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dc.contributor.advisorRobertson, John David, 1960-eng
dc.contributor.authorPeters, Nickie J. J.eng
dc.date.issued2009eng
dc.date.submitted2009 Summereng
dc.descriptionTitle from PDF of title page (University of Missouri--Columbia, viewed on September 17, 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 advisor: Dr. John David Robertson.eng
dc.descriptionVita.eng
dc.descriptionIncludes bibliographical references.eng
dc.descriptionPh. D. University of Missouri--Columbia 2009.eng
dc.descriptionDissertations, Academic -- University of Missouri--Columbia -- Chemistry.eng
dc.description.abstractA novel approach to parametric instrumental neutron activation analysis at MURR has been established. In particular, a detailed MCNP5 steady-state model of the MURR core was developed. The model, which was based on the most recent continuous-energy neutron data from the ENDF and JEFF neutron libraries, was used to compute the local continuous-energy neutron flux distribution. By coupling the computed flux spectrum to the energy-dependent ([nu], [upsilon]) cross-sections for a range of nuclides, their intrinsic reaction rates were predicted in irradiation channel ROW2. The model was initially benchmarked by measuring the intrinsic ([nu], [upsilon]) reaction rates for a set of mostly dilute single-element standards in ROW2. Predictions of the intrinsic reaction rates for many nuclides, including those with high epithermal sensitivity and non-1/v behavior, are within [plus-minus] 5% of the measured values. Using predicted ([nu], [upsilon]) reaction-rates, trace-elemental concentrations were determined in NIST standard reference materials, bovine liver, obsidian and coal fly ash. The agreements with the certified concentrations were generally within [plus-minus]5%. The new methodology has produced better results for a greater number of elements than [kappa]₀. The model was also combined with MONTEBURNS and ORIGEN to test the feasibility of Mo⁹⁹production at MURR from fissioning LEU. Results from a 5-gram low-enriched uranium target show predictions of Mo⁹⁹ end-of-irradiation yields are within 3% of the measured value. This dissertation entails a complete study of the MCNP5 model and the new neutron activation analysis method.eng
dc.format.extentxvi, 175 pageseng
dc.identifier.oclc696800717eng
dc.identifier.urihttp://hdl.handle.net/10355/9663
dc.languageEnglisheng
dc.publisherUniversity of Missouri--Columbiaeng
dc.relation.ispartof2009 Freely available dissertations (MU)eng
dc.relation.ispartofcommunityUniversity of Missouri-Columbia. Graduate School. Theses and Dissertations. Dissertations. 2009 Dissertationseng
dc.subject.lcshUniversity of Missouri. -- Research Reactor Facilityeng
dc.subject.lcshNuclear activation analysiseng
dc.subject.lcshNeutron fluxeng
dc.subject.lcshMolybdenumeng
dc.subject.lcshMonte Carlo methodeng
dc.titleMonte Carlo neutronic simulations for a new approach to parametric INAA and Mo-99 production feasibility at MURReng
dc.typeThesiseng
thesis.degree.disciplineChemistry (MU)eng
thesis.degree.grantorUniversity of Missouri--Columbiaeng
thesis.degree.levelDoctoraleng
thesis.degree.namePh. D.eng


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