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

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Features of heat transfer during boiling of nanofluids by 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 by 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 by 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 by 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 by 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 by 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 by 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 by 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 by 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 by A. A. Avramenko, E. A. Kondrateva, M. M. Kovetskaja, A. I. Tyrinov, V. N. Vasilchenko

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