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dc.contributor.advisorHetrick, David L.en_US
dc.contributor.authorPribyl, David James, 1963-
dc.creatorPribyl, David James, 1963-en_US
dc.date.accessioned2013-03-28T10:23:53Z
dc.date.available2013-03-28T10:23:53Z
dc.date.issued1989en_US
dc.identifier.urihttp://hdl.handle.net/10150/276965
dc.description.abstractAn accidental criticality may occur in a solution of fissile material. Since the processing of nuclear materials in solution is prevalent throughout the fuel cycle, it would be judicious to have the capability to predict a possible hazard. In view of this concern, a computer simulation was performed of the Los Alamos accident of December 30, 1958, in which the actuation of an electric stirrer produced a sudden criticality. A complete equation of state for a liquid containing gas bubbles was coupled with the equations of energy, momentum, and space-independent point kinetics. Multiplication calculations, implemented with the Monte Carlo Code for Neutron and Photon Transport (MCNP), were performed on thermally expanding solution geometries, to generate a reactivity feedback representation. With the knowledge of the total energy produced in the accident, the maximum reciprocal period on which the power rose was computed.
dc.language.isoen_USen_US
dc.publisherThe University of Arizona.en_US
dc.rightsCopyright © is held by the author. Digital access to this material is made possible by the University Libraries, University of Arizona. Further transmission, reproduction or presentation (such as public display or performance) of protected items is prohibited except with permission of the author.en_US
dc.subjectNuclear fuels -- Safety measures.en_US
dc.subjectNuclear reactor accidentsen_US
dc.subjectAccidents -- Prevention.en_US
dc.titleNuclear excursions in criticality accidents with fissile solutionsen_US
dc.typetexten_US
dc.typeThesis-Reproduction (electronic)en_US
dc.identifier.oclc22577587en_US
thesis.degree.grantorUniversity of Arizonaen_US
thesis.degree.levelmastersen_US
dc.identifier.proquest1336554en_US
thesis.degree.disciplineGraduate Collegeen_US
thesis.degree.disciplineNuclear and Energy Engineeringen_US
thesis.degree.nameM.S.en_US
dc.identifier.bibrecord.b17457270en_US
refterms.dateFOA2018-09-04T03:31:23Z
html.description.abstractAn accidental criticality may occur in a solution of fissile material. Since the processing of nuclear materials in solution is prevalent throughout the fuel cycle, it would be judicious to have the capability to predict a possible hazard. In view of this concern, a computer simulation was performed of the Los Alamos accident of December 30, 1958, in which the actuation of an electric stirrer produced a sudden criticality. A complete equation of state for a liquid containing gas bubbles was coupled with the equations of energy, momentum, and space-independent point kinetics. Multiplication calculations, implemented with the Monte Carlo Code for Neutron and Photon Transport (MCNP), were performed on thermally expanding solution geometries, to generate a reactivity feedback representation. With the knowledge of the total energy produced in the accident, the maximum reciprocal period on which the power rose was computed.


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