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Degradation of Zirconium Alloys - Superalloys Lecture 9
This set of lectures is on "Degradation of Zr Alloys" for the Superalloys & High Performance Materials course part 9. This part of the course was taught by Dr Christopher Daniel at The University of Manchester in 2021.
Video 1 will describe why the nuclear reactor environment causes complex processes that degrade the properties of the zirconium cladding.
Video 2 will explain how the stages of periodic corrosion observed in zirconium alloys can be described by changes in the oxide microstructure, as well as describing how second phase particles (SPPs) can improve the corrosion properties.
Video 3 will describe the processes of hydrogen pickup, hydride formation and delayed hydride cracking (DHC) to explain the importance of hydrogen in degrading zirconium cladding properties both in the reactor and out of service in dry storage.
Video 4 will explain how neutron irradiation changes material properties and affects the in-reactor behaviour of the zirconium cladding, including a description of irradiation induced growth in terms of the accumulation of vacancy and interstitial dislocation loops.
Video 5 will describe the processes of irradiation enhanced creep and the mechanism of pellet cladding interaction (PCI), which can degrade the zirconium cladding and limit the power manoeuvring of nuclear power stations.
Video 6 will explain the advantages and disadvantages of alternative cladding materials that could replace zirconium alloys to provide superior accident tolerance.
The live lecture includes poll questions and discussion for the "Degradation of Zr Alloys" topic and was recorded on Tuesday 13th April 2021.
Funding
LightForm: Embedding Materials Engineering in Manufacturing with Light Alloys
Engineering and Physical Sciences Research Council
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