A study on heat capacity of oxide and nitride nuclear fuels by using Einstein-Debye approximation

Nuclear Engineering and Technology

卷:52

B. Duyuran¹  E. Eser²  M.H. Bölükdemir³  H. Koç³ 

[1] Corresponding author.;

[2] Department of Physics, Ankara Hacı Bayram Veli University, Polatlı, Ankara, Turkey;

[3] Department of Physics, Gazi University, Ankara, Turkey;

关键词: Oxide fuel;    Nitride fuel;    Heat capacity;    Einstein-Debye approximation;   

DOI  :  

来源: DOAJ

【 摘 要 】

Knowledge on fuel enthalpy and its temperature derivative, the heat capacity, are 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 UO2, ThO2, PuO2 and UN. Calculated formulas yielded results in consistent with literature.

【 授权许可】

Unknown