Search Results - "LOPATKIN, A. V"

Effect of Hydrogen Gas on Mechanical Properties of Pipe Metal of Main Gas Pipelines by Nastich, S. Yu, Lopatkin, V. A.

“…In this article, literature data on the effect of hydrogen gas and methane-hydrogen mixtures at high pressure on the metal of gas pipelines are reviewed. The…”
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Conceptual Design of a Hybrid Fusion–Fission Power Reactor with a Tokamak and a Depleted Uranium Blanket by Mirnov, S. V., Gladush, G. G., Gostev, A. A., Lopatkin, A. V., Lukasevic, I. B., Lyublinsky, I. E.

“…We assess the viability of energy generation with depleted uranium irradiated with fast neutrons from the reaction of DT fusion driven by a tokamak reactor…”
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Calculated demonstration of VVER-1000 SNF actinide transmutation efficiency by Lopatkin, A. V., Golovin, N. P., Lukasevich, I. B.

“…A simple numerical example suffices to demonstrate the scale of the change in the potential biological hazard when removing actinides from the spent nuclear…”
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Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties by Dolgov, Yu. A., Lopatkin, A. V., Leonov, V. N., Lukasevich, I. B., Slesarev, I. S.

“…The concept of slowing down the kinetics of a fast reactor, according to which a rapid reactivity insertion is used to reduce the development rate of…”
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Assessment of Radiological Hazard of Radioactive Waste Using Effective or Organ Doses: How This May Affect Final Waste Disposal by Ivanov, V.K., Chekin, S. Yu, Lopatkin, A.V., Menyajlo, A.N., Maksioutov, M.A., Tumanov, K.A., Kashcheeva, P.V., Lovachev, S.S.

“…The radiological hazard of spent nuclear fuel and radioactive waste slows down further development of nuclear energy systems. The authors evaluate timescales…”
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Neutronics Efficacy Evaluations of Lithium-Uranium and Lithium-Thorium Blankets in a Thermonuclear Plant by Gladush, G. G., Mirnov, S. V., Lopatkin, A. V., Lukasevich, I. B.

“…The efficacy of uranium and thorium waste in a blanket of a thermonuclear plant, whose tasks are breeding of tritium as fuel for a thermonuclear plant and the…”
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Conditions for Reaching Radiation Equivalence of Native Raw Materials and Long-Lived Radioactive Waste in Nuclear Energy in Russia by Lopatkin, A. V., Platonov, I. V., Popov, V. E.

“…The basic requirements of regeneration of spent fuel from BREST reactors in order to reach radiation equivalence in the nuclear energy system are presented. It…”
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Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation by Adamov, E. O., Kaplienko, A. V., Orlov, V. V., Smirnov, V. S., Lopatkin, A. V., Lemekhov, V. V., Moiseev, A. V.

“…The work performed on the creation of the BREST innovative reactor technology based on a lead-cooled fast reactor, mixed uranium-plutonium nitride fuel,…”
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Homogenous Transmutation of 237Np, 241Am, 243Am in a Lead-Cooled Fast Reactor by Larionov, I. A., Lopatkin, A. V., Lukasevich, I. B., Moroko, V. I., Popov, V. E.

“…The results of a study of the effect of the homogeneous addition of 237 Np, 241 Am, 243 Am into the fuel on the neutronics characteristics of a lead-cooled…”
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Method of Calculating Fission Product Mass Transfer in Multizone Reactor Problems by Lopatkin, A. V., Nikitin, A. V., Mikhailov, A. V., Gordeev, A. A., Vasyukhno, V. P.

“…An analytic solution is given for a system of first-order inhomogeneous linear differential equations describing the mass transfer of fission products in…”
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Refined model of low-impedance film resistors with a comb-like structure by Sadkov, V. D., Lopatkin, A. V.

“…Using the methods of finite element and conformal mapping, analytical models with low and ultralow resistance of the film resistors of the main types of…”
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Concept of a New High-Flux Periodic-Pulse Source of Neutrons Based on Neptunium by Lopatkin, A. V., Tret’yakov, I. T., Romanova, N. V., Goryachikh, A. V., Kokorin, N. D., Popov, V. E., Moroko, V. I., Kravtsova, O. A., Aksenov, V. L., Kulikov, S. A., Rzyanin, M. V., Shvetsov, V. N., Shabalin, E. P.

“…The IBR-2 (JINR) pulsed reactor is used in the field of solid state physics for experiments on extracted beams. It is predicted that the IBR-2 reactor will…”
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Analysis of the Fuel-Loop Characteristics of a Molten-Salt Nuclear Reactor with a Cavity Core by Ignat’ev, V. V., Feinberg, O. S., Smirnov, V. P., Vanyukova, G. V., Lopatkin, A. V.

“…Thermohydraulic validation is a priority for the ZhSR-S [MOSART] molten-salt nuclear transmuter for transuranium elements from the spent nuclear fuel of…”
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POSSIBILITIES OF BREST REACTORS AND TRANSMUTATION FUEL CYCLE UNDER CONDITIONS IMPLEMENTING MODERN PLANS FOR THE DEVELOPMENT OF NUCLEAR POWER by LOPATKIN, A. V, ORLOV, V. V, LUKASEVICH, I. B, ZAIKO, I. V, GANEV, I. Kh

“…The possible dynamics of the development of BREST-1200 fast reactor capacities after 2030 on the basis of plutonium and other actinides accumulated in the…”
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The closed on-site fuel cycle of the brest reactors by Orlov, V.V., Filin, A.I., Lopatkin, A.V., Glazov, A.G., Sukhanov, L.P., Volk, V.I., Poluektov, P.P., Ustinov, O.A., Vorontsov, M.T., Leontiev, V.F., Karimov, R.S.

“…The BREST fast reactor with nitride fuel and lead coolant is being developed as a reactor of new generation, which has to meet a set of requirements placed…”
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CONTRIBUTION OF THE RESEARCH AND DESIGN INSTITUTE OF ELECTRICAL TECHNOLOGY TO THE FORMULATION OF A STRATEGY FOR THE DEVELOPMENT OF NUCLEAR POWER IN RUSSIA by ADAMOV, E. O, GABARAEV, B. A, GANEV, I. Kh, DZHALAVYAN, A. V, LOPATKIN, A. V, MURAV'EV, E. V, ORLOV, V. V

“…The results of investigations performed by specialists at Research and Design Institute of Electrical Technology together with other enterprises, institutes,…”
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Review of Article by Yu. P. Mel’nik, V. V. Pilipenko, A. S. Fomin, S. P. Fomin, and N. F. Shul’ga “Study of self-regulated nuclear burn wave regime in a fast reactor based on a thorium–uranium cycle” by Lopatkin, A. V.

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Potential biological danger of uranium used in the nuclear fuel cycle by GABARAEV, B. A, GANEV, I. Kh, LOPATKIN, A. V

“…It is suggested that long-lived ^sup 226^Ra and ^sup 230^Th be extracted from ore together with uranium and then transmuted to achieve radiation equivalence…”
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Conceptual framework of a strategy for the development of nuclear power in Russia to 2100 by Adamov, E. O., Dzhalavyan, A. V., Lopatkin, A. V., Molokanov, N. A., Muravyov, E. V., Orlov, V. V., Kal’akin, S. G., Rachkov, V. I., Troyanov, V. M., Avrorin, E. N., Ivanov, V. B., Aleksakhin, R. M.

“…The conceptual principles of a long-term strategy for the development of large-scale nuclear power in Russia based on fast reactors with natural safety and a…”
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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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