Thermal conductivity coefficient UO[2] of theoretical density and regular stoichiometry; MATEC Web of Conferences; Vol. 92 : Thermophysical Basis of Energy Technologies (TBET-2016)
| Parent link: | MATEC Web of Conferences Vol. 92 : Thermophysical Basis of Energy Technologies (TBET-2016).— 2017.— [01050, 5 p.] |
|---|---|
| Autor principal: | |
| Autor Corporativo: | |
| Outros Autores: | |
| Resumo: | 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. |
| Idioma: | inglês |
| Publicado em: |
2017
|
| Assuntos: | |
| Acesso em linha: | http://dx.doi.org/10.1051/matecconf/20179201050 http://earchive.tpu.ru/handle/11683/36702 |
| Formato: | Recurso Eletrônico Capítulo de Livro |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=653001 |