nuclear reactor, the core, fuel assemblies, fuel rods, spacers, mixing intensifiers-grating, mixing of coolant, coolant fluid dynamics, mass transfer intercell.
Subject:
Hydrodynamics of the coolant in the cores of stationary nuclear reactors and power plants for transport purposes.
Main publications:
Samoilov O.B., Shipov D.L., Kupriyanov A.V., Sholin E.V., Vishneva T.Yu., Molodtsov A.A., Osin A.B., Dmitriev S.M., Khrobostov A.E., Doronkov D.V., Morozkin O.N., “EFFICIENCY STUDIES OF HEAT-TRANSFER INTENSIFIER GRIDS IN TVSA-T MODEL FUEL ASSEMBLIES”, Atomic Energy, 128:1 (2020), 17-23
Dmitriev S.M., Gerasimov A.V., Dobrov A.A., Doronkov D.V., Pronin A.N., Ryazanov A.V., Solntsev D.N., Khrobostov A.E., Noskov A.S., Shvetsov Yu.K., Shipov D.L., “COMBINED NUMERICAL AND EXPERIMENTAL INVESTIGATIONS INTO THE LOCAL FLUID DYNAMICS OF COOLANT FLOW IN THE MIXED CORE OF A VVER REACTOR”, Thermal Engineering, 67:5 (2020), 282-289
Dmitriev S.M., Gerasimov A.V., Dobrov A.A., Doronkov D.V., Pronin A.N., Solntsev D.N., Khrobostov A.E., Shvetsov Y.K., Shipov D.L., “HYDRODYNAMICS AND MIXING OF A COOLANT IN THE CORE OF THE VVER WITH FUEL ASSEMBLIES OF DIFFERENT DESIGNS”, Thermophysics and Aeromechanics, 26:6 (2019), 845-860
Samoilov O.B., Noskov A.S., Shipov D.L., Dmitriev S.M., Dobrov A.A., Doronkov D.V., Legchanov M.A., Pronin A.N., Solntsev D.N., Sorokin V.D., Khrobostov A.E., “HYDRODYNAMIC FEATURES OF THE FLOW DOWNSTREAM FROM THE MIXING SPACER GRID IN A KVADRAT FUEL ASSEMBLY IN PWRS”, Thermal Engineering, 66:4 (2019), 243-248
Dmitriev S.M., Varentsov A.V., Dobrov A.A., Doronkov D.V., Pronin A.N., Sorokin V.D., Khrobostov A.E., “COMPUTATIONAL AND EXPERIMENTAL INVESTIGATIONS OF THE COOLANT FLOW IN THE CASSETTE FISSILE CORE OF A KLT-40S REACTOR”, Journal of Engineering Physics and Thermophysics, 90:4 (2017), 941-950
S. M. Dmitriev, A. A. Dobrov, D. V. Doronkov, D. S. Doronkova, M. A. Legchanov, A. N. Pronin, A. V. Ryazanov, A. E. Khrobostov, “Studies of the hydrodynamics of the coolant behind mixing intensifier grids of fuel assemblies of a PWR reactor”, TVT, 60:3 (2022), 399–406; High Temperature, 60:3 (2022), 358–365
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