PATRICIA DA SILVA PAGETTI DE OLIVEIRA
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Artigo IPEN-doc 29555 Risk-based design of electric power systems for non-conventional nuclear facilities at shutdown modes2022 - BORSOI, S.S.; BARONI, D.B.; MATTAR NETO, M.; OLIVEIRA, P.S.P.; MATURANA, M.C.The work presents a methodology for assessing the safety of electrical system designs for non-conventional nuclear facilities in shutdown. The methodology adopts the core damage frequency as the main risk measure to assess the different architectures of power systems in a non-conventional nuclear facility. Among the reasons is the absence of a specific regulatory basis for this type of installation. The adoption of standards for nuclear power plants by non-conventional nuclear facilities does not take into account the functional and operational particularities of these installations, imposing criteria that are often overestimated, which can even lead to an increase in the financial risk for carrying out the projects. Safety probabilistic analyzes become essential tools for the facilities design and licensing. The modeling and quantification of systems failures in charge of ensuring the nuclear safety of non-conventional nuclear facilities are carried out in the CAFTA software environment. In these studies, the analysis of electrical system configurations and their influence on the overall risk of the installation stand out.Artigo IPEN-doc 29116 Evaluation of “Safety Related” and “Important to Safety” terminology for safety classification of nuclear installation items in Brazil2022 - BARONI, D.B.; BORSOI, S.S.; MATTAR NETO, M.; OLIVEIRA, P.S.P.; MATURANA, M.C.In general terms, safety demonstration of nuclear installations is carried out through an assessment of compliance with design criteria and safety requirements established in national and international codes and standards applicable to each type of installation. In addition, a safety analysis consisting of installation behavior study during its useful lifetime, shall be developed considering normal operating conditions, transients, and postulated accidents, to determine safety margins and verify the adequacy of items designed to prevent accidents or mitigate their consequences. Also, design requirements applicable to each installation item depend on its classification with respect to safety. Thus, safety classification of structures, systems, and components (SSCs) must be performed based on adequate methods and clear and consistent criteria to ensure that an overall safety level expected for the installation is achieved. It is worth emphasizing the importance of the terminology adopted and the understanding of concepts definitions used in a safety classification process. The objective of this paper is to present a review of the application of “safety related item” and “item important to safety” terminology, evaluating definitions and interpretations given by the International Atomic Energy Agency (IAEA), the United States Nuclear Regulatory Commission (U.S.NRC) and the National Nuclear Energy Commission (CNEN) of Brazil. In this work, this subject is raised to demonstrate that divergent definitions and misinterpretations of concepts may result in inconsistencies in SSCs safety classification.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.Relatório IPEN-doc 27481