Thermal conductivity coefficient UO<sub>2</sub> of theoretical density and regular stoichiometry

Abstract

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.

Original language	English
Article number	01050
Journal	MATEC Web of Conferences
Volume	92
DOIs	https://doi.org/10.1051/matecconf/20179201050
Publication status	Published - 21 Dec 2016
Event	2016 Thermophysical Basis of Energy Technologies, TBET 2016 - Tomsk, Russian Federation Duration: 26 Oct 2016 → 28 Oct 2016

ASJC Scopus subject areas

Chemistry(all)
Materials Science(all)
Engineering(all)

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abstract = "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.",

author = "Kuzmin, {A. V.} and Yurkov, {M. M.}",

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AB - 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.

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Thermal conductivity coefficient UO₂ of theoretical density and regular stoichiometry

Abstract

ASJC Scopus subject areas

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