Navegação por Revista "World Journal of Nuclear Science and Technology"

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  • IPEN-DOC 20234

    CARNEIRO, ALVARO L.G. ; PORTO JUNIOR, ALMIR C.S.. An integrated approach for process control valves diagnosis using fuzzy logic. World Journal of Nuclear Science and Technology, v. 4, p. 148-157, 2014.

    Palavras-Chave: artificial intelligence; expert systems; failures; fuzzy logic; process control; pwr type reactors; reactor maintenance; valves


  • IPEN-DOC 26863

    BELLONI, MARCIO ; CONTI, THADEU das N. . Analysis of materials for heat transport in tokamaks. World Journal of Nuclear Science and Technology, v. 10, n. 1, p. 39-46, 2020. DOI: 10.4236/wjnst.2020.101005

    Abstract: Every nuclear power reactor, whether of fusion or fission, is essentially a thermal system that generates electricity. In this sense, there are several problems in relation to this heat transport. The model of plasma confinement by magnetic force, in the nuclear fusion (sterellator and tokamak), has only been 20 years and recently some success in the quality of the generated plasma has been achieved. However, due to the large amount of energy coming from the plasma, the choice of the material that will carry the generated energy is quite troublesome, due to the need to handle a very high temperature for the nuclear fission standards. Solutions are explored by the scientific community to transport the energy generated in the case of the primary circuit, after exceeding breakeven temperature and models that are based on the fission reactors of the fourth generation and those currently in operation, to search for solutions regarding the transport of heat generated for the generation of electric energy. Several materials such as pressurized water, sodium, helium and boron have been considered and studied to form the primary heat transfer circuit for the exchanger. A thorough analysis of these materials is necessary. This research looked at some of these materials for heat transport and power generation. Lithium and helium were found to be the probable materials for conveying heat and cooling in the blanket. The results show that research on blanket materials needs more attention. The quality of these materials needs to be improved by material research, with the ODS EUROFER alloy and other research to reduce material erosion by helium nano bubbles. Plasma quality needs to be improved to keep constant and free of impurities when using lithium in liquid form.

    Palavras-Chave: nuclear power; reactors; thermonuclear reactions; tokamak devices; renewable energy sources; iter tokamak; heating; heat transfer


  • IPEN-DOC 23193

    SALIBA-SILVA, ADONIS M. ; SANTOS, OLAIR dos ; CARVALHO, ELITA F.U. de ; RIELLA, HUMBERTO G. ; DURAZZO, MICHELANGELO . Determination of uranium traces in nuclear reactor IEA-R1 pool water. World Journal of Nuclear Science and Technology, v. 7, n. 3, p. 155-166, 2017. DOI: 10.4236/wjnst.2017.73014

    Abstract: IEA-R1 nuclear reactor operation has the routine to control uranium content in pool water to be in trace range below 50 μg/L. There are several routes to determine the uranium trace content in water in the literature; voltammetry has been systematically employed. In the present study, the chosen chemical determination of uranium traces used the voltammetric method known as AdCSV (adsorptive cathodic stripping voltammetry). This technique, based on mercury voltammetry, is an adequate methodology to determine uranium traces. The chloranilic acid [CAA] (2,5-dichloro-3,6-dihydroxy-1,4-benzoquinone) is indicated as chelating agent. The redox reaction of 22 UO + with CAA is sensitive in the range of 2 < pH < 3. But pH variation imposes changing on [UO2(CAA)2] reduction potential. In this work, we present the uranium trace results for IEA-R1 reactor water, sampled after an operation routine shutdown. The uranium trace determination for IEA-R1 pool water showed content around 1 μg/L [U] with statistical significance. Therefore the IEA-R1-reactor-water purification showed to be adequate and safe.


  • IPEN-DOC 25802

    PACHECO, R.R.; FREIRE, L.O. ; ROCHA, M.S. ; SCURO, N.L. ; MENEZES, M.O. ; ANDRADE, D.A. . New formulation for semi-empirical correlations for penetration jets. World Journal of Nuclear Science and Technology, v. 9, n. 2, p. 96-111, 2019. DOI: 10.4236/wjnst.2019.92007

    Abstract: Correlations for the extension of a water vapor jet injected in a liquid pool were historically proposed considering the mass flux (kg/m2/s) as a constant. The results were satisfactory, however adjusting the values by linear regression. Although, it presents the following drawbacks: 1) the formulation is only valid for the specific range of data for what it was created; 2) it does not allow the analytical evaluation of the heat transfer coefficient from the extension equation. This paper proposes a new formulation for the calculation of the mass flux, in such a way to remove both of these drawbacks.

    Palavras-Chave: water vapor; vapor jet ejectors; steam jet ejectors; reynolds number; heat transfer; vapor condensation; boiling


  • IPEN-DOC 24789

    SAVOINE, MARCIA M. ; MENEZES, MARIO O. de ; ANDRADE, DELVONEI A. de . Proposal of a methodology for the assessment of security levels of IoT wireless sensor networks in nuclear environments. World Journal of Nuclear Science and Technology, v. 8, n. 2, p. 78-85, 2018. DOI: 10.4236/wjnst.2018.82008

    Abstract: The use of Wireless Sensor Networks (WSN) associated with the reality of an Internet of Things (IoT) scenario in nuclear environments is a growing security concern. In this context, standards are intensified to preserve the physical integrity of these facilities considered to be highly critical due to the size of the impacts of safety accidents. This paper presents a proposal to build a methodology to evaluate the security levels of WSNs with IoT devices when used in nuclear areas. The proposal is initially based on related work to establish a more concrete initial framework and is structured in consistent steps from previous scientific studies.

    Palavras-Chave: internet; computer networks; security; sensors; nuclear facilities; programming; recommendations; local area networks; information systems; documentation


  • IPEN-DOC 20181

    OLIVEIRA, FABIO B.V. de; ANDRADE, DELVONEI A. de . Relation between gamma decomposition and powder formation of 'gamma'-U8Mo nuclear fuel alloys via hydrogen embrittlement and thermal shock. World Journal of Nuclear Science and Technology, v. 4, p. 177-188, 2014.

    Palavras-Chave: nuclear fuels; uranium alloys; molybdenum alloys; mtr reactor; heating; cooling; hydrogen embrittlement; thermal shock


  • IPEN-DOC 22826

    CUNHA, RAQUEL D.S. da ; ANDRADE, DELVONEI A. de . Risk communication and external emergency plan in Angra dos Reis, Brazil. World Journal of Nuclear Science and Technology, v. 6, p. 301-308, 2016. DOI: 10.4236/wjnst.2016.64027

    Abstract: The presence of a potentially hazardous facility in a community demands several safety procedures. Bringing risk communication among those actions may help the population that lives near the facility feel more confident and have the required knowledge on how to behave in an emergency situation. A research performed in Angra dos Reis, RJ, Brazil, where a nuclear power plant is located, shows that there is a lack of information and awareness about the emergency plan.

    Palavras-Chave: hazards; communications; emergency plans; nuclear power plants; brazilian organizations; angra-1 reactor; angra-2 reactor


  • IPEN-DOC 24764

    NEGRO, MIGUEL L.M. ; DURAZZO, MICHELANGELO ; MESQUITA, MARCO A. de; CARVALHO, ELITA F.U. de ; MESQUITA, ROBERTO N. de ; ANDRADE, DELVONEI A. de . Studies on capacity expansion of fuel plants for nuclear research reactors. World Journal of Nuclear Science and Technology, v. 8, n. 2, p. 38-53, 2018. DOI: 10.4236/wjnst.2018.82005

    Abstract: The demand for nuclear fuel for research reactors is rising worldwide. Thus, the production facilities of this kind of fuel need reliable guidance on how to augment their production in order to meet the increasing demand efficiently and safely. We proposed a specific procedure for increasing production ca-pacity. That procedure was tested with data from a real plant, which produces plate-type fuel elements loaded with LEU U3Si2-Al fuel. The test was made by means of discrete event simulation, and the results indicated the proposed procedure is efficient in raising production capacity.

    Palavras-Chave: nuclear fuels; uranium silicides; fuel elements; fuel plates; research reactors; reactors; capacity; expansion; production; nuclear engineering; reactor simulators


  • IPEN-DOC 22836

    NEGRO, MIGUEL L.M. ; DURAZZO, MICHELANGELO ; MESQUITA, MARCO A. de; CARVALHO, ELITA F.U. de ; ANDRADE, DELVONEI A. de . Studies on production planning of dispersion type U3Si2-Al fuel in plate-type fuel elements for nuclear research reactors. World Journal of Nuclear Science and Technology, v. 6, p. 217-231, 2016. DOI: 10.4236/wjnst.2016.64023

    Abstract: Several fuel plants that supply nuclear research reactors need to increase their production capacity in order to meet the growing demand for this kind of nuclear fuel. After the enlargement of the production capacity of such plants, there will be the need of managing the new production level. That level is usually the industrial one, which poses challenges to the managerial staff. Such challenges come from the fact that several of those plants operate today on a laboratorial basis and do not carry inventory. The change to the industrial production pace asks for new actions regarding planning and control. The production process based on the hydrolysis of UF6 is not a frequent production route for nuclear fuel. Production planning and control of the industrial level of fuel production on that production route is a new field of studies. The approach of the paper consists in the creation of a mathematical linear model for minimization of costs. We also carried out a sensitivity analysis of the model. The results help in minimizing costs in different production schemes and show the need of inventory. The mathematical model is dynamic, so that it issues better results if performed monthly. The management team will therefore have a clearer view of the costs and of the new, necessary production and inventory levels.

    Palavras-Chave: fabrication; uranium silicides; fuels; reactors; production; planning; control; mathematical models


  • IPEN-DOC 24772

    PACHECO, RAFAEL R. ; ANDRADE, DELVONEI A. de . Technological perspectives for propulsion on nuclear attack submarines. World Journal of Nuclear Science and Technology, v. 8, n. 1, p. 1-10, 2018. DOI: 10.4236/wjnst.2018.81001

    Abstract: This work aims to present the historical context in which the current understanding of the phenomenon of the direct contact condensation started to call the scientific society attention. The development of nuclear power plants Light Water Reactors demanded a safe way to collect and treat the water used to cool the reactor. Some characteristics of this water in a high energetic thermodynamic state made it unsuitable to be directly discharged in the atmosphere. Small room relieves tanks were developed to contain this discharge. These tanks were partially fulfilled with water, and the vapor injection created a vapor plume. In the interface of liquid and vapor, the thermal exchange would be increased by the characteristic turbulence of this region.

    Palavras-Chave: propulsion systems; submarines; nuclear ships; ship propulsion reactors; emergency plans; cooling systems; vapor condensation; heat transfer; water; nuclear energy; nuclear weapons; technology utilization


  • IPEN-DOC 22828

    FREIRE, LUCIANO O. ; ANDRADE, DELVONEI A. de . Technological perspectives for propulsion on nuclear attack submarines. World Journal of Nuclear Science and Technology, v. 6, p. 1-6, 2016. DOI: 10.4236/wjnst.2016.64028

    Abstract: This work aimed at proposing a new combination of technologies to improve military performances and reduce costs of nuclear attack submarines, without overlooking safety constraints. The last generation of nuclear attack submarines increased size to meet safety and operational requirements, imposing huge burden on costs side, reducing fleet size. The limitations of current Technologies employed were qualitatively discussed, explaining their limitations. There are new technologies (plate and shell heat exchangers) and architectural choices, like passive safety, and segregation of safety and normal systems, which may lead to reduction of costs and size of submarines. A qualitative analysis was provided on this combination of technologies, stressing their commercial nature and maturity, which reduced risks. The qualitative analysis showed the strong and weak points of this proposal, which adopted the concept of strength in numbers. Concluding, new Technologies enabled the existence of 3800 t nuclear attack submarines with powerful propulsion systems and good acoustic discretion.

    Palavras-Chave: propulsion; nuclear weapons; submarines; heat exchangers; pwr type reactors; comparative evaluations


  • IPEN-DOC 23045

    FREIRE, LUCIANO O. ; ANDRADE, DELVONEI A. de . The role of nuclear power from a system engineering standpoint. World Journal of Nuclear Science and Technology, v. 7, n. 3, p. 167-188, 2017. DOI: 10.4236/wjnst.2017.73015

    Abstract: This work proposed the application of system engineering methods to identify organizations vital for society, seeking development and well-being. System engineering requires the identification of blocks (or systems), identification of their service functions, identification of states, identification of required quality and identification of constraints. Analyzing modern societies, vital functions were identified and countries behavior was modeled, identifying their states. In this context, nuclear power was found to be fundamental for development and defense because of its inherent advantages for military naval purposes at war. Another striking conclusion is that nuclear power is the best solution for country energy security, more than to avoid climate changes, but to help the nation to resist climate changes. A solution to mitigate the high overnight costs of nuclear power was also proposed. It was demonstrated qualitatively that the adoption of dual purpose mobile nuclear power plants military performances, economic development and risks management.


  • IPEN-DOC 24804

    UMBEHAUN, PEDRO E. ; TORRES, WALMIR M. ; SOUZA, JOSE A.B. ; YAMAGUCHI, MITSUO ; SILVA, ANTONIO T. e ; MESQUITA, ROBERTO N. de ; SCURO, NIKOLAS L. ; ANDRADE, DELVONEI A. de . Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification. World Journal of Nuclear Science and Technology, v. 8, n. 2, p. 54-69, 2018. DOI: 10.4236/wjnst.2018.82006

    Abstract: This paper presents the sequence of activities to improve the thermal hydraulic analysis of the IEA-R1 research reactor to operate in safe conditions after power upgrade from 2 to 5 MW and core size reduction from 30 to 24 fuel assemblies. A realistic analysis needs the knowledge of the actual operation conditions (heat flow, flow rates) beyond the geometric data and the uncertainties associated with manufacturing and measures. A dummy fuel assembly was designed and constructed to measure the actual flow rate through the core fuel assemblies and its pressure drop. First results showed that the flow distribution over the core is nearly uniform. Nevertheless, the values are below than the calculated ones and the core bypass flow rate is greater than those estimated previously. Based on this, several activities were performed to identify and reduce the bypass flow, such as reduction of the flow rate through the sample irradiators, closing some unnecessary secondary holes on the matrix plate, improvement in the primary flow rate system and better fit of the core components on the matrix plate. A sub-aquatic visual system was used as an important tool to detect some bypass flow path. After these modifications, the fuel assemblies flow rate increased about 13%. Additional tests using the dummy fuel assembly were carried out to measure the internal flow distribution among the rectangular channels. The results showed that the flow rate through the outer channels is 10% - 15% lower than the internal ones. The flow rate in the channel formed between two adjacent fuel assemblies is an estimated parameter and it is difficult to measure because this is an open channel. A new thermal hydraulic analysis of the outermost plates of the fuel assemblies takes into account all this information. Then, a fuel design modification was proposed with the reduction of 50% in the uranium quantity in the outermost fuel plates. In order to avoid the oxidation of the outermost plates by high temperature, low flow rate, a reduction of 50% in the uranium density in the same ones was shown to be adequate to solve the problem.

    Palavras-Chave: thermal hydraulics; reactors; research reactors; uranium; fuel assemblies; iear-1 reactor; flow rate; loss of coolant; materials testing reactors; eccs


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É possível efetuar a busca de um autor ou um termo em todo o RD, por meio do Buscar no Repositório , isto é, o termo solicitado será localizado em qualquer campo do RD. No entanto esse tipo de pesquisa não é recomendada a não ser que se deseje um resultado amplo e generalizado.

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Os filtros disponíveis em Navegar tais como: Coleções, Ano de publicação, Títulos, Assuntos, Autores, Revista, Tipo de publicação são autoexplicativos. O filtro, Autores IPEN apresenta uma relação com os autores vinculados ao IPEN; o ID Autor IPEN diz respeito ao número único de identificação de cada autor constante no RD e sob o qual estão agrupados todos os seus trabalhos independente das variáveis do seu nome; Tipo de acesso diz respeito à acessibilidade do documento, isto é , sujeito as leis de direitos autorais, ID RT apresenta a relação dos relatórios técnicos, restritos para consulta das comunidades indicadas.

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Buscar os artigos apresentados em um evento internacional de 2015, sobre loss of coolant, do autor Maprelian.

Autor: Maprelian

Título: loss of coolant

Tipo de publicação: Texto completo de evento

Ano de publicação: 2015

Para indexação dos documentos é utilizado o Thesaurus do INIS, especializado na área nuclear e utilizado em todos os países membros da International Atomic Energy Agency – IAEA , por esse motivo, utilize os termos de busca de assunto em inglês; isto não exclui a busca livre por palavras, apenas o resultado pode não ser tão relevante ou pertinente.

95% do RD apresenta o texto completo do documento com livre acesso, para aqueles que apresentam o significa que e o documento está sujeito as leis de direitos autorais, solicita-se nesses casos contatar a Biblioteca do IPEN, .

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O RD disponibiliza um quadro estatístico de produtividade, onde é possível visualizar o número dos trabalhos agrupados por tipo de coleção, a medida que estão sendo depositados no RD.

Na página inicial nas referências são sinalizados todos os autores IPEN, ao clicar nesse símbolo será aberta uma nova página correspondente à aquele autor – trata-se da página do pesquisador.

Na página do pesquisador, é possível verificar, as variações do nome, a relação de todos os trabalhos com texto completo bem como um quadro resumo numérico; há links para o Currículo Lattes e o Google Acadêmico ( quando esse for informado).



O gerenciamento do Repositório está a cargo da Biblioteca do IPEN. Constam neste RI, até o presente momento 20.950 itens que tanto podem ser artigos de periódicos ou de eventos nacionais e internacionais, dissertações e teses, livros, capítulo de livros e relatórios técnicos. Para participar do RI-IPEN é necessário que pelo menos um dos autores tenha vínculo acadêmico ou funcional com o Instituto. Nesta primeira etapa de funcionamento do RI, a coleta das publicações é realizada periodicamente pela equipe da Biblioteca do IPEN, extraindo os dados das bases internacionais tais como a Web of Science, Scopus, INIS, SciElo além de verificar o Currículo Lattes. O RI-IPEN apresenta também um aspecto inovador no seu funcionamento. Por meio de metadados específicos ele está vinculado ao sistema de gerenciamento das atividades do Plano Diretor anual do IPEN (SIGEPI). Com o objetivo de fornecer dados numéricos para a elaboração dos indicadores da Produção Cientifica Institucional, disponibiliza uma tabela estatística registrando em tempo real a inserção de novos itens. Foi criado um metadado que contém um número único para cada integrante da comunidade científica do IPEN. Esse metadado se transformou em um filtro que ao ser acionado apresenta todos os trabalhos de um determinado autor independente das variáveis na forma de citação do seu nome.

A elaboração do projeto do RI do IPEN foi iniciado em novembro de 2013, colocado em operação interna em julho de 2014 e disponibilizado na Internet em junho de 2015. Utiliza o software livre Dspace, desenvolvido pelo Massachusetts Institute of Technology (MIT). Para descrição dos metadados adota o padrão Dublin Core. É compatível com o Protocolo de Arquivos Abertos (OAI) permitindo interoperabilidade com repositórios de âmbito nacional e internacional.

1. Portaria IPEN-CNEN/SP nº 387, que estabeleceu os princípios que nortearam a criação do RDI, clique aqui.

2. A experiência do Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP) na criação de um Repositório Digital Institucional – RDI, clique aqui.