Effect of water temperature at inlet to the steam generating channel on stability of the two-phase flow von M. M. Kovetskaja

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Features of heat transfer during boiling of nanofluids von A. A. Avramenko, M. M. Kovetskaja, A. I. Tyrinov

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Effect of permeability of peble bed on heat transfer in the core of nuclear reactor with helium coolant von A. A. Avramenko, N. P. Dmitrenko, M. M. Kovetskaja

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The numerical investigation of heat transfer at a water flow in the vertical steam generating channel von M. M. Kovetskaja, A. I. Skitsko, T. V. Sorokina, V. E. Domashev

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Thermophysical Studies for Safety Assessment of Promising Nuclear Power Plants von A. A. Avramenko, M. M. Kovetskaja, A. V. Kravchuk, Ju. Ju. Kovetskaja

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Study of Heat Transfer Processes in Modelled Core of Nuclear Reactor with Helium Coolant von A. A. Avramenko, M. M. Kovetskaja, N. P. Dmitrenko, Ju. Ju. Kovetskaja

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Heat transfer of supercritical pressure flow in pipe with changing thermal load von A. A. Avramenko, M. M. Kovetskaja, E. A. Kondrateva, A. I. Tyrinov

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Perspective researches of innovative technologies of nuclear power plants von A. A. Avramenko, M. M. Kovetskaja, A. V. Kravchuk, Ju. Ju. Kovetskaja

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Research of modes of the worsened heat transfer for the flow of supercritical parameters in the vertical pipe von A. A. Avramenko, M. M. Kovetskaja, E. A. Kondrateva, A. I. Tyrinov

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Heat transfer of supercritical pressure water in fuel assemblies in unsteady regime von A. A. Avramenko, M. M. Kovetskaja, Ju. Ju. Kovetskaja, A. V. Kravchuk, L. V. Olejnik

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Specifics of supercritical parameters of a flow under non-uniform heating of the fuel assembly channel walls von A. A. Avramenko, E. A. Kondrateva, M. M. Kovetskaja, A. I. Tyrinov, V. N. Vasilchenko

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