important quantities in determination of fuel behavior in normal reactor operation and reactor
transients. The aim of this study is to compare the heat capacity of oxide and nitrite fuels by
using Einstein-Debye approximation. A simple analytical expression was performed to
calculate the heat capacity of fuels. To test the validity and reliability, the calculated formulas
were compared to published results for various nuclear fuels including UO 2, ThO 2, PuO 2 …