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    Article

    Use of software tools for calculating flow accelerated corrosion of nuclear power plant equipment and pipelines

    The results obtained from calculations of flow accelerated corrosion of equipment and pipelines operating at nuclear power plants constructed on the basis of PWR, VVER, and RBMK reactors carried out using the ...

    M. M. Naftal’, V. I. Baranenko, O. M. Gulina in Thermal Engineering (2014)

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    Article

    Development of software means and normative documentation on the flow-accelerated corrosion of pipelines of nuclear power plants

    Software tools (ST) and normative documentation (ND) on the flow-accelerated corrosion (FAC) of pipelines of foreign and domestic nuclear power plants are analyzed.

    V. I. Baranenko, A. A. Prosvirnov, S. V. Evropin, A. A. Aref’ev in Thermal Engineering (2012)

  3. No Access

    Article

    Field examination of the erosion-corrosion wear of pipelines at Russian nuclear power stations equipped with VVER reactors

    Distributions of wall thicknesses differing from their nominal values are analyzed, and factors facilitating the formation of thicknesses equal to and exceeding their nominal values are considered. It is shown...

    V. I. Baranenko, V. M. Markochev, Yu. A. Yanchenko in Thermal Engineering (2011)

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    Article

    Erosion-corrosion wear of the components of pipeline systems at nuclear power stations equipped with RBMK-1000 reactors

    The erosion-corrosion wear of components of pipeline systems at nuclear power stations equipped with RBMK-1000 reactors is analyzed. It is shown that the mechanism of erosion-corrosion wear involves two parall...

    V. I. Baranenko, Yu. A. Yanchenko in Thermal Engineering (2010)

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    Article

    Field inspection of pipelines susceptible to erosion-corrosion wear

    Specific features pertinent to the way in which field inspections of pipelines susceptible to erosion-corrosion wear are organized are discussed. The effect deposits of corrosion products have on the trustwort...

    V. I. Baranenko, Yu. A. Yanchenko, O. M. Gulina, O. S. Tarasova in Thermal Engineering (2009)

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    Article

    Erosion-corrosion wear of the elements of NPP pipeline systems

    The results of the operational control of erosion-corrosion wear of NPP pipelines are analyzed. The peculiar features of the erosion-corrosion wear of different elements of pipeline systems are revealed.

    V. I. Baranenko, Yu. A. Yanchenko in Thermal Engineering (2008)

  7. No Access

    Article

    Development of software tools for calculating corrosion-erosion wear of pipelines at nuclear power stations

    Matters concerning the development, certification, and application of software tools for calculating the rate of erosion-corrosion wear (ECW) of the walls of pipelines at nuclear power stations are discussed. ...

    V. I. Baranenko, A. V. Kumov, Yu. A. Yanchenko, A. S. Prokopenko in Thermal Engineering (2007)

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    Article

    Solving the problems of erosion-corrosion wear of equipment and pipelines in nuclear power plants: Domestic and international experience

    The problem of erosion-corrosion wear (ECW) encountered in the equipment and pipelines of feedwater, condensate, and steam systems of nuclear power plants is considered. Approaches to solving the ECW problem a...

    V. I. Baranenko, Yu. A. Yanchenko in Thermal Engineering (2007)

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    Article

    Development of Software for Calculation of Erosion-Corrosion Wear of NPP Reactor Pi**

    Based on the analysis of laboratory test results and operation inspection reports on steam pi** bend sections, computer programs have been created for predicting erosive-corrosive wear of materials of NPP fa...

    V. I. Baranenko, S. G. Oleinik, V. N. Merkushev, M. B. Bakirov in Strength of Materials (2004)

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    Article

    Erosion-corrosion wear of a metal in the entrance sections of heater coils in nuclear power plants

    V. I. Baranenko, V. S. Kirov, V. P. Kravchenko, N. N. Davidenko in Atomic Energy (1995)

  11. No Access

    Article

    Reliability of high-pressure recovery system in the power-generating units of nuclear power plants with VVÉR-1000 and -440 nuclear reactors

    V. I. Baranenko, A. I. Piontkovskii, S. P. Khmaryuk, N. N. Davidenko in Atomic Energy (1995)

  12. No Access

    Article

    Temperature oscillation in a high-pressure regeneration system of a nuclear power plant with a VVÉR-1000 reactor

    V. I. Baranenko, V. S. Kirov, V. P. Kravchenko, V. A. Korovkin in Atomic Energy (1994)

  13. No Access

    Article

    Damage to the output manifolds of steam generators at nuclear power plants with VVÉR-1000 reactors

    V. I. Baranenko, V. S. Kirov, V. P. Kravchenko, V. A. Korovkin in Atomic Energy (1993)

  14. No Access

    Article

    Intensity of growth or dissolution of vapor-gas bubbles

    V. I. Baranenko, A. N. Musienko, L. N. Fal'kovskii in Atomic Energy (1992)

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    Article

    Solubility of oxygen and carbon dioxide in water

    V. I. Baranenko, L. N. Fal'kovskii, V. S. Kirov, L. N. Kurnyk in Soviet Atomic Energy (1990)

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    Article

    The solubility of nitrogen in water

    V. I. Baranenko, V. S. Sysoev, L. N. Fal'kovskii, V. S. Kirov in Soviet Atomic Energy (1990)

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    Article

    Solubility of helium in water

    V. I. Baranenko, L. N. Fal'kovskii, V. S. Kirov, Yu. V. Filimonov in Soviet Atomic Energy (1989)

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    Article

    Solubility of hydrogen in water in a broad temperature and pressure range

    V. I. Baranenko, V. S. Kirov in Soviet Atomic Energy (1989)

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    Article

    Optical method of investigation of heattransfer mechanism in bubbled boiling

    V. I. Baranenko, G. F. Smirnov in Journal of Applied Mechanics and Technical Physics (1973)

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    Article

    Experimental study of temperature profiles in a thermal boundary layer during the boiling of liquid in a free volume

    The results of an experimental investigation into the thermal boundary layer on a wire associated with boiling in a free volume are presented. The temperature profiles are illustrated and briefly analyzed. The...

    G. F. Smirnov, V. I. Baranenko in Journal of engineering physics (1971)