Search Results - "GABARAEV, B. A"

Innovative Nuclear Power Facilities in Reports at the 5th International Scientific and Technical Conference on Innovative Designs and Technologies for Nuclear Power (ISTC NIKIET-2018) by Gabaraev, B. A., Dzhalavyan, A. V., Karandina, E. A.

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Recommendations on calculation of transport coefficients and thermodynamic properties of helium-xenon gas mixtures by Dragunov, Yu.G., Romadova, E.L., Gabaraev, B.A., Belyakov, M.S., Derbenev, D.S.

“…•Semi-empirical correlations.•Calculation of density.•Calculation of dynamic viscosity coefficient.•Calculation of thermal conductivity coefficient…”
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Safe operation and life extension of RBMK plants by Sorokin, N.M., Gabaraev, B.A., Cherkashov, Yu.M.

“…The article presents an overview of the issues for ensuring safe operation of the Russian nuclear power plants with RBMK-1000 reactors. The operating data for…”
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SPACE NUCLEAR POWER SYSTEMS WITH TURBOMACHINE ENERGY CONVERSION by GABARAEV, B. A, SMETANNIKOV, V. P, ULASEVICH, V. K

“…The expansion of space exploration requires the development of sufficiently powerful and reliable power facilities which can operate for a long time. Such…”
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NUCLEAR CENTRAL HEATING : PROSPECTS AND SOLUTIONS by GABARAEV, B. A, KUZNETSOV, Yu. N, ROMENKOV, A. A

“…Large-scale development of nuclear central heating -- a radical expansion of a sphere of application, large increase of cost-effectiveness and self-financing…”
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Conditions for maximum fuel burnup in a RBMK channel reactor without a moderator by GABARAEV, B. A, GANEV, I. Kh

“…The conditions for attaining an operating regime with maximum burnup of nuclear fuel are examined. This can be a regime with steady continuous reloadings with…”
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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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Role of nuclear power in large-scale power production in russia in the 21st century by ADAMOV, E. O, GABARAEV, B. A, ORLOV, V. V

“…The results are summarized of investigations performed over the last 20 years which culminated in the current fundamental formulation of the problem of nuclear…”
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Boiling curve in temperature wave region by Gabaraev, B.A, Kovalev, S.A, Molochnikov, Yu.S, Soloviev, S.L, Usatikov, S.V

“…Heat transfer was studied for the case of autowave transition from metastable to stable boiling regimes. The boiling curves classification was proposed in…”
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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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Research reactors — a look into the future by Gabaraev, B. A., Lopatkin, A. V., Tret’yakov, I. T., Khmel’shchikov, V. V., Aksenov, V. L.

“…The place of research reactors in validating new energy technologies, which are being developed, and advances in science is analyzed. It is shown that research…”
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Effect of burnup and holding time of irradiated nuclear fuel on the mass ratio of Am, Cm, Np, and fissioning plutonium by GABARAEV, B. A, GANEV, I. Kh, LOPATKIN, A. V, MURATOV, V. G, ORLOV, V. V

“…Computed estimates of the mass ratio of Am, Cm, Np, and plutonium for different burnup of VVÉR and RBMK fuel and the post-reactor holding time are presented…”
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Vessel and channel fast reactors cooled by boiling water or water with supercritical parameters by GABARAEV, B. A, GANEV, I. Kh, DAVYDOV, V. K, KUZNETSOV, Yu. N, RESHETOV, V. A, SMIRNOV, A. V

“…The possibility is examined of developing a vessel-type fast reactor cooled by water with supercritical parameters (BR-VSP) and a channel-type fast…”
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The potential for developing and the possibility of attaining radiation equivalence between uranium and wastes in future nuclear power by ADAMOV, E. O, GABARAEV, B. A, GANEV, I. Kh, LOPATKIN, A. V, MURATOV, V. G, ORLOV, V. V

“…The development of nuclear power with capacity up to 300 GW using thermal reactors and BREST fast reactors with small excess breeding (BR 1.05) and nuclear…”
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Comprehensive analysis of mechanical and thermohydraulic processes in the graphite masonry of channel rectors during an accidental rupture of a fuel channel by SOLOV'EV, S. L, GABARAEV, B. A, NOVOSEL'SKII, O. Yu, FILINOV, V. N, PARAFILO, L. M, KRYUCHKOV, D. V

“…A methodology and preliminary results of a computational analysis of the processes occurring in the graphite masonry in RBMK channel reactors during the…”
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Validation of lifetime extension of power-generating units with RBMK reactors by Gabaraev, B. A., Cherkashov, Yu. M., Petrov, A. A., Evropin, S. V., Strelkov, B. P., Arzhaev, A. I., Savchenko, V. A., Saprykin, G. N.

“…A list of measures for extending the lifetime of power-generating units with RBMK reactors is presented. The normative approaches and criteria are indicated,…”
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Handling irradiated RBMK-1000 and VVÉR-1000 fuel during the growth of nuclear power by GABARAEV, B. A, GANEV, I. Kh, LOPATKIN, A. V, ORLOV, V. V, SMIRNOV, V. G

“…On-site storage facilities, consisting of ponds with water, for irradiated RBMK-1000 fuel are now close to being filled. To continue operating nuclear power…”
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Development of an integrated computer code for simulating processes occurring in the containment shell of nuclear power plants with VVÉR reactors by GABARAEV, B. A, EFANOV, A. D, ZAICHIK, L. I, MELIKHOV, O. I, SOLOV'EV, S. L, SOLOV'EV, A. L

“…The results of a competition for the development and verification of a more accurate domestic integrated computer code for simulating processes occurring in…”
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Direct-Flow Channel Reactor with Supercritical Coolant Pressure by Gabaraev, B. A., Vikulov, V. K., Ermoshin, F. E., Mityaev, Yu. I., Nikolotov, A. M., Rozhdestvenskii, M. I., Romenkov, A. A., Fedik, I. I., Gavrilin, S. S., Deniskin, V. P., Nalivaev, V. I.

“…The concept of a direct-flow channel reactor with supercritical-pressure water (CR-SCP) is presented. Neutron-physics, thermohydraulic, and strength…”
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Radiation characteristics of spent nuclear fuel and wastes in nonaqueous reprocessing methods by ADAMOV, E. O, GABARAEV, B. A, GANEV, I. Kh, LOPATKIN, A. V, MURATOV, V. G, ORLOV, V. V

“…The effect of the technology used to separate elements with nonaqueous radiochemical reprocessing of fuel on the radiation characteristics of the fuel and the…”
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