Search Results - "Osipov, S. L."

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    Numerical Modeling of Delayed-Neutron Precursor Transport in a Sodium-Cooled Fast Reactor by Rogozhkin, S. A., Osipov, S. L., Salyaev, A. V., Usynina, S. G., Pokhilko, V. I., Sazonova, M. L.

    Published in Atomic energy (New York, N.Y.) (01-08-2020)
    “…Methods of determining the efficiency of the system that controls the seal-tightness of fuel-rod cladding and localizes FA with leaky fuel rods in a fast…”
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    Journal Article
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    Computational and Experimental Studies Substantiating Setups for Localizing Fast-Reactor Melted Fuel by Rogozhkin, S. A., Osipov, S. L., Sobolev, V. A., Shepelev, S. F., Kozhaev, A. A., Mavrin, M. S., Ryabov, A. A.

    Published in Atomic energy (New York, N.Y.) (01-04-2014)
    “…Analysis of an unanticipated accident due to complete loss of system and autonomous power together with failure of the emergency protection of the reactor…”
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    Use of URANS approach for determination of temperature fluctuations when mixing triple-jet sodium at different temperatures by Rogozhkin, Sergey A., Aksenov, Andrey A., Zhluktov, Sergey V., Osipov, S. L., Fadeev, I. D., Shaporenko, Elena V., Shepelev, Sergey F., Shmelev, Vladimir V.

    “…The possibility to study temperature fluctuations using URANS approach is studied. The results of numerical simulation of mixing processes for triple-jet…”
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    Numerical Modeling of Thermohydraulic Processes in the Upper Chamber of a Fast Reactor by Rogozhkin, S. A., Osipov, S. L., Fadeev, I. D., Shepelev, S. F., Aksenov, A. A., Zhluktov, S. V., Sazonova, M. L., Shmelev, V. V.

    Published in Atomic energy (New York, N.Y.) (01-03-2014)
    “…Computational hydrodynamics CFD codes based on modern computer technology is being increasingly used to validate the BN-600, -800, and -1200 designs. Such…”
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    Analysis of Proliferation Risk Abatement for Fissile Materials with the Required Run Time in Small Nuclear Power Plants by Alekseev, V. I., Vavilkin, V. N., Osipov, S. L., Peskov, R. A., Petrunin, V. V., Pichkov, S. N., Sorokin, S. E., Sukharev, Yu. P.

    Published in Atomic energy (New York, N.Y.) (01-07-2013)
    “…The effect of small additions of Np, Am, and Cm to fresh uranium fuel on the critical mass, heat release, intensity of the spontaneous neutron radiation, and…”
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    Concept of an advanced power-generating unit with a BN-1200 sodium-cooled fast reactor by Rachkov, V. I., Poplavskii, V. M., Tsibulya, A. M., Bagdasarov, Yu. E., Vasiliev, B. A., Kamanin, Yu. L., Osipov, S. L., Kuzavkov, N. G., Ershov, V. N., Ashirmetov, M. R.

    Published in Atomic energy (New York, N.Y.) (01-08-2010)
    “…The status of work on the development of a 1200 MW sodium-cooled reactor facility for serial construction is presented. The general characteristics of the…”
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    Experimental and Computational Investigation of the Emission of Radioactive Products from Irradiated Fuel of Fast Sodium-Cooled Reactor by Zabrodskaya, S. V., Moseev, L. I., Poplavskii, V. M., Porollo, S. I., Tsikunov, A. G., Veremeev, A. M., Osipov, S. L.

    Published in Atomic energy (New York, N.Y.) (01-10-2017)
    “…The key experimental and computational studies of the emission of long-lived radioactive fission products and actinides from uranium dioxide irradiated in…”
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    HYDRA-IBRAE/LM/V1 Thermohydraulic Code Verification Based on BN-600 Experiments by Klimonov, I. A., Usov, E. V., Dugarov, G. A., Butov, A. A., Kudashov, I. G., Ivanov, E. N., Mosunova, N. A., Strizhov, V. F., Anfimov, A. M., Gorbunov, V. S., Kuznetsov, D. V., Osipov, S. L., Bel’tyukov, A. I.

    Published in Atomic energy (New York, N.Y.) (01-09-2017)
    “…The results of thermohydraulic code HYDRA-IBRAE/LM/V1 verification on experimental data obtained using the BN-600 reactor in different years are described. The…”
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    Systems for Measuring BN-800 Sodium Flow by Kebadze, B. V., Lagutin, A. A., Shurupov, V. A., Generalov, E. V., Fomin, A. N., Pakholkov, V. V., Osipov, S. L., Kryukov, A. N., Mumrenkov, E. A., Shokhonov, V. P., Gubyrin, M. A., Rozenbaum, E. L., Bogatov, S. V.

    Published in Atomic energy (New York, N.Y.) (01-05-2017)
    “…The presented systems are intended for measuring the sodium flow through the main circulation pumps in the first loop and FA in BN-800. The systems are…”
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    Effect of hydrogen sulfide on properties of turbine oil by Gureev, A A, Kholodov, B P, Osipov, S L, Legezin, N E, Al'tshuler, B N

    Published in Chemistry and technology of fuels and oils (01-01-1984)
    “…When natural gas with a high content of hydrogen sulfide is compressed in pipeline compressors, rather larger amounts of this gas may get into the lubricating…”
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