Sökning: "Nuclear materials"
Visar resultat 11 - 15 av 258 avhandlingar innehållade orden Nuclear materials.
11. 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
12. Modeling defect structure evolution in spent nuclear fuel container materials
Sammanfattning : Materials intended for disposal of spent nuclear fuel require a particular combination of physical and chemical properties. The driving forces and mechanisms underlying the material’s behavior must be scientifically understood in order to enable modeling at the relevant time- and length-scales. LÄS MER
13. 2D hybrid modeling of defects in an ultrasonic inspection situation
Sammanfattning : Advanced methods of nondestructive evaluations (NDE) are widely used for in-service inspection in many industrial applications, e.g. nuclear and aerospace industries. In these applications the components are exposed to different degradation mechanisms (e. LÄS MER
14. Development of a Method for Accelerated Ageing of Cementitious Materials Used in Repositories for Nuclear Waste
Sammanfattning : The Swedish nuclear fuel and waste management company (SKB), is required to validate the service life prediction of the concrete structures in nuclear waste repositories. Considering the repository being in contact with water , the decalcification process of cementitious materials although being very slow can during the very long operational lifetime of the repository (up to 100000 years), cause the degradation of chemical and mechanical properties of the concrete structures. LÄS MER
15. Studies of transport in oxides on Zr-based materials
Sammanfattning : 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. LÄS MER