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    Browsing by Subject "Zirconium"

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      • ADVANCED TECHNIQUES FOR THE CHARACTERIZATION OF HYDRIDED ZIRCONIUM ALLOY 

        Allen, Gregory (2011-01-18)
        Zirconium alloy pressure tubes are an important component in CANDU nuclear reactors. During operation these tubes can pick up hydrogen as a result of a corrosion reaction, which can eventually lead to the precipitation ...
      • Characterization of Deformation Mechanisms in Zirconium Alloys: Effect of Temperature and Irradiation 

        Long, Fei (2015-03-02)
        Zirconium alloys have been widely used in the CANDU (CANada Deuterium Uranium) reactor as core structural materials. Alloy such as Zircaloy-2 has been used for calandria tubes; fuel cladding; the pressure tube is manufactured ...
      • Effect of Process Parameters on Deformation of Zr-2.5wt%Nb Alloy 

        Cochrane, Christopher James (2013-10-15)
        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 ...
      • Lattice Strain and Texture of Plastically Deformed Zircaloy-2 at 77K 

        Judge, Colin (2009-12-07)
        Zircaloy-2 is used extensively in the nuclear industry as a structural material for the reactor core in both light and heavy water reactors. The intergranular strains and texture greatly affect the mechanical properties ...
      • MICROSTRUCTURAL EVOLUTION IN ZR AND ZR ALLOY EXCEL UNDER ION IRRADIATION 

        Idrees, Yasir (2014-01-03)
        Zirconium and its alloys have been used extensively in both light and heavy water reactors where neutron irradiation is known to cause microstructural evolution, leading to degradation of mechanical properties and dimensional ...
      • 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 ...
      • Studies on the Measurement and Modeling of Lattice Strains in Rolled Zircaloy-2 

        Skippon, Travis (2013-03-06)
        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 ...
      • Texture Evolution and Variant Selection in Zr-2.5Nb During the α-β Phase Transformation 

        Mosbrucker, Paula L. (2010-09-24)
        Zr-2.5Nb is used as the pressure tube material for 2nd and 3rd generation CANDU reactors. The physical properties of pressure tubes in service, including strength, dimensional stability, and delayed hydride cracking ...

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