Browsing Mechanical and Materials Engineering, Department of by Author "Yao, Zhongwen"
Now showing items 1-9 of 9
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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 ... -
Fabrication, Characterization, and Irradiation of an Austenitic Oxide Dispersion Strengthened Steel Suited for Next Generation Nuclear Applications
Brooks, AdamAs 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 ... -
Investigation of the Stability of C15 Laves Phase Structures in BCC Iron by Molecular Dynamics Method
Wang, Hao (2016-05-02)A new class of interstitial clusters which present a structure of C15 Laves phase has been theoretically predicted in bcc iron. However, these C15 clusters have never been identified experimentally. In this thesis, molecular ... -
Irradiation induced damage in CANDU spacer material Inconel X-750
Zhang, He (2013-09-10)Inconel alloys are commonly used as structural materials in nuclear reactors. One of these alloys, the Inconel X-750, is a γ’ Ni3(Al, Ti) strengthened superalloy extensively used in the cores of reactors, such as spacers ... -
Irradiation induced damage in CANDU spacer material Inconel X-750
Zhang, HeInconel alloys are commonly used as structural materials in nuclear reactors. One of these alloys, the Inconel X-750, is a γ’ Ni3(Al, Ti) strengthened superalloy extensively used in the cores of reactors, such as spacers ... -
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 ... -
The Microstructures of Zr-Excel Alloy: Effects of Heavy Ion Irradiation, Plastic Deformation, Thermal Treatment and In-Situ Heating
Yu, Hongbing (2016-09-26)Zr-Excel alloy (Zr-3.5Sn-0.8Nb-0.8Mo) is a dual phase (α + β) alloy in the as-received pressure tube condition. It has been proposed to be the pressure tube candidate material for the Generation-IV CANDU-Supercritical Water ... -
Molecular Dynamics Simulation of Irradiation Damage in α-Zirconium
Di, Sali (2016-02-29)Zirconium alloys, due to their good corrosion resistance and low neutron absorption cross section, are widely used in heavy and light water nuclear reactors. Irradiation induced defects and deformation lead to mechanical ... -
Radiation Damage Effect on Mechanical Properties and Microstructure of X-750 Ni-based Superalloy
Changizian, PooyanInconel X-750 is an age-hardened Ni-based superalloy with high mechanical strength and creep resistance. The X-750 alloy is extensively used in the cores of reactors, such as spacers in CANada Deuterium Uranium (CANDU) ...