Browsing Mechanical and Materials Engineering, Department of by Author "Daymond, Mark"
Now showing items 1-9 of 9
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Advanced Characterization of Hydrides in Zirconium
Shiman, OksanaZirconium and its alloys are of great importance to the nuclear power industry due to their unique combination of mechanical properties, low neutron-capture cross-section, and sufficient corrosion resistance under reducing ... -
Atomistic simulations of irradiation-induced dislocation loops in zirconium alloys
Dai, CongIrradiation-induced dislocation loops are important defects that affect zirconium alloys used in the manufacture of major structural components of nuclear reactors. In this thesis atomistic simulations and theoretical ... -
Characterization of Strain Rate Sensitivity, Plastic Anisotropy, and Dislocation Content in Zircaloy-2
Skippon, TravisZirconium alloys are used broadly throughout the nuclear industry due to a combination of its mechanical properties, low neutron absorption cross section, and resistance to corrosion. Understanding the process of plastic ... -
The Design and Integration of an In-Situ Proton Irradiation Tensile Rig
Moore, BrodieOne of the biggest challenges faced in the nuclear industry is understanding and accurately predicting the complex environment found in a nuclear power reactor and its impact on core components and materials. The extreme ... -
The Inhomogeneous Microstructure and Deformation of Similar and Dissimilar Al-Zn Containing Mg Friction Stir Welds
Hiscocks, JessicaThe magnesium-based aluminum-zinc alloys have excellent stiffness to weight ratios, and may be combined by friction stir welding to expand the possible applications. The high aluminum alloy AZ80 in particular has the ... -
Mechanical Testing and Characterization of Proton Irradiated 99.4% NI Using the Reactor Materials Testing Laboratory
Mattucci, MitchThe Queen’s Reactor Material Testing Laboratory uses proton irradiation to simulate the damage induced in a material from neutrons, within a nuclear reactor environment. Inconel X-750 is a 70wt% Ni superalloy, used for the ... -
Microstructural Characterization of 3D Deposited Metal Structures
Solomon, JordanThe microstructure of deposited materials is characterized using a variety of techniques. The two specific types of deposited materials studied are electrodeposited nickel and additive manufactured stainless steel. A focus ... -
Microstructural Evolution and Hardening of Zr-2.5Nb-0.5Cu Spacer Material under Irradiation
Dong, QingshanZr-2.5Nb-0.5Cu alloy is considered as a potential replacement of the current Inconel X-750 alloy for future spacer installations in CANDU® reactors. They are designed to be placed in the annular space between pressure and ... -
Mode I Fracture Testing on Zirconium Foils Under Plane-stress Condition
Wang, ZhouyaoZirconium alloys are commonly used in nuclear reactor in-core components due to their good mechanical properties and low neutron-absorption cross-section. Especially for CANada Deuterium Uranium (CANDU) reactors, zirconium ...