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Master's Dissertation
DOI
Document
Author
Full name
Marcelo Moraes dos Santos
E-mail
Institute/School/College
Knowledge Area
Date of Defense
Published
São Paulo, 2019
Supervisor
Committee
Mattar Neto, Miguel (President)
Berretta, José Roberto
Moreira, João Manoel Losada
Title in Portuguese
Avaliação estrutural de um elemento combustível do tipo placa para um reator nuclear compacto
Keywords in Portuguese
análise mecânica
elemento combustível
reatores PWR compactos
Abstract in Portuguese
A melhoria nos aspectos de eficiência e de segurança dos reatores nucleares compactos está diretamente ligada às inovações nos combustíveis e na geometria dos Elementos Combustíveis - ou E.C. - como é o caso do tipo Placa, em comparação com o do tipo Vareta. Do ponto de vista mecânico, garantir que a estrutura de um E.C. está segura para funcionar em um reator PWR compacto é afirmar que esta cumpre os requisitos funcionais de projeto para estruturas deste tipo e aplicação, presentes na norma ANSI/ANS-57.5-1996; e também que as tensões resultantes dos carregamentos impostos sobre si são menores do que os limites mecânicos admissíveis para os seus materiais estruturais, de acordo com a norma ASME III, divisão 1, subseção NB. Para desenvolver uma metodologia de análise mecânica buscando verificar o atendimento aos critérios das normas citadas, foi proposto um modelo conceitual computacional de E.C. placa e, posteriormente, este modelo foi submetido a uma série de análises computacionais que simularam a aplicação das combinações dos principais carregamentos atuantes. Os resultados extraídos das análises revelaram que os valores das tensões resultantes da aplicação dos carregamentos foram inferiores aos valores dos limites admissíveis dos materiais que compõem os seus componentes. Foi observado, também, que os deslocamentos resultantes não ultrapassaram os limites funcionais, que são o contato entre estruturas semelhantes vizinhas e/ou o contato da região superior desta estrutura com as estruturas de suporte do vaso de pressão que o contém.
Title in English
Structural evaluation of a plate-type fuel element for a compact nuclear reactor
Keywords in English
fuel element
mechanical analysis
PWR compact reactors
Abstract in English
The improvement in the efficiency and safety aspects of compact nuclear reactors is directly linked to innovations in fuels and the geometry of Fuel Elements - F.E. - as is the case of the Plate type, as compared to the Rod type. From a mechanical point of view, to ensure that the structure of an F.E. is safe to operate in a compact PWR reactor is necessary to state that it meets the functional design requirements for structures of this type and application, present in ANSI / ANS-57.5-1996; and also that the stresses resulting from the loads imposed on them are less than the permissible mechanical limits for their structural materials in accordance with ASME III, division 1, subsection NB. In order to develop a methodology of mechanical analysis to verify compliance with the criteria of the cited standards, a computational conceptual model of F.E. Plate structure was proposed and later this model was submitted to a series of computational analyzes that simulated the application of the combinations of the main active loads. The results obtained from the analyzes revealed that the values of the stresses resulting from the application of the loads were lower than the values of the allowable limits of the materials that make up their components. It was also observed that the resulting displacements did not exceed the functional limits, which are the contact between neighboring similar structures i.e. the contact of the upper region of this structure with the supporting structures of the pressure vessel containing it.
 
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Publishing Date
2019-09-10
 
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