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dc.contributor.advisorLoyalka, S. K.eng
dc.contributor.advisorTompson, R. V. (Robert Vaughn), 1958-eng
dc.contributor.advisorGhosh, Tushar K., Dr.eng
dc.contributor.authorWilson, Jasoneng
dc.date.issued2012eng
dc.date.submitted2012 Summereng
dc.descriptionTitle from PDF of title page (University of Missouri--Columbia, viewed on November 1, 2012).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 advisors: Dr. Sudarshan K. Loyalka, Dr. Robert V. Tompson, Jr., Dr. Tushar K. Ghosheng
dc.descriptionIncludes bibliographical references.eng
dc.descriptionVita.eng
dc.descriptionPh.D. University of Missouri--Columbia 2012.eng
dc.description"July 2012"eng
dc.description.abstract[ACCESS RESTRICTED TO THE UNIVERSITY OF MISSOURI AT AUTHOR'S REQUEST.] Measuring and quantifying the transport of helium and fission products in reactor materials is a critical element in the future success of Very High Temperature Reactors (VHTR's). While the extreme temperatures in VHTR's, which may be in excess of 950 [degree sign]C, allow for potentially very high efficiency, they also can be problematic due to the increase in fission product transport. The aim of this work was to address safety issues concerning VHTR's by developing better understandings of the flows and transport of fission gases through microcracks and nanopores in the fuel coatings and in the moderators. An additional purpose was also to improve the understanding of the transport of helium through these structures since, in a VHTR, helium will be very abundant. We used an existing system to obtain measurements of slip coefficients, which are useful in determining transport of helium gas mixtures, for varying mixtures of gases that could be present in a VHTR. The mixtures we have studied are helium and air, helium and nitrogen, helium and argon, and helium and nitrogen, with varying trace amounts of xenon. We also constructed a new system to aid in understanding the transport of helium and fission products through reactor grade graphites. This later work has permitted us to obtain results for the permeability and diffusion coefficients of various graphites.eng
dc.description.bibrefIncludes bibliographical references.eng
dc.format.extentix, 93 pageseng
dc.identifier.oclc872569399eng
dc.identifier.urihttps://doi.org/10.32469/10355/15924eng
dc.identifier.urihttps://hdl.handle.net/10355/15924
dc.languageEnglisheng
dc.publisherUniversity of Missouri--Columbiaeng
dc.relation.ispartofcommunityUniversity of Missouri--Columbia. Graduate School. Theses and Dissertationseng
dc.rightsAccess is limited to the campuses of the University of Missouri.eng
dc.subjectvery high temperature reactorseng
dc.subjectsafety issueseng
dc.subjectfission gaseseng
dc.subjectporous mediaeng
dc.titleTransport of helium and fission product gases in porous/fractured geometryeng
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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