Buchumschlag

Computer modeling of the thermal field in the elementary volume of polymer composites

The paper considers the opportunity for investigation of the thermal field in two-component systems of the type of polymeric composite materials with continuous fibrous filler. In view of the widespread use of polymer composites high relevance of issues relating to their processing. Is a literary an...

Ausführliche Beschreibung

Gespeichert in:

Bibliographische Detailangaben
Datum:	2014
1. Verfasser:	Мелентьев, Р. Ю.
Format:	Artikel
Sprache:	Russisch
Veröffentlicht:	Інститут енергетичних машин і систем ім. А. М. Підгорного Національної академії наук України 2014
Schlagworte:	polymer composite materials thermal field thermal conductivity fiber elementary cell УДК 53.053 004.383.4
Online Zugang:	https://journals.uran.ua/jme/article/view/27184
Tags:	Tag hinzufügen Keine Tags, Fügen Sie den ersten Tag hinzu!
Назва журналу:	Energy Technologies & Resource Saving

Institution

Energy Technologies & Resource Saving

Ähnliche Einträge

Computer modeling of the thermal field in the elementary volume of polymer composites
von: Мелентьев, Р. Ю.
Veröffentlicht: (2014)

INFLUENCE OF ELECTRO-THERMAL PARAMETERS OF POLYMER COMPOSITE FUSES ON THE EFFICIENCY OF SOLAR CELLS
von: Korsunskyi , R., et al.
Veröffentlicht: (2025)

Experimental study of the thermal conductivity of composite materials collectors of solar energy
von: Reztsov, V., et al.
Veröffentlicht: (2016)

The investigations of a peculiarities of pyrocarbon gas phase densification of powders of the catalytic carbon formations (CCFS), obtained on nickel
von: Fursov, S.G., et al.
Veröffentlicht: (2021)

The technology of extraction and enrichment of scandium from uranium-phosphorus-rare earth concentrate
von: Mukhachev, A.P., et al.
Veröffentlicht: (2023)

Leaching of uranium ores in the process of sodium sulphate electrolysis
von: Nefedov, V.G., et al.
Veröffentlicht: (2019)

Purification of rare earth elements from thorium, uranium, and radioactive isotopes
von: Mukhachev, A.P., et al.
Veröffentlicht: (2021)

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

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

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)

Electrode processes in electrolysis of zirconium at production of plastic zirconium for nuclear energy
von: Mukhachev, A.P., et al.
Veröffentlicht: (2019)

Microstructure and mechanical properties of oxide dispersion strengthened high-entropy alloys CoCrFeMnNi and CrFe₂MnNi
von: Kolodiy, I.V., et al.
Veröffentlicht: (2021)

Efficiency of combined Fe and Pb radiation shield of transport casks for SNF transportation
von: Rudychev, V.G., et al.
Veröffentlicht: (2022)

Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant
von: Hrinchenko, H., et al.
Veröffentlicht: (2019)

Influence of electrolyte on the zirconium electrolysis process for nuclear power engineering
von: Moravetsky, S.I., et al.
Veröffentlicht: (2020)

Experimental study of transformation of carbonate system components cooling water of Rivne nuclear power plant during water treatment by liming
von: Kuznietsov, P.N., et al.
Veröffentlicht: (2023)

Properties of tubes from Zr-1% Nb alloy after thermochemical treatment and hydrogenation
von: Trush, V.S., et al.
Veröffentlicht: (2021)

Prospects of application of tubes made of duplex steels of a new generation in the heat exchanging equipment of nuclear power plants
von: Dergach, T.A., et al.
Veröffentlicht: (2019)

Burnup and radiation embrittlement of the U-Mo neutron source target
von: Borts, B.V., et al.
Veröffentlicht: (2022)

Fractal model of estimating quality of cold worked fuel cladding tubes
von: Vakhrusheva, V.S., et al.
Veröffentlicht: (2021)

Thermophysical properties of fuel clading with various vacuum-arc coatings
von: Belous, V.A., et al.
Veröffentlicht: (2019)

Radioactive metals in red mud
von: Kolobov, G.А., et al.
Veröffentlicht: (2020)

On the options of Ukraine’s nuclear fuel cycle
von: Krasnorutskyy, V.S., et al.
Veröffentlicht: (2019)

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)

Research the behaviour and properties of WWER type fuel claddings from Zr1%Nb alloy in loss of the coolant accident
von: Semerak, M.M., et al.
Veröffentlicht: (2021)

Monitoring of berillium content in waste water of nsc kipt before and after purification
von: Gordienko, Yu.A., et al.
Veröffentlicht: (2020)

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)

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

Features of formation of crystallographic texture and properties in Ti-3Al-2.5V titanium alloy during tubes manufacture
von: Vakhrusheva, V.S., et al.
Veröffentlicht: (2019)

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

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

Risk-informed method for predicting the operation life extension period of active safety systems at nuclear power plants
von: Skalozubov, V.I., et al.
Veröffentlicht: (2022)

Secondary raw materials of radioactive metals
von: Kolobov, G.A., et al.
Veröffentlicht: (2019)

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)

Increasing the radiation safety of nuclear power plants using the method of controlling the tightness of fuel elements
von: Mamontov, О., et al.
Veröffentlicht: (2022)

Formation of plastic properties of 12Cr18Ni10Ti steel highly irradiated by neutrons
von: Maksimkin, О.P., et al.
Veröffentlicht: (2021)

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)

Nano-mechanisms of connection in the solid phase of tungsten and tantalum in the manufacture of a neutron source target
von: Borts, B.V., et al.
Veröffentlicht: (2023)

Delving into some specific features of the magnetic systems used for the plasma recycling of the spent nuclear fuel (SNF)
von: Yuferov, V.B., et al.
Veröffentlicht: (2022)

Studying the changes in the mechanical properties of neutron-irradiated chromium-nickel steels using the “Shear Punch” method
von: Maksimkin, О.P., et al.
Veröffentlicht: (2019)