K Forsberg and A R Massih 2007 Modelling Simul. Mater. Sci. Eng. 15 335 doi:10.1088/0965-0393/15/3/011
K Forsberg1 and A R Massih2,3,4
Show affiliationsA theoretical framework for the calculation of fission product gas release by diffusion, irradiation-induced re-solution, grain boundary saturation and grain growth in ceramic nuclear fuel (UO2) under time-varying loads is presented. The diffusion equation is subjected to boundary conditions, which account for the aforementioned effects. Analytical solutions to the equation are obtained. The theory is applied to calculate fission gas release and grain growth as functions of temperature and time. Correlation between grain growth and gas release is calculated and the results are discussed in the light of experimental data.
28.41.Bm Fuel elements, preparation, reloading, and reprocessing
61.72.Mm Grain and twin boundaries
Issue 3 (April 2007)
Received 11 July 2006, in final form 31 January 2007
Published 26 March 2007
K Forsberg and A R Massih 2007 Modelling Simul. Mater. Sci. Eng. 15 335
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