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- W4212869894 abstract "Abstract The work is devoted to the thermal calculation of the fuel element of a nuclear reactor. Attention was paid to the mathematical modeling of the temperature field under boundary conditions of the first kind. Approximations of the dependence of the thermal conductivity of uranium oxide on temperature in the form of a quadratic function were used for numerical modeling." @default.
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- W4212869894 date "2022-02-01" @default.
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- W4212869894 title "Mathematical modeling of the fuel element of a nuclear reactor taking into account the temperature dependence of the thermal conductivity of the fuel element made of uranium oxide" @default.
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- W4212869894 doi "https://doi.org/10.1088/1755-1315/990/1/012012" @default.
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