Model for radiation damage-induced grain subdivision and its influence in U 3 Si 2 fuel swelling
Here, the swelling mechanisms of U 3 Si 2 from neutron irradiation under reactor conditions are not unequivocally known. The limited experimental evidence that is available suggests that the main driver of the swelling in this material would be fission gases accumulation at crystalline grain boundaries. The steps that lead to the accumulation of fission gases at these locations are multiple and complex. However, gradually, the gaseous fission products migrate by diffusion. Upon reaching a grain boundary, which acts as a trap, the gaseous fission products start to accumulate, thus leading to formation of bubbles and hence to induced swelling. Therefore, a quantitative model of swelling requires the incorporation of phenomena that increase the presence of grain boundaries and decrease grain sizes, thus creating sites for bubble formation and growth while concurrently deceasing the distance from gas species formation to gas accumulation sites. It is assumed that grain boundary formation results from the conversion of stored energy from accumulated dislocations into energy for the formation of new grain boundaries. This work attempts to develop a quantitative model for grain subdivision in U 3 Si 2 based on the above mentioned phenomena to quantitatively corroborate the presence of such a mechanism. Then the model is used in conjunction with swelling codes to evaluate the total swelling of a fuel pellet during its lifetime in the I 2 S-LWR reactor.