Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation

Yıl 2016, Cilt: 16 Sayı: 3, 517 - 520, 31.12.2016

Ebru Çopuroğlu

Öz

We have proposed an alternative evaluation procedure for calculating specific heat capacity of Uranium Nitride nuclear fuel. The calculation results have been obtained by the use of Einstein-Debye approach. The proposed method is valid for all temperature values. This method can be easily applied to the other nuclear fuels to determine the other thermophysical properties.

Anahtar Kelimeler

Heat Capacity, Einstein-Debye Approximation, Nuclear Fuels

Kaynakça

• Askerov, B.M., Cankurtaran, M., 1994, Isobaric specific-heat and thermal expansion of solid in the Debye approximation. Phys. Stat. Sol. B, 185, 341-348.
• Carbajo, J. J., Yoder, G. L., Popov, S. G., Ivanov, V. K., 2001, A review of the thermophysical properties of MOX and UO2 fuels. J. Nucl. Mater. 299, 181-198.
• Cankurtaran, M., Askerov, V., 1996, Equation of state, isobaric specific heat, and thermal expansion of solids with polyatomic basis in the Einstein-Debye approximation. Phys. Stat. Sol. B, 194, 499-507.
• Fink, J. K., 2000, Thermophysical properties of uranium dioxide. J. Nucl. Mater. 279, 1-18.
• Guseinov, I.I., Mamedov, B.A., 2007, Calculation of integer and noninteger n-dimensional debye functions using binomial coefficients and incomplete gamma functions. Int. J. Thermophys 28, 1420-1426.
• Guseinov, I.I., Mamedov, B.A., 2004, Evaluation of incomplete gamma functions using downward recursion and analytical relations. J. Math. Chem. 36, 341-346.
• Grimvall G., 1999, Thermophysical properties of materials, Elsevier Science B.V., Amsterdam.
• Gradshteyn, I.S., Ryzhik, I.M., 1980, Tables of Integrals, Series and Products, Academic Press, New York.
• Hoch, M., Vernadakis, T., 1976, Thermodynamic properties of solid and liquid metals and ceramics. High Temp.-High Press. 8, 241-246.
• Kurosaki, K., Yamada, K., Uno, M., Yamanaka, S., Yamamoto, K., Namekowa, T., 2001, Molecular dynamics study of mixed oxide fuel. J. Nucl. Mater. 294, 160-167.
• Kang, K. H., Song, K. C., Yang, M. S., Lee, S. H., Ko, J. B., Kim, S. W., 2006, Thermophysical properties of multi-walled carbon nanotube- reinforced polypropylene composites. Int. J. Thermophys. 27, 152-160.
• Koç, H., Eser, E., Mamedov, B.A., 2011, Calculation of heat capacity of the nuclear fuels UO2 and NpO2 using integer and non-integer n- dimensional Debye functions. Nucl. Engin. Design, 241, 3678-3682.
• Lemehov, S.E., Sobolev,V., Van Uffelen, P., 2003, Modelling thermal conductivity and self- irradiation effects in mixed oxide fuels. J. Nucl. Mater. 320, 66-76.
• Landau, L. D., Lifshits, E.M., 1980, Statistical Physics, Pergamon Press, London.
• Mamedov B.A., 2014, Accurate analytical evaluation of heat capacity of nuclear fuels using Einstein-Debye approximation, Nuclear Engineering and Design, 276, 124.
• Peng, S, Grimvall, G., 1994, Heat capacity of actinide dioxides. J. Nucl. Mater. 210, 115- 122.
• Pioro I.L., Khan M., Hopps V. et al., 2008, Journal of Power and Energy Systems, 2, 874.
• Ronchi, C., 2007,Thermophysical properties affecting safety and performance of nuclear fuel. High Temperature 45, 552-571.
• Szpunar B. , Szpunar J.A., 2014, International Journal of Nuclear Energy, 2014, 7.
• White, J.T., Nelson, A.T., 2013, Thermal conductivity of UO2+x and U4O9−y. J. Nucl. Mater. 443, 342-350.
• Yun, Y., Oppeneer, P. M., 2011, First-principles design of next-generation nuclear fuels Mater. Res. Soc. (MRS)-Bulletin 36, 178-184.