermum hispidum DC conducted in Primorsky krai in 2020–2021 are presented. The territories…”
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UTILIZATION OF PLANT PROTEINS IN FUNCTIONAL NUTRITION by V. G. Kulakov, S. V. Kapustin

“…Development of functional food products technology is considered to be a prospect way for creating new food products. Such products are known to be popular…”
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Steel Cladding for VVER Fuel Pins in the Context of Accident-Tolerant Fuel: Prospects by Karpyuk, L. A., Savchenko, A. M., Leont’eva-Smirnova, M. V., Kulakov, G. V., Konovalov, Yu. V.

“…Groups of materials are compared according to their possible use for fuel-pin cladding in the development of accident-tolerant fuel (ATF). Ferritic,…”
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Prospects for using Chromium-Nickel Alloy 42KhNM in Different Types of Reactors by Kulakov, G. V., Vatulin, A. V., Ershov, S. A., Karpyuk, L. A., Konovalov, Yu. V., Kosaurov, A. O., Leontyeva-Smirnova, M. V., Rechitsky, V. N., Golubnichy, A. A.

“…The chromium-nickel alloy 42KhNM developed at VNIINM is used for the cladding on the fuel rods in nuclear icebreakers as well as the absorbing rods for the…”
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Testing of Dispersion Type Fuel Rods with a Heat-Proof Meat with Controlled Porosity for Small Nuclear Power Plants by Savchenko, A. M., Konovalov, Yu. V., Kulakov, G. V., Maranchak, S. V., Ershov, S. A., Mainikov, E. V., Kozlov, A. V., Shishin, V. Yu, Sheldyakov, A. A., Yakovlev, V. V.

“…The results of development work on dispersion type fuel rods, whose meat, containing granules of a uranium-molybdenum alloy in a matrix of special zirconium…”
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42KhNM Alloy and Silicon Carbide as Material for Accident-Tolerant Fuel-Rod Cladding by Karpyuk, L. A., Novikov, V. V., Kulakov, G. V., Konovalov, Yu. V., Leont’eva-Smirnova, M. V., Golubnichii, A. A., Ivanov, S. I., Makarov, F. V., Glebov, A. V.

“…The results of R&D work on alternative materials for accident-tolerant fuel-rod cladding are reported. The chromium-nickel alloy 42KhNM and multilayer…”
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High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding by Kulakov, G. V., Konovalov, Yu. V., Vatulin, A. V., Kosaurov, A. A., Shishin, V. Yu, Shel’dyakov, A. A., Romanov, A. I., Morozov, O. A., Samoilov, O. B.

“…Thermal testing of shortened fuel rods with 42KhNM chromium–nickel alloy cladding, pre-irradiated in the MIR reactor to fission product content 0.9 g/cm 3 ,…”
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Development of Fuel for Research Reactors by Vatulin, A. V., Suprun, V. B., Kulakov, G. V.

“…The different stages in the development of fuel for research reactors are analyzed. Validation is given for high-density fuel based on the alloy U–9Mo for the…”
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Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation by Kulakov, G. V., Konovalov, Yu. V., Kosaurov, A. A., Peregud, M. M., Nikulina, A. B., Shishin, V. Yu, Ovchinnikov, V. A., Shel’dyakov, A. A.

“…The first reactor tests and post-reactor studies of fuel elements with cladding made from the zirconium alloys E-636M, E-635opt, and E-635M1, developed at…”
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Development of Materials and Fuel Elements for Propulsion Reactors and Small Nuclear Power Plants: Experience and Prospects by Kulakov, G. V., Vatulin, A. V., Ershov, S. A., Kosaurov, A. A., Konovalov, Yu. V., Morozov, A. V., Sorokin, V. I., Fedotov, V. V.

“…The primary stages in the develop of disperse fuel elements for the cores of propulsion reactors, floating power-generating units, and small- and medium-size…”
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Peculiarities of fuel cycle with advanced composite fuel for thermal reactors by Savchenko, A.M., Vatulin, A.V., Kulakov, G.V., Lipkina, K.V., Sorokin, V.I., Morozov, A.V., Ershov, S.A., Uferov, O.I., Mainikov, E.V., Kozlov, A.

“…The use of dispersion type fuel elements, with high uranium content such as, U–Mo, U–Nb–Zr, U3Si, with a Zr alloy matrix (“advanced metmet”), is considered…”
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Zirconium alloys matrix as innovative material for composite fuel by Savchenko, A.M., Vatulin, A.V., Morozov, A.V., Kulakov, G.V., Ershov, S.A., Laushkin, A.V., Maranchak, S.V., Konovalov, Y.V., Malamanova, E.K.

“…A novel class of zirconium alloys is suggested as fuel matrix. They are “deep” ternary or quaternary eutectics having relatively low melting point i.e. from…”
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Main results of the development of dispersion type IMF at A.A. Bochvar Institute by Savchenko, A.M., Vatulin, A.V., Glagovsky, E.M., Konovalov, I.I., Morozov, A.V., Kozlov, A.V., Ershov, S.A., Mishunin, V.A., Kulakov, G.V., Sorokin, V.I., Simonov, A.P., Petrova, Z.N., Fedotov, V.V.

“…At A.A. Bochvar Institute a novel conception of IMF to burn civil and weapon’s grade Pu is currently accepted. It consists in the fact, that instead of using…”
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Behavior of the Fuel Elements of Floating Power-Generating Units Under Irradiation by Kulakov, G. V., Vatulin, A. V., Ershov, S. A., Konovalov, Yu. V., Morozov, A. V., Sorokin, V. I., Fedotov, V. V., Shishin, V. Yu, Ovchinnikov, V. A., Shel’dyakov, A. A.

“…The fuel composition uranium dioxide + aluminum alloy was developed for use in the fuel elements of the core of a floating power-generating unit and small…”
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Particulars of the Behavior Under Irradiation of Dispersion Fuel Elements with the Uranium Dioxide + Aluminum Alloy Fuel Composition by Kulakov, G. V., Vatulin, A. V., Ershov, S. A., Konovalov, Yu. V., Morozov, A. V., Sorokin, V. I., Fedotov, V. V., Shishin, V. Yu, Ovchinnikov, V. A.

“…A fuel with the uranium dioxide + aluminum alloy composition was developed for fuel elements to be used in floating power-generating units and small nuclear…”
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Inert matrix fuel in dispersion type fuel elements by Savchenko, A.M., Vatulin, A.V., Morozov, A.V., Sirotin, V.L., Dobrikova, I.V., Kulakov, G.V., Ershov, S.A., Kostomarov, V.P., Stelyuk, Y.I.

“…The advantages of using inert matrix fuel (IMF) as a dispersion fuel in an aluminium alloy matrix are considered, in particular, low temperatures in the fuel…”
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Decommissioning of fuel elements at the reactor of the “Akademik Lomonosov” floating thermal power plant by Kulakov, G. V., Konovalov, Yu. V., Vatulin, A. V., Kosaurov, A. A., Ershov, S. A., Mainikov, E. V., Sorokin, V. I., Kozlov, A. V.

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Application of metal-ceramic uranium-molybdenum fuel in an aluminum matrix for research reactors by Savchenko, A. M., Konovalov, Y. V., Kulakov, G. V., Tarasov, B. A., Ershov, S. A., Mainikov, E. V., Bubenschikov, D. A.

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Fuel-Rod Design and Materials Validation for 10 MW NPP by Kulakov, G. V., Vatulin, A. V., Ershov, S. A., Kozlov, A. V., Konovalov, Yu. V., Mainikov, E. V.

“…The timeliness of the development of small nuclear power plants is determined by their economic utility and prospects for use as an energy source in remote…”
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