Affiliation:
1. Nuclear Science and Technology Research Institute , P. O. Box 11365-3486 , Tehran , I. R. Iran
Abstract
Abstract
A correlation for the volume porosity of irradiated UO2 fuel as a sum of the individual contributions of the pore and swelling porosity in terms of the local density and fractional matrix swelling is developed. By using the existing low temperature low burnup model of swelling, evolution of the matrix swelling and porosity terms are calculated for UO2 fuel in the low burnup but in the high burnup two various models are applied, the one with considering grain recrystallization and another without it but with the method of Xe depletion measurement. The purpose of the paper is comparison of fuel swelling behavior between two models at high burnups. The bulk swelling and porosity evolution in both methods are also validated by experimental data. Finally, one conclusion from this comparison is obtained, as the method which considering grain recrystallization has more rational behavior in the fuel swelling and porosity.
Subject
Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation
Reference21 articles.
1. Blair, P., Romano, A., Hellwig, C., and Chawla, R. (2006). Calculations on fission gas behaviour in the high burnup structure. J. Nucl. Mater. 350: 232–239, https://doi.org/10.1016/j.jnucmat.2006.01.006.
2. Bleiberg, M.L., Berman, R.M., and Lustman, B. (1963). Effects of high burn-up on oxide ceramic fuels. In: Symposium on radiation damage in solid and reactor materials. Proc. Series. IAEA, Venice, p. 319.
3. Cui, Y., Ding, S., Chen, Z., and Huo, Y. (2015). Modifications and applications of the mechanistic gaseous swelling model for UMo fuel. J. Nucl. Mater. 457: 157–164, https://doi.org/10.1016/j.net.2021.02.019.
4. Holt, L., Schubert, A., Van Uffelen, P., Walker, C.T., Fridman, E., and Sonoda, T. (2014). Sensitivity study on Xe depletion in the high burn-up structure of UO2. J. Nucl. Mater. 452: 166–172, https://doi.org/10.1016/j.jnucmat.2014.05.009.
5. Kaganas, G. and Rest, J. (2007). A physical description of fission product behavior fuels for advanced power reactors (No. ANL-07/24). Argonne National Lab. (ANL), Argonne, IL (United States).