Search for dissertations about: "oxidation of zirconium"
Showing result 1 - 5 of 23 swedish dissertations containing the words oxidation of zirconium.
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1. Studies of transport in oxides on Zr-based materials
Abstract : Zr-based materials have found their main application in the nuclear field having high corrosion resistance and low neutron absorption cross-section. The oxide layer that is formed on the surface of these alloys is meant to be the barrier between the metal and the corrosive environment. READ MORE
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2. Microstructure of Zirconium Alloys Oxidized in Steam
Abstract : Zirconium alloys are widely used in nuclear reactors as fuel cladding tubes because of their low thermal neutron capture cross-section, good corrosion properties and satisfactory mechanical properties. However, the main limiting factor of these materials is the oxidation behavior. READ MORE
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3. Study on the Mechanisms for Corrosion and Hydriding of Zircaloy
Abstract : This thesis is focused on the mechanisms for corrosion andhydriding of Zircaloy. Special attention is paid tomicrostructural characterisation by cross sectionaltransmission electron microscopy of the oxide layer formed. READ MORE
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4. Modified oxygen and hydrogen transport in Zr-based oxides
Abstract : Most metals and alloys in the presence of oxygen and moisture will instantaneously react and form a thin (2-5 nm) surface oxide layer. For further reaction to occur, oxygen ions and/or metal cations often diffuse through the already formed oxide layer. READ MORE
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5. Mechanistic Approach to Corrosion of Zirconium by Water - A First Principle Study
Abstract : Zirconium and zirconium oxides are of major technological importance. There are broad applications for these materials, from fuel cell electrolyte to semiconductors and in hip-implants. In nuclear power plants, zirconium alloys are widely used as cladding material to contain the fission fuel in the reactor cores. READ MORE