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dc.contributor.advisorPinhero, Patrick J.eng
dc.contributor.authorSchwarz, Eric A., 1979-eng
dc.coverage.spatialMissourieng
dc.date.issued2011eng
dc.date.submitted2011 Springeng
dc.descriptionTitle from PDF of title page (University of Missouri--Columbia, viewed on July 11, 2011).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.descriptionThesis advisor: Dr. Patrick J. Pinhero.eng
dc.descriptionLaboratory Molten Salt Procedures on p. 52 not included.eng
dc.descriptionIncludes bibliographical references.eng
dc.descriptionM.S. University of Missouri--Columbia 2011.eng
dc.description.abstractNuclear fuel reprocessing is a responsible choice for the continued expansion of a secure, safe and clean source of energy. While the classical method for recycling nuclear fuel is an aqueous liquid-liquid extraction, the use of a dry, non-aqueous electrochemical means of separating constituents is gaining attention. In the 1990's, the University of Missouri (MU) performed molten chemical experiments on mixed lanthanide and actinide systems appropriate for the separation of species known to be encountered when nuclear fuel is recycled. This project was completed by 2000 and new equipment must be ready to restart this electrochemical research. This work describes the technology that is now available to continue this work. Specifically, the containment required for keeping a clean environment for operations is described as well as a new reference electrode designed for molten salt electrochemistry that does not require Vycor or quartz in its construction and demonstrates good reliability. Some electrochemical examinations were conducted on samples of green mill tailings from a hematite mine in southeastern Missouri. These tailings are rich in rare-earth elements (lanthanides) which are technologically important for electronics manufacture. Separation of these elements into pure metals can be accomplished with far fewer waste products using a dry molten salt.eng
dc.format.extentv, 52 pageseng
dc.identifier.urihttp://hdl.handle.net/10355/11506
dc.languageEnglisheng
dc.publisherUniversity of Missouri--Columbiaeng
dc.relation.ispartofcommunityUniversity of Missouri-Columbia. Graduate School. Theses and Dissertations. Theses. 2011Theseseng
dc.rightsOpenAccess.eng
dc.rights.licenseThis work is licensed under a Creative Commons Attribution-NonCommercial-NoDerivs 3.0 License.
dc.subject.lcshAlpha-bearing wasteseng
dc.subject.lcshActinide elementseng
dc.subject.lcshMolten salt reactorseng
dc.subject.lcshNuclear fuelseng
dc.subject.lcshRadioactive waste disposaleng
dc.subject.lcshRare earth metals -- Recyclingeng
dc.titleTechnology for restarting molten salt nuclear fuel chemistry at MUeng
dc.typeThesiseng
thesis.degree.disciplineChemical engineering (MU)eng
thesis.degree.grantorUniversity of Missouri--Columbiaeng
thesis.degree.levelMasterseng
thesis.degree.nameM.S.eng


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