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Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
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Showing 1 to 12 of 12 for “"Zirconium-alloy"”.
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The vanadium-zirconium alloy system
<p>This investigation of the vanadium-zirconium alloy system produced evidence on several points concerning the equilibrium diagram. It was shown that a eutectic reaction between an intermediate phase and a zirconium-rich solid solution occurs at a temperature of 1230° +/- 10°C, and that the …
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Zirconium alloy getter bed air-ingress thermal failure analysis
In the event of an unexpected inrush of air into a packed St-909 getter bed, the exothermic reaction of oxygen and pellet material pushes temperatures within the bed to extremely high levels. This failure mode, which could be caused by a line rupture, was modeled, analyzed, and a full-scale …
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Microstructural study of zirconium oxide grown on a zirconium alloy substrate for orthopaedic applications
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Materials Science and Engineering, 1998.
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Electrochemical study of corrosion phenomena in zirconium alloys
Shadow corrosion of zirconium alloy fuel cladding in BWR environments, the phenomenon in which accelerated corrosion is experienced when the cladding surface is in close proximity to other metals, has become a potentially life-limiting issue for BWR fuel. Recent results from experimentation at MIT, …
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Fuel performance of multi-layered zirconium and silicon carbide based Accident Tolerant Fuel claddings
… severe accidents compared to the standard UO₂-Zr alloy fuel system. This thesis investigates the feasibility of four different cladding concepts, two of which are zirconium-alloy based and two are SiC-based. The Zirconium-alloy based claddings are 1) Zr4-Chromium coated cladding and 2) Zr4-FeCrAl …
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Estudo do processamento termomecânico de liga experimental de zircônio e seu efeito nas propriedades mecânicas e formação de hidretos
Zirconium alloys are used in components of nuclear reactors, particularly in the fuel element, for their excellent properties of corrosion resistance, mechanical resistance, thermal conductivity and low neutron absorption. The interaction with hydrogen during the operation of the reactor leads to …
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Quantifying the fouling resistance of Accident-Tolerant Fuel (ATF) cladding coatings with force spectroscopy
… aluminum carbide (Ti2AlC), and max-phase zirconium alloy 211(Zr4M211) behaved similarly in air and in water. The forces on each surface increased with increasing dwell time for the Fe3O4 particle AFM tip; in contrast, most adhesion forces stayed constant with the NiO AFM tip. Furthermore, …
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Safety of light water reactor fuel with silicon carbide cladding
… cladding - an emerging option to replace the zirconium alloy cladding - are assessed. Its behavior under accident conditions is examined with an integrated approach of experiments, modeling, and simulation. High temperature (1100°C~1500°C) steam oxidation experiments demonstrated that the …
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Hydrogen entry in Zircaloy-4 fuel cladding : an electrochemical study
Corrosion and hydrogen pickup of zirconium alloy fuel cladding in water cooled nuclear reactors are life-limiting phenomena for fuel. This thesis studies the fate of hydrogen liberated by waterside corrosion of Zircaloy-4 fuel cladding in Pressurized Water Reactors (PWRs): are the adsorbed protons …
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Electrochemical Hydrogen Absorption by Zr-Cu-Al-Ni Metallic Glasses
… has been studied on the Zr-based amorphous alloys. The influence of hydrogen absorption on the stability of the amorphous phase and its crystallisation was investigated. Additionally, the cathodic hydrogen reaction mechanism on the surface of the alloy, the reversibility of the absorbed …
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Integridad estructural de vainas de combustible nuclear en condiciones de almacenamiento temporal en seco
… fission products are contained in thin-walled zirconium tubes, known as nuclear fuel cladding. The effect of the hydrogen content on the mechanical properties and fracture behaviour of nuclear fuel cladding was studied in this Doctoral Thesis. The claddings used for this study are made of a …
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RADIATION CHEMISTRY IN PRESSURIZED WATER NUCLEAR REACTORS: H2 GENERATION BY 10B(n,α)7Li, AND THE REACTION OF BORATE WITH •OH
… cells made from tubing of either titanium or zirconium alloy. After exposure for a minimum of one hour, the solution samples were extracted and sparged with argon. The H2 entrained by the sparging gas was sampled with a small mass spectrometer. A small amount of sodium was included in the …