PATRICIA DA SILVA PAGETTI DE OLIVEIRA
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Artigo IPEN-doc 29552 External Events PSA2022 - SILVA, T.P.; MATURANA, M.C.; OLIVEIRA, P.S.P. de; MATTAR NETO, M.Since the Fukushima Daiichi accident, external events analysis has become a priority issue within regulatory bodies, operators, and designers, raising concerns about the capabilities of nuclear power plants to withstand severe conditions. Generally, the methodology applied to the Probabilistic Safety Assessment (PSA) of external events consists of the identification of potential single and combined external hazards, screening of external hazards, analysis of site and plant response, analysis of initiating events and quantification of accident sequences probabilities. Therefore, in this paper, the requirements and other information on new nuclear installations projects necessary to implement a comprehensive PSA of external events throughout plant lifetime are evaluated. In addition, it is necessary to clearly identify all the resources that must be available to continuously expand PSA scope to include all types of initiating events, levels of analysis and plant operation modes.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 27931 Overview of seismic probabilistic safety assessment applied to a nuclear installation located in a low seismicity zone2021 - OLIVEIRA, ELLISON A. de; OLIVEIRA, PATRICIA da S.P. de; MATTAR NETO, MIGUEL; MATURANA, MARCOS C.Deterministic and probabilistic safety analysis methodologies have been developed and updated based on operational experience, investigation of past incidents or accidents, and analysis of postulated initiating events in nuclear plants in order to maintain the protection of workers, the public and the environment. The evaluation of accident sequences and the total radiological risk resulting from off-site releases are general objectives addressed by these methodologies. There are 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 accident. Different levels of ground motion induced by earthquakes may be experienced by structures, systems and components (SSCs) of an installation. In this context, a seismic hazard analysis, seismic demand analysis and seismic fragility analysis must be carried out in order to characterize the local seismic hazard and seismic demands on SSCs, allowing an adequate seismic classification of SSCs, even for installations located in sites with low seismicity. In this article, a general description of the Seismic Probabilistic Safety Assessment (Seismic PSA) methodology is presented, emphasizing the supporting studies. This methodology shall be applied to an experimental nuclear installation containing a PWR reactor designed for naval propulsion to be installed in a low seismicity zone in Brazil.