Thermal conductivity coefficient UO2 of theoretical density and regular stoichiometry

A. V. Kuzmin, M. M. Yurkov

Research output: Contribution to journalConference article

1 Citation (Scopus)

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 languageEnglish
Article number01050
JournalMATEC Web of Conferences
Volume92
DOIs
Publication statusPublished - 21 Dec 2016
Event2016 Thermophysical Basis of Energy Technologies, TBET 2016 - Tomsk, Russian Federation
Duration: 26 Oct 201628 Oct 2016

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Stoichiometry
Thermal conductivity
Uranium dioxide
uranium dioxide

ASJC Scopus subject areas

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

Cite this

Thermal conductivity coefficient UO2 of theoretical density and regular stoichiometry. / Kuzmin, A. V.; Yurkov, M. M.

In: MATEC Web of Conferences, Vol. 92, 01050, 21.12.2016.

Research output: Contribution to journalConference article

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