<![CDATA[The performance of research reactors heavily depends on the intensity of the neutron flux produced, which is a key factor in reactor efficiency and effectiveness. To enhance the performance of research reactors, high-density fuel is required to increase neutron flux in the reactor core, enabling optimal irradiation processes. One of the most promising fuel candidates is uranium-molybdenum (U-Mo) alloy. This study aims to investigate the properties of U-Mo alloys through a series of characterizations, including density measurements, phase analysis using X-ray Diffraction (XRD), and microstructural observations using a Scanning Electron Microscope (SEM). The density measurements revealed values close to theoretical calculations, with densities of 17.423 g/cm³ for U-7Mo, 17.292 g/cm³ for U-8Mo, and 17.229 g/cm³ for U-9Mo. XRD analysis identified the presence of the γ-U phase with a body-centered cubic (bcc) crystal structure, characterized by diffraction peaks at 2θ angles of 37°, 53°, 66°, and 78°. SEM observations showed a pattern of bright and dark areas, which were further analyzed using Energy Dispersive Spectroscopy (EDS). EDS analysis indicated that the bright areas had a higher concentration of Mo and a lower oxide content compared to the dark areas. These findings suggest that the addition of Mo not only improves the structural homogeneity but also enhances the oxidation resistance of U-Mo alloys.]]>
Copyrights © 2025
