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Use este identificador para citar ou linkar para este item: https://www.repositorio.mar.mil.br/handle/ripcmb/848004
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Campo DCValorIdioma
dc.contributor.advisorA. Yakimenko, Oleg-
dc.contributor.advisorSu, Jian-
dc.contributor.authorMatias Avelar, Alan-
dc.date.accessioned2025-09-18T17:31:03Z-
dc.date.available2025-09-18T17:31:03Z-
dc.date.issued2025-
dc.identifier.urihttps://www.repositorio.mar.mil.br/handle/ripcmb/848004-
dc.descriptionThe lack of integration between computer-aided engineering (CAE) and model-based systems engineering (MBSE) tools hinders the assessment of how design changes affect system requirements. To address this challenge, this thesis proposes a model breakdown structure methodology implemented using MathWorks’ System Composer to integrate MBSE and CAE models. The Brazilian Multipurpose Reactor is used as a case study to demonstrate the effectiveness of the proposed methodology. An enhanced, automated verification process is achieved by linking system requirements to a finite element analysis that calculates fuel and cladding temperature distributions in a slow loss of flow accident scenario. First, a Latin hypercube design is employed to evaluate how variations in design factors influence cladding temperature. Second, the Wilks’ theorem is applied to calculate the maximum response with a 95% confidence level and 95% probability. The results indicate that the 95/95 upper limit of the peak cladding temperature remains below the onset of nucleate boiling. Furthermore, the integrated model is expected to significantly reduce the effort required for uncertainty quantification.pt_BR
dc.language.isoenpt_BR
dc.publisherNaval Postgraduate Schoolpt_BR
dc.rightsopenAccesspt_BR
dc.subjectModel-based systems engineeringpt_BR
dc.subjectVerification and validationpt_BR
dc.subjectBest estimate plus uncertaintypt_BR
dc.titleIntegration of Models to Enhance the Verification Process of Nuclear Systemspt_BR
dc.typemasterThesispt_BR
dc.subject.dgpmEngenharia nuclearpt_BR
dc.subject.setorMarinhaDiretoria-Geral do Desenvolvimento Nuclear e Tecnologia da Marinha (DGDNTM)pt_BR
Aparece nas coleções:Ciência, Tecnologia e Inovação: Coleção de Dissertações

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