Search for dissertations about: "zirconium hydride"
Showing result 1 - 5 of 9 swedish dissertations containing the words zirconium hydride.
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1. Phase transformation and stability studies of the Zr-H system
Abstract : Zirconium alloys are widely used in the nuclear industry because of their high strength, good corrosion resistance and low neutron absorption cross-section. Zirconium has a strong affinity for hydrogen, however, and if hydrogen concentration builds up, the material will gradually degrade. READ MORE
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2. In-situ phase studies of the Zr-H system
Abstract : Zirconium alloys are widely used in the nuclear industry because of their high strength, good corrosion resistance and low neutron absorption cross-section. However, zirconium has strong affinity for hydrogen, which may lead to hydrogen concentration build-up over time during a corrosion reaction when exposed to water. READ MORE
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3. 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
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4. Phase-field modeling of stress-induced precipitation and kinetics in engineering metals
Abstract : The formation of brittle compounds in metals operating in corrosive environments can be a tremendous source of embrittlement for industrial structures and such phenomenon is commonly enhanced in presence of stresses. To study this type of microstructural change modeling is preferred to experiment to reduce costs and prevent undesirable environmental impacts. READ MORE
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5. First Principles Approach to the Hydrogen Pick-up during Oxidation of Zirconium Alloys by Water
Abstract : Zirconium alloys are widely used in nuclear power plants as cladding material to contain the fission fuel in the reactor cores. A limiting factor for fuel longevity is the corrosion property of the zirconium alloys. The main corrodent in the reactor core is water. READ MORE