Uncertainty Quantification and Propagation Methodology for Steady State Safety Analysis of Lead-cooled Fast Reactors.

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dc.contributor.advisorJia Hou, Co-Chair
dc.contributor.advisorKostadin Ivanov, Co-Chair
dc.contributor.advisorMaria Avramova, Member
dc.contributor.authorTrivedi, Ishita
dc.date.accepted2020-04-13
dc.date.accessioned2020-04-14T12:31:00Z
dc.date.available2020-04-14T12:31:00Z
dc.date.defense2019-11-11
dc.date.issued2019-11-11
dc.date.released2020-04-14
dc.date.reviewed2020-03-31
dc.date.submitted2020-03-30
dc.degree.disciplineNuclear Engineering
dc.degree.levelthesis
dc.degree.nameMaster of Science
dc.identifier.otherdeg20796
dc.identifier.urihttps://www.lib.ncsu.edu/resolver/1840.20/37392
dc.titleUncertainty Quantification and Propagation Methodology for Steady State Safety Analysis of Lead-cooled Fast Reactors.

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