Thermal conductivity coefficient UO2 of theoretical density and regular stoichiometry

Thermal conductivity coefficient UO2 of theoretical density and regular stoichiometry

The main methodological research results of the thermal conductivity of uranium dioxide (UO2) were considered. UO2 is the main fuel of modern nuclear energetic reactors. The assessment of efficiency of the proposed approximations compared to Fink-Ronchi formula at the theoretical values of UO2 densi...

Ausführliche Beschreibung

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Bibliographische Detailangaben
Hauptverfasser: Kuzmin, A V, Yurkov, M M
Format: Tagungsbericht
Sprache:eng
Schlagworte:
Heat conductivity
Heat transfer
Nuclear fuels
Nuclear reactors
Residential density
Stoichiometry
Theoretical density
Thermal conductivity
Uranium
Uranium dioxide
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Beschreibung
Zusammenfassung:The main methodological research results of the thermal conductivity of uranium dioxide (UO2) were considered. UO2 is the main fuel of modern nuclear energetic reactors. The assessment of efficiency of the proposed approximations compared to Fink-Ronchi formula at the theoretical values of UO2 density is proposed. According to this methodology we conducted the analysis of the experimental dependences of the thermal conductivity obtained by domestic authors.
ISSN:2274-7214
2261-236X
DOI:10.1051/matecconf/20179201050