ANTONIO SOUZA VIEIRA NETO
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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.Artigo IPEN-doc 24182 Soft systems methodology as a systemic approach to nuclear safety management2017 - VIEIRA NETO, ANTONIO S.; GUILHEN, SABINE N.; RUBIN, GERSON A.; CALDEIRA FILHO, JOSE S.; CAMARGO, IARA M.C.Safety approach currently adopted by nuclear installations is built almost exclusively upon analytical methodologies based, mainly, on the belief that the properties of a system, such as its safety, are given by its constituent parts. This approach, however, doesn’t properly address the complex dynamic interactions between technical, human and organizational factors occurring within and outside the organization. After the accident at Fukushima Daiichi nuclear power plant in March 2011, experts of the International Atomic Energy Agency (IAEA) recommended a systemic approach as a complementary perspective to nuclear safety. The aim of this paper is to present an overview of the systems thinking approach and its potential use for structuring sociotechnical problems involved in the safety of nuclear installations, highlighting the methodologies related to the soft systems thinking, in particular the Soft Systems Methodology (SSM). The implementation of a systemic approach may thus result in a more holistic picture of the system by the complex dynamic interactions between technical, human and organizational factors.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 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 11993 Experience of IPEN-CNEN/SP in the executation of the first phase of the safety culture enhancement programme at IEA-R1 research reactor2007 - VIEIRA NETO, ANTONIO S.; MARRA NETO, ADOLFO; OLIVEIRA, PATRICIA da S.P. de; SAXENA, RAJENDRA N.; CARVALHO, RICARDO N. de; FRAJNDLICH, ROBERTO; PAIVA, ROSEMEIRE P.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 01730 MOCUSN - um programa para a determinacao de 'prime implicants'1988 - VIEIRA NETO, A.S.Artigo IPEN-doc 02132 Atualizacao da analise de confiabilidade do sistema de desligamento rapido do reator IPEN/MB-01 com dados da experiencia operacional1993 - OLIVEIRA, P.P.; VIEIRA NETO, A.S.Artigo IPEN-doc 02125 Uma metodologia para certificacao de seguranca de controladores digitais1993 - KOTANI, M.M.; VIEIRA NETO, A.S.; SOUZA, B.J.; BORGES, W.S.