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dc.contributor.advisorLoyalka, S. K.eng
dc.contributor.advisorHanson, Brady D.(Brady Dean)eng
dc.contributor.authorCasella, Andrew M., 1979-eng
dc.date.issued2007eng
dc.date.submitted2007 Summereng
dc.descriptionThe entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file.eng
dc.descriptionTitle from title screen of research.pdf file (viewed on November 26, 2007.eng
dc.descriptionVita.eng
dc.descriptionThesis (Ph. D.) University of Missouri-Columbia 2007.eng
dc.description.abstractThere are two important phenomena associated with the depressurization of a dry spent nuclear fuel canister after the formation of a through-wall pinhole breach. The first phenomenon is the release from the canister of any radioactivity that might have become suspended within the fill gas and the second is the transport of oxygen into the canister (leading to oxidation of cladding and any exposed fuel) after pressure equilibrium has been reached. In order to better quantify the effects associated with these phenomena, several models have been constructed. The first of these models determines the depressurization time of a breached canister in which no particles are suspended in the fill gas. The second model tracks the possible transport of fission gases and helium produced from alpha decay through nano-scale pathways within the spent fuel located in the canister. The third model expands the first model to track any suspended particle release from the canister and to monitor particle deposition within the breach (along with the associated flow area blockage). The fourth model uses Monte Carlo methods to remove several limitations of the third model, including particle deposition patterns, effects of particle size, and breach geometry. The results generated by these models provide a better understanding of the time-dependent behavior of a spent fuel canister that has developed a microscopic through-wall breach and may prove to be useful tools in the future monitoring and handling of spent fuel canisters.eng
dc.identifier.merlinb61467820eng
dc.identifier.oclc182522660eng
dc.identifier.urihttps://hdl.handle.net/10355/4695
dc.identifier.urihttps://doi.org/10.32469/10355/4695eng
dc.languageEnglisheng
dc.publisherUniversity of Missouri--Columbiaeng
dc.relation.ispartofcollectionUniversity 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.
dc.subject.lcshAerosols, Radioactiveeng
dc.subject.lcshNuclear fuelseng
dc.subject.lcshNuclear fuel claddings -- Effect of radiation oneng
dc.subject.lcshMonte Carlo methodeng
dc.titleModeling of molecular and particulate transport in dry spent nuclear fuel canisterseng
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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