Sökning: "Zircaloy"
Visar resultat 1 - 5 av 13 avhandlingar innehållade ordet Zircaloy.
1. Matrix composition in Zircaloy
Sammanfattning : .... LÄS MER
2. Study on the Mechanisms for Corrosion and Hydriding of Zircaloy
Sammanfattning : 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. LÄS MER
3. Modified oxygen and hydrogen transport in Zr-based oxides
Sammanfattning : 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. LÄS MER
4. 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
5. 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