Thermal conductivity coefficient UO[2] of theoretical density and regular stoichiometry

Thermal conductivity coefficient UO[2] of theoretical density and regular stoichiometry

Бібліографічні деталі
Parent link:MATEC Web of Conferences
Vol. 92 : Thermophysical Basis of Energy Technologies (TBET-2016).— 2017.— [01050, 5 p.]
Автор: Kuzmin A. V. Arian Valerievich
Співавтор: Национальный исследовательский Томский политехнический университет (ТПУ) Энергетический институт (ЭНИН) Кафедра атомных и тепловых электростанций (АТЭС)
Інші автори: Yurkov M. M.
Резюме:Title screen
The main methodological research results of the thermal conductivity of uranium dioxide (UO[2]) were considered. UO[2] 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 UO[2] density is proposed. According to this methodology we conducted the analysis of the experimental dependences of the thermal conductivity obtained by domestic authors.
Опубліковано: 2017
Предмети:
электронный ресурс
труды учёных ТПУ
коэффициент теплопроводности
плотность
стехиометрия
диоксид урана
топлива
ядерные реакторы
теплопроводность
Онлайн доступ:http://dx.doi.org/10.1051/matecconf/20179201050
http://earchive.tpu.ru/handle/11683/36702
Формат: Електронний ресурс Частина з книги
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=653001
Опис
Резюме:Title screen
The main methodological research results of the thermal conductivity of uranium dioxide (UO[2]) were considered. UO[2] 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 UO[2] density is proposed. According to this methodology we conducted the analysis of the experimental dependences of the thermal conductivity obtained by domestic authors.
DOI:10.1051/matecconf/20179201050

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