O. Anderoglu

Nanoscale morphologies at alloyed and irradiated metal-oxide bilayers

Individually, alloying and ion irradiation are two avenues for modifying the chemical and phase structure at solid-state interfaces. Both can lead to the phenomena of alloying, intermixing, and, when combined, radiation-induced elemental redistribution. Thus, understanding how each independently influences the structure of interfaces provides insight into the chemical morphologies at the interface, the possible formation of secondary phases, and the basic mechanisms necessary for understanding alloying. Within the analytical framework provided by electron microscopy, we study changes in structure and chemistry in connection with the formation of composite layered interfaces following alloying and ion irradiation at metal-oxide interfaces. In particular, the chemical evolutions of as-deposited Fe/Cr and irradiated Fe thin films on

Viability of thin wall tube forming of ATF FeCrAl

\hbox {TiO}_{2}

Ion irradiation testing of Improved Accident Tolerant Cladding Materials

TiO2 are characterized to reveal structural and chemical changes associated with physical interactions induced by either alloying or irradiation. The results of the study conclude by comparing the effects of alloying with radiation-induced intermixing. We find that the extent of Fe intermixing into the

Development of improved ATF engineering alloy - Mechanical testing of initial alloy

\hbox {TiO}_{2}

The influence of ∑3 twin boundaries on the formation of radiation-induced defect clusters in nanotwinned Cu

TiO2 substrate is similar for both irradiated and alloyed films, indicating that both can lead to the formation of similar complex nanoscale morphologies at the interface. Our results highlight the complex and competing phenomena that dictate the structure and chemistry at these interfaces.

Mechanisms of He escape during implantation in CuNb multilayer composites

HT-9 is a 12Cr - 1Mo ferritic/martensitic steel with significant experience as cladding material in fast reactor applications. Recent investigations into precipitation of ά in HT-9 steel after irradiation at elevated temperatures suggests that it nucleates at dislocation loops. It is recognized that steel shocked below the α to ϵ high-pressure phase transformation results in a material with a high density of stored defects. These defects have profound effect on subsequent mechanical properties and with additional elevated temperature exposure could serve as nucleation sites for the ά precipitate. To investigate the possibility of precipitating ά at dislocations, HT-9 steel was shocked at a peak pressure of 11 GPa and subsequently annealed at 475 °C for up to 16 weeks. The mechanical response of shock prestrained HT-9 steel was investigated and compared to the mechanical response of the shocked and annealed material. Substructure and texture evolution due to shock loading was examined and mechanical respon...