Search Results - "Pakholkov, V. V."

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  1. 1

    Turbulent convective heat transfer in a long cylinder with liquid sodium by Frick, P., Khalilov, R., Kolesnichenko, I., Mamykin, A., Pakholkov, V., Pavlinov, A., Rogozhkin, S.

    Published in Europhysics letters (01-01-2015)
    “…Turbulent convective heat transfer in a closed cylinder with aspect ratio L = 5D (D is the diameter and L is the cylinder length) filled with liquid sodium,…”
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    Journal Article
  2. 2

    Numerical simulation of fluid dynamics and mixing in headers of sodium-air heat exchangers by Smetanin, Timur R., Pakholkov, Vasilii V., Rogozhkin, Sergey A., Shepelev, Sergey F.

    Published in Nuclear energy and technology (26-03-2024)
    “…The paper presents the results of a numerical simulation for sodium fluid dynamics and mixing in the tubing system of an air-cooled heat exchanger (AHX), which…”
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    Journal Article
  3. 3

    Mixing of Different Temperature Flows of Liquid Sodium in the Pipeline behind the Tee by Kolesnichenko, I. V., Khalilov, R. I., Shestakov, A. V., Krylov, A. N., Pakholkov, V. V., Pavlinov, A. M., Mamykin, A. D., Vasiliev, A. Yu, Rogozhkin, S. A., Frick, P. G.

    Published in Thermal engineering (01-03-2023)
    “…Experimental studies into the process of mixing two different-temperature flows of sodium coolant in a T-shaped connection of cylindrical channels (tee) have…”
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    Journal Article
  4. 4

    Refinement of the Parameters of a Reactor Installation and Thermohydraulic Characteristics of the Main Equipment, Based on Commissioning Results for a Power Unit with BN-800 by Fadeev, I. D., Dmitrieva, I. V., Pakholkov, V. V., Rogozhkin, S. A., Shepelev, S. F.

    Published in Atomic energy (New York, N.Y.) (01-12-2021)
    “…The computer programs used to validate the thermohydraulic characteristics of equipment and parameters of fast sodium reactors in normal operation are…”
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    Experimental investigation of a new method for advanced fast reactor shutdown cooling by Pakholkov, V. V., Kandaurov, A. A., Potseluev, A. I., Rogozhkin, S. A., Sergeev, D. A., Troitskaya, Yu. I., Shepelev, S. F.

    Published in Thermal engineering (2017)
    “…We consider a new method for fast reactor shutdown cooling using a decay heat removal system (DHRS) with a check valve. In this method, a coolant from the…”
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  8. 8

    Turbulent convective heat transfer in an inclined tube filled with sodium by Vasil’ev, A. Yu, Kolesnichenko, I. V., Mamykin, A. D., Frick, P. G., Khalilov, R. I., Rogozhkin, S. A., Pakholkov, V. V.

    Published in Technical physics (01-09-2015)
    “…Turbulent free convection of liquid sodium in a straight thermally insulated tube with a length equal to 20 diameters and with end heat exchangers ensuring a…”
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  9. 9

    Experimental study on free convection of sodium in a long cylinder by Kolesnichenko, I. V., Mamykin, A. D., Pavlinov, A. M., Pakholkov, V. V., Rogozhkin, S. A., Frick, P. G., Khalilov, R. I., Shepelev, S. F.

    Published in Thermal engineering (2015)
    “…The operation experience of sodium fast reactor shows that during design-basis validation of pipelines and equipment it is necessary to take into account the…”
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  10. 10

    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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    Journal Article
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