A model of uranium dioxide thermal conductivity


如何引用文章

全文:

开放存取 开放存取
受限制的访问 ##reader.subscriptionAccessGranted##
受限制的访问 订阅存取

详细

Existing models for calculation of thermal conductivity of uranium dioxide are analyzed. Anomalous growth of the thermal conductivity coefficient of nuclear fuel in the high-temperature region is explained. Models of specific heat at constant volume and thermal conductivity are proposed. It is demonstrated that the contribution of degrees of freedom of charge carriers to the observed thermal conductivity coefficient of admixture-free stoichiometric UO2 can be neglected up to the melting point.

作者简介

Yu. Devyatko

National Research Nuclear University MEPhI

编辑信件的主要联系方式.
Email: ydevyatko@mail.ru
俄罗斯联邦, Kashirskoe sh. 31, Moscow, 115409

V. Novikov

Bochvar High-Technology Research Institute of Inorganic Materials

Email: ydevyatko@mail.ru
俄罗斯联邦, ul. Rogova 5a, Moscow, 123098

O. Khomyakov

National Research Nuclear University MEPhI

Email: ydevyatko@mail.ru
俄罗斯联邦, Kashirskoe sh. 31, Moscow, 115409

D. Chulkin

Bochvar High-Technology Research Institute of Inorganic Materials

Email: ydevyatko@mail.ru
俄罗斯联邦, ul. Rogova 5a, Moscow, 123098

补充文件

附件文件
动作
1. JATS XML

版权所有 © Pleiades Publishing, Ltd., 2016