Search Results - "PARFENOV, Yu. V"

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    The present state and problems of standardization in the protection of the civil infrastructure from powerful electromagnetic influences by Sakharov, K. Yu, Parfenov, Yu. V., Zdukhov, L. N., Titov, B. A., Turkin, V. A.

    Published in Measurement techniques (01-05-2012)
    “…The results of work carried out by the SC77C subcommittee of the International Electrotechnical Commission to produce a system of standards on the protection…”
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    Journal Article
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    Analysis of the temperature regime of operation of a filtering unit by Melikhov, V. I., Melikhov, O. I., Parfenov, Yu. V., Yakush, S. E.

    “…The temperature regime of a filtering unit being cooled after an accident at a nuclear power plant is considered. A mathematical model is developed; the model…”
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  3. 3

    The computational-and-experimental investigation into the head-flow characteristic of the two-stage ejector for the emergency core cooling system of the NPP with a water-moderated water-cooled power reactor by Parfenov, Yu. V.

    Published in Thermal engineering (2013)
    “…The results of the computational-and-experimental investigation into the two-stage ejector for the emergency cooling system of the core of the water-moderated…”
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  4. 4

    Current state of system thermohydraulic codes and trends in their development abroad by Asmolov, V. G., Blinkov, V. N., Melikhov, V. I., Melikhov, O. I., Parfenov, Yu. V., Emelyanov, D. A., Kiselev, A. E., Dolganov, K. S.

    Published in High temperature (2014)
    “…The current tendencies in development of the system thermohydraulic codes for analysis of emergency processes in nuclear reactor cooling systems abroad are…”
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    The influence of void fraction on the submerged perforated sheet hydraulic friction factor by Blinkov, V. N., Elkin, I. V., Emelianov, D. A., Melikhov, V. I., Melikhov, O. I., Nerovnov, A. A., Nikonov, S. M., Parfenov, Yu. V.

    Published in Thermal engineering (2015)
    “…The results from an experimental investigation of two-phase flow motion through a submerged perforated sheet (SPS) obtained at the Elektrogorsk Research Center…”
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    Computational-theoretical analysis of the distribution of the thermohydraulic parameters and the concentration of dissolved impurities in a PGV-1000m horizontal steam generator performed using the STEG computer code by TRUNOV, N. B, MELIKHOV, V. I, MELIKHOV, O. I, PARFENOV, Yu. V

    Published in Atomic energy (New York, N.Y.) (01-06-2004)
    “…The STEG computer code for performing thermohydraulic calculations is used for a three-dimensional computational analysis of the distribution of the…”
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  7. 7

    A comparative analysis of the calculation expressions for a two-velocity model describing two-phase flow of steam-water mixture across a tube bundle by Nerovnov, A. A., Parfenov, Yu. V., Melikhov, V. I., Melikhov, O. I.

    Published in Thermal engineering (2012)
    “…The formulas most widely used for calculating an interfacial interaction force for flow of steam-water mixture across a tube bundle are analyzed by way of…”
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    Oxidation of methane–ethane mixtures into alcohols under enhanced pressures by Arutyunov, V.S, Basevich, V.Ya, Vedeneev, V.I, Parfenov, Yu.V, Sokolov, O.V, Leonov, V.E

    Published in Catalysis today (09-07-1998)
    “…Experimental investigation of the direct partial oxidation of methane–ethane mixtures into alcohols in the pressure range from 2 to 15 atm and at 100 atm was…”
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