A model of uranium dioxide thermal conductivity


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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.

Авторлар туралы

Yu. Devyatko

National Research Nuclear University MEPhI

Хат алмасуға жауапты Автор.
Email: ydevyatko@mail.ru
Ресей, Kashirskoe sh. 31, Moscow, 115409

V. Novikov

Bochvar High-Technology Research Institute of Inorganic Materials

Email: ydevyatko@mail.ru
Ресей, ul. Rogova 5a, Moscow, 123098

O. Khomyakov

National Research Nuclear University MEPhI

Email: ydevyatko@mail.ru
Ресей, Kashirskoe sh. 31, Moscow, 115409

D. Chulkin

Bochvar High-Technology Research Institute of Inorganic Materials

Email: ydevyatko@mail.ru
Ресей, ul. Rogova 5a, Moscow, 123098

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© Pleiades Publishing, Ltd., 2016