Demonstration of the model of physicochemical processes in heavy liquid metal cooled reactors in an example of the THEADES experiment simulation K Sergeenko, K Svirid, D Afremov, V Folomeev Nuclear Engineering and Design 395, 111870, 2022 | 6 | 2022 |
LES-simulation of heat transfer in a turbulent pipe flow with lead coolant at different Reynolds numbers KM Sergeenko, VM Goloviznin, VY Glotov | 4 | 2018 |
A study of thermophysical and physicochemical characteristic of the KALLA experiment facility K Sergeenko, K Svirid, V Nikolaev, D Afremov, A Tutukin, I Sapozhnikov Nuclear Engineering and Design 414, 112475, 2023 | 1 | 2023 |
Adaptation of the Turbulence Model to the Heat Transfer in a Hexagonal Rod Bundle K Sergeenko Available at SSRN 4134182, 2022 | 1 | 2022 |
Direct numerical simulation of turbulent flow and heat transfer in a hexagonal rod bundle KM Sergeenko, AY Chulyunin, BI Krasnopolsky Journal of Physics: Conference Series 1369 (1), 012045, 2019 | 1 | 2019 |
LES simulation of heat transfer in a turbulent pipe flow with lead coolant at different Reynolds numbers KM Sergeenko, VM Goloviznin, VY Glotov Mathematical Models and Computer Simulations 11, 176-189, 2019 | 1 | 2019 |
Numerical simulation of hydraulics and heat transfer in the BREST-OD-300 LFR fuel assembly D Fomichev, D Afremov, A Tutukin, V Smirnov, K Sergeenko | 1 | 2017 |
Adaptation of the turbulence model to the heat transfer in a rod bundle K Sergeenko Nuclear Engineering and Design 415, 112664, 2023 | | 2023 |
Mathematical Modeling of Water Flow Through a Broad-Crested Spillway Using the CFD Code Star-CCM+ KM Sergeenko, VV Malakhanov, AR Belousov, IN Vishnyakov, NS Karpov, ... Power Technology and Engineering 52 (5), 534-540, 2019 | | 2019 |
Application of CFD simulation to validate the BREST-OD-300 primary circuit design AV Tutukin, DA Afremov, KM Sergeenko, DV Fomichev | | 2018 |
Application of CFD simulation to design substantiation of the BREST-OD-300 lead A Tutukin, K Sergeenko, D Fomichev, D Afremov | | 2017 |
CFD simulation of heat exchange in conditions of a cross flow around the tube bundle with regard for thermal contact resistance KM Sergeenko, DA Afremov, AV Tutukin, DA Ognerubov, DV Fomichev Innovative designs and technologies of nuclear power. IV International …, 2016 | | 2016 |
Development of a model for the protective oxide film formation on the HLMC reactor primary circuit surfaces and its integration into CFD codes KM Sergeenko, DA Afremov, DV Fomichev, EV Yurmanov, EA Varseev Innovative designs and technologies of nuclear power. IV International …, 2016 | | 2016 |
LES-simulation of heat transfer in a turbulent pipe K Sergeenko, V Goloviznin, V Glotov | | |