Sharif Digital Repository

Zirconium-based alloys are among the most important materials used for nuclear fuel cladding due to their high thermal stability, excellent corrosion resistance, and low neutron absorption cross section. However, under reactor operating conditions, neutron irradiation leads to the formation of point defects, microstructural evolution, and ultimately degradation of the mechanical properties of these alloys. Therefore, the addition of alloying elements such as niobium has been proposed as an effective approach to improve the irradiation tolerance and mechanical performance of zirconium alloys. In this study, the effects of different niobium contents on the irradiation response and mechanical...