Show simple item record

FieldValueLanguage
dc.contributor.authorHuang, Siyu
dc.date.accessioned2024-07-19T04:40:20Z
dc.date.available2024-07-19T04:40:20Z
dc.date.issued2023en_AU
dc.identifier.urihttps://hdl.handle.net/2123/32822
dc.descriptionIncludes publication
dc.description.abstractZirconium alloys are used as structural components and as fuel cladding in nuclear reactors due to their excellent mechanical properties, low neutron absorption cross section, and high corrosion resistance. However, zirconium alloys corrode quickly, their properties can degrade over time via exposure to radiation, and reactions with the reactor coolant produce hydrogen gas, which embrittles the cladding and reduces component lifetime. There is value in better understanding the microstructural features that contribute to the properties of these alloys and may trap the hydrogen. This thesis describes how advanced microscopy techniques were used to study the microstructure of Zr alloys, with a view towards designing alloys which last longer and are less susceptible to hydrogen embrittlement. Samples were primarily studied using atom probe tomography, a microscopy technique with near-atomic spatial resolution and equal sensitivity to all elements, including hydrogen and deuterium. Scanning electron microscopy, transmission electron microscopy, transmission Kikuchi diffraction and electron backscatter diffraction were used to support the APT measurements. In Optimised ZIRLO, electron microscopy and APT allowed for microanalysis of grain boundaries and several types of precipitates, including one never before reported. Electrochemical deuterium charging was used to induce hydride growth in Optimised ZIRLO, and cryogenic sample transfer protocols allowed study of the hydrides and their internal interfaces using APT. In Zircaloy-4, the composition of the precipitates and their interfaces have been characterized by APT for the first time, and microstructural evolution and solute segregation at grain boundaries after high-pressure torsion in Zircaloy-4 has been quantified. All these findings inform future research and applications of Zr alloys. These results contribute valuable information to enhance corrosion and hydrogen embrittlement resistance in the design of Zr alloys.en_AU
dc.language.isoenen_AU
dc.subjectZr alloysen_AU
dc.subjectatom probe tomographyen_AU
dc.subjecthydrogen embrittlementen_AU
dc.subjectmaterial characterizationen_AU
dc.subjectmaterial scienceen_AU
dc.subjectnuclear materialsen_AU
dc.titleUncovering the Nanoscale Distribution of Solutes in Zirconium Alloysen_AU
dc.typeThesis
dc.type.thesisDoctor of Philosophyen_AU
dc.rights.otherThe author retains copyright of this thesis. It may only be used for the purposes of research and study. It must not be used for any other purposes and may not be transmitted or shared with others without prior permission.en_AU
usyd.facultySeS faculties schools::Faculty of Engineering::School of Aerospace Mechanical and Mechatronic Engineeringen_AU
usyd.degreeDoctor of Philosophy Ph.D.en_AU
usyd.awardinginstThe University of Sydneyen_AU
usyd.advisorCairney, Julie
usyd.include.pubYesen_AU


Show simple item record

Associated file/s

Associated collections

Show simple item record

There are no previous versions of the item available.