Now showing items 1-3 of 3
Fabrication, Characterization, and Irradiation of an Austenitic Oxide Dispersion Strengthened Steel Suited for Next Generation Nuclear Applications
As nuclear energy systems become more advanced, the materials encompassing them need to perform at higher temperatures for longer periods of time. In this Master’s thesis we experiment with an oxide dispersion strengthened ...
Effect of Process Parameters on Deformation of Zr-2.5wt%Nb Alloy
Zirconium and its alloys are used extensively in the nuclear industry. In the Canadian Deuterium Uranium reactor, the primary containment in the primary coolant system is composed of Zr-2.5wt%Nb in the form of a pressure ...
Studies on the Measurement and Modeling of Lattice Strains in Rolled Zircaloy-2
Neutron diffraction is a widely used technique for measuring internal stresses inside polycrystalline materials. By examining the diffraction patterns collected during in situ uniaxial deformation, the lattice strains ...