Sökning: "Zircaloy-4"
Hittade 3 avhandlingar innehållade ordet Zircaloy-4.
1. Matrix composition in Zircaloy
Sammanfattning : .... LÄS MER
2. Mechanisms of Uniform Corrosion of Zirconium Alloys in Water and Steam
Sammanfattning : Zirconium alloys are used in key components in nuclear reactors, e.g. fuel cladding tubes in pressurised water reactors. Current trends towards extended burnup of the nuclear fuel in these reactors have accentuated the demand for Zr alloys with higher uniform corrosion resistance under irradiation and lower hydrogen absorption. LÄS MER
3. 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