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

Year 2016, Volume: 16 Issue: 3, 517 - 520, 31.12.2016

Ebru Çopuroğlu

Abstract

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.

Keywords

Heat Capacity Einstein-Debye Approximation Nuclear Fuels

References

  • 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.

Year 2016, Volume: 16 Issue: 3, 517 - 520, 31.12.2016

Ebru Çopuroğlu

Abstract

References

  • 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.
There are 21 citations in total.

Details

Primary Language English
Journal Section Articles
Authors

Ebru Çopuroğlu

Publication Date December 31, 2016
Submission Date May 31, 2016
Published in Issue Year 2016 Volume: 16 Issue: 3

Cite

APA Çopuroğlu, E. (2016). Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation. Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi, 16(3), 517-520.
AMA Çopuroğlu E. Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation. Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi. December 2016;16(3):517-520.
Chicago Çopuroğlu, Ebru. “Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation”. Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi 16, no. 3 (December 2016): 517-20.
EndNote Çopuroğlu E (December 1, 2016) Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation. Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi 16 3 517–520.
IEEE E. Çopuroğlu, “Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation”, Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi, vol. 16, no. 3, pp. 517–520, 2016.
ISNAD Çopuroğlu, Ebru. “Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation”. Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi 16/3 (December 2016), 517-520.
JAMA Çopuroğlu E. Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation. Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi. 2016;16:517–520.
MLA Çopuroğlu, Ebru. “Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation”. Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi, vol. 16, no. 3, 2016, pp. 517-20.
Vancouver Çopuroğlu E. Heat Capacity Study on the Evaluation of Uranium Nitride Using Einstein-Debye Approximation. Afyon Kocatepe Üniversitesi Fen Ve Mühendislik Bilimleri Dergisi. 2016;16(3):517-20.