Thermal conductivity coefficient UO2 of theoretical density and regular stoichiometry

A. V. Kuzmin, M. M. Yurkov

Результат исследований: Материалы для журнала

1 цитирование (Scopus)

Выдержка

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.

Язык оригиналаАнглийский
Номер статьи01050
ЖурналMATEC Web of Conferences
Том92
DOI
СостояниеОпубликовано - 21 дек 2016
Событие2016 Thermophysical Basis of Energy Technologies, TBET 2016 - Tomsk, Российская Федерация
Продолжительность: 26 окт 201628 окт 2016

Отпечаток

Stoichiometry
Thermal conductivity
Uranium dioxide
uranium dioxide

ASJC Scopus subject areas

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

Цитировать

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

В: MATEC Web of Conferences, Том 92, 01050, 21.12.2016.

Результат исследований: Материалы для журнала

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