Sökning: "Pia Tejland"
Hittade 2 avhandlingar innehållade orden Pia Tejland.
1. Microstructure Investigation of the Oxidation Process in Zircaloy-2 - The Effect of Intermetallic Particle Size
Sammanfattning : 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. With an improved corrosion resistance the alloys could be used for much longer times in the reactors, increasing fuel burn-up and decreasing the amount of radioactive waste. LÄS MER
2. Microstructure of Zirconium Alloys Oxidized in Steam
Sammanfattning : 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. LÄS MER