Akademik Veri Yönetim Sistemi
PROGRESS IN NUCLEAR ENERGY, cilt.190, 2026 (SCI-Expanded, Scopus)
In the present study, titanium-aluminum-tin-zirconium-molybdenum (Ti-Al-Sn-Zr-Mo) alloys were synthesized via mechanical alloying and powder injection moulding (PIM) for potential use as nuclear fuel rod cladding materials in pressurised water reactors (PWRs). These Ti-based alloys are proposed as an alternative to conventional zirconium alloys, which are susceptible to hydrogen uptake and oxidation under reactor operating conditions. Al, Zr, Mo, and Sn were strategically added to Ti to reduce its thermal neutron absorption crosssection and improve neutron economy. Corrosion behaviour was evaluated at room temperature and 100 degrees C in 20 wt% NaCl and Na2SO4 aqueous solutions. Electrochemical corrosion tests, including potentiodynamic polarization and cyclic polarization, were conducted to evaluate the general corrosion rate and localized corrosion susceptibility, respectively. Electrochemical potentiokinetic reactivation (EPR) testing was carried out to assess the susceptibility of the alloys to intergranular corrosion. The addition of Mo significantly improved resistance to localized corrosion, while the combined presence of Zr and Mo contributed to a reduction in the overall corrosion rate. The addition of Sn enhanced the sinterability of the alloy, while Al contributed to improved mechanical performance at elevated temperatures. Thermal neutron irradiation experiments were performed using a241Am-Be neutron source in order to determine the macroscopic neutron absorption crosssection of the alloy samples. Density functional theory (DFT)-based first-principles calculations were carried out using the CASTEP code to predict the elastic constants of the alloy and to support the interpretation of experimental results.