MARIA EUGENIA LAGO JACQUES SAUER
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Artigo IPEN-doc 27929 Knowledge base about risk and safety of nuclear facilities to support analysts and decision-makers2021 - VIEIRA NETO, ANTONIO S.; OLIVA, AMAURY M.; OLIVEIRA, PATRICIA da S.P. de; HUNOLD, MARCOS C.; SAUER, MARIA E.L.J.; ANDREA, VINICIUSEpistemic uncertainty (related to lack of knowledge), often found in the documentation of nuclear facility engineering projects, can affect the decision-making process of managers and analysts on safety and risk issues. This article conceptualizes the nature of the major uncertainties involved in engineering projects. It describes a knowledge base developed to gather data and information related to an Open-Pool Light-water Research Reactor (OPLRR) project and whose purpose is to assist professionals who work in nuclear facilities. To reduce the epistemic uncertainties that may arise in the project, the OPLRR knowledge base is designed with a set of information that allows identifying and facilitating the forwarding of solutions to address inconsistencies and/or pending issues that may exist in the project. In this sense, the information and the documents related to the project are organized in a graphical and hierarchical architecture, allowing the knowledge base users to quickly and easily obtain information regarding the systems, processes, equipment, and components of the project. Besides that, a set of documents containing descriptions, reliability data, and some other information about the systems and components are specially created to the knowledge base, and it is crucial to reduce epistemic uncertainties once it raises the issues and the inconsistencies of the project, as well as it clarifies the interrelations between the systems, the functioning of the equipment, their failures modes and the consequences of their failures, and some other data, which are not originally contained in the documents of the project.Artigo IPEN-doc 26383 Knowledge base about risk and safety of nuclear facilities to support analysts and decision makers2019 - VIEIRA NETO, ANTONIO S.; OLIVA, AMAURY M.; SAUER, MARIA E.L.J.; HUNOLD, MARCOS C.; OLIVEIRA, PATRICIA da S.P.de; ANDREA, VINICIUSEpistemic uncertainty (uncertainty related to lack of knowledge), often found in the documentation of nuclear facility engineering projects, can affect the decision-making process of managers and analysts on safety and risk issues. This article conceptualizes the nature of the major uncertainties involved in engineering projects and describes a knowledge base developed in order to gather data and information related to the project of an Open-Pool Light-water Research Rector (OPLRR) and whose purpose is to assist professionals who work in the áreas of safety, design, operation, and maintenance of nuclear facilities. In order to reduce the epistemic uncertainties that may rise in the project, the OPLRR knowledge base is designed to contain a set of information that allows identifying and facilitating the forwarding of solutions to address inconsistencies, and/or pending issues that may exist in the project. In this sense, the information and the documents related to the project are organized in a graphical and hierarchical architecture, allowing the knowledge base users to quickly and easily obtain information regarding the systems, processes, equipment, and components of the Project. Besides that, a set of documents containing descriptions, reliability data and some other important information about the systems and components are specially created to the knowledge base and it is crucial to reduce epistemic uncertainties, once it raises the issues and the inconsistencies of the project, as well as it clarifies the interrelations between the systems, the functioning of the equipment, their failures modes and the consequences of their failures, and some other data, which are not originally contained in the documents of the project.Relatório IPEN-doc 23430 Análise de consequências de acidentes com substâncias inflamáveis e/ou explosivas no sítio do IPEN, para o prédio do reator IPEN/MB-012017 - SAUER, MARIA EUGENIA L.J.Este trabalho apresenta a análise de acidentes com substâncias inflamáveis e/ou explosivas no sítio do Ipen, com o objetivo de avaliar o potencial de danos destas ocorrências na integridade física e na operação do Reator Ipen/MB-01. Os resultados deste estudo serão utilizados para atualizar o Relatório de Análise de Segurança (RAS) da instalação, que deverá ser submetido à CNEN, como parte das exigências a serem cumpridas para obtenção da renovação da licença de operação, em razão da modificação do núcleo do reator. A partir das informações obtidas junto às áreas técnicas do instituto e do levantamento de dados em campo, foram identificadas amônia, GLP e óleo diesel como as substâncias perigosas presentes em maiores quantidades no Ipen. Dentre as hipóteses de acidentes postuladas numa Análise Preliminar de Perigos (APP), em função da periculosidade destas substâncias, foram selecionadas aquelas com potencial de gerar danos ao prédio do Reator Ipen/MB-01. Os dados necessários para a avaliação da vulnerabilidade do reator aos efeitos físicos gerados pelos acidentes postulados considerados relevantes foram obtidos das simulações dos cenários acidentais efetuadas com o aplicativo computacional PHAST Professional®- versão 7.1. Também são apresentadas considerações acerca da possibilidade da ocorrência de acidentes no transporte de produtos perigosos no sítio do Ipen, como fonte de risco para o Reator Ipen/MB-01.Relatório IPEN-doc 21420 Revisão do capítulo 9 do relatório de análise de segurança do CCN-IPEN2014 - TEIXEIRA e SILVA, ANTONIO; BELCHIOR JUNIOR, ANTONIO; RIBEIRO, MARIA A.M.; SAUER, MARIA E.L.J.Artigo IPEN-doc 10575 Base de dados de confiabilidade de componentes para os reatores de pesquisa IEA-R1 e IPEN/MB-01: resultados e aplicacoes2005 - OLIVEIRA, P.S.P.; SAUER, M.E.L.J.; KURAZUMI, E.P.; VIEIRA NETO, A.S.; TONDIN, J.B.M.; RICCI FILHO, W.; MARTINS, M.O.; BITELLI, U.D.; JEREZ, R.Artigo IPEN-doc 10669 Utilizacao do checklist de seguranca na analise do sistema de retratamento de agua do reator IEA-R12005 - SAUER, M.E.L.J.; SARA NETO, A.J.; LIMA, T.C.C.; RIBEIRO, M.A.M.Artigo IPEN-doc 08671 Base de dados de confiabilidade de componentes para os reatores de pesquisa IEA-R1 e IPEN/MB-01: objetivos, estrutura e conteudo2002 - OLIVEIRA, P.S.P.; TONDIN, J.B.M.; RICCI FILHO, W.; MARTINS, M.O.; KURAZUMI, E.P.; VIEIRA NETO, A.S.; SAUER, M.E.L.J.; JEREZ, R.; BITELLI, U.D.Artigo IPEN-doc 11206 Analysis of the IEA-R1 reactor startup procedures: an application of the HazOp method2005 - SAUER, M.E.L.J.; OLIVEIRA NETO, J.M.Artigo IPEN-doc 07116 The experience of IPEN-CNEN/SP in the Probabilistic Safety Assessment Regulatory Review for ANGRA I Brazilian Nuclear Power Plant2001 - OLIVEIRA, P.S.P.; VIEIRA NETO, A.S.; SAUER, M.E.L.J.Artigo IPEN-doc 02136 Analise de confiabilidade do circuito termico experimental-1501993 - SAUER, M.E.L.J.