PATRICIA DA SILVA PAGETTI DE OLIVEIRA

PATRICIA DA SILVA PAGETTI DE OLIVEIRA

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External Events PSA
2021 - SILVA, T.P. da; MATURANA, M.C.; MATTAR NETO, M.; OLIVEIRA, P.S.P. de
Licensing approach for nuclear-powered submarines land support facilities
2021 - BARONI, D.B.; BORSOI, S.S.; MATTAR NETO, MIGUEL; OLIVEIRA, P.S.P. de; MATURANA, M.C.
Evaluation of “Safety Related” and “Important to Safety” terminology for safety classification of nuclear installation items in Brazil
2021 - BARONI, D.B.; BORSOI, S.S.; MATTAR NETO, M.; OLIVEIRA, P.S.P.; MATURANA, M.C.
Overview of seismic probabilistic safety assessment applied to a nuclear installation located in a low seismicity zone
2021 - 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.
RISKAUDIT and CNEN cooperation on probabilistic safety analysis
2019 - GEORGESCU, GABRIEL; NUNES, MARCOS E.C.; OLIVEIRA, PATRICIA da S.P. de; WIELENBERG, ANDREAS; NIEMELA, ILKKA; DUPUY, PATRICIA
The 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.
Overview of the seismic probabilistic safety assessment applied to a nuclear installation located in a low seismicity zone
2019 - 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.
Base de dados de confiabilidade de componentes para os reatores de pesquisa IEA-R1 e IPEN/MB-01: resultados e aplicacoes
2005 - 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.
The experience of IPEN-CNEN/SP in the Probabilistic Safety Assessment Regulatory Review for ANGRA I Brazilian Nuclear Power Plant
2001 - OLIVEIRA, P.S.P.; VIEIRA NETO, A.S.; SAUER, M.E.L.J.