Email this article A model of uranium dioxide thermal conductivity
- Authors: Devyatko Y.N.1, Novikov V.V.2, Khomyakov O.V.1, Chulkin D.A.2
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Affiliations:
- National Research Nuclear University MEPhI
- Bochvar High-Technology Research Institute of Inorganic Materials
- Issue: Vol 7, No 3 (2016)
- Pages: 409-418
- Section: New Methods of Treatment and Production of Materials with Required Properties
- URL: https://journals.rcsi.science/2075-1133/article/view/205100
- DOI: https://doi.org/10.1134/S2075113316030059
- ID: 205100
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Abstract
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.
About the authors
Yu. N. Devyatko
National Research Nuclear University MEPhI
Author for correspondence.
Email: ydevyatko@mail.ru
Russian Federation, Kashirskoe sh. 31, Moscow, 115409
V. V. Novikov
Bochvar High-Technology Research Institute of Inorganic Materials
Email: ydevyatko@mail.ru
Russian Federation, ul. Rogova 5a, Moscow, 123098
O. V. Khomyakov
National Research Nuclear University MEPhI
Email: ydevyatko@mail.ru
Russian Federation, Kashirskoe sh. 31, Moscow, 115409
D. A. Chulkin
Bochvar High-Technology Research Institute of Inorganic Materials
Email: ydevyatko@mail.ru
Russian Federation, ul. Rogova 5a, Moscow, 123098
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