Výsledky vyhledávání - "V. A. Pervichko"

CONV-3D Code Aided Calculation of the Flow Parameters of Fuel-Rod Bundles

Autor: V. V. Chudanov, A. E. Aksenova, V. A. Pervichko

Publikováno v: Atomic Energy. 128:287-290

The results of modeling of incompressible fluid flows in fuel rod bundles performed using the CONV-3D code are reported. The modeling results obtained for different Reynolds numbers and distances between the fuel rods in comparison with experiment ar

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ceb7fe114422a87a506d366ee587e560
https://doi.org/10.1007/s10512-020-00689-1

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Simulation of Heat and Mass Transfer in Wire-Wrapped Fuel Assemblies in the Anisotropic Porous Body Approximation

Autor: A. E. Aksenova, V. S. Kharitonov, V. A. Pervichko, A. S. Korsun, M. V. Bayaskhalanov, I. G. Merinov, V. V. Chudanov

Publikováno v: Thermal Engineering. 67:405-412

Results of the simulation of heat and mass transfer in wire-wrapped fuel assemblies in the anisotropic porous body approximation using the developed APMod software package are presented. The modifications introduced into the porous body model to make

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d92782cfc32b724af69be692333fa08f
https://doi.org/10.1134/s0040601520060063

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Modeling of Incompressible Fluid Flows in a Round Tube in Laminar, Transient, and Turbulent Regimes using the Conv-3d Code

Autor: V. V. Chudanov, A. E. Aksenova, V. A. Pervichko

Publikováno v: Atomic Energy. 127:328-332

The results of using the CONV-3D code to model incompressible fluid flows in round tubes in laminar, transient, and turbulent regimes are presented. The results of modeling with different Reynolds numbers are compared with the Poiseuille parabola and

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3d33dd67fc996d64e0721b8a6e5974b9
https://doi.org/10.1007/s10512-020-00631-5

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Adaptation of CONV-3D Single-Phase Module for Modeling Turbulent Flow in Reactors in the Les Approximation

Autor: V. V. Chudanov, A. E. Aksenova, V. A. Pervichko

Publikováno v: Atomic Energy. 128:340-342

The particulars of the adaptation of the CONV-3D module for modeling turbulent flows in reactors in the LES approximation are presented. The results of modeling coolant flow in a round tube with Reynolds number 4·103–5·105 in comparison with the

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::bcaaa48e5b7ee9a673e8760563623a2d
https://doi.org/10.1007/s10512-020-00697-1

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Modeling of Heat-and-Mass Transfer in Fuel Assemblies in Liquid-Metal-Cooled Reactors with Partial Flow-Passage Blockage

Autor: A. E. Aksenova, V. S. Kharitonov, V. A. Pervichko, I. G. Merinov, V. V. Chudanov, A. S. Korsun

Publikováno v: Atomic Energy. 124:166-172

The results of modeling the heat-and-mass transfer in the FA of liquid metal cooled reactors with partial flow-passage blockage are presented. The model employed for an isotropic porous body is described, and the obtained results are compared with ex

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::46fa7003d4771777046f695b4e6a0f52
https://doi.org/10.1007/s10512-018-0392-7

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CONV-3D Code Application for CFD-Modeling of Lead-Bismuth Coolant

Autor: A. A. Makarevich, A. E. Aksenova, V. V. Chudanov, V. A. Pervichko

Publikováno v: Atomic Energy. 123:87-92

The results of testing the three-dimensional CFD-code on problems very close to real processes for lead–bismuth eutectic are presented: flow in a 19-fuel element assembly with three spacing lattices and convection in the ‘tumbler’ model. The re

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::d20f7fbc8d803e9131ecd2343f70b5b6
https://doi.org/10.1007/s10512-017-0306-0

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Use of the CFD-Code CONV-3D in Reactor Applications

Autor: A. A. Makarevich, A. E. Aksenova, V. V. Chudanov, V. A. Pervichko, I. V. Romero Reyes

Publikováno v: Atomic Energy. 121:179-184

The results of testing the CONV-3D code and methods of direct numerical modeling, using supercomputers, of turbulent flows in the elements of nuclear power plants are presented for problems as close as possible to real processes: natural and forced c

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a8dd3926be21b0022dec67c9fac63647
https://doi.org/10.1007/s10512-017-0180-9

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