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dc.contributor.advisorMiller, William Hughes, 1941-eng
dc.contributor.advisorHanson, Brady D.(Brady Dean)eng
dc.contributor.authorCasella, Amanda J., 1980-eng
dc.coverage.spatialNevada -- Yucca Mountaineng
dc.date.issued2008eng
dc.date.submitted2008 Falleng
dc.descriptionTitle from PDF of title page (University of Missouri--Columbia, viewed on Feb 24, 2010).eng
dc.descriptionThe entire thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file; a non-technical public abstract appears in the public.pdf file.eng
dc.descriptionDissertation supervisors: Dr. William H. Miller, Dr. Brady D. Hanson.eng
dc.descriptionVita.eng
dc.descriptionIncludes bibliographical references.eng
dc.descriptionPh. D. University of Missouri--Columbia 2008.eng
dc.descriptionDissertations, Academic -- University of Missouri--Columbia -- Nuclear engineering.eng
dc.description.abstractAs part of the performance assessments of proposed geologic repositories the effects of temperature, dissolved O₂, and water and fuel chemistry on the dissolution rates of spent fuel are necessary to provide a quantitative estimate of the potential dose over geologic time frames. In this research, fuels containing Gd₂O₃-doped UO₂ were tested in a single-pass flow-through setup. These tests have verified that in bicarbonate solutions as temperature increased the dissolution rate increased. However, the presence of silicate in the feedwater altered the system and lowered the dissolution rate at higher temperatures. Only the pure UO₂ samples exhibited a dependence on the dissolved O₂ concentration, which increased with rising temperature. The Gd₂O₃-dopant stabilized the fuel matrix and lowered the dissolution rate increasingly up to 4 wt%. The dissolution rates for pure UO₂ compared reasonably well with the Yucca Mountain Model for tests performed at 50°C and 75°C, but were found to be approximately half the values predicted by the model at 25°C. After long time periods when the radiolytic field has diminished, additional benefits in dissolution reduction should exist due to constituents such as Gd₂O₃ in the fuel matrix and silicate in the groundwater. Thus, the durability of spent fuel in Yucca Mountain may be greater than previously modeled.eng
dc.format.extentxx, 166 pageseng
dc.identifier.oclc556274531eng
dc.identifier.urihttps://hdl.handle.net/10355/6625
dc.identifier.urihttps://doi.org/10.32469/10355/6625eng
dc.languageEnglisheng
dc.publisherUniversity of Missouri--Columbiaeng
dc.relation.ispartofcommunityUniversity of Missouri--Columbia. Graduate School. Theses and Dissertationseng
dc.subject.lcshSpent reactor fuels -- Storage -- Mathematical modelseng
dc.titleThe dissolution rate of unirratiated UO₂ under repository conditions: the influence of fuel and water chemistry, dissolved oxygen, and temperatureeng
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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