Open AccessMathematical 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
Author(s) -
Aleksandr Ivanovich Kanareykin
Publication year - 2022
Publication title -
iop conference series. earth and environmental science
Language(s) - English
Resource type - Journals
eISSN - 1755-1307
pISSN - 1755-1315
DOI - 10.1088/1755-1315/990/1/012012
Subject(s) - uranium oxide , thermal conductivity , nuclear fuel , uranium , work (physics) , nuclear engineering , materials science , nuclear reactor , thermal , finite element method , oxide , mechanics , thermodynamics , physics , engineering , metallurgy
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.