Nuclear Engineering Commons^™

Fundamentals Of Cavity Formation In Α-Fe And Fe-Cr Alloys, Yan-Ru Lin

Doctoral Dissertations

Ferritic-martensitic steels are attractive candidate materials for fusion and advanced fission reactors primarily due to their low swelling characteristic, attractive thermo-mechanical properties, and the potential for development of nanostructured ferritic alloys. However, significant discrepancies exist regarding the effect of solutes and irradiation temperature on cavity swelling under ion versus neutron irradiation conditions. Several mechanisms have been proposed that may affect cavity swelling, but no general theory or model has received complete acceptance to explain these phenomena.

To better understand the formation of cavities in ferritic steels, we have performed multi-temperature (400-550°C) single-beam and simultaneous dual-beam irradiations (ex-situ and in-situ) on …

Nuclear Fuel Materials Under Extremes: Redox Behavior And Resulting Defect Structure, William Cureton

Doctoral Dissertations

Oxide nuclear fuel materials and analogues are often subject to complex structural and chemical changes when exposed to extreme environments. For example, oxidation and buildup of fission products cause changes to the local- and long-range structure as well as the chemistry and stoichiometry of UO₂ during operation in light water reactors. Highly ionizing energetic fission fragments have been shown to cause redox effects and associated defect structures in oxide nuclear fuel-type materials. The underlying mechanisms that lead to defect structures produced in a wider range of nuclear fuel material compositions and microstructures is not well understood.

This research project …

Microstructural Investigation Of Hydride Reorientation In Zirconium Based Spent Nuclear Fuel Cladding, Tyler S. Smith

Doctoral Dissertations

Hydride embrittlement and the impact of hydride reorientation are failure phenomena of particular interest during the transportation process of spent nuclear fuel from wet storage to dry storage. This process exposes the cladding to elevated temperatures and high pressure-induced hoop stresses that can release the hydride platelets back into solution and cause them to radially precipitate upon cooling. Though the impact of high temperature and high-pressure conditions on hydride reorientation have been investigated for many nonirradiated specimens, a data gap remains for the coupling effects of irradiation at these conditions in high burnup spent nuclear fuel rods. To simulate this …