Thermal conductivity coefficient UO[2] of theoretical density and regular stoichiometry; MATEC Web of Conferences; Vol. 92 : Thermophysical Basis of Energy Technologies (TBET-2016)

Xehetasun bibliografikoak
Parent link:MATEC Web of Conferences
Vol. 92 : Thermophysical Basis of Energy Technologies (TBET-2016).— 2017.— [01050, 5 p.]
Egile nagusia: Kuzmin A. V. Arian Valerievich
Erakunde egilea: Национальный исследовательский Томский политехнический университет (ТПУ) Энергетический институт (ЭНИН) Кафедра атомных и тепловых электростанций (АТЭС)
Beste egile batzuk: Yurkov M. M.
Gaia: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.
Hizkuntza:ingelesa
Argitaratua: 2017
Gaiak:
Sarrera elektronikoa:http://dx.doi.org/10.1051/matecconf/20179201050
http://earchive.tpu.ru/handle/11683/36702
Formatua: Baliabide elektronikoa Liburu kapitulua
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=653001

MARC

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330 |a 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. 
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