Buchumschlag

Mathematical relations of models of single-phase flows in the channels of reactors and steam generators of NPP's for calculation of heat transfer processes and hydrodynamic characteristics

The article presents the mathematical relationships of models of single-phase flows in channels of a other design for calculating the parameters of heat transfer processes and hydrodynamic (gas-dynamic) characteristics of flows. A comparative analysis of these ratios and their differences are indica...

Ausführliche Beschreibung

Gespeichert in:

Bibliographische Detailangaben
Veröffentlicht in:	Вопросы атомной науки и техники
Datum:	2022
Hauptverfasser:	Yefimov, O.V., Pylypenko, M.M., Kavertsev, V.L., Harkusha, T.A., Tiutiunyk, L.J., Motovilnik, A.V.
Format:	Artikel
Sprache:	Englisch
Veröffentlicht:	Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2022
Schlagworte:	Physics and technology of structural materials
Online Zugang:	https://nasplib.isofts.kiev.ua/handle/123456789/195925
Tags:	Tag hinzufügen Keine Tags, Fügen Sie den ersten Tag hinzu!
Назва журналу:	Digital Library of Periodicals of National Academy of Sciences of Ukraine
Zitieren:	Mathematical relations of models of single-phase flows in the channels of reactors and steam generators of NPP's for calculation of heat transfer processes and hydrodynamic characteristics / O.V. Yefimov, M.M. Pylypenko, V.L. Kavertsev, T.A. Harkusha, L.J. Tiutiunyk, A.V. Motovilnik // Problems of Atomic Science and Technology. — 2022. — № 1. — С. 179-185. — Бібліогр.: 11 назв. — англ.

Institution

Digital Library of Periodicals of National Academy of Sciences of Ukraine

Ähnliche Einträge

Mathematical relationships of models of two-phase flows in channels of reactors and steam generators of NPP's for the calculation of their hydrodynamic characteristics
von: Yefimov, О.V., et al.
Veröffentlicht: (2022)

Computer simulation of thermal and hydraulic processes in NPP steam generator channels on the basis of interval-iterative method
von: Yefimov, O.V., et al.
Veröffentlicht: (2022)

The method for optimizing the iron content in the structural material Zr1%Nb for fuel element cladding of NPP nuclear reactors
von: Yefimov, O.V., et al.
Veröffentlicht: (2023)

Determination of the dependence of the NPP unit power on the steam temperature at the outlet of the superheater separator first stage with an uncertainty of information
von: Yefimov, O.V., et al.
Veröffentlicht: (2022)

Interval models of temperature characteristics of superheater separators in nuclear power plant units with the capacity of 1000 MW
von: Yefimov, O.V., et al.
Veröffentlicht: (2022)

Improving the efficiency of the unit of the Zaporizhzhia NPP with a WWER–1000 reactor
von: Cheilytko, A.A., et al.
Veröffentlicht: (2020)

Components of automated intellectual systems supporting decisions at the stage of operation and equipment diagnostics of nuclear power units
von: Yefimov, О.V., et al.
Veröffentlicht: (2020)

Processing of experimental data of the process of refining nuclear material Zr1%Nb by electron-beam melting by means of interval analysis methods
von: Yefimov, A.V., et al.
Veröffentlicht: (2019)

Influence of iron additives on the corrosion resistance of the Zr-1%Nb alloy under operating conditions of a nuclear reactor
von: Pylypenko, M.M., et al.
Veröffentlicht: (2022)

Estimation of the dependence parameters of nuclear structural materials hardness on the content of gas impurities: an interval approach
von: Potanina, Т.V., et al.
Veröffentlicht: (2021)

The numerical investigation of heat transfer at a water flow in the vertical steam generating channel
von: M. M. Kovetskaja, et al.
Veröffentlicht: (2017)

Empirical predicted residual life of the base metal of MCP of WWER-1000 reactors in operation
von: Gozhenko, S.V.
Veröffentlicht: (2023)

CFD model as a digital twin of the radiation state of the new safe confinement of the chernobyl NPP
von: Krukovskyi, P.G., et al.
Veröffentlicht: (2020)

A similarity criterion for spherical fuel elements free fall velocity in cylindrical channels with viscous liquid
von: Andrieieva, O.L., et al.
Veröffentlicht: (2021)

Analysis of reliability of the automatic core protection function of the reactor V-412 in response to local parameters: maximum linear power, departure from nucleate boiling ratio
von: Lys, S.S., et al.
Veröffentlicht: (2021)

Basic approaches to the choice of material for working blades of the last stages of the LPC of powerful steam turbines
von: Slaston, L.O., et al.
Veröffentlicht: (2020)

Comparative characteristics of mechanical and adsorption properties of activated charcoals applied for adsorbers of NPP air discharge systems
von: Lepin, I.V., et al.
Veröffentlicht: (2020)

Physical-mechanical aspects of degradation of heat-echange tubes metal for steam-generators of the type PGW-1000
von: Voyevodin, V.N., et al.
Veröffentlicht: (2019)

Assessment of impacting the thin protective coatings on the stress–strain state of the cladding of fuel rods of nuclear reactors
von: Povolotskii, E.V., et al.
Veröffentlicht: (2020)

Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding
von: Zuyok, V., et al.
Veröffentlicht: (2022)

Influencing of thin protective coatings on natural frequencies of radial oscillations of claddings of fuel rods of nuclear reactors
von: Mazurenko, Yu.E., et al.
Veröffentlicht: (2020)

Research by direct methods of the base metal of main circulation pipeline of the power unit 3 of the south ukraine NPP after 200 thousand hours of operation
von: Vasilenko, R.L., et al.
Veröffentlicht: (2022)

Concerning the Chornobyl NPP reactor graphite management
von: Yu. O. Olkhovyk
Veröffentlicht: (2019)

Steam explosions at severe accidents in pressurized nuclear reactors
von: I. L. Kozlov
Veröffentlicht: (2014)

Application of interval analysis for improving reliability of estimation of hardness value spread for nuclear structural materials
von: Yefimov, A.V., et al.
Veröffentlicht: (2020)

Hydrodynamics of a reactor with updated structure of frame mixing device
von: V. O. Zazymko, et al.
Veröffentlicht: (2021)

Conditions of appearance of steam explosions during accidents in tank reactors
von: V. I. Skalozubov, et al.
Veröffentlicht: (2015)

Effect of TiN inclusions and vibration loads on damage of heat exchange pipes of PGV-1000 steam generators
von: Mitrofanov, A.S.
Veröffentlicht: (2022)

Automated system for diagnostics and repair of reactor containment at Bilibin NPP
von: R. Rozert, et al.
Veröffentlicht: (2012)

Zooplankton of channels of cooling system of the Khmelnitsky NPP
von: Ju. F. Gromova, et al.
Veröffentlicht: (2015)

Zone refining of zirconium in an electric field
von: Kozhevnikov, O.E., et al.
Veröffentlicht: (2020)

On the extension of service life of Ukraine&#039;s NPP reactors
von: M. F. Shulha
Veröffentlicht: (2016)

Nuclear zirconium – the basis of alloys with improved neutron-physical, radiation, and corrosion properties
von: Mukhachev, A.P., et al.
Veröffentlicht: (2020)

Processing substandard materials of magnesium-thermal zirconium production
von: Pylypenko, M.M., et al.
Veröffentlicht: (2019)

Pure hafnium for nuclear power
von: Pylypenko, M.M., et al.
Veröffentlicht: (2020)

The refining of titanium by the method of zone recrystallization in an electric field
von: Kozhevnikov, O.E., et al.
Veröffentlicht: (2022)

Concomitant extraction process of niobium at the titanium tetrachloride production
von: Sarsembekov, Т.К., et al.
Veröffentlicht: (2020)

Effect of hydrogenation on creep and structure evolution of nanocrystalline Zr1Nb alloy
von: Savchuk, E.S., et al.
Veröffentlicht: (2023)

Possible Mechanism of Formation of Nuclei of Hydrodynamic Plastic Flow Channels in Crystals
von: V. I. Zasimchuk, et al.
Veröffentlicht: (2014)

Residual life of NPP reactor equipment exposed to high-temperature and radiation fields
von: V. A. Pukhlij
Veröffentlicht: (2011)