Sökning: "cladding materials"
Visar resultat 1 - 5 av 38 avhandlingar innehållade orden cladding materials.
1. Evolution of microstructure and nanoscale chemistry of Zircaloy-2-type alloys during nuclear reactor operation
Sammanfattning : Zirconium alloys are used as fuel cladding tubes in nuclear reactors. During reactor operation, these alloys are degraded by corrosion, hydrogen pickup (HPU), and radiation-induced growth, processes influenced by the alloying elements. LÄS MER
2. Atom probe tomography of Zircaloy-2 exposed to boiling water reactor operation
Sammanfattning : Zirconium alloys are used as cladding tubes for the fuel in nuclear reactors. In boiling water reactors (BWRs), the alloy Zircaloy-2, which contains the alloying elements Sn, Fe, Cr, Ni, and O, is commonly used. LÄS MER
3. Laser cladding : an experimental and theoretical investigation
Sammanfattning : Avhandlingen omfattar studier vid laserpåsvetsning och lasergjutning med CO2-laser och Nd:YAG-laser. Avhandlingen är indelad i sex kapitel. Kapitel 1 är en presentation/introduktion av laserpåsvetsning och några applikationsområden tillsammans med alla abstract, sammanfattningar och de viktigaste figurerna som ingår i de övriga kapitlen. LÄS MER
4. Cold spray Cr-coated Optimized ZIRLO claddings: an option for accident tolerant fuels
Sammanfattning : Accident tolerant fuel development has started with the aim of providing nuclear fuels able to endure severe accident conditions. Research in this field has also sparked a wave of material renewal in the nuclear industry that had being delayed for the last few decades. LÄS MER
5. Atom Probe Tomography of Hydrogen and of Grain Boundaries in Corroded Zircaloy-2
Sammanfattning : Due to their low thermal neutron capture cross-section, zirconium alloys are widely used in the nuclear industry for fuel cladding and structural components. The lifetime of the fuel assemblies in the reactors are largely dictated by the ability of the fuel cladding to withstand corrosion and mechanical damage. LÄS MER