Reevaluation of environmental monitoring program for radiological emergency at Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro - Brazil

International Nuclear Information System (INIS)

Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar

1996-01-01

In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra dos Reis, Rio de Janeiro, the Emergency Response Team of the Institute for Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. The purpose of this program is to define a monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measures in case of a radiological accident, taking into account atmospheric diffusion, population conglomerates and their habits, water and land use, contemplating the entire Emergency Planning Zone of 15 km radius. This program has been reevaluated recently, aiming to optimize it and keep it up to date to assure adequacy of environmental surveillance data in support to a prompt response in case of an emergency situation in the nuclear power plant. It has been organized in the form of a handbook to facilitate handling by field teams. Future revisions will be necessary to incorporate additional pertinent information and keep the handbook up to date, since Angra dos Reis is a summer resort region, subject to constant changes. This paper discusses the structure of the environmental monitoring program and describes the content and preparation of this handbook. (author)

Maria Firmina dos Reis e seu conto Gupeva: uma breve digressão indianista

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Rafael Balseiro Zin

2017-07-01

Full Text Available Se o tratamento que a escritora maranhense Maria Firmina dos Reis atribui às personagens negras e à questão da escravidão em seu romance inaugural Úrsula, publicado em 1859, e em seu conto A escrava, de 1887, é um tanto particular para a literatura brasileira produzida até aquele momento, em outro tema bastante em voga no período, o encontro da cultura europeia com a cultura indígena autóctone, ela também vai apresentar concepções distintas. Levando em consideração essa perspectiva, o presente artigo tem por objetivo analisar as ideias da autora contidas em seu conto indianista Gupeva, de 1861-2, uma vez que, nessa narrativa, ela se dedica a pensar o lugar destinado ao índio na sociedade brasileira oitocentista, no sentido de registrar a sua contribuição e de marcar o seu ideário acerca da questão nacional.

Selection of bioindicators for 90-Sr among the benthic marine algae from the Saco do Piraquara de Fora, Angra dos Reis, RJ (preliminary results)

International Nuclear Information System (INIS)

Azevedo, H.L.P. de; Vianna, M.E.C.; Monteiro, D.; Fernandes, H.; Gusmao Pedrini, A. de

1983-01-01

With the aim of pre-selecting bioindicators for Sr-90 among the marine algae, monthly sampling in three different fixed locations, have benn done and strontium and calcium concentrations have been determined in the most abundant species of algae in the region of Angra dos Reis. In order to establish the influence of seasonal variations, the sea water salinity and strontium and calcium concentrations have also been analysed. (E.G.) [pt

Os primeiros reis-de-armas do Brasil

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Rui Vieira da Cunha

1963-12-01

Full Text Available A filiação direta dos arautos aos fetiales romanos (1 é negada pela pesquisa moderna, embora longe de dissipar as som-bras envolventes de suas origens (2 . Referidos nos poemas de Chrétien de Troyes, circa 1170, aparecem vinculados aos tor-neios e, pelos meados do século XIV, erravam à busca de onde prestar seus serviços, salvo uns poucos felizardos que estavam incluídos na casa de grandes senhores . Nesse último grupo, alguns, com autoridade sôbre os companheiros, eram denomi-nados reis, apelativo escolhido para significar, à época, análo-ga preeminência entre os menestréis, os devassos, os mendigos.

Análise hidrológica e socioambiental da bacia hidrográfica do córrego Romão dos Reis, Viçosa-MG The hydrographic watershed of Romão dos Reis stream, Viçosa-MG

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Genice Vieira Santos

2007-10-01

Full Text Available O objetivo deste trabalho foi analisar os aspectos hidrológico e socioeconômico da bacia hidrográfica do córrego Romão dos Reis, que se localiza no Município de Viçosa, na região da Zona da Mata do Estado de Minas Gerais. O estudo enfatizou o uso e ocupação da terra como fatores determinantes na análise da qualidade da água, além dos fatores físicos da bacia. Esta foi dividida em sub-bacias, o que possibilitou a escolha de locais representativos para coleta e análise de dados. Coletaram-se os dados referentes a vazão, qualidade da água, elevações, precipitação, uso do solo, tipo de solo e aspectos sociais e econômicos. Para a elaboração dos mapas, utilizou-se o modelo digitalizado, construído a partir de mosaicos e fotos aéreas da região, na escala de 1:30.000. As informações sobre o número de moradores e proprietários, assim como os seus respectivos sistemas de cultivos e ocupação na bacia, foram obtidas por meio de entrevistas semi-estruturadas, visando melhor compreender a organização social e o manejo de uso da terra das propriedades. Foram apontados indicadores de degradação, assim como estratégias de manejo adequadas à melhoria ambiental, que venham contribuir e garantir a sustentabilidade da bacia.This study was carried out to analyze the hydrological and socioeconomic aspects in the hydrographic watershed of Romão dos Reis stream in Viçosa county, Zona da Mata region, Minas Gerais State. In this study, the land use and occupation are emphasized as determinant factors for analyzing water quality, besides physical factors. The watershed was divided into sub-watersheds enabling to choose the representative sites for data collection and analysis. Data on flow rate, water quality, relief, precipitation, landscape (top, hillside and terrace, soil type, social and economic aspects were collected. A digitalized model built from mosaics and aerial photos of the area at 1:30.000 scale was used to draw up

Sacrifício rei, estado ruandês e genocídio

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Christopher C. Taylor

Full Text Available Em contraste com as análises do genocídio ruandês de 1994, que privilegiam o político, este artigo sustenta que o poder e a política durante o tempo que precedeu o genocídio foram afetadas por noções ruandesas específicas de cosmologia e ontologia. Para entender esse componente "imaginário" da violência, precisamos examinar atentamente as crenças e práticas relacionadas com a instituição da realeza sagrada em Ruanda. Embora essas crenças e práticas foram oficialmente encerradas em 1931, quando o último rei de Ruanda sagrado foi deposto e substituído por seu filho educado por missionários, a sua matriz cosmológica manteve-se em tempos recentes. Isto pode ser visto na literatura popular de rua Ruandesa, que circulou amplamente nos dias que antecederam o genocídio. Nessa literatura, o então presidente Juvenal Habyarimana era comparado explicitamente a um rei ruandês. Mais importante ainda para os objetivos deste artigo, foi a comparação mais difusa, implícita, e simbólica entre Habyarimana e um rei sagrado. Em particular, alguns dos elementos-chave neste simbolismo iluminam (e mostram a importância da persistência da imagem de como um rei (ou presidente deveria se comportar. Como havia muitos jornalistas ruandeses reacionários (e racistas que tinham começado a duvidar da capacidade do presidente Habyarimana de ser um "bom rei", seu "sacrifício"'subseqüente estava, em um sentido simbólico, fortemente predestinado.

Concentration of heavy metals in benthic algae from Ribera Bay, Angra dos Reis, R.J. State, Brazil, suggesting monitor species

International Nuclear Information System (INIS)

Guimaraes, J.R.D.; Lacerda, L.D. de; Teixeira, V.L.; Faculdade de Biologia e Psicologia Maria Thereza, Niteroi

1982-01-01

Concentrations of Cu, Cr, Cd, Zn, Mn, Co, Pb and Ni were determined in benthic algae of Bay of Ribeira, Angra dos Reis, SE Brazilian coast. The results showed that these elements are concentrate under different degrees depending on the algae species considered: Galaxaura marginata and Caulerpa racemosa presented the highest concentrations (ppm) for Cu (5,2), Cd (1,5), Mn (91,5), Co (6,2) and Ni (8,0) and Cr (7,9) and Pb (21,9) respectively. These algae are then suggested as potential monitor species for these metals in tropical coastal waters. The estimated bioaccumulation factors varied from 10 2 for Ni to 10 5 for Pb, falling within the range reported in the literature, with the exception of Cd, which was found to be two orders of magnitude greater. (Author) [pt

Phytoplankton community of Reis lake in the Brazilian Amazon

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ISE G. SILVA

2013-06-01

Full Text Available Reis Lake is located in the municipality of Caracaraí, state of Roraima (Brazil and is subject to fluctuations in water level. The aim of this study was to analyze the structure of the phytoplankton community on the nictemeral and seasonal scales and determined the influence of limnological variables. Sampling was performed in the rainy season (June/2006 and dry season (November/2006, considering two nictemeral cycles. The phytoplankton community was assessed with regard to composition and density, abiotic variables were analyzed simultaneously. The lake had low concentrations of oxygen, clinograde profile and water stratified during the day and homogenous at night, with low concentrations of nutrients and waters ranging from slightly acidic to alkaline. The phytoplankton was represented by 43 taxa, 35 species in the dry season and 29 species in the rainy season. Low densities of phytoplankton occurred in both nictemeral cycles, with accentuated vertical gradient. The highest densities were recorded in the dry season. Reis Lake exhibits characteristics that classify it as a polymythic and oligotrophic environment. The variability in the data was more important seasonally than on the nictemeral scale, supporting the hypothesis of the influence of the hydrological cycle on the dynamics of phytoplankton communities in floodplain lakes.O lago dos Reis está localizado no município de Caracaraí, no estado de Roraima (Brasil e está sujeito a flutuações no nível da água. O objetivo do estudo foi analisar a estrutura da comunidade fitoplanctônica nas escalas nictemeral e sazonal e determinar a influência de variáveis limnológicas nesta comunidade. As amostragens foram realizadas nos periodos chuvoso e seco, considerando dois ciclos nictemeral. A comunidade fitoplanctônica foi avaliada no que diz respeito à composição e densidade, simultaneamente, variáveis abióticas foram analisadas. O lago apresentou baixas concentrações de oxig

Iconografia da honra e do prestígio: Reis de Armas e cavaleiros das Ordens Militares em Portugal e Castela (séculos XVII-XVIII)

OpenAIRE

Guillén Berrendero, José Antonio

2016-01-01

O tema deste artigo é demonstrar o poder das representações visuais dos indivíduos honrados nas coroas de Castela e de Portugal. Mostra uma visão transversal da representação da honra e do prestígio mediante a identificação das distintas marcas de nobreza que são atribuídas aos cavaleiros das Ordens Militares e pelos Reis de Armas. No caso dos primeiros, o autor analisa os elementos próprios de indivíduos identificados pela sua condição de nobres. No caso dos Reis de Armas, centra-se no valor...

Maracatus Solar e Reis de Paus: tradição e modernidade no carnaval de rua em Fortaleza

OpenAIRE

Silva, Roberto Antônio de Sousa da

2013-01-01

Trata-se de um estudo etnográfico e comparativo dos Maracatus Solar (2006) e Reis de Paus (1960), cujo objetivo foi verificar o que existe de antigo e tradicional no novo maracatu praticado pela agremiação Solar e, em contrapartida, o que existe de novo ou moderno no velho maracatu ritualizado pela agremiação Reis de Paus. Cabe ressaltar que por meio deste estudo de caso pretendeu-se também observar etnograficamente e compreender melhor os processos de rupturas e continuidades ...

The long history of REI Conference: The first 30 years

International Nuclear Information System (INIS)

Mazzoldi, P.

2010-01-01

An analysis of the REI Conference evolution from the first, in 1981, to the last, 2009, REI-15, is reported, considering the contributions in the different topics, as fundamental processes, materials, nanosystem and application and revisiting some invited talks and presentations. Historical information concerning some Universities, which organized REI-Conferences, are introduced in the exposition.

Analysis of Particle Production in the Municipalities of Angra dos Reis, Campos and Petropolis in Rio de Janeiro

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Sebastião Lourenço dos Santos João

2014-12-01

Full Text Available The productive clusters are currently constant reference in the research lines turn into strategic issue. Cities with production clusters have differentiated development in relation to other cities. This development has a direct influence on the location / installation and management of companies. This factor allows the organization gain a competitive advantage due to proximity to their suppliers and direct contact with the local population. With supplier companies increase the mobility of its supply chain and benefit from the existence of quality equipment in the network. This study aims to analyze, evaluate and classify the productive clusters of cities in the State of Rio de Janeiro, particularly in the municipalities of Angra dos Reis, Campos and Petropolis, to achieve balanced local development that benefits all stakeholders by product / city services. Productive clusters must necessarily contribute to improving the level of service offered to the customer. The methodology adopted was proposed by the Suzigan et al (2003 and Britto and Albuquerque (2002, to assess, analyze and classify the clusters in addition to bibliographic survey to support the study. The results show that depending on the importance of economic activity for the city, the production clusters greatly contribute to local development and increase the range of options for the local consumer.

Development of REI meetings (concluding remarks)

International Nuclear Information System (INIS)

Roessler, K.

1988-01-01

It is an honour and a pleasure to deliver the concluding remarks of this Fourth International Conference on Radiation Effects in Insulators. After commenting upon the present meeting, the genesis of REI conferences, their aims and position relative to related meetings in radiation and ion implantation research will be treated, particularly in order to inform new-comers. The development of the last four REI meetings will be discussed on the base of a statistical analysis. Some recommendations and an outlook of future trends will be given. (orig.)

Behavior of Cs and Co in marine sediments of Enseada de Piraquara de Fora, Angra dos Reis, RJ, Brazil; Comportamento Cs e Co em sedimentos marinhos da Enseada de Piraquara de Fora - Angra dos Reis

Energy Technology Data Exchange (ETDEWEB)

Ferreira, I. M.; Carvalho, F. M.; Lauria, D.C., E-mail: dejanira@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro - RJ (Brazil)

2017-07-01

The release of {sup 137}Cs and {sup 60}Co in the liquid effluents from the Angra dos Reis power plants could radiologically impact the Saco de Piraquara de Fora (SPF) inlet. The mobility and trend of the radionuclides in the water-sediment compartment were investigated by studies of thermodynamic and sorption-desorption. The values of distribution coefficients (Kd) were around 500 L. kg{sup -1} for {sup 60}Co and 400 L. kg{sup -1} for {sup 137}Cs that are lower than the literature values. The predominance of kaolinite in the clay fraction may have played a major role in the low observed Kd values. For both radionuclides, the sorption was higher for the sediment with higher cation exchange capacity, and the equilibrium conditions were reached only after the third day. Despite the relatively low Kd values and low sorption rates, both can considerably be accumulated in sediments, and the sorption reactions are partially irreversible. {sup 60}Co and {sup 137}Cs accumulate in orders of magnitude of 1010 and 109 Bq g{sup -1} sediment, respectively, which shows the ability of the sediments to remove and retain much of the {sup 137}Cs and {sup 60}Co released by the power plants. Considering the range of temperature of the SPF water, both sorption and desorption of the two metals increase with temperature. However, in general, the retention rates of the radionuclides in sediments remain constant. The sorption sites are heterogeneous since the sorption data can be adjusted by the Langmuir and Freündlich isotherms. The sorption of Co and Cs are endothermic processes, which are spontaneous at low temperature. (author)

An alternative nuclear program

International Nuclear Information System (INIS)

Goldemberg, J.

1981-01-01

An analysis of the development of nuclear energy in Brazil is made since its beginning, showing the fundamental policy changes introduced in the end of the 60's with the purchase of the Angra dos Reis I reactor. This decision discouraged the existing efforts of an autonomous development in nuclear energy. The reaction to this policy led to the Nuclear Deal with Germany, which although incorporating some positive aspects is nor capable to lead to nuclear independence. The presently existing options are discussed, as well as the transformation of the Nuclear Program in a R and D Program based only in the reactors I, II and III, located in Angra dos Reis. (Author) [pt

Alternative Nuclear Program

International Nuclear Information System (INIS)

Goldemberg, J.

1982-01-01

An analysis of the development of nuclear energy in Brazil is made since its beginning, showing the fundamental policy changes introduced in the end of the 60's with the purchase of the Angra dos Reis I reactor. This decision discouraged the existing efforts of an autonomous development in nuclear energy. The reaction to this policy led to the Nuclear Deal with Germany, which although incorporating some positive aspects is not capable to lead to nuclear independence. The presently existing options are discussed, as well as the transformation of the Nuclear Program in a R and D Program based only in the reactors I, II and III, located in Angra dos Reis. (Author) [pt

Temperature distribution in the Piraquara de Fora Bay resulting from residual heat liberation of the Angra-1 Nuclear Power Plant in Angra dos Reis, RJ, Brazil and its possible ecological effects

International Nuclear Information System (INIS)

Mota Singer, E. da.

1979-01-01

A preliminary evaluation was done of the potential environmental consequences derived from the emission from the condenser cooling of the nuclear power plants at the Angra dos Reis site. The calculation of the temperature field starting from the point of emission of the coolant discharge was done using the model of Stolzenbach for three dimensional heated surface discharge. Considerations were made of the potential environmental damage to the marine life based on the calculated temperature increase. Special atention was given to the potential damage to the necton's life, by estimating the probability of occurance of higher than lethal temperature for the known species living at the site. These species were given in the Safety Analysis Report of the Unity I of the nuclear station. (Author) [pt

OS IMPACTOS AMBIENTAIS E O PROCESSO DE GESTÃO INTEGRADA: EXPERIÊNCIAS NA VILA DE ABRAÃO – ILHA GRANDE, ANGRA DOS REIS (RJ / The Environmental Impacts and The Process of Integrated Management: Experiences in The Vila de Abraão – Ilha Grande, Angra dos Reis (RJ

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Sueli Maurício Leal Filha

2006-12-01

Full Text Available The Ilha Grande is situated at the intersection of the parallels 23°05' and 23°14' degrees Southlatitude with the meridians 44°05' and 44°23' West longitude, in Angra dos Reis county, at the Riode Janeiro state Southern coast. It has approximately 193Km² and has two districts, Araçatiba,situated at the western portion whose main villa of residents is Provetá, and Abraão, situated atthe East portion where detaches as the main village the Vila de Abraão. The Vila de Abraão isconsidered the “capital” of the Ilha Grande, where arrive and alter on a daily basis, inhabitants,visitors, public managers, researchers and environmental defenders. The present article considersenvironmental impacts in the Vila de Abraão as important vectors in the construction of managementprocess and territorial planning, mainly after the Island’s change of function - from federal prison(Instituto Penal Cândido Mendes and environmental conservation area it becomes the headoffice of the Centro de Estudos Ambientais e Desenvolvimento Sustentável, a State University ofRio de Janeiro (UERJ unit, which has both an institutional and environmental conservation use,however framed in touristic activity growth context.

Preliminary evaluation of SACI-O code for the analysis of transients in a pressurized water reactor core

International Nuclear Information System (INIS)

Soares, P.A.; Sirimarco, L.F.; Veloso, M.A.F.

1979-03-01

SACI-O is a computer code which deals with the dynamics of the core of pressurized light water reactors (PWR). Its applicability is determined by the evaluation of the models used in the simulation of the several phenomena and processes which occur in the core during transients. This report presents a comparison between the results obtained with SACI-O and those presented in the Final Safety Analysis Report (FSAR) of Angra dos Reis Nuclear Station, Unit 1. Although some data used in the calculations done by Westinghouse are not known, there was a good agreement between the mentioned results. (Author) [pt

LÁ VEM A BANDEIRA... OS REIS E SEUS ATORES

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Mauro Passos

2011-01-01

Full Text Available A religiosidade popular manifesta-se por meio de rituais, festas, comemorações e celebrações. Alicerçadas em elementos místicos, as tradições populares integram o natural, o social e o sagrado. Este artigo faz um estudo das “Folias de Reis”, particularmente em duas cidades do interior de Minas Gerais. Foram utilizados os procedimentos metodológicos da história oral, através de um conjunto de depoimentos. A religiosidade faz parte da cultura das classes populares. Seu estudo é um importante instrumento para a compreensão das raízes culturais e históricas do povo brasileiro. Na verdade, trata-se do mundo de Deus e mundo dos homens, ancorados no rio da vida. As Folias de Reis estão permeadas por múltiplos atores, lastreadas de continuidades / descontinuidades. Em vista disso, é necessário analisar seu significado e sua dinâmica.

Elites em perspectiva: uma discussão sobre hierarquias, composição da riqueza e consolidação dos grupos hegemônicos em São João del Rei = Elites in perspective: a discussion about hierarchies, composition of wealth and consolidation of hegemonic groups in São João del Rei

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Melo, Keila Cecília de

2014-01-01

Full Text Available O artigo analisa aspectos econômicos da elite colonial mineira a partir de meados do século XVIII, mediante a investigação empírica da sociedade de São João Del Rei. O comércio em São João assumiu um papel central na liquidez da economia regional, permitindo a formação de grupos hegemônicos no século XIX. Mas há ainda muitas dúvidas sobre quem era essa elite no século XVIII. Com base em pesquisa prosopográfica que reconstrói os caminhos dos homens arrolados por Domingos Nunes Vieira como os mais ricos da capitania de Minas Gerais no ano de 1756, percebemos que a elite mineira que se formou no século XVIII diferia dos padrões mais gerais para a caracterização de grupos hegemônicos em outras regiões do Brasil, no mesmo período

Fusion of classifiers for REIS-based detection of suspicious breast lesions

Science.gov (United States)

Lederman, Dror; Wang, Xingwei; Zheng, Bin; Sumkin, Jules H.; Tublin, Mitchell; Gur, David

2011-03-01

After developing a multi-probe resonance-frequency electrical impedance spectroscopy (REIS) system aimed at detecting women with breast abnormalities that may indicate a developing breast cancer, we have been conducting a prospective clinical study to explore the feasibility of applying this REIS system to classify younger women (breast cancer. The system comprises one central probe placed in contact with the nipple, and six additional probes uniformly distributed along an outside circle to be placed in contact with six points on the outer breast skin surface. In this preliminary study, we selected an initial set of 174 examinations on participants that have completed REIS examinations and have clinical status verification. Among these, 66 examinations were recommended for biopsy due to findings of a highly suspicious breast lesion ("positives"), and 108 were determined as negative during imaging based procedures ("negatives"). A set of REIS-based features, extracted using a mirror-matched approach, was computed and fed into five machine learning classifiers. A genetic algorithm was used to select an optimal subset of features for each of the five classifiers. Three fusion rules, namely sum rule, weighted sum rule and weighted median rule, were used to combine the results of the classifiers. Performance evaluation was performed using a leave-one-case-out cross-validation method. The results indicated that REIS may provide a new technology to identify younger women with higher than average risk of having or developing breast cancer. Furthermore, it was shown that fusion rule, such as a weighted median fusion rule and a weighted sum fusion rule may improve performance as compared with the highest performing single classifier.

Lagrangian modeling of atmospheric dispersion of radionuclides and geographical information systems as tools to support emergency planning in area of influence of nuclear complex of Angra dos Reis, RJ, Brazil; Modelagem Lagrangeana da dispersao atmoferica de radionuclideos e sistemas de informacao geografica como ferramentas de suporte ao planejamento de emergencia na area de influencia do complexo nuclear de Angra dos Reis, RJ

Energy Technology Data Exchange (ETDEWEB)

Silva, Corbiniano

2013-07-01

Industrial accidents generally endanger structures and the set of environmental influence area where the enterprises are located, especially when affected by atmospheric dispersion of their pollutants, whose concern with the evacuation of the population is the main goal in emergency situations. Considering the nuclear complex Angra dos Reis - RJ, based on computer modeling analysis of the mechanisms of pollutant dispersion in conjunction with geographic information systems were developed. Thus, information about the dispersion of radionuclides - from simulations performed on the HYSPLIT; meteorological data (direction, intensity and calm on the wind regime and analysis of the wind field in the region using WRF), occurrence of landslides and data on the environmental study area were integrated into a GIS database using ArcGIS platform. Aiming at the identification and definition of escape routes in case of evacuation from accidental events in CNAAA, the results point solutions for long-term planning, based on weather and landslides, and short-term, supported by simulations of the dispersion radionuclides, in order to support actions that assist local emergency planning. (author)

Anthropogenic impact on the sedimentation in coastal regions: an example in Saco do Bracui - Ribeira Bay, Angra dos Reis, Brazil; O impacto antropogenico sobre a sedimentacao em regioes costeiras: um exemplo no Saco do Bracui - Baia da Ribeira, Angra dos Reis, Brasil

Energy Technology Data Exchange (ETDEWEB)

Barbosa, Alayde Alfaia

2001-07-01

The Saco do Bracui, located in the littoral zone of the Brazilian southeast, receives run off from the region of Angra dos Reis. Anthropological intervention in this area has modified local morphology during the last 40 years. These modifications include an intense deforestation of mangrove regions, construction of the Bracui Boat Yard, the dredging of part of the draining basin and development of the coastal plain. Results from seismic surveys identify three different stratigraphic units separated by two reflectors as well as Holocenic paleodeltas and paleochannels of the Bracui and Gratau rivers. Results from this study and previous work indicate an age of 6800 years for the top of the superior unit. Areal photographs from the years 1964, 1965, 1978 and 1991 reveal the principal modifications occurring during the last 40 years in the area. Field observations from this study as well as bathymetric profiles based on the nautical maps of 1980 and 1944 reveal shoaling and erosion areas in the Saco do Bracui. Sedimentation rates, using lead-210 profiles, are between 0,17 - 1,90 cm/year and lead-210 inventory values are between 16-6-dpm/cm{sup 2}/year. The results for sedimentation rate and inventory show a high accumulation around Bracui, Gratau and Frade mouth rivers and agree with results from the bathymetric profiles with respect to the site of erosion and shoaling in the Saco do Bracui. The results for grain size and lead-210 analyses support the idea that the Saco do Bracui is suffering shoaling processes in specific sites and erosion in others. Comparison between long term sedimentation rates obtained by seismic results and short term rates obtained by lead-210 shows an increase of the sedimentary discharge in the 1960's, when the intense anthropological intervention in the area began. (author)

Does familiarity breed contempt or liking? Comment on Reis, Maniaci, Caprariello, Eastwick, and Finkel

NARCIS (Netherlands)

Norton, M.I.; Frost, J.H.; Ariely, D.

2011-01-01

Reis, Maniaci, Caprariello, Eastwick, and Finkel (2011) conducted 2 studies that demonstrate that in certain cases, familiarity can lead to liking-in seeming contrast to the results of our earlier article (Norton, Frost, & Ariely, 2007). We believe that Reis et al. (a) utilized paradigms far removed

Brazil-Argentina bilateral cooperation - Protocol 11. Nuclear safety and radiation protection. Visit of CNEA engineers to Brazil

International Nuclear Information System (INIS)

Gasparian, A.E.

1991-01-01

The activities carried out by Techniques of Argentine Organization (CNEA) during visitation to Angra dos Reis (Brazil) are related. Licensing procedures for nuclear installations (reactors), and transport, licensing of personnels for nuclear installations, quality assurance and regulatory inspections were discussed. (M.C.K.)

Sustainable Materials Management (SMM) - Recycling Economic Information (REI) Report

Data.gov (United States)

U.S. Environmental Protection Agency — The 2016 Recycling Economic Information (REI) Report aims to increase the understanding of the economic implications of material reuse and recycling. The report...

A prática oceanográfica e a coleção iconográfica do rei dom Carlos I

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Maria Estela Jardim

2014-09-01

Full Text Available Após a expedição do Challenger (1872-1878, outras nações começaram a interessar-se pela pesquisa oceanográfica e a organizar suas próprias expedições. Desde 1885 que o príncipe Albert I de Mónaco realizava campanhas oceanográficas, com a colaboração de alguns dos melhores cientistas em biologia marinha e em oceanografia física, inventando técnicas e instrumentos para a realização dos trabalhos oceanográficos. A atividade científica do príncipe Albert certamente contribuiu para estimular o interesse do seu amigo, o rei dom Carlos I de Portugal, pelo estudo dos oceanos e da vida marinha. Ambos compartilhavam a necessidade de usar a fotografia para documentar suas pesquisas. Este artigo analisa o papel da fotografia científica na ciência oceanográfica, particularmente nas expedições realizadas pelo monarca português.

Stockscheider Quartzo-Moscovíticos e Pegmatíticos na Zona de Cúpula do Granitóide Ritápolis, Região de São João del Rei, Minas Gerais

Directory of Open Access Journals (Sweden)

Ronaldo Mello Pereira

2011-01-01

Full Text Available Em quatro áreas da Província Pegmatítica de São João del Rei são encontrados clusters de corpos constituídos basicamente por quartzo-moscovita, que estão em estreita associação com pegmatitos posicionados paralelamente à zona de cúpula do granitóide Ritápolis, no contato deste com as rochas metassedimentares - metavulcânicas da faixa greenstone Rio das Mortes. As associações mineralógicas determinadas para os stockscheider quartzo-moscovíticos e pegmatíticos, representadas por columbita-tantalita, cassiterita, gahnita, zircão, xenotímio e monazita, são semelhantes às determinadas para os demais pegmatitos da Província Pegmatítica de São João del Rei. Os tipos de inclusões (Pb-tantalita, microlita, Pb-microlita, U-microlita, Ba-microlita, zircão rico em Hf contidas na Fe-columbita associada ao stocksheider também são as mesmas da Fe-columbita associada aos pegmatitos mais evoluídos da província. Os stockscheider quartzo-moscovíticos e pegmatíticos estão vinculados ao granitóide Ritápolis e este, aos demais pegmatitos da Província Pegmatítica de São João del Rei. O mecanismo proposto para a formação dos clusters de stockscheider quartzo-muscovíticos e pegmatíticos é o da cristalização de bolsões localizados contendo fluidos tardi-magmáticos e pós-magmáticos (hidrotermais - metassomáticos segregados do magma granítico, os quais foram injetados ao longo de fraturas paralelas à zona de cúpula do granitóide Ritápolis.

Anthropogenic impact on the sedimentation in coastal regions: an example in Saco do Bracui - Ribeira Bay, Angra dos Reis, Brazil

International Nuclear Information System (INIS)

Barbosa, Alayde Alfaia

2001-01-01

The Saco do Bracui, located in the littoral zone of the Brazilian southeast, receives run off from the region of Angra dos Reis. Anthropological intervention in this area has modified local morphology during the last 40 years. These modifications include an intense deforestation of mangrove regions, construction of the Bracui Boat Yard, the dredging of part of the draining basin and development of the coastal plain. Results from seismic surveys identify three different stratigraphic units separated by two reflectors as well as Holocenic paleodeltas and paleochannels of the Bracui and Gratau rivers. Results from this study and previous work indicate an age of 6800 years for the top of the superior unit. Areal photographs from the years 1964, 1965, 1978 and 1991 reveal the principal modifications occurring during the last 40 years in the area. Field observations from this study as well as bathymetric profiles based on the nautical maps of 1980 and 1944 reveal shoaling and erosion areas in the Saco do Bracui. Sedimentation rates, using lead-210 profiles, are between 0,17 - 1,90 cm/year and lead-210 inventory values are between 16-6-dpm/cm 2 /year. The results for sedimentation rate and inventory show a high accumulation around Bracui, Gratau and Frade mouth rivers and agree with results from the bathymetric profiles with respect to the site of erosion and shoaling in the Saco do Bracui. The results for grain size and lead-210 analyses support the idea that the Saco do Bracui is suffering shoaling processes in specific sites and erosion in others. Comparison between long term sedimentation rates obtained by seismic results and short term rates obtained by lead-210 shows an increase of the sedimentary discharge in the 1960's, when the intense anthropological intervention in the area began. (author)

Echoes of Portuguese Navigation in the Kitab-i Bahriye by Piri Reis

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Rui Manuel Loureiro

2013-10-01

Full Text Available The world map drawn by Piri Reis in 1513, of which only the Atlantic fragment kept in Istanbul is known, is justly famous. Its surprising modernity is fully explained by the use of Iberian sources, resulting from nearly a century of exploration of both sides of the Atlantic by Portuguese and Spanish navigators, along with other collaborators. The ‘Book of maritime affairs’, prepared in the 1520s by the Turkish cartographer, gathering precious geographic and cartographic information about the Mediterranean and many other regions, is equally important, although rather less well known. In the foreword to his Kitab-i Bahriye, Piri Reis appears to be especially well informed about Portuguese explorations along the African coast and in the Asian seas, after the voyages of Bartolomeu Dias and of Vasco da Gama. Is it possible to identify the textual and cartographic sources used by Piri Reis in the preparation of both his cartographic works?

Lagrangian modeling of atmospheric dispersion of radionuclides and geographical information systems as tools to support emergency planning in area of influence of nuclear complex of Angra dos Reis, RJ, Brazil

International Nuclear Information System (INIS)

Silva, Corbiniano

2013-01-01

Industrial accidents generally endanger structures and the set of environmental influence area where the enterprises are located, especially when affected by atmospheric dispersion of their pollutants, whose concern with the evacuation of the population is the main goal in emergency situations. Considering the nuclear complex Angra dos Reis - RJ, based on computer modeling analysis of the mechanisms of pollutant dispersion in conjunction with geographic information systems were developed. Thus, information about the dispersion of radionuclides - from simulations performed on the HYSPLIT; meteorological data (direction, intensity and calm on the wind regime and analysis of the wind field in the region using WRF), occurrence of landslides and data on the environmental study area were integrated into a GIS database using ArcGIS platform. Aiming at the identification and definition of escape routes in case of evacuation from accidental events in CNAAA, the results point solutions for long-term planning, based on weather and landslides, and short-term, supported by simulations of the dispersion radionuclides, in order to support actions that assist local emergency planning. (author)

Distrofia de Reis-Bücklers: Presentación de una familia

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Daisy Flores Pérez

2003-09-01

Full Text Available Se presentan los resultados de un estudio realizado en 12 pacientes integrantes de una familia de la raza blanca. Se diagnosticaron 5 con distrofia de Reis-Bücklers. El defecto refractivo que predominó fue el astigmatismo. Se obtuvo un patrón de herencia autosómico dominante en la familia en estudio.The results of the study performed in 12 patients from a Caucasian family are presented. Five were diagnosed with Reis-BücKler dystrophy. The predominant refractory defect was astigmatism. A dominant autosomal hereditary pattern was obtained in the studied family.

Distribution of cysts of Strongyluris sp. (Nematoda) in the pallial system of Achatina fulica Bowdich, 1822 from Vila Dois Rios and Vila do Abraão, Ilha Grande, Angra dos Reis, Rio de Janeiro.

Science.gov (United States)

Oliveira, J L; Santos, S B

2018-04-19

This work aimed to assessing Strongyluris sp. cysts distribution pattern in the several inner organs from pallial system of Achatina fulica Bowdich, 1822. Also we verified if there is a relationship between the mollusk size and the number of specimens from parasites collected from two touristic villages in Ilha Grande (Angra dos Reis, Rio de Janeiro state): Vila Dois Rios (VDR) and Vila do Abraão (ABR). The samples were obtained through a field work conducted bimonthly during 2007, 2008, 2010, and 2011, at both locations. Height and width were measured from shells collected, and the all specimens were classified in different classes: class 1 - biomass and a larger area of the pallial system, allowing an efficient parasite colonization. Other possible explanation could be the long exposure of the molluscs of class 3 to the parasites, which allowed a longer time to the larvae to allocate themselves.

An overview of acceptance and knowledge of Angra dos Reis city about the operation of the nuclear power plants considering the associated risks and benefits

International Nuclear Information System (INIS)

Araujo, Jefferson Borges; Delcourt, Jules H.

2015-01-01

The use of nuclear power plants for electricity supply is presently considered as an important factor to be considered in any energy matrix to ensure the diversification and availability criteria. Currently several countries resumed or started programs for the construction of nuclear power plants of new projects, with extremely improved security levels. Additionally, events and accidents in nuclear power plants have contributed substantially to the occurrence of design modifications and/or update the regulatory requirements to further enhance operational safety of these plants. Nowadays, one of the regulatory requirements necessary for the selection of a site for construction and operation of nuclear installations is the public hearing and discussion. The city of Angra dos Reis has two nuclear power plants in operation and a third one under construction. There are also, plans for the construction of more nuclear power plants in the country, to meet the growing demand for electricity. The first nuclear power plant in Brazil went into operation in 1983 and the second in 2000. The selection of the site for construction of these plants was due to political, economic and strategic factors, present in Brazil, in the decade of 70. The licensing process in de 70's decade did not involve an extensive participation of the society as a whole and of the local population, such as the occurrence of public hearings and the wide possibility for discussion and debate about the acceptance of the location of the plant. In the initial years of operation of the Angra 1 nuclear power plant, the level of knowledge of the local population was practically null, occurring mainly in local clarifications, made through seminars and lectures on special occasions, such as at the time of the annual exercises of the external emergency plan, specific information Programs or technical visits of educational institutions and the Government to Angra dos Reis Nuclear power plant. Since the

An overview of acceptance and knowledge of Angra dos Reis city about the operation of the nuclear power plants considering the associated risks and benefits

Energy Technology Data Exchange (ETDEWEB)

Araujo, Jefferson Borges, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN/CGRC), Rio de Janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo Combustivel; Ribeiro, Katia Maria Bruno; Medice Junior, Fabio, E-mail: Katiapsi.67@gmail.com [Universidade Estacio de Sa (UNESA), Angra dos Reis, RJ (Brazil); Delcourt, Jules H., E-mail: juleshd@gmail.com [Colegio Naval, Angra dos Reis, RJ (Brazil)

2015-07-01

The use of nuclear power plants for electricity supply is presently considered as an important factor to be considered in any energy matrix to ensure the diversification and availability criteria. Currently several countries resumed or started programs for the construction of nuclear power plants of new projects, with extremely improved security levels. Additionally, events and accidents in nuclear power plants have contributed substantially to the occurrence of design modifications and/or update the regulatory requirements to further enhance operational safety of these plants. Nowadays, one of the regulatory requirements necessary for the selection of a site for construction and operation of nuclear installations is the public hearing and discussion. The city of Angra dos Reis has two nuclear power plants in operation and a third one under construction. There are also, plans for the construction of more nuclear power plants in the country, to meet the growing demand for electricity. The first nuclear power plant in Brazil went into operation in 1983 and the second in 2000. The selection of the site for construction of these plants was due to political, economic and strategic factors, present in Brazil, in the decade of 70. The licensing process in de 70's decade did not involve an extensive participation of the society as a whole and of the local population, such as the occurrence of public hearings and the wide possibility for discussion and debate about the acceptance of the location of the plant. In the initial years of operation of the Angra 1 nuclear power plant, the level of knowledge of the local population was practically null, occurring mainly in local clarifications, made through seminars and lectures on special occasions, such as at the time of the annual exercises of the external emergency plan, specific information Programs or technical visits of educational institutions and the Government to Angra dos Reis Nuclear power plant. Since the

Does familiarity breed contempt or liking? Comment on Reis, Maniaci, Caprariello, Eastwick, and Finkel

OpenAIRE

Norton, M.I.; Frost, J.H.; Ariely, D.

2011-01-01

Reis, Maniaci, Caprariello, Eastwick, and Finkel (2011) conducted 2 studies that demonstrate that in certain cases, familiarity can lead to liking-in seeming contrast to the results of our earlier article (Norton, Frost, & Ariely, 2007). We believe that Reis et al. (a) utilized paradigms far removed from spontaneous, everyday social interactions that were particularly likely to demonstrate a positive link between familiarity and liking and (b) failed to include and incorporate other sources o...

A series of luminescent Re(I) complexes with electron-donor/acceptor moieties: Synthesis, characterization, and photoluminescence

International Nuclear Information System (INIS)

Ge Hu; Qing She; Lei Guo

2012-01-01

In this paper, we synthesize three Re(I) complexes of Re(CO) 3 (PPO)Br, Re(CO) 3 (PTO)Br, and Re(CO) 3 (PBI)Br, where PPO=2-phenyl-5-(pyridin-2-yl)-1,3,4-oxadiazole, PTO=2-(pyridin-2-yl)-5-p-tolyl-1,3,4-oxadiazole, PBI=2-(pyridin-2-yl)-1H-benzo[d]imidazole. Their single crystals and photophysical properties are measured and discussed in detail. The correlation between ligand structure and corresponding PL characteristics of Re(I) complex has been investigated. It is found that a ligand with strong electron-donor can efficiently increase both absorption and emissive energy of Re(I) complex. In addition, electron-rich ligand can increase the electron density of the complex and thus enhance the oscillator strength of electronic transition, improving the photoluminescence performance. - Highlights: ► Three novel phosphorescent Re(I) complexes are synthesized. ► Molecular structures, photophysical, and electronic properties are studied. ► Strong electron-donor can increase emissive energy. ► Electron-rich ligand can enhance the oscillator strength of electronic transition.

Granular corneal dystrophy Groenouw type I (GrI) and Reis-Bücklers' corneal dystrophy (R-B). One entity?

Science.gov (United States)

Møller, H U

1989-12-01

This paper maintains that Reis-Bücklers' corneal dystrophy and granular corneal dystrophy Groenouw type I are one and the same disease. Included are some of the technically best photographs of Reis-Bücklers' dystrophy found in the literature, and these are compared with photographs from patients with granular corneal dystrophy examined by the author. It is argued that most of the histological and ultrastructural findings on Reis Bücklers' dystrophy described in the literature are either congruent with what is found in granular corneal dystrophy or unspecific.

Väljapaistev riigimees August Rei puhkab kodumaa mullas / Urve Sagur

Index Scriptorium Estoniae

Sagur, Urve

2006-01-01

Asutava Kogu ja Riigikogu esimehe, riigivanema, ministri ja diplomaadi August Rei ja tema abikaasa urnid maeti Metsakalmistule Kuulsuste künkale. Mälestusteenistusel kõnelesid president Arnold Rüütel ja Riigikogu esimees Toomas Varek. Lisa: Ametid

Palinologia de espécies de Asteraceae de utilidade medicinal para a comunidade da Vila Dois Rios, Ilha Grande, Angra dos Reis, RJ, Brasil Pollen morpology of species of Asteraceae with medicinal utility for the community from Vila Dois Rios, Ilha Grande, Angra dos Reis, Rio de Janeiro State, Brazil

Directory of Open Access Journals (Sweden)

Marcelo Neto Galvão

2009-03-01

Full Text Available O trabalho trata da morfologia polínica e de descrições taxonômicas de 12 espécies de Asteraceae correspondentes em 12 diferentes gêneros, distribuídos em nove tribos. Todas as espécies estudadas são utilizadas como medicamentos pelos moradores da Vila Dois Rios, Ilha Grande, Angra dos Reis, Rio de Janeiro. Neste estudo objetivou-se caracterizar os tipos polínicos das espécies usadas por esta comunidade e fornecer chaves diagnósticas de caracteres macromorfológicos e micromorfológicos que auxiliem a identificação das mesmas. A identificação taxonômica e palinológica correta é pré-requisito para estudos que validem a eficácia e segurança terapêutica dessas espécies. Deve-se considerar, ainda, que a utilização desses conhecimentos é importante para a comunidade, como por exemplo, na melissopalinologia. Os grãos de pólen foram acetolisados, medidos, descritos e ilustrados sob microscopia de luz. Para observar detalhes da superfície e abertura, grãos de pólen não acetolisados foram analisados em microscópio eletrônico de varredura. Foram estudadas as características dos grãos de pólen como forma, tamanho, constituição da sexina e abertura. Os resultados mostraram que a morfologia polínica é bem definida entre as espécies estudadas, podendo ser usada para sua identificação e sustenta o caráter euripalinológico de Asteraceae.This study is a palynologycal characterization and taxonomic description of 12 species within 12 genera, distributed in nine tribes from Asteracaeae. All studied species are used as medicines by people from Vila Dois Rios and they occur in Ilha Grande. This work aimed to characterize the pollen grains of medicinal species of Asteraceae from Vila Dois Rios and provide diagnostic keys based on macromorphological and pollen characters to help their identification, since the correct taxonomic and palynological recognition of these species is necessary for further studies on therapeutic

Extreme-value limit of the convolution of exponential and multivariate normal distributions: Link to the Hüsler–Reiß distribution

KAUST Repository

Krupskii, Pavel

2017-11-02

The multivariate Hüsler–Reiß copula is obtained as a direct extreme-value limit from the convolution of a multivariate normal random vector and an exponential random variable multiplied by a vector of constants. It is shown how the set of Hüsler–Reiß parameters can be mapped to the parameters of this convolution model. Assuming there are no singular components in the Hüsler–Reiß copula, the convolution model leads to exact and approximate simulation methods. An application of simulation is to check if the Hüsler–Reiß copula with different parsimonious dependence structures provides adequate fit to some data consisting of multivariate extremes.

Extreme-value limit of the convolution of exponential and multivariate normal distributions: Link to the Hüsler–Reiß distribution

KAUST Repository

Krupskii, Pavel; Joe, Harry; Lee, David; Genton, Marc G.

2017-01-01

The multivariate Hüsler–Reiß copula is obtained as a direct extreme-value limit from the convolution of a multivariate normal random vector and an exponential random variable multiplied by a vector of constants. It is shown how the set of Hüsler–Reiß parameters can be mapped to the parameters of this convolution model. Assuming there are no singular components in the Hüsler–Reiß copula, the convolution model leads to exact and approximate simulation methods. An application of simulation is to check if the Hüsler–Reiß copula with different parsimonious dependence structures provides adequate fit to some data consisting of multivariate extremes.

Preface [13. international workshop on hadron physics, Angra dos Reis, RJ (Brazil), 22-27 March 2015

International Nuclear Information System (INIS)

2016-01-01

The Hadron Physics series of workshops, which started in 1988, take place every two or three years. They have the format of an advanced school, consisting of didactic courses, thematic seminars and the presentation of posters on frontier topics in the physics of strong interactions. It is characterized by the active participation of graduate students and postdocs, and also promotes collaboration between reserach groups in Latin America and others distributed worldwide. The XIII International Workshop on Hadron Physics - XIII Hadron Physics - was held from 22-27 March 2015, in Hotel do Bosque, Mambucaba, near the city of Angra dos Reis, Rio de Janeiro state. With good weather, a beach and splendid natural beauty, the surroundings offered all the conditions for a fruitful and pleasant meeting. The scientific program of the XIII Hadron Physics workshop was composed of courses, seminars and contributed papers. The courses consisted of four sets of lectures of three hours each, which are all reproduced in the present volume, thanks to the kind efforts of the lecturers, for the use and appreciation of a wider public. These courses provided a pedagogical and updated account of recent developments that gave support to the discussion of frontier problems in the physics of strong interactions. Organizers and participants are aware that the lecturers bore primary responsibility for the success of the workshop and are especially grateful to them. The seminars reviewed recent developments in theory, computational techniques and experimentations investigating QCD in nonperturbative and high density regimes. Most of these seminars are reproduced in this volume. The Organizing Committee is thankful to the invited speakers for the quality of the presentations, which contributed to the success of the workshop. The contributed papers, mainly representing the scientific activity of young physicists, were exhibited as posters all throughout the event in the breakout area, and are also

Insertion of the Biogenesis Factor Rei1 Probes the Ribosomal Tunnel during 60S Maturation.

Science.gov (United States)

Greber, Basil Johannes; Gerhardy, Stefan; Leitner, Alexander; Leibundgut, Marc; Salem, Michèle; Boehringer, Daniel; Leulliot, Nicolas; Aebersold, Ruedi; Panse, Vikram Govind; Ban, Nenad

2016-01-14

Eukaryotic ribosome biogenesis depends on several hundred assembly factors to produce functional 40S and 60S ribosomal subunits. The final phase of 60S subunit biogenesis is cytoplasmic maturation, which includes the proofreading of functional centers of the 60S subunit and the release of several ribosome biogenesis factors. We report the cryo-electron microscopy (cryo-EM) structure of the yeast 60S subunit in complex with the biogenesis factors Rei1, Arx1, and Alb1 at 3.4 Å resolution. In addition to the network of interactions formed by Alb1, the structure reveals a mechanism for ensuring the integrity of the ribosomal polypeptide exit tunnel. Arx1 probes the entire set of inner-ring proteins surrounding the tunnel exit, and the C terminus of Rei1 is deeply inserted into the ribosomal tunnel, where it forms specific contacts along almost its entire length. We provide genetic and biochemical evidence that failure to insert the C terminus of Rei1 precludes subsequent steps of 60S maturation. Copyright © 2016 Elsevier Inc. All rights reserved.

Environmental monitoring program for radiological emergencies at the Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro, Brazil

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

1997-12-31

In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra do Reis, Rio de Janeiro, the Emergency Response Team of the Institute of Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. A monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measure in case of a radiological accident is presented. For the selection of the monitoring points, the program takes into account atmospheric diffusion, population conglomerates and their habits, water and land use; it includes the entire Emergency Planning Zone of 15 km radius. The program has been organized in the form of a handbook to facilitate handling by field teams 2 refs., 1 fig.; e-mail: lilia at ird.gov.br

Uptake by benthic algae of critical radionuclides to be released in the liquid effluent of the Angra dos Reis Nuclear Power Plant, R.J., Brazil

International Nuclear Information System (INIS)

Guimaraes, J.R.D.

1982-06-01

In vitro interaction of benthic algae from the Angra dos Reis region, R.J., Brazil, was studied with critical radionuclides to be released in the liquid effluent of CNAAA (unit I). 137 Cs- 60 Co - and 125 I uptake and loss by Sargassum filipendula, Padina Vickersiae and Acanthophora Spicifera were observed. Biological half-lives and bioaccumulation factors (B.F.) were estimated. Co and I uptake were fast (apparent equilibrium in 3 to 7 days). Cs uptake was slower (2 to 3 weeks). Loss followed an inverse pattern (fast for Cs, slow for Co and I). B.F. ranged from 10 1 for Cs, to 10 3 for I and 10 3 -10 4 for Co. Higher B.F. for Co and I were found for P. vickersiae (up to 1,4 X 10 4 ) an A. spicifera (up to 7 X 10 3 ) respectively. These species represent important potential media for the transference of Co-I-and-to a much lesser extent - Cs isotopes, through food-webs. They exhibited high capacity to compete with local sandy sediments for the retention of Co and I. High B.F., rapid uptake and moderate to long biological half-lives enable S. filipendula, P. vickersiae and A. specifera to be powerful aids in the monitoring of radioactive contamination by Co and I isotopes. Since the majority of marine organisms tends to exhibit Cs B.F. similars to those reported here, these algae may also be used as monitors for Cs isotopes, the low B.F. being compensated by their abundance, wide distribution and facility of collection. (M.A.) [pt

A support vector machine designed to identify breasts at high risk using multi-probe generated REIS signals: a preliminary assessment

Science.gov (United States)

Gur, David; Zheng, Bin; Lederman, Dror; Dhurjaty, Sreeram; Sumkin, Jules; Zuley, Margarita

2010-02-01

A new resonance-frequency based electronic impedance spectroscopy (REIS) system with multi-probes, including one central probe and six external probes that are designed to contact the breast skin in a circular form with a radius of 60 millimeters to the central ("nipple") probe, has been assembled and installed in our breast imaging facility. We are conducting a prospective clinical study to test the performance of this REIS system in identifying younger women (detection of a highly suspicious breast lesion and 50 were determined negative during mammography screening. REIS output signal sweeps that we used to compute an initial feature included both amplitude and phase information representing differences between corresponding (matched) EIS signal values acquired from the left and right breasts. A genetic algorithm was applied to reduce the feature set and optimize a support vector machine (SVM) to classify the REIS examinations into "biopsy recommended" and "non-biopsy" recommended groups. Using the leave-one-case-out testing method, the classification performance as measured by the area under the receiver operating characteristic (ROC) curve was 0.816 +/- 0.042. This pilot analysis suggests that the new multi-probe-based REIS system could potentially be used as a risk stratification tool to identify pre-screened young women who are at higher risk of having or developing breast cancer.

Soil sampling in emergency situations

International Nuclear Information System (INIS)

Carvalho, Zenildo Lara de; Ramos Junior, Anthenor Costa

1997-01-01

The soil sampling methods used in Goiania's accident (1987) by the environmental team of Brazilian Nuclear Energy Commission (CNEN) are described. The development of this method of soil sampling to a emergency sampling method used in a Nuclear Emergency Exercise in Angra dos Reis Reactor Site (1991) is presented. A new method for soil sampling based on a Chernobyl environmental monitoring experience (1995) is suggested. (author)

António Reis and Margarida Cordeiro, eccentric filmmakers

Directory of Open Access Journals (Sweden)

Lucas Tavares Neves

2016-02-01

Full Text Available The international symposium "António Reis and Margarida Cordeiro, eccentric filmmakers" took place in Paris between the 3rd and the 4th of June, 2015. Speakers exchanged on the political, social and poetical aspects of the duo's cinematography, as well as on the reverberations of titles such as Jaime (1974 and Trás-os-montes (1976 on the Portuguese filmic landscape of the decades that followed.

Transient study of a PWR pressurizer

International Nuclear Information System (INIS)

Sotoma, H.

1973-01-01

An appropriate method for the calculation and transient performance of the pressurizer of a pressurized water reactor is presented. The study shows a digital program of simulation of pressurizer dynamics based on the First Law of Thermodynamic and Laws of Heat and Mass Transfer. The importance of the digital program that was written for a pressurizer of PWR, lies in the fact that, this can be of practical use in the safety analysis of a reactor of Angra dos Reis type with a power of about 500 M We. (author)

Biodosimetric analysis of medium pressure UV disinfection reactor treating unfiltered surface water

International Nuclear Information System (INIS)

Leinan, B.E.; Craik, S.A.; Smith, D.W.; Belosevic, M.

2002-01-01

Many small and medium-sized communities use chlorination of surface water as their sole treatment of potable water. Ultraviolet (UV) disinfection may offer these communities a cost effective treatment option for protection against pathogens not readily inactivated by chlorine. The effectiveness of UV reactors for microorganism reduction, however, is sensitive to UV dose delivery, which is in turn influenced by water quality characteristics. The effectiveness of a Calgon Carbon Inc. Sentinel medium-pressure UV reactor for microorganism reduction was determined using biodosimetry with two non-pathogenic indicator organisms - MS2 phage and Bacillus subtilis. Testing was conducted using low turbidity (<0.5 NTU) lake water characterized by relatively high absorbance in the UV range (UVT of approx. 87 to 88% at 254 nm). The efficiency of UV dose delivery in the reactor was determined for various operating conditions by calculating the normalized reductive equivalent irradiance (REI). With a single lamp in operation, the normalized REI measured with B. subtilis increased significantly when the flow rate through the reactor was increased from 380 L/min to 1140 L/min. This increase in reactor efficiency was believed to be due to improved reactor hydrodynamics and axial mixing that accompanied the higher flow rates. In contrast, treatment efficiency based on biodosimetry with MS2 phage was found to decrease with increasing flow rate when a single lamp was in operation. In general, treatment efficiency was greater when more than one adjacent lamp was in operation, suggesting that the influence of flow short-circuiting with single lamp operation. Differences between the outcomes observed with the two indicator microorganisms were not resolved, however, it was concluded that reactor efficiency was sensitive to both water flow rate and the number of adjacent lamps that were in operation. (author)

Soil sampling in emergency situations; Amostragem de solos em situacoes de emergencia

Energy Technology Data Exchange (ETDEWEB)

Carvalho, Zenildo Lara de [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil); Ramos Junior, Anthenor Costa [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Superintendencia de Licenciamento e Controle

1997-12-31

The soil sampling methods used in Goiania`s accident (1987) by the environmental team of Brazilian Nuclear Energy Commission (CNEN) are described. The development of this method of soil sampling to a emergency sampling method used in a Nuclear Emergency Exercise in Angra dos Reis Reactor Site (1991) is presented. A new method for soil sampling based on a Chernobyl environmental monitoring experience (1995) is suggested. (author) 15 refs.

Cinema, história pública e educação: circularidade do conhecimento histórico em Xica da Silva (1976) e Chico Rei (1985)

OpenAIRE

Rodrigo de Almeida Ferreira

2014-01-01

No contexto da educaçãA tese Cinema, história pública e educação: circularidade do conhecimento histórico em Xica da Silva (1976) e Chico Rei (1985) propõe compreender o filme de gênero histórico no que tange a mediação, divulgação e produção do conhecimento histórico, tanto em espaço escolar, quanto não-escolar. Problematiza-se esse gênero fílmico para o saber histórico a partir da análise dos imaginários sociais presentes nos filmes, construídas na interface entre a historiografia e outros ...

A Companhia de Reis Santa Luzia, Londrina/PR: considerações acerca do catolicismo tradicional popular brasileiro e o papel de seus mestres-rituais

Directory of Open Access Journals (Sweden)

André Camargo Lopes

2009-07-01

Full Text Available Este artigo é resultado de uma série deentrevistas realizadas com o mestreembaixadorAntonio Francisco, da Companhiade Reis Santa Luzia, assim como o trabalho deobservação participante da jornada de Reis2007/2008 que realizamos junto a Companhiapelos bairros do município de Londrina/PR.Temos por objetivo apontar neste artigo algunselementos que caracterizam o catolicismo tradicionalpopular brasileiro, em seu aspectocultural, configurando a partir desta perspectivaa formação de seus mestres-rituais e a estruturaritualística e organizacional da jornada deReis dentro deste universo cultural.

Efecto de dos metales pesados, cadmio y níquel, sobre la eficiencia de remoción de carga orgánica de un reactor UASB a escala de laboratorio

Directory of Open Access Journals (Sweden)

Luis Eduardo Forero

2004-01-01

Full Text Available Se realizaron ensayos en tres reactores UASB de tres litros cada uno, a un tiempo de retención hidráulico (TRH de cuatro horas y carga orgánica volumétrica de 4,8 g/L/d. Después de la fase inicial de arranque, tiempo de 4.000 horas para los tres reactores, se procedió a afectarlos de la siguiente forma: el primer reactor fue alimentado con 5 mg/L de cloruro de cadmio en forma continua, el segundo reactor fue alimentado con 10 mg/L de cloruro de níquel en forma continua también, mientras que el tercer reactor no se afectó con sustancia alguna y sirvió como control. La eficiencia de remoción de demanda química de oxígeno (DQO del primer reactor cambió del 60% de la fase de arranque (fase 1 al 18% en la fase afectada con cadmio (fase dos; la eficiencia de remoción de DQO en el reactor dos pasó del 60 al 24% y a su vez para el reactor tres control no hubo cambio significativo en dicha eficiencia. A su vez el reactor uno acumuló el cadmio en el lodo, mientras que el reactor dos no hizo lo propio con el níquel.

Does familiarity breed contempt or liking? Comment on Reis, Maniaci, Caprariello, Eastwick, and Finkel (2011).

Science.gov (United States)

Norton, Michael I; Frost, Jeana H; Ariely, Dan

2011-09-01

Reis, Maniaci, Caprariello, Eastwick, and Finkel (see record 2011-04644-001) conducted 2 studies that demonstrate that in certain cases, familiarity can lead to liking--in seeming contrast to the results of our earlier article (see record 2006-23056-008). We believe that Reis et al. (a) utilized paradigms far removed from spontaneous, everyday social interactions that were particularly likely to demonstrate a positive link between familiarity and liking and (b) failed to include and incorporate other sources of data-both academic and real-world-showing that familiarity breeds contempt. We call for further research exploring when and why familiarity is likely to lead to contempt or liking, and we suggest several factors that are likely to inform this debate. PsycINFO Database Record (c) 2011 APA, all rights reserved.

The CONNIE experiment

Energy Technology Data Exchange (ETDEWEB)

Aguilar-Arevalo, A.; et al.

2016-10-19

The CONNIE experiment uses fully depleted, high resistivity CCDs as particle detectors in an attempt to measure for the first time the Coherent Neutrino-Nucleus Elastic Scattering of antineutrinos from a nuclear reactor with silicon nuclei.This talk, given at the XV Mexican Workshop on Particles and Fields (MWPF), discussed the potential of CONNIE to perform this measurement, the installation progress at the Angra dos Reis nuclear power plant, as well as the plans for future upgrades.

Analytik von Minorlipiden: Ferulasäureester von Phytosterolen (gamma-Oryzanol) in Reis

OpenAIRE

Miller, Andreas

2005-01-01

Ferulasäureestern von Phytosterolen (γ-Oryzanol) werden antioxidative und cholesterinsenkende Eigenschaften zugeschrieben. Bisher beschriebene Methoden zur Analytik von γ-Oryzanol in Reis erforderten eine aufwendige Aufreinigung des Probenextrakts. In dieser Arbeit wurde basierend auf der on-line LC-GC eine Methode entwickelt, die die simultane Bestimmung von γ-Oryzanol-Gehalt und Sterylferulat-Verteilung ohne Aufreinigung des Probenextrakts erlaubt. Mit Hilfe der Technik wurden die natürlich...

Influence of marine sediments in the distribution of the main radionuclides of the effluent from the nuclear power plant Almirante Alvaro Alberto (Unit 1)

International Nuclear Information System (INIS)

Brugnara, Miriam

1977-01-01

This study aimed to: 1) Characterize bottom sediments of the Angra dos Reis region, in the dispersion area of the effluent of the central Almirante Nuclear Alvaro Alberto, Unit 1. 2) Determining the adsorption capacity of these sediments to the long half-life and mean radionuclides to be released in the reactor effluent in a higher concentration. 3) Estimate the fraction of the different studied radionuclides that will be immobilized in sediments. 4) Identify critical radionuclides available for food chain

Proposta de bioremediació de l'estany Olla del Rei de Castelldefels

OpenAIRE

Vidiella Martin, Maria

2017-01-01

The UPC campus and the Mediterranean Technology Park (PMT) is an educational and research site that includes a naturalized area that sets it apart: the lake called "Olla del Rei", included in the inventory of wetlands in Catalonia. The evolution of the system and the effects caused by the network of drainage channels connected to the lagoon, have generated huge problems that threaten the existence of the lake as a natural area: eutrophication and loss of quality of the water, the exponential ...

A História encenada: O Processo do Rei, de João Mario Grilo, a imagem melancólica de um país

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Tavares, Mirian

2014-04-01

Full Text Available This text analyses João Mário Grilo’s film: O Processo do Rei (The King’s Trial (1989. Based on the trial of Afonso VI, the director was able to remain faithful to the seventeenth century historical setting, but at the same time give it a contemporary feel, while exploring eternal and recurrent aspects of the story itself. Cinema, in this film, works as a stage where the story reveals the scenography that history books habitually conceal. In order to thoroughly examine the issues raised by this text, the article discusses the relationship between cinema and theatre starting with the concept of mise en scéne. What joins and separates these two artistic forms? How has cinema built its own mise en scéne throughout its history while resorting mostly to editing?En este texto analizaré la película O Processo do Rei (1989, de João Mário Grilo. Basado en el proceso contra D. Afonso VI, el realizador consiguió ser fiel al tiempo histórico –siglo XVII-, pero también profundamente contemporáneo, explorando aspectos eternos y cíclicos de la propia Historia. El cine, en esta película, funciona como un escenario donde la Historia revela la escenografía que los libros de Historia acostumbran a ocultar. Para profundizar en esta cuestión comienzo por discutir las relaciones entre el cine y el teatro a partir do concepto de mise en scéne. ¿Qué aproxima, y qué distancia, a estas dos formas artísticas? ¿De qué manera el cine, a lo largo de su historia, construyó su propia puesta en escena recurriendo, sobre todo, al montaje?

Entre tradição e modernidade: Almeida Reis eo Paraíba

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Alberto Martín Chillón

2014-11-01

Full Text Available Often highlighted are the modern features of some art works that caused them to be rejected in their time, such as the Paraíba, by Almeida Reis, 1866, set in Europe during the scholarship of the artist. In this paper, we analyze and question the modern or traditional character of this work, through its detailed study, its relationships and influences, its situation in the tradition of the subject represented, and the important fact that it was received into a very different artistic environment to the one in which it was created.

Reactor building 3D-model for evaluating the pressures on concrete regularization and foundation waterproofing membrane

Energy Technology Data Exchange (ETDEWEB)

Mello Junior, Glauco J.T.; Cardoso, Tarcisio de F.; Prates, Carlos L.M. [Eletrobras Termonuclear S.A. - ELETRONUCLEAR, Rio de Janeiro, RJ (Brazil). Gerencia de Analise de Tensoes GAN.T], e-mail: glauco@eletronuclear.gov.br, e-mail: tarci@eletronuclear.gov.br, e-mail: prates@eletronuclear.gov.br

2009-07-01

Angra dos Reis site in Brazil has already 2 operating PWR NPPs. Unit 3, with identical design to Unit 2, also a 1350 MW PWR, is expected to have its construction started in 2009. This new plant shall be founded directly on sound rock. The first step is to prepare this rock surface with a concrete regularization and a foundation waterproofing membrane. This study presents a 3D model approach of the corresponding reactor building to verify the maximum pressure acting on this surface. The 3D model permits to show a more realistic pressure distribution at every foundation specific detail. A static analysis is performed using ANSYS Mechanical Release 11.1. Dead weight, permanent and live loads, Safe Shutdown Earthquake (SSE) combined with Burst Pressure Wave (BPW) from the Feedwater Tank (SSB=SSE+BPW) and differences of temperature are taken into account. Considering all foundation nodes , the pressure distribution on the waterproofing membrane for each load case is obtained for vertical and horizontal directions, which corresponds to compression and tangential reaction loads. The maximum values occur in distinct positions for each load case. The maximum results are obtained according to DIN 25449 (2008) load combination criteria. The results are compared to a simplified analysis performed before, showing a good agreement in global values. (author)

Reactor building 3D-model for evaluating the pressures on concrete regularization and foundation waterproofing membrane

International Nuclear Information System (INIS)

Mello Junior, Glauco J.T.; Cardoso, Tarcisio de F.; Prates, Carlos L.M.

2009-01-01

Angra dos Reis site in Brazil has already 2 operating PWR NPPs. Unit 3, with identical design to Unit 2, also a 1350 MW PWR, is expected to have its construction started in 2009. This new plant shall be founded directly on sound rock. The first step is to prepare this rock surface with a concrete regularization and a foundation waterproofing membrane. This study presents a 3D model approach of the corresponding reactor building to verify the maximum pressure acting on this surface. The 3D model permits to show a more realistic pressure distribution at every foundation specific detail. A static analysis is performed using ANSYS Mechanical Release 11.1. Dead weight, permanent and live loads, Safe Shutdown Earthquake (SSE) combined with Burst Pressure Wave (BPW) from the Feedwater Tank (SSB=SSE+BPW) and differences of temperature are taken into account. Considering all foundation nodes , the pressure distribution on the waterproofing membrane for each load case is obtained for vertical and horizontal directions, which corresponds to compression and tangential reaction loads. The maximum values occur in distinct positions for each load case. The maximum results are obtained according to DIN 25449 (2008) load combination criteria. The results are compared to a simplified analysis performed before, showing a good agreement in global values. (author)

Commissioning of the nuclear power plant

International Nuclear Information System (INIS)

Furtado, P.M.; Rolf, F.

1984-01-01

Nuclear Power Plant Angra 2, located at Itaorna Beach-Angra dos Reis is the first plant of the Brazilian-German Agreement to be commissioned. The Nuclear Power Plant is a pressurized water reactor rated at 3765 Mw thermal/1325 Mw electrical. For commissioning purpose the plant is divided into 110 systems. Plant commissioning objective is to demonstrate the safe and correct operation of each plan component, system and of the whole plant in agreement with design conditions, licensing requirements and contractual obligations. This work gives a description of plant commissioning objectives, activities their time sequence, and documentation. (Author) [pt

De jure sacro: a inquisição nas vilas d'El Rei De jure sacro: the inquisition in the villages of the king

Directory of Open Access Journals (Sweden)

Maria Leônia Chaves de Resende

2011-06-01

Full Text Available Esse artigo tem por objetivo divulgar as denúncias registradas nos Cadernos do Promotor relativos a Minas Gerais, pertencentes ao fundo da Inquisição de Lisboa, depositados no Arquivo Nacional da Torre de Tombo/Portugal, com ênfase nos estudos de caso relativos a São João del-Rei e TiradentesThe purpose of this article is to make known the accusations registered in the Lisbon Inquisition's Cadernos do Promotor (Prosecutor'S Notebooks and the prosecuted cases pertaining to Minas Gerais, especially the villages of São João del-Rei and Tiradentes. These sources are deposited in Portugal's Arquivo Nacional da Torre de Tombo/Lisboa

O Rei Maia Kukulcán e seus discursos de propaganda política em Chichén Itzá

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Alexandre Guida Navarro

2013-08-01

Full Text Available Chichén Itzá foi um populoso centro urbano maia responsável por tributar centenas de cidades, organizar um exército eficaz para os empreendimentos guerreiros e realizar comércio de longa distância com outras cidades maias e de outras etnias. Durante seu auge, no século IX, a cidade foi governada por um rei chamado Kukulcán, que foi responsável pela maioria das construções arquitetônicas da cidade. Tal governo foi marcado por uma eficiente propaganda política que foi planejada segundo um processo cognitivo de representação imagética do governante, cuja principal manifestação deu-se em forma de uma serpente emplumada. Estas imagens serviram de propaganda política para perpetuar a soberania deste rei, além de ser um registro imagético de sua importância na memória coletiva desta cidade maia.

Linguagem fílmica: uma metáfora de comunicação para a análise dos discursos nas organizações

Directory of Open Access Journals (Sweden)

Alessandra Demite Gonçalves de Freitas

2015-03-01

Full Text Available O objetivo da pesquisa aqui relatada foi investigar a linguagem fílmica como metáfora de comunicação para a análise dos discursos nas organizações. Trata-se de uma pesquisa qualitativa, com uso da estratégia de análise fílmica. Os dados foram coletados por meio da observação indireta e não participante, registrados em protocolo de observação. Foi utilizada a estratégia de análise de discurso do personagem do Rei George VI no filme comercial/artístico O discurso do rei; a análise documental do filme documentário The king speaks - "The true story behind the film" e a análise de conteúdo da obra literária biográfica O discurso do rei - "Como um homem salvou a monarquia britânica". Nos resultados, reforçou-se que o uso da linguagem fílmica, nesta pesquisa, contribui para o entendimento do fenômeno da comunicação nas organizações. Seu uso cria a oportunidade de simulação a partir de cenas que podem ser comparadas com dados inseridos no contexto organizacional, como metáforas, desde que haja cuidado com a dimensão afetiva envolvida no processo de significação fílmica. Sua utilização torna-se conveniente, desde que não se permita a escolha do filme pelo filme e que haja um alinhamento entre o filme escolhido e o construto que se pretende investigar.

Leishmaniose tegumentar americana na Ilha Grande. Rio de Janeiro: V. Observações sobre a biologia dos transmissores em condiçoes naturais

Directory of Open Access Journals (Sweden)

Nelson A. de Araújo Filho

1981-12-01

Full Text Available Durante um surto de Leishmaniose Tegumentar Americana (LTA na Praia Vermelha, Ilha Grande, município de Angra dos Reis, Rio de Janeiro, foram coletados 4.192 exemplares de flebotomíneos em ambiente domiciliar e silvestre, com isca animal e outros abrigos naturais, durante o período de janeiro de 1976 a abril de 1977. Entre o total de 11 espécies coletadas encontraram-se 2.493 exemplares de Lutzomyia intermedia, 1.594 de Lutzomyia migonei e 105 exemplares de outras espécies. A L. intermedia apresentou densidade mais elevada no domicílio humano, enquanto a L. migonei apresentou coletas mais rendosas com iscas animais e galinheiros. O sinantropismo e a elevada densidade no ambiente domiciliar incriminam as espécies L. intermedia e L. migonei como as prováveis vetoras da LTA na Ilha Grande.During an outbreak of mucocutaneous leishmaniasis in Praia Vermelha, Ilha Grande (Great Island in the county of Angra dos Reis, State of Rio de Janeiro, 4.192 species of Phlebotomus were collected in domestic and wild environment with the use of animal baits and other natural shelters from January 1976 to April 1977. In a total of 11 species collected, 2.493 samples of Lutzomyia intermedia, 1.594 of Lutzomyia migonei and 105 samples of other species were found. The Lutzomyia intermedia presented a higher density in human dwellings, while the Lutzomyia migonei presented better results with animal baits and chicken-coops. The sinantropism and high density found in the houses incriminate the species L. intermedia and L. migonei as the probable vectors of Mucocutaneous Leishmaniasis in Ilha Grande.

Tradução de teatro grego: Édipo Rei, de Sófocles.

Directory of Open Access Journals (Sweden)

Tereza Virgínia Ribeiro Barbosa

2009-02-01

Full Text Available http://dx.doi.org/10.5007/2175-7968.2008v2n22p89 Tendo em vista a especificidade do texto teatral, debatemos quais os elementos desse gênero devem ser preservados na tradução; discutimos a importância de algumas metáforas-base e das materializações no texto poético teatral como fios condutores da tradução. Finalmente, focalizamos as aparições da metáfora da terra (gê na peça de Sófocles, Édipo Rei e suas eventuais substituições por outros termos.

Tradução de teatro grego: Édipo Rei, de Sófocles.

OpenAIRE

Barbosa, Tereza Virgínia Ribeiro

2009-01-01

http://dx.doi.org/10.5007/2175-7968.2008v2n22p89Tendo em vista a especificidade do texto teatral, debatemos quais os elementos desse gênero devem ser preservados na tradução; discutimos a importância de algumas metáforas-base e das materializações no texto poético teatral como fios condutores da tradução. Finalmente, focalizamos as aparições da metáfora da terra (gê) na peça de Sófocles, Édipo Rei e suas eventuais substituições por outros termos. Considering the specificity of theatrical t...

Establishment of criteria for classification of area remediation measures contaminated after an eventual radiation accident in Angra dos Reis, RJ, nuclear power plant; Estabelecimento de criterios para a classificacao de medidas de remediacao de areas contaminadas apos um eventual acidente nuclear na usina de Angra dos Reis (RJ)

Energy Technology Data Exchange (ETDEWEB)

Silva, Diogo Neves Gomes da

2016-07-01

When a radiological or nuclear accident that leads to the release of radioactive material to the environment occurs, it is important to implement protective and remediation measures in order to reduce human exposure to radionuclides. Therefore, it is necessary that the procedures to be chosen by the affected country authorities are the most efficient ones, which can only be defined based on previously established criteria. In Brazil, since the radiological accident in Goiania, in 1987, the development of tools to support decision-making in emergencies of this nature was started. The main objective of this work was to establish an acting basis for contaminated areas, in order to protect the individuals of public in case of any accident related to Almirante Alvaro Alberto nuclear power plant, in the municipality of Angra dos Reis (RJ), which leads to contamination to the environment and the consequent exposure of local population or from more distant regions to ionizing radiation. Initially, the high-risk areas near the location of the nuclear power plant were defined. Typical urban environments found in the main cities of these municipalities were surveyed, including homes, streets and recreation areas. The main characteristics of the study area were evaluated using images from Google Earth® and web pages of the municipalities. After the types of areas to be simulated were selected, these were quantified in terms of the number of residents, the size of the streets, and the number of trees, among others, per unit area. Considering the different housing characteristics for the selected municipalities, six main standard scenarios were developed for urban areas, including homes with different shielding, buildings and parks. The simulation of the procedures for each scenario was made with SIEM model, developed by the Institute of Radiation Protection and Dosimetry (IRD/CNEN), formed by the integration of various models including CORAL, focusing on agricultural areas

Structural Properties and UV-Visible Absorption Spectroscopy of Retinal-pyridyl-CN Re(I) Carbonyl Bipyridine Complex: A Theoretical Study.

Science.gov (United States)

Eng, Julien; Daniel, Chantal

2015-10-29

The structural, electronic, and optical properties of the all-trans and five cis conformers of [Re(CO)3(bpy)(ret-pyr-CN)](+) (bpy = 2,2'-bipyridine; ret-pyr-CN = pyridyl-CN-3,7-dimethyl-9-(2,6,6-trimethylcyclohex-2-n)-none-(2,4,6,8-tetraen) were studied in solvent by means of density functional theory (DFT) and time-dependent DFT. The isolated retinal-like chromophore ret-pyr-CN was investigated as well for comparison. By coordination to the complex the two lowest intraligand (IL) states localized on the retinal group are slightly red-shifted from 627 to 690 nm and from 415 to 450 nm, respectively. Several isomerization pathways are open upon irradiation of the Re(I) complex by visible light (400-450 nm), especially to two cis conformers corresponding to the isomerization of the two double bonds of the retinal-like ligand close to the pyridyl group linked to the Re(I) fragment. The metal-to-ligand charge transfer states localized either on the retinal group or on the bpy ligand should play a minor role in the isomerization process itself but could improve its efficiency via ultra-fast intersystem crossing.

Modelling of the tritium dispersion from postulated accidental release of nuclear power plants

International Nuclear Information System (INIS)

Soares, Abner Duarte; Simoes Filho, Francisco Fernando Lamego; Cunha, Tatiana Santos da; Aguiar, Andre Silva de; Lapa, Celso Marcelo Franklin

2011-01-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models to simulation of tritium dispersion caused by an accident in a Candu reactor located in the ongoing Angra 3 site. The Candu reactor is one that uses heavy water (D 2 O) as moderator and coolant of the core. It was postulated, then, the LOCA accident (without fusion), where was lost 66 m3 of soda almost instantaneously. This inventory contained 35 P Bq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m 3 ) during the first 14 days after the accident. (author)

Modelling of the tritium dispersion from postulated accidental release of nuclear power plants; Modelagem da dispersao de tritio a partir de liberacoes acidentais postuladas de centrais nucleares

Energy Technology Data Exchange (ETDEWEB)

Soares, Abner Duarte; Simoes Filho, Francisco Fernando Lamego; Cunha, Tatiana Santos da [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Aguiar, Andre Silva de; Lapa, Celso Marcelo Franklin, E-mail: asoares@cnen.gov.b, E-mail: flamego@ien.gov.b, E-mail: lapa@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2011-07-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models to simulation of tritium dispersion caused by an accident in a Candu reactor located in the ongoing Angra 3 site. The Candu reactor is one that uses heavy water (D{sub 2}O) as moderator and coolant of the core. It was postulated, then, the LOCA accident (without fusion), where was lost 66 m3 of soda almost instantaneously. This inventory contained 35 P Bq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m{sup 3}) during the first 14 days after the accident. (author)

Validación del modelo REI para medir la clase social en población adulta

Directory of Open Access Journals (Sweden)

Antonio Cabrera de León

2009-01-01

mayor riesgo de problemas de salud, con mayor fuerza en las mujeres: sedentarismo (OR = 1,8, obesidad (OR = 4,4, obesidad abdominal (OR = 5,4, síndrome metabólico (OR = 3,4 y diabetes mellitus (OR = 2,0. Conclusiones: REI es un indicador válido, no basado en la ocupación ni en la situación laboral, fácilmente estandarizable, apto para medir cuantitativamente la clase social en estudios que precisen analizar el impacto de la misma como determinante de salud.

Study on the marine fouling communities near Central Nuclear Almirante Alvaro Alberto (CNAAA), Angra dos Reis, R.J. (Brazil)

International Nuclear Information System (INIS)

Nunes, A.J.B.

1983-01-01

The effects of chemical and thermal effluents from CNAAA (Angra 1 Reactor) on local biota are studied. The seasonal variations and the ecologic aspects are presented and the biota is used as pollution indicator. The biota taxonomic study is desctibed. (M.A.C.) [pt

Olhos de inferno: a morte no Rei Édipo de Sófocles

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Ortep J. Trindade-Serra

1995-12-01

Full Text Available Os derradeiros versos do "Rei Édipo", de Sófocles, versos que se referem a um tópos consagrado, ocasionaram, através de uma paráfrase de Frínico, a criação do "mito" de Sófocles, cuja vida feliz a tradição consagrou como uma antítese do destino de seu personagem. O paradoxo desses versos, todavia, merece consideração mais profunda. Com efeito, em toda a tragédia a morte é representada de maneira paradoxal. Édipo faz a experiência de uma situação liminar em que morte e vida, cegueira e visão se confundem. Uma evidência disso é simbolicamente dada no verso 987 de Oedipus Rex.

Establishment of criteria for classification of area remediation measures contaminated after an eventual radiation accident in Angra dos Reis, RJ, nuclear power plant

International Nuclear Information System (INIS)

Silva, Diogo Neves Gomes da

2016-01-01

When a radiological or nuclear accident that leads to the release of radioactive material to the environment occurs, it is important to implement protective and remediation measures in order to reduce human exposure to radionuclides. Therefore, it is necessary that the procedures to be chosen by the affected country authorities are the most efficient ones, which can only be defined based on previously established criteria. In Brazil, since the radiological accident in Goiania, in 1987, the development of tools to support decision-making in emergencies of this nature was started. The main objective of this work was to establish an acting basis for contaminated areas, in order to protect the individuals of public in case of any accident related to Almirante Alvaro Alberto nuclear power plant, in the municipality of Angra dos Reis (RJ), which leads to contamination to the environment and the consequent exposure of local population or from more distant regions to ionizing radiation. Initially, the high-risk areas near the location of the nuclear power plant were defined. Typical urban environments found in the main cities of these municipalities were surveyed, including homes, streets and recreation areas. The main characteristics of the study area were evaluated using images from Google Earth® and web pages of the municipalities. After the types of areas to be simulated were selected, these were quantified in terms of the number of residents, the size of the streets, and the number of trees, among others, per unit area. Considering the different housing characteristics for the selected municipalities, six main standard scenarios were developed for urban areas, including homes with different shielding, buildings and parks. The simulation of the procedures for each scenario was made with SIEM model, developed by the Institute of Radiation Protection and Dosimetry (IRD/CNEN), formed by the integration of various models including CORAL, focusing on agricultural areas

Cucos, formigas, abelhas e a evolução dos instintos

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César Ades

Full Text Available Neste artigo, abordo o capítulo VII de "A Origem das Espécies" (Instinto, no qual Charles Darwin efetua uma aplicação da teoria da evolução por seleção natural ao domínio dos instintos, inaugurando a análise biológica do comportamento. Darwin pretendeu mostrar a possibilidade de uma evolução gradual no caso de exemplos complexos como o parasitismo de ninhada do cuco, o hábito escravagista de formigas e a construção das células do favo de abelhas melíferas. Atribuiu ao comportamento um caráter funcional, comparou espécies próximas para reconstituir etapas evolucionárias, colocou os cálculos de custo e benefício e de otimização subjacentes à seleção do comportamento, indicou aspectos de competição entre espécies e de manipulação de umas por outras, e utilizou o pensamento da seleção de grupo para dar conta da presença de indivíduos estéreis em insetos eusociais. Mais do que soluções e resultados, Darwin traz, no capítulo Instinto, argumentos e uma proposta paradigmática para a análise dos comportamentos típicos da espécie, verdadeiro ponto de partida para as abordagens atuais da etologia e da ecologia comportamental.

Detecção de ácido ocadaico em cultivo de mexilhões Perna perna, Angra dos Reis, RJ Okadaic acid detection in mussel cultivation Perna perna, Angra dos Reis, RJ

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Geisi Ferreira Mariné

2010-02-01

Full Text Available A ficotoxina ácido ocadaico (AO é produzida por um grupo de microalgas conhecidas como dinoflagelados. Os mexilhões, ao se alimentarem dessas microalgas, acumulam a toxina em sua glândula digestiva, desencadeando a Síndrome ou Envenenamento Diarreico por Moluscos (EDM no ser humano. Os sintomas se apresentam em torno de 30 minutos após o consumo do molusco contaminado, variando entre náuseas, dores abdominais, vômitos e diarreia. Quando a ingestão da toxina acontece em quantidades inferiores a 48µg g-1, os sintomas não se desenvolvem, porém seu consumo continuado favorece o surgimento de tumores no trato gastrointestinal em razão do poder carcinogênico do AO. Este estudo pretendeu detectar e quantificar a toxina diarreica AO em mexilhões Perna perna coletados entre os meses de maio e outubro de 2006. A detecção do AO nos mexilhões foi realizada por Cromatografia Líquida de Alta Eficiência com Detecção Fluorimétrica (CLAE-DF. Os resultados cromatográficos indicaram a presença da toxina AO em baixas concentrações, em todas as amostras de mexilhões obtidas de maio a outubro de 2006. Os resultados indicam a necessidade da elaboração e aplicação efetiva de um programa de controle higiênico-sanitário dos moluscos, assim como o monitoramento do ambiente aquático, objetivando, acima de tudo, a segurança da saúde pública.Okadaic acid (OA is a phycotoxin produced by a group of microalgae known as Dino-flagellates. When mussels feed themselves from this micro seaweed the toxin accumulates in their hepatopancreas, triggering the Syndrome or Diarrhetic Shellfish Poisoning (DSP in the human being. The symptoms appear around 30 minutes after the consumption of contaminated mussels and include abdominal nauseas, pains, vomits and diarrhea. When the toxin ingestion happens in amounts lower than 48µg g-1, the above described symptoms do not develop. However, the continued consumption favors the emergence of tumors in the

Essential learning tools for continuing medical education for physicians, geneticists, nurses, allied health professionals, mental health professionals, business administration professionals, and reproductive endocrinology and infertility (REI) fellows: the Midwest Reproductive Symposium International.

Science.gov (United States)

Collins, Gretchen G; Jeelani, Roohi; Beltsos, Angeline; Kearns, William G

2018-04-01

Essential learning tools for continuing medical education are a challenge in today's rapidly evolving field of reproductive medicine. The Midwest Reproductive Symposium International (MRSi) is a yearly conference held in Chicago, IL. The conference is targeted toward physicians, geneticists, nurses, allied health professionals, mental health professionals, business administration professionals, and reproductive endocrinology and infertility (REI) fellows engaged in the practice of reproductive medicine. In addition to the scientific conference agenda, there are specific sessions for nurses, mental health professionals, and REI fellows. Unique to the MRSi conference, there is also a separate "Business Minds" session to provide education on business acumen as it is an important element to running a department, division, or private clinic.

GERAÇÃO DE DRENAGEM ÁCIDA E DE CONTAMINAÇÃO POR METAIS PESADOS EM PERFIS DE SOLOS CONSTRUÍDOS EM ÁREA DE MINERAÇÃO DE CARVÃO

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Dioni Glei Bonini Bitencourt

2015-12-01

�reas IV e VII, apesar de proporcionar condições químicas favoráveis ao estabelecimento de culturas agrícolas, não evitaram a formação de drenagem ácida em profundidade. O processo de sulfurização e sua relação com a liberação de metais foi melhor caracterizado pela análise de componentes principais realizada nas áreas IV e VII, em razão da correlação entre pH e saturação por bases nos estéreis só se expressar em saturações por bases acima de 40 %, não observada nos materiais dos estéreis das áreas I e II.

As misericórdias e as transferências de bens: o caso dos Monteiros, entre o Porto e a Ásia (1580-1640

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Isabel dos Guimarães Sá

Full Text Available Resumo Os testamentos de dois mercadores da mesma família, envolvidos na viagem do Japão, Antônio e Domingos Monteiro, revelam um modo de vida marcado pela mobilidade entre vários territórios do Sudeste Asiático, transacionando grande variedade de produtos. Por meio de sua rede de relações, é possível discernir a presença de parentes seus, sobretudo sobrinhos, e de outros negociantes portuenses, sugerindo que o modelo português de emigração para o Brasil já estava em ação no Oriente. Embora a transmissão de bens competisse aos provedores dos defuntos e ausentes, as misericórdias transferiam capitais de defuntos para a metrópole, em detrimento dos agentes diretos do rei, embora fosse impossível evitar a ingerência destes últimos. Apesar da vontade em fazer chegar o dinheiro à metrópole rapidamente para convertê-lo em padrões de juro, conveniências do trato, a burocracia régia e litígios sucessórios tornavam moroso o processo de transferência.

Rivalidade das casas reinantes hispano-lusas na divisão do mar oceano, conquista da América e apossamento do Brasil

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Edmundo M. Genófre

1960-03-01

Full Text Available Acompanhadas de documentos extraídos diretamente dos arquivos espanhóis acêrca da divisão e repartição do mar oceano, da conquista da América bem como da carta de Dom Manuel, rei de Portugal, que assinalou na Europa a posse oficial do Brasil.

GEOMORFOLOGIA E SEDIMENTOLOGIA GLACIAL APLICADAS NA RECONSTRUÇÃO DA EVOLUÇÃO DO AMBIENTE DE DEGLACIAÇÃO DA GELEIRA WANDA, ILHA REI GEORGE, ANTÁRTICA

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Kátia Kellem Rosa

2010-09-01

Full Text Available Este artigo apresenta resultados das atividades de campo realizadas durante o OPERANTAR XXVI, no verão de 2007/2008, ao longo da área de deglaciação da geleira Wanda, ilha Rei George, Antártica. A geleira tem apresentado retração glacial nas últimas décadas, resultando num ambiente sedimentar, com a exposição de várias geoformas e depósitos. Esses registros geomorfológicos são úteis para a reconstrução da evolução deste ambiente de deglaciação. Os dados foram obtidos através da análise em laboratório dos sedimentos coletados em campo e posterior fotointerpretação de fotos aéreas (2003 na escala de 1:50.000, fornecidas pelo SHOA/SAF (Servicio Hidrográfico y Oceanográfico de la Armada de Chile/ Servicio Aéreo Fotogramétrico, juntamente com a análise de imagens de satélites SPOT de diferentes anos. Os resultados mostram distintas fases de deglaciação para a geleira Wanda com uma aceleração de sua retração e perda de espessura nas últimas décadas. Registros sedimentares também indicam que a geleira possui regime termal basal úmido.

Integrity evaluation of the pressure vessels of Angra-2 and Angra-3 reactors by stress analysis

International Nuclear Information System (INIS)

Gomes, E.

1978-01-01

The integrity of the reactor pressure vessel of the unit II/III of the Nuclear Power Station at 'Angras do Reis' is evaluated by stress analysis, through the dynamics relaxation method. For the solution of the problem an axisymmetric model is fixed. Initially, the data of the Oak Ridge Vessel V-7 is compared with those obtained by two computer programs used in this study. The methods used in the computer programs are FEM and DEM. A11 the results are compared with the ASME Code Section III 1974 edition. The range deviation is determined to 99% confidence limit, in order to minimize the error probabilities. Finally, the equivalent intensity stress obtained is calculated and compared with the acceptable values of the ASME Code Section III, 1974 edition [pt

Sobre a relação entre Rei, Lei e Parlamento no Antigo Regime

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Alexander Martins Vianna

2010-09-01

Full Text Available Este ensaio pretende desenvolver um entendimento sobre as relações mutáveis entre Rei, Lei e Parlamento na Inglaterra, entre a “Grande Matéria” (1532-1535 de Henrique VIII e a Guerra Civil Inglesa (meados do século XVII, que as situe adequadamente nos caracteres institucionais (práticos e doutrinais do Antigo Regime, rompendo com a chave de leitura da historiografia liberal que, desde o século XIX, tende a essencializar uma espécie de distinção histórica entre Inglaterra e França, como se fossem protótipos, respectivamente, de “contratualismo” e “absolutismo”.

Leishmaniose tegumentar americana na Ilha Grande. Rio de Janeiro: V. Observações sobre a biologia dos transmissores em condiçoes naturais

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Nelson A. de Araújo Filho

1981-12-01

Full Text Available Durante um surto de Leishmaniose Tegumentar Americana (LTA na Praia Vermelha, Ilha Grande, município de Angra dos Reis, Rio de Janeiro, foram coletados 4.192 exemplares de flebotomíneos em ambiente domiciliar e silvestre, com isca animal e outros abrigos naturais, durante o período de janeiro de 1976 a abril de 1977. Entre o total de 11 espécies coletadas encontraram-se 2.493 exemplares de Lutzomyia intermedia, 1.594 de Lutzomyia migonei e 105 exemplares de outras espécies. A L. intermedia apresentou densidade mais elevada no domicílio humano, enquanto a L. migonei apresentou coletas mais rendosas com iscas animais e galinheiros. O sinantropismo e a elevada densidade no ambiente domiciliar incriminam as espécies L. intermedia e L. migonei como as prováveis vetoras da LTA na Ilha Grande.

The efficiency of two anaerobic reactor components; Eficiencias de dos componentes de un reactor anaerobio

Energy Technology Data Exchange (ETDEWEB)

Vazquez Borges, E.; Mendez Novelo, R.; Magana Pietra, A. [Facultad de Ingenieria. Universidad de Yucatan (Mexico); Martinez Pereda, P.; Fernandez Villagomez, G. [Universidad Nacional Autonoma de Mexico. Division de Estudios de posgrado de la Facultad de Ingenieria. Mexico (Mexico)

1997-09-01

This study examined the behaviour of an anaerobic digester in treating pig farm sewage. The experimental model consisted of a UASB reactor at the bottom and a high-rate sedimentator at the top with a total capacity of 534 litres. The digester was installed on a pig farm and its performance under different operating conditions was determined, with hydraulic retention time (HRT) as the critical parameter for evaluating the anaerobic system`s efficiency. The results obtained during the experiment to establish the critical operating parameters are reported. The organic loads applied for a HRT of 1 day were 7.3 kg/m``3/day of total DQO and 3 kg/m``3/day of soluble DQO, following organic matter removal rates (as total DQO) of 36% and 49% respectively and removal rates (as soluble DQO) of 74% in the UASB and 8% in the sedimentator. The efficiency of the reactor as a whole at this HRT time was a removal rate of 74% of total DQO and 75% of soluble DQO. (Author) 25 refs.

Folia de Reis não é folia de rádio Off the radio: preserving popular culture in São Paulo

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Mônica de Carvalho

2010-12-01

Full Text Available O objetivo deste artigo é analisar o sentido da preservação da Folia de Reis no distrito da Freguesia do Ó, Zona Norte da cidade de São Paulo, tomando como contraponto o evento Revelando São Paulo, que, organizado pelo governo do estado, também tem por objetivo a preservação da cultura popular tradicional paulista. Tomando como referência teórico-metodológica o debate iniciado nos anos de 1940 entre Florestan Fernandes e os folcloristas, a intenção é demonstrar que naquela figuração o que está em disputa é o sentido mesmo de preservação e, mais do que isso, o seu próprio objeto.This article explores the meaning of attempts to preserve the Folia de Reis (Revelry of the Wise Men in the district of Freguesia do Ó, in the north of São Paulo city. As a counterpoint, it analyzes the event Revelando São Paulo (Revealing São Paulo, organized by the State Government, which also looks to preserve São Paulo's traditional popular culture. Using the debate between Florestan Fernandes and the folklorists, initiated in the 1940s, as a theoretical and methodological starting point, the article aims to demonstrate that what is being disputed in the former's figuration is not only the meaning of preservation but, more importantly, how the preservation itself is achieved.

CARACTERIZAÇÃO GEOMORFOLÓGICA DAS ÁREAS LIVRES DE GELO EM RESPOSTA DA TENDÊNCIA DE RETRAÇÃO DA GELEIRA POLAR CLUB, PENÍNSULA POTTER, ILHA REI GEORGE, ANTÁRTICA

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Betânia Bonada

2018-01-01

Full Text Available Este trabalho objetiva investigar a dinâmica geomorfológica glacial das áreas livres de gelo na Península Potter, Ilha Rei George, Antártica, em resposta à recente retração da geleira Polar Club. O mapeamento geomorfológico e a interpretação da evolução dos sistemas lacustres entre 2006 e 2011 das áreas livres de gelo na Península Potter foi realizado através da interpretação visual em uma imagem Quickbird (RGB432, em imagens COSMO-SkyMed polarizações VV e HH em modo spotlight processadas com filtros espaciais e perfis topográficos. Também foram considerados os aspectos morfométricos da península, interpretados através da geração de mapas de hipsometria, declividade, curvas de nível e sombreamento. A variação frontal da geleira Polar Club entre os anos de 1981 a 2015 foi obtida pela análise temporal de imagens Landsat. O mapeamento geomorfológico da Península Potter evidenciou os processos geomorfológicos proglaciais e o padrão de disposição espacial das feições lineares marginais ao gelo, como cordões morâinicos e feições glaciofluviais (relacionadas ao aporte da fusão sazonal da neve e do gelo, bem como terraços marinhos, ravinas e afloramentos rochosos. O modelo de evolução da variação frontal da geleira Polar Club indica que condição de último avanço glacial registrado pela geomorfologia proglacial pode estar relacionado à Pequena Idade do Gelo e que houve um contínuo processo de retração desde então. Entre 1981-2015 evidenciou-se a redução de área de 2,95km² para a geleira Polar Club (perda de área total de 9,4%. Este processo pode estar relacionado com a tendência de aumento das temperaturas médias do ar, a tendência de aumento de dias com precipitação líquida no verão e o número de dias em que a temperatura média ultrapassou os 0°C na região nas últimas décadas. O recuo da geleira Polar Club é pouco expressivo quando comparado a outras geleiras da Ilha Rei George

A miopia da eficiência entrevista com Fábio Wanderley Reis

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Marcos Antônio Lopes

2004-12-01

Full Text Available Fábio Wanderley Reis é professor emérito da Faculdade de Filosofia e Ciências Humanas da Universidade Federal de Minas Gerais. Doutor em Ciência Política pela Universidade Harvard, é organizador de trabalhos de relevo como A democracia no Brasil: dilemas e perspectivas, com Guillermo O'Donnell. Por seu Política e Racionalidade, foi ganhador do Prêmio Anpocs, como melhor obra científica em Ciências Humanas. Seus livros mais recentes são Mercado e Utopia (Edusp, 2000 e Tempo Presente (Editora UFMG, 2002.Obra labiríntica, por sua riqueza temática-uma visão panorâmica da política brasileira no último quarto de século -, Tempo Presente, resenhado por Mediações, revela-nos o alcance da atividade intelectual de um pensador dotado de vasta cultura política e de apurado grau de sofisticação analítica.Aposentado há alguns anos, depois de ensinar por mais de três décadas, ele tem participado ativamente do debate público. Os principais veículos de nossa grande imprensa têm dado destaque ao rigor crítico de suas idéias. Observador arguto da cena política brasileira atual, Fábio Wanderley concedeu a seguinte entrevista a Mediações.

Friar José Teixeira advocate of Venice False: Sebastianism and political culture in the seventeenth century

OpenAIRE

Athaide, Filipe Duret

2017-01-01

Este artigo tem como objetivo analisar a participação do dominicano português José Teixeira na trama do Falso d. Sebastião de Veneza. Condenado à morte em 1603, o falso rei veneziano foi um dos mais significativos casos de falsos reis portugueses ocorridos durante a União Ibérica (1580-1640). Por sua vez, o envolvimento de Frei Teixeira no caso, e a consequente publicação das “Adventures admirables” em Paris no ano de 1601, contribuíram para o estabelecimento e fixação do sebastianismo letrad...

Comparison of efficiency and reproductive aptitude indexes between a reference and field strains of the cattle tick Rhipicephalus (Boophilus microplus, in Sinaloa, Mexico Comparação dos índices de eficiência e aptidão reprodutiva entre uma cepa de referência e outra de campo do carrapato do gado, Rhipicephalus (Boophilus microplus, em Sinaloa, México

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Soila Gaxiola-Camacho

2009-12-01

Full Text Available The objective of this work was to study the reproductive behavior of two strains of R. (B. microplus, one wild-caught (Native and one reference strain (Media Joya for two years, measuring the reproductive efficiency index (REI and reproductive aptitude index (RAI. Engorged ticks from each strain were collected monthly from February 2002 to February 2004. These were weighed and kept in the laboratory until egg-laying. Oogenic masses were individually weighed and incubated until larvae emergence. REI and RAI were calculated from each sample, grouping ticks by weight in 100 mg range classes. An analysis of variance and Duncan's multiple rank tests were carried out on the data (P O objetivo deste trabalho foi estudar a conduta reprodutiva de duas cepas de R. (B. microplus, uma coletada no campo (Nativa e outra de referência (Média Jóia, por dois anos, calculando o índice de eficiência reprodutiva (REI e o índice de aptidão reprodutiva (RAI. Foram coletados mensalmente carrapatos fêmeas engurgitadas de cada cepa no período de Fevereiro de 2002 a Fevereiro de 2004. Estas foram pesadas e conservadas no laboratório até ovipositar. As massas de ovos foram pesadas individualmente e incubadas até a eclosão das larvas. O REI e o RAI foram calculados para cada coleta, agrupando os carrapatos em classe de peso de 100 mg. Os dados foram submetidos a uma análise de variância e prova de classe múltipla de Duncan (P < 0,05. Foram calculados os coeficientes de correlação de Pearson (P < 0,01 para estimar a associação entre o peso dos carrapatos engurgitados e o peso e número de ovos postos e eclosionados. A cepa Nativa mostrou um peso ao engurgitamento mais alto do que a cepa Média Jóia. Os valores de REI e de RAI em ambas cepas foram similares em todos as classes de peso, mostrando tendência cuadrática na Média Jóia e linear-cuadrática na cepa Nativa (P < 0,05. Ambos os índices por classe de peso no engurgitamento foram sempre mais

A justiça e a produção do direito em Castela no século XV = Justice and Law production in Castille in Century XV

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Vidotte, Adriana

2011-01-01

Full Text Available O reinado dos Reis Católicos – Fernando de Aragão e Isabel de Castela – (1474-1504 se situa no período de transição da Idade Média para a Idade Moderna e foi considerado um período de paz e justiça em Castela. Isto nos possibilita questionar sobre as implicações, para o direito, da organização de um reino em uma era de transição. Propomos verificar o que caracteriza a passagem de um direito medieval para um direito moderno, e quais os elementos que indicam essa transição no governo dos Reis Católicos. Enfatizamos duas prerrogativas principais, uma de tradição medieval, a de juiz, e outra de caráter moderno, a legislativa, que se encerram na figuras de Fernando e Isabel

Development phase of corrosion program in aquatic ecosystems

International Nuclear Information System (INIS)

Moreira, P.A.

1983-01-01

Providences adopted to implantation of corrosion program in aquatic ecosystems, developed by CDTN, NUCLEN and FURNAS are presented. The area, the atmospheric exposition station of Angra dos Reis, the marine floating, the material to test specimen and its preparation are described. (C.M.) [pt

Pangim, a capital do Estado de Goa. Por espaços da lusofonia.

OpenAIRE

Fonseca, Maria do Céu

2007-01-01

Passado o tempo dos reis e dos impérios, os bilhetes postais são outros. Paraíso tropical, jóia da Índia, pérola do Oriente em cenários de recatadas pousadas e resorts de luxo mais do que asiático, são agora os jargões correntes do Lonely Planet ou Footprint, que susbstituem o antigo guião do escrivão de Cananor.

Homens de letras e homens de leis ao serviço da monarquia portuguesa (séculos XII-XIII

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Armando Norte

2014-06-01

Full Text Available Ao longo da primeira dinastia, os letrados ao serviço da Coroa portuguesa desempenharam um papel decisivo e cada vez mais importante na afirmação do poder real. Homens de leis e homens de letras serviram à casa real como oficiais, representaram os reis portugueses em atos políticos e diplomáticos e exerceram um grande leque de funções na esfera da administração central - políticas, jurídicas, médicas, económicas, administrativas. A presença desses elementos ao lado dos monarcas fez-se sentir desde a fundação do reino, logo desde o reinado de D. Afonso Henriques, coincidindo o corolário deste processo de recrutamento com a chegada de D. Afonso III ao trono, numa política continuada, de forma firme, por D. Dinis. O conjunto de eruditos recenseados junto dos reis portugueses da época fundacional constitui, nessa medida, um interessante estudo de caso para compreender, em parte, em que consistia um círculo áulico, à luz dos valores do século XII e XIII.

Preservação do Patrimônio Arquitetônico e Urbano em São João Del Rei, Brasil: apontamentos sobre a atuação do Conselho Municipal de Preservação do Patrimônio Cultural .

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Daniela Abritta Cota

2012-11-01

Full Text Available Este artigo busca refletir sobre a gestão do patrimônio arquitetônico e urbano em São João Del Rei, MG – Brasil, a partir das práticas empreendidas pelo Conselho Municipal de Preservação do Patrimônio Cultural (CMPPC, considerando a sua efetiva atuação no âmbito municipal. Inicialmente será apresentada uma reflexão teórico-conceitual sobre os condicionantes para intervenções urbanas em contextos com significativo patrimônio cultural, seguida da evolução da política patrimonial no Brasil. Posteriormente será dada ênfase ao estudo de caso de São João Del Rei.

Radionuclide dispersion and hydrodynamics of Ilha Grande Bay (Angra dos Reis, RJ) simulated from hypothetical accidental releases of liquid wastes

International Nuclear Information System (INIS)

Simoes Filho, Fernando Lamego; Lapa, Celso Marcelo Franklin; Aguiar, Andre Silva; Soares, Abner Duarte

2011-01-01

This study has the aim to assess the impact of accidental release of radionuclides postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamic circulation and transport for the simulation of tritium dispersion caused by an accidental release in Ilha Grande Bay from the site of the future third plant in two circulation scenarios. The main difference between the scenarios is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1 x 10 9 to 5 x 10 5 Bq/m³ close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (< 11 kBq/m³). (author)

AS AULAS RÉGIAS E OS SALÁRIOS DOS PROFESSORES NO PERÍODO DE REORGANIZAÇÃO DOS ESTUDOS (MINAS GERAIS, 1795-1800

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Cleide Cristina Oliveira

2012-10-01

Full Text Available RESUMO:Em 1777 D. Maria I assumiu o trono de Portugal. Todavia, a rainha fora afastada do poder por se encontrar em um estado de insanidade mental e, durante a regência de seu filho D. João, iniciada em 1792, suas determinações sofreram uma inflexão. Sob um contexto de crise econômica, houve uma tentativa de reorganização das escolas, baseada em um processo de centralização administrativa. A partir deste contexto é que analisamos os temas discutidos neste artigo: a disseminação das aulas régias na Capitania de Minas Gerais e os salários dos professores. Para tanto, tomamos como fontes de pesquisa documentos oficiais, produzidos entre 1795 e 1800. Identificamos as aulas de Primeiras Letras e de Gramática Latina como as mais numerosas e, ainda, que nem sempre as escolas oficialmente autorizadas funcionavam. Os valores dos salários dos mestres eram diferenciados conforme a especialidade ensinada: Filosofia (460$000 réis anuais, Retórica (440$000, Gramática Latina (400$000 e Primeiras Letras (150$000. No final do século XVIII, havia professores que não recebiam os salários integralmente e muitos que não recebiam absolutamente nada há anos. Os professores de Primeiras Letras eram os que possuíam salários atrasados com maior frequência e, mesmo assim, continuavam a exercer suas atividades.PALAVRAS-CHAVE: aulas régias; reorganização dos estudos; salários de professores.ABSTRACT: In 1777 Queen Mary I took the throne of Portugal. However, the queen was removed from power because he is in a state of insanity and, during the regency of his son King John, started in 1792, its provisions have undergone a shift. Under a context of economic crisis, there was an attempt to reorganize the schools, based on an administrative centralization process. From this context is that we analyze the issues discussed in this article: the spread of royal schools in Minas Gerais captaincy and teacher salaries. To this end, we take as research

Estudo observacional do comportamento empreendedor de Irineu Evangelista de Sousa da ótica de Filion no filme "Mauá - o Imperador e o Rei"

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Fátima Regina Ney Matos

Full Text Available Análise do comportamento empreendedor de Irineu Evangelista de Sousa, observado no filme "Mauá - O Imperador e o Rei". Procurou-se usar como base argumentativa o trabalho de Louis Jacques Filion (2004, 2000, 1993, 1991 sobre características empreendedoras básicas - inovação, aprendizagem, rede de relações e visão. A escolha do tema deveu-se ao pouco conhecimento dos alunos de graduação e pós-graduação em administração - detectado em uma pesquisa exploratória informal - sobre os empreendedores brasileiros e seu papel na evolução econômica do país, sendo relevante este resgate histórico. Após cinco exibições coletivas e algumas exibições individuais do filme, foi realizado um estudo observacional, tipo de observação de "segunda mão", indireta e não participante, com produtivas discussões em equipe. Na revisão bibliográfica buscou-se contextualizar, de maneira sucinta, as características do comportamento empreendedor da ótica de Filion (1991. Pode-se concluir que as características empreendedoras propostas na tipologia do autor apresentam-se com vigor no comportamento do Barão de Mauá, um homem à frente de seu tempo e que procurou contribuir na construção de um novo projeto para o Brasil, possibilitando a transição de um modelo econômico agrário exportador e escravocrata para uma economia de mercado baseada na industrialização, no trabalho assalariado e na livre iniciativa, sendo esse conhecimento essencial para o desenvolvimento do senso crítico e analítico do aluno.

International topical meeting on research reactor fuel management (RRFM) - United States foreign research reactor (FRR) spent nuclear fuel (SNF) acceptance program: 2010 update

International Nuclear Information System (INIS)

Messick, C.E.; Taylor, J.L.; Niehus, M.T.; Landers, C.

2010-01-01

The Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel, adopted by the United States Department of Energy (DOE), in consultation with the Department of State (DOS) in May 1996, scheduled to expire May 12, 2016, to return research reactor fuel until May 12, 2019 to the U.S. is in its fourteenth year. This paper provides a brief update on the program, part of the National Nuclear Security Administration (NNSA), and discusses program initiatives and future activities. The goal of the program continues to be recovery of U.S.-origin nuclear materials, which could otherwise be used in weapons, while assisting other countries to enjoy the benefits of nuclear technology. The NNSA is seeking feedback from research reactor operators to help us understand ways to include eligible research reactors who have not yet participated in the program. (author)

Preliminary version of corrosion program to be done among CDTN, NUCLEN and FURNAS

International Nuclear Information System (INIS)

Moreira, P.A.P.

1982-01-01

The corrosion at atmospheric exposition Program developed by CDTN (Centro de Desenvolvimento da Tecnologia Nuclear) in galvanized materials, that serve as model for implantation a similar Program in Angra dos Reis area is presented. A materials list that will be tested and necessary costs to project elaboration are still presented. (C.M.) [pt

Tiit Kask, Aldur Vunk (Hrsg.): Reis (nõukogude) läände / Journey to the [Soviet] west. Kuurortlinn Pärnu 1940-88. Artiklite kogumik / Resort town of Pärnu 1940-88. Collection of articles, Pärnu: Pärnu Linnavalitsus 2009, 121 S., 97 Abb. / Andr

Index Scriptorium Estoniae

Fülberth, Andreas

2011-01-01

Raamatuarvustus: Reis (nõukogude) läände : kuurortlinn Pärnu 1940-88 : artiklite kogumik = Journey to the [Soviet] West : resort town of Pärnu during 1940-88 : collection of articles. Pärnu, 2009

DOS.

Science.gov (United States)

Traven, Bill

1988-01-01

Discusses using the DOS PATH command (for MS-DOS) to enable the microcomputer user to move from directory to directory on a hard drive. Lists the commands to be programed, gives examples, and explains the use of each. (MVL)

primary spinal cord mansoni schistosomiasis : a case report

African Journals Online (AJOL)

3 dos Reis FR, Brito JC, Costa MD et al. Brown-Sequard syndrome in schistosomiasis. Report of a Case. Arq Neuropsiquiatr 1993; 51:281-4. 4 Ikhayat RA, Girgis M. Bilharzial granuloma of the conus: case report. Neumurgwy 1993; 32:1022-4; discussion 10224. 5 Ferrari TC, Moreira PR, Oliveria RC, Ferrari ML, Gazinelli G,.

A expedição portuguesa ao Brasil em 1501-1502 e Amerigo Vespucci

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Thomaz Oscar Marcondes de Souza

1960-07-01

Full Text Available O único cronista português que dá notícia do envio, pelo rei D. Manuel, de uma expedição exploradora ao litoral brasileiro em 1501 é Antônio Gaivão, na sua obra publicada em Lisboa em 1563 sob o título: Tratado dos Descobrimentos.

Dinâmica Glacial e Características Sedimentares Resultantes na Zona Proglacial da Geleira Ecology-Baía do Almirantado, Ilha Rei George Antártica.

OpenAIRE

Kátia Kellem Rosa; Rosemary Vieira; Jefferson Cardia Simões

2006-01-01

A geleira Ecology, localizada na ilha Rei George, ilhas Shetlands do Sul, está sofrendo um processo de rápida retração ao longo das últimas décadas, sendo que no período de 1956 a 1992/95 a geleira retrocedeu 0,37 Km2. Isto gerou um ambiente de deglaciação, com a exposição de várias geoformas na zona proglacial. Este trabalho objetiva estudar o ambiente de deglaciação da zona proglacial da geleir...

A disputa entre o Papa Bonifácio VIII e o Rei Filipe IV no final do século XIII

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Strefling, Sérgio Ricardo

2007-01-01

Full Text Available A questão das relações entre Igreja e Estado provocou debates prolongados e acesos, principalmente durante a idade média, no momento em que a igreja, dotada de um domínio próprio temporal, encontrava-se em convívio com o Sacro Império Romano que abraçava os mesmos súditos e apoiava-se sobre bases jurídicas derivadas do Cristianismo. Sob tal situação ainda era possível manter uma diferenciação entre estado e Igreja? No presente estudo, apresentaremos a polêmica causada pela teoria do Papa Bonifácio VIII no conflito com o Rei Filipe, o Belo. Daí surgem três documentos importantes, entre eles, a Bula Unam Sanctam

História da Palestina nos tempos do Novo Testamento (VI

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D. João Mehlmann O.S.B.

1961-09-01

Roma tolerava o instituto dos reis e príncipes aliados, porque êstes, geralmente em caráter vitalício, precediam a nomeação de governadores romanos, depois de preparados os respectivos territórios para serem definitivamente incorporados ao sistema provincial romano (n. 230 . Ora, a incumbência principal dos governadores romanos era, evidentemente, a manutenção da paz e da ordem em suas respectivas provín-cias, e, conforme o caso, a defesa das fronteiras do Império.

Uso de detectores de neutrinos para el monitoreo de reactores nucleares Uso de detectores de neutrinos para el monitoreo de reactores nucleares

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Gerardo Moreno

2012-02-01

Full Text Available Se estudia la factibilidad del uso de los detectores de antineutrinos para el monitoreo de reactores nucleares. Usando un modelo sencillo de cascada de fisión a dos componentes, se ilustra la dependencia del número de antineutrinos detectados a una distancia L del reactor según la composición nuclear del combustible. Se explica el principio de detección de neutrinos de reactores en base al decaimiento beta inverso y se describe como los detectores de neutrinos pueden emplearse para el monitoreo de la producción de materiales fisibles en el reactor. Se comenta como generalizar este análisis al caso real de un reactor nuclear in situ y uno de los principales experimentos internacionales dedicados a este propósito. We study the feasibility to use antineutrinos detectors for monitoring of nuclear reactors. Using a simple model of fission shower with two components, we illustrate how the numbers of antineutrinos detected at a distance L from the reactor depend on the composition of the nuclear combustible. We explain the principles of reactor neutrino detection using inverse beta decays and we describe how neutrinos detectors can be used for monitoring the production of fissile materials within the reactors. We comment how to generalize this analysis to the realistic case of a nuclear reactor in situ and one of the main international experiments dedicated to study the use of neutrinos detectors as nuclear safeguards.

The reactor physics computer programs in PC's era

International Nuclear Information System (INIS)

Nainer, O.; Serghiuta, D.

1995-01-01

The main objective of reactor physics analysis is the evaluation of flux and power distribution over the reactor core. For CANDU reactors sophisticated computer programs, such as FMDP and RFSP, were developed 20 years ago for mainframe computers. These programs were adapted to work on workstations with UNIX or DOS, but they lack a feature that could improve their use and that is 'user friendly'. For using these programs the users need to deal with a great amount of information contained in sophisticated files. To modify a model is a great challenge. First of all, it is necessary to bear in mind all the geometrical dimensions and accordingly, to modify the core model to match the new requirements. All this must be done in a line input file. For a DOS platform, using an average performance PC system, could it be possible: to represent and modify all the geometrical and physical parameters in a meaningful way, on screen, using an intuitive graphic user interface; to reduce the real time elapsed in order to perform complex fuel-management analysis 'at home'; to avoid the rewrite of the mainframe version of the program? The author's answer is a fuel-management computer package operating on PC, 3 time faster than on a CDC-Cyber 830 mainframe one (486DX/33MHz/8MbRAM) or 20 time faster (Pentium-PC), respectively. (author). 5 refs., 1 tab., 5 figs

Public relations policy: The Electronuclear experience

International Nuclear Information System (INIS)

Soares, Luiz

2000-01-01

This presentation discusses the following topics: Historical and Cultural Aspects of Electrical Sector in Brazil; Nuclear Power and Public Acceptance in Brazil; The chances decision of Angra 3; Community Activities of the ELETRONUCLEAR Regional Programs and Emergency Planning Department whose function is to promote activities with or for the communities of Angra dos Reis region; Public Relations Actions

Estudio hidrodinámico de reactores empacados de flujo ascendente(REFA)

OpenAIRE

Díaz Marrero, Miguel Ángel; Dueñas Moreno, Jaime; Cabrera Díaz, Ania

2014-01-01

En el presente trabajo se emplean las técnicas de estímulo respuesta para estudiar los modelos de flujos de dos reactores tipo REFA, con volúmenes de 3,4 y 6 litros respectivamente, usando tiempos de retención hidráulicos y trazadores diferentes en ambos. Se determinaron las curvas de concentración contra tiempo para ambos reactores y se realizó el análisis comparativo de un grupo de relaciones entre los diferentes tiempos que se obtuvieron en los gráficos. Se aplica con los mismos experiment...

Acknowledgments to Brazilian Journal of Family and Community Medicine (RBMFC) Reviewers

OpenAIRE

Revista Brasileira de Medicina de Família e Comunidade RBMFC

2012-01-01

A Revista Brasileira de Medicina de Família e Comunidade (RBMFC) agradece aos membros de seu Corpo Editorial abaixo listados, pelas horas dedicadas voluntariamente para avaliação dos trabalhos submetidos à publicação e pelas demais contribuições para a melhoria da qualidade científica de nosso periódico.Adilson Domingos dos Reis Filho - UNIC Adriana Valéria Assunção Ramos - UNIFOR Airton Tetelbom Stein - UFCSPA Alberto Novaes Ramos Jr - UFC Aldaísa Cassanho Forster - UNIVALI Alessandro da Sil...

Status of the DOE's foreign research reactor spent nuclear fuel acceptance program

International Nuclear Information System (INIS)

Chacey, K.; Saris, E.C.

1997-01-01

In May 1996, the U.S. Department of Energy (DOE), in consultation with the U.S. Department of State (DOS), adopted a policy to accept and manage in the United States ∼20 tonnes of spent nuclear fuel from research reactors in up to 41 countries. This spent fuel is being accepted under the nuclear weapons non-proliferation policy concerning foreign research reactor spent nuclear fuel. Only spent fuel containing uranium enriched in the United States is covered under this policy. Implementing this policy is a top priority of the DOE. The purpose of this paper is to provide the current status of the foreign research reactor acceptance program, including achievements to date and future challenges

Upgrading the Siemens Argonaut Reactor Graz with a digital monitoring system

International Nuclear Information System (INIS)

Froehlich, O.; Ninaus, W.

1999-01-01

This paper presents a modern design of a reactor monitoring system (MS) which was developed for a research reactor. This MS is using digital concepts, and it is more flexible than an analog MS, it co-operates better with the user, and it is a very helpful tool for a training-reactor in an university environment. The heart of the system is a process computer, and it was possible to access all important signals and functions of the original nuclear instrumentation by additional hardware. The monitoring software was written in C for the platform '32Bit-DOS-protected-mode' and shows on several high-resolution screen pages all the collected signals and the working conditions of the reactor. Moreover, all signals which are recorded on the random access memory can be saved to the hard disk of the computer and may thereby be used offline as well.(author)

Análise de expressões formulaicas em textos tradicionais das Folias de Reis

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Elisângela Tavares Dias

2013-06-01

Full Text Available Neste trabalho, focalizamos a relação entre intertexto e expressões formulaicas em Folias de Reis brasileiras. À luz da tradição discursiva (cf. Kabatek, 2006; Koch, 1997; Oesterreicher, 1997, e seguindo ferramentas teórico-metodológicas da Análise Textual (cf. Jubran, 2006; Marcuschi, 2008, nossa proposta é apontar como se dá a reiterabilidade do texto em dois momentos da folia: o início e a chegada da jornada. Dialogamos também com alguns autores que consubstanciam o pareamento escrito/falado na produção da língua/linguagem em sua interlocução, a saber: Zumthor (1997 e Ong (1982, dentre outros. Recorremos para nossa análise, a um corpus representativo de quatorze folias presentes nos estados de MG, RJ, GO, ES, SP e RN. Em face disso, suscitar essa relação dialógica permite-nos pontuar que é inegável a contribuição dada pela tradição oral, seja por seus traços ideológicos e histórico-culturais, seja pela continuidade do folguedo, sobretudo, porque a utilização de um texto dá realidade à retórica que o funda, pois é pela atualização da voz que este se justifica e existe em situação de performance (ZUMTHOR,1997.

Experience report: a training center for health response

International Nuclear Information System (INIS)

Maurmo, Alexandre M.; Leite, Teresa C.S.B.

2009-01-01

The Professor Nelson Valverde Training Center was created within FEAM (The ELETRONUCLEAR Medical Assistance Foundation) with the objective of capacitating Radio Nuclear Accident Responders for the Health Area in the Almirante Alvaro Alberto Nuclear Central (Angra dos Reis - RJ - Brazil). The first step was structuring the contents for this training using IAEA's Manuals as base (EPR Medical - 2005, EPR First Responders - 2006 and TMT - Handbook - 2009) and data from REAC/TS. The second step was to capacitate instructors. The third step was the integration with the Company's Radiological Protection Division, giving radiological assessment. Finally, the development of training applications, ending with Drills, Tests and Assessment, gathering data and suggestions, objectifying the constant improvement. Training Programs with pre and post evaluations have been started. Since 2004 training internal courses were ministered for 125 professionals with annual re-training and were ministered to 130 professionals from several external institutions. During the same period training courses were ministered to 140 trainees from the Radiological Protection Division of The Nuclear Power Plant of Angra dos Reis, as First Lay Responders, objectifying the improvement of the quality of the emergency response. (author)

TPDWR2: thermal power determination for Westinghouse reactors, Version 2. User's guide

International Nuclear Information System (INIS)

Kaczynski, G.M.; Woodruff, R.W.

1985-12-01

TPDWR2 is a computer program which was developed to determine the amount of thermal power generated by any Westinghouse nuclear power plant. From system conditions, TPDWR2 calculates enthalpies of water and steam and the power transferred to or from various components in the reactor coolant system and to or from the chemical and volume control system. From these results and assuming that the reactor core is operating at constant power and is at thermal equilibrium, TPDWR2 calculates the thermal power generated by the reactor core. TPDWR2 runs on the IBM PC and XT computers when IBM Personal Computer DOS, Version 2.00 or 2.10, and IBM Personal Computer Basic, Version D2.00 or D2.10, are stored on the same diskette with TPDWR2

Hormonal contraception in women with polycystic ovary syndrome: choices, challenges, and noncontraceptive benefits

OpenAIRE

Melo,Anderson; Reis,Rosana; Ferriani,Rui; Vieira,Carol

2017-01-01

Anderson Sanches de Melo, Rosana Maria dos Reis, Rui Alberto Ferriani, Carolina Sales Vieira Department of Gynecology and Obstetrics, Ribeirão Preto School of Medicine, University of São Paulo, Ribeirão Preto, São Paulo, Brazil Abstract: Polycystic ovary syndrome (PCOS) is an endocrine disorder among women of reproductive age characterized by chronic anovulation and polycystic ovary morphology and/or hyperandrogenism. Mana...

Os organismos geneticamente modificados e a rotulagem dos alimentos - uma análise a partir dos direitos dos consumidores

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Marcello Vitor Rocha Cota

2015-11-01

Full Text Available Ao longo do presente trabalho serão analisados os organismos geneticamente modificados (OGMs frente aos riscos à saúde alimentar e ao meio ambiente, sobretudo o princípio da precaução e a rotulagem dos produtos. A partir de uma dimensão comparativa de três realidades distintas, isto é, a estadunidense, a europeia, com ênfase mercado ao português, e a brasileira – sob um prisma ambiental, a rotulagem dos produtos será confrontada com os direitos dos consumidores, embora em determinadas ocasiões, diante da inexistência de informações adequadas e claras dos produtos, que estão sendo ofertados e consumidos, os consumidores não sabem o que estão consumindo.

Autonomia profissional dos professores

OpenAIRE

Guerra, Teresa P.; Veiga, Feliciano

2007-01-01

Este estudo pretendeu analisar as representações dos professores acerca da sua autonomia em contexto escolar, com recurso a uma amostra de 203 professores de ambos os sexos, pertencentes a escolas dos distritos de Lisboa, Setúbal, Leiria e Aveiro. Utilizou-se a Escala de Autonomia Profissional dos Professores (EAPP).

The use of genetic algorithms with niching methods in nuclear reactor related problems; A utilizacao dos metodos de nichos dos algoritmos geneticos na otimizacao de problemas de reatores nucleares

Energy Technology Data Exchange (ETDEWEB)

Sacco, Wagner Figueiredo

2000-03-01

Genetic Algorithms (GAs) are biologically motivated adaptive systems which have been used, with good results, in function optimization. However, traditional GAs rapidly push an artificial population toward convergence. That is, all individuals in the population soon become nearly identical. Niching Methods allow genetic algorithms to maintain a population of diverse individuals. GAs that incorporate these methods are capable of locating multiple, optimal solutions within a single population. The purpose of this study is to test existing niching techniques and two methods introduced herein, bearing in mind their eventual application in nuclear reactor related problems, specially the nuclear reactor core reload one, which has multiple solutions. Tests are performed using widely known test functions and their results show that the new methods are quite promising, specially in real world problems like the nuclear reactor core reload. (author)

Partida de um reator anaeróbio horizontal para tratamento de efluentes do processamento dos frutos do cafeeiro Start-up of an anaerobic horizontal-flow reactor for treating wastewater from a coffee fruits processing

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Alisson C. Borges

2009-01-01

Full Text Available O presente estudo teve o objetivo de avaliar a partida e a adaptação de um reator anaeróbio horizontal de leito fixo (RAHLF no tratamento de águas residuárias do processamento primário dos frutos do cafeeiro (ARC. O reator foi construído com tubos de PVC de 0,2 m de diâmetro e 3,2 m de comprimento. O sistema foi preenchido com cubos de espuma de poliuretano para imobilização de biomassa ativa. O reator apresentou volume total de 0,1 m³ e volume útil equivalente a 0,04 m³. Em média, houve remoção de 49% da matéria orgânica, com o reator trabalhando sob carga orgânica volumétrica média de 2,66 kg m-3 d-1, medida como DQO. A suplementação de alcalinidade, somada à inoculação prévia de biomassa, proporcionou partida estável do RAHLF, confirmada pelo consumo de ácidos voláteis e adaptação da microbiota ao resíduo. O sistema apresentou resistência às variações de vazão e de carga orgânica observadas, e os teores de fenol e potássio monitorados não causaram inibição da atividade biológica no RAHLF. O maior controle sobre as variações de carga é fator importante na continuidade dos estudos.This study aimed to evaluate the start-up and the adaptation of an anaerobic horizontal-flow immobilized biomass (HAIB reactor in order to treat wastewater from a primary processing of coffee fruits. The reactor was built with PVC tubes of 0.2 m in diameter and 3.2 m in length. The system was filled with cubes of polyurethane foam for immobilization of active biomass. The reactor presented a total capacity of 0.1 m³ and reaction volume equal to 0.04 m³. 49% of organic matter. Removal efficiency was observed, with medium organic volumetric loads equal to 2.66 kg m-3 d-1 (as chemical oxygen demand. The supplementary addition of alkalinity and the previous biomass inoculation provided a stable start-up of the reactor, as confirmed by the reduction of volatile acids and an adaptation of the present microbiology community

Editorial. Kultūros reiškiniai šiuolaikinių informacijos ir komunikacijos technologijų sąlygomis: nuo meno ir televizijos iki politikos

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Jovilė Barevičiūtė

2015-10-01

Full Text Available Šiame žurnalo numeryje aptariami kai kurie daugiaaspekčiai šiuolaikinės kultūros reiškiniai, apimant tokius jų, kaip menas, televizija, politika ir kt. Medijos ir komunikacija nūdien intensyviai skverbiasi kone į visas darbo ir laisvalaikio veiklos, viešojo ir privataus sektorių sritis, reprezentuodamos dinamišką ir netolygią gyvenamojo pasaulio tikrovę. Medijuotoji komunikacija vis labiau tampa dominuojančia socializacijos forma, ji išstumia gyvąją komunikaciją: kuo toliau, tuo labiau šis reiškinys nusako ne tik jaunimo, bet ir brandaus amžiaus žmonių šiandienį bendravimo būdą. Tad akivaizdu, kad XXI a. žmogus vis labiau pasineria į įvairių medijų tinklus, apraizgančius jo gyvenimą ir tampančius pagrindine socialios ir visavertės eg zistencijos sąlyga. Tokios socialinės institucijos, kaip menas, televizija, politika, religija, šeima ir daugelis kitų, nūdien jau nebėra tokios savarankiškos, kaip, tarkime, prieš dešimt, dvidešimt ar daugiau metų. Jų suverenitetą daugiausia transformuoja būtent medijos, šioms institucijoms diktuojančios savas sąlygas ir primetančios savas taisykles. Kitaip tariant, medijos tampa tokios galingos, kad ima steigti savuosius dėsnius, kuriems vis labiau paklūsta tradicinė gyvosios socializacijos aplinka. Taip kyla daugybė diskutuotinų ir ginčytinų klausimų, paliečiančių socialinių institucijų apibrėžties, autonomijos ir suvereniteto aspektus. Šiuos aspektus iš įvairių perspektyvų gvildena ir šio numerio autoriai. Eugenija Krukauskienė ir Viktorija Žilinskaitė-Vytienė savo straipsnyje aptaria kultūros vartojimo klausimus tirdamos, kaip šiuolaikinio lietuviškojo kino meno pavyzdžius suvokia ir vertina tam tikrų amžiaus kategorijų jaunimas. Algis Mickūnas gilinasi į filosofinius šiuolaikinių diskursų klausimus, pasirinkdamas kūniškumo, lytėjimo ir taktilikos aspektus, glaudžiai susijusius su medijuotosios komunikacijos tema

Transit and absorption of nuclear industry derivatives by marine biota

International Nuclear Information System (INIS)

Mayr, L.; Moraes, R.; Lopes, M.A.; Vicente, C.; Mauro, J.N.

1988-01-01

A broard research program on radionuclides became necessary due to the construction of the Nuclear Power Plant at Angra dos Reis. As part of this program the research developped by the Marine Biology Departament, UFRJ, aimed at estimating the radiation doses to wich the population of the region might be exposed and to determine biological indicators to radioactive contamination. Up to the present moment, the bioacumulation factors (BFs) of 60 Co, 137 Cs and 131 I by ''clam'' (Anomalocardia brasiliana) and the biological half-life of cobalt and cesium in this animal were determined, as well as the B.F. of 85 Sr by ''snail'' (Strombus pugilis) and by ''barnacle'' (Megabalanus tintinnabulum). The remobilization of 60 Co by microbiological activity in marine sediment was also studied. These studies were made using the standard methodology for bioaccumulation and elimination in closed water systems. The results showed an important microbiological activity in the remobilization of elements in the sediment. Due to the low bioaccumulation factors obtained the studied organisms were not considered ideal biological indicators for radioactive pollution. However, their importance as edible animals in the Angra dos Reis region recommends their radiometry for routine radiological monitoring. Studies on other organisms and/or radionuclides are now in progress at the Marine Biology Departament (UFRJ). (author) [pt

O descobrimento do Brasil através dos textos: edições críticas e comentadas

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Joaquim Barradas de Carvalho

1969-06-01

Full Text Available Em 14 de dezembro de 1508 (94 D. Manuel encarregou um chamado João Serrão de dar caça, com uma pequena frota, ao corsário francês Mondragon, que tinha atacado navios portuguêses pro-venientes da Ilidia . João Serrão não cumpriu a contento a sua mis-são e o rei substituiu-o por Duarte Pacheco Pereira .

O imaginário do sangue e de sua pureza na antiga França

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Arlette Jouanna

2011-01-01

Full Text Available A palavra sangue, na França dos primeiros tempos modernos, por um lado designava o líquido vital que corria nas veias, e por outro a linhagem, a "raça". O sangue era com efeito considerado o veículo das qualidades físicas e morais hereditárias que caracterizavam a personalidade de uma linhagem. Sua pureza devia facilitar o exercício das virtudes. Essa crença permitia explicar a superioridade da nobreza e afirmar que a hierarquia social era justa, já que natural; era igualmente ela que legitimava o poder dos reis, caracterizados pela excelência de seu sangue.

Pareceristas da RBHCS no Triênio 2015-2017

OpenAIRE

Editores RBHCS

2017-01-01

Pareceristas da RBHCS no Triênio 2015-2017   Adelar Heinsfeld (UPF) Adilson Júnior Ishihara Brito (UFPA) Adilson Prizmic Momce (UFMS) Alcileide Cabral do Nascimento (UFRPE) Alexandre de Oliveira Karsburg (UNISINOS) Alfredo Veiga-Neto (UFRGS) Ana Carolina de Carvalho Viotti (UNESP) Ana Paula Korndörfer (UNISINOS) Ana Silvia Volpi Scott (NEPO/Unicamp) Anderson Roberti dos Reis (UFMT) Andréia Orsato (IFSul) Andrés Cobo de Guzmán (Université Gren...

The Critical Edition of Eça de Queirós: an evaluation

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Ernesto Rodrigues

2008-12-01

Full Text Available A construção da narrativa queirosiana – O espólio de Eça de Queirós, de Carlos Reis e Maria do Rosário Milheiro (1989, funciona como guião para a Edição Crítica em epígrafe: apresentado esse título, dá-se notícia de cada um dos volumes editados entre 1992 e 2008.

Anníbal marques da costa e a "matemática em versos e prosas": histórias da matemática na são joão del-rei do início do século XX Anníbal Marques da Costa and the "Matemática em versos e prosas": histories of mathematics in Sao João del-Rei in the early twentieth century

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Romélia Mara Alves Souto

2011-01-01

Full Text Available Neste artigo, apresentamos os resultados de um estudo analítico-descritivo que realizamos da obra "Matemática em versos e prosas", de Anníbal Marques da Costa, encontrada no acervo do Clube Teatral Artur Azevedo, na Universidade Federal de São João del-Rei (UFSJ, em Minas Gerais. A obra é um manuscrito, em dois volumes, produzida entre 1942 e 1954, que, com explícita intenção de divulgação da matemática, embora nunca tenha sido impressa, trata de conceitos e propriedades da matemática elementar. A investigação possibilitou-nos elaborar uma descrição seguida de uma análise histórica e crítica do texto, que foi enriquecida pelo acréscimo de algumas informações sobre o autor e a época em que ele viveu.This paper presents the results of an analytical-descriptive study of the book "Matemática em versos e prosas" by Anníbal Marques da Costa, found in Clube Teatral Artur Azevedo, archives from the Universidade Federal de São João del-Rei (UFSJ, in Minas Gerais. The book has never been published and is a manuscript in two volumes produced between 1942 and 1954 aiming to promote Mathematics. It deals with the concepts and properties of elementary mathematics. The research enabled the development of a description and a historical and critical analysis of the text, enriched by some information about the author and the time he lived.

DOS cones along atomic chains

International Nuclear Information System (INIS)

Kwapiński, Tomasz

2017-01-01

The electron transport properties of a linear atomic chain are studied theoretically within the tight-binding Hamiltonian and the Green’s function method. Variations of the local density of states (DOS) along the chain are investigated. They are crucial in scanning tunnelling experiments and give important insight into the electron transport mechanism and charge distribution inside chains. It is found that depending on the chain parity the local DOS at the Fermi level can form cone-like structures (DOS cones) along the chain. The general condition for the local DOS oscillations is obtained and the linear behaviour of the local density function is confirmed analytically. DOS cones are characterized by a linear decay towards the chain which is in contrast to the propagation properties of charge density waves, end states and Friedel oscillations in one-dimensional systems. We find that DOS cones can appear due to non-resonant electron transport, the spin–orbit scattering or for chains fabricated on a substrate with localized electrons. It is also shown that for imperfect chains (e.g. with a reduced coupling strength between two neighboring sites) a diamond-like structure of the local DOS along the chain appears. (paper)

DOS cones along atomic chains

Science.gov (United States)

Kwapiński, Tomasz

2017-03-01

The electron transport properties of a linear atomic chain are studied theoretically within the tight-binding Hamiltonian and the Green’s function method. Variations of the local density of states (DOS) along the chain are investigated. They are crucial in scanning tunnelling experiments and give important insight into the electron transport mechanism and charge distribution inside chains. It is found that depending on the chain parity the local DOS at the Fermi level can form cone-like structures (DOS cones) along the chain. The general condition for the local DOS oscillations is obtained and the linear behaviour of the local density function is confirmed analytically. DOS cones are characterized by a linear decay towards the chain which is in contrast to the propagation properties of charge density waves, end states and Friedel oscillations in one-dimensional systems. We find that DOS cones can appear due to non-resonant electron transport, the spin-orbit scattering or for chains fabricated on a substrate with localized electrons. It is also shown that for imperfect chains (e.g. with a reduced coupling strength between two neighboring sites) a diamond-like structure of the local DOS along the chain appears.

Use of new technologies in the documentation of the origin and urban development of São João Del Rei Minas Gerais, Brasil.

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Altino Barbosa Caldeira

2015-01-01

Full Text Available The city of São Joao del Rei, situated in the state of Minas Gerais, Brazil, has a currently economic, social and tourism performance that stands outamong the other cities of the state. This article seeks to clarify these reasons, taking into account the region and the occupied territory, theirsubsequent development and the changes occurring in the landscape from this occupation. It also aims to demonstrate how to use the resources ofnew technologies to document the cultural heritage left by past  generations and how spread it to new generations. For this, we will make use of the physical and human geography, as well as its history, to analyze facts, activities and the reasons that led to its current appearence. It will be considered the natural environment, human interventions and cultural expressions of its people regarding aspects of intangible heritage to analyzes the spatial dimension of the local culture, using the concepts of cultural geography.

REDUÇÃO DOS CUSTOS DA QUALIDADE COM MELHORIA DOS PROCESSOS: UM ESTUDO DE CASO

OpenAIRE

Oliveira, Gabriel Rech; Universidade de Caxias do Sul; Motta, Marta Elisete Ventura; Universidade de Caxias do Sul; Camargo, Maria Emilia; Universidade de Caxias do Sul; Tondolo, Vilmar Antonio Gonçalves; Universidade Federal de Rio Grande; Zanadrea, Gabriela; Universidade de Caxias do Sul; Russo, Suzana Leitão; Universidade Federal de Sergipe

2016-01-01

Com o objetivo de se tornarem competitivas, as empresas impulsionam a redução dos custos dos processos que impactam diretamente no preço do produto, destacando-se os custos de qualidade. Neste cenário, a busca pela qualidade total torna-se o caminho para a sobrevivência, devido ao fato da crescente exigência dos clientes para produtos com qualidade superior e preços baixos. Dentre os principais gastos que contribuem para o aumento dos custos da qualidade destacam-se a sucata e retrabalho de p...

Self-regulating the effortful "social dos".

Science.gov (United States)

Cortes, Kassandra; Kammrath, Lara K; Scholer, Abigail A; Peetz, Johanna

2014-03-01

In the current research, we explored differences in the self-regulation of the personal dos (i.e., engaging in active and effortful behaviors that benefit the self) and in the self-regulation of the social dos (engaging in those same effortful behaviors to benefit someone else). In 6 studies, we examined whether the same trait self-control abilities that predict task persistence on personal dos would also predict task persistence on social dos. That is, would the same behavior, such as persisting through a tedious and attentionally demanding task, show different associations with trait self-control when it is framed as benefitting the self versus someone else? In Studies 1-3, we directly compared the personal and social dos and found that trait self-control predicted self-reported and behavioral personal dos but not social dos, even when the behaviors were identical and when the incentives were matched. Instead, trait agreeableness--a trait linked to successful self-regulation within the social domain--predicted the social dos. Trait self-control did not predict the social dos even when task difficulty increased (Study 4), but it did predict the social don'ts, consistent with past research (Studies 5-6). The current studies provide support for the importance of distinguishing different domains of self-regulated behaviors and suggest that social dos can be successfully performed through routes other than traditional self-control abilities. (PsycINFO Database Record (c) 2014 APA, all rights reserved).

PR-EDB: Power Reactor Embrittlement Data Base, version 1: Program description

International Nuclear Information System (INIS)

Stallmann, F.W.; Kam, F.B.K.; Taylor, B.J.

1990-06-01

Data concerning radiation embrittlement of pressure vessel steels in commercial power reactors have been collected form available surveillance reports. The purpose of this NRC-sponsored program is to provide the technical bases for voluntary consensus standards, regulatory guides, standard review plans, and codes. The data can also be used for the exploration and verification of embrittlement prediction models. The data files are given in dBASE 3 Plus format and can be accessed with any personal computer using the DOS operating system. Menu-driven software is provided for easy access to the data including curve fitting and plotting facilities. This software has drastically reduced the time and effort for data processing and evaluation compared to previous data bases. The current compilation of the Power Reactor Embrittlement Data base (PR-EDB, version 1) contains results from surveillance capsule reports of 78 reactors with 381 data points from 110 different irradiated base materials (plates and forgings) and 161 data points from 79 different welds. Results from heat-affected-zone materials are also listed. Electric Power Research Institute (EPRI), reactor vendors, and utilities are in the process of providing back-up quality assurance checks of the PR-EDB and will be supplementing the data base with additional data and documentation. 2 figs., 28 tabs

Comparative analysis of three atmospheric dispersion coefficient systems at the Angra dos Reis, RJ, region; Analise comparativa de tres sistemas de coeficientes de dispersao atmosferica na regiao de Angra dos Reis, RJ

Energy Technology Data Exchange (ETDEWEB)

Biagio, Rosa Maria de Souza

1982-07-01

A comparative analysis was made in this work among Pasquill-Gifford (PG) atmospheric dispersion coefficients and those determined at the Juelich and Karlsruhe sites with the purpose of suggesting which one would be the most applicable to the Angra site. Each one of the three systems was determined by different experiments, carried out over sites with diversified features. The systems of Juelich and Karlsruhe were obtained over sites with high surface roughness and from stacks (elevated releases), while the PG system was obtained over sites with a small surface roughness and from ground level releases. The results of the application of these systems at a complex site like Angra,which has a highly diversified structure encompassing sea, vegetation, predominance of light winds and stable stability classes, show that the PG system, the most used in the world, is still the best choice. (author)

Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

International Nuclear Information System (INIS)

Henry, A.F.

1980-01-01

Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

Internetinio marketingo elementų analizė Lietuvos turizmo info rmacijos centrų pavyzdžiu

OpenAIRE

Bivainienė, Lina; Dauginaitė, Živilė

2008-01-01

Straipsnyje aktualizuojama internetinio marketingo sąvoka, aptariami internetinio marketingo elementai. Mokslininkai (Kotler, Keller, 2007 ir kt.) pabrėžia, kad internetas marketingo specialistams suteikia didesnes dialogo ir individualizacijos galimybes. Įmonėms tai reiškia santykių pradžią ir bendravimą su dar didesnėmis vartotojų grupėmis. Straipsnio tikslas – išanalizuoti internetinio marketingo elementus Lietuvos (Vilniaus, Kauno, Klaipėdos, Šiaulių, Panevėžio) turizmo informacijos centr...

Reactor core in FBR type reactor

International Nuclear Information System (INIS)

Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

1989-01-01

In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

Representações e expectativas dos profissionais dos serviços de pediatria do Hospital de Braga relativamente à intervenção dos "Doutores Palhaços"

OpenAIRE

Almeida, Isabel Cristina Ferreira de

2012-01-01

Dissertação de mestrado em Estudos da Criança (área de especialização em Intervenção Psicossocial com Crianças, Jovens e Famílias) Neste estudo são dadas a conhecer as representações e expetativas dos profissionais de saúde dos serviços de pediatria do Hospital de Braga, relativamente ao trabalho dos palhaços profissionais da Operação Nariz Vermelho: os “Doutores Palhaços” (DP). A recolha dos dados realizou-se cerca de um mês antes do início da intervenção dos DP naquela unidad...

Reactor core and initially loaded reactor core of nuclear reactor

International Nuclear Information System (INIS)

Koyama, Jun-ichi; Aoyama, Motoo.

1989-01-01

In BWR type reactors, improvement for the reactor shutdown margin is an important characteristic condition togehter with power distribution flattening . However, in the reactor core at high burnup degree, the reactor shutdown margin is different depending on the radial position of the reactor core. That is , the reactor shutdown margin is smaller in the outer peripheral region than in the central region of the reactor core. In view of the above, the reactor core is divided radially into a central region and as outer region. The amount of fissionable material of first fuel assemblies newly loaded in the outer region is made less than the amount of the fissionable material of second fuel assemblies newly loaded in the central region, to thereby improve the reactor shutdown margin in the outer region. Further, the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower portion of the first fuel assemblies is made smaller than the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower region of the second fuel assemblies, to thereby obtain a sufficient thermal margin in the central region. (K.M.)

Dinâmica Glacial e Características Sedimentares Resultantes na Zona Proglacial da Geleira Ecology-Baía do Almirantado, Ilha Rei George Antártica.

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Kátia Kellem Rosa

2006-12-01

Full Text Available A geleira Ecology, localizada na ilha Rei George, ilhas Shetlands do Sul, está sofrendo um processo de rápida retração ao longo das últimas décadas, sendo que no período de 1956 a 1992/95 a geleira retrocedeu 0,37 Km2. Isto gerou um ambiente de deglaciação, com a exposição de várias geoformas na zona proglacial. Este trabalho objetiva estudar o ambiente de deglaciação da zona proglacial da geleira Ecology e seus respectivos depósitos na zona proglacial, além de inferir o regime termo-basal desta geleira. O produto resultante deste trabalho é a criação de um modelo geomorfológico para a zona proglacial da geleira, o qual pode ser usado para comparar com zonas proglaciais de outras geleiras.

Cobalt adsorption/desorption on sediments from Piraquara de Fora bay, Angra dos Reis, Brazil

International Nuclear Information System (INIS)

Ferreira, Ingryd M.; Carvalho, Franciane M.; Ribeiro, Fernando C.A.; Martins, Nadia S.F.; Peres, Sueli S.; Lauria, Dejanira C.

2015-01-01

Among the radionuclides released with the liquid effluents from PWR power plants, cobalt isotopes ( 60 Co and 58 Co) play an important role for risk and environmental impact assessments. The laboratory experiments on radionuclide adsorption-desorption, followed by the use of adsorption isotherms are useful tools for prediction of transport, distribution, accumulation, and fate of a contaminant into a specific medium. Adsorption and desorption experiments were carried out in batches, using two sediment samples collected in Piraquara de Fora Bay, near the discharge channel of the liquid effluents from CNAAA. Aiming the assessment of the radioisotope adsorption mechanisms, sediment samples were shaken with solutions containing cobalt chloride which concentrations ranged between 10 -10 and 10 -3 M. In order to estimate the efficiency of adsorption, 100 Bq of 60 Co were used as radioactive tracer. The experimental data fitted well with Freundlich and Langmuir isotherms. Results point out a favorable and high cobalt adsorption on the sediments, although smaller than the ones reported in literature studies. Such smaller trend of adsorption coefficients may be caused by the low exchange capacity of the prevailing clay, kaolinite. The maximum adsorption capacities were found to be 10 and 17 moles/g for sediments in PT-01 and PT-02, respectively. Values lower than 8% of the adsorbed cobalt underwent desorption and this amount decreased to 4%, with time, which show the high retention capacity of these sediments. (author)

Experiments on radionuclide accumulation by fishes from the Angra Dos Reis region of Brazil

International Nuclear Information System (INIS)

Guimaraes, J.R.D.

1988-11-01

To follow the bioaccumulation and tissue distribution of 137 Cs and 60 Co in fish from tropical waters near the Angra nuclear power station in Brazil, juvenile grouper (Epinephelus sp.) were exposed under laboratory conditions to Angra sea water containing the two radionuclides initially added in chloride form. During the 4-month exposure period, the sea water was not changed and the fish received regular rations of non-radioactive food. Following uptake, the fish were dissected and composite tissue samples monitored for radioactivity. 137 Cs concentration factors (CFs) were 3 and 5 in whole fish and muscle, respectively. The highest concentration of 137 Cs was found in the muscle which accounted for 66% of the total body burden. In contrast, the highest concentration and greatest fraction (19%) of 60 Co was located in the liver. Whole body and muscle CFs for 60 Co, 0.2 and 0.08 respectively, were much lower than those for 137 Cs. Compared with published data, only very small amounts of both radionuclides were taken up by bone in the present study. This observation and the fact that much higher 137 Cs CFs have been reported in fish from field studies suggests that uptake through the food chain is the principal pathway for bioaccumulation in nature. Elution of freshly-prepared and previously-used radioactive sea water through chelating resins indicated that 60 Co added in the cationic form was almost totally converted to neutral or anionic forms after four months. Additional experiments carried out with the previously-used experimental media demonstrated that the possibly ligand-bound 60 Co was approximately 2.5 times more available for uptake by grouper than the cationic forms initially present. It is concluded that the uptake of 60 Co by fish exposed to radioactive effluents would be a function of the different forms of 60 Co present. 20 refs, 2 figs, 2 tabs

Nuclear reactor physics course for reactor operators

International Nuclear Information System (INIS)

Baeten, P.

2006-01-01

The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

Reactor core of FBR type reactor

International Nuclear Information System (INIS)

Hayashi, Hideyuki; Ichimiya, Masakazu.

1994-01-01

A reactor core is a homogeneous reactor core divided into two regions of an inner reactor core region at the center and an outer reactor core region surrounding the outside of the inner reactor core region. In this case, the inner reactor core region has a lower plutonium enrichment degree and less amount of neutron leakage in the radial direction, and the outer reactor core region has higher plutonium enrichment degree and greater amount of neutron leakage in the radial direction. Moderator materials containing hydrogen are added only to the inner reactor core fuels in the inner reactor core region. Pins loaded with the fuels with addition of the moderator materials are inserted at a ratio of from 3 to 10% of the total number of the fuel pins. The moderator materials containing hydrogen comprise zirconium hydride, titanium hydride, or calcium hydride. With such a constitution, fluctuation of the power distribution in the radial direction along with burning is suppressed. In addition, an absolute value of the Doppler coefficient can be increased, and a temperature coefficient of coolants can be reduced. (I.N.)

OS SACRAMENTAIS, SACRAMENTOS DOS POBRES

Directory of Open Access Journals (Sweden)

Victor Codina

1990-01-01

Full Text Available Basta ter tido um pouco de experiência pastoral com setores populares, concretamente na América Latina, para constatar a importância dos sacramentais na vida cristã do povo. Além das manifestações de piedade popular que se costuma estudar sob a rubrica de religiosidade popular (peregrinações, festas de padroeiro, procissões..., gostaria de destacar aqui outros elementos mais estreitamente ligados ao mundo dos sacramentos, ainda que não formem parte dos sete sacramentos tridentinos.

Camponeses e esquecimento na Antiguidade Tardia: as revoltas dos bagaudas e dos circunceliões

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Uiran Gebara da Silva

2016-12-01

Full Text Available Esse artigo apresenta alguns dos problemas com os quais eu tive de lidar ao realizar um estudo comparativo entre dois conjuntos de revoltas rurais do Império Romano tardio: as revoltas dos bagaudas na Gália e dos circunceliões na África. O artigo toma como eixo articulador a hipótese lançada por E. A. Thompson sobre o papel do esquecimento na produção dos relatos antigos sobre os bagaudas e a problematiza. Num segundo momento o artigo trata do problema relacionado à compreensão do caráter social de ambos os grupos, levando em consideração os múltiplos relatos presentes nas fontes antigas e as divergentes interpretações modernas sobre eles, enfatizando a necessidade de se reconhecer a tópica da inversão social como um elemento que diferencia os relatos sobre os revoltosos daqueles sobre a bandidagem. Outro elemento importante é o reconhecimento da heterogeneidade dos discursos cristãos com relação às classes subalternas e aos revoltosos, que apontam não para um fortalecimento do patronato rural, mas para o enfraquecimento ou para a crise dessas relações no campo tardo-romano.

Nuclear reactors

International Nuclear Information System (INIS)

Barre, Bertrand

2015-10-01

After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

Country Report: Rep. of Korea. {sup 188}re-Tricabonyl Labeling Strategy: Preparation of 1{sup 188}Re(I) Tricarbonyl Precursor [{sup 188}Re(OH{sub 2}){sub 3}(CO){sub 3}]+ for the Labeling of Biomolecules

Energy Technology Data Exchange (ETDEWEB)

Park, Sang Hyun [Radiation Research Division for Biotechnology, Korea Atomic Energy Research Institute (Korea, Republic of)

2010-07-01

The {sup 99m}Tc(I) and {sup 188}Re(I) tricarbonyl precursors [M(OH{sub 2}){sub 3}(CO){sub 3}]{sup +} have been shown to be excellent starting materials for the synthesis of {sup 99m}Tc(I) and {sup 188}Re(I) tricarbonyl complexes as well as radiolabeling of target-specific biomolecules.{sup 1-8} Recently, a user-friendly kit formulation (IsoLink{sup TM}) was developed using potassium boranocarbonate, K{sub 2}[BH{sub 3}CO{sub 2}], for preparation of the {sup 99m}Tc precursor complex. This solid reagent serves both as a source of carbon monoxide and a reducing agent for technetium. It was also used by Schibli and coworkers for the preparation of the corresponding {sup 188}Re precursor complex (“Schibili’s kit”).{sup 9} This approach involved the reduction of [{sup 188}Re]perrhenate eluate (1 ml) in neutral solution with 3 mg K{sub 2}[BH{sub 3}CO{sub 2}] and 5 mg BH3≅NH3 by incubation at 60 °C for 15 min. The amounts of reducing agents and acid (concentrated phosphoric acid) were carefully balanced not only to avoid fast hydrolysis of the boranes, but also to maintain a sufficiently low pH to stabilize reduced rhenium intermediates. The preparations resulted in yields >85 % of the desired precursor complex. In addition, perrhenate (7±3 %), colloidal {sup 188}ReO{sub 2} (<5 %), and a byproduct of unknown composition were also detected. To increase the yields even further, we evaluated the recently described borohydride exchange resin (BER) as an additional reducing agent and an anion scavengers.

Reactor core for LMFBR type reactors

International Nuclear Information System (INIS)

Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

1987-01-01

Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

REDUÇÃO DOS CUSTOS DA QUALIDADE COM MELHORIA DOS PROCESSOS: UM ESTUDO DE CASO

Directory of Open Access Journals (Sweden)

Gabriel Rech Oliveira

2016-06-01

Full Text Available Com o objetivo de se tornarem competitivas, as empresas impulsionam a redução dos custos dos processos que impactam diretamente no preço do produto, destacando-se os custos de qualidade. Neste cenário, a busca pela qualidade total torna-se o caminho para a sobrevivência, devido ao fato da crescente exigência dos clientes para produtos com qualidade superior e preços baixos. Dentre os principais gastos que contribuem para o aumento dos custos da qualidade destacam-se a sucata e retrabalho de produtos durante o processo produtivo. Devido à ocorrência desses fatores, este trabalho tem como finalidade analisar os custos da qualidade e propor melhorias no processo produtivo utilizando ferramentas da qualidade para reduzir os desperdícios com sucata. As fases do projeto envolvem o comprometimento e dedicação de equipes para levantar as principais causas dos principais problemas do processo de produção de tubos capilares em cobre, resultando na redução dos gastos com sucata e aumento da produtividade. As metodologias utilizadas para atingir os objetivos foram baseadas pesquisa exploratória e estudo de caso. A partir da redução de custo e aumento da produtividade alcançada, constata-se a importância deste trabalho envolvendo equipes responsáveis para a obtenção de resultados em curto prazo.

O rei do cangaço, o governador do sertão; o bandido ousado do sertão, o cangaceiro malvado : processos referenciais na construção da memoria discursiva sobre Lampião

OpenAIRE

Geralda de Oliveira Santos Lima

2008-01-01

Resumo: O presente trabalho aborda a questão da referenciação na construção e reconstrução da memória discursiva (e social) sobre Lampião, personagem da história do nordeste brasileiro. A escolha do tema foi baseada na riqueza de fatos contados e recontados sobre o cangaceiro. Esta investigação diz respeito ao uso de processos referenciais no interior de fontes orais. Propõe-se, pois, a analisar como se constrói e se reconstrói a memória discursiva do rei do cangaço via cadeias referenciais p...

Evaluación del comportamiento hidrodinámico como herramienta para optimización de reactores anaerobios de crecimiento en medio fijo

Directory of Open Access Journals (Sweden)

Andrea Pérez

2008-01-01

Full Text Available Las condiciones de flujo no ideal en los reactores afectan su desempeño; las causas comunes son cortos circuitos, zonas muertas y recirculación interna por corrientes cinéticas y/o de densidad. En este estudio se optimizó el diseño de un filtro anaerobio a escala real que trata las aguas residuales del proceso de extracción de almidón de yuca, el cual presentaba problemas de represamiento y bajas eficiencias de remoción. La evaluación del comportamiento hidrodinámico inicial mostró la presencia de flujo dual (32% flujo pistón - FP y 37% mezcla completa - CM, zonas muertas (20% y ausencia de cortos circuitos; adicionalmente, la modelación del reactor indicó un grado de dispersión elevado y un comportamiento tendiente a un reactor CM en serie de dos unidades. Con base en estos resultados, se implementaron dos modificaciones en el diseño del reactor: falso fondo y tubería perforada para evacuación de biogás, las cuales permitieron incrementar la fracción de FP (44%, reducir la fracción de zonas muertas (15%, disminuir el Índice de Dispersión (ID e incrementar la tendencia del reactor a un CM en serie de tres unidades, lo que aumentó el tiempo de retención hidráulico (TRH real de 9,6 a 10,2 horas (TRH teórico 12 horas y las eficiencias teóricas de remoción de 73 a 78%.

Improvement of the reactivity computer using windows for HANARO research reactor

International Nuclear Information System (INIS)

Park, S. Z.; Kim, M. J.; Seo, C. K.; Kim, H. N.

2001-01-01

A multi-channel wide range digital reactivity computer, which was developed by KAERI, has been used for HANARO research reactor since its fuel loading. It was based on the PC (personal computer) system equipped with an ADC (analog to digital converter), and the application program was developed in the MS-DOS envrionment. There exist some difficulties in upgrading the system through adding the necessary functions because not only DOS does not sure to presist in parallel with Windows, but also it has a drawback in supporting the advanced abilities of the innovatively developing PC. And it is very hard to change or replace some components, if needed, due to the strong dependence of the system on the PC hardware, which is fast obsolete. To solve these problems stemming from the MS-DOS envrionment, we replaced some parts of the existing system for neutron signal acquisition and completely upgraded on the Windows environment the application program including various helpful tools that are necessary for the reactivity measuring experiments. And to improve the processing features for the wide range neutron signal, we elaborated and implemented the new concept that a single channel of the neutron signal is renovated to multi ADC channels with different gains for the purpose of selectively utilizing a proper neutron signal

Progress of the United States foreign research reactor spent nuclear fuel acceptance program

International Nuclear Information System (INIS)

Huizenga, D.G.; Clapper, M.; Thrower, A.W.

2002-01-01

The United States Department of Energy (DOE), in consultation with the Department of State (DOS), adopted the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel in May 1996. To date, the Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program has completed 23 shipments. Almost 5000 spent fuel assemblies from eligible research reactors throughout the world have been accepted into the United States under this program. Over the past year, another cross-country shipment of fuel was accomplished, as well as two additional shipments in the fourth quarter of calendar year 2001. These shipments attracted considerable safeguards oversight since they occurred post September 11. Recent guidance from the Nuclear Regulatory Commission (NRC) pertaining to security and safeguards issues deals directly with the transport of nuclear material. Since the Acceptance Program has consistently applied above regulatory safety enhancements in transport of spent nuclear fuel, this guidance did not adversely effect the Program. As the Program draws closer to its termination date, an increased number of requests for program extension are received. Currently, there are no plans to extend the policy beyond its current expiration date; therefore, eligible reactor operators interested in participating in this program are strongly encouraged to evaluate their inventory and plan for future shipments as soon as possible. (author)

Operating Experience with the VERA Zero-Energy Fast Reactor; Fonctionnement du Reacteur VERA a Neutrons Rapides, de Puissance Zero; Opyt ehkspluatatsii reaktora VERA na bystrykh nejtronakh nulevoj moshchnosti; Experiencia Adquirida con el Reactor Rapido VERA de Potencia Nula

Energy Technology Data Exchange (ETDEWEB)

Weale, J. W.; McTaggart, M. H.; Goodfellow, H.; Paterson, W. J. [Atomic Weapons Research Establishment, Aldermaston (United Kingdom)

1964-02-15

elements combustibles; incidences des irregularites des faces et de l'heterogeneite de la structure sur l'exactitude avec laquelle on determine la masse critique d'un assemblage equivalent 'ideal'; possibilite de reproduire l'etat critique apres avoir demonte l'assemblage ou separe les deux moities; variation de la reactivite lors de la separation des deux moities, et effets d'un chargement asymetrique; sensibilite de divers compteurs, intensite de la source de neutrons, utilisation d'un accelerateur comme source de neutrons; vitesse de reponse des circuits de securite et restrictions qu'elle peut entrainer pour la vitesse d'assemblage des deux moities; precautions supplementaires qu'il faut prendre pour utiliser le plutonium comme combustible; notes sur l'exactitude des mesures de la reactivite et sur les limitations d'ordre pratique imposees a diverses autres mesures en physique des reacteurs. (author) [Spanish] Los autores describen brevemente las caracteristicas de un reactor rapido de potencia nula de dos mitades, en especial las que determinan la posibilidad de efectuar mediciones de precisidn en la esfera de la fisica de los reactores. Examinan las ventajas e inconvenientes de este tipo de reactor, basandose en la experiencia adquirida durante dos anos de funcionamiento. Exam in an los siguientes temas: ventajas, desde el punto de vista experimental, de la disposicion y de la construccidn en dos mitades; dimensiones y tolerancias de los elementos combustibles, y precisian con la que se puede determinar la posicion de dichos elementos; influencia de las irregularidades marginales y de heterogeneidad estructural sobre la exactitud con la que se determine la masa critica de un conjunto 'ideal' equivalente; posibilidad de reproducir las condiciones criticas despues de desmontar el conjunto o de separar las dos mitades; variaciones de la reactividad cuando se separan las dos mitades, en especial los efectos de una carga asimetrica; sensibilidad de varios contadores

Neurobiologia dos transtornos do controle dos impulsos The neurobiology of impulse control disorders

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Wendol A Williams

2008-05-01

Full Text Available OBJETIVO: Revisar os artigos sobre substratos neurobiológicos dos transtornos do controle dos impulsos. O jogo patológico é o foco central desta revisão na medida em que a maioria dos estudos biológicos dos formalmente classificados como transtornos do controle dos impulsos examinou este transtorno. MÉTODO: Foi feita uma busca no banco de dados Medline de artigos publicados de 1966 até o presente para identificar aqueles relevantes para serem revisados neste artigo. DESFECHOS: Estudos pré-clínicos sugerem que a neuromodulação das monoaminas cerebrais está associada à tomada de decisões impulsivas e aos comportamentos de risco. Os estudos clínicos implicam diversos sistemas de neurotransmissores (serotoninérgico, dopaminérgico, adrenérgico e opióide na fisiopatologia do jogo patológico e de outros transtornos do controle dos impulsos. Estudos de neuroimagem preliminares têm indicado o córtex pré-frontal ventromedial e o estriato ventral como atuantes na fisiopatologia do jogo patológico e de outros transtornos do controle dos impulsos. As contribuições genéticas para o jogo patológico parecem substanciais e os estudos iniciais têm relacionado esse transtorno a polimorfismos alélicos específicos, ainda que os achados de varredura genômica ainda tenham que ser publicados. CONCLUSÃO: Mesmo que tenham sido logrados avanços significativos em nossa compreensão sobre os transtornos do controle dos impulsos, mais pesquisas são necessárias para ampliar o conhecimento existente e traduzir esses achados em avanços clínicos.OBJECTIVE: To review the neurobiological substrates of impulse control disorders. Pathological gambling is a main focus of the review in that most biological studies of the formal impulse control disorders have examined this disorder. METHOD: The medical database Medline from 1966 to present was searched to identify relevant articles that were subsequently reviewed to generate this manuscript

Nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

This patent describes an improved liquid metal nuclear reactor construction comprising: (a) a nuclear reactor core having a bottom platform support structure; (b) a reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core; (c) a containment structure surrounding the reactor vessel and having a sidewall spaced outwardly from the reactor vessel side wall and having a base mat spaced below the reactor vessel bottom end wall; (d) a central small diameter post anchored to the containment structure base mat and extending upwardly to the reactor vessel to axially fix the bottom end wall of the reactor vessel and provide a center column support for the lower end of the reactor core; (e) annular support structure disposed in the reactor vessel on the bottom end wall and extending about the lower end of the core; (f) structural support means disposed between the containment structure base mat and bottom end of the reactor vessel wall and cooperating for supporting the reactor vessel at its bottom end wall on the containment structure base mat to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event; (g) a bed of insulating material disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall; freely expand radially from the central post as it heats up while providing continuous support thereof; (h) a deck supported upon the wall of the containment vessel above the top open end of the reactor vessel; and (i) extendible and retractable coupling means extending between the deck and the top open end of the reactor vessel and flexibly and sealably interconnecting the reactor vessel at its top end to the deck

Participação dos Pais na Psicoterapia da Criança: Práticas dos Psicoterapeutas

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Luiz Ronaldo Freitas de Oliveira

Full Text Available Resumo A participação dos pais na psicoterapia de crianças é um tema controverso na literatura. Há autores a favor de uma abordagem mais intervencionista em relação aos pais e outros que circunscrevem seu papel à manutenção do tratamento e provimento de informações sobre a criança. O objetivo deste estudo exploratório, de levantamento, transversal, foi identificar experiências de psicoterapeutas de crianças brasileiros quanto às formas de inclusão dos pais no tratamento. Participaram 76 psicólogos, que responderam a um questionário on-line e as análises contemplaram estatística descritiva e análise de conteúdo. De acordo com os resultados, os respondentes foram predominantemente mulheres (89,5%, residentes na Região Sul (86,8%, entre 26 e 35 anos (53,9% e com até três anos de experiência clínica (43,4%. De maneira geral, os participantes incluem os pais na psicoterapia (76,3%; em entrevistas específicas (90,8%; coleta de informações (88,2%, para aconselhamento/orientação (72,4%; e para fortalecer a aliança terapêutica (61,8%. Riscos e benefícios da participação dos pais foram reportados e constituíram seis categorias: a criança como sintoma dos conflitos familiares; resistência dos pais à psicoterapia e às mudanças; cumprimento do contrato pelos pais; aliança terapêutica; compreensão da dinâmica familiar e dos sintomas da criança; e fortalecimento dos vínculos pais-filhos. Conclui-se que há tendência de inclusão dos pais, por parte dos psicoterapeutas, no processo de psicoterapia de crianças.

NÍVEL DE PREPARAÇÃO PARA LIDERANÇA, SOB A PERSPECTIVA DOS ACADÊMICOS DE CIÊNCIAS CONTÁBEIS DA UNEMAT E UNIC EM TANGARÁ DA SERRA – FORMANDOS 2013/2

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Ana Caroline Bastos Casagrande

2014-06-01

Full Text Available Em um cenário de constante crescimento do setor contábil, cada vez mais o mercado exige dos profissionais recém-formados perfis e características diferenciadas, e a liderança vem sendo uma característica de suma importância, uma vez que o contador passa de funções meramente operacionais para o contato direto com o cliente, exercendo influência na tomada de decisões, e mantendo o controle das variáreis contábeis. Este estudo aborda uma pesquisa entre os formandos de Ciências Contábeis da Universidade do Estado de Mato Grosso e da Universidade de Cuiabá de Tangará da Serra – MT, com o intuito de questionar a preparação dos acadêmicos de Ciências Contábeis como líderes no mercado de trabalho e suas perspectivas, além de, verificar as pretensões após a conclusão do curso, a preparação para assumir uma equipe, e a responsabilidade desta preparação, bem como analisar a grade destas universidades com uma universidade que seja o modelo ideal a ser seguido. As metodologias usadas foram às pesquisas: bibliográfica e descritiva buscando fundamentação teórica, e a qualitativa, quantitativa e pesquisa de campo para o levantamento dos dados, realizados através de aplicação de questionários aos formandos do curso de Ciências Contábeis da UNEMAT e da UNIC de Tangará da Serra – MT. Diante do exposto, baseado nos dados levantados, verificou-se que grande parte dos acadêmicos do oitavo semestre afirma que não sentia preparados para serem gestores e ocupar cargos de liderança, eles também julgaram que a universidade não os preparou para este tipo de desafio no mercado de trabalho. Ao analisar a grade destas universidades em questão com a de uma universidade modelo, pode-se verificar que elas estão desatualizadas em relação a suas grades curriculares, porém a UNEMAT vem passando por mudanças positivas nestes aspectos, para em 2014 passar a vigorar uma nova grade curricular que tentará se assemelhar a de uma

Marker-assisted selection of maintainer lines within an onion tropical population Seleção assistida por marcadores de linha mantenedora dentro de uma população de cebola tropical

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Carlos Antonio Fernandes Santos

2010-04-01

Full Text Available The traditional onion (Allium cepa hybrid production requires the development of maintainer and male sterile lines and also a pollinator line with good specific combination ability. We report the identification of maintainer and male-sterile onion lines within the Brazilian 'Baia Periforme' derived population, 'Alfa São Francisco', associating random field pairing of male-fertile plants with selected male-sterile plants and PCR-based marker system monitoring S, T and N-cytoplasms. Male-sterile plants produced flowers with light green anthers which were easily detected in the field. A frequency of 2.0% of male-sterile plants was estimated in the 'Alfa São Francisco' sampled population. Male-sterile plants produced the 5'cob-marker 180-bp and the orfA501-marker 473-bp fragments, suggesting the T-cytoplasm type, while the maintainer line produced only the 5'cob-marker 180-bp. These identified lines will be important to develop tropical onion hybrids well-adapted to Brazilian low latitudes and to future comparative studies with other onion cytoplasmic genic male sterility systems.A produção tradicional de híbrido de cebola (Allium cepa requer o desenvolvimento de linhas mantenedoras e linhas macho estéreis, bem como uma linha polinizadora de boa capacidade específica de combinação. Reporta-se a identificação de linhas de cebola mantenedora e macho-estéreis numa população 'Alfa São Francisco' derivada da brasileira 'Baia Periforme', associando pareamento ao acaso no campo de plantas férteis com plantas macho-estéreis e sistema de PCR para monitoramento dos citoplasmas S, T e N. Plantas macho-estéreis produziram flores com anteras verde-claras, que foram facilmente identificadas no campo. A freqüência de 2,0% de plantas macho-estéreis foi estimada dentro de uma amostra da população 'Alfa São Francisco'. Plantas macho-estéreis produziram o marcador 5´cob de 180-pb e o marcador orfA501 de 473-pb, sugerindo que o citoplasma �

Gregarine Cephaloidophora communis mawrodiadi, 1908 in the barnacle Euraphia rhyzophorae, Oliveira, 1940 from Brazil

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Lacombe Dyrce

2002-01-01

Full Text Available The gregarine Cephaloidophora communis was observed for the first time in Brazil in the barnacles Euraphia rhyzophorae collected in Angra dos Reis, Rio de Janeiro, Brazil, between 1990 and 1996. Histological studies showed growth phases of the parasite in specific parts of the digestive system. The intracellular forms occurred in the vacuoles of the intestinal cells. Syzygy was frequent, and the most common form following syzygy was cylindrical, with a single membrane. The cytoplasm of the gregarines was always irregular, dense, and occasionally presenting a dark stoch area.

A vida de Augusto, de Nicolau de Damasco: tradução acompanhada de breve introdução

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Sandra Lúcia Rodrigues da Rocha

2014-12-01

Full Text Available A Vida de Augusto, de Nicolau de Damasco (séc. I a.C., é uma das mais antigas biografias de um rei na tradição helenística. Seu valor como fonte para o estudo do gênero bíos  impõe-se por si só. Neste trabalho, apresento uma breve introdução à primeira metade da obra em sua atual forma fragmentária, assim como uma tradução dos respectivos  fragmentos para o Português.

A viagem de Pedro Álvares Cabral sob o ponto de vista náutico

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Thomaz Oscar Marcondes de Souza

1964-09-01

Full Text Available Em 1850, numa das sessões do Instituto Histórico e Geográfico Brasileiro, com sede no Rio de Janeiro, o sócio Joaquim Norberto de Sousa e Silva, baseando-se principalmente em um dos tópicos da carta que Mestre João escreveu de Pôrto Seguro a 1.° de maio de 1500 ao rei D. Manuel, concluiu a sua conferência afirmando ter sido o Brasil descoberto intencionalmente por Álvares Cabral, quando da sua viagem para Calicute.

Generation IV reactors: reactor concepts

International Nuclear Information System (INIS)

Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

2003-01-01

Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

Caracterização isoenzimática e morfológica de clones e introduções de alho Morphological and electrophoretic characterization of garlic clones

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Walter José Siqueira

1985-01-01

Full Text Available Em virtude do grande número de denominações locais para clones de alho, nem sempre correspondentes a materiais distintos, conduziu-se o presente estudo objetivando a caracterização e classificação de 72 clones e introduções de alho (Allium sativum L., e um clone de alho-rei (A. ampeloprasum L.. Isso foi feito analisando as isoenzimas alcooldesidrogenase (ADH, esterase (EST, peroxidase (PRX e fosfoglucoisomerase (PGI através da técnica de eletroforese horizontal em gel de amido hidrolisado de batata. Verificou-se que os clones nacionais e introduzidos se enquadram nos grupos aqui denominados DIKA ou CJLB, respectivamente para os padrões de ADH, EST, PRX e PGI. Entretanto, os padrões CILB, CJKB e CIKB foram observados em alguns clones estrangeiros, sugerindo sua maior variabilidade em relação aos nacionais. O alho-rei apresentou padrões diferentes dos encontrados na espécie A. sativum L. A associação dos resultados da técnica de eletroforese de isoenzinas com a caracterização morfológica da parte aérea, bulbos, bulbilhos, coloração externa dos bulbos e bulbilhos e ciclo cultural, permitiu a classificação dos clones nacionais de alho em 19 grupos distintos.Since there exist different local names for the same garlic (Allium sativum L. clones, it was made an attempt to distinguish them by the morphology, cycle and isozyme electrophoresis. The isozyme analysis of alcoholdehydrogenase, esterase, peroxydase and phosphoglucoisomerase separated the Brazilian clones in two groups. The foreign clones had different band patterns adding other three more groups. Morphology of bulbs and clones allowed the separation of clones into eight groups; top morphology into ten and cycle length into three. Morphology, cycle and electrophoresis together characterized the seventy two analysed clones into nineteen distinct groups.

“Financing for urbanizing” Rio de Janeiro: José de Oliveira Reis between the Department of Urban Planning and the Superintendency of Urban Planning and Sanitation in the implementation of the Plano de Realizações

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Rodrigo Santos de Faria

2009-06-01

Full Text Available The present article is characterized by the analysis of the insertion of engineer José de Oliveira Reis in a specific moment (not the only one of the continued construction process of the municipal administrative instances in charge of urban planning and urban plans in Rio de Janeiro. From 1956 through 1960, José de Oliveira Reis reassumes, for the last time, the Department of Urban Planning of Distrito Federal City Hall, actively taking part in the ascribed institutional construction-creationimprovement process of municipal organs responsible for the planning, financing and execution of public urban works. In this case, for the creation of the Superintendency of Urban Planning and Sanitation (SURSAN of the Special Fund for Public Works, and for the implementation of the Execution Plan issued in deliberations in Law no. 899, of November 28th 1957. The understanding of the national context – in the scope of the Brazilian Municipalist Movement – of this whole process of the creation of municipal instances in the urban planning sector, during the 1950s, is also fundamental for comprehending engineer José de Oliveira Reis’s positions as the director of the Department. Centered in the basic precepts of political and financial autonomy, Brazilian Municipalism preconizes an important set of deliberations resulting from National Congresses of Brazilian Municipalities – especially from the four first ones - , among which the need for the implementation of mechanisms and instruments for increasing municipal budgets in the execution of works, that is, “financing for urbanizing”. In the case of the Execution Plan, through the focus in the road system problematics undertaken by the Department of Urban Planning, explicating debate on the construction of the Perimetral Avenue.

Nuclear reactor

International Nuclear Information System (INIS)

Hattori, Sadao; Sato, Morihiko.

1994-01-01

Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

The CAREM reactor and present currents in reactor design

International Nuclear Information System (INIS)

Ordonez, J.P.

1990-01-01

INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author) [es

Teologia no renascimento e na reforma = Theology in the Renaissance and the Reformation

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Zilles, Urbano

2013-01-01

Full Text Available Na Idade Média decadente, a teologia católica realizou-se no contexto de uma Igreja que passou pelo “cativeiro babilônico” e pelo “cisma do Ocidente”, que enfraqueceu a autoridade dos papas não só sobre o poder temporal de imperadores e reis, mas também fixou-se na doutrina dos grandes expoentes da Escolástica, desconsiderando a contribuição inovadora de filósofos e teólogos não escolásticos e dos grandes místicos. A teologia desvinculou-se, por um lado, das fontes bíblicas e, por outro, da vivência da fé. Dessa maneira, abriu-se espaço para a Reforma que dividiu o cristianismo do Ocidente e criou um abismo que separa a doutrina católica oficial do desenvolvimento científico-cultural desde o Renascimento até o Concílio Vaticano II

Os supostos espaços de discussão futebolística na televisão: as "mesas redondas"

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Thiago Aragão Escher

2012-03-01

Full Text Available Este artigo analisa os programas esportivos que supostamente são os espaços de discussão do futebol. Para tanto, escolhemos os programas "Terceiro Tempo", da Rede Bandeirantes de Televisão e "Mesa Redonda", da TV Gazeta, por serem os mais relevantes do gênero e por serem constantemente citados nas respostas dos entrevistados de Reis (2008. Analisamos a estrutura de apresentação dos programas veiculados no ano de 2008, durante a realização do Campeonato Brasileiro de futebol, principalmente sua composição com o merchandising. Conclui-se que a compreensão desse processo não deve ser visto como uma mera mercadorização do esporte, e sim como uma mistura entre o processo simbólico que existe no futebol e sua latente transformação em mercadoria, que contribui também para uma visão fragmentada da violência no futebol e dos torcedores.

Modelling of tritium dispersion from postulated accidental release of nuclear power plants

International Nuclear Information System (INIS)

Soares, Abner Duarte

2010-01-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. This exercise was accomplished with the aid of a code system (SisBAHIA) developed in the Rio de Janeiro Federal University (COPPE/UFRJ). The CANDU reactor is one that uses heavy water (D 2 O) as moderator and coolant of the core. It was postulated, then, the LOCA (Loss of Coolant Accident) accident in the emergency cooling system of the nucleus (without fusion), where was lost 66 m 3 of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped and operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m 3 ) during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x10 9 to 5x10 5 Bq/m 3 close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value ( 3 ). (author)

Modelling of tritium dispersion from postulated accidental release of nuclear power plants; Modelagem da dispersao de tritio a partir de liberacoes acidentais postuladas de centrais nucleares

Energy Technology Data Exchange (ETDEWEB)

Soares, Abner Duarte

2010-07-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. This exercise was accomplished with the aid of a code system (SisBAHIA) developed in the Rio de Janeiro Federal University (COPPE/UFRJ). The CANDU reactor is one that uses heavy water (D{sub 2}O) as moderator and coolant of the core. It was postulated, then, the LOCA (Loss of Coolant Accident) accident in the emergency cooling system of the nucleus (without fusion), where was lost 66 m{sup 3} of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped and operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m{sup 3} ) during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x10{sup 9} to 5x10{sup 5} Bq/m{sup 3} close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (< 11 kBq/m{sup 3}). (author)

Planning the nuclear contribution to the Brazilian power program

International Nuclear Information System (INIS)

Barbalho, A. Rodrigues; Alves, R. Nazare; Pinto, C. Syllus M.; Souza Santos, T.D. de; Abrao, A.

1977-01-01

The thermo-electric power in Brazil accounts for less than 20% of the total generating capacity. Brazil's power is essentially generated hydraulically, which grants the growing development. The electric energy consumption keeps growing, with the annual average rate of 13%/year in the last five years. The present installed capacity is 20 000 MWe and the projections are: 35 000MWe, in 1980; 50 000 MWe in 1985; 75 000 MWe, in 1990 and 150 000 MWe, in 2 000. Most of the hydraulic resources are located in remote areas of the country, very far from the consumption centers. Under the agreement between the Federal Republic of Germany and Brazil (signed in June 1975), besides the nuclear power station, American made, under construction in Agra dos Reis, with a power capacity of 626 MWe, two more units, each one with 1 300 MWe capacity are to be erected at the same site, and planned to be in operation in 1982 and 1983. Several joint German-Brazilian companies will be established for reactor and fuel manufacture, in the country. The Brazilian state holding nuclear company, Empresas Nucleares Brasileiras S/A., NUCLEBRAS, will participate in the formation of all joint companies with at least 51% of capital investments. The Brazilian Government will spend 10 billion dollars (U.S.), during the agreement's duration, to make its industry stronger, to develop its technology and to reduce its dependence on energy imports. Brazil's target: full independence in nuclear technology (including reactor manufacture and complete fuel cycle) in about 15 years [es

Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants

International Nuclear Information System (INIS)

Aguiar, Andre Silva de; Simoes Filho, Francisco Fernando Lamego; Lapa, Celso Marcelo Franklin; Alvim, Antonio Carlos Marques; Soares, Abner Duarte

2013-01-01

This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamics and transport for the simulation of tritium dispersion caused by an accident in a CANDU reactor located in the ongoing Angra 3 site. It was postulated, then, the LOCA - Loss of Coolant Accident -, accident in the emergency cooling system of the nucleus ( without fusion), where was lost 66m 3 of soda almost instantaneously. This inventory contained 35 PBq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios ( plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1MBq/m 3 ), during the first 14 days after the accident. The main difference between the scenario without and with seawater recirculation (pumping and discharge) is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1x10 9 to 5x10 5 Bq/m 3 close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value ( 3 ). (author)

Neutron behavior, reactor control, and reactor heat transfer. Volume four

International Nuclear Information System (INIS)

Anon.

1986-01-01

Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant)

Reactor science and technology: operation and control of reactors

International Nuclear Information System (INIS)

Qiu Junlong

1994-01-01

This article is a collection of short reports on reactor operation and research in China in 1991. The operation of and research activities linked with the Heavy Water Research Reactor, Swimming Pool Reactor and Miniature Neutron Source Reactor are briefly surveyed. A number of papers then follow on the developing strategies in Chinese fast breeder reactor technology including the conceptual design of an experimental fast reactor (FFR), theoretical studies of FFR thermo-hydraulics and a design for an immersed sodium flowmeter. Reactor physics studies cover a range of topics including several related to work on zero power reactors. The section on reactor safety analysis is concerned largely with the assessment of established, and the presentation of new, computer codes for use in PWR safety calculations. Experimental and theoretical studies of fuels and reactor materials for FBRs, PWRs, BWRs and fusion reactors are described. A final miscellaneous section covers Mo-Tc isotope production in the swimming pool reactor, convective heat transfer in tubes and diffusion of tritium through plastic/aluminium composite films and Li 2 SiO 3 . (UK)

Nuclear power reactors

International Nuclear Information System (INIS)

1982-11-01

After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

O rei do pop e as nuances da pós-modernidade trágica

Directory of Open Access Journals (Sweden)

Nayana M. Moraes

2010-12-01

Full Text Available Este artigo mostra a relação das celebridades com os aspectos trágicos de suas vidas e o envolvimento dos fãs a partir da catarse. Todos estes termos imbricados dialogarão com um dos gêneros literários mais antigos: a tragédia grega. Esta permeará um entendimento acerca da forma com que nós, espectadores, analisamos alguns famosos, bem como sua influência na indústria do entretenimento. Neste contexto, alguns deles não conseguem adquirir um equilíbrio entre a fama e sua vida pessoal, que cai diante de sua hybris (desequilíbrio interno. E um destes artistas, considerado o mito da música e do entretenimento, compreenderá esta discussão: Michael Jackson. O filósofo grego Aristóteles discutiu e revigorou a importância e verossimilhança desta literatura no ser humano. Veremos, entretanto, que mesmo com estes conflitos, o mito permanece.

Research reactors

International Nuclear Information System (INIS)

Merchie, Francois

2015-10-01

This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

Roles of plasma neutron source reactor in development of fusion reactor engineering: Comparison with fission reactor engineering

International Nuclear Information System (INIS)

Hirayama, Shoichi; Kawabe, Takaya

1995-01-01

The history of development of fusion power reactor has come to a turning point, where the main research target is now shifting from the plasma heating and confinement physics toward the burning plasma physics and reactor engineering. Although the development of fusion reactor system is the first time for human beings, engineers have experience of development of fission power reactor. The common feature between them is that both are plants used for the generation of nuclear reactions for the production of energy, nucleon, and radiation on an industrial scale. By studying the history of the development of the fission reactor, one can find the existence of experimental neutron reactors including irradiation facilities for fission reactor materials. These research neutron reactors played very important roles in the development of fission power reactors. When one considers the strategy of development of fusion power reactors from the points of fusion reactor engineering, one finds that the fusion neutron source corresponds to the neutron reactor in fission reactor development. In this paper, the authors discuss the roles of the plasma-based neutron source reactors in the development of fusion reactor engineering, by comparing it with the neutron reactors in the history of fission power development, and make proposals for the strategy of the fusion reactor development. 21 refs., 6 figs

Reactor physics aspects of CANDU reactors

International Nuclear Information System (INIS)

Critoph, E.

1980-01-01

These four lectures are being given at the Winter Course on Nuclear Physics at Trieste during 1978 February. They constitute part of the third week's lectures in Part II: Reactor Theory and Power Reactors. A physical description of CANDU reactors is given, followed by an overview of CANDU characteristics and some of the design options. Basic lattice physics is discussed in terms of zero energy lattice experiments, irradiation effects and analytical methods. Start-up and commissioning experiments in CANDU reactors are reviewed, and some of the more interesting aspects of operation discussed - fuel management, flux mapping and control of the power distribution. Finally, some of the characteristics of advanced fuel cycles that have been proposed for CANDU reactors are summarized. (author)

Research reactors

International Nuclear Information System (INIS)

Kowarski, L.

1955-01-01

It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

Informatividade dos lucros contábeis e divulgação dos ativos biológicos: evidências brasileiras

OpenAIRE

Holanda, Allan Pinheiro

2013-01-01

A pesquisa tem o objetivo de investigar a influência exercida pela divulgação dos ativos biológicos na informatividade dos lucros contábeis nas firmas brasileiras listadas na BM&FBovespa, considerando-se o período de 2010 a 2011. Para a investigação da informatividade dos ativos biológicos foi utilizada a adaptação dos modelos propostos por Easton e Harris (1991) e Francis e Schipper (1999). Os ativos biológicos, por sua vez, foram mensurados de duas maneiras, pela simples existência da c...

Comparison between TRU burning reactors and commercial fast reactor

International Nuclear Information System (INIS)

Fujimura, Koji; Sanda, Toshio; Ogawa, Takashi

2001-03-01

Research and development for stabilizing or shortening the radioactive wastes including in spent nuclear fuel are widely conducted in view point of reducing the environmental impact. Especially it is effective way to irradiate and transmute long-lived TRU by fast reactors. Two types of loading way were previously proposed. The former is loading relatively small amount of TRU in all commercial fast reactors and the latter is loading large amount of TRU in a few TRU burning reactors. This study has been intended to contribute to the feasibility studies on commercialized fast reactor cycle system. The transmutation and nuclear characteristics of TRU burning reactors were evaluated and compared with those of conventional transmutation system using commercial type fast reactor based upon the investigation of technical information about TRU burning reactors. Major results are summarized as follows. (1) Investigation of technical information about TRU burning reactors. Based on published reports and papers, technical information about TRU burning reactor concepts transmutation system using convectional commercial type fast reactors were investigated. Transmutation and nuclear characteristics or R and D issue were investigated based on these results. Homogeneously loading of about 5 wt% MAs on core fuels in the conventional commercial type fast reactor may not cause significant impact on the nuclear core characteristics. Transmutation of MAs being produced in about five fast reactors generating the same output is feasible. The helium cooled MA burning fast reactor core concept propose by JAERI attains criticality using particle type nitride fuels which contain more than 60 wt% MA. This reactor could transmute MAs being produced in more than ten 1000 MWe-LWRs. Ultra-long life core concepts attaining more than 30 years operation without refueling by utilizing MA's nuclear characteristics as burnable absorber and fertile nuclides were proposed. Those were pointed out that

Nuclear reactor types

International Nuclear Information System (INIS)

Jones, P.M.S.

1987-01-01

The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

Reactor containment and reactor safety in the United States

International Nuclear Information System (INIS)

Kouts, H.

1986-01-01

The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

Reactor Physics

International Nuclear Information System (INIS)

Ait Abderrahim, A.

2002-01-01

SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2001-04-01

The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

Reactor Physics

International Nuclear Information System (INIS)

Ait Abderrahim, A.

2001-01-01

The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

Reactor

International Nuclear Information System (INIS)

Toyama, Masahiro; Kasai, Shigeo.

1978-01-01

Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2002-04-01

SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

Research reactor standards and their impact on the TRIGA reactor community

International Nuclear Information System (INIS)

Richards, W.J.

1980-01-01

The American Nuclear Society has established a standards committee devoted to writing standards for research reactors. This committee was formed in 1971 and has since that time written over 15 standards that cover all aspects of research reactor operation. The committee has representation from virtually every group concerned with research reactors and their operation. This organization includes University reactors, National laboratory reactors, Nuclear Regulatory commission, Department of Energy and private nuclear companies and insurers. Since its beginning the committee has developed standards in the following areas: Standard for the development of technical specifications for research reactors; Quality control for plate-type uranium-aluminium fuel elements; Records and reports for research reactors; Selection and training of personnel for research reactors; Review of experiments for research reactors; Research reactor site evaluation; Quality assurance program requirements for research reactors; Decommissioning of research reactors; Radiological control at research reactor facilities; Design objectives for and monitoring of systems controlling research reactor effluents; Physical security for research reactor facilities; Criteria for the reactor safety systems of research reactors; Emergency planning for research reactors; Fire protection program requirements for research reactors; Standard for administrative controls for research reactors. Besides writing the above standards, the committee is very active in using communications with the nuclear regulatory commission on proposed rules or positions which will affect the research reactor community

A Rickettsia Genome Overrun by Mobile Genetic Elements Provides Insight into the Acquisition of Genes Characteristic of an Obligate Intracellular Lifestyle

Science.gov (United States)

Joardar, Vinita; Williams, Kelly P.; Driscoll, Timothy; Hostetler, Jessica B.; Nordberg, Eric; Shukla, Maulik; Walenz, Brian; Hill, Catherine A.; Nene, Vishvanath M.; Azad, Abdu F.; Sobral, Bruno W.; Caler, Elisabet

2012-01-01

We present the draft genome for the Rickettsia endosymbiont of Ixodes scapularis (REIS), a symbiont of the deer tick vector of Lyme disease in North America. Among Rickettsia species (Alphaproteobacteria: Rickettsiales), REIS has the largest genome sequenced to date (>2 Mb) and contains 2,309 genes across the chromosome and four plasmids (pREIS1 to pREIS4). The most remarkable finding within the REIS genome is the extraordinary proliferation of mobile genetic elements (MGEs), which contributes to a limited synteny with other Rickettsia genomes. In particular, an integrative conjugative element named RAGE (for Rickettsiales amplified genetic element), previously identified in scrub typhus rickettsiae (Orientia tsutsugamushi) genomes, is present on both the REIS chromosome and plasmids. Unlike the pseudogene-laden RAGEs of O. tsutsugamushi, REIS encodes nine conserved RAGEs that include F-like type IV secretion systems similar to that of the tra genes encoded in the Rickettsia bellii and R. massiliae genomes. An unparalleled abundance of encoded transposases (>650) relative to genome size, together with the RAGEs and other MGEs, comprise ∼35% of the total genome, making REIS one of the most plastic and repetitive bacterial genomes sequenced to date. We present evidence that conserved rickettsial genes associated with an intracellular lifestyle were acquired via MGEs, especially the RAGE, through a continuum of genomic invasions. Robust phylogeny estimation suggests REIS is ancestral to the virulent spotted fever group of rickettsiae. As REIS is not known to invade vertebrate cells and has no known pathogenic effects on I. scapularis, its genome sequence provides insight on the origin of mechanisms of rickettsial pathogenicity. PMID:22056929

Reactor operation

CERN Document Server

Shaw, J

2013-01-01

Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

An Evaluation of Mobile Applications for Reproductive Endocrinology and Infertility Providers.

Science.gov (United States)

Shaia, Kathryn L; Farag, Sara; Chyjek, Kathy; Knopman, Jaime; Chen, Katherine T

2017-03-01

To identify and rate reproductive endocrinology and infertility (REI) mobile applications (apps) targeted toward REI providers. A list of REI apps was found in both the Apple iTunes and Google Play stores using the following seven MeSH terms: reproductive endocrinology, REI, infertility, fertility, In Vitro Fertilization, IVF, and embryology. Patient-centered apps were excluded. The remaining apps were then evaluated for accuracy using reliable references. Mobile technology. None. Accurate apps were evaluated for comprehensiveness (the extent of the ability to aid in clinical decision-making) and rated with objective and subjective components using the APPLICATIONS scoring system. Using the seven REI-related MeSH terms, 985 apps and 1,194 apps were identified in the Apple iTunes and Google Play stores, respectively. Of these unique apps, only 20 remained after excluding patient-centered apps. Upon further review for applicability to REI specifically and content accuracy, only seven apps remained. These seven apps were then rated using the APPLICATIONS scoring system. Only 0.32% of 2,179 apps reviewed for this study were useful to REI providers. There is potential for further mobile resource development in the area of REI, given the limited number and varying comprehensiveness and quality of available apps.

Improved nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding liquid metal coolant and housing the core within the pool. A generally cylindrical concrete containment structure surrounds the reactor vessel and a central support pedestal is anchored to the containment structure base mat and supports the bottom wall of the reactor vessel and the reactor core. The periphery of the reactor vessel bore is supported by an annular structure which allows thermal expansion but not seismic motion of the vessel, and a bed of thermally insulating material uniformly supports the vessel base whilst allowing expansion thereof. A guard ring prevents lateral seismic motion of the upper end of the reactor vessel. The periphery of the core is supported by an annular structure supported by the vessel base and keyed to the vessel wall so as to be able to expand but not undergo seismic motion. A deck is supported on the containment structure above the reactor vessel open top by annular bellows, the deck carrying the reactor control rods such that heating of the reactor vessel results in upward expansion against the control rods. (author)

Reactor as furnace and reactor as lamp

International Nuclear Information System (INIS)

Goldanskii, V.I.

1992-01-01

There are presented general characteristics of the following ways of transforming of nuclear energy released in reactors into chemical : ordinary way (i.e. trough the heat, mechanical energy and electricity); chemonuclear synthesis ; use of high-temperature fuel elements (reactor as furnace); use of the mixed nγ-radiation of reactors; use of the radiation loops; radiation - photochemical synthesis (reactor as lamp). Advantage and disadvantages of all above variants are compared. The yield of the primary product of fixation of nitrogen (nitric oxide NO) in reactor with the high-temperature (above ca. 1900degC) fuel elements (reactor-furnace) can exceed W ∼ 200 kg per gram of burned uranium. For the latter variant (reactor-lamp) the yield of chemical products can reach W ∼ 60 kg. per gram of uranium. Such values of W are close to or even strongly exceed the yields of chemical products for other abovementioned variants and - what is particularly important - are not connected to the necessity of archscrupulous removal of radioactive contamination of products. (author)

Comparative analysis of three atmospheric dispersion coefficient systems at the Angra dos Reis, RJ, region

International Nuclear Information System (INIS)

Biagio, Rosa Maria de Souza

1982-01-01

A comparative analysis was made in this work among Pasquill-Gifford (PG) atmospheric dispersion coefficients and those determined at the Juelich and Karlsruhe sites with the purpose of suggesting which one would be the most applicable to the Angra site. Each one of the three systems was determined by different experiments, carried out over sites with diversified features. The systems of Juelich and Karlsruhe were obtained over sites with high surface roughness and from stacks (elevated releases), while the PG system was obtained over sites with a small surface roughness and from ground level releases. The results of the application of these systems at a complex site like Angra,which has a highly diversified structure encompassing sea, vegetation, predominance of light winds and stable stability classes, show that the PG system, the most used in the world, is still the best choice. (author)

Development of Reactor Console Simulator for PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Mohd Idris Taib; Izhar Abu Hussin; Mohd Khairulezwan Abdul Manan; Nufarhana Ayuni Joha; Mohd Sabri Minhat

2012-01-01

The Reactor Console Simulator will be an interactive tool for operator training and teaching of PUSPATI TRIGA Reactor. Behaviour and characteristic for reactor console and reactor itself can be evaluated and understand. This Simulator will be used as complement for actual present reactor console. Implementation of man-machine interface is using computer screens, keyboard and mouse. Multiple screens are used to match the physical of present reactor console. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate the estimated reactor console parameters. (author)

O Jardim dos Sonhos

Directory of Open Access Journals (Sweden)

RAUL CÂNOVAS

2010-06-01

Full Text Available O jardim dos sonhos sempre foi um ideal dos homens. No Antigo Egito, já se falava em um jardim sempre verde para onde as pessoas de bom coração iam após a morte. E na mitologia grega, um lindo jardim era palco das festas bucólicas dos deuses. As grandes religiões também citavam jardins como paraísos, como o Jardim do Éden. Neste artigo, Raul Cânovas nos leva a refletir sobre o sentido de um “jardim perfeito”, sem tratar a perfeição como apenas plástica e estruturada com exatidão, mas referindo-se a um jardim que nos inspire e emocione, emancipado de modismos passageiros. O paisagista também nos alerta sobre as condições mutáveis de um jardim, que nunca está finalizado. O paisagismo não é apenas técnica; é também sensibilidade, utilidade, sustentabilidade e equilíbrio das forças da natureza.

The United States foreign research reactor spent nuclear fuel acceptance program: Proposal to modify the program

International Nuclear Information System (INIS)

Messick, C.E.

2005-01-01

The United States Department of Energy (DOE), in consultation with the Department of State (DOS), adopted the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel in May 1996. The policy was slated to expire in May 2009. However, in October 2003, a petition requesting a program extension was delivered to the United States Secretary of Energy from a group of research reactor operators from foreign countries. In April 2004, the Secretary directed DOE undertake an analysis, as required by the National Environmental Policy Act (NEPA), to consider potential extension of the Program. On December 1, 2004, a Federal Register Notice was issued approving the program extension. This paper discusses the findings from the NEPA analysis and the potential changes in the program that may result from implementation of the proposed changes. (author)

Reactor safeguards

CERN Document Server

Russell, Charles R

1962-01-01

Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

International Nuclear Information System (INIS)

Greneche, D.

2014-01-01

This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

Control of reactor coolant flow path during reactor decay heat removal

International Nuclear Information System (INIS)

Hunsbedt, A.N.

1988-01-01

This patent describes a sodium cooled reactor of the type having a reactor hot pool, a slightly lower pressure reactor cold pool and a reactor vessel liner defining a reactor vessel liner flow gap separating the hot pool and the cold pool along the reactor vessel sidewalls and wherein the normal sodium circuit in the reactor includes main sodium reactor coolant pumps having a suction on the lower pressure sodium cold pool and an outlet to a reactor core; the reactor core for heating the sodium and discharging the sodium to the reactor hot pool; a heat exchanger for receiving sodium from the hot pool, and removing heat from the sodium and discharging the sodium to the lower pressure cold pool; the improvement across the reactor vessel liner comprising: a jet pump having a venturi installed across the reactor vessel liner, the jet pump having a lower inlet from the reactor vessel cold pool across the reactor vessel liner and an upper outlet to the reactor vessel hot pool

The research reactors their contribution to the reactors physics

International Nuclear Information System (INIS)

Barral, J.C.; Zaetta, A.; Johner, J.; Mathoniere, G.

2000-01-01

The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

Reactor noise analysis of experimental fast reactor 'JOYO'

International Nuclear Information System (INIS)

Ohtani, Hideji; Yamamoto, Hisashi

1980-01-01

As a part of dynamics tests in experimental fast reactor ''JOYO'', reactor noise tests were carried out. The reactor noise analysis techniques are effective for study of plant characteristics by determining fluctuations of process signals (neutron signal, reactor inlet temperature signals, etc.), which are able to be measured without disturbances for reactor operations. The aims of reactor noise tests were to confirm that no unstable phenomenon exists in ''JOYO'' and to gain initial data of the plant for reference of the future data. Data for the reactor noise tests treated in this paper were obtained at 50 MW power level. Fluctuations of process signals were amplified and recorded on analogue tapes. The analysis was performed using noise code (NOISA) of digital computer, with which statistical values of ASPD (auto power spectral density), CPSD (cross power spectral density), and CF (coherence function) were calculated. The primary points of the results are as follows. 1. RMS value of neutron signal at 50 MW power level is about 0.03 MW. This neutron fluctuation is not disturbing reactor operations. 2. The fluctuations of A loop reactor inlet temperatures (T sub(AI)) are larger than the fluctuations of B loop reactor inlet temperature (T sub(BI)). For this reason, the major driving force of neutron fluctuations seems to be the fluctuations of T sub(AI). 3. Core and blanket subassemblies can be divided into two halves (A and B region), with respect to the spacial motion of temperature in the reactor core. A or B region means the region in which sodium temperature fluctuations in subassembly are significantly affected by T sub(AI) or T sub(BI), respectively. This phenomenon seems to be due to the lack of mixing of A and B loop sodium in lower plenum of reactor vessel. (author)

Os Fungos no Funcionamento dos Ecossistemas Florestais

OpenAIRE

Santos-Silva, Celeste; Machado, Helena

2011-01-01

Os fungos no funcionamento dos ecossistemas Florestais: Papel dos fungos sapróbios na degradação da matériaorgânica Papel dos fungos micorrízicos na nutrição e saúde das árvores Diversidade fúngica e estabilidade das florestas Relações entre os fungos e os animais Doenças radiculares associadas ao declínio do montado de sobro e azinho

Effect of temperature on two-phase anaerobic reactors treating slaughterhouse wastewater

Directory of Open Access Journals (Sweden)

Simone Beux

2007-11-01

Full Text Available The effectiveness of the anaerobic treatment of effluent from a swine and bovine slaughterhouse was assessed in two sets of two-phase anaerobic digesters, operated with or without temperature control. Set A, consisting of an acidogenic reactor with recirculation and an upflow biological filter as the methanogenic phase, was operated at room temperature, while set B, consisting of an acidogenic reactor without recirculation and an upflow biological filter as the methanogenic phase, was maintained at 32°C. The methanogenic reactors showed COD (Chemical Demand of Oxygen removal above 60% for HRT (Hydraulic Retention Time values of 20, 15, 10, 8, 6, 4, and 2 days. When the HRT value in those reactors was changed to 1 day, the COD percentage removal decreased to 50%. The temperature variations did not have harmful effects on the performance of reactors in set A.Avaliou-se a eficiência do tratamento anaeróbio de efluente de matadouro de suínos e bovinos em dois conjuntos de biodigestores anaeróbios de duas fases, operados com e sem controle de temperatura. O conjunto A, formado por um reator acidogênico com recirculação e um filtro biológico de fluxo ascendente, foi operado a temperatura ambiente e o conjunto B, formado por um reator de fluxo ascendente e um filtro biológico de fluxo ascendente, foi mantido a 32°C. Os reatores metanogênicos apresentaram remoção de DQO acima de 60 % para os TRHs de 20, 15, 10, oito, seis, quatro e dois dias. Quando o TRH destes reatores foi mudado para um dia observou-se uma queda da porcentagem de remoção de DQO para 50 %. As variações de temperatura parecem não ter prejudicado o desempenho dos reatores do conjunto A.

Reactor physics and reactor computations

International Nuclear Information System (INIS)

Ronen, Y.; Elias, E.

1994-01-01

Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

Reactor water spontaneous circulation structure in reactor pressure vessel

International Nuclear Information System (INIS)

Takahashi, Kazumi

1998-01-01

The gap between the inner wall of a reactor pressure vessel of a BWR type reactor and a reactor core shroud forms a down comer in which reactor water flows downwardly. A feedwater jacket to which feedwater at low temperature is supplied is disposed at the outer circumference of the pressure vessel just below a gas/water separator. The reactor water at the outer circumferential portion just below the air/water separator is cooled by the feedwater jacket, and the feedwater after cooling is supplied to the feedwater entrance disposed below the feedwater jacket by way of a feedwater introduction line to supply the feedwater to the lower portion of the down comer. This can cool the reactor water in the down comer to increase the reactor water density in the down comer thereby forming strong downward flows and promote the recycling of the reactor water as a whole. With such procedures, the reactor water can be recycled stably only by the difference of the specific gravity of the reactor water without using an internal pump. In addition, the increase of the height of the pressure vessel can be suppressed. (I.N.)

Reactor

International Nuclear Information System (INIS)

Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

1979-01-01

Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

Reactor Physics Training

International Nuclear Information System (INIS)

Baeten, P.

2007-01-01

University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

FBR type reactor

International Nuclear Information System (INIS)

Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

1994-01-01

In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

RB Research nuclear reactor RB reactor, Annual report for 2000

International Nuclear Information System (INIS)

Milosevic, M.

2000-12-01

Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

Reactor container

International Nuclear Information System (INIS)

Kato, Masami; Nishio, Masahide.

1987-01-01

Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

Reactor Physics Programme

Energy Technology Data Exchange (ETDEWEB)

De Raedt, C

2000-07-01

The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

Reactor Physics Programme

International Nuclear Information System (INIS)

De Raedt, C.

2000-01-01

The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

A percepção dos trabalhadores de enfermagem sobre o manejo dos resíduos químicos perigosos

Directory of Open Access Journals (Sweden)

Taiza Florêncio Costa

2012-12-01

Full Text Available Este estudo objetivou identificar a percepção dos trabalhadores de enfermagem sobre o manejo dos resíduos químicos perigosos no Hospital Universitário da Universidade de São Paulo e elaborar uma proposta para o manejo desses resíduos. Trata-se de pesquisa de abordagem qualitativa, cuja amostra foi intencional, composta por dezoito trabalhadores de enfermagem. A coleta de dados foi realizada por meio da técnica de grupo focal. Com a análise temática foram identificadas quatro categorias que evidenciaram a deficiência de treinamento nas etapas do manejo, como a primeira dificuldade expressa, tendo aparecido ainda o desconhecimento da exposição e impactos, assim como o uso dos equipamentos de proteção individual em detrimento da proteção coletiva, seguidos das sugestões quanto às medidas de competência institucional e dos trabalhadores para o manejo seguro dos resíduos químicos perigosos. Esses dados permitiram recomendar propostas para o manejo adequado dos resíduos químicos perigosos pela enfermagem.

A percepção dos trabalhadores de enfermagem sobre o manejo dos resíduos químicos perigosos

Directory of Open Access Journals (Sweden)

Taiza Florêncio Costa

Full Text Available Este estudo objetivou identificar a percepção dos trabalhadores de enfermagem sobre o manejo dos resíduos químicos perigosos no Hospital Universitário da Universidade de São Paulo e elaborar uma proposta para o manejo desses resíduos. Trata-se de pesquisa de abordagem qualitativa, cuja amostra foi intencional, composta por dezoito trabalhadores de enfermagem. A coleta de dados foi realizada por meio da técnica de grupo focal. Com a análise temática foram identificadas quatro categorias que evidenciaram a deficiência de treinamento nas etapas do manejo, como a primeira dificuldade expressa, tendo aparecido ainda o desconhecimento da exposição e impactos, assim como o uso dos equipamentos de proteção individual em detrimento da proteção coletiva, seguidos das sugestões quanto às medidas de competência institucional e dos trabalhadores para o manejo seguro dos resíduos químicos perigosos. Esses dados permitiram recomendar propostas para o manejo adequado dos resíduos químicos perigosos pela enfermagem.

O descobrimento da América: o tratado de Tordesillas e as molucas

Directory of Open Access Journals (Sweden)

Thomaz Oscar Marcondes de Souza

1962-09-01

Full Text Available Mais ou menos entre fins de 1483 e comêço de 1484, Colombo se apresentou a D. João II, rei de Portugal, solicitando navios e gente para atingir "o país das especiarias" por uma rota completamente oposta àquela procurada pelos portuguêses e, segundo narra o cronista João Barros, apelidado o Tito-Lívio dos lusitanos, pelo alto mérito da sua obra Décadas da Ásia, começada em 1539 mas só publicada pela primeira vez em 1552, mandou o referido monarca português que o projeto fôsse en-viado aos que há muito tempo dirigiam a navegação do rei-no, sendo êles o bispo de Ceuta, D. Diogo Ortiz e os Mestres José Vizinho e Rodrigo, médicos e doutos nas ciências mate-máticas e cosmográficas, os quais depois de ouvirem demora-damente a exposição do Genovês, a julgaram errônea e mes-mo imaginária, por ser ela baseada em coisas da ilha de Ci-pango de Marco Polo.

Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007; Padrao da mortalidade da populacao circunvizinha a Central Nuclear Almirante Alvaro Alberto / 1986 a 2007

Energy Technology Data Exchange (ETDEWEB)

Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos [Fundacao Eletronuclear de Assistencia Medica (CIRA/FEAM), Angra dos Reis, RJ (Brazil). Centro de Informacoes sobre Radioepidemiologia; Xavier, Diego Ricardo [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil). lnst. de Comunicacao e Informacao Cientifica e Tecnologica; Silva, Roseli Monteiro da [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil)

2011-05-15

This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

Dom Sebastião: do mito português à adoração maranhense.

OpenAIRE

Rayan Dominici

2012-01-01

O presente trabalho se propõe a analisar a vida e morte de Dom Sebastião destacando o contexto e os fatores que propiciaram a transposição do movimento sebastianista, que originalmente era português, para o Maranhão onde aparece em vários aspectos da cultura e da religião afro-brasileira. Aqui buscaremos compreender como um Rei, que tradicionalmente era católico, e que teria morrido na batalha de Alcácer-Quibir lutando contra os mouros nas Cruzadas reaparece na Ilha dos Lençóis como um touro ...

Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007

International Nuclear Information System (INIS)

Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos

2011-05-01

This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

A Teoria dos Conjuntos de Cantor

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Antônio Acra Freiria

1992-07-01

Full Text Available No final dos anos 50 e começo doe anos 60, houve uma reformulação significativa da Matemática no Brasil. Sob a bandeira do modernismo, seus defensores buscaram inovações no ensino da Matemática. Dessa forma, os reformistas se concentraram essencialmente na linguagem abusiva e no formalismo da Teoria dos Conjuntos, o que trouxe mais danos do que benefícios do ensino da Matemática de 1º e 2ºgraus. A linguagem formal da Teoria dos Conjuntos é porém sua parte menos importante. A teoria criada por Cantor tão logo revelou-se como o fundamento de toda a Matemática, possibilitando o desenvolvimento de novas disciplinas, como a Topologia, a Algebra Abstrata, a Teoria da Medida e Integração, a Teoria da Probabilidade e a Análise Funcional. O objetivo deste trabalho é um relato sucinto de como surgiu essa teoria, apresentando o "Conjunto de Cantor" como um dos mais ricos exemplos de "Conjunto perfeito" encontrados na literatura matemática.

Development and Evaluation of a Reverse-Entry Ion Source Orbitrap Mass Spectrometer

Science.gov (United States)

Poltash, Michael L.; McCabe, Jacob W.; Patrick, John W.; Laganowsky, Arthur; Russell, David H.

2018-05-01

As a step towards development of a high-resolution ion mobility mass spectrometer using the orbitrap mass analyzer platform, we describe herein a novel reverse-entry ion source (REIS) coupled to the higher-energy C-trap dissociation (HCD) cell of an orbitrap mass spectrometer with extended mass range. Development of the REIS is a first step in the development of a drift tube ion mobility-orbitrap MS. The REIS approach retains the functionality of the commercial instrument ion source which permits the uninterrupted use of the instrument during development as well as performance comparisons between the two ion sources. Ubiquitin (8.5 kDa) and lipid binding to the ammonia transport channel (AmtB, 126 kDa) protein complex were used as model soluble and membrane proteins, respectively, to evaluate the performance of the REIS instrument. Mass resolution obtained with the REIS is comparable to that obtained using the commercial ion source. The charge state distributions for ubiquitin and AmtB obtained on the REIS are in agreement with previous studies which suggests that the REIS-orbitrap EMR retains native structure in the gas phase.

Nuclear reactors. Introduction

International Nuclear Information System (INIS)

Boiron, P.

1997-01-01

This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

Nuclear reactor, reactor core thereof, and device for constituting the reactor

International Nuclear Information System (INIS)

Takiyama, Masashi.

1994-01-01

A reactor core is constituted by charging coolants (light water) in a reactor pressure vessel and distributing fuel assemblies, reflecting material sealing pipes, moderator (heavy water and helium gas) sealing pipes, and gas sealing pipes therein. A fuel guide tube is surrounded by a cap and the gap therebetween is made hollow and filled with coolant steams. The cap is supported by a baffle plate. The moderator sealing pipe is disposed in a flow channel of coolants in adjacent with the cap. The position of the moderator sealing tube in the reactor core is controlled by water stream from a hydraulic pump with a guide tube extending below the baffle plate being as a guide. Then, the position of the moderator sealing tube is varied to conduct power control, burnup degree compensation, and reactor shut down. With such procedures, moderator cooling facility is no more necessary to simplify the structure. Further, heat generated from the moderator is transferred to the coolants thereby improving heat efficiency of the reactor. (I.N.)

O EQUIVALENTE EM CARBONATO DE CÁLCIO DOS CORRETIVOS DA ACIDEZ DOS SOLOS

Directory of Open Access Journals (Sweden)

J.C. ALCARDE

1996-05-01

Full Text Available Os corretivos da acidez dos solos podem ter dois equivalentes em carbonato de cálcio: um, calculado pelos teores de cálcio e magnésio utilizando a expressão: % CaO x 1,79 + % MgO x 2,48 = %ECaCO3; outro, determinado analiticamente pelo poder ou valor de neutralização. Para uma mesma amostra ambos os valores deveriam coincidir, o que raramente acontece. Diversas hipóteses foram levantadas para justificar essa diferença. Os resultados deste trabalho permitiram inferir que nem todo o cálcio e magnésio dos corretivos devem estar associados às bases quimicamente efetivas mas também a fosfato, sulfato ou outras bases de forças inexpressivas; também os constituintes neutralizantes podem estar aprisionados em cristais de outros componentes dos corretivos, como sílica por exemplo, que só são atingidos por um ataque mais enérgico da amostra. Como conclusão, a avaliação química atual dos corretivos da acidez dos solos pode não estar se compatibilizando com o comportamento agrícola desses produtos.Agricultural liming materials can have two calcium carbonate equivalents: one calculated in function of calcium and magnesium oxide percentages, by the expression: % CaO x 1,79 + % MgO x 2,48 = %ECaCO3; and the other determined analytically by the neutralization power or value. For one sample, both values should be similar, however, this rarely occurs. Several hypoteses were raised to justify the difference. Results of this research permit to infer that not all calcium and magnesium should be associated to the chemically effective bases, but they are also associated to phosphate, sulphate or other bases of inexpressive strength. It is also possible that, the neutralizing components could be captured inside cristals, like silica for example, which react only after a strong solubilization of the sample. It is concluded that the chemical evaluation of agricultural liming materials at the present time cannot explain the agronomical behaviour of

Tratamento descentralizado de esgotos de empreendimentos comercial e residencial empregando a ecotecnologia dos wetlandsconstruídos

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Camila Maria Trein

Full Text Available ResumoO objetivo deste trabalho é apresentar o desempenho dos wetlandsconstruídos de fluxo vertical (WCFV submetidos a diferentes carregamentos orgânicos e hidráulicos, a fim de incorporar esta tecnologia como opção no tratamento descentralizado de esgotos em empreendimentos comercial e residencial. Avaliou-se ao longo de dois anos dois sistemas de tratamento: (i sistema 1 - empreendimento comercial: composto por um Reator Aneróbio Compartimentado (RAC seguido de WCFV (área superficial total de 189 m2; (ii sistema 2 - condomínio residencial: composto pela sequência RAC e WCFV com fundo saturado (área superficial total de 3.141 m2. Com o monitoramento operacional e analítico junto aos wetlands, determinaram-se taxas hidráulicas aplicadas variando de 130 a 12 mm.d-1 e carregamentos médios aplicados variando de 87 a 1,9 gDQO m-2.d-1 para os sistemas 1 e 2, respectivamente. Os distintos carregamentos foram resultantes da demanda atual dos empreendimentos, sendo que os sistemas 1 e 2 apresentaram eficiências médias globais de remoção em termos de concentração de 75% e 93% para DQO, de 88% e 97% para DBO e de 83% e 94% para SS, respectivamente. A partir dos resultados obtidos, recomenda-se a utilização dos WCFV como alternativa tecnológica de tratamento de esgoto sob o contexto da descentralização.

IL CONTRIBUTO DI INNOCENZO III ALLA FORMAZIONE DELLA CULTURA GIURIDICA OCCIDENTALE: IN PARTICOLARE IN RELAZIONE AL NOTO PRINCIPIO «REI PUBLICAE INTEREST NE CRIMINA REMANEANT IMPUNITA»

Directory of Open Access Journals (Sweden)

Cesare Edoardo Varalda

2016-12-01

Full Text Available Within the period so called renovatio, many principles contained in the Roman legal sources have been explained in a new and innovative way, influencing the history of juridical thought and contributing to the development of the European legal experience. In fact, the principle "Rei publice interest it crimina remaneant impunita" (mentioned in two decretals of Innocent III: i.e. the Inauditum in 1199 and i.e. the Ut famae in 1203 has an essential role in the development of the conceptual system of modern criminal law. The content of this study will be, on the one hand, the detailed study of historical iter by which this principle has been consolidated and has been embraced by canonical experience and, more generally, in the Western one; on the other hand, it will analyse both from a technical and a metagiuridico point of view the origin of such formula and on the contribution that Christian theology might have given by clarifying and specifying its meaning. Therefore, it’s clear the importance of this principle in the development of the European legal system and, broadly, in the Western legal experience.

Slurry reactors

Energy Technology Data Exchange (ETDEWEB)

Kuerten, H; Zehner, P [BASF A.G., Ludwigshafen am Rhein (Germany, F.R.)

1979-08-01

Slurry reactors are designed on the basis of empirical data and model investigations. It is as yet not possible to calculate the flow behavior of such reactors. The swarm of gas bubbles and cluster formations of solid particles and their interaction in industrial reactors are not known. These effects control to a large extent the gas hold-up, the gas-liquid interface and, similarly as in bubble columns, the back-mixing of liquids and solids. These hydrodynamic problems are illustrated in slurry reactors which constructionally may be bubble columns, stirred tanks or jet loop reactors. The expected effects are predicted by means of tests with model systems modified to represent the conditions in industrial hydrogenation reactors. In his book 'Mass Transfer in Heterogeneous Catalysis' (1970) Satterfield complained of the lack of knowledge about the design of slurry reactors and hence of the impossible task of the engineer who has to design a plant according to accepted rules. There have been no fundamental changes since then. This paper presents the problems facing the engineer in designing slurry reactors, and shows new development trends.

O Cabimento dos Embargos de Divergência

OpenAIRE

LOURENCO, S. R.

2012-01-01

A presente pesquisa objetiva demonstrar os embargos de divergência com enfoque nos elementos processuais do cabimento de tal modalidade recursal em nosso ordenamento jurídico. Para tanto, investigaremos os aspectos gerais dos embargos de divergência, a partir da análise dos elementos históricos enquanto a criação do instituto, como também sua finalidade e classificação no ordenamento jurídico brasileiro. Após, analisaremos o requisito de admissibilidade do cabimento dos embargo...

Optimal reactor strategy for commercializing fast breeder reactors

International Nuclear Information System (INIS)

Yamaji, Kenji; Nagano, Koji

1988-01-01

In this paper, a fuel cycle optimization model developed for analyzing the condition of selecting fast breeder reactors in the optimal reactor strategy is described. By dividing the period of planning, 1966-2055, into nine ten-year periods, the model was formulated as a compact linear programming model. With the model, the best mix of reactor types as well as the optimal timing of reprocessing spent fuel from LWRs to minimize the total cost were found. The results of the analysis are summarized as follows. Fast breeder reactors could be introduced in the optimal strategy when they can economically compete with LWRs with 30 year storage of spent fuel. In order that fast breeder reactors monopolize the new reactor market after the achievement of their technical availability, their capital cost should be less than 0.9 times as much as that of LWRs. When a certain amount of reprocessing commitment is assumed, the condition of employing fast breeder reactors in the optimal strategy is mitigated. In the optimal strategy, reprocessing is done just to meet plutonium demand, and the storage of spent fuel is selected to adjust the mismatch of plutonium production and utilization. The price hike of uranium ore facilitates the commercial adoption of fast breeder reactors. (Kako, I.)

Computerized reactor monitor and control for nuclear reactors

International Nuclear Information System (INIS)

Buerger, L.

1982-01-01

The analysis of a computerized process control system developed by Transelektro-KFKI-Videoton (Hangary) for a twenty-year-old research reactor in Budapest and or a new one in Tajura (Libya) is given. The paper describes the computer hardware (R-10) and the implemented software (PROCESS-24K) as well as their applications at nuclear reactors. The computer program provides for man-machine communication, data acquisition and processing, trend and alarm analysis, the control of the reactor power, reactor physical calculations and additional operational functions. The reliability and the possible further development of the computerized systems which are suitable for application at reactors of different design are also discussed. (Sz.J.)

Safeguarding research reactors

International Nuclear Information System (INIS)

Powers, J.A.

1983-03-01

The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

Control of reactor coolant flow path during reactor decay heat removal

Science.gov (United States)

Hunsbedt, Anstein N.

1988-01-01

An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

Reactor operations Brookhaven medical research reactor, Brookhaven high flux beam reactor informal monthly report

International Nuclear Information System (INIS)

Hauptman, H.M.; Petro, J.N.; Jacobi, O.

1995-04-01

This document is the April 1995 summary report on reactor operations at the Brookhaven Medical Research Reactor and the Brookhaven High Flux Beam Reactor. Ongoing experiments/irradiations in each are listed, and other significant operations functions are also noted. The HFBR surveillance testing schedule is also listed

Reactor core for FBR type reactor

International Nuclear Information System (INIS)

Fujita, Tomoko; Watanabe, Hisao; Kasai, Shigeo; Yokoyama, Tsugio; Matsumoto, Hiroshi.

1996-01-01

In a gas-sealed assembly for a FBR type reactor, two or more kinds of assemblies having different eigen frequency and a structure for suppressing oscillation of liquid surface are disposed in a reactor core. Coolant introduction channels for introducing coolants from inside and outside are disposed in the inside of structural members of an upper shielding member to form a shielding member-cooling structure in the reactor core. A structure for promoting heat conduction between a sealed gas in the assembly and coolants at the inner side or the outside of the assembly is disposed in the reactor core. A material which generates heat by neutron irradiation is disposed in the assembly to heat the sealed gases positively by radiation heat from the heat generation member also upon occurrence of power elevation-type event to cause temperature expansion. Namely, the coolants flown out from or into the gas sealed-assemblies cause differential fluctuation on the liquid surface, and the change of the capacity of a gas region is also different on every gas-sealed assemblies thereby enabling to suppress fluctuation of the reactor power. Pressure loss is increased by a baffle plate or the like to lower the liquid surface of the sodium coolants or decrease the elevating speed thereof thereby suppressing fluctuation of the reactor power. (N.H.)

Space-time reactor kinetics for heterogeneous reactor structure

Energy Technology Data Exchange (ETDEWEB)

Raisic, N [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

1969-11-15

An attempt is made to formulate time dependent diffusion equation based on Feinberg-Galanin theory in the from analogue to the classical reactor kinetic equation. Parameters of these equations could be calculated using the existing codes for static reactor calculation based on the heterogeneous reactor theory. The obtained kinetic equation could be analogues in form to the nodal kinetic equation. Space-time distribution of neutron flux in the reactor can be obtained by solving these equations using standard methods.

Teaching Bibliometric Analysis and MS/DOS Commands.

Science.gov (United States)

Dou, Henri; And Others

1988-01-01

Outlines the steps involved in bibliometric studies, and demonstrates the ability to execute simple studies on microcomputers by downloading files using only the capability of MS/DOS. Detailed illustrations of the MS/DOS commands used are provided. (eight references) (CLB)

Nuclear Reactor RA Safety Report, Vol. 4, Reactor

International Nuclear Information System (INIS)

1986-11-01

RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices [sr

O ecologismo dos pobres

Directory of Open Access Journals (Sweden)

Juan Martinez ALIER

1997-12-01

Full Text Available O ecologísmo tem colocado em cheque as leis capitalistas de mercado, principalmente na sua fase globalizada, devido à apropriação e exploração inconsequente dos recursos naturais. Ao mesmo tempo tem apontado que o meio ambiente não se reduz ao tratamento somente cientifico da natureza. O presente artigo ressalta aspectos importantes do ecologísmo como a participação das mulheres, o marxismo, o neo-narodnismo, etc. e é rico em exemplos de problemas ambientais decorrentes das relações de produção. O ecologísmo dos pobres é apontado como uma perspectiva necessária às lutas ambientais no Terceiro Mundo.

Negro é o inferno! Um ensaio sobre as cores dos homens, dos demônios e dos deuses

Directory of Open Access Journals (Sweden)

Walker Douglas Pincerati

2016-10-01

Full Text Available http://dx.doi.org/10.5007/1984-8420.2016v17n2p46 Problematiza-se o par negro.branco na formação social brasileira, trabalhando a hipótese de que ‘negro’ não é cor, mas a metáfora do corpo do ser infernal. Estatísticas oficiais, a história da formação do Brasil, um enunciado de um Deputado Federal Pastor, o quadro A libertação dos Escravos de Pedro Américo (1889 e a história da construção das catedrais góticas medievais são evocadas para analisá-lo, desde o ponto de vista linguístico-discursivo. Nota-se, destarte, uma longa história do alinhamento dos significantes branco-luz-deuses-céu-liberdade... e negro-escuridão-demônios-inferno-escravidão... atuando ainda no nosso país.

Feasible reactor power cutback logic development for an integral reactor

International Nuclear Information System (INIS)

Han, Soon-Kyoo; Lee, Chung-Chan; Choi, Suhn; Kang, Han-Ok

2013-01-01

Major features of integral reactors that have been developed around the world recently are simplified operating systems and passive safety systems. Even though highly simplified control system and very reliable components are utilized in the integral reactor, the possibility of major component malfunction cannot be ruled out. So, feasible reactor power cutback logic is required to cope with the malfunction of components without inducing reactor trip. Simplified reactor power cutback logic has been developed on the basis of the real component data and operational parameters of plant in this study. Due to the relatively high rod worth of the integral reactor the control rod assembly drop method which had been adapted for large nuclear power plants was not desirable for reactor power cutback of the integral reactor. Instead another method, the control rod assembly control logic of reactor regulating system controls the control rod assembly movements, was chosen as an alternative. Sensitivity analyses and feasibility evaluations were performed for the selected method by varying the control rod assembly driving speed. In the results, sensitivity study showed that the performance goal of reactor power cutback system could be achieved with the limited range of control rod assembly driving speed. (orig.)

COMPARAÇÃO DOS MÉTODOS OFICIAIS DE ANÁLISE E CROMATOGRÁFICOS PARA A DETERMINAÇÃO DOS TEORES DE ALDEÍDOS E ÁCIDOS EM BEBIDAS ALCOÓLICAS

OpenAIRE

NASCIMENTO,Ronaldo F.; CERRONI,Jefferson L.; CARDOSO,Daniel R.; LIMA NETO,Benedito Santos; FRANCO,Douglas W.

1998-01-01

É apresentado um estudo comparativo entre os métodos oficiais e cromatográficos para a análise de aldeídos e de ácidos em bebidas alcoólicas. Foram analisadas trinta e cinco amostras de destilados alcoólicos. Com respeito a determinação dos teores totais de aldeídos e de ácidos. Os métodos oficiais e cromatográficos apresentam similar exatidão e reprodutibilidade. Entretanto, apenas os métodos cromatográficos permitem identificar e quantificar os componentes de cada série homologa. As metodol...

¿DOS CULTURAS O DOS PREJUICIOS? UN APORTE PARA LA COMPRENSION

Directory of Open Access Journals (Sweden)

Edelmira Ochoa Camacho

2015-12-01

Full Text Available Uno de los propósitos explícitos en el proceso de educar debería ser el favorecer la comprensión de la mirada interdisciplinar del conocimiento, que aporte a la formación de personas integrales, curiosas, críticas e imaginativas (Mendoza, Callejas, Porras y Moralejo 2011, y la universidad juega un papel importante en este aspecto. Por lo que esta investigación busca contribuir al acercamiento de las dos culturas, la humanística y la  científico-tecnológica,  separadas  tradicionalmente  por  los  prejuicios  que  han propiciado la incomprensión y el rechazo hacia los otros.  Esta investigación forma parte del Proyecto de Enseñanza y Aprendizaje sobre la Naturaleza de la Ciencia y la Tecnología (EANCYT. En este trabajo se presentan los resultados globales obtenidos en un curso de Electiva interdisciplinar titulado “Consolidación de la cultura científica” de nivel universitario, donde se aplicó una Secuencia de Enseñanza y Aprendizaje (SEA  denominada “¿Dos culturas o dos prejuicios?”, diseñada por Mendoza et al (2011, que tuvo como uno de los objetivos que los estudiantes interpreten las relaciones entre las ciencias y las humanidades con base en la lectura de textos y la discusión con pares. Antes  y  después  de  la  aplicación  de  la  SEA,  se  aplicó  un  test  a  los  estudiantes estructurado  por    6 cuestiones  pertenecientes  al  Cuestionario  de Opiniones  sobre Ciencia-Tecnología-Sociedad, COCTS (Manassero, Vázquez y Acevedo, 2003. Luego de la aplicación de la SEA se obtuvieron mayores índices (que significan opiniones más adecuadas en las cuestiones referidas a unión de dos culturas, valores y estándares, decisiones sociales, ética e instituciones educativas.

RA Reactor

International Nuclear Information System (INIS)

1978-02-01

In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation [sr

H Reactor

Data.gov (United States)

Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

Reactor container

International Nuclear Information System (INIS)

Naruse, Yoshihiro.

1990-01-01

The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

Hybrid reactors

International Nuclear Information System (INIS)

Moir, R.W.

1980-01-01

The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

Nuclear research reactors

International Nuclear Information System (INIS)

1985-01-01

It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

Electrostaticspray preparation and properties of RDX/DOS composites

Directory of Open Access Journals (Sweden)

Jian Yao

2017-08-01

Full Text Available A composite explosive based on 1, 3, 5-trinitro-1, 3, 5-triazinane (RDX was prepared by electrostaticspray method with dioctyl sebacate (DOS as desensitizer. After preparation, the particle size and crystal structure were characterized and chemical features, such as chemical bonds, functional groups, thermal decomposition parameters and mechanical sensitivity were investigated as well. In terms of the morphologies of the composites, the particle sizes were in the range of 1–3 μm. Compared with RDX, the crystal types, chemical bonds and functional groups of the RDX/DOS composites were unchanged. The activation energy of the composites was lower than that of raw RDX, and the 3wt % DOS composites had the lowest activation energy. The impact sensitivity and friction sensitivity of the RDX/DOS composites were lower than those of raw RDX, and the 10wt% DOS composites had the highest H50 (125.9 cm and the lowest friction sensitivity (8%.

Strategic planning for research reactors. Guidance for reactor managers

International Nuclear Information System (INIS)

2001-04-01

The purpose of this publication is to provide guidance on how to develop a strategic plan for a research reactor. The IAEA is convinced of the need for research reactors to have strategic plans and is issuing a series of publications to help owners and operators in this regard. One of these covers the applications of research reactors. That report brings together all of the current uses of research reactors and enables a reactor owner or operator to evaluate which applications might be possible with a particular facility. An analysis of research reactor capabilities is an early phase in the strategic planning process. The current document provides the rationale for a strategic plan, outlines the methodology of developing such a plan and then gives a model that may be followed. While there are many purposes for research reactor strategic plans, this report emphasizes the use of strategic planning in order to increase utilization. A number of examples are given in order to clearly illustrate this function

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1991-04-01

The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

Research reactors - an overview

International Nuclear Information System (INIS)

West, C.D.

1997-01-01

A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

Multiregion reactors

International Nuclear Information System (INIS)

Moura Neto, C. de; Nair, R.P.K.

1979-08-01

The study of reflected reactors can be done employing the multigroup diffusion method. The neutron conservation equations, inside the intervals, can be written by fluxes and group constants. A reflected reactor (one and two groups) for a slab geometry is studied, aplying the continuity of flux and current in the interface. At the end, the appropriated solutions for a infinite cylindrical reactor and for a spherical reactor are presented. (Author) [pt

Code for calculation of spreading of radioactivity in reactor containment systems

International Nuclear Information System (INIS)

Vertes, P.

1992-09-01

A detailed description of the new version of TIBSO code is given, with applications for accident analysis in a reactor containment system. The TIBSO code can follow the nuclear transition and the spatial migration of radioactive materials. The modelling of such processes is established in a very flexible way enabling the user to investigate a wide range of problems. The TIBSO code system is described in detail, taking into account the new developments since 1983. Most changes improve the capabilities of the code. The new version of TIBSO system is written in FORTRAN-77 and can be operated both under VAX VMS and PC DOS. (author) 5 refs.; 3 figs.; 21 tabs

Reactor building

International Nuclear Information System (INIS)

Maruyama, Toru; Murata, Ritsuko.

1996-01-01

In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

Statistical properties of proportional residual energy intake as a new measure of energetic efficiency.

Science.gov (United States)

Zamani, Pouya

2017-08-01

Traditional ratio measures of efficiency, including feed conversion ratio (FCR), gross milk efficiency (GME), gross energy efficiency (GEE) and net energy efficiency (NEE) may have some statistical problems including high correlations with milk yield. Residual energy intake (REI) or residual feed intake (RFI) is another criterion, proposed to overcome the problems attributed to the traditional ratio criteria, but it does not account for production or intake levels. For example, the same REI value could be considerable for low producing and negligible for high producing cows. The aim of this study was to propose a new measure of efficiency to overcome the problems attributed to the previous criteria. A total of 1478 monthly records of 268 lactating Holstein cows were used for this study. In addition to FCR, GME, GEE, NEE and REI, a new criterion called proportional residual energy intake (PREI) was calculated as REI to net energy intake ratio and defined as proportion of net energy intake lost as REI. The PREI had an average of -0·02 and range of -0·36 to 0·27, meaning that the least efficient cow lost 0·27 of her net energy intake as REI, while the most efficient animal saved 0·36 of her net energy intake as less REI. Traditional ratio criteria (FCR, GME, GEE and NEE) had high correlations with milk and fat corrected milk yields (absolute values from 0·469 to 0·816), while the REI and PREI had low correlations (0·000 to 0·069) with milk production. The results showed that the traditional ratio criteria (FCR, GME, GEE and NEE) are highly influenced by production traits, while the REI and PREI are independent of production level. Moreover, the PREI adjusts the REI magnitude for intake level. It seems that the PREI could be considered as a worthwhile measure of efficiency for future studies.

Nuclear reactor

International Nuclear Information System (INIS)

Garabedian, G.

1988-01-01

A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

Reactor physics challenges in GEN-IV reactor design

Energy Technology Data Exchange (ETDEWEB)

Driscoll, Michael K.; Hejzlar, Pavel [Massachusetts Institute of Technology, MA (United States)

2005-02-15

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources.

Reactor physics challenges in GEN-IV reactor design

International Nuclear Information System (INIS)

Driscoll, Michael K.; Hejzlar, Pavel

2005-01-01

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources

Reactor Vessel Surveillance Program for Advanced Reactor

Energy Technology Data Exchange (ETDEWEB)

Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

2008-10-15

This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

O texto teatral no desenvolvimento da oralidade em língua

Directory of Open Access Journals (Sweden)

Islia Cristina Vaz

2013-11-01

Full Text Available O seguinte trabalho, efetuado com o auxílio do Conselho Nacional de Desenvolvimento Científico e Tecnológico (CNPq, tem como objetivo principal investigar a eficácia da utilização do texto teatral em sala de aula, auxiliando no desenvolvimento da oralidade em língua estrangeira. A principal motivação para que a presente pesquisa fosse realizada foi a percepção que se teve de um aparente medo de falar dos alunos que chegam ao nível intermediário do curso de francês. Como metodologia, foi utilizada a Pesquisa-Ação (BARBIER, 2007, juntamente com o auxílio das reflexões teóricas de Courtillon (2003, Schneuwly e Dolz (2010 e Reis (2008. Como material de pesquisa, foram feitas análises qualitativas dos diários de bordo recebidos dos alunos da Prática do Francês Oral e Escrito 4 (PFOE 4, na Universidade de Brasília (UnB, turma em que a experiência foi realizada.

Percepção de valor em uma oferta: o papel dos valores dos consumidores

OpenAIRE

Xavier Júnior, Carlos Eduardo Ramos

2006-01-01

O valor percebido e os valores pessoais dos consumidores são temas que vêm sendo investigados na literatura de marketing por diversos pesquisadores há décadas. Neste sentido, o objetivo desta dissertação foi investigar as relações entre os valores pessoais (KAHLE; KENNEDY, 1989) dos consumidores e a importância atribuída por estes às diversas dimensões do valor percebido apresentadas na literatura (SWEENEY; SOUTAR, 2001). Para isto, definiu-se o público de estudantes universitá...

The nuclear reactor strategy between fast breeder reactors and advanced pressurized water reactors

International Nuclear Information System (INIS)

Seifritz, W.

1983-01-01

A nuclear reactor strategy between fast breeder reactors (FBRs) and advanced pressurized water reactors (APWRs) is being studied. The principal idea of this strategy is that the discharged plutonium from light water reactors (LWRs) provides the inventories of the FBRs and the high-converter APWRs, whereby the LWRs are installed according to the derivative of a logistical S curve. Special emphasis is given to the dynamics of reaching an asymptotic symbiosis between FBRs and APWRs. The main conclusion is that if a symbiotic APWR-FBR family with an asymptotic total power level in the terawatt range is to exist in about half a century from now, we need a large number of FBRs already in an early phase

Abordagem teórica dos condicionantes da formação e consolidação dos parques tecnológicos

Directory of Open Access Journals (Sweden)

Alexandre Augusto Pereira Gaino

2014-03-01

Full Text Available O artigo discute as condições teóricas para a instalação e consolidação dos parques tecnológicos, mecanismos utilizados na promoção da inovação tecnológica e do desenvolvimento regional, alvo de diversas iniciativas de políticas públicas na atualidade. Para a consecução desse objetivo foi adotada uma abordagem teórica e exploratória, por meio de revisão bibliográfica, em especial de referências internacionais. O artigo apresenta e analisa diversos conceitos e definições de parque tecnológico e constata que essa diversidade decorre das diferentes realidades regionais e das variadas motivações dos stakeholders. O papel dos parques tecnológicos no desenvolvimento regional assume múltiplas feições em decorrência dos distintos interesses dos atores envolvidos em sua instalação. O artigo enfatiza e adverte que há importantes limitações da ideia de que o sucesso do parque depende fundamentalmente da capacidade de cooperação e mobilização de recursos por parte dos agentes envolvidos.

Increased SRP reactor power

International Nuclear Information System (INIS)

MacAfee, I.M.

1983-01-01

Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

Influência dos valores laborais dos pais sobre os valores laborais dos filhos Parents work values influence on sons work values

Directory of Open Access Journals (Sweden)

Juliana Barreiros Porto

2006-01-01

Full Text Available Valores laborais são princípios ou metas, hierarquicamente organizadas, que as pessoas buscam e que guiam a sua vida no trabalho. A família, a escola e a experiência de trabalho são apontadas como as variáveis mais influentes na formação dos valores laborais. Os pais são considerados os agentes socializadores mais influentes nesse processo, pois servem como modelo de trabalhador para as crianças. O objetivo do presente trabalho é investigar a influência dos valores paterno e materno nos valores laborais de estudantes universitários. Participaram 129 estudantes universitários, de 17 cursos escolhidos aleatoriamente, seus pais (84 mães e 45 pais e 956 colegas de curso dos estudantes. Os participantes responderam à Escala de Valores Relativos ao Trabalho. Os resultados das regressões hierárquicas indicaram que os pais e os colegas exercem influência sobre os valores laborais de Realização Profissional e Estabilidade dos estudantes. São discutidas a relevância e as limitações desses resultados no artigo.Work values are principles or goals, ordered by importance, that people seek and that guide his/her life at work. Family, school and work experiences are indicated as the most important factors in the formation of work values. Parents are considered the most influential social agent in this process, since they serve as a role model to their children. The present study examines the impact of the work values of parents on the work values of college students. One hundred and twenty nine (129 students and their parents (84 mothers and 45 fathers in 17 randomly chosen undergraduate courses, as well as 956 colleagues of these students participated in this investigation. They answered the Work Values Scale. The results of the hierarchical regressions demonstrated that parents and colleagues influence the student's work values of Professional Achievement and Stability. The relevance and limitations of these results are discussed in

48 CFR 632.702-70 - DOS policy.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false DOS policy. 632.702-70... REQUIREMENTS CONTRACT FINANCING Contract Funding 632.702-70 DOS policy. The Department's policy is to provide... incremental funding of cost-reimbursement contracts. Fixed-price, labor-hour, and time-and-materials contracts...

Tokamak reactor studies

International Nuclear Information System (INIS)

Baker, C.C.

1981-01-01

This paper presents an overview of tokamak reactor studies with particular attention to commercial reactor concepts developed within the last three years. Emphasis is placed on DT fueled reactors for electricity production. A brief history of tokamak reactor studies is presented. The STARFIRE, NUWMAK, and HFCTR studies are highlighted. Recent developments that have increased the commercial attractiveness of tokamak reactor designs are discussed. These developments include smaller plant sizes, higher first wall loadings, improved maintenance concepts, steady-state operation, non-divertor particle control, and improved reactor safety features

Computerized reactor monitor and control for research reactors

International Nuclear Information System (INIS)

Buerger, L.; Vegh, E.

1981-09-01

The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

Calculation of low-energy reactor neutrino spectra reactor for reactor neutrino experiments

Energy Technology Data Exchange (ETDEWEB)

Riyana, Eka Sapta; Suda, Shoya; Ishibashi, Kenji; Matsuura, Hideaki [Dept. of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Kyushu (Japan); Katakura, Junichi [Dept. of Nuclear System Safety Engineering, Nagaoka University of Technology, Nagaoka (Japan)

2016-06-15

Nuclear reactors produce a great number of antielectron neutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may take part in special weak interactions. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectrum from a typical pressurized water reactor (PWR) reactor core. To calculate neutrino spectra, we need information about all generated nuclides that emit neutrinos. They are mainly fission fragments, reaction products and trans-uranium nuclides that undergo negative beta decay. Information in relation to trans-uranium nuclide compositions and its evolution in time (burn-up process) were provided by a reactor code MVP-BURN. We used typical PWR parameter input for MVP-BURN code and assumed the reactor to be operated continuously for 1 year (12 months) in a steady thermal power (3.4 GWth). The PWR has three fuel compositions of 2.0, 3.5 and 4.1 wt% {sup 235}U contents. For preliminary calculation we adopted a standard burn-up chain model provided by MVP-BURN. The chain model treated 21 heavy nuclides and 50 fission products. The MVB-BURN code utilized JENDL 3.3 as nuclear data library. We confirm that the antielectron neutrino flux in the low energy region increases with burn-up of nuclear fuel. The antielectron-neutrino spectrum in low energy region is influenced by beta emitter nuclides with low Q value in beta decay (e.g. {sup 241}Pu) which is influenced by burp-up level: Low energy antielectron-neutrino spectra or emission rates increase when beta emitters with low Q value in beta decay accumulate. Our result shows the flux of low energy reactor neutrinos increases with burn-up of nuclear fuel.

Nuclear Reactor Physics

Science.gov (United States)

Stacey, Weston M.

2001-02-01

An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

Reactor. Mind picture of the future Jules-Horowitz Reactor (RHJ)

International Nuclear Information System (INIS)

Eustache, S.

1999-01-01

This paper gives information about the future research reactor, named Reactor Jules-Horowitz (RJH). This irradiation reactor will be placed at industrialists disposal, for research concerning the competitiveness and the safety french electro-nuclear park. Principles and innovations are detailed. This reactor will respect the ALARA principle (as low as reasonably achievable). (A.L.B.)

Considerações gerais sôbre os órgãos odoríferos sexuais dos machos dos Lepidópteros

Directory of Open Access Journals (Sweden)

Rudolf Barth

1953-12-01

Full Text Available São determinadas as seguintes regras sôbre a função dos órgãos odoríferos dos machos dos Lepidópteros: l.ª regra: A secreção das glândulas age em forma de gás sobre a fêmea diminuindo a reação normal de fuga e provocando a disposição e preparação para a copulação. 2.ª regra: Os órgãos odoríferos nos machos de um grupo de espécies parentes encontram-se constantemente nos mesmos órgãos possuindo o mesmo tipo de estrutura (constância orgânica . 3.ª regra: As partes quitinosas (escamas odoríferas, cerdas distribuidoras, inserções etc. são especificadas para cada espécie (constância de forma. 4.ª regra: O grau de desenvolvimento e com isto o grau de eficiência dos órgãos odoríferos dos Lepidópteros noturnos é sempre mais elevado do que os dos diurnos.

OptaDOS - a new tool for EELS calculations

Science.gov (United States)

Nicholls, R. J.; Morris, A. J.; Pickard, C. J.; Yates, J. R.

2012-07-01

Many modern (Scanning) Transmission Electron Microscopes ((S)TEMs) are equipped with an energy loss spectrometer. The Electron Energy Loss (EEL) spectra collected provide an experimental method of probing the bonding within a material. With the extra addition of monochromators, the energy resolution obtainable means that even more information is revealed within the fine structure of the spectra. Interpreting the fine structure can often be aided by simulation. Density-functional theory (DFT) is one method of simulating EEL spectra. DFT allows us to simulate DOS and EEL spectra from different structures. This comparison between simulation and experiment enables us to explore how changes in the spectrum are related to changes within the sample. CASTEP is a pseudopotential DFT code which can simulate both low-loss and core-loss EEL spectra. Recent developments have resulted in a separate analysis tool, OptaDOS. This package computes various spectral properties including DOS, projected DOS, joint DOS, core-loss and low-loss EEL spectra and optical spectra. One of the important aspects of the code is the way in which the DOS is calculated. This is done via linear extrapolation or adaptive smearing, methods which are not currently available within CASTEP (or indeed any other code) and which allow detailed analysis of spectral properties. This paper summarises these developments and what they mean for the interpretation of EEL spectra.

The analysis for inventory of experimental reactor high temperature gas reactor type

International Nuclear Information System (INIS)

Sri Kuntjoro; Pande Made Udiyani

2016-01-01

Relating to the plan of the National Nuclear Energy Agency (BATAN) to operate an experimental reactor of High Temperature Gas Reactors type (RGTT), it is necessary to reactor safety analysis, especially with regard to environmental issues. Analysis of the distribution of radionuclides from the reactor into the environment in normal or abnormal operating conditions starting with the estimated reactor inventory based on the type, power, and operation of the reactor. The purpose of research is to analyze inventory terrace for Experimental Power Reactor design (RDE) high temperature gas reactor type power 10 MWt, 20 MWt and 30 MWt. Analyses were performed using ORIGEN2 computer code with high temperatures cross-section library. Calculation begins with making modifications to some parameter of cross-section library based on the core average temperature of 570 °C and continued with calculations of reactor inventory due to RDE 10 MWt reactor power. The main parameters of the reactor 10 MWt RDE used in the calculation of the main parameters of the reactor similar to the HTR-10 reactor. After the reactor inventory 10 MWt RDE obtained, a comparison with the results of previous researchers. Based upon the suitability of the results, it make the design for the reactor RDE 20MWEt and 30 MWt to obtain the main parameters of the reactor in the form of the amount of fuel in the pebble bed reactor core, height and diameter of the terrace. Based on the main parameter or reactor obtained perform of calculation to get reactor inventory for RDE 20 MWT and 30 MWT with the same methods as the method of the RDE 10 MWt calculation. The results obtained are the largest inventory of reactor RDE 10 MWt, 20 MWt and 30 MWt sequentially are to Kr group are about 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq, for group I are 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq and for groups Cs are 2,20E+16 Bq, 2,40E+16 Bq, 2,60E+16 Bq. Reactor inventory will then be used to calculate the reactor source term and it

Much Ado about Babies, Murky Bathwater, and Trickle-Down Politics: A Reply to Kauffman. Commentary.

Science.gov (United States)

Goetz, Lori

1990-01-01

In response to Kauffman (EC 221 675), the article challenges the following: that the Regular Education Initiative (REI) is a Reagan-Bush plot to cut the costs of special education; that REI is value-driven with placement as the only consideration; and that REI is intended to do away with special education and strengthen regular education. (DB)

FBR type reactors

International Nuclear Information System (INIS)

Suzuoki, Akira; Yamakawa, Masanori.

1985-01-01

Purpose: To enable safety and reliable after-heat removal from a reactor core. Constitution: During ordinary operation of a FBR type reactor, sodium coolants heated to a high temperature in a reactor core are exhausted therefrom, collide against the reactor core upper mechanisms to radially change the flowing direction and then enter between each of the guide vanes. In the case if a main recycling pump is failed and stopped during reactor operation and the recycling force is eliminated, the swirling stream of sodium that has been resulted by the flow guide mechanism during normal reactor operation is continuously maintained within a plenum at a high temperature. Accordingly, the sodium recycling force in the coolant flow channels within the reactor vessel can surely be maintained for a long period of time due to the centrifugal force of the sodium swirling stream. In this way, since the reactor core recycling flow rate can be secured even after the stopping of the main recycling pump, after-heat from the reactor core can safely and surely be removed. (Seki, T.)

FBR type reactor

International Nuclear Information System (INIS)

Hayase, Tamotsu.

1991-01-01

The present invention concerns an FBR type reactor in which transuranium elements are eliminated by nuclear conversion. There are loaded reactor core fuels being charged with mixed oxides of plutonium and uranium, and blanket fuels mainly comprising depleted uranium. Further, liquid sodium is used as coolants. As transuranium elements, isotope elements of neptunium, americium and curium contained in wastes taken out from light water reactors or the composition thereof are used. The reactor core comprises a region with a greater mixing ratio and a region with a less mixing ratio of the transuranium elements. The mixing ratio of the transuranium elements is made greater for the fuels in the reactor core region at the boundary with the blanket of great neutron leakage. With such a constitution, since the positive reactivity value at the reactor core central portion is small in the Na void reactivity distribution in the reactor core, the positive reactivity is small upon Na boiling in the reactor core central region upon occurrence of imaginable accident, to attain reactor safety. (I.N.)

CRISE E NOVAS EXPRESSÕES DOS MOVIMENTOS POPULARES E SINDICALCRISE E NOVAS EXPRESSÕES DOS MOVIMENTOS POPULARES E SINDICALCRISE E NOVAS EXPRESSÕES DOS MOVIMENTOS POPULARES E SINDICAL

OpenAIRE

Ivo Lesbaupin

1995-01-01

O Brasil tem visto nos últimos tempos o surgimento e desenvolvimento de inúmeros movimentos: movimentos de bairro, movimentos de mulheres, movimento negro, movimento dos atingidos pelas barragens, movimento dos sem-terra, movimento ecológico, e outros. Porque se formam tais movimentos? Qual o alcance, a capacidade de mudança social que têm estes movimentos? Quais as condições para que u m movimento seja bem sucedido?

Estudio de seguridad del acoplamiento de un reactor de alta temperatura (VHTR) con una planta de producción de hidrógeno, análisis de los accidentes relevantes asociados

OpenAIRE

Moyart, Quentin

2008-01-01

Un estudio preliminar de seguridad dedicado al acoplamiento de un reactor nuclear de muy alta temperatura (Very High Temperature Reactor) con una planta de producción de hidrógeno (HYdrogen Production Plant) según el proceso de electrólisis a alta temperatura (High Temperature Electrolysis) se presenta en esta memoria. La primera parte de este documento está dedicada a las hipótesis de funcionamiento elegidas para el estudio, así como a la breve descripción de las dos instalaciones en el esta...

Disk Operating System--DOS. Teacher Packet. Learning Activity Packets.

Science.gov (United States)

Oklahoma State Dept. of Vocational and Technical Education, Stillwater. Curriculum and Instructional Materials Center.

The Learning Activity Packets (LAPs) contained in this manual are designed to assist the beginning user in understanding DOS (Disk Operating System). LAPs will not work with any version below DOS Version 3.0 and do not address the enhanced features of versions 4.0 or higher. These elementary activities cover only the DOS commands necessary to…

Nuclear reactor

International Nuclear Information System (INIS)

Tilliette, Z.

1975-01-01

A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-07-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

International Nuclear Information System (INIS)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

A live oral Lawsonia intracellularis vaccine does not result in protective immunity comparable to that of a virulent strain

DEFF Research Database (Denmark)

Hvass, Henriette Cordes; Riber, Ulla; Ståhl, Marie

in subclinical disease. Both groups were treated with antibiotics from day 21 to 26 and challenged at day 49 with the virulent strain. A control group (CC) only received challenge. We here report on clinical outcome, L. intracellularis infection of the intestines and immunological responses. While Re-I pigs had...... in both Vac and Re-I groups after primary inoculation/vaccination compared to the CC group. After challenge, however Vac and CC levels were high and Re-I levels low, indicating that Re-I pigs were protected from disease whereas vaccinated pigs were not. These results show that the vaccination does...

The design and installation of a core discharge monitor for CANDU-type reactors

International Nuclear Information System (INIS)

Halbig, J.K.; Monticone, A.C.; Ksiezak, L.; Smiltnieks, V.

1990-01-01

A new type of surveillance systems that monitors neutron and gamma radiation in a reactor containment is being installed at the Ontario Hydro Darlington Nuclear Generating Station A, Unit 2. Unlike video or film surveillance that monitors mechanical motion, this system measures fuel-specific radiation emanating from irradiated fuel as it is pushed from the core of CANDU-type reactors. Proof-of-principle measurements have been carried out at Bruce Nuclear Generating Station A, Unit 3. The system uses (γ,n) threshold detectors and ionization detectors. A microprocessor-based electronics package, GRAND-II (Gamma Ray and Neutron Detector electronics package), provides detector bias, preamplifier power, and signal processing. Firmware in the GRAND-2 controls the surveillance activities, including data acquisition and a level of detector authentication, and it handles authenticated communication with a central data logging computer. Data from the GRAND-II are transferred to an MS-DOS-compatible computer and stored. These data are collected and reviewed for fuel-specific radiation signatures from the primary detector and proper ratios of signals from secondary detectors. 5 figs

Thai research reactor

International Nuclear Information System (INIS)

Aramrattana, M.

1987-01-01

The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

Study of sea surface temperature distribution, in Angra dos Reis Nuclear Plant region - Mission Angra 01

International Nuclear Information System (INIS)

Stevenson, M.R.; Steffen, C.A.; Villagra, H.M.I.

1982-03-01

A study of spectral and temporal variations of sea surface temperature, using data obtained from level of satellite, aircraft and surface, with the purpose of evaluate and plot the small scale variations of sea surface temperature, due to thermal discharge from a nuclear the results of the first mission called Angra 1. (maps). (C.G.C.)

The evolution and improvements of the external emergency plans of Angra dos Reis nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Goes, Alexandre Gromann de; Araujo, Jefferson Borges, E-mail: gromann@cnen.gov.br, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN/CGRC), Rio de Janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo Combustivel

2015-07-01

The scenery that now has been configuring in the area of science and nuclear technology in the society, with their obstacles and their evolution tendencies, their philosophical discussions around fundamental concepts, and the necessity to evolve the capacity in emergency response is described in this paper. Some obstacles related to the acceptance of the nuclear energy are mentioned and some proposed strategies are also presented, as well as, specific politics for the analyzed case. One can conclude that it is imperative, that the opinion and public perception of the risk, associated with radioactive facilities should be considered and that the debate continues involving legislators, operators and the public in general. (author)

The evolution and improvements of the external emergency plans of Angra dos Reis nuclear power plant

International Nuclear Information System (INIS)

Goes, Alexandre Gromann de; Araujo, Jefferson Borges

2015-01-01

The scenery that now has been configuring in the area of science and nuclear technology in the society, with their obstacles and their evolution tendencies, their philosophical discussions around fundamental concepts, and the necessity to evolve the capacity in emergency response is described in this paper. Some obstacles related to the acceptance of the nuclear energy are mentioned and some proposed strategies are also presented, as well as, specific politics for the analyzed case. One can conclude that it is imperative, that the opinion and public perception of the risk, associated with radioactive facilities should be considered and that the debate continues involving legislators, operators and the public in general. (author)

Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

Energy Technology Data Exchange (ETDEWEB)

Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Poore, III, Willis P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Moe, Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-03-01

This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

Nuclear reactor instrumentation at research reactor renewal

International Nuclear Information System (INIS)

Baers, B.; Pellionisz, P.

1981-10-01

The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

Evidências Empíricas sobre a Rentabilidade dos Ativos dos Bancos no Brasil antes da Crise Americana do Subprime

Directory of Open Access Journals (Sweden)

Fernando da Silva Vinhado

2014-12-01

Full Text Available Segundo a visão pós-keynesiana, defendida por Tobin (1982, os ativos dos bancos são divididos basicamente entre aqueles de natureza defensiva, representados fundamentalmente por títulos financeiros, com característica de maior liquidez e menor rentabilidade, e as operações de crédito, que são ativos não defensivos com perfil de oferecer menor liquidez e maior rentabilidade. Com base nessa visão e a partir de dados organizados em painel, contemplando 71 instituições financeiras que atuaram no Brasil entre 2000 e 2008, no presente artigo foi utilizada a técnica econométrica do método dos momentos generalizados em sistema (GMM-SYS a fim de analisar empiricamente a influência de variáveis macro e microeconômicas sobre a rentabilidade de ativos dos bancos no país, tanto em títulos financeiros quanto em operações de crédito. Os exercícios econométricos propostos, que objetivaram melhorar a compreensão em relação à formação da rentabilidade dos ativos dos bancos no mercado bancário brasileiro, permitiram identificar aspectos como a persistência nos níveis de rentabilidade, a nacionalidade e personalidade jurídica dos bancos mais rentáveis por tipo de ativo, a influência do tamanho da instituição e do nível de capitalização sobre a rentabilidade dessas aplicações, além das evidências contrárias à hipótese de estrutura-conduta-performance (HCP no mercado bancário brasileiro. As estimativas envolvendo as variáveis macroeconômicas revelaram influência positiva da taxa básica de juros e característica pró-cíclica da rentabilidade dos ativos bancários. Assim, os achados permitem melhor decifrar o comportamento do desempenho dos ativos das instituições financeiras no Brasil, o que pode, inclusive, vir a orientar esforços de gestão e supervisão no sistema financeiro.

Evidências Empíricas sobre a Rentabilidade dos Ativos dos Bancos no Brasil antes da Crise Americana do Subprime

Directory of Open Access Journals (Sweden)

Fernando da Silva Vinhado

2014-11-01

Full Text Available Segundo a visão pós-keynesiana, defendida por Tobin (1982, os ativos dos bancos são divididos basicamente entre aqueles de natureza defensiva, representados fundamentalmente por títulos financeiros, com característica de maior liquidez e menor rentabilidade, e as operações de crédito, que são ativos não defensivos com perfil de oferecer menor liquidez e maior rentabilidade. Com base nessa visão e a partir de dados organizados em painel, contemplando 71 instituições financeiras que atuaram no Brasil entre 2000 e 2008, no presente artigo foi utilizada a técnica econométrica do método dos momentos generalizados em sistema (GMM-SYS a fim de analisar empiricamente a influência de variáveis macro e microeconômicas sobre a rentabilidade de ativos dos bancos no país, tanto em títulos financeiros quanto em operações de crédito. Os exercícios econométricos propostos, que objetivaram melhorar a compreensão em relação à formação da rentabilidade dos ativos dos bancos no mercado bancário brasileiro, permitiram identificar aspectos como a persistência nos níveis de rentabilidade, a nacionalidade e personalidade jurídica dos bancos mais rentáveis por tipo de ativo, a influência do tamanho da instituição e do nível de capitalização sobre a rentabilidade dessas aplicações, além das evidências contrárias à hipótese de estrutura-conduta-performance (HCP no mercado bancário brasileiro. As estimativas envolvendo as variáveis macroeconômicas revelaram influência positiva da taxa básica de juros e característica pró-cíclica da rentabilidade dos ativos bancários.  Assim, os achados permitem melhor decifrar o comportamento do desempenho dos ativos das instituições financeiras no Brasil, o que pode, inclusive, vir a orientar esforços de gestão e supervisão no sistema financeiro.

Reactor System Design

International Nuclear Information System (INIS)

Chi, S. K.; Kim, G. K.; Yeo, J. W.

2006-08-01

SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

BWR type reactor

International Nuclear Information System (INIS)

Watanabe, Shoichi

1983-01-01

Purpose : To flatten the radial power distribution in the reactor core thereby improve the thermal performance of the reactor core by making the moderator-fuel ratio of fuel assemblies different depending on their position in the reactor core. Constitution : The volume of fuels disposed in the peripheral area of the reactor core is decreased by the increase of the volume of moderators in fuel assemblies disposed in the peripheral area of the reactor core to thereby make the moderator-fuel volume greater in the peripheral area than that in the central area. The moderator-fuel ratio adjustment is attained by making the number of water rods greater, decreasing the diameter of fuel pellets or decreasing the number of fuel pins in fuel assemblies disposed at the peripheral area of the reactor core as compared with fuel assemblies disposed at the central area of the reactor core. In this way, the infinite multiplication factors of fuels can be increased to thereby improve the reactor core performance. (Aizawa, K.)

Prevention device for rapid reactor core shutdown in BWR type reactors

International Nuclear Information System (INIS)

Koshi, Yuji; Karatsu, Hiroyuki.

1986-01-01

Purpose: To surely prevent rapid shutdown of a nuclear reactor upon partial load interruption due to rapid increase in the system frequency. Constitution: If a partial load interruption greater than the sum of the turbine by-pass valve capacity and the load setting bias portion is applied in a BWR type power plant, the amount of main steams issued from the reactor is decreased, the thermal input/output balance of the reactor is lost, the reactor pressure is increased, the void is collapsed, the neutron fluxes are increased and the reactor power rises to generate rapid reactor shutdown. In view of the above, the turbine speed signal is compared with a speed setting value in a recycling flowrate control device and the recycling pump is controlled to decrease the recycling flowrate in order to compensate the increase in the neutron fluxes accompanying the reactor power up. In this way, transient changes in the reactor core pressure and the neutron fluxes are kept within a setting point for the rapid reactor shutdown operation thereby enabling to continue the plant operation. (Horiuchi, T.)

Reactor core of nuclear reactor

International Nuclear Information System (INIS)

Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

1994-01-01

In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

Análise da lucratividade dos clientes

OpenAIRE

Madeira, Paulo

2000-01-01

Um bom sistema de Análise da lucratividade de Clientes pode ajudar a melhorar a rendibilidade global do negócio, selecionando os clientes de qualidade, e a indicar o principal caminho a segui rpara atingir uma maior lucartividade, indicando o impacto financeiro actual e potencial dos movimentos estratégicos dos clientes.

High-temperature and breeder reactors - economic nuclear reactors of the future

International Nuclear Information System (INIS)

Djalilzadeh, A.M.

1977-01-01

The thesis begins with a review of the theory of nuclear fission and sections on the basic technology of nuclear reactors and the development of the first generation of gas-cooled reactors applied to electricity generation. It then deals in some detail with currently available and suggested types of high temperature reactor and with some related subsidiary issues such as the coupling of different reactor systems and various schemes for combining nuclear reactors with chemical processes (hydrogenation, hydrogen production, etc.), going on to discuss breeder reactors and their application. Further sections deal with questions of cost, comparison of nuclear with coal- and oil-fired stations, system analysis of reactor systems and the effect of nuclear generation on electricity supply. (C.J.O.G.)

Incidente com Jornalistas portugueses no Iraque. Imprudência ou espírito missionário? A batalha dos argumentos nas colunas dos jornais

OpenAIRE

Oliveira, Madalena

2007-01-01

O chamado jornalismo de guerra é, desde o desenvolvimento de tecnologias que permitiram o relato de conflitos em directo, um dos tópicos mais estimulantes do debate em torno dos escolhos e dos desafios do ofício daqueles que têm por missão informar. Os riscos associados às movimentações dos jornalistas em campos de bata-lha são, com frequência, o fermento de notícias que enchem secções especializadas nos media. O baleamento de uma jornalista da SIC e o sequestro de um repórter da TSF, no Iraq...

PR-EDB: Power Reactor Embrittlement Data Base, Version 2. Revision 2, Program description

Energy Technology Data Exchange (ETDEWEB)

Stallmann, F.W.; Wang, J.A.; Kam, F.B.K.; Taylor, B.J. [Oak Ridge National Lab., TN (United States)

1994-01-01

Investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes Standard Review Plans (SRP`s) and Guides for license renewal can be greatly expedited by the use of a well-designed computerized data base. Also, such a data base is essential for the validation of embrittlement prediction models by researchers. The Power Reactor Embrittlement Data Base (PR-EDB) is such a comprehensive collection of data for US commercial nuclear reactors. The current version of the PR-EDB contains the Charpy test data that were irradiated in 252 capsules of 96 reactors and consists of 207 data points for heat-affected-zone (HAZ) materials (98 different HAZ), 227 data points for weld materials (105 different welds), 524 data points for base materials (136 different base materials), including 297 plate data points (85 different plates), 119 forging data points (31) different forging), and 108 correlation monitor materials data points (3 different plates). The data files are given in dBASE format and can be accessed with any computer using the DOS operating system. ``User-friendly`` utility programs are used to retrieve and select specific data, manipulate data, display data to the screen or printer, and to fit and plot Charpy impact data. The results of several studies investigated are presented in Appendix D.

Heterogeneous reactors

International Nuclear Information System (INIS)

Moura Neto, C. de; Nair, R.P.K.

1979-08-01

The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

Nuclear reactor neutron shielding

Science.gov (United States)

Speaker, Daniel P; Neeley, Gary W; Inman, James B

2017-09-12

A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

Reproductive Endocrinologists' Utilization of Genetic Counselors for Oncofertility and Preimplantation Genetic Diagnosis (PGD) Treatment of BRCA1/2 Mutation Carriers.

Science.gov (United States)

Goetsch, Allison L; Wicklund, Catherine; Clayman, Marla L; Woodruff, Teresa K

2016-06-01

Genetic counselors believe fertility preservation and preimplantation genetic diagnosis (PGD) discussions to be a part of their role when counseling BRCA1/2 mutation-positive patients. This study is the first to explore reproductive endocrinologists' (REI) practices and attitudes regarding involvement of genetic counselors in the care of BRCA1/2 mutation carriers seeking fertility preservation and PGD. A survey was mailed to 1000 REIs from Reproductive Endocrinology & Infertility (SREI), an American Society for Reproductive Medicine (ASRM) affiliate group. A 14.5 % response rate was achieved; data was analyzed using SPSS software. The majority of participating REIs were found to recommend genetic counseling to cancer patients considering fertility preservation (82 %) and consult with a genetic counselor regarding PGD for hereditary cancer syndromes (92 %). Additionally, REIs consult genetic counselors regarding PGD patient counseling (88 %), genetic testing (78 %), and general genetics questions (66 %). Two areas genetic counselors may further aid REIs are: elicitation of family history, which is useful to determine fertility preservation and PGD intervention timing (32 % of REIs utilize a cancer family history to determine intervention timing); and, interpretation of variants of uncertain significance (VOUS) as cancer panel genetic testing becomes more common (36 % of REIs are unfamiliar with VOUS). Given our findings, the Oncofertility Consortium® created an online resource for genetic counselors focused on fertility preservation education and communication strategies.

Reproductive Endocrinologists’ Utilization of Genetic Counselors for Oncofertility and Preimplantation Genetic Diagnosis (PGD) Treatment of BRCA1/2 Mutation Carriers

Science.gov (United States)

Goetsch, Allison L.; Wicklund, Catherine; Clayman, Marla L.; Woodruff, Teresa K.

2016-01-01

Genetic counselors believe fertility preservation and preimplantation genetic diagnosis (PGD) discussions to be a part of their role when counseling BRCA1/2 mutation-positive patients. This study is the first to explore reproductive endocrinologists’ (REI) practices and attitudes regarding involvement of genetic counselors in the care of BRCA1/2 mutation carriers seeking fertility preservation and PGD. A survey was mailed to 1000 REIs from Reproductive Endocrinology & Infertility (SREI), an American Society for Reproductive Medicine (ASRM) affiliate group. A 14.5 % response rate was achieved; data was analyzed using SPSS software. The majority of participating REIs were found to recommend genetic counseling to cancer patients considering fertility preservation (82 %) and consult with a genetic counselor regarding PGD for hereditary cancer syndromes (92 %). Additionally, REIs consult genetic counselors regarding PGD patient counseling (88 %), genetic testing (78 %), and general genetics questions (66 %). Two areas genetic counselors may further aid REIs are: elicitation of family history, which is useful to determine fertility preservation and PGD intervention timing (32 % of REIs utilize a cancer family history to determine intervention timing); and, interpretation of variants of uncertain significance (VOUS) as cancer panel genetic testing becomes more common (36 % of REIs are unfamiliar with VOUS). Given our findings, the Oncofertility Consortium® created an online resource for genetic counselors focused on fertility preservation education and communication strategies. PMID:26567039

Fast breeder reactors

International Nuclear Information System (INIS)

Heinzel, V.

1975-01-01

The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

Reactor container

International Nuclear Information System (INIS)

Shibata, Satoru; Kawashima, Hiroaki

1984-01-01

Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

Reactor technology: power conversion systems and reactor operation and maintenance

International Nuclear Information System (INIS)

Powell, J.R.

1977-01-01

The use of advanced fuels permits the use of coolants (organic, high pressure helium) that result in power conversion systems with good thermal efficiency and relatively low cost. Water coolant would significantly reduce thermal efficiency, while lithium and salt coolants, which have been proposed for DT reactors, will have comparable power conversion efficiencies, but will probably be significantly more expensive. Helium cooled blankets with direct gas turbine power conversion cycles can also be used with DT reactors, but activation problems will be more severe, and the portion of blanket power in the metallic structure will probably not be available for the direct cycle, because of temperature limitations. A very important potential advantage of advanced fuel reactors over DT fusion reactors is the possibility of easier blanket maintenance and reduced down time for replacement. If unexpected leaks occur, in most cases the leaking circuit can be shut off and a redundant cooling curcuit will take over the thermal load. With the D-He 3 reactor, it appears practical to do this while the reactor is operating, as long as the leak is small enough not to shut down the reactor. Redundancy for Cat-D reactors has not been explored in detail, but appears feasible in principle. The idea of mobile units operating in the reactor chamber for service and maintenance of radioactive elements is explored

Fusion-fission hybrid reactors

International Nuclear Information System (INIS)

Greenspan, E.

1984-01-01

This chapter discusses the range of characteristics attainable from hybrid reactor blankets; blanket design considerations; hybrid reactor designs; alternative fuel hybrid reactors; multi-purpose hybrid reactors; and hybrid reactors and the energy economy. Hybrid reactors are driven by a fusion neutron source and include fertile and/or fissile material. The fusion component provides a copious source of fusion neutrons which interact with a subcritical fission component located adjacent to the plasma or pellet chamber. Fissile fuel and/or energy are the main products of hybrid reactors. Topics include high F/M blankets, the fissile (and tritium) breeding ratio, effects of composition on blanket properties, geometrical considerations, power density and first wall loading, variations of blanket properties with irradiation, thermal-hydraulic and mechanical design considerations, safety considerations, tokamak hybrid reactors, tandem-mirror hybrid reactors, inertial confinement hybrid reactors, fusion neutron sources, fissile-fuel and energy production ability, simultaneous production of combustible and fissile fuels, fusion reactors for waste transmutation and fissile breeding, nuclear pumped laser hybrid reactors, Hybrid Fuel Factories (HFFs), and scenarios for hybrid contribution. The appendix offers hybrid reactor fundamentals. Numerous references are provided

Reactor protection systems for the Replacement Research Reactor, ANSTO

International Nuclear Information System (INIS)

Morris, C.R.

2003-01-01

The 20-MW Replacement Research Reactor Project which is currently under construction at ANSTO will have a combination of a state of the art triplicated computer based reactor protection system, and a fully independent, and diverse, triplicated analogue reactor protection system, that has been in use in the nuclear industry, for many decades. The First Reactor Protection System (FRPS) consists of a Triconex triplicated modular redundant system that has recently been approved by the USNRC for use in the USA?s power reactor program. The Second Reactor Protection System is a hardwired analogue system supplied by Foxboro, the Spec 200 system, which is also Class1E qualified. The FRPS is used to drop the control rods when its safety parameter setpoints have been reached. The SRPS is used to drain the reflector tank and since this operation would result in a reactor poison out due to the time it would take to refill the tank the FRPS trip setpoints are more limiting. The FRPS and SRPS have limited hardwired indications on the control panels in the main control room (MCR) and emergency control centre (ECC), however all FRPS and SRPS parameters are capable of being displayed on the reactor control and monitoring system (RCMS) video display units. The RCMS is a Foxboro Series I/A control system which is used for plant control and monitoring and as a protection system for the cold neutron source. This paper will provide technical information on both systems, their trip logics, their interconnections with each other, and their integration into the reactor control and monitoring system and control panels. (author)

Zumbi dos Palmares: a afroresiliencia

Directory of Open Access Journals (Sweden)

Josué Petrônio Quirino de Oliveira

2017-10-01

Full Text Available O artigo buscou fazer uma releitura de Zumbi dos Palmares sob o prisma da resiliência, demonstrando uma visão singular ao olhar para os escravos nos quilombos e suas histórias de superação e transformação perante as adversidades, levando não só a reconstruir o imaginário afrodescendente brasileiro com o caleidoscópio da resiliência, mas revelar que a resiliência sempre foi inerente a história dos negros no Brasil. Para tanto se caracterizou como uma pesquisa exploratória com abordagem qualitativa e procedimentos bibliográficos que foram essenciais para a construção do artigo, amadurecendo e ampliando os conhecimentos envolvidos na temática. Nesta abordagem o quilombo dos Palmares foi um conjunto complexo de condições, atitudes e ações que apesar das adversidades tiveram resultados positivos, os fatos demonstraram que os negros nos quilombos foram uma prova que a resiliência negra não foi apenas um fator individual, mas uma característica comunitária que desencadeou um processo de ruptura e recuperação social, um grito de liberdade em defesa da consciência de uma raça, e de um povo. Zumbi não foi apenas um líder de um movimento libertário que marcou a história dos negros oriundos de Pernambuco e Alagoas, mas a história de uma raça por gerações no país, que se tornou sinônimo de resiliência.

Reactor container

International Nuclear Information System (INIS)

Fukazawa, Masanori.

1991-01-01

A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

A multi-purpose reactor

International Nuclear Information System (INIS)

Changwen Ma

2000-01-01

An integrated natural circulation self pressurized reactor can be used for sea water desalination, electrogeneration, ship propulsion and district or process heating. The reactor can be used for ship propulsion because it has following advantages: it is a integrated reactor. Whole primary loop is included in a size limited pressure vessel. For a 200 MW reactor the diameter of the pressure vessel is about 5 m. It is convenient to arranged on a ship. Hydraulic driving facility of control rods is used on the reactor. It notably decreases the height of the reactor. For ship propulsion, smaller diameter and smaller height are important. Besides these, the operation reliability of the reactor is high enough, because there is no rotational machine (for example, circulating pump) in safety systems. Reactor systems are simple. There are no emergency water injection system and boron concentration regulating system. These features for ship propulsion reactor are valuable. Design of the reactor is based on existing demonstration district heating reactor design. The mechanic design principles are the same. But boiling is introduced in the reactor core. Several variants to use the reactor as a movable seawater desalination plant are presented in the paper. When the sea water desalination plant is working to produce fresh water, the reactor can supply electricity at the same time to the local electricity network. Some analyses for comprehensive application of the reactor have been done. Main features and parameters of the small (Thermopower 200 MW) reactor are given in the paper. (author)

Meteoritic basalts: the nakhlites, their parental magmas, cooling rates, and equivalents on Earth. Final technical report

International Nuclear Information System (INIS)

Treiman, A.H.

1987-07-01

Proposed one-bar phase equilibrium experiments, designed to determine the compositions of the nakhlites' parental magmas, are in progress. Proposed field studies on Earth, designed to find occurrences of rocks like the nakhlites, were extraordinarily successful. Other work supported in the past year included: attendance at the 1986 national meeting of the Geological Society of America; attendance at the 18th Lunar and Planetary Science Conference; completion and publication of a study of core formation in the SNC parent body; initiation of a study of the flux of SNC meteorites onto the Earth; and initiation of petrologic study of the Angra dos Reis achondrite

TU Electric reactor physics model verification: Power reactor benchmark

International Nuclear Information System (INIS)

Willingham, C.E.; Killgore, M.R.

1988-01-01

Power reactor benchmark calculations using the advanced code package CASMO-3/SIMULATE-3 have been performed for six cycles of Prairie Island Unit 1. The reload fuel designs for the selected cycles included gadolinia as a burnable absorber, natural uranium axial blankets and increased water-to-fuel ratio. The calculated results for both startup reactor physics tests (boron endpoints, control rod worths, and isothermal temperature coefficients) and full power depletion results were compared to measured plant data. These comparisons show that the TU Electric reactor physics models accurately predict important measured parameters for power reactors

Atividades Física, Educativa e de Dança: Um Estudo dos Valores Pessoais dos Consumidores Idosos

Directory of Open Access Journals (Sweden)

Luciana Torres Souza Kelly

2012-02-01

Full Text Available Este artigo apresenta como objetivo principal identificar os valores pessoais dos consumidores idosos dos serviços de atividades física, educativa e de dança, sob o aspecto motivacional hedônico e utilitário. Adotou-se o modelo de cadeia meios-fim de Gutman (1982, o qual sugere que a pesquisa deve utilizar uma abordagem qualitativa através da entrevista em profundidade no levantamento dos dados e da análise de conteúdo. Uma fase da metodologia é quantitativa, decorrente da tabulação das conseqüências e valores em tabelas, visando construir os mapas hierárquicos, os quais se constituem em diagramas de freqüência. Por meio dos resultados indicados nos mapas hierárquicos de valor foi possível observar que os valores e benefícios associados à participação em cada atividade são tanto de interesse individual quanto coletivo, e tanto de natureza hedônica quanto utilitária. Constatou-se através dos resultados, a identificação de valores convergentes e divergentes apontando o perfil heterogêneo do consumidor idoso indicando que a cultura, as vivências, as experiências e as realidades atuais corroboram para a manifestação de um valor pessoal característico na sua vida. E nas situações de compra e utilização de serviços, apresentam como meta a aquisição de novas amizades e a experimentação de momentos variados (com novidades na vida diária. DOI: 10.5585/remark.v10i3.2251

Supercritical Water Reactors

International Nuclear Information System (INIS)

Bouchter, J.C.; Dufour, P.; Guidez, J.; Latge, C.; Renault, C.; Rimpault, G.

2014-01-01

The supercritical water reactor (SCWR) is one of the 6 concepts selected for the 4. generation of nuclear reactors. SCWR is a new concept, it is an attempt to optimize boiling water reactors by using the main advantages of supercritical water: only liquid phase and a high calorific capacity. The SCWR requires very high temperatures (over 375 C degrees) and very high pressures (over 22.1 MPa) to operate which allows a high conversion yield (44% instead of 33% for a PWR). Low volumes of coolant are necessary which makes the neutron spectrum shift towards higher energies and it is then possible to consider fast reactors operating with supercritical water. The main drawbacks of supercritical water is the necessity to use very high pressures which has important constraints on the reactor design, its physical properties (density, calorific capacity) that vary strongly with temperatures and pressures and its very high corrosiveness. The feasibility of the concept is not yet assured in terms of adequate materials that resist to corrosion, reactor stability, reactor safety, and reactor behaviour in accidental situations. (A.C.)

Tank type reactor

International Nuclear Information System (INIS)

Otsuka, Fumio.

1989-01-01

The present invention concerns a tank type reactor capable of securing reactor core integrity by preventing incorporation of gases to an intermediate heat exchanger, thgereby improving the reliability. In a conventional tank type reactor, since vortex flows are easily caused near the inlet of an intermediate heat exchanger, there is a fear that cover gases are involved into the coolant main streams to induce fetal accidents. In the present invention, a reactor core is suspended by way of a suspending body to the inside of a reactor vessel and an intermediate heat exchanger and a pump are disposed between the suspending body and the reactor vessel, in which a vortex current preventive plate is attached at the outside near the coolant inlet on the primary circuit of the intermediate heat exchanger. In this way vortex or turbulence near the inlet of the intermediate heata exchanger or near the surface of coolants can be prevented. Accordingly, the cover gases are no more involved, to insure the reactor core integrity and obtain a tank type nuclear reactor of high reliability. (I.S.)

New about research reactors

International Nuclear Information System (INIS)

Egorenkov, P.M.

2001-01-01

The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

Evaluation of Pressure Changes in HANARO Reactor Hall after a Reactor Shutdown

International Nuclear Information System (INIS)

Han, Geeyang; Han, Jaesam; Ahn, Gukhoon; Jung, Hoansung

2013-01-01

The major objective of this work is intended to evaluate the characteristics of the thermal behavior regarding how the decay heat will be affected by the reactor hall pressure change and the increase of pool water temperature induced in the primary coolant after a reactor shutdown. The particular reactor pool water temperature at the surface where it is evaporated owing to the decay heat resulting in the local heat transfer rate is related to the pressure change response in the reactor hall associated with the primary cooling system because of the reduction of the heat exchanger to remove the heat. The increase in the pool water temperature is proportional to the heat transfer rate in the reactor pool. Consequently, any limit on the reactor pool water temperature imposes a corresponding limit on the reactor hall pressure. At HANARO, the decay heat after a reactor shutdown is mainly removed by the natural circulation cooling in the reactor pool. This paper is written for the safety feature of the pressure change related leakage rate from the reactor hall. The calculation results show that the increase of pressure in the reactor hall will not cause any serious problems to the safety limits although the reactor hall pressure is slightly increased. Therefore, it was concluded that the pool water temperature increase is not so rapid as to cause the pressure to vary significantly in the reactor hall. Furthermore, the mathematical model developed in this work can be a useful analytical tool for scoping and parametric studies in the area of thermal transient analysis, with its proper representation of the interaction between the temperature and pressure in the reactor hall

Design guide for Category III reactors: pool type reactors

International Nuclear Information System (INIS)

Brynda, W.J.; Lobner, P.R.; Powell, R.W.; Straker, E.A.

1978-11-01

The Department of Energy (DOE) in the ERDA Manual requires that all DOE-owned reactors be sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate consideration to health and safety factors. Specific guidance pertinent to the safety of DOE-owned reactors is found in Chapter 0540 of the ERDA Manual. The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC). This Design Guide deals principally with the design and functional requirement of Category III reactor structures, components, and systems

The computerized reactor period measurement system for China fast burst reactor-II

International Nuclear Information System (INIS)

Zhao Wuwen; Jiang Zhiguo

1996-01-01

The article simply introduces the hardware, principle, and software of the computerized reactor period measurement system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between fission yield and pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computerized measurement system makes the reactor period measurement into automatical and intelligent and also improves the speed and precision of period data on-line process

Computer measurement system of reactor period for China fast burst reactor-II

International Nuclear Information System (INIS)

Zhao Wuwen; Jiang Zhiguo

1997-01-01

The author simply introduces the hardware, principle, and software of the reactor period computer measure system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between Fission yield and Pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computer measure system makes the reactor period measurement into automation and intellectualization and also improves the speed and precision of period data process on-line

Reactor safety method

International Nuclear Information System (INIS)

Vachon, L.J.

1980-01-01

This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature

Small propulsion reactor design based on particle bed reactor concept

International Nuclear Information System (INIS)

Ludewig, H.; Lazareth, O.; Mughabghab, S.; Perkins, K.; Powell, J.R.

1989-01-01

In this paper Particle Bed Reactor (PBR) designs are discussed which use 233 U and /sup 242m/Am as fissile materials. A constant total power of 100MW is assumed for all reactors in this study. Three broad aspects of these reactors is discussed. First, possible reactor designs are developed, second physics calculations are outlined and discussed and third mass estimates of the various candidates reactors are made. It is concluded that reactors with a specific mass of 1 kg/MW can be envisioned of 233 U is used and approximately a quarter of this value can be achieved if /sup 242m/Am is used. If this power level is increased by increasing the power density lower specific mass values are achievable. The limit will be determined by uncertainties in the thermal-hydraulic analysis. 5 refs., 5 figs., 6 tabs

Physics of nuclear reactors

International Nuclear Information System (INIS)

Baeten, Peter

2006-01-01

This course gives an introduction to Nuclear Reactor Physics. The first chapter explains the most important parameters and concepts in nuclear reactor physics such as fission, cross sections and the effective multiplication factor. Further on, in the second chapter, the flux distributions in a stationary reactor are derived from the diffusion equation. Reactor kinetics, reactor control and reactor dynamics (feedback effects) are described in the following three chapters. The course concludes with a short description of the different types of existing and future reactors. (author)

ESCRITORAS BAIANAS DOS OITOCENTOS ENFRENTANDO PRECONCEITOS

Directory of Open Access Journals (Sweden)

Helena Parente Cunha

2017-05-01

Full Text Available Tem sido a conquista dos últimos anos o reconhecimento das autoras brasileiras dos séculos passados, mias numerosas do que se supunha e que foram esquecidas devido aos preconceitos do canone Literário. A partir da segunda metade do século XIX, com o levantamento dos períodos em todo o país, dirigidos e editados por mulheres e para mulheres, veiculavam as ideias avançadas e, ao mesmo tempo, concepções do sistema patriarcado. O medo do corpo e do erotismo se transmite à produção literária feminina que, ao se inspirar no amor, quase sempre usa linguagem pudica, procuando santificar o sentimento. Mas não raro surgem passagens de uma audácia inesperada, num desafio ostensivo aos convencionalizmos do cânone comportamental. Estudam-se como as escritoreas Ana Ribeiro, Ildefonsa Laura César e Adelio Fonseca, dentro deste contexto

Estudio de inmunogenicidad para dos vacunas recombinantes contra hepatitis B

Directory of Open Access Journals (Sweden)

O. Juliao

1991-12-01

Full Text Available Este estudio compara la inmunogenicidad (seroconversión, seroprotección e Hiperrespuesta, producida por dos vacunas recombinantes contra la hepatitis B (Engerix-B de Bélgica y Cubana, en dos esquemas (012 y 016 meses, empleando los métodos de cuantificación para Anti-HBsAg (Abbott y Organón, los cuales fueron también comparados. En el estudio participaron 257 voluntarios,  divididos al azar en 4 grupos (dos vacunas, dos esquemas. Resultados: los dos métodos de Abbon y Organon, no presentan diferencias estadísticas significativas. La vacuna cubana muestra una mayor respuesta inmunogénica para dos dosis de vacuna y para el esquema 012. No hay diferencia entre los esquemas 012 y 016 y en el esquema 016 no se ven diferencias estadísticamente significativas con la vacuna Engerix-B. En esta Última el esquema 016 muestra mejores resultados que el 012.

Generation III+ Reactor Portfolio

International Nuclear Information System (INIS)

2010-03-01

While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

Guide to power reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-07-15

The IAEA's major first scientific publication is the Directory of Power Reactors now in operation or under construction in various parts of the world. The purpose of the directory is to present important details of various power projects in such a way as to provide a source of easy reference for anyone interested in the development of the peaceful uses of atomic energy, either at the technical or management level. Six pages have been devoted to each reactor the first of which contains general information, reactor physics data and information about the core. The second and third contain sketches of the fuel element or of the fuel element assembly, and of the horizontal and vertical sections of the reactor. On the fourth page information is grouped under the following heads: fuel element, core heat transfer, control, reactor vessel and over-all dimensions, and fluid flow. The fifth page shows a simplified flow diagram, while the sixth provides information on reflector and shielding, containment and turbo generator. Some information has also been given, when available, on cost estimates and operating staff requirements. Remarks and a bibliography constitute the last part of the description of each reactor. Reactor projects included in this directory are pressurized light water cooled power reactors. Boiling light water cooled power reactors, heavy water cooled power reactors, gas cooled power reactors, organic cooled power reactors liquid metal cooled power reactors and liquid metal cooled power reactors

Analysis of dynamic stability and safety of reactor system by reactor simulator

International Nuclear Information System (INIS)

Raisic, N.

1963-11-01

In order to enable qualitative analysis of dynamic properties of reactors RA and RB, mathematical models of these reactors were formulated and adapted for solution on analog computer. This report contains basic assessments for creating the model and complete equations for each reactor. Model was used to analyse three possible accidents at the RA reactor and possible hypothetical accidents at the RB reactor

Nuclear reactor physics

CERN Document Server

Stacey, Weston M

2010-01-01

Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

Sodium-cooled nuclear reactor

International Nuclear Information System (INIS)

Hammers, H.W.

1982-01-01

The invention concerns a sodium-cooled nuclear reactor, whose reactor tank contains the primary circuit, shielding surrounding the reactor core and a primary/secondary heat exchanger, particularly a fast breeder reactor on the module principle. In order to achieve this module principle it is proposed to have electromagnetic circulating pumps outside the reactor tank, where the heat exchanger is accomodated in an annular case above the pumps. This case has several openings at the top end to the space above the reactor core, some smaller openings in the middle to the same space and is connected at the bottom to an annular space between the tank wall and the reactor core. As a favoured variant, it is proposed that the annular electromagnetic pumps should be arranged concentrically to the reactor tank, where there is an annual duct on the inside of the reactor tank. In this way the sodium-cooled nuclear reactor is made suitable as a module with a large number of such elements. (orig.) [de

Atomic reactor thermal engineering

International Nuclear Information System (INIS)

Kim, Gwang Ryong

1983-02-01

This book starts the introduction of atomic reactor thermal engineering including atomic reaction, chemical reaction, nuclear reaction neutron energy and soon. It explains heat transfer, heat production in the atomic reactor, heat transfer of fuel element in atomic reactor, heat transfer and flow of cooler, thermal design of atomic reactor, design of thermodynamics of atomic reactor and various. This deals with the basic knowledge of thermal engineering for atomic reactor.

Argentinean integrated small reactor design and scale economy analysis of integrated reactor

International Nuclear Information System (INIS)

Florido, P. C.; Bergallo, J. E.; Ishida, M. V.

2000-01-01

This paper describes the design of CAREM, which is Argentinean integrated small reactor project and the scale economy analysis results of integrated reactor. CAREM project consists on the development, design and construction of a small nuclear power plant. CAREM is an advanced reactor conceived with new generation design solutions and standing on the large experience accumulated in the safe operation of Light Water Reactors. The CAREM is an indirect cycle reactor with some distinctive and characteristic features that greatly simplify the reactor and also contribute to a highly level of safety: integrated primary cooling system, self pressurized, primary cooling by natural circulation and safety system relying on passive features. For a fully doupled economic evaluation of integrated reactors done by IREP (Integrated Reactor Evaluation Program) code transferred to IAEA, CAREM have been used as a reference point. The results shows that integrated reactors become competitive with power larger than 200MWe with Argentinean cheapest electricity option. Due to reactor pressure vessel construction limit, low pressure drop steam generator are used to reach power output of 200MWe for natural circulation. For forced circulation, 300MWe can be achieved. (author)

PADRONIZAÇÃO DA SÍNTESE DOS PRINCIPAIS CONSTITUINTES FEROMONAIS DE INSETOS DOS GÊNEROS METAMASIUS E RHYNCHOPHORUS

Directory of Open Access Journals (Sweden)

JOHNNATAN DUARTE DE FREITAS

2011-05-01

Full Text Available Os curculionídeos são insetos que causam grandes problemas econômicos aos agricultores e atingem culturas, como coco, dendê, cana-de-açúcar, milho, banana, algodão, etc. O controle de pragas agrícolas, ainda hoje, utiliza grandes quantidades de inseticidas, que são prejudiciais à saúde dos animais, do homem e do meio ambiente. Uma alternativa ao uso desses inseticidas é o uso de feromônios, por serem mais seletivos e menos tóxicos. Nesse trabalho, descrevemos a síntese, em escala preparativa, dos compostos (±-5-Nonanol, (±-2-Metil-4-octanol, (±-2-Metil-4-heptanol, (±-3-Metil-4-octanol, (±-5-Metil-4-octanol, (±-4-Metil-5-nonanol, (±-6-Metil-2-hepten-4-ol, 2-Metil-4-octanona, 2-Metil-4-heptanona e (±-4-Metil-5-nonanona, principais constituintes feromonais de alguns insetos dos gêneros Metamasius e Rhynchophoruseas. A síntese consistiu na reação de Grignard entre um aldeído e um brometo de alquilmagnésio. As oxidações dos álcoois para obtenção das cetonas foram realizadas com hipoclorito de sódio.

Fast reactors

International Nuclear Information System (INIS)

Vasile, A.

2001-01-01

Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

Reactor power measuring device

International Nuclear Information System (INIS)

Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

1993-01-01

The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

Reactor container

International Nuclear Information System (INIS)

Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

1997-01-01

In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

Study on Reactor Performance of Online Power Monitoring in PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

2014-01-01

The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on reactor performance of online power monitoring based on various parameter of reactor such as log power, linear power, period, Fuel and coolant temperature and reactivity parameter with using neutronic and other instrumentation system of reactor. Methodology of online power estimation and monitoring is to evaluate and analysis of reactor power which is important of reactor safety and control. Neutronic instrumentation system will use to estimate power measurement, differential of log and linear power and period during reactor operation .This study also focus on noise fluctuation from fission chamber during reactor operation .This work will present result of online power monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that optimization of online power monitoring will improved the reactor control and safety parameter of reactor during operation. (author)

Números primos: os átomos dos números

OpenAIRE

Rigoti, Marcio Dominicali

2015-01-01

Este trabalho apresenta um estudo sobre os Números Primos que passa por resultados básicos, como a infinitude dos números primos e o Teorema Fundamental da Aritmética, e resultados mais sofisticados, como o Teorema de Wilson e a consequente função geradora de primos. Além dos resultados teóricos apresenta-se uma interpretação geométrica para os números primos. Essa interpretação e aplicada na ilustração de alguns dos resultados relacionados a primos abordados no ensino básico. Atividades envo...

Efeitos deleterios dos cloretos em reservatorios de concreto

OpenAIRE

Matoski, Adalberto

1998-01-01

Dissertação (mestrado) - Universidade Federal de Santa Catarina, Centro Tecnologico Caracterização dos reservatórios de água potável das regiões de Curitiba e Florianópolis, quanto às patologias apresentadas. Utilização do ensaio de potencial de eletrodo para a definição das linhas equipotenciais sobre a laje de concreto dos reservatórios. Análise dos efeitos do cloro adicionado à água, para sua desinfecção, sobre o concreto. Comparaçao entre os ensaios químico e de espectrometria de raio...

Nuclear power reactors: reactor safety and military and civil defence

International Nuclear Information System (INIS)

Hvinden, T.

1976-01-01

The formation of fission products and plutonium in reactors is briefly described, followed by a short general discussion of reactor safety. The interaction of reactor safety and radioactive release considerations with military and civil defence is thereafter discussed. Reactors and other nuclear plants are factors which must be taken into account in the defence of the district around the site, and as potential targets of both conventional and guerilla attacks and sabotage, requiring special defence. The radiological hazards arising from serious damage to a power reactor by conventional weapons are briefly discussed, and the benefits of underground siting evaluated. Finally the author discusses the significance of the IAEA safeguards work as a preventive factor. (JIW)

Research reactors in Argentina

International Nuclear Information System (INIS)

Carlos Ruben Calabrese

1999-01-01

Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

To the analysis of reactor noise in boiling water reactors

International Nuclear Information System (INIS)

Seifritz, W.

1972-01-01

The paper contains some basic thoughts on the problem of neutron flux oscillations in power reactors. The advantages of self-powered detectors and their function are explained. In addition, noise measurements of the boiling water reactors at Lingen and Holden are described, and the possibilities of an employment of vanadium detectors for the analysis of reactor noise are discussed. The final pages of the paper contain a complete list of the author's publications in the field of reactor noise analysis. (RW/AK) [de

The CEA research reactors

International Nuclear Information System (INIS)

Schwartz, J.P.

1993-01-01

Two main research reactors, specifically designed, PEGASE reactor and Laue-Langevin high flux reactor, are presented. The PEGASE reactor was designed at the end of the 50s for the study of the gas cooled reactor fuel element behaviour under irradiation; the HFR reactor, was designed in the late 60s to serve as a high yield and high level neutron source. Historical backgrounds, core and fuel characteristics and design, flux characteristics, etc., are presented. 5 figs

State space modeling of reactor core in a pressurized water reactor

Energy Technology Data Exchange (ETDEWEB)

Ashaari, A.; Ahmad, T.; M, Wan Munirah W. [Department of Mathematical Science, Faculty of Science, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Shamsuddin, Mustaffa [Institute of Ibnu Sina, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Abdullah, M. Adib [Swinburne University of Technology, Faculty of Engineering, Computing and Science, Jalan Simpang Tiga, 93350 Kuching, Sarawak (Malaysia)

2014-07-10

The power control system of a nuclear reactor is the key system that ensures a safe operation for a nuclear power plant. However, a mathematical model of a nuclear power plant is in the form of nonlinear process and time dependent that give very hard to be described. One of the important components of a Pressurized Water Reactor is the Reactor core. The aim of this study is to analyze the performance of power produced from a reactor core using temperature of the moderator as an input. Mathematical representation of the state space model of the reactor core control system is presented and analyzed in this paper. The data and parameters are taken from a real time VVER-type Pressurized Water Reactor and will be verified using Matlab and Simulink. Based on the simulation conducted, the results show that the temperature of the moderator plays an important role in determining the power of reactor core.

O legado dos desenhadores da guerra

OpenAIRE

Almeida, Reginaldo Rodrigues de

2017-01-01

O comportamento que causa dano ou prejuízo moral é um comportamento violento, logo temido. Porém, não se foge dele, antes se procura.Verifica-se uma avidez global em busca de imagens,sejam fotografias ou vídeos, tendo a fotografia do interior da casa de espectáculos parisiense Le Bataclan, com os cadáveres dos reféns,ainda que pouco perceptível, sido vista até à exaustão, na sequência dos ataque terroristas dodia 13 de Novembro de 2015 em Paris.

Virtual nuclear reactor for education of nuclear reactor physics

International Nuclear Information System (INIS)

Tsuji, Masashi; Narabayashi, Takashi; Shimazu, Youichiro

2008-01-01

As one of projects that were programmed in the cultivation program for human resources in nuclear engineering sponsored by the Ministry of Economy, Trade and Industry, the development of a virtual reactor for education of nuclear reactor physics started in 2007. The purpose of the virtual nuclear reactor is to make nuclear reactor physics easily understood with aid of visualization. In the first year of this project, the neutron slowing down process was visualized. The data needed for visualization are provided by Monte Carlo calculations; The flights of the respective neutrons generated by nuclear fissions are traced through a reactor core until they disappear by neutron absorption or slow down to a thermal energy. With this visualization and an attached supplement textbook, it is expected that the learners can learn more clearly the physical implication of neutron slowing process that is mathematically described by the Boltzmann neutron transport equation. (author)

Repercussões da aceleração dos ritmos de trabalho na saúde dos servidores de um juizado especial

Directory of Open Access Journals (Sweden)

Daiane Dal Pai

2014-09-01

Full Text Available Os recentes incrementos tecnológicos promovidos junto ao serviço judiciário federal trouxeram avanços importantes para a melhoria dos atendimentos prestados à população, contudo originaram novas demandas organizacionais aos trabalhadores do setor. Objetivo Conhecer as repercussões da organização do trabalho no cotidiano laboral e na saúde dos servidores do Juizado Especial Federal de Porto Alegre (RS.Procedimentos metodológicos Desenvolveu-se uma pesquisa de abordagem qualitativa, por meio de entrevistas semiestruturadas com 17 servidores de um juizado especial federal. As falas foram gravadas em áudio, transcritas e submetidas à análise de conteúdo. O referencial teórico da psicodinâmica do trabalho fundamentou a interpretação dos achados.Resultados Foram identificadas duas categorias de análise: (1 Mudanças na organização do trabalho: de processos judiciais físicos à aceleração virtual e (2 Adaptação dos profissionais às mudanças e suas repercussões sobre a saúde. Na primeira categoria foram discutidas as transformações vivenciadas pelos trabalhadores a partir da implantação dos sistemas informatizados de recebimento e análise dos processos judiciais. Na segunda categoria revelaram-se as exigências psíquicas e físicas que os trabalhadores associaram ao contexto laboral.Conclusão Concluiu-se que os trabalhadores se percebem diante de um ritmo acelerado e elevado volume de trabalho, convivendo com sintomas que sugerem o adoecimento e sentindo-se desassistidos quanto às mudanças estabelecidas ao processo de trabalho.

Reactor physics and reactor strategy investigations into the fissionable material economy of the thorium and uranium cycle in fast breeder reactors and high temperature reactors

International Nuclear Information System (INIS)

Schikorr, W.M.

In this work the properties governing the fissionable material economy of the uranium and thorium cycles are investigated for the advanced reactor types currently under development - the fast breeder reactor (FBR) and the high temperature reactor (HTR) - from the point of view of the optimum utilization of the available nuclear fuel reserves and the continuance of supply of these reserves. For this purpose, the two reactor types are first of all considered individually and are subsequently discussed as a complementary overall system

Reactor core

International Nuclear Information System (INIS)

Azekura, Kazuo; Kurihara, Kunitoshi.

1992-01-01

In a BWR type reactor, a great number of pipes (spectral shift pipes) are disposed in the reactor core. Moderators having a small moderating cross section (heavy water) are circulated in the spectral shift pipes to suppress the excess reactivity while increasing the conversion ratio at an initial stage of the operation cycle. After the intermediate stage of the operation cycle in which the reactor core reactivity is lowered, reactivity is increased by circulating moderators having a great moderating cross section (light water) to extend the taken up burnup degree. Further, neutron absorbers such as boron are mixed to the moderator in the spectral shift pipe to control the concentration thereof. With such a constitution, control rods and driving mechanisms are no more necessary, to simplify the structure of the reactor core. This can increase the fuel conversion ratio and control great excess reactivity. Accordingly, a nuclear reactor core of high conversion and high burnup degree can be attained. (I.N.)

Nuclear reactor

International Nuclear Information System (INIS)

Batheja, P.; Huber, R.; Rau, P.

1985-01-01

Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

ESTUDO DOS PRINCÍPIOS APLICADOS À UTILIZAÇÃO DOS AGENTES QUÍMICOS DESINFETANTES HOSPITALARES

Directory of Open Access Journals (Sweden)

Vanda M. Galvão Jouclas

Full Text Available As autoras realizaram um levantamento bibliográfico coletando dados atualizados sobre a utilização dos agentes químicos desinfetantes hospitalares, levando-se em consideração suas possibilidades e suas limitações. São abordados na fundamentação científica o conceito de desinfecção e esterilização, as condições necessárias para a ação efetiva de um agente químico, os critérios de escolha do agente químico, e a classificação dos agentes químicos utilizados em equipamentos e materiais médico-cirúrgicos.

Performance improvement of the Annular Core Pulse Reactor for reactor safety experiments

International Nuclear Information System (INIS)

Reuscher, J.A.; Pickard, P.S.

1976-01-01

The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past several years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. The new features of the improvements are described

Identification of nuclear reactor characteristics by the reactor noise analysis

International Nuclear Information System (INIS)

Yashima, Hideyuki

1980-01-01

Reactor noise analysis method was applied to TRIGA II Research Reactor (Atomic Research Laboratory, Musashi Institute of Technology) and computed power spectral density (PSD) from the CIC current record. PSD has provided many valuable informations regarding to the reactor kinetics, including the effect of control rods vibration. Another information of neutron physics parameters were obtained and this result was compared with the parameter which was formerly measured by the Feynman-α experiment. Through these experiments we could find overall frequency characteristics of TRIGA II Reactor. (author)

Research on the reactor physics and reactor safety of VVER reactors. AER Symposium 2016

Energy Technology Data Exchange (ETDEWEB)

Kliem, S.

2017-09-15

The selected paperscan be attributed to the following main subjects: Reactor start-up tests and use of corresponding data for code validation, code development and application, approaches for safety analyses, closure of nuclear fuel cycle, prospective reactor concepts.

The fast breeder reactor

International Nuclear Information System (INIS)

Collier, J.

1990-01-01

The arguments for and against the fast breeder reactor are debated. The case for the fast reactor is that the world energy demand will increase due to increasing population over the next forty years and that the damage to the global environment from burning fossil fuels which contribute to the greenhouse effect. Nuclear fission is the only large scale energy source which can achieve a cut in the use of carbon based fuels although energy conservation and renewable sources will also be important. Fast reactors produce more energy from uranium than other types of (thermal) reactors such as AGRs and PWRs. Fast reactors would be important from about 2020 onwards especially as by then many thermal reactors will need to be replaced. Fast reactors are also safer than normal reactors. The arguments against fast reactors are largely economic. The cost, especially the capital cost is very high. The viability of the technology is also questioned. (UK)

Análise e Mapeamento sobre a Avaliação da Evidenciação dos Atos Públicos dos Entes Governamentais

Directory of Open Access Journals (Sweden)

Lucas dos Santos Matos

2015-08-01

Full Text Available O aumento da demanda da população e dos órgãos fiscalizadores por informações relacionadas à gestão governamental ocasionou a necessidade de melhorar a evidenciação dos relatórios públicos, tanto na abrangência e qualidade da informação quanto na sua transparência. Surge então a necessidade de desenvolver modelos de avaliação da transparência dos atos públicos que contemplem a necessidade dos usuários. Assim, esta pesquisa, de natureza exploratório-descritiva, com abordagem qualitativa e quantitativa, objetiva realizar um mapeamento sobre o tema avaliação da evidenciação dos atos públicos dos entes governamentais a partir da seleção de um rol de artigos internacionais reconhecidos cientificamente e, a partir deste portfólio, realizar uma análise de conteúdo destes artigos, visando à identificação de oportunidades de pesquisas. Dessa forma, foi selecionado o Knowledge Development Process – Constructivist (ProKnow-C como instrumento de intervenção do processo. O resultado foi um conjunto de 14 artigos científicos, publicados entre 2000 e 2013, com reconhecimento e, para estes artigos, evidenciou-se os principais artigos, periódicos, autores e palavras-chave acerca do tema de estudo. A análise de conteúdo possibilitou encontrar destaques e oportunidades para pesquisas futuras. Verificou-se que a literatura trata apenas de modelos de avaliação da transparência pública conforme os critérios definidos por normas e legislações, mas é necessário considerar as necessidades dos usuários.

Exposição de pacientes e qualidade da imagem em radiografias de tórax: uma avaliação crítica Patients exposure and imaging quality in chest radiographs: a critical evaluation

Directory of Open Access Journals (Sweden)

Adelaja Otolorin Osibote

2007-04-01

Full Text Available OBJETIVO: Foi realizada avaliação da dose de entrada na pele, da dose efetiva e da qualidade da imagem em radiografias de tórax de pacientes adultos. MATERIAIS E MÉTODOS: O estudo realizou-se em oito hospitais, sendo sete públicos (dois filantrópicos e um particular nos municípios de Angra dos Reis, Cabo Frio, Campos dos Goytacazes, Itaperuna, Niterói, Recife e Rio de Janeiro. Foram avaliadas a dose de entrada na pele e a dose efetiva de 735 radiografias de tórax nas incidências póstero-anterior/ântero-posterior e perfil. No que se refere aos critérios de imagem, foram avaliadas 44 radiografias. RESULTADOS: Constatou-se variação de até nove vezes nos valores da dose de entrada na pele e de até seis vezes na dose efetiva para um mesmo tipo de projeção. Os valores das técnicas radiográficas também apresentaram grandes discrepâncias. A qualidade das imagens também não é boa, pois foi obtido valor médio de presença dos critérios de apenas 55%. CONCLUSÃO: Há necessidade de melhoria/padronização de procedimentos em radiologia convencional, o que pode ser atingido se for implantado um programa de controle e garantia de qualidade no setor de radiologia, incluindo o treinamento dos técnicos, a aferição do desempenho dos equipamentos emissores de radiação e o controle sensitométrico do sistema de processamento radiográfico.OBJECTIVE: Entrance skin dose, effective dose, and imaging quality in chest radiographs of adult patients have been evaluated. MATERIALS AND METHODS: The study has been developed in eight institutions - seven public hospitals (two of them philanthropic institutions and one private - in the cities of Agra dos Reis, Cabo Frio, Campos dos Goytacazes, Itaperuna, Niterói, Recife and Rio de Janeiro. Entrance skin dose and effective dose have been evaluated in 735 chest radiographs obtained in posteroanterior/anteroposterior and lateral projections. As regards imaging criteria, 44 radiographs have been

Reactor feedwater system

International Nuclear Information System (INIS)

Kagaya, Hiroyuki; Tominaga, Kenji.

1993-01-01

In a simplified water type reactor using a gravitationally dropping emergency core cooling system (ECCS), the present invention effectively prevents remaining high temperature water in feedwater pipelines from flowing into the reactor upon occurrence of abnormal events. That is, (1) upon LOCA, if a feedwater pipeline injection valve is closed, boiling under reduced pressure of the remaining high temperature water occurs in the feedwater pipelines, generated steams prevent the remaining high temperature water from flowing into the reactor. Accordingly, the reactor is depressurized rapidly. (2) The feedwater pipeline injection valve is closed and a bypassing valve is opened. Steams generated by boiling under reduced pressure of the remaining high temperature water in the feedwater pipelines are released to a condensator or a suppression pool passing through bypass pipelines. As a result, the remaining high temperature water is prevented from flowing into the reactor. Accordingly, the reactor is rapidly depressurized and cooled. It is possible to accelerate the depressurization of the reactor by the method described above. Further, load on the depressurization valve disposed to a main steam pipe can be reduced. (I.S.)

A proteção dos deslocados ambientais no regime internacional dos refugiados

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Andrea Pacheco Pacífico

Full Text Available O deslocamento de pessoas por causas ambientais gera discussões pela ausência de reconhecimento legal e proteção jurídica específica para essa categoria de pessoas. Assim, este artigo examina o Regime Internacional dos Refugiados (RIR, conceitua deslocados ambientais (DA e reflete sobre a ausência de proteção pelo RIR. Em seguida, examina as causas e as consequências dos deslocamentos e as formas de proteção aos DA, concluindo que os regimes vigentes não lhes oferecem proteção efetiva. Uma solução, segundo Betts (2009, seria cooperação para proteção por persuasão via cruzamento de assuntos de interesse estatal, persuadindo Estados a cooperarem em seus interesses, como saída eficaz para a ausência de proteção efetiva aos DA.

Neutron transport. Physics and calculation of nuclear reactors with applications to pressurized water reactors and fast neutron reactors. 2 ed.

International Nuclear Information System (INIS)

Bussac, J.; Reuss, P.

1985-01-01

This book presents the main physical bases of neutron theory and nuclear reactor calculation. 1) Interactions of neutrons with matter and basic principles of neutron transport; 2) Neutron transport in homogeneous medium and the neutron field: kinetic behaviour, slowing-down, resonance absorption, diffusion equation, processing methods; 3) Theory of a reactor constituted with homogeneous zones: critical condition, kinetics, separation of variables, calculation and neutron balance of the fundamental mode, one-group and multigroup theories; 4) Study of heterogeneous cell lattices: fast fission factor, resonance absorption, thermal output factor, diffusion coefficient, computer codes; 5) Operation and control of reactors: perturbation theory, reactivity, fuel properties evolution, poisoning by fission products, calculation of a reactor and fuel management; 6) Study of some types of reactors: PWR and fast breeder reactors, the main reactor types of the present French program [fr

EDITORIAL: Plágio e ineditismo dos artigos

Directory of Open Access Journals (Sweden)

Fernando Castro Amoras

2016-06-01

Full Text Available EDITORIAL: Plágio e ineditismo dos artigos A partir deste ano de 2016, a revista Estação Científica (UNIFAP passou a adotar, como instrumento auxiliar da seleção dos artigos que serão publicados, a checagem de plágio nos conteúdos dos trabalhos que recebemos. Consta no site da revista a informação de que todos os trabalhos passarão por verificação de plágio, e desta forma alerta-se que sejam apresentados à Estação Científica (UNIFAP apenas os trabalhos que tenham autenticidade de autoria.

Ulysse, mentor reactor

International Nuclear Information System (INIS)

Bouquin, B.; Rio, I.; Safieh, J.

1997-01-01

On July 23, 1961, the ULYSSE reactor began its first power rise. Designed at that time to train nuclear engineering students and reactor operators, this reactor still remains an indispensable tool for nuclear teaching and a choice instrument for scientists. (author)

Siting of research reactors

International Nuclear Information System (INIS)

1987-01-01

The purpose of this document is to develop criteria for siting and the site-related design basis for research reactors. The concepts presented in this document are intended as recommendations for new reactors and are not suggested for backfitting purposes for facilities already in existence. In siting research reactors serious consideration is given to minimizing the effects of the site on the reactor and the reactor on the site and the potential impact of the reactor on the environment. In this document guidance is first provided on the evaluation of the radiological impact of the installation under normal reactor operation and accident conditions. A classification of research reactors in groups is then proposed, together with a different approach for each group, to take into account the relevant safety problems associated with facilities of different characteristics. Guidance is also provided for both extreme natural events and for man-induced external events which could affect the safe operation of the reactor. Extreme natural events include earthquakes, flooding for river or coastal sites and extreme meteorological phenomena. The feasibility of emergency planning is finally considered for each group of reactors

Experience in using a research reactor for the training of power reactor operators

International Nuclear Information System (INIS)

Blotcky, A.J.; Arsenaut, L.J.

1972-01-01

A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

Governo colonial, distância e espera nas minas e capitania de Goiás

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Fernando Lobo Lemes

Full Text Available A temporalidade da espera associada aos intervalos impostos pelas distâncias geográficas à burocracia do governo colonial instala a vida dos habitantes de Goiás num ambiente transitório, constituído de eventos provisórios, onde os protagonistas devem fazer face às incertezas, enquanto esperam pelas decisões do rei de Portugal. Com a morte súbita do capitão-general João Manoel de Melo, a formação de um governo provisório aparece como estratégia das elites locais para controlar o tempo de espera e preencher o vazio de poder deixado pela ausência do governador. Neste cenário, os acontecimentos são percebidos como interações de força, cujas tensões podem transformar, ainda que transitoriamente, as relações estabelecidas na hierarquia dos poderes do império.

Reactor transients tests for SNR fuel elements in HFR reactor

International Nuclear Information System (INIS)

Plitz, H.

1989-01-01

In HFR reactor, fuel pins of LMFBR reactors are putted in irradiation specimen capsules cooled with sodium for reactor transients tests. These irradiation capsules are instrumented and the experiences realized until this day give results on: - Fuel pins subjected at a continual variation of power - melting fuel - axial differential elongation of fuel pins

Measuring both systems of reasoning: a study of the predictive capacity of a new version of the Rational-Experiential Inventory

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Edgar Sánchez

2012-12-01

Full Text Available Previous research on the Rational-Experiential Inventory (REI; Epstein, Pacini, Denes-Raj and Heier, 1996 has produced inconsistent results concerning its predictive validity with specific reasoning tasks. To evaluate the predictive capacity of the REI in greater detail we used ten tasks requiring different types of reasoning (e.g., deductive and probabilistic. The latest version of the REI (Pacini and Epstein, 1999 was adapted to Spanish and answered by 120 participants. Findings suggest that thinking styles of processing as measured by the REI reflect the existence of individual differences, but that its predictive capacity is limited to some particular reasoning tasks. Some explanations for these limitations are discussed within the context of dual-reasoning theories

Nuclear reactor coolant channels

International Nuclear Information System (INIS)

Macbeth, R.V.

1978-01-01

A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

AVALIAÇÃO DA EFICIÊNCIA DA APLICAÇÃO DOS ROYALTIES DA MINERAÇÃO NO DESENVOLVIMENTO SOCIAL DOS MUNICÍPIOS MINEIROS

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Alexandre de Cássio Rodrigues

2016-12-01

Full Text Available Tendo os royalites da mineração como origens de recursos públicos dos municípios nos quais a atividade mineral ocorre, essa pesquisa tem como objetivo analisar, por meio de indicadores sociais, se a aplicação dos royalties da mineração tem impactado positivamente no desenvolvimento dos municípios mineiros. Para tanto, utilizou-se na pesquisa documental a prestação de contas anual das prefeituras e câmaras municipais, informações sobre população municipal no site do IBGE e obtido o Índice Firjan de Desenvolvimento Municipal, sendo posteriormente utilizadas técnicas de regressão linear e análise de clusters. Os resultados indicam que o aumento da dependência dos royalties da mineração implica na redução do desenvolvimento humano dos municípios de base mineral. Além disso, não foram encontradas evidências de que a atividade mineral proporcione altos níveis de geração de emprego e distribuição de renda. Portanto, é necessário que esses recursos sejam geridos de forma mais eficiente, priorizando-se projetos que estimulem a diversificação econômica dos municípios.

Training reactor deployment. Advanced experimental course on designing new reactor cores

International Nuclear Information System (INIS)

Skoda, Radek

2009-01-01

Czech Technical University in Prague (CTU) operating its training nuclear reactor VR1, in cooperation with the North West University of South Africa (NWU), is applying for accreditation of the experimental training course ''Advanced experimental course on designing the new reactor core'' that will guide the students, young nuclear engineering professionals, through designing, calculating, approval, and assembling a new nuclear reactor core. Students, young professionals from the South African nuclear industry, face the situation when a new nuclear reactor core is to be build from scratch. Several reactor core design options are pre-calculated. The selected design is re-calculated by the students, the result is then scrutinized by the regulator and, once all the analysis is approved, physical dismantling of the current core and assembling of the new core is done by the students, under a close supervision of the CTU staff. Finally the reactor is made critical with the new core. The presentation focuses on practical issues of such a course, desired reactor features and namely pedagogical and safety aspects. (orig.)

Three-dimensional reactor dynamics code for VVER type nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Kyrki-Rajamaeki, R. [VTT Energy, Espoo (Finland)

1995-10-01

A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.).

Three-dimensional reactor dynamics code for VVER type nuclear reactors

International Nuclear Information System (INIS)

Kyrki-Rajamaeki, R.

1995-10-01

A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.)

Reactor performances and microbial communities of biogas reactors: effects of inoculum sources.

Science.gov (United States)

Han, Sheng; Liu, Yafeng; Zhang, Shicheng; Luo, Gang

2016-01-01

Anaerobic digestion is a very complex process that is mediated by various microorganisms, and the understanding of the microbial community assembly and its corresponding function is critical in order to better control the anaerobic process. The present study investigated the effect of different inocula on the microbial community assembly in biogas reactors treating cellulose with various inocula, and three parallel biogas reactors with the same inoculum were also operated in order to reveal the reproducibility of both microbial communities and functions of the biogas reactors. The results showed that the biogas production, volatile fatty acid (VFA) concentrations, and pH were different for the biogas reactors with different inocula, and different steady-state microbial community patterns were also obtained in different biogas reactors as reflected by Bray-Curtis similarity matrices and taxonomic classification. It indicated that inoculum played an important role in shaping the microbial communities of biogas reactor in the present study, and the microbial community assembly in biogas reactor did not follow the niche-based ecology theory. Furthermore, it was found that the microbial communities and reactor performances of parallel biogas reactors with the same inoculum were different, which could be explained by the neutral-based ecology theory and stochastic factors should played important roles in the microbial community assembly in the biogas reactors. The Bray-Curtis similarity matrices analysis suggested that inoculum affected more on the microbial community assembly compared to stochastic factors, since the samples with different inocula had lower similarity (10-20 %) compared to the samples from the parallel biogas reactors (30 %).

The fast reactor

International Nuclear Information System (INIS)

1980-02-01

The subject is discussed as follows: brief description of fast reactors; advantage in conserving uranium resources; experience, in UK and elsewhere, in fast reactor design, construction and operation; safety; production of plutonium, security aspects; consideration of future UK fast reactor programme. (U.K.)

APLICAÇÃO DE SISTEMAS DE WETLANDS CONTRUÍDOS OPERANDO COMO UNIDADES DE POLIMENTO DE EFLUENTES DE REATORES UASB

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Luciano Matos Queiroz

2014-08-01

Full Text Available O presente trabalho objetivou a realização de uma análise crítica sobre a aplicação de wetlands construídoscomo unidades de polimento de efluentes de reatores UASB (Upflow Anaerobic Sludge Blanket Reactors.O estudo foi realizado a partir de informações e dados obtidos por meio de trabalhos técnicos e científicospublicados entre os anos de 2000 e 2009, os quais estudaram a capacidade de degradação da matériaorgânica e o grau de remoção de nutrientes em sistemas de wetlands construídos exclusivamente paraessa finalidade. Foi realizada uma análise estatística relacionando cada um dos parâmetros chave adotadosnos projetos dos sistemas (taxas de aplicação superficial, tipos de substrato e macrófitas com a eficiênciade remoção de poluentes. As técnicas utilizadas para verificação da correlação entre as variáveis estudadasforam a estatística descritiva e análise de regressão linear multivariada. Todos os dados foram tratados emnível de significância de 95%. Os resultados permitiram concluir que, de maneira geral, os sistemas dewetlands construídos estudados apresentaram valores médios de eficiência de remoção de 78,3%, 54,4% e66,9% para matéria orgânica, medida como DQO, Nitrogênio Total Kjedhal (NTK e fósforo (P,respectivamente. O excelente desempenho da tecnologia para remoção de DQO foi ratificado pelo teste dehipótese. Os resultados mostram que o tipo de substrato utilizado (areia e brita não é significativo para aobtenção de elevadas eficiências e remoção de poluentes nos sistemas; por outro lado, o tipo de macrófitautilizado mostrou-se relevante para a remoção de NTK e P.

PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Masood, Z.

2016-01-01

The PUSPATI TRIGA Reactor is the only research reactor in Malaysia. This 1 MW TRIGA Mk II reactor first reached criticality on 28 June 1982 and is located at the Malaysian Nuclear Agency premise in Bangi, Malaysia. This reactor has been mainly utilised for research, training and education and isotope production. Over the years several systems have been refurbished or modernised to overcome ageing and obsolescence problems. Major achievements and milestones will also be elaborated in this paper. (author)

Fast Spectrum Reactors

CERN Document Server

Todd, Donald; Tsvetkov, Pavel

2012-01-01

Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

Reactor Engineering Department annual report

International Nuclear Information System (INIS)

1985-08-01

Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

Matsuura, Shojiro; Nakahara, Yasuaki; Takano, Hideki

1982-09-01

Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

Request for Naval Reactors Comment on Proposed PROMETHEUS Space Flight Nuclear Reactor High Tier Reactor Safety Requirements and for Naval Reactors Approval to Transmit These Requirements to Jet Propulsion Laboratory

International Nuclear Information System (INIS)

D. Kokkinos

2005-01-01

The purpose of this letter is to request Naval Reactors comments on the nuclear reactor high tier requirements for the PROMETHEUS space flight reactor design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval Reactors approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the reactor safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear reactor high tier safety requirements are consistent with the long standing safety culture of the Naval Reactors Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophy on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear Reactors (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory

Multi-purpose reactor

International Nuclear Information System (INIS)

1991-05-01

The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MW t h, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co 60 ) production capacity is 50000 Ci/yr, 200 Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N 16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

Mirror reactor studies

International Nuclear Information System (INIS)

Moir, R.W.; Barr, W.L.; Bender, D.J.

1977-01-01

Design studies of a fusion mirror reactor, a fusion-fission mirror reactor, and two small mirror reactors are summarized. The fusion reactor uses 150-keV neutral-beam injectors based on the acceleration of negative ions. The injectors provide over 1 GW of continuous power at an efficiency greater than 80%. The fusion reactor has three-stage, modularized, Venetian blind, plasma direct converter with a predicted efficiency of 59% and a new concept for removal of the lune-shaped blanket: a crane is brought between the two halves of the Yin-Yang magnet, which are separated by a float. The design has desirable features such as steady-state operation, minimal impurity problems, and low first-wall thermal stress. The major disadvantage is low Q resulting in high re-circulating power and hence high cost of electrical power. However, the direct capital cost per unit of gross electrical power is reasonable [$1000/kW(e)]. By contrast, the fusion-fission reactor design is not penalized by re-circulating power and uses relatively near-term fusion technology being developed for the fusion power program. New results are presented on the Th- 233 U and the U- 239 Pu fuel cycles. The purpose of this hybrid is fuel production, with projected costs at $55/g of Pu or $127/g of 233 U. Blanket and cooling system designs, including an emergency cooling system, by General Atomic Company, lead us to the opinion that the reactor can meet expected safety standards for licensing. The smallest mirror reactor having only a shield between the plasma and the coil is the 4.2-m long fusion engineering research facility (FERF) designed for material irradiation. The smallest mirror reactor having both a blanket and shield is the 7.5-m long experimental power reactor (EPR), which has both a fusion and a fusion-fission version. (author)

Das bruxas, dos índios, dos negros e dos jovens da Febem

Directory of Open Access Journals (Sweden)

Sylvia Leser de Mello

2001-01-01

Full Text Available Este artigo visa discutir os temas Pesquisa e Direitos Humanos, partindo da definição do que pretende a Ciência, suas limitações e momentos seus a serviço de condenações de bruxas e ateus. Trata-se de levantar a questão da 'parcialidade' da Ciência e das formas de exclusão que ela ajudou a gerar e manter face aos criminosos, aos loucos, aos negros e, sem dúvida, aos jovens das camadas populares que são institucionalizados na FEBEM. E, na tentativa de resistência a se deixar levar pelo que de nefasto existe na mercantilização da Ciência hoje, buscar radicalizar a exigência de defesa dos Direitos Humanos.

Reactor Simulations for Safeguards with the MCNP Utility for Reactor Evolution Code

International Nuclear Information System (INIS)

Shiba, T.; Fallot, M.

2015-01-01

To tackle nuclear material proliferation, we conducted several proliferation scenarios using the MURE (MCNP Utility for Reactor Evolution) code. The MURE code, developed by CNRS laboratories, is a precision, open-source code written in C++ that automates the preparation and computation of successive MCNP (Monte Carlo N-Particle) calculations and solves the Bateman equations in between, for burnup or thermal-hydraulics purposes. In addition, MURE has been completed recently with a module for the CHaracterization of Radioactive Sources, called CHARS, which computes the emitted gamma, beta and alpha rays associated to any fuel composition. Reactor simulations could allow knowing how plutonium or other material generation evolves inside reactors in terms of time and amount. The MURE code is appropriate for this purpose and can also provide knowledge on associated particle emissions. Using MURE, we have both developed a cell simulation of a typical CANDU reactor and a detailed model of light water PWR core, which could be used to analyze the composition of fuel assemblies as a function of time or burnup. MURE is also able to provide, thanks to its extension MURE-CHARTS, the emitted gamma rays from fuel assemblies unloaded from the core at any burnup. Diversion cases of Generation IV reactors have been also developed; a design of Very High Temperature Reactor (a Pebble Bed Reactor (PBR), loaded with UOx, PuOx and ThUOx fuels), and a Na-cooled Fast Breeder Reactor (FBR) (with depleted Uranium or Minor Actinides in the blanket). The loading of Protected Plutonium Production (P3) in the FBR was simulated. The simulations of various reactor designs taking into account reactor physics constraints may bring valuable information to inspectors. At this symposium, we propose to show the results of these reactor simulations as examples of the potentiality of reactor simulations for safeguards. (author)

Reactor Sharing Program

International Nuclear Information System (INIS)

Tehan, Terry

2002-01-01

Support utilization of the RINSC reactor for student and faculty instructions and research. The Department of Energy award has provided financial assistance during the period 9/29/1995 to 5/31/2001 to support the utilization of the Rhode Island Nuclear Science Center (RINSC) reactor for student and faculty instruction and research by non-reactor owning educational institutions within approximately 300 miles of Narragansett, Rhode Island. Through the reactor sharing program, the RINSC (including the reactor and analytical laboratories) provided reactor services and laboratory space that were not available to the other universities and colleges in the region. As an example of services provided to the users: Counting equipment, laboratory space, pneumatic and in-pool irradiations, demonstrations of sample counting and analysis, reactor tours and lectures. Funding from the Reactor Sharing Program has provided the RINSC to expand student tours and demonstration programs that emphasized our long history of providing these types of services to the universities and colleges in the area. The funding have also helped defray the cost of the technical assistance that the staff has routinely provided to schools, individuals and researchers who have called on the RINSC for resolution of problems relating to nuclear science. The reactor has been featured in a Public Broadcasting System documentary on Pollution in the Arctic and how a University of Rhode Island Professor used Neutron Activation Analysis conducted at the RINSC to discover the sources of the ''Arctic Haze''. The RINSC was also featured by local television on Earth Day for its role in environmental monitoring

NUCLEAR REACTOR

Science.gov (United States)

Miller, H.I.; Smith, R.C.

1958-01-21

This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

Technological status of reactor coolant pumps in generation III+ pressurized nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Brecht, Bernhard; Bross, Stephan [KSB Aktiengesellschaft, Frankenthal (Germany)

2016-05-15

KSB has been developing and producing pumps for thermal power plants for nearly 90 years. Consequently, KSB also started to develop and manufacture pumps for all kinds of nuclear power plants from the very beginning of the civil use of nuclear energy. This is especially true for reactor coolant pumps for pressurized water reactors. For the generation of advanced evolutionary reactors (Generation III+ reactors), KSB developed an advanced shaft seal system which is also able to fulfill the requirements of station blackout conditions. The tests in the KSB test rigs, which were successfully completed in December 2015, proved the full functionality of the new design. For generation III+ passive plant reactors KSB developed a new reactor coolant pump type called RUV, which is based on the experience of classic reactor coolant pumps and reactor internal pumps. It is a very compact, hermetically sealed vertical pump-motor unit with a wet winding motor. A full scale prototype successfully passed the 1st stage qualification test program in October 2015.

Reactor control device

International Nuclear Information System (INIS)

Fukami, Haruo; Morimoto, Yoshinori.

1981-01-01

Purpose: To operate a reactor always with safety operation while eliminating the danger of tripping. Constitution: In a reactor control device adapted to detect the process variants of a reactor, control a control rod drive controlling system based on the detected signal to thereby control the driving the control rods, control the reactor power and control the electric power generated from an electric generator by the output from the reactor, detection means is provided for the detection of the electric power from said electric generator, and a compensation device is provided for outputting control rod driving compensation signals to the control rod driving controlling system in accordance with the amount of variation in the detected value. (Seki, T.)

Research reactor DHRUVA

International Nuclear Information System (INIS)

Veeraraghaven, N.

1990-01-01

DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 10 14 n/cm 2 /sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

Fully integrated analysis of reactor kinetics, thermalhydraulics and the reactor control system in the MAPLE-X10 research reactor

International Nuclear Information System (INIS)

Shim, S.Y.; Carlson, P.A.; Baxter, D.K.

1992-01-01

A prototype research reactor, designated MAPLE-X10 (Multipurpose Applied Physics Lattice Experimental - X 10MW), is currently being built at AECL's Chalk River Laboratories. The CATHENA (Canadian Algorithm for Thermalhydraulic Network Analysis) two-fluid code was used in the safety analysis of the reactor to determine the adequacy of core cooling during postulated reactivity and loss-of-forced-flow transients. The system responses to a postulated transient are predicted including the feedback between reactor kinetics, thermalhydrauilcs and the reactor control systems. This paper describes the MAPLE-X10 reactor and the modelling methodology used. Sample simulations of postulated loss-of-heat-sink and loss-of-regulation transients are presented. (author)

Power Trip Set-points of Reactor Protection System for New Research Reactor

International Nuclear Information System (INIS)

Lee, Byeonghee; Yang, Soohyung

2013-01-01

This paper deals with the trip set-point related to the reactor power considering the reactivity induced accident (RIA) of new research reactor. The possible scenarios of reactivity induced accidents were simulated and the effects of trip set-point on the critical heat flux ratio (CHFR) were calculated. The proper trip set-points which meet the acceptance criterion and guarantee sufficient margins from normal operation were then determined. The three different trip set-points related to the reactor power are determined based on the RIA of new research reactor during FP condition, over 0.1%FP and under 0.1%FP. Under various reactivity insertion rates, the CHFR are calculated and checked whether they meet the acceptance criterion. For RIA at FP condition, the acceptance criterion can be satisfied even if high power set-point is only used for reactor trip. Since the design of the reactor is still progressing and need a safety margin for possible design changes, 18 MW is recommended as a high power set-point. For RIA at 0.1%FP, high power setpoint of 18 MW and high log rate of 10%pp/s works well and acceptance criterion is satisfied. For under 0.1% FP operations, the application of high log rate is necessary for satisfying the acceptance criterion. Considering possible decrease of CHFR margin due to design changes, the high log rate is suggested to be 8%pp/s. Suggested trip set-points have been identified based on preliminary design data for new research reactor; therefore, these trip set-points will be re-established by considering design progress of the reactor. The reactor protection system (RPS) of new research reactor is designed for safe shutdown of the reactor and preventing the release of radioactive material to environment. The trip set point of RPS is essential for reactor safety, therefore should be determined to mitigate the consequences from accidents. At the same time, the trip set-point should secure margins from normal operational condition to avoid

COMPARAÇÃO DOS MÉTODOS OFICIAIS DE ANÁLISE E CROMATOGRÁFICOS PARA A DETERMINAÇÃO DOS TEORES DE ALDEÍDOS E ÁCIDOS EM BEBIDAS ALCOÓLICAS

Directory of Open Access Journals (Sweden)

NASCIMENTO Ronaldo F.

1998-01-01

Full Text Available É apresentado um estudo comparativo entre os métodos oficiais e cromatográficos para a análise de aldeídos e de ácidos em bebidas alcoólicas. Foram analisadas trinta e cinco amostras de destilados alcoólicos. Com respeito a determinação dos teores totais de aldeídos e de ácidos. Os métodos oficiais e cromatográficos apresentam similar exatidão e reprodutibilidade. Entretanto, apenas os métodos cromatográficos permitem identificar e quantificar os componentes de cada série homologa. As metodologias propostas utilizando as técnicas de cromatografia gasosa e cromatografia líquida são simples, rápidas e apresentam maior sensibilidade que os métodos oficiais sendo aplicáveis também a amostras coloridas.

Investigation of the basic reactor physics characteristics of the Dalat Nuclear Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Huy, Ngo Quang [Centre for Nuclear Technique Application, Ho Chi Minh City (Viet Nam); Thong, Ha Van; Khang, Ngo Phu [Nuclear Research Inst., Da Lat (Viet Nam)

1994-10-01

The Dalat nuclear research reactor was reconstructed from TRIGA MARK II reactor, built in 1963 with nominal power of 250 KW, and reached its planned nominal power of 500 kW for the first time in Feb. 1984. The Dalat reactor has some characteristics distinct from the former TRIGA reactor. Investigation of its characteristics is carried out by the determination of the reactor physics parameters. This paper represents the experimental results obtained for the effective fraction of the delayed photoneutrons, the extraneous neutron source left after the reactor is shut down, the lowest power levels of reactor critical states, the relative axial and radial distributions of thermal neutrons, the safe positive reactivity inserted into the reactor at deep subcritical state, the reactivity temperature coefficient of water, the temperature on the surface of the fuel elements, etc. (author). 10 refs., 10 figs., 2 tabs.

Influência da forma dos agregados miúdos nas propriedades do concreto

Directory of Open Access Journals (Sweden)

F. Fabro

Full Text Available Os agregados miúdos utilizados na produção de concretos são basicamente as areias naturais provenientes dos leitos dos rios e os agregados artificiais oriundos da britagem de rocha. A principal diferença entre estes dois agregados está no formato de seus grãos. O objetivo principal deste trabalho é avaliar o formato dos grãos de agregados miúdos por meio de diferentes parâmetros, analisando as diferenças entre as formas dos agregados, e suas conseqüências nas propriedades das argamassas e concretos confeccionadas com estes materiais. Para medição dos grãos dos agregados empregou-se a análise digital de imagens e foram calculados os seguintes parâmetros: relação de aspecto, esfericidade, indicador de lamelaridade e coeficiente de forma, sendo que os dois últimos foram os que melhor avaliaram a forma dos agregados. Observou-se que o formato dos grãos dos agregados artificiais depende do tipo de britador empregado pelas pedreiras no processo de britagem das rochas. Os agregados oriundos do britador do tipo vertical de impacto possuem grãos mais arredondados, semelhantes aos grãos da areia natural. Verificou-se que o formato dos grãos dos agregados tem influência direta sobre a consistência das argamassas e concretos, porém não apresentou influência nos resultados de resistência à compressão.

Reactor safety device

International Nuclear Information System (INIS)

Okada, Yasumasa.

1987-01-01

Purpose: To scram control rods by processing signals from a plurality of temperature detectors and generating abnormal temperature warning upon occurrence of abnormal temperature in a nuclear reactor. Constitution: A temperature sensor comprising a plurality of reactors each having a magnetic body as the magnetic core having a curie point different from each other and corresponding to the abnormal temperature against which reactor core fuels have to be protected is disposed in an identical instrumentation well near the reactor core fuel outlet/inlet of a reactor. A temperature detection device actuated upon detection of an abnormal temperature by the abrupt reduction of the reactance of each of the reactors is disposed. An OR circuit and an AND circuit for conducting OR and AND operations for each of the abnormal temperature detection signals from the temperature detection device are disposed. The output from the OR circuit is used as the abnormal temperature warning signal, while the output from the AND circuit is utilized as a signal for actuating the scram operation of control rod drive mechanisms. Accordingly, it is possible to improve the reliability of the reactor scram system, particularly, improve the reliability under a high temperature atmosphere. (Kamimura, M.)

A prática de enfermagem em uma Unidade de Queimados: análise dos discursos dos enfermeiros

Directory of Open Access Journals (Sweden)

Lídia Aparecida Rossi

1994-06-01

Full Text Available Este estudo teve como objetivo analisar a prática de enfermagem em uma Unidade de Queimados. Essa análise foi realizada a partir dos depoimentos de enfermeiros dessa Unidade, obtidos em um estudo anterior através de técnica de observação participante e de registro cursivo(19. Concluímos que os enfermeiros estão insatisfeitos com os salários, com a jornada de trabalho, com o relacionamento médico-enfermeiro e com as situações que envolvem o sofrimento e a agressividade dos pacientes. O cuidado direto parece consistir em uma fonte de satisfação, mas o enfermeiro está dividido entre a realização desse cuidado e os problemas que têm que resolver. O planejamento da assistência foi ajustado às rotinas do serviço e não às necessidades dos pacientes.

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

1980-09-01

Research activities in the Division of Reactor Engineering in fiscal 1979 are described. The work of the Division is closely related to development of multi-purpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committees on Reactor Physics and on Decomissioning of Nuclear Facilities. (author)

Reactor scram device for FBR type reactor

International Nuclear Information System (INIS)

Kumasaka, Katsuyuki; Arashida, Genji; Itooka, Satoshi.

1991-01-01

In a control rod attaching structure in a reactor scram device of an FBR type reactor, an anti-rising mechanism proposed so far against external upward force upon occurrence of earthquakes relies on the engagement of a mechanical structure but temperature condition is not taken into consideration. Then, in the present invention, a material having curie temperature characteristics and which exhibits ferromagnetism only under low temperature condition and a magnet device are disposed to one of a movable control rod and a portion secured to the reactor. Alternatively, a bimetal member or a shape memory alloy which actuates to fix to the mating member only under low temperature condition is secured. The fixing device is adapted to operate so as to secure the control rods when the low temperature state is caused depending on the temperature condition. With such a constitution, when the control rods are separated from a driving device, they are prevented from rising even if they undergo external upward force due to earthquakes and so on, which can improve the reactor safety. (N.H.)

Nuclear reactor engineering: Reactor systems engineering. Fourth edition, Volume Two

International Nuclear Information System (INIS)

Glasstone, S.; Sesonske, A.

1994-01-01

This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Extensively updated, the fourth edition includes new materials on reactor safety and risk analysis, regulation, fuel management, waste management and operational aspects of nuclear power. This volume contains the following: the systems concept, design decisions, and information tools; energy transport; reactor fuel management and energy cost considerations; environmental effects of nuclear power and waste management; nuclear reactor safety and regulation; power reactor systems; plant operations; and advanced plants and the future

Refuelling nuclear reactors

International Nuclear Information System (INIS)

Stacey, J.; Webb, J.; White, W.P.; McLaren, N.H.

1981-01-01

An improved nuclear reactor refuelling machine is described which can be left in the reactor vault to reduce the off-load refuelling time for the reactor. The system comprises a gripper device rangeable within a tubular chute, the gripper device being movable by a pantograph. (U.K.)

Compilation of reactor physics data of the year 1984, AVR reactor

International Nuclear Information System (INIS)

Werner, H.; Bergerfurth, A.; Thomas, F.; Geskes, B.

1985-12-01

The 'AVR reactor physics data' is a documentation published once a year, the data presented being obtained by a simulation of reactor operation using the AVR-80 numerical model. This model is constantly updated and improved in response to new results and developments in the field of reactor theory and thermohydraulics, and in response to theoretical or practical modifications of reactor operation or in the computer system. The large variety of measured data available in the AVR reactor simulation system also makes it an ideal testing system for verification of the computing programs presented in the compilation. A survey of the history of operations in 1984 and a short explanation of the computerized simulation methods are followed by tables and graphs that serve as a source of topical data for readers interested in the physics of high-temperature pebble-bed reactors. (orig./HP) [de

Compilation of reactor physics data of the year 1983, AVR reactor

International Nuclear Information System (INIS)

Werner, H.; Bergerfurth, A.; Thomas, F.; Geskes, B.

1985-06-01

The 'AVR reactor physics data' is a documentation published once a year, the data presented being obtained by a simulation of reactor operation using the AVR-80 numerical model. This model is constantly updated and improved in response to new results and developments in the field of reactor theory and thermohydraulics, and in response to theoretical or practical modifications of reactor operation or in the computer system. The large variety of measured data available in the AVR reactor simulation system also makes it an ideal testing system for verification of the computing programs presented in the compilation. A survey of the history of operations in 1983 and a short explanation of the computerized simulation methods are followed by tables and graphs that serve as a source of topical data for readers interested in the physics of high-temperature pebble-bed reactors. (orig./HP) [de

Reactor containment

International Nuclear Information System (INIS)

Kawabe, Ryuhei; Yamaki, Rika.

1990-01-01

A water vessel is disposed and the gas phase portion of the water vessel is connected to a reactor container by a pipeline having a valve disposed at the midway thereof. A pipe in communication with external air is extended upwardly from the liquid phase portion to a considerable height so as to resist against the back pressure by a waterhead in the pipeline. Accordingly, when the pressure in the container is reduced to a negative level, air passes through the pipeline and uprises through the liquid phase portion in the water vessel in the form of bubbles and then flows into the reactor container. When the pressure inside of the reactor goes higher, since the liquid surface in the water vessel is forced down, water is pushed up into the pipeline. Since the waterhead pressure of a column of water in the pipeline and the pressure of the reactor container are well-balanced, gases in the reactor container are not leaked to the outside. Further, in a case if a great positive pressure is formed in the reactor container, the inner pressure overcomes the waterhead of the column of water, so that the gases containing radioactive aerosol uprise in the pipeline. Since water and the gases flow being in contact with each other, this can provide the effect of removing aerosol. (T.M.)

Multipurpose research reactors

International Nuclear Information System (INIS)

1988-01-01

The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

1978-10-01

Research activities in the Division of Reactor Engineering in fiscal 1977 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committee on Reactor Physics. (Author)

An internally illuminated monolith reactor: Pros and cons relative to a slurry reactor

NARCIS (Netherlands)

Carneiro, Joana T.; Carneiro, J.T.; Berger, Rob; Moulijn, Jacob A.; Mul, Guido

2009-01-01

In the present study, kinetic models for the photo-oxidation of cyclohexane in two different photoreactor systems are discussed: a top illumination reactor (TIR) representative of a slurry reactor, and the so-called internally illuminated monolith reactor (IIMR) representing a reactor containing

Undergraduate reactor control experiment

International Nuclear Information System (INIS)

Edwards, R.M.; Power, M.A.; Bryan, M.

1992-01-01

A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

Advances in reactor physics education: Visualization of reactor parameters

International Nuclear Information System (INIS)

Snoj, L.; Kromar, M.; Zerovnik, G.

2012-01-01

Modern computer codes allow detailed neutron transport calculations. In combination with advanced 3D visualization software capable of treating large amounts of data in real time they form a powerful tool that can be used as a convenient modern educational tool for reactor operators, nuclear engineers, students and specialists involved in reactor operation and design. Visualization is applicable not only in education and training, but also as a tool for fuel management, core analysis and irradiation planning. The paper treats the visualization of neutron transport in different moderators, neutron flux and power distributions in two nuclear reactors (TRIGA type research reactor and a typical PWR). The distributions are calculated with MCNP and CORD-2 computer codes and presented using Amira software. (authors)

Comparative study between two austenitic steels with the EPR (Electrochemical Potentiokinetic Reactivation) technique.; Estudio comparativo entre dos aceros austeniticos mediante la tecnica EPR (Reactivacion Electroquimica Potenciocinetica)

Energy Technology Data Exchange (ETDEWEB)

Guillen M, A N

1997-09-01

In the mid 19704s, the intergranular corrosion with stress corrosion cracking (IGSCC) have been identified as a greater problem in Boiling Water Reactors BWR in several places of the world. The Electrochemical Potentiokinetic Reactivation - Single Loop (EPR-SL) test and the Double Loop (EPR-DL) test, were developed as methods for measuring the Degree of Sensitization (DOS), show sensitised materials at subject to Intergranular Corrosion. In Mexico, the Laguna Verde4s reactor is BWR type and many of its principal components was built with AISI 304 stainless steels, while that in VVER reactors as well as Juragua4s reactor in Cuba is used 321 Stainless stell in its Russian equivalent designation 08Ch18N10T. In this work, were studied 304 and 08Ch18N10T stainless steels by means of EPR-SL, EPR-DL and ASTM A-262 techniques, they have been found a good correlation for 304 steel but not in 08Ch18N10T steel and was proposed one modification in the criterion by the evaluation on the sensitisation in this steels. Finally, both materials were welded with procedures used in the nuclear industry, by Slow Strain Rate Test (SSRT) to determine the Stress Corrosion Cracking SCC susceptibility, and subsequently the susceptibility to localized corrosion was studied by means of Cyclic Polarization test and the uniform corrosion rate in a solution with chlorides by the Tafel plot, Potentiodynamic Anodic Polarization Resistance. (Author).

SATISFAÇÃO DOS CLIENTES: UMA ANÁLISE DA QUALIDADE DOS SERVIÇOS PRESTADOS POR UM HOSPITAL DO NORTE FLUMINENSE

Directory of Open Access Journals (Sweden)

PIANNA, L M

2015-12-01

Full Text Available A satisfação dos clientes demonstra a qualidade nos serviços prestados pela organização. O atendimento é atualmente um dos assuntos mais importantes e pesquisados pelas instituições hospitalares que almejam prestar um serviço de melhor qualidade aos seus pacientes. Segundo Kotler (1998, p. 53 algumas das empresas mais bem-sucedidas de hoje estão aumentando as expectativas dos consumidores e melhorando suas condições de atendimento por meio das pesquisas de satisfação. A satisfação do cliente é um dos principais indicadores da qualidade no atendimento à saúde, por isso a importância de analisar o bem-estar dos usuários em relação aos serviços que lhe são oferecidos é de extrema importância. Com base neste contexto, a avaliação dos serviços prestados sobre percepção dos usuários, transformou-se em uma ferramenta fundamental para os tomadores de decisão. A administração deste tipo de serviço é um processo complexo, cheio de subjetivismo, envolvem valores, experiências dentre outros aspectos. Para Las Casas (2008, p.62 as empresas voltadas para o cliente devem priorizar as pesquisas dos consumidores. Assim, é possível conhecer as atuais necessidades e desejos, ou então identificar os níveis de satisfação que o consumidor em relação à empresa. Empresas com foco no cliente desenvolvem práticas permanentes para identificar suas necessidades. A compreensão das expectativas e necessidades dos clientes facilita a empresa aderir a procedimentos que correspondem a essas necessidades. Entretanto, o objetivo principal deste estudo é identificar o nível de satisfação dos clientes com base na metodologia servqual em um hospital do Norte Fluminense. Para atender o objetivo geral deste estudo, foram propostos os seguintes objetivos específicos: construir referencial teórico sobre qualidade em serviços; elencar dimensões do modelo servqual para avaliação da qualidade em serviço; apontar possíveis perdas

Reactor feedwater system

International Nuclear Information System (INIS)

Hikabe, Katsumi.

1978-01-01

Purpose: In order to prevent thermal stresses of a core of PWR type reactor, described has been a method for feeding heated recirculating water to the core in the case of the reactor start-up or shut-down. Constitution: A recirculating water is degassed, cleaned up and heated in the steam condensers, and then feeds the water to the reactor, characterized in that heaters are provided in the bypasses of the turbine, so that heated water is constantly supplied to the reactor. (Nakamura, S.)

New reactor concepts

International Nuclear Information System (INIS)

Meskens, G.; Govaerts, P.; Baugnet, J.-M.; Delbrassine, A.

1998-11-01

The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

Nuclear reactor design

CERN Document Server

2014-01-01

This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

Fission reactors and materials

International Nuclear Information System (INIS)

Frost, B.R.T.

1981-12-01

The American-designed boiling water reactor and pressurized water reactor dominate the designs currently in use and under construction worldwide. As in all energy systems, materials problems have appeared during service; these include stress-corrosion of stainless steel pipes and heat exchangers and questions regarding crack behavior in pressure vessels. To obtain the maximum potential energy from our limited uranium supplies is is essential to develop the fast breeder reactor. The materials in these reactors are subjected to higher temperatures and neutron fluxes but lower pressures than in the water reactors. The performance required of the fuel elements is more arduous in the breeder than in water reactors. Extensive materials programs are in progress in test reactors and in large test rigs to ensure that materials will be available to meet these conditions

Spectral shift reactor control method

International Nuclear Information System (INIS)

Impink, A.J. Jr.

1981-01-01

A method of operating a nuclear reactor having a core and coolant displacer elements arranged in the core wherein is established a reator coolant temperature set point at which it is desired to operate said reactor and first reactor coolant temperature band limits are provided within which said set point is located and it is desired to operate said reactor charactrized in that said reactor coolant displacer elements are moved relative to the reactor core for adjusting the volume of reactor coolant in said core as said reactor coolant temperature approaches said first band limits thereby to maintain said reactor coolant temperature near said set point and within said first band limits

Method of operating a reactor

International Nuclear Information System (INIS)

Oosumi, Katsumi; Yamamoto, Michiyoshi.

1980-01-01

Purpose: To prevent stress corrosion cracking in the structural material of a reactor pressure vessel. Method: Prior to the starting of a reactor, the reactor pressure vessel is evacuated to carry out degassing of reactor water, and, at the same time, reactor water is heated. After reactor water is heated to a predetermined temperature, control rods are extracted to start nuclear heating. While the temperature of the reactor water is in a temperature range where elution of a metal which is a structural material of the reactor pressure vessel becomes vigorous and the sensitivity to the stress corrosion cracks increases, the reactor is operated at the maximum permissible temperature raising speed or maximum permissible cooling speed. (Aizawa, K.)

Reactor container

International Nuclear Information System (INIS)

Abe, Yoshihito; Sano, Tamotsu; Ueda, Sabuo; Tanaka, Kazuhisa.

1987-01-01

Purpose: To improve the liquid surface disturbance in LMFBR type reactors. Constitution: A horizontal flow suppressing mechanism mainly comprising vertical members is suspended near the free liquid surface of coolants in the upper plenum. The horizontal flow of coolants near the free liquid surface is reduced by the suppressing mechanism to effectively reduce the surface disturbance. The reduction in the liquid surface disturbance further prevails to the entire surface region with no particular vertical variations to the free liquid surface to remarkably improve the preventive performance for the liquid surface disturbance. Accordingly, it is also possible to attain the advantageous effects such as prevention for the thermal fatigue in reactor vessel walls, reactor upper mechanisms, etc. and prevention of burning damage to the reactor core due to the reduction of envolved Ar gas. (Kamimura, M.)

Solubilidade e disponibilidade dos micronutrientes em fertilizantes