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dc.contributor.authorDong, Qingshan
dc.contributor.otherQueen's University (Kingston, Ont.). Theses (Queen's University (Kingston, Ont.))en
dc.date.accessioned2018-09-21T13:50:11Z
dc.date.available2018-09-21T13:50:11Z
dc.identifier.urihttp://hdl.handle.net/1974/24857
dc.description.abstractZr-2.5Nb-0.5Cu alloy is considered as a potential replacement of the current Inconel X-750 alloy for future spacer installations in CANDU® reactors. They are designed to be placed in the annular space between pressure and calandria tubes to support the pressure tube and prevent it from coming into contact with the calandria tube. During their service lifetime, they are exposed to a high flux of fast neutrons and multiple-directional loads. Therefore, it is important to study the effect of irradiation on the microstructure, microchemistry, and mechanical property of this alloy. In this dissertation, the effect of ion irradiation, heat treatment, alloying elements, pre-existing crystal defects on the microstructure and irradiation hardening was investigated to help us have a better understanding of this alloy before its application. Chapters 1 and 2 present a general introduction to the current investigated material and a literature review to previous related studies. Characterization of the microstructure and precipitates of the as-received material is presented in Chapter 3. Three types of microstructure and three types of second phase particles are detected in the as-received material. A comparison between annealing in TEM thin foils and bulk material is displayed in Chapter 4. The change of microstructure and precipitates is significantly slower in TEM thin foils than in bulk material, due to the presence of the foil surfaces. Chapter 5 reports the precipitate stability in the three types of microstructure under heavy ion irradiation. The starting microstructure shows a remarkable influence on the precipitate stability; the precipitates are more stable in the microstructure with a high density of point defect sinks. Chapters 6 and 7 cover the impact of alloying elements Nb and Cu on the loop formation and hardening in Zr alloys under self-ion irradiation. The existence of Nb and Cu exhibits a significant influence on the loop density and Burgers Vector of loops obtained, as well as ω precipitation and subsequent hardening behaviour. In Chapters 8 and 9, pure Mg was used as an analogue of Zr to provide additional insight into the influence that crystal internal defects, such as grain boundaries and gliding dislocations, have on the loop formation during irradiation. Noticeably different loop formation behaviour was observed in the vicinity of a grain boundary under electron irradiation. The pre-existing dislocations also displayed a noteworthy impact on the loop formation.en_US
dc.language.isoengen_US
dc.relation.ispartofseriesCanadian thesesen
dc.rightsCC0 1.0 Universal*
dc.rightsQueen's University's Thesis/Dissertation Non-Exclusive License for Deposit to QSpace and Library and Archives Canadaen
dc.rightsProQuest PhD and Master's Theses International Dissemination Agreementen
dc.rightsIntellectual Property Guidelines at Queen's Universityen
dc.rightsCopying and Preserving Your Thesisen
dc.rightsThis publication is made available by the authority of the copyright owner solely for the purpose of private study and research and may not be copied or reproduced except as permitted by the copyright laws without written authority from the copyright owner.en
dc.rights.urihttp://creativecommons.org/publicdomain/zero/1.0/*
dc.subjectZr-2.5Nb-0.5Cuen_US
dc.subjectIrradiationen_US
dc.subjectMicrostructureen_US
dc.subjectHardnessen_US
dc.titleMicrostructural Evolution and Hardening of Zr-2.5Nb-0.5Cu Spacer Material under Irradiationen_US
dc.typethesisen
dc.description.degreeDoctor of Philosophyen_US
dc.contributor.supervisorYao, Zhongwen
dc.contributor.supervisorDaymond, Mark
dc.contributor.departmentMechanical and Materials Engineeringen_US
dc.embargo.termsI want to restrict it for five years for these two reasons. 1) some papers are still not published; 2) this studied material is restricted from a nuclear company.en_US
dc.embargo.liftdate2023-09-20T17:56:23Z


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