Отправить статью по E-mail A model of uranium dioxide thermal conductivity
- Авторы: Devyatko Y.N.1, Novikov V.V.2, Khomyakov O.V.1, Chulkin D.A.2
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Учреждения:
- National Research Nuclear University MEPhI
- Bochvar High-Technology Research Institute of Inorganic Materials
- Выпуск: Том 7, № 3 (2016)
- Страницы: 409-418
- Раздел: 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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Аннотация
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.
Об авторах
Yu. Devyatko
National Research Nuclear University MEPhI
Автор, ответственный за переписку.
Email: ydevyatko@mail.ru
Россия, Kashirskoe sh. 31, Moscow, 115409
V. Novikov
Bochvar High-Technology Research Institute of Inorganic Materials
Email: ydevyatko@mail.ru
Россия, ul. Rogova 5a, Moscow, 123098
O. Khomyakov
National Research Nuclear University MEPhI
Email: ydevyatko@mail.ru
Россия, Kashirskoe sh. 31, Moscow, 115409
D. Chulkin
Bochvar High-Technology Research Institute of Inorganic Materials
Email: ydevyatko@mail.ru
Россия, ul. Rogova 5a, Moscow, 123098
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