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dc.contributor.advisorGhosh, Tushar K.eng
dc.contributor.advisorLoyalka, Sudarshan Keng
dc.contributor.authorLee, Yoonjo J., 1983-eng
dc.date.issued2016eng
dc.date.submitted2016 Falleng
dc.descriptionDissertation supervisor: Dr. Tushar K. Ghosh nad Dr. Sudarshan K. Loyalka.eng
dc.descriptionIncludes vita.eng
dc.description.abstractOne of the most severe accidents anticipated for the Very High Temperature Reactor (VHTR) is an air ingress accident caused by a pipe break, where the reactor vessel and core become fully immersed in air as the core temperature rises potentially reaching 1873 K. Graphite oxidation is predicted to be severe under these conditions. Gasification of graphite impacts its geometry and reduces thermal and mechanical properties, thus affecting the safe performance and shortening the service-life of components constructed of graphite. We have studied the oxidation rate of several nuclear-grade and matrix-grade graphites including NBG-18 and IG-110 as well as GKrS, respectively. Oxidation data was collected thermogravimetrically for air ingress accident scenarios from 873 to 1873 K using a Thermax700[registered trademark symbol] thermogravimetric analyzer. A semi-empirical Arrhenius rate equation was developed for the kinetic regime for each graphite grade. The activation energy for the matrix-grade graphite was within the limited historically reported values while the activation energy of nuclear-grade graphite was determined to be well within literature values. The surfaces of oxidized graphite samples were further characterized by SEM, EDS, FTIR and XPS.eng
dc.description.bibrefIncludes bibliographical references.eng
dc.format.extent1 online resource (viii, 107 pages) : illustrationseng
dc.identifier.merlinb118814680eng
dc.identifier.oclc989737607eng
dc.identifier.urihttps://hdl.handle.net/10355/59845
dc.identifier.urihttps://doi.org/10.32469/10355/59845eng
dc.languageEnglisheng
dc.publisherUniversity of Missouri--Columbiaeng
dc.relation.ispartofcommunityUniversity of Missouri--Columbia. Graduate School. Theses and Dissertationseng
dc.rightsOpenAccess.eng
dc.rights.licenseThis work is licensed under a Creative Commons Attribution-NonCommercial-NoDerivs 3.0 License.eng
dc.subject.FASTNuclear reactors -- Safety measures -- Researcheng
dc.subject.FASTGraphite -- Thermal propertieseng
dc.subject.FASTOxidationeng
dc.subject.FASTMaterials at high temperatures -- Testing.eng
dc.titleOxidation of nuclear- and matrix-grade graphite for VHTR air ingress accident scenarioseng
dc.title.alternativeOxidation of nuclear- and matrix-grade graphite for Very High Temperature Reactor air ingress accident scenarioseng
dc.typeThesiseng
thesis.degree.disciplineNuclear engineering (MU)eng
thesis.degree.grantorUniversity of Missouri--Columbiaeng
thesis.degree.levelDoctoraleng
thesis.degree.namePh. D.eng


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