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dc.contributor.advisorGhosh, Tushar K., Dr.eng
dc.contributor.authorMaynard, Raymond K.eng
dc.date.issued2011eng
dc.date.submitted2011 Summereng
dc.description"July 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.descriptionTitle from PDF of title page (University of Missouri--Columbia, viewed on May 17, 2012).eng
dc.descriptionDissertation advisor: Dr. Tushar K. Ghosheng
dc.descriptionVita.eng
dc.descriptionIncludes bibliographical references.eng
dc.descriptionDissertations, Academic -- University of Missouri--Columbia -- Nuclear engineering.eng
dc.description.abstractAn experimental system was constructed in accordance with the standard ASTM C835-06 to measure the total hemispherical emissivity of structural materials of interest in Very High Temperature Reactor (VHTR) systems. The system was tested with 304 stainless steel as well as oxidized and un-oxidized nickel, and good reproducibility and agreement with the literature data was found. Emissivity of each candidate material was measured over a wide range of temperatures, with conditions that included: i) 'as received' (original sample) from the supplier; ii) increased surface roughness; iii) oxidized, and; iv) graphite coated. The emissivity of as-received materials increased with temperature for Hastelloy X (from 0.18 at 473 K to 0.28 at 1498 K), Haynes 230 (from 0.178 at 600 K to 0.235 at 1375 K), and Alloy 617 (about 0.2 at 600 K to about 0.35 at 1275 K). Oxidation was found to increase emissivity, but as there is some oxidation of these materials used in the construction of VHTRs, this represents an essentially neutral finding in terms of the safety implications in post-accident VHTR environments. However, a coating of graphite powder was shown to substantially increase emissivity, and this has strong favorable safety implications in terms of decay heat removal in post-accident VHTR environments.eng
dc.format.extentxi, 74 pageseng
dc.identifier.oclc872561299eng
dc.identifier.otherMarynardR-072611-D600eng
dc.identifier.urihttp://hdl.handle.net/10355/14216eng
dc.languageEnglisheng
dc.publisherUniversity of Missouri--Columbiaeng
dc.relation.ispartofcollectionUniversity of Missouri--Columbia. Graduate School. Theses and Dissertations.eng
dc.subjectnext generation nuclear reactoreng
dc.subjectvery high temperature reactorseng
dc.subjectenergy productioneng
dc.subjectemissivityeng
dc.titleTotal hemispherical emissivity of very high temperature reactor (VHTR) candidate materials: Hastelloy X, Haynes 230, and Alloy 617eng
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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