PATRICIA DA SILVA PAGETTI DE OLIVEIRA
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Artigo IPEN-doc 28303 Risk-based design of electric power systems for non-conventional nuclear facilities at shutdown modes2021 - BORSOI, S.S.; BARONI, D.B.; MATTAR NETO, M.; OLIVEIRA, P.S.P.; MATURANA, M.C.Artigo IPEN-doc 28302 External Events PSA2021 - SILVA, T.P. da; MATURANA, M.C.; MATTAR NETO, M.; OLIVEIRA, P.S.P. deArtigo IPEN-doc 28237 Licensing approach for nuclear-powered submarines land support facilities2021 - BARONI, D.B.; BORSOI, S.S.; MATTAR NETO, MIGUEL; OLIVEIRA, P.S.P. de; MATURANA, M.C.Artigo IPEN-doc 28222 Evaluation of “Safety Related” and “Important to Safety” terminology for safety classification of nuclear installation items in Brazil2021 - BARONI, D.B.; BORSOI, S.S.; MATTAR NETO, M.; OLIVEIRA, P.S.P.; MATURANA, M.C.Artigo IPEN-doc 26789 RISKAUDIT and CNEN cooperation on probabilistic safety analysis2019 - GEORGESCU, GABRIEL; NUNES, MARCOS E.C.; OLIVEIRA, PATRICIA da S.P. de; WIELENBERG, ANDREAS; NIEMELA, ILKKA; DUPUY, PATRICIAThe Brazilian project BR3.01/12 financed by European Union through the “Instrument for Nuclear Safety Cooperation” (INSC) programme and accomplished by RISKAUDIT organization (IRSN, GRS and STUK) constituted a support for enhancing and strengthening Brazilian Safety Authority (CNEN) expertise in regulatory and licensing activities, including probabilistic safety analysis (PSA), deterministic analysis and ageing management. The objectives of the project PSA task were to provide support to CNEN on the enhancement of its regulatory capability related to PSA development, review and applications and to provide support to CNEN on the review of the documents related to parts of Level 1 and 2 PSAs submitted by the utility, Eletronuclear (ETN), for the Brazilian NPPs of the CNAAA, which is a nuclear station located in Angra dos Reis, Rio de Janeiro. The activities focused on the updating and enhancement of Brazilian regulatory requirements for development and use of PSA, development of the Brazilian guide on regulatory review of PSA, support CNEN on the preliminary review of the PSAs for Angra 2 NPP, support CNEN on the management of Level 1 PSA computer codes and training CNEN staff on PSA methods, PSA review and PSA applications. The project, which started in May 2015, successfully ended in May 2018.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.Artigo IPEN-doc 26374 Overview of the seismic probabilistic safety assessment applied to a nuclear installation located in a low seismicity zone2019 - OLIVEIRA, ELLISON A.; OLIVEIRA, PATRICIA S.P.; MATTAR NETO, MIGUEL; MATURANA, MARCOS C.Permanent concern on the safety of nuclear installations shall be assured in order to maintain the protection of workers, individuals from the public and the environment. Safety analysis methodologies for both approaches, deterministic and probabilistic, have been developed and updated based on operational experience, investigation of past incidents or accidents, and analysis of postulated initiating events. In general terms, the main objectives of a nuclear safety study are the identification of a comprehensive list of accident initiating events, the evaluation of their impact on the installation and the assessment of the total radiological risk resulting from accidents with off-site releases. Among all initiating events and hazards, there are external hazards that continually challenge the safety of a nuclear facility or its nearby area. In particular, seismic events represent a major contributor to the risk of a nuclear facility. Large levels of ground motion induced by earthquakes may be experienced due to the propagation of mechanical waves on the ground, caused by the displacement of tectonic plates. In this context, a seismic hazard analysis can be carried out in order to predict local acceleration levels with the associated uncertainty distribution, allowing an adequate seismic classification of plant structures, systems and components, including installations located in sites with low seismicity. In order to estimate the risk of a nuclear installation concerning accidents induced by seismic events, a Seismic Probabilistic Safety Assessment (Seismic PSA) shall be performed. In this article, a general description of the Seismic PSA methodology is presented, with emphasis on the supporting studies for this assessment. Finally, this study is under the scope of a master degree project at IPEN – CNEN/SP which intends to apply the methodology described in this article to an experimental nuclear installation containing a PWR reactor designed for naval propulsion to be installed in a low seismicity zone in Brazil.Artigo IPEN-doc 05890 Artigo IPEN-doc 15592 Reliability database of IEA-R1 brazilian research reactor: applications to the improvement of installation safety2010 - OLIVEIRA, P.S.P.; TONDIN, J.B.M.; MARTINS, M.O.; YOVANOVICH, M.; RICCI FILHO, WALTERArtigo 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.