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Sample records for bolsa chica-1 reactor

  1. The Brazilian Bolsa Escola

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    Rachel Cassidy

    2008-12-01

    Full Text Available The Bolsa Escola (‘school stipend’ and its successor the Bolsa Familia (‘family stipend’ schemes have formed a crucial and successful part of Brazil’s welfare program. Bolsa Escola provided aid to Brazil’s poorest families on the condition that their children attended school, and Bolsa Familia has extended this idea, giving aid on the condition that children both attend school and receive vaccinations. Bolsa Familia is currently the largest Conditional Cash Transfer Program (CCTP in the world, costing roughly 0.5% of Brazilian GDP and helping around 11.2 million families (around 44 million Brazilians, constituting roughly one fifth of the population. Multilateral institutions have praised the schemes, and they are setting a leading example to other developing nations. In 2005, Paul Wolfowitz (former president of the World Bank said, ‘Bolsa Familia has already become a highly praised model of effective social policy. Countries around the world are drawing lessons from Brazil’s experience and are trying to produce the same results for their own people’.

  2. La Nueva Bolsa de Londres - Gran Bretaña

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    Llewellyn-Davies, Richard

    1974-06-01

    Full Text Available It will occupy the space of the present Stock Exchange of the capital of the United Kingdom, between Throgmorton, Bartholomew, Threadneedle and Old Bross streets Due to its evident insufficiency it has been necessary to enlarge the old building - by constructing a high block of 26 stories intended to accomodate the administrative council of the Stock Exchange in the first eleven, various offices in another eleven and installations in the four remaining ones. Likewise a spacious business hall without intermediate columns has been constructed surrounded by smaller office rooms for the Stock Exchange agents. The general construction of the tower is carried out with a core, poured in site, with the vertical circulations —eight lifts, two winches and two staircases—, W.C.s and cavities for various conductions and the sides of the polygon formed by prefabricated alternating members, some of them hollow to accomodate the installations and some solid, as structural elements. The construction was carried out in three phases: I tower; II business hall. Brokers and public relations block; III demolition of old parts.Ocupará el lugar que alberga la actual Bolsa de la capital del Reino Unido, entre las calles Throgmorton, Bartholomew Threadneedle y Old Broad. Dada su manifiesta insuficiencia ha sido preciso ampliar el viejo edificio construyendo un bloque alto, de veintiséis plantas, destinado a acomodar: el Consejo y Administración de la Bolsa, en las once primeras; oficinas varias, en otras once, y las instalaciones, en las cuatro restantes. Se ha creado, asimismo, un amplio salón de operaciones sin pilares intermedios, rodeado de despachos más pequeños para los agentes de Bolsa. La construcción general de la torre está materializada por un núcleo, hormigonado in situ, con las circulaciones verticales —ocho ascensores, dos montacargas y dos escaleras—, aseos y huecos para conducciones varias, y los lados del polígono formados por

  3. Autoimagem de clientes com colostomia em relação à bolsa coletora

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    Maria do Rosário de Fátima Franco Batista

    2011-12-01

    Full Text Available Objetivou-se analisar a percepção do portador de colostomia em relação ao uso da bolsa coletora. Realizou-se uma pesquisa descritiva com abordagem qualitativa, no Centro Integrado de Saúde Lineu Araújo, Teresina-PI. Participaram da pesquisa dez clientes portadores de bolsa de colostomia. Os dados foram produzidos por meio de entrevistas semiestruturadas. A análise de conteúdo permitiu revelar os sentimentos, as mudanças ocorridas e como acontece o processo de adaptação da pessoa portadora da bolsa de colostomia. Constatou-se que a relação entre a pessoa portadora de colostomia e a bolsa coletora é permeada por sentimentos negativos, mudanças significativas de ordem físicas, psicológicas, sexuais, bem como na teia de suas relações sociais.

  4. Timpanismo bilateral de bolsa gutural em potro Bilateral tympany of a guttural pouch in foal

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    Carlos Augusto Araújo Valadão; Júlio Carlos Canola; Roberta Ferro de Godoy

    2004-01-01

    Uma potra da raça Quarto de Milha com dois meses de idade apresentava aumento de volume bilateral na região da parótida desde algumas horas após o nascimento. Por exame radiográfico diagnosticou-se timpanismo bilateral de bolsa gutural. Realizou-se a abertura cirúrgica da bolsa gutural esquerda e fenestrou-se o septo medial das bolsas guturais. Adicionalmente, procedeu-se à ressecção parcial da mucosa na abertura do orifício guturo-faríngeo. A afecção foi debelada, sem recidivas.A 2-month old...

  5. Cistos de bolsa de Rathke: diagnóstico e tratamento

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    Rodrigues Flávio Freinkel

    2001-01-01

    Full Text Available Estudamos retrospectivamente quatro pacientes com cisto de bolsa de Rathke. Chamamos a atenção para a apresentação clínica e para o tratamento destas lesões. Todos ocorreram em pacientes do sexo feminino. Os sintomas predominantes foram amenorréia, cefaléia e déficit visual. Revisamos várias séries publicadas de cistos de bolsa de Rathke. Concluimos que o tratamento cirúrgico é ainda a melhor conduta e que a via transesfenoidal é a abordagem mais indicada.

  6. Bolsa Família e desigualdade da renda domiciliar entre 2006 e 2011 = Bolsa Família and inequality of household income between 2006 and 2011

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    Carvalho, Cleusení Hermelina de

    2014-01-01

    Full Text Available Os programas de transferência condicionada de renda têm crescentemente desempenhado um papel importante no combate à pobreza em vários países da América Latina, principalmente no Brasil. O objetivo deste artigo é analisar a contribuição do programa Bolsa Família na diminuição da desigualdade da renda domiciliar per capita no Brasil, entre 2006 e 2011. Para isso, analisa-se a participação relativa de oito fontes de renda – trabalho, aposentadorias, programa Bolsa Família (variável proxy, pensões, abonos, doações, aluguéis e juros – no Brasil e nas suas cinco macrorregiões. Assim, além do artigo detalhar a técnica matemática utilizada para decompor o Índice de Gini, apresenta e discute os resultados empíricos encontrados para o Brasil e suas macrorregiões. Dentre os resultados, destaca-se a capacidade do programa Bolsa Família em contribuir para a queda da desigualdade da renda domiciliar nacional, o que se explica por sua acentuada focalização

  7. Gamesa: Energía eólica y aeronáutica en Bolsa

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    García Pérez de Lema, Domingo

    2000-01-01

    Las altas tasas de crecimiento han sido una constante en la corta historia de Gamesa como consecuencia de su posición de liderazgo en un sector que ha crecido de forma explosiva en los últimos años en España: la energía eólica. La salida a bolsa es un paso adelante en su objetivo de convertirse en una de las grandes empresas tecnológicas de España.

  8. Timpanismo bilateral de bolsa gutural em potro Bilateral tympany of a guttural pouch in foal

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    Carlos Augusto Araújo Valadão

    2004-08-01

    Full Text Available Uma potra da raça Quarto de Milha com dois meses de idade apresentava aumento de volume bilateral na região da parótida desde algumas horas após o nascimento. Por exame radiográfico diagnosticou-se timpanismo bilateral de bolsa gutural. Realizou-se a abertura cirúrgica da bolsa gutural esquerda e fenestrou-se o septo medial das bolsas guturais. Adicionalmente, procedeu-se à ressecção parcial da mucosa na abertura do orifício guturo-faríngeo. A afecção foi debelada, sem recidivas.A 2-month old Quarter Horse filly presented, since few hours after birth, increased bilateral volume in the parotid gland region, with progressive enlargement. The radiographic examination revealed bilateral tympany of guttural pouch. Surgery was performed by medial septal fenestration. In addition, partial ressection of mucous membrane of the pharingeal orifice was performed. The disease was healed without recurrences.

  9. A produção da maternidade no Programa Bolsa-Escola The production of maternity in the Bolsa-Escola Program

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    Carin Klein

    2005-04-01

    Full Text Available Neste trabalho, analiso alguns processos de produção e veiculação de representações de maternidade, tomando como referência o Programa Nacional Bolsa-Escola. Meu estudo insere-se nos campos dos Estudos Culturais e dos Estudos Feministas, nas vertentes que têm proposto uma aproximação crítica com a abordagem pós-estruturalista. Para a operacionalização da pesquisa, selecionei um conjunto de documentos referentes a esse Programa, produzidos e publicados no período de 1999 a 2003. Exploro os textos do Programa tomando como base os conceitos de discurso, representação, identidade, gênero e poder com o intuito de analisar os diferentes modos pelos quais a maternidade é, ali, representada e significada.In this work I analyze some processes of production and conveyance of maternity representations, having the Programa Nacional Bolsa-Escola as its reference. My study is located in the field of cultural theory, mainly in the Cultural Studies and Feminist Studies perspectives, in approaches that have proposed a critical approximation to the post-structuralist analysis. In order to perform this research, I selected a set of documents related to the Program, which were produced and published from 1999 to 2003. I have explored the texts of the Program on the basis of concepts such as discourse, representation, identity, gender and power, aiming at analyzing the different ways by which maternity has been represented and signified there.

  10. O PROGRAMA BOLSA FAMÍLIA E O “EFEITO PREGUIÇA”

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    Maria Luiza Souza Caetano

    2016-07-01

    Full Text Available During the implementation of the Bolsa Família Program emerged some myths like "laziness effect". This present study aims to reflect on the existence of laziness effect in terms of the works of Campello and Neri (2013 and Weissheimer (2006. Methodologically it is a theoretical article. For this, was made a review of the program, cash transfers and laziness effect. Finally, from the reflections on the works of the authors, it is clear that the laziness effect is a myth.

  11. Desempenho de estimadores de volatilidade na bolsa de valores de São Paulo

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    Bernardo de Sá Mota

    2004-09-01

    Full Text Available O objetivo deste artigo é avaliar o desempenho de diferentes métodos de extração da volatilidade do Índice da Bolsa de Valores de São Paulo (IBOVESPA tendo como referência a volatilidade realizada. Comparamos modelos da família GARCH com estimadores alternativos baseados em cotações de abertura, fechamento, máximo e mínimo. Os resultados indicam que os estimadores alternativos são tão precisos quanto os modelos do tipo GARCH, apesar de serem muito mais econômicos em termos computacionais.

  12. EVALUACIÓN DE LA CALIDAD MICROBIOLÓGICA DEL AGUA ENVASADA EN BOLSAS PRODUCIDA EN SINCELEJO - COLOMBIA

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    Jhon Vidal D; Adolfo Consuegra S; Luty Gomescaseres P; Jose Marrugo N

    2009-01-01

    Objetivo. Evaluar la calidad microbiológica y fisico-quimica del agua envasada en bolsas producidad en la ciudad de Sincelejo-Colombia con destino al consumo humano. Materiales y métodos. Para la estimación de organismos coliformes totales y fecales, Pseudomona aeruginosa y mesófilos en el agua envasada de 13 marcas, se utilizó el método de filtración por membrana (FxM). Resultados. El 92 % de las marcas de agua envasada en bolsa que se produce en la ciudad de Sincelejo presentaron bacterias...

  13. [The impact of conditional cash transfers on health status: the Brazilian Bolsa Familia Programme].

    Science.gov (United States)

    Rivera Castiñeira, Berta; Currais Nunes, Luis; Rungo, Paolo

    2009-01-01

    Conditional cash transfers are becoming the standard approach to reducing poverty levels; the Brazilian Bolsa Familia Program, in particular, is the largest program of this kind, and the evaluation of its impact allows for drawing some interesting conclusions, which may apply to other countries. In this paper, the lack of positive results in terms of both health status and modification of unhealthy habits is underlined. Among different causes, which are discussed here, the existence of barriers on the supply side appears as the most important limitation for obtaining better results. The positive impact of this program on both education and poverty reduction however, allows for predicting improvements in health status in the long run.

  14. Bolsas plásticas: Re-cycling, Re-think, Re-change

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    Barbán Franceschi, Roberta

    2011-01-01

    El trabajo se fundamenta en el discurso teórico donde el problema ambiental, es la justificación de la investigación del residuo doméstico (bolsa de plástico). En la construcción de dicho discurso teórico se justifica y ubica la problemática en la sociedad de consumo y su modelo actual, modelo que ha llevado a un modo de vida insostenible. Adoptamos el concepto “diseño sostenible”, que contempla la dimensión intrínseca del hombre recolocándole en una posición cultural por encima de la prod...

  15. Redistribution and development? the political economy of the Bolsa Família program

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    Celia Lessa Kerstenetzky

    2010-01-01

    Full Text Available The article offers a qualitative evaluation of Brazil's Bolsa Família (Family Grant or Family Stipend Program, viewing it from the perspective of an income redistribution and development policy. Analyzing the program's most striking institutional characteristics -- targeting the poorest and setting conditions such as school enrollment and immunization of the family's children -- the article identifies a major weakness in the program's political economy that could jeopardize its sustainability as a redistributive and development policy. The article suggests that policies with such characteristics in extremely unequal countries like Brazil can make budget limitations endogenous, thus hindering the achievement of the program's own objectives. Two alternative directions are briefly explored: conversion of the program into a hybrid policy, both targeted and universal, and emphasis on the provision of child education services.

  16. Las bolsas de valores en el area del TLCAN: un analisis a largo plazo

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    Édgar Ortiz

    2007-01-01

    a largo plazo. Las pruebas de raíces unitarias de Perron (1989 y Zivot y Andrews (1992 permiten identificar cambios estructurales en el Índice de Precios y Cotizaciones (IPC de la Bolsa Mexicana de Valores (BMV. El estudio de las relaciones de largo plazo entre estos mercados se basa en el modelo de Johansen, Mosconi y Nielsen (2000 que extiende el análisis de cointegración para el caso en que se presentan cambios estructurales. La evidencia empírica sugiere que la integración entre los mercados de capitales del tlcan es cambiante en el tiempo, con periodos en los que incluso disminuye la intensidad de sus relaciones.

  17. Efeitos do Programa Bolsa Família na fecundidade das beneficiárias

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    Patrícia Simões

    2012-12-01

    Full Text Available Procuramos verificar se o Programa Bolsa Família contribui para aumentar a fecundidade entre as beneficiárias, visto que o aumento no tamanho da família, até certo limite, leva ao aumento dos benefícios. Utilizamos um modelo de contagem no qual testamos e tratamos a possibilidade de endogeneidade da variável de política por dois métodos distintos (dois-estágios estilo Heckman e GMM, além de incluir diversos cofatores da PNDS (2006. Os resultados mostram que o PBF não apresentou este efeito, pelo menos no início do programa. Pelo contrário, beneficiárias pareciam mais inclinadas a trocar quantidade por qualidade do que não beneficiárias elegíveis ao programa.

  18. Bolsas de plástico y lazos sociales. Notas de campo sobre reciclaje

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    Cecilia Montero Mórtola

    2011-01-01

    Full Text Available La protección del medio ambiente no sólo consiste en grandes campañas mediáticas y políticas. Existe una ciudadanía silenciosa que ha empezado a modificar actitudes, rescatar viejas costumbres y adaptarlas a distintos espacios de este mundo globalizado (domésticos, informales.... Un cambio cultural donde la reutilización de objetos desechados, a través de actividades artesanales y educativas, sirve para poner en marcha una serie de vínculos y lazos sociales. Estudiando el reciclaje de bolsas de plástico, la antropología puede restituir esos curiosos procesos organizativos, prácticas sociales sólo visibles a partir de un trabajo de campo continuado.

  19. Percepções sobre o Programa Bolsa Família na sociedade brasileira

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    Henrique Carlos de Oliveira de Castro

    2009-11-01

    Full Text Available O artigo trata de percepções da sociedade brasileira sobre o Programa Bolsa Família (PBF a partir de uma pesquisa realizada em amostra da população. A pesquisa indicou que a população reconhece o Programa e entende que ele está sendo utilizado de forma adequada, mesmo considerando problemas em sua execução. Houve uma importante diferença entre a opinião daqueles que conhecem beneficiários em relação àqueles que não conhecem, sendo que os primeiros se manifestaram de forma mais positiva em relação aos resultados e mais cautelosos em relação às críticas, conclui que o PBF adquiriu legitimidade junto à sociedade brasileira dado o nível de conhecimento da política e mesmo de apoio à sua existência e argumenta sobre a importância de buscar e considerar a opinião da sociedade como importante elemento de avaliação de políticas públicas.The paper is about perceptions of Brazilian society concerning the cash transfer program Bolsa Família of Brazilian government obtained in a national survey. It indicated that population recognizes the program and understands that it is being used in an appropriated way, even though considering problems in its execution. Important differences occurred in the opinion of those who knew beneficiaries comparing with those who didn't. The first group manifested positive opinion and criticized less then the second. The paper concludes that the program acquired legitimacy in the Brazilian society, considering the knowledge of this policy and supporting its existence. It argues for the importance of searching and considering the public opinion as a fundamental element of public policy assessing.

  20. Programa Bolsa Família e estado nutricional infantil: desafios estratégicos Bolsa Família Program and child nutritional status: strategic challenges

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    Fabiana de Cássia Carvalho Oliveira

    2011-07-01

    Full Text Available Anemia e desnutrição, principais carências nutricionais na infância, têm como principais determinantes os socioeconômicos. Assim, por se tratar da principal política de combate à pobreza, espera-se que o Programa Bolsa Família (PBF promova impacto no estado nutricional infantil. Objetivou-se analisar as diferenças na situação nutricional de crianças cadastradas no PBF de um município da Zona da Mata Mineira. Foram avaliadas 446 crianças com idade entre 6 e 84 meses, sendo que 262 eram beneficiárias e 184 não-beneficiárias. A avaliação nutricional constituiu-se da análise dos parâmetros peso e estatura, através dos índices peso/idade, peso/estatura, estatura/idade e Índice de Massa Corporal/idade, e dos níveis de hemoglobina, com uso do Hemocue. As prevalências de anemia, déficit estatural e obesidade foram 22,6, 6,3 e 5,2%, respectivamente, sendo que não houve diferença estatística entre os beneficiários e não-beneficiários. Inicialmente, o grupo beneficiário apresentava piores condições socioeconômicas, porém, com o recebimento do benefício, os grupos se igualaram financeiramente. É possível que a similaridade dos dois grupos também quanto ao estado nutricional possa ser atribuída ao recebimento do benefício, tanto devido ao incremento financeiro, quanto ao acompanhamento nutricional exigido como condicionalidade do programa.The main nutritional deficiencies during childhood, namely anemia and malnutrition, are predominantly related to socio-economic factors. Thus, as the Bolsa Família Program (BFP is the main policy to combat poverty, it is expected that it will have an impact on child nutrition. The aim was to analyze the differences in the nutritional situation of children registered with the BFP of a municipality located in Zona da Mata of Minas Gerais state. 446 children aged between 6 and 84 months were evaluated, of which 262 were non-beneficiaries and 184 were beneficiaries. Nutritional

  1. ¿Cuál es el Impacto del Programa Bolsa Família en la Educación?

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    Paul Glewwe; Ana Lúcia Kassouf

    2012-01-01

    Muchos investigadores han mostrado que el programa Bolsa Família de Brasil ha tenido un largo impacto en la reducción de pobreza y desigualdad de ingresos. Pero existe poca evidencia del impacto del programa en los resultados educativos. ¿Aumenta Bolsa Família la tasa de escolarización? ¿Reduce la tasa de abandono escolar? ¿Mejora la promoción escolar? (?)

  2. Impactos do Programa Bolsa Família federal sobre o trabalho infantil e a frequência escolar Impacts of the Bolsa Família Program on child labor and school attendance

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    Maria Cristina Cacciamali

    2010-08-01

    Full Text Available Este trabalho analisa o impacto do Programa Bolsa Família sobre a incidência de trabalho infantil e a frequência escolar das crianças de famílias pobres no Brasil em 2004, segundo a situação censitária e regional. Para o cálculo dos testes estatísticos, utilizamos um modelo probit bivariado, que estima conjuntamente as opções trabalhar e estudar dos jovens. Os resultados corroboram a eficiência do Programa Bolsa Família em elevar a frequência escolar das crianças; contudo, o Programa apresenta efeitos perversos sobre a incidência de trabalho infantil, elevando a probabilidade de sua ocorrência. Ademais, crianças de famílias pobres situa das em áreas rurais apresentam piores condições em relação àquelas de áreas urbanas, demandando ações específicas a seu favor.This paper analyses the impacts of the Bolsa Família Program on the occurrence of child labor and school attendance of children from poor families in Brazil in 2004, according to census and regional areas. A bivariate probit model was used to estimate the statistical tests. The results corroborate the efficiency of the Bolsa Família to increase the school attendance of children, however, the Program increases the likelihood of occurrence of child labor. Moreover, children of poor households in rural areas have worse conditions than those of urban areas, demanding specific actions to them.

  3. EVALUACIÓN DE LA CALIDAD MICROBIOLÓGICA DEL AGUA ENVASADA EN BOLSAS PRODUCIDA EN SINCELEJO- COLOMBIA

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    Jhon Vidal D

    2009-08-01

    Full Text Available Objetivo. Evaluar la calidad microbiológica y fisico-quimica del agua envasada en bolsas producidad en la ciudad de Sincelejo-Colombia con destino al consumo humano. Materiales y métodos. Para la estimación de organismos coliformes totales y fecales, Pseudomona aeruginosa y mesófilos en el agua envasada de 13 marcas, se utilizó el método de filtración por membrana (FxM. Resultados. El 92 % de las marcas de agua envasada en bolsa que se produce en la ciudad de Sincelejo presentaron bacterias mesófilas en su producto, mientras que en el 33% de ellas se encontraron coliformes totales. Cabe destacar que una marca presentó coliformes fecales, otra Pseudomonas aeruginosa y el reporte microbiano fue mayor en las envasadoras que poseían registro INVIMA. Conclusiones. Gran parte del agua envasada en bolsas de la ciudad de Sincelejo genera un riesgo a la salud de los consumidores, debido a la presencia de microorganismos patógenos, lo que está relacionado con inadecuados procesos de producción y a la intermitencia del suministro del agua utilizada como materia prima.

  4. Redes Neuronales y su aplicación predictiva en la Bolsa de Valores española

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    Ibarra Alfaraz, J.A.

    1999-01-01

    Full Text Available Este trabajo recoge una visión general de las redes neuronales y su tendencia en la investigación actual. Además de las aplicaciones conocidas donde las redes neuronales han demostrado su aplicabilidad se abren nuevos campos de investigación. En nuestro caso, nos centraremos en el área económica y más concretamente en la financiera. Esta metodología se aplica al caso concreto del análisis predictivo de la bolsa de valores, concretamente se utiliza el índice del mercado continuo de la bolsa española, Ibex-35, y los recientemente aparecidos índices sectoriales del Ibex: Servicios, Financiero, Utilities y Complementario. La red neuronal utilizada, Perceptron, ha sido entrenada con los datos reales procedentes de la bolsa de valores utilizando diferentes periodos de tiempo y efectuando cambios en los parámetros que condicionan la capacidad predictiva de la red. Los resultado se han contrastado con los obtenidos en otros trabajos empíricos realizados con metodologías clásicas.

  5. Programa bolsa família: a condicionante saúde realmente existe?

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    Núbia Maria Uchôa Barbosa

    2014-12-01

    Full Text Available Historicamente, o Sistema de Proteção Social do Brasil se caracteriza por apresentar uma estrutura dual de seguridade social: aos grupos mais vulneráveis socialmente e não inseridos no mercado de trabalho, destina-se a assistência social, enquanto os trabalhadores inseridos no mercado formal de trabalho vinculam-se à previdência social. As camadas pobres da sociedade brasileira, marcadas pela quase ausência de pressão social e sem posição sócio-ocupacional definida, em alguns momentos históricos, foram beneficiadas, e seu atendimento sempre foi justificado como um ato humanitário ou uma moeda política(1. Nesse aspecto, destaca-se o Programa Bolsa Família (PBF, como um programa de combate à pobreza, criado através de Medida Provisória n.o 132/2003, transformado em Lei n.o 10.836/2004 e regulamentado por Decreto n.o 5.209/2004. Foi iniciado em outubro de 2003 e constituído através da unificação de quatro programas de transferência de renda: Bolsa Escola, Auxílio-Gás, Bolsa Alimentação e Cartão Alimentação(2. A gestão do Programa Bolsa Família é descentralizada e compartilhada entre União, estados, Distrito Federal e municípios. Os entes federados trabalham em conjunto para aperfeiçoar, ampliar e fiscalizar a execução. O programa é destinado a famílias em situações de extrema pobreza e pobreza(3. Desde 2004, o PBF encontra-se vinculado ao Ministério do Desenvolvimento Social e Combate à Fome (MDS, mais especificamente à Secretaria Nacional de Renda de Cidadania (Senarc. A inserção das famílias no programa é feita mediante inscrição no Cadastro Único (CadÚnico, de gestão municipal, do qual são selecionadas, de acordo com os critérios do governo federal para o recebimento do benefício(4. Uma das questões mais polêmicas sobre os programas de combate à pobreza é o alcance de sua efetividade. Em pesquisa realizada em 2006(1, em João Pessoa-PB, junto a vinte mães beneficiárias do PBF, os

  6. Bolsa Família (Family Grant Programme: an analysis of Brazilian income transfer programme

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    Luciana Mourão

    2012-06-01

    Full Text Available Income transfer programmes are common in various countries and play an important role in combating poverty. This article presents a review of the results of the Bolsa Família (Family Grant Programme, implemented in Brazil by the government of Lula da Silva in 2004. Over the last seven years many evaluations of the programme have been conducted, allowing an overview of its results and its strong and weak points to be mapped. Five central aspects relating to the programme are discussed in article five: (1 programme access, (2 hunger fighting results, (3 programme financial impacts, (4 conditioning factors of education and health, (5 supplementary programs and social mobility. The results of scientific research were presented for each of these aspects, and any of these believed to be convergent or divergent were discussed. As a general result it was concluded that the programme has generated significant results for the country, but there are still some issues that need to be reviewed, such as conditioning factors and the integrated management of the programme.

  7. El diseño de un juego autogenerativo de títulos de bolsa

    Directory of Open Access Journals (Sweden)

    Guillermo Buenaventura Vera

    2004-01-01

    Full Text Available Contando el establecimiento de la función generadora de precios aleatorios, se desarrolla la metodología básica para la construcción de un modelo simulador de juego de bolsa que sea capaz de generar las propias variaciones de los precios de las acciones. El artículo realiza la presentación estructurada de modelo, partiendo de las bases teóricas para la elaboración de la formulación. La generación de números aleatorios distribuidos mediante la función normal estándar se construye a partir de la función uniforme generadora de números aleatorios (RAND. Las consideraciones de programación de computadores, así como una estructura básica de la misma, son tratadas enfocando tanto aplicaciones individuales del juego de simulación, como aplicaciones en red.

  8. ASSISTANCE SOCIAL POLICY IN BRAZIL AND BOLSA FAMÍLIA PROGRAM: CRITICAL POINTS

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    Haidée de Caez-Pedroso- Rodrigues

    2015-06-01

    Full Text Available This article deals with the social assistance policy in Brazil. It Is based on the critical social theory and brings as a starting point reflections on the relationship between capital accumulation and the emergence of the social question. Considering the Brazilian society and the correlation of forces between social classes, we try to present as the social rights were made in the country. Into contemporary debate, we have reviewed the main social causes, political and economic that mediated the implementation of social policies in the context of neoliberal reforms in the 1990s, when come to the fore the income transfer programs as poverty reduction strategies. When the Trabalhadores Party takes the federal government, some changes occurred mainly in the management of social welfare policy, but the liberal-conservative character of social policies remains, and in particular the actions recommended in the Bolsa Família Program. These elements point to the challenges of professionals working in the management and implementation of these social policies that are committed to the interests of the working class, both in terms of their training with regard to their professional practice.

  9. Cartografias da cópia: estudo sobre o consumo subalterno de bolsas de luxo piratas

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    Carla Gavilan Carvalho

    2012-06-01

    Full Text Available Normal 0 21 false false false PT-BR X-NONE X-NONE /* Style Definitions */ table.MsoNormalTable {mso-style-name:"Tabela normal"; mso-tstyle-rowband-size:0; mso-tstyle-colband-size:0; mso-style-noshow:yes; mso-style-priority:99; mso-style-qformat:yes; mso-style-parent:""; mso-padding-alt:0cm 5.4pt 0cm 5.4pt; mso-para-margin-top:0cm; mso-para-margin-right:0cm; mso-para-margin-bottom:10.0pt; mso-para-margin-left:0cm; line-height:115%; mso-pagination:widow-orphan; font-size:11.0pt; font-family:"Calibri","sans-serif"; mso-ascii-font-family:Calibri; mso-ascii-theme-font:minor-latin; mso-fareast-font-family:"Times New Roman"; mso-fareast-theme-font:minor-fareast; mso-hansi-font-family:Calibri; mso-hansi-theme-font:minor-latin;} Este artigo pretende refletir sobre o consumo de bolsas de marcas luxuosas como prática social com implicações culturais e suas relações produzidas, a partir da perspectiva de que o consumo é capaz de definir modos de ser, trabalhar e atuar enquanto cidadão. Avalia também como tal prática tem resignificado o consumo tradicional, assim como a definição de luxo na sociedade contemporânea.

  10. Una aproximación a la predicción del valor de acciones en la bolsa de valores aplicando técnicas de Data Mining

    OpenAIRE

    Espinosa Muñoz, Javier Isaac

    2015-01-01

    La predicción del valor de las acciones en la bolsa de valores ha sido un tema importante en el campo de inversiones, que por varios años ha atraído tanto a académicos como a inversionistas. Esto supone que la información disponible en el pasado de la compañía que cotiza en bolsa tiene alguna implicación en el futuro del valor de la misma. Este trabajo está enfocado en ayudar a un persona u organismo que decida invertir en la bolsa de valores a través de gestión de compra o venta de acciones ...

  11. [Poverty and social policy: the implementation of complementary programs for the Bolsa Família Program].

    Science.gov (United States)

    Santos, Cláudia Roberta Bocca; Magalhães, Rosana

    2012-05-01

    The Bolsa Família Program involves the transfer of income and the implementation of complementary programs to foster human capital development and empower the beneficiaries. To analyze the implementation of complementary programs in Manguinhos, Rio de Janeiro, a review of documents and secondary data was conducted, focus groups of beneficiaries studied and semi-structured interviews were staged with governmental, nongovernmental stakeholders and beneficiaries. The design, coverage and evaluation of the complementary programs have been weak, and beneficiaries were even unaware of vocational training courses. The program administrators acknowledged the failings and the fact that the courses offered by Próximo Passo are not adapted to local demand, even though they were conceived as a vocational training strategy aimed at creating construction jobs in the Growth Acceleration Program and the tourist industry in the city. Considering that the social inclusion perspective is linked to access to public policies, the supply and follow-up of these activities by government agencies and civil society organizations are essential for the effectiveness of the fight against poverty and hunger, aimed at contributing to the so-called "exit routes" from the Bolsa Família Program.

  12. Programa Bolsa-Familia: qualidade da dieta de populacao adulta do municipio de Curitiba, PR

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    Flavia Emilia Leite de Lima

    2013-03-01

    Full Text Available Este estudo avaliou a qualidade da dieta da população beneficiária do Programa Bolsa-Família, em Curitiba, PR. Estudo transversal, de base populacional, realizado no período de julho de 2006 a julho de 2007. Foram entrevistados 747 beneficiários, a partir dos 19 anos de idade, de ambos os sexos. Para avaliação da qualidade da dieta foi aplicado recordatório de 24 horas, e o Índice de Qualidade da Dieta (IQD foi utilizado como parâmetro para classificação do grupo em níveis de consumo. Estatística descritiva foi utilizada para descrever a qualidade da dieta da população. Para a comparação de médias do índice segundo as variáveis socioeconômicas foram realizados o teste t de Wald e a análise de variância ANOVA, considerando-se um nível de significância de 5%. A amostra foi constituída por 91,4% de mulheres e 8,6 % de homens. A média de idade da população foi de 36,4 ± 13,3 anos, com cerca de 75 % possuindo o ensino fundamental incompleto. A média do IQD foi de 51 pontos, o que caracteriza uma dieta que precisa de ajustes. A população possui uma dieta monótona, com um consumo adequado de leguminosas, porém baixo para frutas, verduras e produtos lácteos. Na comparação entre as categorias de qualidade da dieta dos indivíduos, todos os componentes, com exceção do sódio, apresentaram medianas de pontuação estatisticamente diferentes (p < 0,01. Estudos que avaliem a qualidade da dieta são fundamentais para subsidiar a implantação de programas de educação alimentar direcionados para o cerne do problema nas populações estudadas.

  13. Pobreza e Política Social: a implementação de programas complementares do Programa Bolsa Família Poverty and Social Policy: the implementation of complementary programs for the Bolsa Família Program

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    Cláudia Roberta Bocca Santos

    2012-05-01

    Full Text Available O Programa Bolsa Família articula a transferência de renda à implementação de programas complementares, a fim de promover o desenvolvimento de capital humano e a autonomização dos beneficiários. Para analisar a implementação dos programas complementares em Manguinhos, Rio de Janeiro, realizamos consultas documentais; grupos focais com beneficiários; entrevistas semiestruturadas com atores governamentais, não-governamentais e beneficiários, além da coleta de dados secundários. O desenho, a cobertura e a avaliação dos programas complementares mostraram-se frágeis. Os beneficiários desconheciam cursos de qualificação profissional. Os gestores reconheceram a debilidade das ações e destacaram que os cursos do Próximo Passo não se adéquam à demanda local, ainda que pensados como estratégia de capacitação voltada às obras do Programa de Aceleração do Crescimento e à vocação turística da cidade do Rio de Janeiro. Considerando que a perspectiva de inclusão social está atrelada ao acesso às políticas públicas, a oferta e o acompanhamento destas ações pelas esferas governamentais e organizações civis constituem um eixo crucial para o combate à pobreza e à fome, contribuindo para as chamadas "portas de saída" do Programa Bolsa Família.The Bolsa Família Program involves the transfer of income and the implementation of complementary programs to foster human capital development and empower the beneficiaries. To analyze the implementation of complementary programs in Manguinhos, Rio de Janeiro, a review of documents and secondary data was conducted, focus groups of beneficiaries studied and semi-structured interviews were staged with governmental, nongovernmental stakeholders and beneficiaries. The design, coverage and evaluation of the complementary programs have been weak, and beneficiaries were even unaware of vocational training courses. The program administrators acknowledged the failings and the fact that

  14. Efeito do Programa Bolsa Família sobre a oferta de trabalho das mães The impact of the Bolsa Família Program on the labor supply of working mothers

    OpenAIRE

    Priscilla Albuquerque Tavares

    2010-01-01

    Este artigo investiga a existência de um possível incentivo adverso à oferta de trabalho (participação no mercado e jornada) das mães beneficiadas pelo Programa Bolsa Família. Utiliza-se o procedimento de propensity score matching para encontrar mães não atendidas pelo programa comparáveis às mães atendidas, a partir de três grupos de controle. Os resultados apontam a existência de um efeito-renda associado ao valor do benefício, uma vez que quanto maior a transferência recebida, menor o enga...

  15. Efeito do Programa Bolsa Família sobre a oferta de trabalho das mães The impact of the Bolsa Família Program on the labor supply of working mothers

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    Priscilla Albuquerque Tavares

    2010-12-01

    Full Text Available Este artigo investiga a existência de um possível incentivo adverso à oferta de trabalho (participação no mercado e jornada das mães beneficiadas pelo Programa Bolsa Família. Utiliza-se o procedimento de propensity score matching para encontrar mães não atendidas pelo programa comparáveis às mães atendidas, a partir de três grupos de controle. Os resultados apontam a existência de um efeito-renda associado ao valor do benefício, uma vez que quanto maior a transferência recebida, menor o engajamento da mãe no mercado de trabalho. Entretanto, o efeito líquido de ser beneficiário do programa é positivo, indicando a existência de um efeito-substituição, provavelmente decorrente da redução da oferta de trabalho dos filhos, da maior disponibilidade de tempo das mães para trabalhar ou mesmo do estigma em participar do programa.This paper investigates the existence of a possible adverse incentive on the labor supply and weekly working hours of beneficiary mothers of the Bolsa Família Program. Three control groups are analyzed using propensity-score matching to compare non-beneficiary mothers to beneficiary mothers. The results show that there is a wealth effect related to the value of the benefits, given that the larger the benefit, the less active beneficiary mothers are in the labor market. Nonetheless, the net effect is positive, showing that there is a substitution effect due to a reduction in the children´s labor supply, a rise in the mother's available time, as well as decreasing the stigma.

  16. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

    This pamphlet describes how reactors work; discusses reactor design; describes research, teaching, and materials testing reactors; production reactors; reactors for electric power generation; reactors for supply heat; reactors for propulsion; reactors for space; reactor safety; and reactors of tomorrow. The appendix discusses characteristics of U.S. civilian power reactor concepts and lists some of the U.S. reactor power projects, with location, type, capacity, owner, and startup date.

  17. O Impacto das Regras do Programa Bolsa Família Sobre a Fecundidade das Beneficiárias

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    Luis Antonio Winck Cechin

    2015-09-01

    Full Text Available Este trabalho investiga um possível incentivo do Programa Bolsa Família ao aumento da fecundidade de suas beneficiárias em decorrência de suas regras, dado que a quantidade de recursos transferidos depende do número de filhos da família. O diferencial deste estudo reside na análise desse impacto em um maior período de exposição das beneficiárias aos efeitos do PBF. Aplica-se o algoritmo de seleção de covariadas proposto por Imbens (2014 e o método de Propensity Score Matching. Os resultados apontaram que o PBF gera pequeno incentivo à geração do segundo filho, sendo que as regiões Centro-Oeste e Nordeste apresentaram os maiores valores de impacto.

  18. Programas de transferência de renda no Brasil: um estudo multidimensional da implementação do Bolsa Escola, Bolsa Alimentação e Cartão Alimentação Cash transfer programs in Brazil: a multidimensional study of Bolsa Escola, Bolsa Alimentação and Cartão Alimentação Program implementation

    Directory of Open Access Journals (Sweden)

    Leonor Maria Pacheco Santos

    2011-03-01

    Full Text Available Foi analisada a implementação dos programas de transferência de renda (PTR Bolsa Escola (PNBE, Bolsa Alimentação (PBA e Cartão Alimentação (PCA, coletando-se informações sobre "estrutura" normativa, infraestrutura, "processos" de implementação e "resultados" relativos a benefícios concedidos e impactos. A argumentação central do trabalho considerou que a adoção de PTR no Brasil representou um diferencial com relação às formas de intervenção antes adotadas especialmente no campo da promoção do direito humano à alimentação adequada. Verificou-se que lacunas na "estrutura" normativa podem dificultar a implantação; assim ocorreu com a opção centralizadora no PNBE, a indefinição de atribuições estaduais no PBA e a ausência de normatização clara no PCA. Ocorreram restrições no processo de implementação, resultando numa sinergia de fatores impeditivos ao acesso de parcelas dos mais excluídos. Exigências de documentos civis, comprovante de residência e cobrança de notas fiscais de compra de alimentos foram mecanismos de reforço a desigualdades existentes. Assim, este estudo evidencia que o desafio está posto na direção de articular os PTR com os demais programas que promovem acesso aos direitos sociais, avançando na intersetorialidade como forma de garantir aos mais excluídos o ingresso ao mundo dos direitos.The implementation of cash transfer (CT programs Bolsa Escola (PNBE, Bolsa Alimentação (PBA and Cartão Alimentação (PCA was analyzed, collecting data about the legislative "structure" and infrastructure, the implementation "process" and the "results", as far as benefits granted and impacts. This study considers that the adoption of CT policies in Brazil implies in an improvement when compared to previous interventions, especially as regard the promotion of human right to adequate food. It was observed that inadequate legislation can hinder program implementation; so it happened with the

  19. A CRISE DA BOLSA DE VALORES CHINESA: UMA ANÁLISE DOS EFEITOS SOBRE MERCADOS ACIONÁRIOS INTERNACIONAIS

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    Antônio André Cunha Callado

    2014-04-01

    Full Text Available Estudos de eventos têm sido amplamente utilizados para investigar a Hipótese dos Mercados Eficientes tem sido amplamente investigada ao longo das últimas duas décadas. O artigo tem como objetivo investigar a reação de índices de diversos mercados acionários ao evento na Bolsa de Valores da China em fevereiro de 2007. Para a realização do estudo foram utilizados 12 índices pertencentes a diversos mercados acionários (Alemanha, Argentina, Austrália, Brasil, Estados Unidos, França, Hong Kong, Índia, Indonésia, Inglaterra, Japão e México. Os procedimentos referentes ao delineamento do estudo consideraram a definição da janela de tempo, bem como os procedimentos inerentes a um estudo de evento para realçar alterações no comportamento dos retornos dos índices de mercado e investigar a ocorrência de retornos anormais acumulados. Os resultados obtidos demonstram evidências inerentes à reação de alguns dos mercados acionários investigados em relação ao evento ocorrido na Bolsa chinesa. A queda dos Índices de Performance de Sharpe observada em todos os índices de mercado investigados revelam evidências que corroboram o impacto significativo e sistemático decorrente da queda ocorrida no mercado acionário chinês. Este resultado sugere que a importância relativa da China no cenário internacional dos mercados de capitais não deve ser subestimada.

  20. Intersetorialidade, convergência e sustentabilidade: desafios do programa Bolsa Família em Manguinhos, RJ Intersectoral, convergent and sustainable actions: the challenges of the "Bolsa Família" program in Manguinhos shantytown in Rio de Janeiro

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    Rosana Magalhães

    2011-11-01

    Full Text Available Alguns estudos têm revelado o impacto de programas de transferência condicionada de renda na melhoria das condições de vida e no acesso a serviços básicos de saúde e educação em diferentes países. No entanto, persistem lacunas no que se refere à avaliação dos benefícios de tais intervenções entre os grupos que apresentam maiores dificuldades em acessar serviços públicos ou dos avanços na qualidade do ensino e desempenho escolar. Além disso, existem poucas evidências sobre a adequação das ações aos respectivos contextos de implementação, níveis de adesão e cooperação, local e estratégias adotadas para a integração com as demais políticas de proteção social. O artigo discute os resultados da pesquisa avaliativa sobre a implementação do programa de transferência condicionada de renda Bolsa Família em Manguinhos (RJ realizada entre os anos de 2007 e 2008. Foram realizadas entrevistas com gestores das secretarias municipais de assistência social, saúde e educação e agentes implementadores locais. Em Manguinhos, a sustentabilidade das ações voltadas à redução da pobreza e promoção da saúde envolve o fortalecimento de canais de interlocução entre níveis de governo, gestores públicos e associações civis, reconhecimento da complexidade das demandas sociais locais e pactuação de uma agenda intersetorial.Some studies have revealed the impact of the family welfare allowance based on the fulfillment of certain conditions on improving living conditions and access to health and education services in different countries. However, gaps persist relating to the evaluation of the benefits of such programs among the groups that have greater difficulty in gaining access to public services or advances in the quality of education and school performance. Moreover, there is limited evidence of adequacy of the program to the respective contexts of implementation, levels of adhesion and local cooperation and

  1. Discutindo o papel do Programa Bolsa Família na decisão das eleições presidenciais brasileiras de 2006

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    Rosa Maria Marques

    2009-03-01

    Full Text Available This paper investigates the relationship between the impact of Bolsa Família Program in the Brazilian population and the result of the presidential elections of 2006. The database involves municipal information provided by MDS, IBGE and TSE. To control the experiment, the eventual influences of other variables in the determination of this relationship had been studied. All those variables come from specific characteristics of the cities, such as: city with predominant urban or not urban population; size of the city population; among others. The results state that the Bolsa Família was, in fact, a very important factor in the determination of the votes in Lula. It was, in itself, responsible by 45% of the total votes in Lula.

  2. Programa Bolsa Família: uma análise do programa de transferência de renda brasileiro Bolsa Família (Family Grant Programme: an analysis of Brazilian income transfer programme Le programme Bolsa Família (Bourse familiale : analyse du programme brésilien de transfert conditionnel de revenus El programa Bolsa Família: un análisis del programa brasileño de transferencia de ingresos

    Directory of Open Access Journals (Sweden)

    Luciana Mourão

    2012-02-01

    Full Text Available Income transfer programmes are common in various countries and play an important role in combating poverty. This article presents a review of the results of the Bolsa Família (Family Grant Programme, implemented in Brazil by the government of Lula da Silva in 2004. Over the last seven years many evaluations of the programme have been conducted, allowing an overview of its results and its strong and weak points to be mapped. Five central aspects relating to the programme are discussed in article five: (1 programme access, (2 hunger fighting results, (3 programme financial impacts, (4 conditioning factors of education and health, (5 supplementary programs and social mobility. The results of scientific research were presented for each of these aspects, and any of these believed to be convergent or divergent were discussed. As a general result it was concluded that the programme has generated significant results for the country, but there are still some issues that need to be reviewed, such as conditioning factors and the integrated management of the programme.Les programmes de transfert de revenus sont courants dans plusieurs pays et jouent un rôle important dans la lutte contre la pauvreté. Cet article présente un examen des résultats du programme Bolsa Família (Bourse familiale entrepris au Brésil par le gouvernement de Lula da Silva en 2004. Au cours des sept dernières années, de nombreuses évaluations du programme ont été réalisées, ce qui permet d'avoir un aperçu de ses résultats et une vue d'ensemble de ses points forts et de ses points faibles. Cinq aspects clés de ce programme sont abordés dans cet article : (1 l'accès au programme, (2 les résultats en matière de lutte contre la faim, (3 les répercussions financières du programme, (4 les facteurs conditionnels de l'éducation et de la santé, (5 les programmes complémentaires et la mobilité sociale. Des résultats issus de la recherche scientifique ont été pr

  3. Mulher e família no Programa Bolsa-Escola: maternidades veiculadas e instituídas pelos anúncios televisivos Woman and family at the Bolsa-Escola Program: maternities propagated and instituted through TV advertisements

    Directory of Open Access Journals (Sweden)

    Carin Klein

    2007-12-01

    Full Text Available Este artigo problematiza alguns processos de produção e veiculação de representações de maternidade, tomando como referência o Programa Nacional Bolsa-Escola, e insere-se no campo da teorização cultural, principalmente na perspectiva dos Estudos Culturais e dos Estudos Feministas, nas vertentes que têm proposto uma aproximação crítica com a análise pós-estruturalista. Para a operacionalização do trabalho, selecionei um conjunto de anúncios televisivos que divulgaram o Programa à população no primeiro ano de sua implantação. Exploro os anúncios com o intuito de analisar os diferentes modos de representar e significar a maternidade. Discuto como se organiza e divulga, no âmbito do Programa, um conjunto de ensinamentos e propostas a serem desenvolvidas, principalmente na família, a fim de buscar (recolocar, sobretudo, as mulheres-mães e a educação das crianças no centro desses debates.This work discusses and questions some processes of production and propagation of maternity representations, having the National Bolsa-Escola Program as its starting point, and localized in the field of cultural theory, mainly from the perspectives of both Cultural Studies and Feminist Studies, with a critical approximation to the post-structuralist analysis. In order to carry out the work, I have selected a series of television advertisements used to publicize the Program in its first year of implementation. I have explored these advertisements in order to analyze the different ways through which maternity has been represented and meant. I have discussed how a set of teachings and proposals was publicized in the Program so as to be mainly developed by the families, thus relocating women/mothers and children’s education into the center of those debates.

  4. Main food sources of carotenoids, according to the purpose and degree of processing, for beneficiaries of the 'Bolsa Família' in Brazil

    OpenAIRE

    Alan Giovanini de Oliveira Sartori; Marina Vieira da Silva

    2014-01-01

    The intake of carotenoids is associated with antioxidant properties and some of these substances have activity of pro-vitamin A. This study aimed to estimate the intake of carotenoids (average values) by the Brazilian population focusing on beneficiaries of the 'Bolsa Família' Program and identify the dietary sources, according to the purpose and degree of processing and the inclusion of food additives. The database used is the personal food consumption module of the Household Budget Survey o...

  5. Avaliação de Impacto das condicionalidades de educação do Programa Bolsa Família (2005 e 2009

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    Ernesto Friedrich de Lima Amaral

    2013-09-01

    Full Text Available Dans cet article, on examine les impacts des conditionnalités de l'éducation dans le Programme Bolsa Família sur l'absentéisme scolaire d'enfants qui bénéficient de ce programme. L'hypothèse principale est que l'enfant qui habite dans un foyer recevant cette aide a moins de chances d'abandonner l'école. On se sert de données de l'Étude de l'impact du Programme Bolsa Família (AIBF de 2005 à 2009 du Ministère du Développement Social et de la Lutte contre la Faim (MDS. Des modèles logistiques ont estimé les chances d'abandon scolaire de 2005 à 2009, à partir de trois niveaux de revenu domiciliaire par habitant, compte tenu des caractéristiques du foyer, de la mère et de l'enfant. Les enfants habitant dans des foyers bénéficiaires du Programme Bolsa Família ont révélé une nette réduction du taux d'abandon scolaire en 2005. Les données pour 2009 n'ont pas été statistiquement significatives, bien que montrant une diminution de l'abandon scolaire comme résultat de l'aide reçue du Bolsa Família.

  6. Uma análise do efeito do programa bolsa família sobre o desempenho médio das escolas brasileiras

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    Pedro Cavalcanti Camargo

    2014-12-01

    Full Text Available O objetivo deste artigo é avaliar o efeito de um aumento na proporção de alunos beneficiados pelo Programa Bolsa Família nas escolas sobre o desempenho médio das mesmas. Utilizando dados do Censo Escolar de 2008, da pesquisa de Acompanhamento da Freqüência Escolar dos beneficiários do Programa Bolsa Família de 2008 e da Prova Brasil 2009, este artigo procura relacionar o desempenho médio por escola dos alunos de 4ª série observado em 2009 com a proporção de alunos participantes do programa Bolsa Família em 2008. Os resultados encontrados sugerem que um aumento na proporção de alunos beneficiados reduz, em média, a taxa de abandono. Entretanto, as evidências para a taxa de aprovação e exames de proficiência não foram estatisticamente robustas.

  7. Bolsa família: projeto social ou marketing político? Family grant: social policy or political marketing?

    Directory of Open Access Journals (Sweden)

    Paulo Gabriel Martins de Moura

    2007-06-01

    Full Text Available Esse ensaio, à luz da análise política, critica o Programa Bolsa Família, implementado pelo governo Lula, a partir da metodologia de ongoing analysis conjuntural, originada na ciência política norte-americana. Busca estabelecer paralelo dessas análises com as críticas de especialistas ao Bolsa Família, veiculadas na imprensa, que sugerem a ausência de um referencial conceitual, amparado no conhecimento acumulado na área (ou sua não-aplicação prática, a nortear as políticas sociais do governo Lula. Baseando-se em fontes secundárias sobre dados oficiais e em depoimentos de especialistas, a análise identifica uma aparente 'esquizofrenia' nos referenciais 'filosóficos' que norteiam as políticas sociais do governo, sugerindo que a solução escolhida foi uma resposta conjuntural a uma demanda de marketing governamental, e não orientada por uma deliberada política pública de governo pré-concebida como tal que, se existiu, não transparece nas ações governamentais aplicadas.This essay, a political analysis, criticizes the Family Grant Program, implemented by the Lula government of 2003-2005. It is based on the ongoing analysis methodology originated in U.S. political science. It seeks to establish a parallel of these analyses with criticisms of the Family Grant program presented in the media and made by specialists. They focus on the absence of a conceptual reference for the program (or its practical non-application, supported by accumulated knowledge in the field, that would guide the social policies of the Lula government. Based on secondary sources about official data and on statements from specialists, the analysis identifies an apparent 'schizophrenia' in the 'philosophical' references that orient the government's social policies, suggesting that the solution chosen was a situational response to a demand for government marketing and not oriented to a deliberate public policy pre-conceived as such, which, if it exists, is

  8. Velocidad de ajuste del precio de las acciones por sector económico en la Bolsa Mexicana de Valores

    Directory of Open Access Journals (Sweden)

    Verónica Patricia Rodríguez Vázquez

    2009-01-01

    Full Text Available Este estudio analiza la velocidad de ajuste del precio de las acciones de la Bolsa Mexicana de Valores de enero de 1998 a diciembre de 2007; para ello, se agruparon las acciones por sectores económicos y se compararon con el Índice de Precios y Cotizaciones (IPC. Asimismo, se clasificó a los sectores económicos en fuertes y débiles, dependiendo del porcentaje de influencia dentro de la muestra del IPC. Entre los sectores fuertes se ubicó a comunicaciones y transportes, comercio, construcción e industria extractiva; mientras que en los débiles a transformación, servicios y varios. El modelo de regresión utilizado fue el propuesto por Marshall y Walker (2002, con el que se buscó comprobar que los sectores fuertes ajustaban más rápidamente sus precios que los sectores débiles con respecto a la rentabilidad del mercado. Se encontró que existe evidencia de que los retornos de los sectores fuertes se adelantan a los retornos de los sectores débiles, principalmente porque los primeros ajustan más rápidamente sus precios a los movimientos del mercado.

  9. Seguranca alimentar, renda e Programa Bolsa Familia: estudo de coorte em municipios do interior da Paraiba, Brasil, 2005-2011

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    Caroline Sousa Cabral

    2014-02-01

    Full Text Available Este trabalho tem por objetivo avaliar o impacto do Programa Bolsa Família na superação da Insegurança Alimentar. Realizou-se um estudo de coorte em 2005 e 2011, em amostra de famílias residentes em São José dos Ramos e Nova Floresta, Paraíba, Brasil. Em 2005 foram avaliados 609 domicílios e em 2011 foram encontradas e entrevistadas 406 famílias. Houve aumento da segurança alimentar/insegurança alimentar leve e melhoria nos indicadores socioeconômicos. Percebeu-se uma relação significativa entre a elevação da renda e a melhoria dos níveis de Insegurança Alimentar. O programa impacta positivamente no aumento da renda, propiciando melhorias dos níveis de segurança alimentar/insegurança alimentar leve. Percebeu-se que outras variáveis socioeconômicas podem estar contribuindo na melhoria deste perfil. Diante disso, no combate à insegurança alimentar e nutricional, são necessárias outras políticas e programas que ajam nos demais determinantes.

  10. Programa Bolsa-Família: qualidade da dieta de população adulta do município de Curitiba, PR Bolsa-Família Program: Diet quality of adult population in Curitiba, Paraná

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    Flávia Emília Leite de Lima

    2013-03-01

    Full Text Available Este estudo avaliou a qualidade da dieta da população beneficiária do Programa Bolsa-Família, em Curitiba, PR. Estudo transversal, de base populacional, realizado no período de julho de 2006 a julho de 2007. Foram entrevistados 747 beneficiários, a partir dos 19 anos de idade, de ambos os sexos. Para avaliação da qualidade da dieta foi aplicado recordatório de 24 horas, e o Índice de Qualidade da Dieta (IQD foi utilizado como parâmetro para classificação do grupo em níveis de consumo. Estatística descritiva foi utilizada para descrever a qualidade da dieta da população. Para a comparação de médias do índice segundo as variáveis socioeconômicas foram realizados o teste t de Wald e a análise de variância ANOVA, considerando-se um nível de significância de 5%. A amostra foi constituída por 91,4% de mulheres e 8,6 % de homens. A média de idade da população foi de 36,4 ± 13,3 anos, com cerca de 75 % possuindo o ensino fundamental incompleto. A média do IQD foi de 51 pontos, o que caracteriza uma dieta que precisa de ajustes. A população possui uma dieta monótona, com um consumo adequado de leguminosas, porém baixo para frutas, verduras e produtos lácteos. Na comparação entre as categorias de qualidade da dieta dos indivíduos, todos os componentes, com exceção do sódio, apresentaram medianas de pontuação estatisticamente diferentes (p This study evaluated the quality of diet of the population receiving the Bolsa Familia Program in Curitiba, state of Parana, Brazil. It was a population-based cross-sectional study, conducted from July 2006 to July 2007. 747 beneficiaries were interviewed from 19 years of age, of both genders. A 24 hour-recall was implemented in order to assess the quality of the diet and the Healthy Eating Index (HEI was used as a parameter for the classification of the group in consumption levels. Descriptive statistics were used to describe the diet quality of the studied population. Wald

  11. Perfil dos pesquisadores com bolsa de produtividade em pesquisa do CNPq da área de saúde coletiva

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    Rita Barradas Barata

    2003-12-01

    Full Text Available O artigo analisa, com base nas informações do currículo Lattes, o perfil dos pesquisadores com bolsa de produtividade em pesquisa do CNPq na área de Saúde Coletiva. A análise levou em conta a formação graduada e pós-graduada, área de atuação, produção e divulgação científica. As comparações são feitas entre as classes de pesquisadores e com dados do diretório de grupos de pesquisa. A maioria dos pesquisadores (70% são formados em Ciências da Saúde, principalmente em Medicina, ou em Ciências Humanas (18%, principalmente Sociologia. Sessenta por cento fizeram mestrado e doutorado em Saúde Coletiva, mas há entre 20 e 30% de pesquisadores, dependendo da classe, sem formação específica na área. A maioria atua em Epidemiologia. A produção científica, expressa em produtos bibliográficos, varia de 10,56 produtos/ano de obtenção do doutorado para os pesquisadores 2C a 6,60 produtos/ano para os pesquisadores 1A. Para artigos completos publicados em periódicos os valores são 3,56 e 2,87, respectivamente. A produção é divulgada principalmente em periódicos A internacional e, A e B nacional. Os periódicos que concentram a publicação são Cadernos de Saúde Pública e Revista de Saúde Pública.

  12. El efecto de la volatilidad del peso mexicano en los rendimientos y riesgo de la Bolsa Mexicana de Valores

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    Raúl de Jesús Gutiérrez

    2013-01-01

    Full Text Available El efecto de las colas pesadas originado por los eventos extremos y los diferentes niveles de asimetría asociados a la alta volatilidad en aglomeraciones en los mercados financieros de economías emergentes requieren de modelos más sofisticados para su modelación. El objetivo de esta investigación es aplicar la teoría de valores extremos (TVE para cuantificar el riesgo de la cola de los rendimientos diarios de la Bolsa Mexicana de Valores bajo la agregación del riesgo del tipo de cambio durante el periodo de enero de 1971 a diciembre de 2010. Este análisis sugiere el uso de la distribución de valor extremo generalizada y la técnica de bloques máximos para explicar el comportamiento asintótico de los rendimientos extremos. Los resultados empíricos muestran el potencial de la medida VaR basada en la TVE para capturar las propiedades de colas pesadas en los rendimientos de los mercados accionarios altamente volátiles a diferencia de los modelos VaR convencionales. Además, la evidencia empírica demuestra que los inversionistas internacionales con posiciones financieras largas están más propensos a experimentar pérdidas más grandes que los que toman posiciones cortas en el mercado accionario mexicano durante periodos de crisis financieras y depreciaciones de la moneda local.

  13. Evaluación de tres tipos de empaque (bolsas de polietileno para almacenamiento de guayaba manzana (Psidium guajava var., Klom sali

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    Luis Román Ardila Núñez

    2011-05-01

    Full Text Available La Universidad Nacional de Colombia, a través del Departamento de Ingeniería Agrícola de Santafé de Bogotá, ha venido adelantando investigación sobre manejo postcosecha de productos hortofrutícolas, con miras a minimizar las pérdidas de estos productos y a conservar su calidad. En el presente artículo se muestran los resultados obtenidos de comportamiento del fruto guayaba manzana (Psidium guajava varoKlom Sali, al ser almacenado en frío con bolsas de polietileno de baja densidad de tres tipos: abierto, perforado y cerrado, a una temperatura de 10ºC y humedad relativa de 95 %. Se compararon los resultados durante los días del almacenamiento, tomando como base los índices de madurez del fruto, tales como la pérdida de peso, la intensidad respiratoria, la firmeza, el contenido deácidos, el contenido de sólidos solubles y el pH. Además, se tomaron datos del almacenamiento de este fruto en bolsas abiertas del mismo tipo, en condiciones ambiente (temperatura 20,1 ºC y humedad relativa de 50,3 %, lo cual se utilizó como testigo. De esta investigación se concluyó que la mejor condición de almacenamiento es en frío con bolsa cerrada, pues el producto conserva mejor su calidad que en los otros dos tipos de empaques evaluados.

  14. Transferencia de ingresos dirigida a los más pobres: la experiencia brasileña con el Programa Bolsa-Familia

    OpenAIRE

    Cecília Paiva

    2010-01-01

    En Brasil se implementó, a partir de los años noventa, un nuevo modelo de protección social acorde con el nuevo orden económico mundial, lo que significó una ruptura con el proceso de constitución de un sistema de protección social basado en los derechos a la salud y la universalidad. En este contexto predominan las políticas diseñadas para combatir la pobreza a través de programas de transferencia no contributiva de ingresos. El artículo examina el programa Bolsa-Familia, el principal progra...

  15. Capacidades Estatais no Programa Bolsa Família: O Desafio de Consolidação do Sistema Único de Assistência Social

    OpenAIRE

    Diogo R. Coutinho

    2013-01-01

    Por meio de uma abordagem centrada na análise de arranjos político-institucionais criados para implementar políticas de desenvolvimento no contexto democrático pós-1988, este trabalho utiliza as categorias de capacidades técnico-administrativas (associadas à dimensão de efetividade) e capacidades políticas (associadas à dimensão de legitimidade) para descrever o Programa Bolsa Família (PBF) em sua interação com o campo da assistência social. Discute como se relacionam tais capacidades no plan...

  16. A voz do beneficiário: uma análise da eficácia do Programa Bolsa Família

    OpenAIRE

    Michelle Costa Marques dos Santos; Antonio Gouveia Junior; Paulo Roberto Marques de Oliveira; Daniel Reis Armond de Melo; Waldemar Antonio da Rocha de Souza

    2014-01-01

    Esta pesquisa analisa a eficácia do Programa Bolsa Família (PBF), pela perspectiva dos beneficiários deste programa de transferência de renda. Para tanto, foi desenvolvida uma pesquisa quali-quantitativa com 50 beneficiários e seu resultado analisado pela metodologia do discurso do sujeito coletivo (DSC), desenvolvida por Lefèvre e Lefèvre (2003). Da análise dos discursos, foi constatado que o beneficiário percebe como resultado de sua inserção no PBF o aumento da renda e a melhoria da qualid...

  17. Evaluación de tres tipos de empaque (bolsas de polietileno) para almacenamiento de guayaba manzana (psidium guajava var., klom sali)

    OpenAIRE

    Luis Román Ardila Núñez; Alfonso Parra Coronado

    2011-01-01

    La Universidad Nacional de Colombia, a través del Departamento de Ingeniería Agrícola de Santafé de Bogotá, ha venido adelantando investigación sobre manejo postcosecha de productos hortofrutícolas, con miras a minimizar las pérdidas de estos productos y a conservar su calidad. En el presente artículo se muestran los resultados obtenidos de comportamiento del fruto guayaba manzana (Psidium guajava varoKlom Sali), al ser almacenado en frío con bolsas de polietileno de baja densidad de tres tip...

  18. Las redes de conocimiento: caso una empresa dedicada a la elaboración de bolsas de polietileno localizada en la ciudad de Puebla

    OpenAIRE

    Evaristo JA Anzaldo Ortiz,; MA Monserrat Vera Muñoz

    2013-01-01

    Este trabajo presenta un análisis de las relaciones que existen entre la empresa y diferentes actores, como son los clientes, proveedores, agrupaciones, gobierno e instituciones educativas de nivel superior, entre otros; Estas relaciones constituyen las llamadas redes de conocimiento o redes sociales. Por lo que el objetivo de este trabajo es indagar el papel que han desempeñado las redes sociales respecto a la transferencia de conocimientos en una empresa dedicada a la elaboración de bolsas ...

  19. N Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The last of Hanfordqaodmasdkwaspemas7ajkqlsmdqpakldnzsdflss nine plutonium production reactors to be built was the N Reactor.This reactor was called a dual purpose...

  20. Determinantes da gestão do Programa Bolsa Família: análise do índice de gestão descentralizada em Minas Gerais Municipal performance in the public administration of Programa Bolsa Família: analysis of the decentralized management index in Minas Gerais

    Directory of Open Access Journals (Sweden)

    Doraliza Auxiliadora Abranches Monteiro

    2009-06-01

    Full Text Available Este trabalho analisa os fatores que determinam a gestão do Programa Bolsa Família em Minas Gerais. O trabalho toma como referência o Índice de Gestão Descentralizada do Programa Bolsa Família (IGD, criado pelo Governo Federal no intuito de regulamentar, normatizar e incentivar a qualidade de gestão do programa, em nível municipal. Como incentivo direto, destaca-se o fato de a disponibilidade de recursos estar associada ao escore de pontuação do município, nesse índice. / Foram utilizadas diversas abordagens teóricas, baseando-se na gestão e descentralização de políticas públicas para a contextualização do Programa Bolsa Família na região de estudo. O trabalho segue uma abordagem quanti-quali, em que foram utilizadas, como técnicas de investigação, análise de informativos do Programa Bolsa Família e estatisticamente realizou-se Análise Exploratória dos Dados (AED e Testes de Correlação de Pearson. Dentre os principais resultados destacam-se a existência, em Minas Gerais, de municípios com baixos escores nos itens que compõem o IGD, demonstrando deficiências em diversos aspectos, tais como informações do CadÚnico e gestão das condicionalidades "saúde" e "educação". Esses fatores expõem a fragilidade da gestão pública social municipal e comprometem a eficiência do programa no Estado. Outros fatores, como o aumento da população e das famílias beneficiadas, também influenciam de forma negativa a gestão do programa, pois municípios maiores apresentaram menores escores de IGD.This study analyzes the factors that determine the management of Programa Bolsa Família (Family Grant Program in the State of Minas Gerais. The work uses as reference the Índice de Gestão Decentralizada (IGD - Decentralized Management Index of Programa Bolsa Família, created by the Federal Government in order to regulate, standardize and motivate both efficiency and quality in the program's management in the municipal level

  1. Programa Bolsa Família: uma nova modalidade de biopolítica Family Allowance Program: a new type of biopolitics

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    Rémi Fernand Lavergne

    2012-06-01

    Full Text Available O propósito deste artigo é mostrar como o Programa Bolsa Família (PBF remete a uma forma de biopolítica nos termos evocados por Michel Foucault e inscreve-se numa perspectiva de normalização, funcionando pela norma e pela regulamentação. Busca também evidenciar como o Serviço Social e a educação "por toda a vida" têm um importante papel nos processos de subjetivação e de produção de subjetividades com vistas a incidir sobre a conduta das populações indigentes e marginalizadas.The purpose of this article is to show how the Family Allowance Program (Programa Bolsa Família - PBF refers to a form of biopolitics such as evoked by Foucault. Besides illustrating how the PBF is inscribed in a normalizing perspective, the article seeks to show how the Social Services and the Education "for a lifetime" play an important role in terms of building up subjectivity processes and subjective opinions and feelings whose aim is to guide and control the poor and marginalized populations' behavior.

  2. Consideraciones para calcular el ratio precio-utilidad de la bolsa de Valores de Lima: metodología y aplicaciones

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    Javier Pereda

    2012-06-01

    Full Text Available En el presente trabajo se elabora una metodología para calcular el ratio precio-utilidad (PER del Índice General de la Bolsa de Valores de Lima (IGBVL en el periodo 1995-2011, dentro del enfoque planteado por Shiller (2005. A partir del PER calculado se estima la prima por riesgo del mercado de acciones (implicitequity premia, siguiendo la metodología planteada por Hayford y Malliaris (2004. Tanto el PER como la prima por riesgo estimadas se usan como indicadores para evaluar el desempeño del mercado de acciones en el periodo analizado. Los resultados muestran que los precios de las acciones respondieron básicamente a la evolución esperada de las utilidades de las empresas, incluso durante el periodo de auge de la bolsa de valores que precedió a la crisis financiera externa del 2008, sin evidencia de que haya existido una sobrevaluación en este mercado.

  3. Condicionalidades em saúde do programa Bolsa Família – Brasil: uma análise a partir de profissionais da saúde

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    Alice Teles de Carvalho

    2014-12-01

    Full Text Available Este estudo apresenta a percepção de profissionais de equipes de Saúde da Família de municípios do Nordeste do Brasil acerca das mudanças na vida das famílias participantes do programa Bolsa Família, da relação destas com os serviços de saúde e do impacto na dinâmica de trabalho dos profissionais, a partir do acompanhamento das condicionalidades de saúde do programa Bolsa Família. As informações foram obtidas por meio de entrevistas semiestruturadas e encontros de grupo focal. Os profissionais acreditam que o programa ocasionou mudanças favoráveis na vida das famílias participantes, como a redução da pobreza, o aumento da frequência escolar das crianças e mudanças positivas na relação entre as famílias participantes e os serviços de saúde. No entanto, relataram dificuldades de caráter organizacional no acompanhamento das condicionalidades, sobretudo devido ao aumento da demanda de trabalho. É importante que as condicionalidades de saúde proporcionem oportunidades para a realização de ações que visem ao empoderamento e autonomia dos sujeitos quanto ao autocuidado e desenvolvimento da cidadania.

  4. [Intersectoral, convergent and sustainable actions: the challenges of the "Bolsa Família" program in Manguinhos shantytown in Rio de Janeiro].

    Science.gov (United States)

    Magalhães, Rosana; Coelho, Angela Virginia; Nogueira, Milena Ferreira; Bocca, Cláudia

    2011-11-01

    Some studies have revealed the impact of the family welfare allowance based on the fulfillment of certain conditions on improving living conditions and access to health and education services in different countries. However, gaps persist relating to the evaluation of the benefits of such programs among the groups that have greater difficulty in gaining access to public services or advances in the quality of education and school performance. Moreover, there is limited evidence of adequacy of the program to the respective contexts of implementation, levels of adhesion and local cooperation and strategies adopted for integration with other social policy programs. The scope of this article is to discuss the findings of the study of the implementation of the "Bolsa Familia" in the Manguinhos shantytown area in Rio de Janeiro conducted in 2007 and 2008 based on semi-structured interviews with program officials and local stakeholders. In conclusion, the study shows that the sustainability of "Bolsa Familia" actions to reduce poverty and promote health equity calls for strengthening the vertical and horizontal communication channels between government levels, public managers and civil associations, recognition of the complexity of the local social demands and an intersectoral agenda.

  5. Perfil dos pesquisadores com bolsa de produtividade em pesquisa do CNPq da área de fonoaudiologia

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    Rosely de Fátima Pellizzon

    2014-10-01

    Full Text Available OBJETIVO: identificar o perfil dos bolsistas de produtividade em pesquisa do Conselho Nacional de Desenvolvimento Científico e Tecnológico - CNPq, na área de Fonoaudiologia.MÉTODOS: a partir da lista dos bolsistas de produtividade da área de Fonoaudiologia com bolsas vigentes em 2010, foram verificadas características de formação, publicação de artigos nas bases de dados: LILACS, SciELO Brasil, MEDLINE e Web of Science, identificando a produção de artigos científicos dos bolsistas na comunidade científica brasileira, publicados no período de 2006-2010. Também foi utilizado o indicador JCR e a classificação Qualis para análise das revistas.RESULTADOS: das 46 bolsistas, 45 (98% são graduadas em Fonoaudiologia e exercem a atividade de docência, 22 (47,83% na Região Sudeste e 24 (52,17% têm vínculo institucional nas universidades públicas (estaduais. Em relação à produção, foram identificados 935 artigos, sendo 816 (87,27% em 48 revistas brasileiras e 119 (12,72%em 47 revistas estrangeiras.Comrespeito às revistas, dos 95 títulos brasileiros e estrangeiros analisados, 38 (40% não apresentam o fator de impacto.CONCLUSÕES: a presença feminina é grande nesta área do conhecimento, sendo a maior ocorrência de pesquisadoras PQ com vinculação institucional nas universidades públicas, localizadas nas regiões Sudeste e Sul do país. A análise da produção de artigos científicos das bolsistas de Fonoaudiologia mostrou uma tendência a publicar seus artigos em revistas brasileiras, sem deixar de buscar a qualidade editorial: revisão de pares e indexação em bases de dados, aliadas ao indicador JCR e àclassificação do Qualis.

  6. Síndrome de la bolsa de orina púrpura: Presentación de un caso Purple urine bag syndrome: Case report

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    M. Zanetti

    2012-12-01

    Full Text Available El síndrome de la bolsa de orina púrpura es una entidad poco frecuente que fue descrita por primera vez en el año 1978. Son factores relacionados con su aparición la edad avanzada, sexo femenino, cateterización urinaria crónica, constipación crónica, alcalinización de la orina y un alto contenido bacteriano en orina. Se produce cuando el producto derivado del aminoácido triptófano es metabolizado a sulfato de indoxil. Al encontrarse esta sustancia en una orina alcalina, mediante reacciones enzimáticas y de acuerdo a la concentración de oxígeno, cambia a índigo (azul e indirrubina (rojo; los cuales precipitan en la orina y, junto con los materiales sintéticos del catéter y la bolsa urinaria, dan el color púrpura característico. Se presenta el caso de un varón adolescente de 17 años de edad, con antecedentes de paraplejia por lesión medular debida a proyectil de arma de fuego, que fallece en el domicilio sin asistencia médica. La paraplejia le obligaba al uso de sonda urinaria de forma permanente y al practicar la autopsia judicial se apreció un llamativo color púrpura en la bolsa colectora de orina.The purple urine bag syndrome is a rare entity first described in 1978. Factors related to its production are elderly female, urinary catheterization, chronic constipation, alkaline urine and high bacterial levels in urine. It occurs when the product of the amino acid tryptophan is metabolized to indoxyl sulfate. This substance due to enzymatic reactions, in presence of an alkaline urine, and according to the oxygen concentration switches to indigo (blue and indirubin (red, which precipitate in the urine and together with synthetic materials urinary catheter, give the characteristic purple color. We present the case of a 17-year-old male, with antecedents of paraplegia secondary a firearm wound, who died at home without medical care. Due to the paraplegic condition, chronic urinary catheterization was needed. At the judicial

  7. Society-State relationships, citizen participation and political clientelism inside programs that combat poverty. The case of «Bolsa Familia» in Brazil Relaciones sociedad-estado, participación ciudadana y clientelismo político en programas contra la pobreza. El caso de «bolsa familia» en Brasil

    Directory of Open Access Journals (Sweden)

    Felipe J. HEVIA

    2011-06-01

    Full Text Available Relations between poor people and the government that creates the Programa Bolsa Familia at Brazil may be summarized in two dimensions: 1 favor direct relationships without the intervention of collective action and 2 are distant relations in terms of type of interaction and communication between the authorities and beneficiaries. While there are instances of formal social control, operation of the program makes minimal intermediation and highly institutional and civic organizations have little room to act and to represent the beneficiaries of Bolsa Familia in institutionalized interfaces. Direct links generate positive effect low levels of political patronage vote buying and coercion, but also generate unintended effects such as the lack of program operation, difficulty to defend themselves collectively by irregularities and create an active citizenry.Las relaciones entre los pobres y el gobierno que genera la implementación del programa Bolsa Familia pueden resumirse en dos dimensiones: 1 se privilegian «relaciones directas» sin intermediación de acción colectiva y 2 también «relaciones lejanas» en términos del tipo de interacción y comunicación entre las autoridades y los beneficiarios. Si bien existen instancias formales de control social, la operación del programa hace que la intermediación sea mínima, altamente institucional y que las organizaciones civiles tengan poco espacio para actuar representando a los beneficiarios. Estas relaciones generan bajos niveles de compra y coacción del voto, pero crean también efectos no intencionales como son el desconocimiento de la operación del programa, dificultad para defenderse de manera colectiva de abusos de poder, así como obstáculos para generar ciudadanía activa.

  8. 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.

  9. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    2013-01-01

    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

  10. 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

  11. Transferencia de ingresos dirigida a los más pobres: la experiencia brasileña con el Programa Bolsa-Familia

    Directory of Open Access Journals (Sweden)

    Cecília Paiva

    2010-03-01

    Full Text Available En Brasil se implementó, a partir de los años noventa, un nuevo modelo de protección social acorde con el nuevo orden económico mundial, lo que significó una ruptura con el proceso de constitución de un sistema de protección social basado en los derechos a la salud y la universalidad. En este contexto predominan las políticas diseñadas para combatir la pobreza a través de programas de transferencia no contributiva de ingresos. El artículo examina el programa Bolsa-Familia, el principal programa de atención a las familias beneficiarias, así como acceso de estas a los derechos sociales.

  12. Programa Bolsa Família como estratégia de combate à pobreza em Dissertações e Teses no Brasil

    OpenAIRE

    Viviam Rafaela Barbosa Pinheiro Freire; Simone Souza da Costa Silva; Lilia Iêda Chaves Cavalcante; Fernando Augusto Ramos Pontes

    2013-01-01

    Esta pesquisa objetivou mapear Dissertações e Teses sobre o Programa Bolsa Família (PBF) disponíveis no Banco de Teses da Capes. A busca e seleção resultaram em 166 trabalhos entre os anos de 2004-2009. Os resumos foram analisados e categorizados em: 1) Publicação de Dissertações e Teses por nível acadêmico e ano; 2) Área, palavras-chave e método das Dissertações e Teses; 3) Enfoque de investigação nas regiões do Brasil; e 4) Conteúdo temático por nível acadêmico. Observou-se que 75,9% das pe...

  13. Research reactors

    International Nuclear Information System (INIS)

    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)

  14. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    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

  15. Empoderamento das mulheres beneficiárias do Programa Bolsa Família na percepção dos agentes dos Centros de Referência de Assistência Social

    Directory of Open Access Journals (Sweden)

    Nathalia Carvalho Moreira

    2012-04-01

    Full Text Available Este trabalho teve como objetivo analisar o empoderamento das mulheres beneficiárias do Programa de Transferência de Renda, conhecido como "Programa Bolsa Família", na percepção dos agentes sociais dos Centros de Referência de Assistência Social (Cras. Para tanto, realizou-se um estudo de caso múltiplo, tendo como sujeitos de pesquisa 11 gestores de diferentes Cras do estado de Minas Gerais. A partir da técnica de análise de conteúdo, as respostas das perguntas, que compuseram as entrevistas, foram agrupadas de acordo com as categorias Bolsa Família, Cras e Mulher. Os resultados apontam a importância do Cras na execução do Programa Bolsa Família e no processo de empoderamento, pois a convivência e a participação neste local têm contribuído para a conscientização sobre direitos, para a inserção social e para a melhoria do bem-estar das mulheres, fatores evidenciados por intermédio do interesse das mulheres por cursos, oficinas, informações sobre programas sociais e atendimento psicológico. Na percepção dos agentes, foi possível observar melhoria nas condições de vida, nas relações familiares, conscientização e autoestima, implicando reflexos sobre o empoderamento feminino. Portanto, embora sendo um processo lento e embrionário, pode-se dizer que o ciclo do empoderamento das mulheres beneficiárias do Bolsa Família pode ser completado, pois consegue atingir as três dimensões (individual, familiar e comunitária.

  16. Reactor building

    International Nuclear Information System (INIS)

    The whole reactor building is accommodated in a shaft and is sealed level with the earth's surface by a building ceiling, which provides protection against penetration due to external effects. The building ceiling is supported on walls of the reactor building, which line the shaft and transfer the vertical components of forces to the foundations. The thickness of the walls is designed to withstand horizontal pressure waves in the floor. The building ceiling has an opening above the reactor, which must be closed by cover plates. Operating equipment for the reactor can be situated above the building ceiling. (orig./HP)

  17. Avaliando resultados de um programa de transferência de renda: o impacto do Bolsa-Escola sobre os gastos das famílias brasileiras

    Directory of Open Access Journals (Sweden)

    Anne Caroline Costa Resende

    2008-01-01

    Full Text Available Este trabalho tem como objetivo analisar os efeitos de programas de transferências monetárias sobre os gastos totais bem como sobre seus componentes para as famílias beneficiárias no Brasil, através do programa Bolsa-Escola. Para se alcançar tal objetivo é adotado um método não- experimental conhecido como pareamento baseado no escore de propensão (propensity score matching, utilizando os microdados da Pesquisa de Orçamentos Familiares (POF 2002-2003. Realiza-se, ainda, uma análise de sensibilidade dos resultados obtidos a fim de se verificar a robustez do método à presença de variáveis não observadas, bem como à especificação do modelo de escore de propensão. Os resultados estimados sugerem um efeito positivo das transferências monetárias sobre o consumo das famílias pobres beneficiárias. O fato de os recursos serem prioritariamente destinados a despesas com alimentos, educação, produtos de higiene e vestuário em detrimento de itens como bebidas e cigarros, despesas diversas e bens duráveis significa que, em alguma medida, estes recursos estão sendo gastos de forma eficiente. É provável, também, que o aumento do consumo destas famílias eleve o seu nível de bem-estar, representando um "alívio" imediato sobre a pobreza.The aim of this work is to analyze the effects of cash transfers of public programs on household’s expenditures and their components, taking the Brazilian program Bolsa-Escola as a representative example. It is used a non experimental method called propensity score matching, with microdata from the Pesquisa de Orçamentos Familiares (POF 2002-2003. Further, a sensitivity analysis is carried to certify that the propensity score model is well specified and still works in the presence of unobservable variables. Results suggest a positive effect of cash transfers on the poor beneficiary household’s consumption. The fact that household’s expenditures are concentrated on education, hygiene

  18. Prospección geológica y geofísica de sulfuros en el área de Virorco-La Bolsa, provincia de San Luis Geological and geophysical sulfide prospection in the Virorco-La Bolsa area, San Luis province

    Directory of Open Access Journals (Sweden)

    J. Kostadinoff

    2005-09-01

    Full Text Available En los cuerpos máficos-ultramáficos del área de Virorco y La Bolsa, bloque central de la sierra de San Luis, se han detectado sulfuros polimetálicos en venillas y diseminados. Como herramienta de prospección geofísica se utilizó el método de autopotencial en combinación con estudios geomagnéticos. Los lentes máfico-ultramáficos están enmarcados por una caja gnéisicamigmatítica de alto grado. Una foliación milonítica de rumbo NNE y buzamiento de alto ángulo al ESE, afecta al basamento y también a los bordes de los cuerpos máfico-ultramáficos. Hacia el interior de estos últimos, alternan sectores que preservan las texturas granulares ígneas y una foliación buzante al oeste, con fajas de cizalla con foliación milonítica buzante al ESE. El estudio geofísico en Virorco indica una correspondencia entre los valores de autopotencial negativos (-150 mV y los máximos de magnetismo terrestre (+350 nT. En la zona de La Bolsa se realizaron dos perfiles de autopotencial, los cuales muestran un núcleo de autopotencial negativo de entre -40 y -55 mV, ligeramente alargado y buzante al ESE. Sobre el margen oriental, un valor de -90 mV constituye el núcleo de una anomalía alargada y también buzante al ESE. La disposición espacial de estas anomalías es coincidente con la orientación de la foliación milonítica. La correspondencia establecida con esta nueva herramienta de prospección, sustenta la removilización y concentración de los sulfuros primarios diseminados durante el evento de milonitización, ya planteada previamente en base a otras técnicas de estudio.In the Virorco and La Bolsa mafic-ultramafic bodies, central block of the Sierra de San Luis, polymetallic sulfides occur in veinlets and disseminated. The autopotential method in combination with geomagnetic studies, were utilized as geophysical prospection tools. The maficultramafic lenses are surrounded by high-grade gneissic-migmatitic country-rocks. A penetrative

  19. Bolsa Floresta: um instrumento inovador para a promoção da saúde em comunidades tradicionais na Amazônia Bolsa Floresta (Forest Conservation Allowance): an innovative mechanism to promote health in traditional communities in the Amazon

    OpenAIRE

    Virgilio M. Viana

    2008-01-01

    O Programa Bolsa Floresta implementa uma série de atividades prioneiras no campo da conservação ambiental e desenvolvimento sustentável na Amazônia. Sua concepção se insere no contexto das mudanças climáticas globais e de redução do desmatamento, com especial ênfase para as comunidades tradicionais da "Amazônia profunda". Este artigo descreve o conceito e a estratégia de implementação do Programa, com uma ênfase especial para as ações de saúde. Primeiro, é apresentado o contexto no qual foi c...

  20. Prospección geológica y geofísica de sulfuros en el área de Virorco-La Bolsa, provincia de San Luis Geological and geophysical sulfide prospection in the Virorco-La Bolsa area, San Luis province

    OpenAIRE

    J. Kostadinoff; S. Delpino; E. Bjerg; A. Mogessie; A. Raniolo; Arrese, M; G. Ferracutti

    2005-01-01

    En los cuerpos máficos-ultramáficos del área de Virorco y La Bolsa, bloque central de la sierra de San Luis, se han detectado sulfuros polimetálicos en venillas y diseminados. Como herramienta de prospección geofísica se utilizó el método de autopotencial en combinación con estudios geomagnéticos. Los lentes máfico-ultramáficos están enmarcados por una caja gnéisicamigmatítica de alto grado. Una foliación milonítica de rumbo NNE y buzamiento de alto ángulo al ESE, afecta al basamento y tambié...

  1. Os custos eleitorais do Bolsa Família: reavaliando seu impacto sobre a eleição presidencial de 2006

    Directory of Open Access Journals (Sweden)

    Diego Sanches Corrêa

    2015-12-01

    Full Text Available O padrão geográfico da flutuação da votação de Lula entre as eleições presidenciais de 2002 e 2006 é um dos mais intrigantes fenômenos políticos da história recente brasileira. Diversos estudos mostram que o programa Bolsa Família aumentou consideravelmente o apoio a Lula entre os pobres, tendo um papel determinante nos resultados da eleição de 2006. Neste artigo, eu demonstro com base em um banco de dados municipais e técnicas de econometria espacial que seu desempenho eleitoral também se associa negativamente à proporção de ricos. Meu argumento é de que o programa explica ambos os efeitos: os pobres responderam às melhorias em suas condições materiais de vida e os ricos aos custos de oportunidade de investimentos públicos que não lhes beneficiaram diretamente.

  2. Estratégias de Investimento em Bolsa de Valores: Uma Pesquisa Exploratória da Visão Fundamentalista de Benjamin Graham

    Directory of Open Access Journals (Sweden)

    Vinicius de Castro Scottá dos Passos

    2010-11-01

    Full Text Available

    Investimentos em bolsa de valores têm sido associados às incertezas e grandes riscos, quando na verdade existem teorias que podem ser assimiladas por qualquer pessoa que deseje diversificar seus investimentos. Estudar as ferramentas de análise de mercado de ações e as estratégias utilizadas por célebres investidores pode oferecer preciosas orientações de como devemos nos preparar psicologicamente e tecnicamente para operar no mercado de ações. O cenário globalizado favorece o fluxo de informação, mas, ainda assim, existe a assimetria informacional do mercado. A análise fundamentalista tem sido forte aliada do mercado de capitais e tem em Benjamin Graham um de seus principais expoentes. Este artigo versará sobre as teorias de Graham, buscando a aplicabilidade de tais premissas na realidade brasileira. A realização da pesquisa poderá ser mais um passo no aprendizado de variáveis que se correlacionam com o mercado bursátil, contribuindo para futuros investidores.

  3. Estratégias de Investimento em Bolsa de Valores: Uma Pesquisa Exploratória da Visão Fundamentalista de Benjamin Graham

    Directory of Open Access Journals (Sweden)

    Vinicius de Castro Scottá dos Passos

    2010-11-01

    Full Text Available Investimentos em bolsa de valores têm sido associados às incertezas e grandes riscos, quando na verdade existem teorias que podem ser assimiladas por qualquer pessoa que deseje diversificar seus investimentos. Estudar as ferramentas de análise de mercado de ações e as estratégias utilizadas por célebres investidores pode oferecer preciosas orientações de como devemos nos preparar psicologicamente e tecnicamente para operar no mercado de ações. O cenário globalizado favorece o fluxo de informação, mas, ainda assim, existe a assimetria informacional do mercado. A análise fundamentalista tem sido forte aliada do mercado de capitais e tem em Benjamin Graham um de seus principais expoentes. Este artigo versará sobre as teorias de Graham, buscando a aplicabilidade de tais premissas na realidade brasileira. A realização da pesquisa poderá ser mais um passo no aprendizado de variáveis que se correlacionam com o mercado bursátil, contribuindo para futuros investidores.

  4. Divulgación de información sobre el capital intelectual de empresas nacionales que cotizan en la Bolsa Mexicana de Valores

    Directory of Open Access Journals (Sweden)

    Ruth Leticia Hidalgo Gallardo

    2009-01-01

    Full Text Available Con la nueva visión económica se reconoce al capital intelectual como una herramienta de creación de valor para las empresas que buscan una mayor competitividad en el mercado. En este trabajo se analiza la divulgación que en materia de intangibles llevan a cabo las empresas mexicanas, así como los factores que motivan tal divulgación; para ello, se analizaron los reportes de los anuales de cien empresas que cotizan en la Bolsa Mexicana de Valores. Los resultados reflejaron que para las empresas mexicanas es más importante la divulgación de información del capital estructural, seguido del capital relacional y posteriormente del capital humano; el tamaño de la empresa es el factor clave de la divulgación. De igual forma, se encontró que las empresas de los sectores: industrial, de alimentos y bebidas, y construcción e inmobiliaria son proactivos en el momento de divulgar información sobre intangibles.

  5. Análisis de series de tiempo para la predicción de los precios de la energía en la bolsa de Colombia

    Directory of Open Access Journals (Sweden)

    Cano Cano Jovan Alfonso

    2008-08-01

    Full Text Available Debido a la reestructuración del sector eléctrico colombiano,
    durante las dos últimas décadas, el comportamiento del precio de la
    energía eléctrica ha incrementado su volatilidad, reflejando el
    riesgo existente para los diferentes agentes que intervienen en el
    mercado. El objetivo de este artículo es presentar una metodología
    para la implementación de modelos de regresión, sobre la serie
    histórica de precios de bolsa de energía en Colombia. A medida que
    la cantidad de datos aumente, podrán desarrollarse modelos más
    amplios, que describan de forma adecuada comportamientos del
    mercado, que empleando las técnicas y la información disponible
    actualmente, no es posible identificar.

  6. Síndrome de la orina morada en bolsa en paciente anciana con suplementos nutricionales Purple urine bag syndrome in elderly woman with nutritional supplements

    Directory of Open Access Journals (Sweden)

    A. R. Domínguez Alegría

    2012-12-01

    Full Text Available El síndrome de la orina morada en bolsa es una entidad poco frecuente que afecta característicamente a mujeres de edad avanzada con sondaje vesical prolongado y debilitadas por enfermedades crónicas. La presencia de patología urológica previa, el encamamiento prolongado y el estreñimiento crónico son factores predisponentes. El color morado de la orina se debe a la presencia de elevadas concentraciones de bacterias con actividad indoxilsulfatasa/fosfatasa que se desarrollan en un ambiente alcalino en presencia de otros factores. En el caso que presentamos la administración de suplementos nutricionales ricos en triptófano tuvieron un papel relevante en la generación de este síndrome.The purple urine bag syndrome is a rare entity which typically affects elderly women with prolonged urinary catheterization and weakening chronic diseases. Other predisposing factors are previous urologic pathology, immobility syndrome and chronic constipation. The purple color is due to the presence of high loads of bacteria with sulphatase - phosphatase activity which develop in an alkaline environment as well as the presence of other factors. In the case we present the administration of nutritional supplements containing tryptophan conditioned the generation of this syndrome.

  7. Compact Reactor

    International Nuclear Information System (INIS)

    Weyl's Gauge Principle of 1929 has been used to establish Weyl's Quantum Principle (WQP) that requires that the Weyl scale factor should be unity. It has been shown that the WQP requires the following: quantum mechanics must be used to determine system states; the electrostatic potential must be non-singular and quantified; interactions between particles with different electric charges (i.e. electron and proton) do not obey Newton's Third Law at sub-nuclear separations, and nuclear particles may be much different than expected using the standard model. The above WQP requirements lead to a potential fusion reactor wherein deuterium nuclei are preferentially fused into helium nuclei. Because the deuterium nuclei are preferentially fused into helium nuclei at temperatures and energies lower than specified by the standard model there is no harmful radiation as a byproduct of this fusion process. Therefore, a reactor using this reaction does not need any shielding to contain such radiation. The energy released from each reaction and the absence of shielding makes the deuterium-plus-deuterium-to-helium (DDH) reactor very compact when compared to other reactors, both fission and fusion types. Moreover, the potential energy output per reactor weight and the absence of harmful radiation makes the DDH reactor an ideal candidate for space power. The logic is summarized by which the WQP requires the above conditions that make the prediction of DDH possible. The details of the DDH reaction will be presented along with the specifics of why the DDH reactor may be made to cause two deuterium nuclei to preferentially fuse to a helium nucleus. The presentation will also indicate the calculations needed to predict the reactor temperature as a function of fuel loading, reactor size, and desired output and will include the progress achieved to date

  8. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  9. 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.

  10. Chemical Reactors.

    Science.gov (United States)

    Kenney, C. N.

    1980-01-01

    Describes a course, including content, reading list, and presentation on chemical reactors at Cambridge University, England. A brief comparison of chemical engineering education between the United States and England is also given. (JN)

  11. NUCLEAR REACTOR

    Science.gov (United States)

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  12. Nuclear reactor

    International Nuclear Information System (INIS)

    In order to reduce neutron embrittlement of the pressue vessel of an LWR, blanked off elements are fitted at the edge of the reactor core, with the same dimensions as the fuel elements. They are parallel to each other, and to the edge of the reactor taking the place of fuel rods, and are plates of neutron-absorbing material (stainless steel, boron steel, borated Al). (HP)

  13. Bolsa Família: insegurança alimentar e nutricional de crianças menores de cinco anos

    Directory of Open Access Journals (Sweden)

    Flávia Monteiro

    2014-05-01

    Full Text Available Estudo transversal descritivo de base populacional realizado no município de Colombo (PR. Os objetivos foram identificar a prevalência de insegurança alimentar das famílias beneficiárias do Programa Bolsa Família e os fatores relacionados a essa condição, bem como descrever o estado nutricional das crianças menores de cinco anos. As análises de associação foram realizadas por meio do teste exato de Fischer. A amostra incluiu 442 famílias, das quais 168 com menores de cinco anos em sua constituição. Para avaliação da insegurança alimentar foi aplicada a Escala Brasileira de Insegurança Alimentar e o estado nutricional das 199 crianças avaliadas foi determinado pelos índices estatura para idade, peso para idade e índice de massa corporal para idade, de acordo com os valores de referência da OMS 2006. A prevalência de insegurança alimentar foi de 81,6%. O excesso de peso e o déficit estatural entre as crianças coexistiram. A insegurança alimentar apresentou-se associada ao índice estatura para idade entre crianças menores de dois anos. A renda familiar per capita e as dívidas alimentares influenciaram significativamente a situação de insegurança alimentar familiar.

  14. Análisis de portafolio por sectores mediante el uso de algoritmos genéticos: caso aplicado a la Bolsa Mexicana de Valores

    Directory of Open Access Journals (Sweden)

    Martha del Pilar Rodríguez García

    2015-01-01

    Full Text Available El tipo de sector, el tamaño de la empresa, el número de trabajadores, etc. son variables que se consideran de control en una gran cantidad de publicaciones. En este trabajo consideramos estudiar la variable sector —más que como una variable de control— como una variable determinante del desempeño financiero (Baird et al. 2012 y del riesgo (Artikis y Nifora, 2011. Así, se analiza seis sectores de la economía mexicana divididos de acuerdo con la Bolsa Mexicana de Valores en Industrial, Productos de consumo básico, Materiales, Productos de consumo no básico, Telecomunicaciones y Servicios financieros. La muestra se compone de 30 empresas mexicanas dentro del periodo de 2007-2012. Para medir el desempeño del portafolio se utilizan dos indicadores clásicos: (1 Alfa de Jensen y (2 Ratio de Sharpe; se utiliza una métrica condicional que mide el número de veces que el rendimiento del portafolio supera el rendimiento promedio del mercado. El objetivo es encontrar un portafolio que maximice estos parámetros y comparar los resultados entre los diferentes sectores bajo estudio. Debido a un problema de programación no lineal, se utilizan algoritmos genéticos para obtener el portafolio óptimo que maximice estas métricas. Los resultados muestran un mejor desempeño financiero ajustado a riesgo en el sector de Materiales y Servicios financieros y un desempeño más bajo en sectores como el Industrial y el de Telecomunicaciones.

  15. Estudos endoscópico e histológico prospectivos e sequenciais da bolsa gástrica em 130 pacientes obesos mórbidos submetidos à bypass gástrico em Y-de-Roux Prospective sequential endoscopic and histologic studies of the gastric pouch in 130 morbidly obese patients submitted to Roux-en-Y gastric bypass

    OpenAIRE

    Attila Csendes; Gladys Smok; Ana Maria Burgos; Moira Canobra

    2012-01-01

    RACIONAL: Bypass gástrico em Y-de-Roux é a operação bariátrica mais comumente realizada. Pequena bolsa gástrica é criada, deixando uma anastomose gastrojejunal estreita, com uma alça jejunal mais comprida. Muito pouco é conhecido sobre o comportamento desta bolsa em anos após o procedimento. OBJETIVO: Determinar através de estudos prospectivos endoscópico e histológico seqüenciais o tamanho da bolsa gástrica, o diâmetro da anastomose e o comportamento da infecção por H. pylori após a operação...

  16. Surgical treatment of familial adenomatous polyposis: ileoretal anastomosis or restorative proctolectomy? Tratamento cirúrgico da polipose adenomatosa familiar: anastomose íleo-retal ou bolsa ileal?

    Directory of Open Access Journals (Sweden)

    Fábio Guilherme Campos

    2009-12-01

    (clinical, endoscopic, genetic indicate that the best choice for operative treatment should be based on individual features discussed by a specialist; 5. all patients require continuous and long-term surveillance during postoperative follow-up.CONTEXTO: As controvérsias quanto a melhor forma de tratamento da polipose adenomatosa familiar confrontam a morbidade da proctocolectomia restauradora contra a suposta mortalidade decorrente de câncer retal após íleo-reto anastomose. OBJETIVOS: Avaliar as complicações operatórias e a evolução oncológica dos pacientes submetidos a íleo-reto anastomose ou proctocolectomia restauradora. MÉTODOS: Analisaram-se os dados dos doentes tratados entre 1977 e 2006, procedendo ao levantamento de dados clínicos gerais, endoscópicos, resultados do tratamento cirúrgico, dados anatomopatológicos e informações sobre a evolução precoce e tardia dos pacientes. RESULTADOS: Foram tratados 88 pacientes, sendo 41 homens (46,6% e 47 mulheres (53,4%. Por ocasião do diagnóstico, 53 pacientes (60,2% já tinham câncer colorretal associado à polipose. Registraram-se complicações operatórias em 25 doentes (29,0 % dentre os 86 operados, sendo 17 (19,7% precoces e 8 (9,3% tardias. Houve mais complicações após proctocolectomia restauradora (48,1% em comparação às proctocolectomias com ileostomia (26,6% e íleo-reto anastomose (19,0% (P = 0,03. Não houve mortalidade operatória. O risco cumulativo de câncer retal após íleo-reto anastomose foi de 17,2% após 5 anos, 24,1% após 10 anos e 43,1% após 15 anos de seguimento pós-operatório. Já o risco cumulativo idade-dependente começou a existir a partir de 30 anos (4,3%, passando para 9,6% aos 40 anos, 20,9% aos 40 anos e 52% aos 60 anos. Entre os pacientes submetidos a bolsa ileal com seguimento (26, apenas 1 doente (3,8% desenvolveu câncer na bolsa ileal. CONCLUSÕES: 1. Ocorreram complicações operatórias em cerca de 1/3 dos pacientes, sendo mais frequentes após a confec

  17. El sistema de la bolsa es útil como espaciador para la administración de los aerosoles presurizados A plastic bag is useful as spacer device for pressurized aerosol delivery

    OpenAIRE

    Laura Mendoza I; Carolina Contreras C; Angélica Espinoza N; Ely Jover R; Gabriel Cavada C

    2005-01-01

    Se ha demostrado que el depósito y efecto de los medicamentos administrados a través de los inhaladores presurizados mejora con el uso de espaciadores, pero la adherencia a estos accesorios no es buena por su costo y por su tamaño incómodo. Nuestro objetivo fue determinar si un sistema artesanal tipo reservorio, armado con una bolsa plástica unida a una boquilla de cartón, es efectivo como espaciador. Para esto, seleccionamos a 17 sujetos mayores de 16 años con espirometría con limitación ven...

  18. Análisis de las implicaciones económicas y operativas de las estratégias de financiamiento de capital de trabajo operativo en empresas que tranzan en la bolsa de valores de Colombia

    OpenAIRE

    Dávila Taborda , Gustavo Adolfo

    2011-01-01

    En la presente tesis se analiza, para el período comprendido entre 1997 y 2008, el capital de trabajo desde el punto de vista de la inversión, financiación y relación con variables como: activos totales, ventas, pasivo y patrimonio y el costo de capital (a manera de ejercicio); así como los efectos económicos y operativos de las implicaciones de las estrategias de inversión y financiamiento de capital de trabajo en empresas listadas en la Bolsa de Valores de Colombia exceptuando aquellas que ...

  19. Análisis de las dificultades financieras de las empresas en una economía emergente las bases de datos y las variables independientes en el sector hotelero de la bolsa mexicana de valores /

    OpenAIRE

    Ibarra Mares, Alberto

    2002-01-01

    Consultable des del TDX Títol obtingut de la portada digitalitzada Este trabajo desarrolla de forma muy detallada la primera fase de un modelo predictivo para evaluar el éxito o fracaso empresarial dentro de un sector muy específico en una economía emergente, como es el caso de México dentro del sector hotelero que cotiza en la Bolsa Mexicana de Valores. Esta situación conlleva importantes particularidades por el aspecto tan "sui generis" que presenta el análisis financiero en empresas ...

  20. Análisis de las dificultades financieras de las empresas en una economía emergente: las bases de datos y las variables independientes en el sector hotelero de la bolsa mexicana de valores

    OpenAIRE

    Ibarra Mares, Alberto

    2001-01-01

    Este trabajo desarrolla de forma muy detallada la primera fase de un modelo predictivo para evaluar el éxito o fracaso empresarial dentro de un sector muy específico en una economía emergente, como es el caso de México dentro del sector hotelero que cotiza en la Bolsa Mexicana de Valores. Esta situación conlleva importantes particularidades por el aspecto tan "sui generis" que presenta el análisis financiero en empresas de economías emergentes. En general los modelos predictivos presentan dos...

  1. Análisis de la degradación, desintegración y biodegradabilidad de bolsas de poliéster y almidón en compostaje de residuos urbanos: escalas de laboratorio e industrial

    OpenAIRE

    Fernando de Fuentes, Aida

    2015-01-01

    El principal objetivo de esta tesis es verificar que las bolsas biodegradables de copoliéster (PBAT) con base de almidón (UNE 13432: 2001) alcanzan los niveles de degradación y desintegración requeridos para su certificación (%D= ≥ 90%), medido en condiciones reales de compostaje industrial. Para lograr mayor representatividad, los ensayos se han realizado en dos plantas de tratamiento de residuos urbanos en las que se aplican las técnicas de compostaje más comunes en el ámbito europeo y naci...

  2. Armonización de las NIC/NIIF en las prácticas contables de entes emisores no financieros que cotizan en la Bolsa de Valores de Caracas, Venezuela

    OpenAIRE

    Oda Gómez; Aminta De La Hoz; Betty De La Hoz

    2011-01-01

    Esta investigación de tipo documental y empírica tiene el propósito de analizar la armonización contable material de las Normas Internacionales de Contabilidad (nic) y las Normas Internacionales de Información Financiera (niif) de los entes emisores no financieros; para ello, se abordó inicialmente el proceso de aplicación de las mismas en el nivel mundial, así como el proceso correspondiente en Venezuela. Se consultó el anuario estadístico de 2007 emitido por la Bolsa de Valores de Caracas; ...

  3. A bolsa na mediação "estar ostomizado" - "estar profissional": análise de uma estratégia pedagógica La bolsa como mediadora entre "estar ostomizado" y "estar profesional": análisis de una estratégia pedagógica The pouch mediating the relation between "being an ostomized person" and "being professional": analysis of a pedagogic strategy

    Directory of Open Access Journals (Sweden)

    Vera Lúcia Conceição de Gouveia Santos

    2000-07-01

    Full Text Available Este estudo analisou a (reconstrução das significações sobre a ostomia, o ostomizado, o cuidar em enfermagem e o papel profissional de 30 enfermeiros que utilizaram bolsa coletora, em experiência pedagógica, durante os Cursos de Estomaterapia. A análise dos depoimentos revelou dois grandes eixos discursivos: "estar ostomizado" e "estar profissional". O enfermeiro, tendo por mediação o uso da bolsa coletora, vivencia o "estar ostomizado" por meio de violações da identidade e qualidade de vida, perpassadas por transformações desde papéis às relações com o outro. A mobilização de conteúdos simbólicos e afetivos acerca do "estar ostomizado" gera uma crise de significação do "estar profissional", até então caracterizado por um cuidar fragmentado. Re-conhecendo o cuidar passado como um fazer técnico voltado principalmente para a ostomia-bolsa, o aluno-enfermeiro projeta um cuidar futuro mais holístico do ser humano portador de uma ostomia, incorporando as dimensões afetivas, simbólicas e relacionais.El estudio es acerca de la (reconstrucción de los significados sobre el estoma, el ostomizado, el cuidado de enfermería y el rol profesional, hecha por 30 enfermeros que usaran bolsas de drenaje, como una estrategia pedagógica en los Cursos de Terapia Enterostomal. El análisis de los discursos reveló dos grandes categorias: "estar ostomizado" y "estar profesional". El enfermero, teniendo por mediación la bolsa, vive el "estar ostomizado" con sentimientos de transgresión de la identidad, de la calidad de vida, cambios de roles y de sus relaciones sociales. La movilización de los contenidos simbólicos y afectivos acerca del "estar ostomizado" resulta en una crisis de significado del "estar profesional" caracterizado por el cuidar fragmentado. Reconociendo el cuidar pasado como un hacer técnico dirigido principalmente para el estoma-bolsa, el enfermero proyecta un cuidar futuro del ostomizado más humanizado, agregando

  4. Características y diferencias entre recién nacidos intervenidos con la bolsa corporal de polietileno y el secado convencional durante la Adaptación neonatal en la Sede Materno Infantil del Hospital la Victoria y el Hospital de Engativá, Bogotá, 2013

    OpenAIRE

    Montilla Velásquez, María del Pilar

    2014-01-01

    INTRODUCCION: La hipotermia en el recién nacido es causa condiciones mórbidas. En países en vía de desarrollo la tecnología básica para la adaptación neonatal puede no estar disponible. Las bolsas de polietileno pueden ser alternativas a la lámpara de calor radiante para evitar hipotermia OBJETIVO: Caracterizar las diferencias entre Recién nacidos a término intervenidos con Bolsa corporal de polietileno o secado convencional durante la adaptación neonatal en la Sede Materno ...

  5. Sonochemical Reactors.

    Science.gov (United States)

    Gogate, Parag R; Patil, Pankaj N

    2016-10-01

    Sonochemical reactors are based on the generation of cavitational events using ultrasound and offer immense potential for the intensification of physical and chemical processing applications. The present work presents a critical analysis of the underlying mechanisms for intensification, available reactor configurations and overview of the different applications exploited successfully, though mostly at laboratory scales. Guidelines have also been presented for optimum selection of the important operating parameters (frequency and intensity of irradiation, temperature and liquid physicochemical properties) as well as the geometric parameters (type of reactor configuration and the number/position of the transducers) so as to maximize the process intensification benefits. The key areas for future work so as to transform the successful technique at laboratory/pilot scale into commercial technology have also been discussed. Overall, it has been established that there is immense potential for sonochemical reactors for process intensification leading to greener processing and economic benefits. Combined efforts from a wide range of disciplines such as material science, physics, chemistry and chemical engineers are required to harness the benefits at commercial scale operation.

  6. Orçamento familiar e gênero: percepções do Programa Bolsa Família Family income and gender: perceptions of the Family Aid Program

    Directory of Open Access Journals (Sweden)

    André Pires

    2012-04-01

    Full Text Available O estudo apresenta os resultados de uma investigação etnográfica realizada entre os participantes do Programa Bolsa Família no município de Campinas, Estado de São Paulo. A análise parte de percepção, presente na fala dos entrevistados, de que o "Bolsa Família ajuda". O objetivo é compreender os sentidos do termo "ajuda" em dois momentos: como viver numa localidade como Campinas interfere na forma de as pessoas avaliarem o programa; e como o termo "ajuda" denota uma incorporação simbólica permeada pelas relações de gênero desse dinheiro pela família.This study presents the results of an ethnographic investigation among beneficiaires of the Family Aid Program in the municipality of Campinas, São Paulo State, Brazil. The analysis took as its starting-point the perception present in the discourse of participants for whom the "Family Allowance helps". The aim was to grasp the meaning of this 'help" at two moments, trying to understand: how living in a city like Campinas interferes in the way through which people evaluated the program; and, how the word "help" denotes a gendered incorporation of the money.

  7. Estructura de capital de las empresas que cotizan en la bolsa de valores chilena Un análisis comparativo basado en la teoría de asimetrías de información

    Directory of Open Access Journals (Sweden)

    Paolo Saona Hoffmann

    2009-01-01

    Full Text Available En este trabajo se estudia la estructura de capital de las empresas que cotizan en la bolsa de valores de Chile, para lo cual se efectúa un análisis comparativo basado en la teoría de asimetrías de información. De acuerdo con esta teoría, las empresas de mejor calidad envían señales al mercado sobre su condición con el propósito de establecer un criterio de separación y diferenciarse de las que tienen una calidad inferior (Akerlof, 1970. Se ha considerado a las empresas pertenecientes al Índice de Precios Selectivo de Acciones (ipsa en el mercado de valores chileno como las que cuentan con menores asimetrías de información y se han comparado con el resto de las empresas que cotizan en la bolsa, pero que no pertenecen al índice, suponiendo que son las que poseen mayores asimetrías de información. Entre los principales hallazgos se encontró que pertenecer al índice implica una reducción en la brecha informativa con el mercado y que la mayor visibilidad de las empresas indexadas les permite acceder más fácilmente a los mercados de deuda.

  8. Staphylococcus spp. in the oral cavity and periodontal pockets of chronic periodontitis patients Staphylococcus spp. na cavidade bucal e na bolsa periodontal de indivíduos com periodontite crônica

    Directory of Open Access Journals (Sweden)

    Jussara Cia S. Loberto

    2004-06-01

    outras infecções pode predispor o aumento do número de Staphylococcus spp. na boca, pois estes adquirem facilmente resistência aos antibióticos, podendo resultar em superinfecção. O objetivo deste estudo foi verificar a presença de Staphylococcus spp. na cavidade bucal e nas bolsas periodontais de pacientes com periodontite crônica; identificar as cepas isoladas; verificar a relação entre a presença de Staphylococcus spp. na cavidade bucal e presença de bolsa periodontal. Participaram deste estudo 88 pacientes, entre 25 e 60 anos de idade e apresentando periodontite crônica, com pelo menos dois sítios com profundidade de sondagem maior ou igual a 5mm. Após anamnese e exame clínico periodontal foram feitas coletas de material da bolsa periodontal com cones de papel e da cavidade bucal por meio de bochechos. Do total de pacientes 37,50% apresentaram Staphylococcus spp. na bolsa periodontal e 61,36% na cavidade bucal, sendo que 27,27% apresentaram a bactéria nos 2 sítios. S. epidermidis foi a espécie mais prevalente para bolsa periodontal (15,9% e cavidade bucal (27,27%. Não houve diferença estatística significante quanto à presença desses microrganismos entre as faixas etárias e aumento da profundidade de sondagem. A presença de bactérias oportunistas na cavidade bucal pode representar dificuldades para a manutenção do tratamento periodontal.

  9. Evaluación del Programa Bolsa Familia en los municipios con bajo Índice de Desarrollo Humano y el cumplimiento de las condicionalidades de la salud.

    Directory of Open Access Journals (Sweden)

    Leonor Maria Pacheco SANTOS

    2011-12-01

    Full Text Available El Programa Bolsa Familia se ha evaluado en las cinco regiones de Brasil en municipios de bajo Índice de Desarrollo Humano. Se realizó análisis de documentos, entrevistas con los directores y los informantes claves, cuestionarios y grupos de discusión con las familias inscritas y no inscritas. El estudio mostró una estructura de marco regulador adecuado y en constante evolución. También evaluando estructura, los recursos humanos, las computadoras y acceso a internet no eran aptos para aplicación del programa. No había Banca en uno de los municipios y las familias se trasladaban para recibir el efectivo en el condado vecino. En términos de procesos hube problemas en registración, control social y las cuotas determinadas por el gobierno federal quedaran insuficientes para el número de familias elegibles. Los resultados mostraran excelente focalización del programa entre las familias estudiadas (99%, pero confirmaran baja cobertura. Datos administrativos habían Revista Tempus Actas de Saúde Coletiva 141 indicado que más del 80% de las familias se inscribieron, esto no se confirmó en el estudio empírico; se encontró 53% de cobertura entre las familias estudiadas, información corroborada por las declaraciones locales. Se recibieron informes sobre la retención ilegal de las tarjetas en los comercios locales como condición para la apertura de un crédito, pero la práctica era aceptada por las mujeres sin problemas. Sólo el 19% de las familias identificó la existencia de condicionalidades de salud y 7.7% reportó saber que deben llevar los niños a la clínica para sean pesados. Algunos gerentes de local, aunque considerando la importancia del programa, tenían en cuenta la transferencia de ingresos como un incentivo para la comodidad y no como un derecho ciudadano. Los resultados indican la importancia de las inversiones para la mejora de la gestión local del programa.

  10. Modelación de la volatilidad y pronóstico del índice general de la bolsa de valores de Colombia (IGBC

    Directory of Open Access Journals (Sweden)

    Edder Parody Camargo

    2014-01-01

    Full Text Available El objetivo de esta investigación es determinar ¿cuál es el modelo que permite explicar con mayor precisión el comportamiento histórico del índice general de la bolsa de valores de Colombia (IGBC, durante el periodo comprendido entre el 01 de enero de 2008 y el 31 de mayo del año 2012?, analizando dicho fenómeno desde la perspectiva teórica del Dow jons y el análisis técnico y empleando la metodología de los modelos de la familia ARCH. Se estudia la volatilidad del mercado, se comparan los modelos ARCH, GARCH, EGARCH y PARCH utilizando los criterios tradicionales de evaluación y concluyendo que el modelo EGARCH (1,1 posee la mejor capacidad para predecir. Finalmente, se identifica como futura línea de investigación, la necesidad de contractar empíricamente la pertinencia de medir la volatilidad del IGBC según las directrices fijadas por la superintendencia financiara colombiana para el cálculo del riesgo de mercado.Palabras clave: ARCH; GARCH; volatilidad; metodología; IGBC.Modelling of the volatility and forecasting the index of the general stock exchange of Colombia (IGBCAbstract This research aims to determine, what is the model that allows to explain more precisely the historical behavior of the general index of the stock exchange of Colombia (IGBC, from the period January 1 2008 to May 31-2012? Analyzing this phenomenon from the theoretical perspective of the Dow Jones and the technical analysis and using the methodology of the ARCH family models. It is studied the market volatility, the ARCH, GARCH, EGARCH and PARCH models are compared using traditional evaluation criteria and it`s concluded that the EGARCH (1, 1 model has the best ability to predict. Finally, it is identified like a future line of research, the need for empirically contracting the relevance of measuring the volatility of the IGBC under the guidelines established by the Colombian financial Superintendence for the calculation of market risk

  11. Reactor container

    International Nuclear Information System (INIS)

    A reactor container has a suppression chamber partitioned by concrete side walls, a reactor pedestal and a diaphragm floor. A plurality of partitioning walls are disposed in circumferential direction each at an interval inside the suppression chamber, so that independent chambers in a state being divided into plurality are formed inside the suppression chamber. The partition walls are formed from the bottom portion of the suppression chamber up to the diaphragm floor to isolate pool water in a divided state. Operation platforms are formed above the suppression chamber and connected to an access port. Upon conducting maintenance, inspection or repairing, a pump is disposed in the independent chamber to transfer pool water therein to one or a plurality of other independent chambers to make it vacant. (I.N.)

  12. NEUTRONIC REACTORS

    Science.gov (United States)

    Anderson, J.B.

    1960-01-01

    A reactor is described which comprises a tank, a plurality of coaxial steel sleeves in the tank, a mass of water in the tank, and wire grids in abutting relationship within a plurality of elongated parallel channels within the steel sleeves, the wire being provided with a plurality of bends in the same plane forming adjacent parallel sections between bends, and the sections of adjacent grids being normally disposed relative to each other.

  13. Fluxos decisórios na formulação das condicionalidades de saúde do programa bolsa família Decision-making fluxes related to counterpart healthcare condition's concept in the programa bolsa família

    Directory of Open Access Journals (Sweden)

    Jorginete de Jesus Damião Trevisani

    2012-06-01

    Full Text Available Os programas de transferência condicionada de renda (TCR entram na agenda pública por sua potencialidade em interferir no ciclo intergeracional de pobreza. Este artigo tem como objetivo analisar o processo de formulação das condicionalidades de saúde do Programa Bolsa Família e, secundariamente, avaliar sua interface com a trajetória das políticas de alimentação e nutrição no Brasil. Para isso, o estudo adotou como referencial analítico o modelo de análise de múltiplos fluxos, proposto por Kingdon, para quem a mudança na agenda pública acontece com a convergência entre o fluxo dos problemas, o fluxo das soluções e alternativas e o fluxo político. A trajetória desses fluxos foi recomposta por meio da análise de documentos governamentais e de relatos orais obtidos por meio de entrevistas. No momento da formulação das condicionalidades de saúde, no fluxo de problemas, havia a necessidade de mudar a estratégia de combate à desnutrição, devido às críticas ao Incentivo ao Combate às Carências Nutricionais (ICCN e à extinção do Programa de Distribuição de Estoques de Alimentos (PRODEA. No que diz respeito ao fluxo das soluções, diversas propostas de TCR estavam em curso. No fluxo político, havia a decisão de criação de uma rede de proteção social. Nesse processo, a Coordenação Geral da Política de Alimentação e Nutrição assumiu o papel de empreendedora de políticas. A reflexão sobre esse processo ajuda a compreender o papel dos serviços de saúde em um programa de caráter intersetorial.This paper discusses the formulation process of conditional cash transfer associated with healthcare conditions demanded by Brazil's Family Allowance Program, Programa Bolsa Família (PBF, and also aims to analyze the interfaces of PBF and other nutrition policies. It used the multiple streams model proposed by Kingdon, which implies moving into a new "decision agenda" from the interation of three streams

  14. Programa Bolsa Família: a interface entre a atuação profissional e o direito humano a alimentação adequada The "Bolsa Família" family grant scheme: the interface between professional practice and the human right to adequate food and nutrition

    Directory of Open Access Journals (Sweden)

    Camila Irigonhé Ramos

    2012-08-01

    Full Text Available O Direito Humano à Alimentação Adequada deve ser garantido através de políticas públicas de Segurança Alimentar e Nutricional (SAN. Nesse contexto está inserido o Programa Bolsa Família (PBF, que, além da transferência de renda, visa a garantia de acesso aos direitos sociais básicos. Este estudo objetiva analisar a operacionalização do PBF e, consequentemente, o entendimento dos profissionais de saúde a respeito do programa, enquanto eixo estruturante da política pública de SAN. Para isso, realizou-se entrevistas semiestruturadas com trabalhadores da atenção primária, envolvidos diretamente, tanto com o PBF, quanto com as famílias que recebem este beneficio. Ao final do estudo, foi possível evidenciar a importância da formação dos profissionais que atuam nessa área, pois, ao desconectar a realidade social em que os beneficiários estão inseridos, dos objetivos do programa, colabora-se para a simples mecanização dessas práticas. Nesse sentido, aponta-se que os profissionais de saúde precisam entender as proposições do programa como estratégias político-sociais, as quais, para além do alívio imediato, visam a superação dos problemas relacionados à pobreza e à fome.The Human Right to Adequate Nutrition must be ensured through the public policies included in SAN, namely the Food and Nutritional Security campaign. Besides the income transfer geared to ensuring access to basic social rights, the "Bolsa Família" Program (PBF is included in this context. This study seeks to analyze the operational aspects of the PBF and also ascertain whether or not the health professionals see the program as a core element of the SAN public policy. With this in mind, semi-structured interviews were conducted with primary healthcare workers involved directly both with the PBF and with the families who receive this benefit. By the end of the study, it was possible to perceive the importance of training health professionals who

  15. El sistema de la bolsa es útil como espaciador para la administración de los aerosoles presurizados A plastic bag is useful as spacer device for pressurized aerosol delivery

    Directory of Open Access Journals (Sweden)

    Laura Mendoza I

    2005-01-01

    Full Text Available Se ha demostrado que el depósito y efecto de los medicamentos administrados a través de los inhaladores presurizados mejora con el uso de espaciadores, pero la adherencia a estos accesorios no es buena por su costo y por su tamaño incómodo. Nuestro objetivo fue determinar si un sistema artesanal tipo reservorio, armado con una bolsa plástica unida a una boquilla de cartón, es efectivo como espaciador. Para esto, seleccionamos a 17 sujetos mayores de 16 años con espirometría con limitación ventilatoria obstructiva y respuesta espirométrica significativa a 200 µg de salbutamol en aerosol presurizado. Se les asignó aleatoriamente a dos grupos: uno con aerocámara y otro con bolsa. Con esta última se obtuvo aumento del VEF1 y de la CVF post broncodilatador de mayor magnitud que con la aerocámara, con diferencia estadística significativa. Nos parece que estos resultados validan al sistema de la bolsa como espaciador de aerosoles presurizados para el uso de los pacientesIt has been demostrated that the effect of inhaled medications is enhanced by spacer devices, but their sizes make them unpractical to carry around and they have additional cost. In order to test if a homemade cheap spacer is as effective as the commercial spacers, we tested a small plastic bag with a cardboard mouth piece. We recluted 17 patients over 16 years of age with an obstructive ventilatory limitation in spirometry with a significative response with 200 µg of albuterol. We randomized patients into two groups: one received the bronchodilator through a commercial spacer and the other through the homemade device. We observed that with the latter we obtained similar or better FEV1 and FVC increases. We conclude that the use of this cheap device can be used in patients with advantage over commercial ones

  16. Nuclear research reactors

    International Nuclear Information System (INIS)

    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.)

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    A nuclear reactor is described in which the core components, including fuel-rod assemblies, control-rod assemblies, fertile rod-assemblies, and removable shielding assemblies, are supported by a plurality of separate inlet modular units. These units are referred to as inlet module units to distinguish them from the modules of the upper internals of the reactor. The modular units are supported, each removable independently of the others, in liners in the supporting structure for the lower internals of the reactor. The core assemblies are removably supported in integral receptacles or sockets of the modular units. The liners, units, sockets and assemblies have inlet openings for entry of the fluid. The modular units are each removably mounted in the liners with fluid seals interposed between the opening in the liner and inlet module into which the fluid enters in the upper and lower portion of the liner. Each assembly is similarly mounted in a corresponding receptacle with fluid seals interposed between the openings where the fluid enters in the lower portion of the receptacle or fitting closely in these regions. As fluid flows along each core assembly a pressure drop is produced along the fluid so that the fluid which emerges from each core assembly is at a lower pressure than the fluid which enters the core assembly. However because of the seals interposed in the mountings of the units and assemblies the pressures above and below the units and assemblies are balanced and the units are held in the liners and the assemblies are held in the receptacles by their weights as they have a higher specific gravity than the fluid. The low-pressure spaces between each module and its liner and between each core assembly and its module is vented to the low-pressure regions of the vessel to assure that fluid which leaks through the seals does not accumulate and destroy the hydraulic balance

  18. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    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

  19. Do direito incondicional à condicionalidade do direito: as contrapartidas do Programa Bolsa Família Unconditional to conditional rights: counterparts in Brazil's Family Allowance Program

    Directory of Open Access Journals (Sweden)

    Giselle Lavinas Monnerat

    2007-12-01

    Full Text Available Este artigo analisa a concepção e desafios em torno da exigência de contrapartidas do Programa Bolsa Família (PBF. A obrigatoriedade de inserção de crianças e adolescentes na escola e de crianças, gestantes e nutrizes nos serviços de saúde é central no desenho do PBF e, à semelhança do que ocorre em outros países, tem sido alvo de intensa polêmica. Busca-se, assim, mapear a discussão teórica que embasa os argumentos favoráveis e contrários aos programas de transferência monetária condicionada, utilizando como estratégia metodológica a sistematização bibliográfica e estudo da legislação do PBF. A análise demonstra que, se de um lado, estão aqueles que rejeitam as contrapartidas sob alegação de que estas feririam o direito incondicional de cidadania, de outro, situam-se os que defendem as condicionalidades sob argumentos distintos. Aqui estão tanto concepções que entendem que é preciso dar algo em troca do recebimento do benefício quanto aquelas que vêem tais exigências como estratégia para favorecer o acesso aos serviços sociais e romper o ciclo da pobreza. Esta última visão está presente nos documentos oficiais do programa. Porém, na legislação complementar, a operacionalização das condicionalidades é definida de forma coercitiva, distanciando-se da concepção de inserção social.This paper analyzes the concepts and challenges of the counterpart contributions demanded by Brazil's Family Allowance Program, which requires mandatory school attendance for children and adolescents, and healthcare for children, pregnant women and breast-feeding mothers. These issues are prompting much discussion in Brazil and elsewhere in the world. This study charts theoretical aspects that underpin arguments for and against conditional cash transfer programs, through a review and systematization of the literature and a study of the related legislation. This analysis demonstrates that the opponents of counterpart

  20. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T.; Sahimi, Muhammad; Fayyaz-Najafi, Babak; Harale, Aadesh; Park, Byoung-Gi; Liu, Paul K. T.

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  1. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T. (Inventor); Sahimi, Muhammad (Inventor); Fayyaz-Najafi, Babak (Inventor); Harale, Aadesh (Inventor); Park, Byoung-Gi (Inventor); Liu, Paul K. T. (Inventor)

    2011-01-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  2. Inoculation of Lacazia loboi into the subcutaneous tissue of the hamster cheek pouch Inoculação de Lacazia loboi no tecido celular subcutâneo da bolsa jugal do hamster

    Directory of Open Access Journals (Sweden)

    Diltor Vladimir Araujo OPROMOLLA

    2000-06-01

    Full Text Available The subcutaneous tissue of the hamster cheek pouch, a site of immunologic privilege, has been used to investigate the potential infectivity of different types of parasites. It has been demonstrated that the implantation of fragments of lesions induced by the fungus Lacazia loboi, the etiologic agent of Jorge Lobo's disease, into the subcutaneous tissue of the hamster cheek pouch resulted in parasite multiplication and dissemination to satellite lymph nodes16. Here we describe the evolution of lesions induced by the inoculation of the isolated fungus into this immunologically privileged site. The morphology of the inflammatory response and fungal viability and proliferation were evaluated. Inoculation of the fungus into the cheek pouch induced histiocytic granulomas with rare lymphocytes. Although fungal cells were detected for a period of up to 180 days in these lesions, the fungi lost viability after the first day of inoculation. In contrast, when the parasite was inoculated into the footpad, non-organized histiocytic lesions were observed. Langhan's giant cells, lymphocytes and fungal particles were observed in these lesions. Fungal viability was observed up to 60 days after inoculation and non-viable parasites were present in the persistent lesions up to 180 days post-inoculation. These data indicate that the subcutaneous tissue of the hamster cheek pouch is not a suitable site for the proliferation of Lacazia loboi when the fungus isolated from human tissues is tested.O tecido celular subcutâneo da bolsa jugal do hamster, um local de privilégio imunológico, tem sido usado para a investigação da infectividade potencial de diferentes tipos de parasitas. Está demonstrado que o implante de fragmentos de lesões induzidas pelo fungo Lacazia loboi, o agente etiológico da doença de Jorge Lobo, no tecido subcutâneo da bolsa jugal do hamster resultou na multiplicação e disseminação do parasita para linfonodos satélites16. Neste trabalho

  3. Perfil dos pesquisadores com bolsa de produtividade em pesquisa do CNPq da área de saúde coletiva A profile of researchers in public health with productivity grants from the Brazilian National Research Council (CNPq)

    OpenAIRE

    Rita Barradas Barata; Moisés Goldbaum

    2003-01-01

    O artigo analisa, com base nas informações do currículo Lattes, o perfil dos pesquisadores com bolsa de produtividade em pesquisa do CNPq na área de Saúde Coletiva. A análise levou em conta a formação graduada e pós-graduada, área de atuação, produção e divulgação científica. As comparações são feitas entre as classes de pesquisadores e com dados do diretório de grupos de pesquisa. A maioria dos pesquisadores (70%) são formados em Ciências da Saúde, principalmente em Medicina, ou em Ciências ...

  4. Prospección geológica y geofísica de sulfuros en el área de Virorco-La Bolsa, provincia de San Luis

    OpenAIRE

    J. Kostadinoff; S. Delpino; E. Bjerg; A. Mogessie; A. Raniolo; Arrese, M; G. Ferracutti

    2005-01-01

    En los cuerpos máficos-ultramáficos del área de Virorco y La Bolsa, bloque central de la sierra de San Luis, se han detectado sulfuros polimetálicos en venillas y diseminados. Como herramienta de prospección geofísica se utilizó el método de autopotencial en combinación con estudios geomagnéticos. Los lentes máfico-ultramáficos están enmarcados por una caja gnéisicamigmatítica de alto grado. Una foliación milonítica de rumbo NNE y buzamiento de alto ángulo al ESE, afecta al basamento y tambié...

  5. Propuesta de implantación de un Sistema de Gestión Ambiental en una empresa de fabricación de bolsas de plástico

    OpenAIRE

    CLIMENT CANALEJAS, MAR

    2014-01-01

    La elaboración del proyecto final de carrera tiene como fin la realización del diagnóstico ambiental como punto de partida para la implantación de un Sistema de Gestión Medioambiental normalizado en una empresa de fabricación de bolsas de plástico. Además se plantearán objetivos y metas y se definirán programas ambiéntales como parte de esa implantación, concretamente, de la fase de Planificación del Sistema de Gestión Ambiental. Este estudio preliminar podrá facilitar a la empresa en el futu...

  6. Investigação do transplante heterólogo de quelóide na bolsa jugal do hamster (Mesocricetus auratus Investigation of keloid heterologous graft into hamster (Mesocricetus auratus cheek pouch

    Directory of Open Access Journals (Sweden)

    Bernardo Hochman

    2003-08-01

    Full Text Available OBJETIVO: Descrever a integração do transplante heterólogo de quelóide no subepitélio da bolsa jugal do hamster (Mesocricetus auratus. MÉTODOS: A amostragem consiste de 18 hamsters machos, não isogênicos, com 10 a 14 semanas de idade. Fragmentos de quelóide foram obtidos de cicatrizes queloideanas da região mamária de paciente adulta parda. Cada hamster foi enxertado em ambas as bolsas com fragmentos de quelóide, totalizando 36 fragmentos enxertados. Os animais foram distribuídos, em 6 grupos, para exame dos fragmentos enxertados com 5, 12, 21, 42, 84 e 168 dias. Uma avaliação macroscópica é realizada comparando a bolsa contendo o fragmento enxertado em cada período com a mesma bolsa no pós-operatório imediato, mediante a comparação de fotografias padronizadas. À microscopia, considera-se a presença de vasos sangüíneos no tecido conjuntivo do fragmento enxertado como critério de integração do mesmo. Outros eventos, como secreção de queratina, presença de infiltrados celulares e aspecto do epitélio e das fibras colágenas do quelóide, também são observados. RESULTADOS: A macroscopia revela intensa vascularização na bolsa até 12 dias de enxertia, e a presença constante de pigmentação castanho-escura nos fragmentos de quelóide enxertados. Na microscopia constata-se a integração dos fragmentos de quelóide pela presença de capilares sangüíneos no tecido conjuntivo. Observa-se, também, a presença de intenso infiltrado celular do tipo inflamatório até 12 dias, a permanência do epitélio do quelóide até 21 dias, e o aparecimento de melanócitos a partir de 42 dias. CONCLUSÃO: A bolsa jugal do hamster representa, a priori, modelo experimental para investigação do quelóide.PURPOSE: To describe the integration of keloid heterograft into hamster (Mesocricetus auratus sub-epithelium. METHODS: The sample is formed by 18 male hamsters, not isogenetic ones, aged between 10 and 14 weeks. Keloid

  7. Reactor container

    International Nuclear Information System (INIS)

    Purpose: To prevent shocks exerted on a vent head due to pool-swell caused within a pressure suppression chamber (disposed in a torus configuration around the dry well) upon loss of coolant accident in BWR type reactors. Constitution: The following relationship is established between the volume V (m3) of a dry well and the ruptured opening area A (m2) at the boundary expected upon loss of coolant accident: V >= 30340 (m) x A Then, the volume of the dry well is made larger than the ruptured open area, that is, the steam flow rate of leaking coolants upon loss of coolant accident to decrease the pressure rise in the dry well at the initial state where loss of coolant accident is resulted. Accordingly, the pressure of non-compressive gases jetted out from the lower end of the downcomer to the pool water is decreased to suppress the pool-swell. (Ikeda, J.)

  8. DETERMINACIÓN DE LAS ÁREAS DE ACTIVIDAD Y ORGANIZACIÓN DEL ESPACIO DOMÉSTICO EN UNA UNIDAD RESIDENCIAL DEL SITIO ALDEANO TEMPRANO LA BOLSA 1 (TAFÍ DEL VALLE, TUCUMÁN, REP. ARGENTINA (Identification of Activity Areas and Organization of Domestic Space in a Residential Unit of the Early Villager Site La Bolsa 1 (Tafí del Valle, Tucumán, Republic of Argentina

    Directory of Open Access Journals (Sweden)

    Julián Salazar

    2013-02-01

    Full Text Available Este trabajo está orientado a la identificación de áreas de actividad dentro de una unidad residencial ubicada en el valle de Tafí (Tucumán, Argentina, con el objetivo de aportar al conocimiento de la organización en el espacio de las actividades cotidianas desarrolladas durante el primer milenio d. C. La vivienda analizada (U14 se encuentra en el sitio arqueológico La Bolsa 1, el cual constituye un asentamiento aldeano habitado principalmente desde 200 a. C. hasta 800 d. C. Se analizaron, integral y contextualmente, los rasgos fijos y semifijos de la estructura arquitectónica, las características morfológicas, tecnológicas y funcionales del conjunto cerámico y lítico y los resultados de los análisis sedimentológicos de muestras de suelo tomadas de todos los recintos. Esta información fue complementada con vestigios materiales analizados en el marco de previas investigaciones (microvestigios vegetales, dataciones radiocarbónicas y material óseo. ENGLISH: This study analyzes the activity areas within an archaeological dwelling from the Tafí valley, with the aim of addressing the spatial organization of quotidian activities developed during the first millennium AD. The analyzed household (U14, is located in the villager archaeological site La Bolsa 1, located in the north of the Tafí valley (Tucumán, Argentina, and inhabited since 200 BC up to 800 AD. Analyses included the study of fixed and semi-fixed features of the architectural structure, the morphological, technological and functional characteristics of pottery and lithic assemblages, and soil chemistry analysis from occupational floors. This information was complemented with previously studied evidence —botanical microfossils, radiocarbon dates and animal bones.

  9. Virus de la Enfermedad Infecciosa de la Bolsa de Fabricio: Relaciones antigénicas de aislados cubanos y chilenos Infectious Bursal Disease Virus: antigenic interrelationships between

    Directory of Open Access Journals (Sweden)

    J Noda

    2005-01-01

    Full Text Available La Enfermedad Infecciosa de la Bolsa (EIB sigue afectando la industria avícola por la aparición de variantes patogénicas y antigénicas del virus, originadas en la permanente evolución del virus producto de la presión inmunológica por el uso intensivo de vacunas. La caracterización antigénica de los virus de campo resulta esencial para la aplicación de vacunas más adecuadas en el control de la enfermedad. En este trabajo se determinaron las relaciones antigénicas de aislados cubanos y chilenos, obtenidos de poblaciones de pollos vacunados con el virus de la EIB. Los aislados virales se adaptaron a cultivos celulares y se obtuvieron antisueros monoespecíficos de cada uno de ellos y de una cepa de referencia. Las relaciones se establecieron por virusneu-tralización cruzada utilizando nueve aislados cubanos (BD, BL, 35/95, 29/96, 118/96, BF2, BF8, BF9 y 70/98, tres chilenos (G1, G2 y G4 y una cepa de referencia del serotipo 1 (Lukert. Los aislados cubanos y chilenos se adaptaron eficientemente a cultivos de fibroblastos de embrión de pollo (con excepción de BF3 y G3. Además, los aislados cubanos se adaptaron a células VERO, presentando mayores títulos infectivos en fibroblastos de embrión de pollo que en esta línea celular. Los resultados de la seroneutralización cruzada mostraron entre los aislados cubanos una relación mayor a un 80% y entre éstos y la cepa de referencia mayor de un 70%, de igual modo con los aislados chilenos G1 y G4 (mayor de 77%. El aislado G2 presentó diferencias antigénicas consideradas menores con los aislados cubanos BL, 35/95 y 29/96 (­ 69%. Ninguno de los aislados mostró relaciones antigénicas inferiores al 30% con la cepa de referencia del serotipo 1, por lo tanto no corresponden a cepas variantesInfectious Bursal Disease (IBD is still affecting the poultry industry through the appearance of pathogenic and antigenic variations of the virus. This is due to its permanent evolution as a

  10. Research Nuclear Reactors

    International Nuclear Information System (INIS)

    Published in English and in French, this large report first proposes an overview of the use and history of research nuclear reactors. It discusses their definition, and presents the various types of research reactors which can be either related to nuclear power (critical mock-ups, material test reactors, safety test reactors, training reactors, prototypes), or to research (basic research, industry, health), or to specific particle physics phenomena (neutron diffraction, isotope production, neutron activation, neutron radiography, semiconductor doping). It reports the history of the French research reactors by distinguishing the first atomic pile (ZOE), and the activities and achievements during the fifties, the sixties and the seventies. It also addresses the development of instrumentation for research reactors (neutron, thermal, mechanical and fission gas release measurements). The other parts of the report concern the validation of neutronics calculations for different reactors (the EOLE water critical mock-up, the MASURCA air critical mock-up dedicated to fast neutron reactor study, the MINERVE water critical mock-up, the CALIBAN pulsed research reactor), the testing of materials under irradiation (OSIRIS reactor, laboratories associated with research reactors, the Jules Horowitz reactor and its experimental programs and related devices, irradiation of materials with ion beams), the investigation of accident situations (on the CABRI, Phebus, Silene and Jules Horowitz reactors). The last part proposes a worldwide overview of research reactors

  11. Reactor Physics Training

    International Nuclear Information System (INIS)

    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

  12. Safeguarding research reactors

    International Nuclear Information System (INIS)

    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

  13. Disputas, ajustes e acomodações na produção da agenda eleitoral: a cobertura jornalística ao Programa Bolsa Família e as eleições de 2006

    Directory of Open Access Journals (Sweden)

    Flávia Biroli

    2010-06-01

    Full Text Available Resumo: Este artigo apresenta uma análise da cobertura jornalística ao Programa Bolsa Família durante as eleições presidenciais de 2006. A pesquisa abrange um total de 166 textos que mencionaram o Programa, publicados pelos jornais O Globo, O Estado de São Paulo, Folha de São Paulo e Valor Econômico entre os dias 1º de setembro e 31 de outubro de 2006. Discutimos a dinâmica de produção da agenda eleitoral, observando as disputas, ajustes e acomodações que constituem a cobertura. A análise conjunta das vozes e dos enquadramentos presentes no material permite observar aspectos relevantes das interações entre os campos da mídia e da política no contexto em que a cobertura foi realizada. As conclusões ressaltam a baixa pluralidade do noticiário, associada a representações das eleições de 2006 e da democracia brasileira que têm como aspectos centrais a estigmatização dos eleitores de baixa renda e dos beneficiários de programas sociais.Abstract: This article presents an analysis of the news about an important social program maintained by the federal government, Programa Bolsa Família, in the period of brazilian major elections of 2006. The study is based in 166 texts published in the newspapers O Globo, O Estado de São Paulo, Folha de São Paulo e Valor Econômico between September 1st and October 31st. We discuss the production of electoral agenda, observing disputes, adjustments and acommodations that constitute news coverage. The analysis of voices and framings in the texts leads to the observation of relevant aspects of the relations between media and politics at that moment. Conclusions underline the low plurality in press coverage, connected to representations of the elections of 2006 and Brazilian democracy that include stigmatization of low income voters and beneficiaries of social programs.

  14. Prospección geológica y geofísica de sulfuros en el área de Virorco-La Bolsa, provincia de San Luis

    Directory of Open Access Journals (Sweden)

    J. Kostadinoff

    2005-09-01

    Full Text Available En los cuerpos máficos-ultramáficos del área de Virorco y La Bolsa, bloque central de la sierra de San Luis, se han detectado sulfuros polimetálicos en venillas y diseminados. Como herramienta de prospección geofísica se utilizó el método de autopotencial en combinación con estudios geomagnéticos. Los lentes máfico-ultramáficos están enmarcados por una caja gnéisicamigmatítica de alto grado. Una foliación milonítica de rumbo NNE y buzamiento de alto ángulo al ESE, afecta al basamento y también a los bordes de los cuerpos máfico-ultramáficos. Hacia el interior de estos últimos, alternan sectores que preservan las texturas granulares ígneas y una foliación buzante al oeste, con fajas de cizalla con foliación milonítica buzante al ESE. El estudio geofísico en Virorco indica una correspondencia entre los valores de autopotencial negativos (-150 mV y los máximos de magnetismo terrestre (+350 nT. En la zona de La Bolsa se realizaron dos perfiles de autopotencial, los cuales muestran un núcleo de autopotencial negativo de entre -40 y -55 mV, ligeramente alargado y buzante al ESE. Sobre el margen oriental, un valor de -90 mV constituye el núcleo de una anomalía alargada y también buzante al ESE. La disposición espacial de estas anomalías es coincidente con la orientación de la foliación milonítica. La correspondencia establecida con esta nueva herramienta de prospección, sustenta la removilización y concentración de los sulfuros primarios diseminados durante el evento de milonitización, ya planteada previamente en base a otras técnicas de estudio.

  15. Programa bolsa família e o nordeste: impactos na renda e na educação, nos anos de 2004 e 2006 Education: evidence for the Brazilian northeast, in 2004 and 2006

    Directory of Open Access Journals (Sweden)

    Daniella Medeiros Cavalcanti

    2013-04-01

    Full Text Available Este artigo tem como objetivo verificar o impacto do Programa Bolsa Família (PBF para as famílias do Nordeste brasileiro, sobre suas principais metas: o alívio imediato da pobreza/desigualdade de renda e a frequência escolar. Para tanto, utilizou os microdados da PNAD, nos anos de 2004 e 2006. Visando a expurgar possível viés de seleção apontado por Heckman et al. (1998, aplica-se a metodologia de Propensity Score Matching (PSM. Ademais, foi calculado o índice Foster-Greer-Thorbecke (FGT para verificar se há menos domicílios abaixo da linha de pobreza, bem como se a desigualdade entre os pobres diminui. Os resultados apontam para um efeito positivo na renda dos tratados, no entanto o impacto exercido sobre a frequência escolar para as famílias beneficiadas, diferentemente do que acontece com as elegíveis, é maior do que o efeito anteriormente reportado.This article aims at assessing the impact of the Bolsa Família Program (PBF on the Brazilian families residing in the Northeast region, regarding its main goals: the immediate relief of poverty/inequality of income and school attendance. For that purpose, we used data from the National Household Survey, for the 2004 and 2006 periods. Seeking to purge possible selection bias pointed out by Heckman et al. (1998, we applied the methodology of Propensity Score Matching (PSM. Furthermore, we calculated the FGT index to check if there are fewer households below the poverty line, as well as if the inequality between the poor decreases. The results indicate a positive effect on the benefited income; however, the impact exerted on the school attendance for benefited families face the eligible ones is higher than the previously reported. It has been noted that the increase of the benefit value exerts a bigger influence if compared to the coverage comprehensiveness.

  16. 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.

  17. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  18. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    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

  19. Reactor System Design

    International Nuclear Information System (INIS)

    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

  20. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kawakami, Hiroto

    1995-02-07

    A reactor container of the present invention has a structure that the reactor container is entirely at the same temperature as that at the inlet of the reactor and, a hot pool is incorporated therein, and the reactor container has is entirely at the same temperature and has substantially uniform temperature follow-up property transiently. Namely, if the temperature at the inlet of the reactor core changes, the temperature of the entire reactor container changes following this change, but no great temperature gradient is caused in the axial direction and no great heat stresses due to axial temperature distribution is caused. Occurrence of thermal stresses caused by the axial temperature distribution can be suppressed to improve the reliability of the reactor container. In addition, since the laying of the reactor inlet pipelines over the inside of the reactor is eliminated, the reactor container is made compact and the heat shielding structures above the reactor and a protection structure of container walls are simplified. Further, secondary coolants are filled to the outside of the reactor container to simplify the shieldings. The combined effects described above can improve economical property and reliability. (N.H.).

  1. Fossil nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Maurette, M.

    1976-01-01

    The discussion of fossil nuclear reactors (the Oklo phenomenon) covers the earth science background, neutron-induced isotopes and reactor operating conditions, radiation-damage studies, and reactor modeling. In conclusion possible future studies are suggested and the significance of the data obtained in past studies is summarized. (JSR)

  2. Estudos endoscópico e histológico prospectivos e sequenciais da bolsa gástrica em 130 pacientes obesos mórbidos submetidos à bypass gástrico em Y-de-Roux Prospective sequential endoscopic and histologic studies of the gastric pouch in 130 morbidly obese patients submitted to Roux-en-Y gastric bypass

    Directory of Open Access Journals (Sweden)

    Attila Csendes

    2012-12-01

    Full Text Available RACIONAL: Bypass gástrico em Y-de-Roux é a operação bariátrica mais comumente realizada. Pequena bolsa gástrica é criada, deixando uma anastomose gastrojejunal estreita, com uma alça jejunal mais comprida. Muito pouco é conhecido sobre o comportamento desta bolsa em anos após o procedimento. OBJETIVO: Determinar através de estudos prospectivos endoscópico e histológico seqüenciais o tamanho da bolsa gástrica, o diâmetro da anastomose e o comportamento da infecção por H. pylori após a operação. MÉTODOS: Em 130 pacientes submetidos ao bypass gástrico foram realizadas várias avaliações sequenciais endoscópica (até 120 meses e histológica de rotina da bolsa gástrica. RESULTADOS: Após a operação, foram realizadas em média 3,6 endoscopias por paciente. Macroscopicamente quase 95% das pequenas bolsas gástricas eram normais, e o principal achado patológico foi uma úlcera marginal. Esofagite erosiva desapareceu em 93% dos pacientes. Não houve aumento no tamanho orocaudal da bolsa durante o período de observação. Não houve dilatação do diâmetro da anastomose gastrojejunal. Perto de 54% de todos os pacientes tinham mucosa fúndica normal, enquanto 18% tinham gastrite crônica ativa, coincidente com a infecção por H. pylori. Cinco pacientes tinham metaplasia intestinal. CONCLUSÃO: Com base nesta avaliação endoscópica sequencial, não houve aumento no tamanho orocaudal da bolsa gástrica, nem do diâmetro da anastomose gastrojejunal. O comportamento do H. pylori foi inconsistente e difícil de interpretar.BACKGROUND: Roux-en-Y gastric bypass is the most common performed bariatric surgery. A small gastric pouch is created, leaving a narrow gastrojejunal anastomosis, with a long jejunal limb. Very little is known regarding the behavior of this pouch years after surgery. AIM: To determine through prospective sequential endoscopic studies the size of the gastric pouch, the diameter of the anastomosis, and the

  3. Atresia anal, fístula uretrorretal congênita, bolsa escrotal acessória e pseudo-hermafroditismo em bezerro mestiço Anal atresia, congenital urethrorectal fistula, accessory scrotum and pseudohermafroditism in a crossbred calf

    Directory of Open Access Journals (Sweden)

    Thaís Gomes Rocha

    2010-05-01

    Full Text Available Neste trabalho, é descrito o caso de um bezerro mestiço recém-nascido que apresentava atresia anal tipo 2, fístula uretrorretal congênita, bolsa escrotal bífida e pseudo-hermafroditismo masculino. O principal sinal clínico era a eliminação de fezes por meio do óstio prepucial, uma apresentação incomum em casos de fístula uretrorretal em animais machos. Apesar de o quadro de atresia anal ser relativamente comum nessa espécie, os outros defeitos congênitos encontrados são pouco frequentes.In this study, the case of a newborn calf, which presented type 2 anal atresia, congenital urethrorectal fistula, bifid scrotum and male pseudohermafroditism is described. The main clinical sign was the elimination of feces by the prepucial ostium, an unusual finding in cases of urethrorectal fistula in male animals. Although anal atresia is relatively common in bovines, the other congenital defects found in this case are uncommon.

  4. Selección de una cartera de valores mediante la aplicación de métodos multiobjetivo interactivos a datos reales de la Bolsa española.

    Directory of Open Access Journals (Sweden)

    Mariano Luque Gallego,

    2004-01-01

    Full Text Available En este trabajo aplicamos diversos métodos multiobjetivo interactivos a datos reales de la bolsa española, en concreto datos semanales del periodo 1995-2002. En nuestro modelo consideramos 5 funciones objetivo relacionadas con el deseo del decisor de maximizar la rentabilidad obtenida soportando el menor riesgo posible. Así, tratamos de maximizar la rentabilidad, minimizar la beta de la cartera como representante del riesgo sistemático, minimizar la desviación estándar y la covarianza las cuales recogen el riesgo global soportado y, por último, minimizar la varianza de los residuos como representante del riesgo específico. Tras obtener una solución mediante el método interactivo G-D-F, y tras solicitar información sobre sus preferencias al decisor, vamos cambiando de método para aprovechar las ventajas de cada uno hasta obtener una solución aceptada por el decisor.

  5. Relaciones sociedad-estado, participación ciudadana y clientelismo político en programas contra la pobreza. El caso de «bolsa familia» en Brasil

    Directory of Open Access Journals (Sweden)

    Felipe J. HEVIA

    2011-06-01

    Full Text Available Las relaciones entre los pobres y el gobierno que genera la implementación del programa Bolsa Familia pueden resumirse en dos dimensiones: 1 se privilegian «relaciones directas» sin intermediación de acción colectiva y 2 también «relaciones lejanas» en términos del tipo de interacción y comunicación entre las autoridades y los beneficiarios. Si bien existen instancias formales de control social, la operación del programa hace que la intermediación sea mínima, altamente institucional y que las organizaciones civiles tengan poco espacio para actuar representando a los beneficiarios. Estas relaciones generan bajos niveles de compra y coacción del voto, pero crean también efectos no intencionales como son el desconocimiento de la operación del programa, dificultad para defenderse de manera colectiva de abusos de poder, así como obstáculos para generar ciudadanía activa.

  6. Análise da contribuição do Programa Bolsa Família para o enfrentamento da pobreza e a autonomia dos sujeitos beneficiários

    Directory of Open Access Journals (Sweden)

    Maurício Gregianin Testa

    2013-12-01

    Full Text Available Esta pesquisa reflete sobre a contribuição do Programa Bolsa Família (PBF para o enfrentamento da pobreza e uma maior autonomia dos sujeitos beneficiários. Foram coletados dados quantitativos com 103 famílias beneficiárias, complementados com entrevistas qualitativas com profissionais e famílias. Entre as formas de privação (educação, saúde, trabalho e renda etc., a educação mostrou-se o aspecto de privação que obteve os melhores resultados na percepção das famílias na busca da autonomia. A participação em atividades de apoio social tem efeito direto na percepção de melhoria da situação da família; entretanto, a participação das famílias mostrou-se incipiente. Essas atividades contribuem para o desenvolvimento da autonomia e podem ser compreendidas como o principal mecanismo do programa para as pessoas encontrarem as "portas de saída".

  7. Nuclear reactor repairing device

    International Nuclear Information System (INIS)

    Purpose: To enable free repairing of an arbitrary position in an LMFBR reactor. Constitution: A laser light emitted from a laser oscillator installed out of a nuclear reactor is guided into a portion to be repaired in the reactor by using a reflecting mirror, thereby welding or cutting it. The guidance of the laser out of the reactor into the reactor is performed by an extension tube depending into a through hole of a rotary plug, and the guidance of the laser light into a portion to be repaired is performed by the transmitting and condensing action of the reflecting mirror. (Kamimura, M.)

  8. 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

  9. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  10. Spinning fluids reactor

    Science.gov (United States)

    Miller, Jan D; Hupka, Jan; Aranowski, Robert

    2012-11-20

    A spinning fluids reactor, includes a reactor body (24) having a circular cross-section and a fluid contactor screen (26) within the reactor body (24). The fluid contactor screen (26) having a plurality of apertures and a circular cross-section concentric with the reactor body (24) for a length thus forming an inner volume (28) bound by the fluid contactor screen (26) and an outer volume (30) bound by the reactor body (24) and the fluid contactor screen (26). A primary inlet (20) can be operatively connected to the reactor body (24) and can be configured to produce flow-through first spinning flow of a first fluid within the inner volume (28). A secondary inlet (22) can similarly be operatively connected to the reactor body (24) and can be configured to produce a second flow of a second fluid within the outer volume (30) which is optionally spinning.

  11. Percurso metodológico de análise do Programa Bolsa Família na RMS/Bahia: estudo de caso de Camaçari, Candeias e Simões Filho = The methodological pathway of the analysis of Family Scholarship (Bolsa Família in RMS/Bahia: a case study of Camaçari, Candeias e Simões Filho

    Directory of Open Access Journals (Sweden)

    Dornelles, Denise Yasodã Freitas

    2010-01-01

    Full Text Available O artigo apresenta o caminho metodológico seguido durante o percurso da investigação, apresentando os diferentes processos em que a mesma foi desenvolvida: enquadramento do estudo, constituição da amostra e trabalho de campo. A situação de entrevistas: contextos, atores, efeitos sociais e a metodologia de tratamento dos dados sobre os impactos dos Programas de Transferência de Renda, nomeadamente o Programa Bolsa Família no universo dos municípios de Camaçari, Candeias e Simões Filho, situados na Região Metropolitana da cidade de Salvador no estado da Bahia. Torna-se importante destacar que os aportes que balizaram o referencial teórico e empírico da pesquisa foram de cunho sociológico, na perspectiva de uma investigação científica permeada por um olhar característico do Serviço Social, portanto, uma pesquisa orientada e aplicada eminentemente dentro deste universo heurístico. Neste sentido, os diálogos conceituais postularam elementos do campo das políticas sociais, de estudos sobre família, pobreza, vulnerabilidade e dos estudos sobre exclusão social

  12. 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.

  13. Avaliação antropométrica e consumo alimentar em crianças menores de cinco anos residentes em um município da região do semiárido nordestino com cobertura parcial do programa bolsa família Anthropometric assessment and food intake of children younger than 5 years of age from a city in the semi-arid area of the Northeastern region of Brazil partially covered by the bolsa família program

    Directory of Open Access Journals (Sweden)

    Silvia Regina Dias Médici Saldiva

    2010-04-01

    Full Text Available OBJETIVO: Avaliar as condições de saúde e nutrição de crianças menores de cinco anos, e associar a qualidade do consumo alimentar aos beneficiários do Programa Bolsa Família de um município do semiárido brasileiro. MÉTODOS: Foram avaliadas 189 crianças, a partir de uma amostragem de 411 domicílios do município de João Câmara (RN. Foram realizadas medidas de peso e altura, e levantadas às condições socioeconômicas e determinação dos hábitos alimentares. Para o diagnóstico nutricional das crianças foram utilizados os indicadores Peso/Idade, Altura/Idade e Peso/Altura. Análises univariadas foram realizadas e modelos bivariados e multivariados de regressão logística foram construídos para testar a hipótese do estudo. RESULTADOS: O déficit de peso foi de 4,3% e o de altura de 9,9%, e o excesso de peso de 14,0%. Não foram encontradas diferenças estatísticas entre o estado nutricional de crianças beneficiárias e não beneficiárias do Programa Bolsa Família. Em ambos os grupos, os consumos de frutas, verduras e legumes foram baixos e semelhantes entre si. As crianças do programa bolsa família têm risco três vezes maior de consumir guloseimas (OR 3,06 - IC 1,35-6,95. CONCLUSÃO: Os resultados do padrão de consumo alimentar dessa população apontam para uma situação de "risco alimentar e nutricional", e exigem uma intervenção por parte dos profissionais de saúde para a promoção da alimentação saudável.OBJECTIVE: The objective of this study was to assess the health and nutritional status of children under five years of age and to associate the quality of the foods consumed with the Bolsa Família Program in a city located in the Brazilian semi-arid region. METHOD: A total of 189 children from a sample of 411 households in the city of João Câmara (RN were assessed. Weight and height were measured and socioeconomic and food habits were determined with the use of questionnaires. The nutritional status of

  14. 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...

  15. Multipurpose research reactors

    International Nuclear Information System (INIS)

    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

  16. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported.

  17. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. 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. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  18. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    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)

  19. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kanbe, Mitsuru

    1997-04-04

    An LMFBR type reactor comprises a plurality of reactor cores in a reactor container. Namely, a plurality of pot containing vessels are disposed in the reactor vessel and a plurality of reactor cores are formed in a state where an integrated-type fuel assembly is each inserted to a pot, and a coolant pipeline is connected to each of the pot containing-vessel to cool the reactor core respectively. When fuels are exchanged, the integrated-type fuel assembly is taken out together with the pot from the reactor vessel in a state where the integrated-type fuel assembly is immersed in the coolants in the pot as it is. Accordingly, coolants are supplied to each of the pot containing-vessel connected with the coolant pipeline and circulate while cooling the integrated-type fuel assembly for every pot. Then, when the fuels are exchanged, the integrated type fuel assembly is taken out to the outside of the reactor together with the pot by taking up the pot from the pot-containing vessel. Then, neutron economy is improved to thereby improve reactor power and the breeding ratio. (N.H.)

  20. Evaluación de la terapia mecánica periodontal en bolsas profundas: Respuesta clínica y bacteriológica Evaluation of periodontal mechanical therapy in deep pockets: Clinical and bacteriological response

    Directory of Open Access Journals (Sweden)

    G Bazzano

    2012-12-01

    Full Text Available Objetivos: Evaluar la composición microbiológica y los parámetros clínicos de bolsas periodontales ≥5 mm de profundidad al inicio, 1 semana, 3 y 12 meses post raspado y alisado radicular. Materiales y Métodos: Se tomaron registros clínicos y muestras de placa subgingival de 44 sitios de pacientes con diagnóstico de periodontitis crónica. Se identificaron por técnica de Reacción en Cadena de la Polimerasa (PCR patógenos putativos periodontales: Aggregatibacter actinomycetemcomitans (Aa, Porphyromonas gingivalis (Pg, Treponema denticola (Td, Tannerella forsythia (Tf y Prevotella intermedia (Pi. Los pacientes recibieron terapia mecánica periodontal y fueron reevaluados a los 7 días, 3 y 12 meses. Resultados: Luego del tratamiento, todos los parámetros clínicos (Placa Bacteriana, Hemorragia, Supuración, Profundidad al Sondaje y Nivel de Inserción Clínica se redujeron significativamente y los valores obtenidos se mantuvieron hasta los 12 meses. Al inicio, las especies bacterianas prevalentes fueron Pg, presente en 66% de los sitios, Tf (55% y Td (41%. Los sitios más profundos se relacionaron con las asociaciones Tf-Td (6.8 mm y Tf-Td-Pi (7 mm. Post terapia, el número de sitios positivos para Td, Tf y Pg se redujo significativamente. Conclusiones: El raspado y alisado radicular mejoró significativamente los parámetros clínicos y redujo la prevalencia de los patógenos periodontales Pg, Tf y Td en bolsas periodontales profundas. Los resultados obtenidos se mantuvieron hasta los 12 meses. No se detectaron mayores pérdidas de inserción clínica en el 86% de los sitios a 3 meses y en 79% a los 12 meses. Los sitios en los que el tratamiento no fue efectivo en la eliminación de patógenos a los 12 meses desarrollaron mayores profundidades de sondaje.Objectives: To evaluate the microbial composition and clinical parameters of periodontal pockets with probing depth ≥5 mm at baseline, 1 week, 3 and 12 months after scaling and root

  1. Armonización de las NIC/NIIF en las prácticas contables de entes emisores no financieros que cotizan en la Bolsa de Valores de Caracas, Venezuela

    Directory of Open Access Journals (Sweden)

    Oda Gómez

    2011-01-01

    Full Text Available Esta investigación de tipo documental y empírica tiene el propósito de analizar la armonización contable material de las Normas Internacionales de Contabilidad (nic y las Normas Internacionales de Información Financiera (niif de los entes emisores no financieros; para ello, se abordó inicialmente el proceso de aplicación de las mismas en el nivel mundial, así como el proceso correspondiente en Venezuela. Se consultó el anuario estadístico de 2007 emitido por la Bolsa de Valores de Caracas; de un total de 49 empresas que aparecen en él, veinte corresponden al sector financiero y de seguros, y veintinueve al sector no financiero; de estas últimas se obtuvieron los estados financieros auditados comparativos de los años 2007-2006 de veinticinco empresas, que fue la muestra que se analiza. El análisis de los resultados indica que para la mayoría de las unidades estudiadas, en más del 70% las prácticas de contabilidad utilizadas por las empresas objeto de estudio coinciden con las disposiciones establecidas por las nic-niif. Sin embargo, se puede observar que de los 221 atributos examinados, 48% no aplica a las empresas objeto de estudio o no aparece la información en los elementos de los estados financieros; al aplicar el índice de Jaccard son excluidos de la base de datos para determinar la similitud.

  2. MODELADO DEL PRECIO DEL CAFÉ COLOMBIANO EN LA BOLSA DE NUEVA YORK USANDO REDES NEURONALES ARTIFICIALES MODELLING OF THE COLOMBIAN COFFEE PRICE IN THE NEW YORK STOCK EXCHANGE USING ARTIFICIAL NEURAL NETWORKS

    Directory of Open Access Journals (Sweden)

    Juan David Velásquez Henao

    2007-12-01

    Full Text Available En este artículo, se modela el precio promedio mensual del café colombiano en la Bolsa de Nueva York, usando varios modelos alternativos. El modelo final seleccionado está compuesto por una componente lineal autorregresiva más una red neuronal artificial tipo perceptron multicapa con dos neuronas en la capa oculta, que permite representar la dinámica que sigue el valor esperado de la serie de precios; mientras que la dinámica de los residuales es especificada usando un proceso heterocedástico condicional autoregresivo de primer orden. Los residuales normalizados del modelo son incorrelacionados y homocedásticos, y siguen aproximadamente una distribución normal. Los resultados indican que el precio actual depende de los precios ocurridos en los últimos cuatro meses.In this paper, the monthly average price of the Colombian coffee in the New York Stock Exchange, is modelling by means of several alternative models. The preferred model is composed by a lineal autoregressive component plus a multilayer perceptron neural network with two neurons in the hidden layer, that allow us to representing the dynamic following by the expected value of the price time series; while, the dynamic of the residuals is specified by an autoregressive conditional heterocedastic model of first order. The normalized residuals of the preferred model are uncorrelated, homocedastic and are distributed following a normal distribution. The results indicate that the current price depend of the prices in the previous four months.

  3. Factores que explican la extensión de revelación de activos intangibles de los bancos que cotizan en la Bolsa de Valores de Panamá

    Directory of Open Access Journals (Sweden)

    Edila E. Herrera R.

    2013-01-01

    Full Text Available En este estudio se analiza el nivel de revelación de información voluntaria de activos intangibles; asimismo, identifica los factores que explican su divulgación por parte de los bancos que cotizan en la Bolsa de Valores de Panamá durante el periodo 2005-2009. La información es registrada en un índice que contiene 158 indicadores, distribuidos en cinco categorías: capital humano, estructural tecnológico, estructural organizativo, relacional del negocio y relacional social. Las tres hipótesis que se plantean son: H1 existe una relación positiva entre el tamaño y la extensión de revelación de información de activos intangibles; H1 existe una relación positiva entre los años de constitución y la extensión de revelación de información de activos intangibles; H1 existe una relación positiva entre el nivel de endeudamiento y la extensión de revelación de información de activos intangibles. Los resultados indican que para los bancos panameños es más importante revelar información sobre intangibles en el orden siguiente: capital relacional del negocio, relacional social, estructural organizativo, humano y estructural tecnológico. Cabe aclarar que H1 la fue aceptada excepto en la categoría capital estructural tecnológico; la H1 fue aceptada en todas sus categorías, mientras que la H1 fue rechazada.

  4. Hegemonia, consenso e coerção e os beneficiários do Programa Bolsa Família Hegemony, consensus and coercion and the beneficiaries of the Family Grant Program

    Directory of Open Access Journals (Sweden)

    Sônia Maria Ranincheski

    2013-06-01

    Full Text Available Este artigo investiga as razões da desobediência a regras impostas pelo Estado pelos beneficiários de políticas sociais, especificamente os do Programa Bolsa Família, instituído pelo Governo Federal em 2003. A investigação é feita a partir dos dados coletados em uma pesquisa qualitativa que entrevistou titulares legais de famílias que recebiam o benefício, mas que estavam em situação de descumprimento das condicionalidades. Procura compreender os elementos intrínsecos à ideologia de grupos ou indivíduos que descumprem normas sociais, mesmo sujeitos a penalidades. Problematiza a perspectiva hegemônica do Programa, baseando-se nos conceitos de hegemonia, consenso e coerção de Antonio Gramsci: o alcance e os limites das penalidades - a coerção - e o reconhecimento e a aceitação das regras - o consenso.This article investigates the reasons for disobedience of the rules imposed by the state by beneficiaries of social policies, specifically the Family Grant Program, instituted by Brazil's federal government in 2003. The investigation is based on the data collected in a qualitative study that interviewed legal heads of households who receive the benefit, but who are in a situation of non-compliance with the conditionalities. It tries to understand the elements intrinsic to the ideology of groups or individuals who do not comply with the social norms, even when subject to penalties. It analyzes the hegemonic perspective of the program, based on concepts of hegemony, consensus and coercion from Antonio Gramsci. The reach and limits of the penalties are seen as a form of coercion and the recognition and acceptance of rules as consensus.

  5. Effectiveness of the Brazilian Conditional Cash Transfer Program--Bolsa Alimentação--on the variation of linear and ponderal increment in children from northeast of Brazil.

    Science.gov (United States)

    Assis, Ana Marlúcia Oliveira; Costa, Priscila Ribas de Farias; Silva, Maria da Conceição Monteiro da; Santana, Mônica Leila Portela de; Pitangueira, Jacqueline Costa Dias; Fonseca, Nedja Silva dos Santos; Pinheiro, Sandra Maria da Conceição; Santos, Sandra Maria Chaves dos

    2014-10-03

    Objetivo: Evaluar la eficacia del programa de transferencia de ingreso brasileno - Bolsa Alimentacao (PBA) sobre la variacion media del incremento del peso e de la talla de ninos. Métodos: Cohorte de 1.847 ninos fue seguida durante 12 meses: 1.615 eran ninos PBA; 232 eran ninos no PBA. Se han registrado la pierda de 316 (14,6%) ninos durante el estudio. Se adopta el diseno casi-experimental y la estrategia antes-despues con el enfoque de eficacia para evaluar el impacto del programa sobre el estado antropometrico de los ninos. La regresion lineal multinivel fue usada en el analisis estadistico. La variacion media del incremento del crecimiento de la talla y del peso para la edad fueron los outcomes and la participacion en el programa la variable de exposicion principal. Se establecieron cuatro grupos de participacion en el programa: ninos no expuesto al programa (control interno; expuestos al programa durante 12 meses de acompanamiento, expuesto al programa solo en los ultimos 6; ninos expuestos al programa solo en los primeros 6 meses. Las medidas repetidas se obtuvieron al inicio y a los 12 meses del seguimiento. Resultados: Despues de ajustar los efectos por los factores de confusion, la exposicion al programa se asocio a una variacion media de peso por edad de 0,34 Z-score (IC = -0,44- 0,63) y talla para la edad de 0,38 Z-score (IC = 0,05-0,70) para los ninos que fueron expuestos al programa durante los 12 meses. La exposicion al programa en otros periodos de seguimiento no fue estadisticamente asociado con una variacion media de peso o la talla para la edad. Conclusiones: Transferencias directas de ingreso a la familia se asociaron con la reduccion de los deficits antropometricos en la infancia.

  6. A concepção de pobreza subjacente ao programa Bolsa Familia: rumo à construção da cidadania? (Conception of poverty underlying the Family Allowance Program: does it provide access to citizenship? Doi: 10.5212/Emancipacao.v.14i2.0008

    Directory of Open Access Journals (Sweden)

    Lucas Arcanjo Cassini

    2016-03-01

    Full Text Available Resumo: Este artigo discute a concepção de pobreza subjacente ao programa Bolsa Família nos dois governos Lula e seu continuísmo no governo Dilma. Valendose de pesquisa bibliográfica e documental, o artigo tem como objetivo verificar se esse programa, no fundamental, constitui-se em medidas compensatórias ou se traz oportunidades efetivas de acesso à cidadania. Pôde-se chegar às seguintes conclusões: na implementação do Bolsa Família, desconsidera-se a “positividade concreta” dos pobres; a pobreza não é tomada enquanto fenômeno multifacetado; o programa não contribui para que entre os pobres construam-se condições para o exercício de uma cidadania protagonista.Palavras-chave: pobreza. Programa Bolsa Família. Cidadania Abstract: This article discusses the design of poverty underlying the Family Allowance Program in two governments Lula and Dilma its continuity in government. Supported on a bibliographical and documentary research, its main purpose is to verify whether that program is essentially made up of compensatory arrangements or whether it provides real opportunities of access to citizenship. This work’s main conclusions are as follows: min the Family Allowance Program’s accomplishment, the “concrete positiveness” of the poor people is not considered; poverty isn’t faced as a multifaceted phenomenon; the program doesn’t help poor people to build conditions for the exercise of a protagonist citizenship. Keywords: poverty. Family Allowance Program. citizenship.

  7. Hamster (Mesocricetus auratus cheek pouch as an experimental model to investigate human skin and keloid heterologous graft Bolsa jugal no hamster (Mesocricetus auratus como modelo experimental de investigação de enxertos heterólogos de pele humana e quelóide

    Directory of Open Access Journals (Sweden)

    Bernardo Hochman

    2004-12-01

    Full Text Available To describe the integration process of grafts of total human skin and keloid in hamster (Mesocricetus auratus cheek pouch, whose sub-epithelium is naturally an "Immunologically Privileged Site". Fragments of human normal skin and keloid from the breast region of mulatto female patients were transplanted into the cheek pouch subepithelium in situ. Surgical procedure and grafted pouches for microscopic exam at several time points of the transplantation were standardized. The integration of grafted fragments of human skin and keloid was seen in late periods (84 days since the microscopic assessment showed the presence of blood vases within the conjunctive tissue of grafted fragments. It was also possible to see among the grafted fragments the epithelium, the appearing of early cellular infiltrated, epithelial secretion of keratin, the presence of melanocytes, and delayed changes on the aspect of collagen fibers of conjunctive tissue. Pooled results allow to define hamster cheek pouch sub-epithelium as an experimental model to investigating heterologous graft physiology of human total skin and keloid with epithelium.Descrever a integração dos enxertos de pele total humana e quelóide na bolsa jugal do hamster (Mesocricetus auratus, cujo subepitélio é, naturalmente, um "Local de Privilégio Imunológico". Foram transplantados fragmentos, de pele humana normal e de quelóide, obtidos da região mamária de pacientes pardas, no subepitélio da bolsa jugal in situ. O procedimento operatório, e de preparo das bolsas enxertadas para exame microscópico em vários períodos de transplante, foi padronizado. Verificou-se a integração dos fragmentos enxertados de pele humana e de quelóide em períodos tardios (84 dias, uma vez que a avaliação microscópica revelou a presença de vasos sangüíneos no tecido conjuntivo dos fragmentos enxertados. Foi também possível observar, nos fragmentos enxertados, o epitélio, o aparecimento de infiltrado

  8. One piece reactor removal

    International Nuclear Information System (INIS)

    Japan Research Reactor No.3 (JRR-3) was the first reactor consisting of 'Japanese-made' components alone except for fuel and heavy water. After reaching its initial critical state in September 1962, JRR-3 had been in operation for 21 years until March 1983. It was decided that the reactor be removed en-bloc in view of the work schedule, cost and management of the reactor following the removal. In the special method developed jointly by the Japanese Atomic Energy Research Institute and Shimizu Construction Co., Ltd., the reactor main unit was cut off from the building by continuous core boring, with its major components bound in the block with biological shield material (heavy concrete), and then conveyed and stored in a large waste store building constructed near the reactor building. Major work processes described in this report include the cutting off, lifting, horizontal conveyance and lowering of the reactor main unit. The removal of the JRR-3 reactor main unit was successfully carried out safely and quickly by the en-block removal method with radiation exposure dose of the workers being kept at a minimum. Thus the high performance of the en-bloc removal method was demonstrated and, in addition, valuable knowhow and other data were obtained from the work. (Nogami, K.)

  9. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2001-04-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  10. Light water reactor program

    Energy Technology Data Exchange (ETDEWEB)

    Franks, S.M.

    1994-12-31

    The US Department of Energy`s Light Water Reactor Program is outlined. The scope of the program consists of: design certification of evolutionary plants; design, development, and design certification of simplified passive plants; first-of-a-kind engineering to achieve commercial standardization; plant lifetime improvement; and advanced reactor severe accident program. These program activities of the Office of Nuclear Energy are discussed.

  11. Research reactor DHRUVA

    International Nuclear Information System (INIS)

    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 1014 n/cm2/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

  12. TRIGA research reactors

    International Nuclear Information System (INIS)

    TRIGA (Training, Research, Isotope production, General-Atomic) has become the most used research reactor in the world with 65 units operating in 24 countries. The original patent for TRIGA reactors was registered in 1958. The success of this reactor is due to its inherent level of safety that results from a prompt negative temperature coefficient. Most of the neutron moderation occurs in the nuclear fuel (UZrH) because of the presence of hydrogen atoms, so in case of an increase of fuel temperature, the neutron spectrum becomes harder and neutrons are less likely to fission uranium nuclei and as a consequence the power released decreases. This inherent level of safety has made this reactor fit for training tool in university laboratories. Some recent versions of TRIGA reactors have been designed for medicine and industrial isotope production, for neutron therapy of cancers and for providing a neutron source. (A.C.)

  13. Mirror reactor surface study

    International Nuclear Information System (INIS)

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included

  14. Iris reactor conceptual design

    Energy Technology Data Exchange (ETDEWEB)

    Carelli, M.D.; Conway, L.E.; Petrovic, B.; Paramonov, D.V. [Westinghouse Electric Comp., Pittsburgh, PA (United States); Galvin, M.; Todreas, N.E. [Massachusetts Inst. of Tech., Cambridge, MA (United States); Lombardi, C.V.; Maldari, F.; Ricotti, M.E. [Politecnico di Milano, Milan (Italy); Cinotti, L. [Ansaldo SpA, Genoa (Italy)

    2001-07-01

    IRIS (International Reactor Innovative and Secure) is a modular, integral, light water cooled, low-to-medium power (100-350 MWe) reactor which addresses the requirements defined by the US DOE for Generation IV reactors, i.e., proliferation resistance, enhanced safety, improved economics and fuel cycle sustainability. It relies on the proven technology of light water reactors and features innovative engineering, but it does not require new technology development. This paper discusses the current reference IRIS design, which features a 1000 MWt thermal core with proven 5%-enriched uranium oxide fuel and five-year long straight burn fuel cycle, integral reactor vessel housing helical tube steam generators and immersed spool pumps. Other major contributors to the high level of safety and economic attractiveness are the safety by design and optimized maintenance approaches, which allow elimination of some classes of accidents, lower capital cost, long operating cycle, and high capacity factors. (author)

  15. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ballagny, A. [Commissariat a l`Energie Atomique, Saclay (France)

    1997-08-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm{sup 3}. The OSIRIS reactor has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 2} fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU.

  16. Compact torsatron reactors

    International Nuclear Information System (INIS)

    Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

  17. 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.

  18. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    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)

  19. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1983 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, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  20. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities conducted in Reactor Engineering Division in fiscal 1975 are summarized in this report. Works in the division are closely related to the development of multi-purpose High-temperature Gas Cooled Reactor, the development of Liquid Metal Fast Breeder Reactor by Power Reactor and Nuclear Fuel Development Corporation, and engineering research of thermonuclear fusion reactor. Many achievements are described concerning 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 activities of the Committee on Reactor Physics. (auth.)

  1. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    The principles of nuclear, thermal and hydraulic performance calculations for water cooled reactors are discussed. The principles are illustrated by describing their implementation in the UKAEA PATRIARCH scheme of computer codes. This material was originally delivered as a course of lectures at the Technical University of Helsinki in Summer of 1969.

  2. Safety of research reactors

    International Nuclear Information System (INIS)

    The number of research reactors that have been constructed worldwide for civilian applications is about 651. Of the reactors constructed, 284 are currently in operation, 258 are shut down and 109 have been decommissioned. More than half of all operating research reactors worldwide are over thirty years old. During this long period of time national priorities have changed. Facility ageing, if not properly managed, has a natural degrading effect. Many research reactors face concerns with the obsolescence of equipment, lack of experimental programmes, lack of funding for operation and maintenance and loss of expertise through ageing and retirement of the staff. Other reactors of the same vintage maintain effective ageing management programmes, conduct active research programmes, develop and retain high calibre personnel and make important contributions to society. Many countries that operate research reactors neither operate nor plan to operate power reactors. In most of these countries there is a tendency not to create a formal regulatory body. A safety committee, not always independent of the operating organization, may be responsible for regulatory oversight. Even in countries with nuclear power plants, a regulatory regime differing from the one used for the power plants may exist. Concern is therefore focused on one tail of a continuous spectrum of operational performance. The IAEA has been sending missions to review the safety of research reactors in Member States since 1972. Some of the reviews have been conducted pursuant to the IAEA' functions and responsibilities regarding research reactors that are operated within the framework of Project and Supply Agreements between Member States and the IAEA. Other reviews have been conducted upon request. All these reviews are conducted following procedures for Integrated Safety Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety

  3. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  4. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1989 (April 1, 1989 - March 31, 1990). One of major Department's programs is the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Development of a high energy proton linear accelerator for the nuclear engineering including is also TRU incineration promoted. Other major tasks of the Department are various basic researches on nuclear data and group constants, theoretical methods and code development, on reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  5. Slurry reactor design studies

    Energy Technology Data Exchange (ETDEWEB)

    Fox, J.M.; Degen, B.D.; Cady, G.; Deslate, F.D.; Summers, R.L. (Bechtel Group, Inc., San Francisco, CA (USA)); Akgerman, A. (Texas A and M Univ., College Station, TX (USA)); Smith, J.M. (California Univ., Davis, CA (USA))

    1990-06-01

    The objective of these studies was to perform a realistic evaluation of the relative costs of tublar-fixed-bed and slurry reactors for methanol, mixed alcohols and Fischer-Tropsch syntheses under conditions where they would realistically be expected to operate. The slurry Fischer-Tropsch reactor was, therefore, operated at low H{sub 2}/CO ratio on gas directly from a Shell gasifier. The fixed-bed reactor was operated on 2.0 H{sub 2}/CO ratio gas after adjustment by shift and CO{sub 2} removal. Every attempt was made to give each reactor the benefit of its optimum design condition and correlations were developed to extend the models beyond the range of the experimental pilot plant data. For the methanol design, comparisons were made for a recycle plant with high methanol yield, this being the standard design condition. It is recognized that this is not necessarily the optimum application for the slurry reactor, which is being proposed for a once-through operation, coproducing methanol and power. Consideration is also given to the applicability of the slurry reactor to mixed alcohols, based on conditions provided by Lurgi for an Octamix{trademark} plant using their standard tubular-fixed reactor technology. 7 figs., 26 tabs.

  6. Test reactor technology

    International Nuclear Information System (INIS)

    The Reactor Development Program created a need for engineering testing of fuels and materials. The Engineering Test Reactors were developed around the world in response to this demand. The design of the test reactors proved to be different from that of power reactors, carrying the fuel elements closer to the threshold of failure, requiring more responsive instrumentation, more rapid control element action, and inherent self-limiting behavior under accident conditions. The design of the experimental facilities to exploit these reactors evolved a new, specialized, branch of engineering, requiring a very high-lvel scientific and engineering team, established a meticulous concern with reliability, the provision for recovery from their own failures, and detailed attention to possible interactions with the test reactors. This paper presents this technology commencing with the Materials Testing Reactor (MTR) through the Fast Flux Test Facility, some of the unique experimental facilities developed to exploit them, but discusses only cursorily the experiments performed, since sample preparation and sample analyses were, and to some extent still are, either classified or proprietary. The Nuclear Engineering literature is filled with this information

  7. Fast Breeder Reactor studies

    International Nuclear Information System (INIS)

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts

  8. Fast Breeder Reactor studies

    Energy Technology Data Exchange (ETDEWEB)

    Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

    1980-07-01

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts.

  9. Licensed operating reactors

    International Nuclear Information System (INIS)

    The Operating Units Status Report --- Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff on NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non- power reactors in the US

  10. nuclear reactor design calculations

    International Nuclear Information System (INIS)

    In this work , the sensitivity of different reactor calculation methods, and the effect of different assumptions and/or approximation are evaluated . A new concept named error map is developed to determine the relative importance of different factors affecting the accuracy of calculations. To achieve this goal a generalized, multigroup, multi dimension code UAR-DEPLETION is developed to calculate the spatial distribution of neutron flux, effective multiplication factor and the spatial composition of a reactor core for a period of time and for specified reactor operating conditions. The code also investigates the fuel management strategies and policies for the entire fuel cycle to meet the constraints of material and operating limitations

  11. Course on reactor physics

    International Nuclear Information System (INIS)

    In Germany only few students graduate in nuclear technology, therefore the NPP operating companies are forced to develop their own education and training concepts. AREVA NP has started together with the Technical University of Dresden a one-week course ''reactor physics'' that includes the know-how of the nuclear power plant construction company. The Technical University of Dresden has the training reactor AKR-2 that is retrofitted by modern digital instrumentation and control technology that allows the practical training of reactor control.

  12. PWR type reactor

    International Nuclear Information System (INIS)

    From a PWR with a primary circuit, consisting of a reactor pressure vessel, a steam generator and a reactor coolant pump, hot coolant is removed by means of an auxiliary system containing h.p. pumps for feeding water into the primary circuit and being connected with a pipe, originating at the upper part, which has got at least one isolating value. This is done by opening an outlet in a part of the auxiliary system that has got a lower pressure than the reactor vessel. Preferably a water jet pump is used for mixing with the water of the auxiliary system. (orig.)

  13. Microfluidic electrochemical reactors

    Science.gov (United States)

    Nuzzo, Ralph G.; Mitrovski, Svetlana M.

    2011-03-22

    A microfluidic electrochemical reactor includes an electrode and one or more microfluidic channels on the electrode, where the microfluidic channels are covered with a membrane containing a gas permeable polymer. The distance between the electrode and the membrane is less than 500 micrometers. The microfluidic electrochemical reactor can provide for increased reaction rates in electrochemical reactions using a gaseous reactant, as compared to conventional electrochemical cells. Microfluidic electrochemical reactors can be incorporated into devices for applications such as fuel cells, electrochemical analysis, microfluidic actuation, pH gradient formation.

  14. A Frequência Escolar e a Educação a partir do ponto de vista das Beneficiárias do Programa Bolsa Família

    Directory of Open Access Journals (Sweden)

    Feijó, Ana Paula Speck

    2015-05-01

    Full Text Available The “Programa Bolsa Família” (Family Income Program is a cash transfer policy implemented by the Brazilian federal government in 2003, which it aims to fight poverty. It benefits families with per capita income equal or inferior to R$ 140.00. The program design seeks to face the poverty by articulating actions in two periods of time. In short term, to transfer income directly to the families, acting in the reduction of the so-called absolute poverty. In long term, to fight the so-called intergenerational transmission of poverty by means of conditionality’s associated to health, and above all, education. Regarding education, it is required a minimum school attendance of 85% for children between 6 and 15 years of age, and 75% for adolescents between 16 and 17 years of age. The assumption of this understanding, which ties the transference of income to the school attendance requirement, is that children and adolescents, if entering early in the labor market, would reduce their schooling and therefore drastically reduce their chances of leaving poverty when becoming adults. This article aims to understand how the relation between school frequency and poverty output is established, according to the point of view of the very PBF beneficiary families resident in the south of Campinas municipality (SP, Brazil. The research results indicate that interviewees had no problem to fulfill the conditional education requirements, once none verbalized having had difficulty to obtain school vacancy or access for their children. Thirteen of the fifteen interviewees affirmed that their children would be in the school even if they had not been participating in the Family Allowance Program. However, the higher the children’s age, the more difficult becomes the task to fulfill the requirement, as their speech certify. Regarding the comprehension about education and the role it plays in the confrontation with poverty, the mothers express conviction that

  15. O Bolsa Família: problematizando questões centrais na política de transferência de renda no Brasil The Family Allowance Program: reflecting on core issues in Brazil's income transfer policy

    Directory of Open Access Journals (Sweden)

    Maria Ozanira da Silva e Silva

    2007-12-01

    Full Text Available O Programa Bolsa Família foi criado em 2003 com o objetivo de unificar os Programas de Transferência de Renda iniciados em nível municipal, estadual e federal desde 1995. É concebido como uma expressão do processo de desenvolvimento desses programas no Brasil. Transferência de renda é entendida enquanto uma transferência monetária direta efetuada a indivíduos ou a famílias. O pressuposto central é de que articular uma transferência de renda com políticas e programas estruturantes, principalmente no campo da educação, saúde e trabalho, direcionados a famílias pobres, pode interromper o ciclo vicioso da pobreza do presente e sua reprodução no futuro. Portanto, uma articulação entre uma transferência monetária com políticas e programas estruturantes, direcionados a famílias pobres, pode possibilitar a construção de uma política de enfrentamento à pobreza e à desigualdade social. Nesse artigo, é apresentado o desenvolvimento histórico dos Programas de Transferência de Renda, no Brasil, orientado por um esforço problematizador do significado e do alcance desses programas no âmbito das políticas sociais brasileiras, considerando suas potencialidades e limites enquanto política de inclusão social.Introduced in 2003, Brazil's Family Allowance Program was intended to unite several Income Transfer Programs run at the Municipal, State and Federal levels since 1995. Designed as an expression of the development of direct monetary transfers to families or individuals, its key assumption is that linking income transfers to poor families with structural policies and programs (mainly in the fields of education, healthcare and jobs could break through the vicious cycle of poverty in the present and halt its future replication. Linking cash transfers to structuring policies and programs for poor families might well underpin a policy combating poverty and social inequality. This paper presents a retrospective of these Income

  16. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given

  17. NEUTRONIC REACTOR FUEL COMPOSITION

    Science.gov (United States)

    Thurber, W.C.

    1961-01-10

    Uranium-aluminum alloys in which boron is homogeneously dispersed by adding it as a nickel boride are described. These compositions have particular utility as fuels for neutronic reactors, boron being present as a burnable poison.

  18. Pulsed fusion reactors

    International Nuclear Information System (INIS)

    This summer school specialized in examining specific fusion center systems. Papers on scientific feasibility are first presented: confinement of high-beta plasma, liners, plasma focus, compression and heating and the use of high power electron beams for thermonuclear reactors. As for technological feasibility, lectures were on the theta-pinch toroidal reactors, toroidal diffuse pinch, electrical engineering problems in pulsed magnetically confined reactors, neutral gas layer for heat removal, the conceptual design of a series of laser fusion power plants with ''Saturn'', implosion experiments and the problem of the targets, the high brightness lasers for plasma generation, and topping and bottoming cycles. Some problems common to pulsed reactors were examined: energy storage and transfer, thermomechanical and erosion effects in the first wall and blanket, the problems of tritium production, radiation damage and neutron activation in blankets, and the magnetic and inertial confinement

  19. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2002-04-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system.

  20. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2001-04-01

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given.

  1. Reactor Neutrino Spectra

    CERN Document Server

    Hayes, A C

    2016-01-01

    We present a review of the antineutrino spectra emitted from reactors. Knowledge of these and their associated uncertainties are crucial for neutrino oscillation studies. The spectra used to-date have been determined by either conversion of measured electron spectra to antineutrino spectra or by summing over all of the thousands of transitions that makeup the spectra using modern databases as input. The uncertainties in the subdominant corrections to beta-decay plague both methods, and we provide estimates of these uncertainties. Improving on current knowledge of the antineutrino spectra from reactors will require new experiments. Such experiments would also address the so-called reactor neutrino anomaly and the possible origin of the shoulder observed in the antineutrino spectra measured in recent high-statistics reactor neutrino experiments.

  2. Experience with Kamini reactor

    International Nuclear Information System (INIS)

    Kamini is a 233U fuelled, 30 kW(th) research reactor. It is one of the best neutron source facility with a core average flux of 1012 n/cm2/s in IGCAR used for neutron radiography of active and nonradioactive objects, activation analysis and radiation physics research. The core consists of nine plate type fuel elements with a total fuel inventory of 590 g of 233U. Two safety control plates made of cadmium are used for start up and shutdown of the reactor. Three beam tubes, two-thimble irradiation site outside reflector and one irradiation site nearer to the core constitute the testing facilities of Kamini. Kamini attained first criticality on 29th October 96 and nominal power of 30 kW in September 1997. This paper covers the design features of the reactor, irradiation facilities and their utilities and operating experience of the reactor. (author)

  3. Reactor pressure boundary materials

    International Nuclear Information System (INIS)

    With a long-term operation of nuclear power plants, the component materials are degraded under severe reactor conditions such as neutron irradiation, high temperature, high pressure and corrosive environment. It is necessary to establish the reliable and practical technologies for improving and developing the component materials and for evaluating the mechanical properties. Especially, it is very important to investigate the technologies for reactor pressure boundary materials such as reactor vessel and pipings in accordance with their critical roles. Therefore, this study was focused on developing and advancing the microstructural/micro-mechanical evaluation technologies, and on evaluating the neutron irradiation characteristics and radiation effects analysis technology of the reactor pressure boundary materials, and also on establishing a basis of nuclear material property database

  4. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2002-04-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed.

  5. New reactor type proposed

    CERN Multimedia

    2003-01-01

    "Russian scientists at the Research Institute of Nuclear Power Engineering in Moscow are hoping to develop a new reactor that will use lead and bismuth as fuel instead of uranium and plutonium" (1/2 page).

  6. Special lecture on nuclear reactor

    International Nuclear Information System (INIS)

    This book gives a special lecture on nuclear reactor, which is divided into two parts. The first part has explanation on nuclear design of nuclear reactor and analysis of core with theories of integral transports, diffusion Nodal, transports Nodal and Monte Carlo skill parallel computer and nuclear calculation and speciality of transmutation reactor. The second part deals with speciality of nuclear reactor and control with nonlinear stabilization of nuclear reactor, nonlinear control of nuclear reactor, neural network and control of nuclear reactor, control theory of observer and analysis method of Adomian.

  7. Jet-Stirred Reactors

    OpenAIRE

    Herbinet, Olivier; Guillaume, Dayma

    2013-01-01

    The jet-stirred reactor is a type of ideal continuously stirred-tank reactor which is well suited for gas phase kinetic studies. It is mainly used to study the oxidation and the pyrolysis of hydrocarbon and oxygenated fuels. These studies consist in recording the evolution of the conversion of the reactants and of the mole fractions of reaction products as a function of different parameters such as reaction temperature, residence time, pressure and composition of the inlet gas. Gas chromatogr...

  8. Generation IV reactors: economics

    International Nuclear Information System (INIS)

    The operating nuclear reactors were built over a short period: no more than 10 years and today their average age rounds 18 years. EDF (French electricity company) plans to renew its reactor park over a far longer period : 30 years from 2020 to 2050. According to EDF this objective implies 3 constraints: 1) a service life of 50 to 60 years for a significant part of the present operating reactors, 2) to be ready to built a generation 3+ unit in 2020 which infers the third constraint: 3) to launch the construction of an EPR (European pressurized reactor) prototype as soon as possible in order to have it operating in 2010. In this scheme, generation 4 reactor will benefit the feedback experience of generation 3 and will take over in 2030. Economic analysis is an important tool that has been used by the generation 4 international forum to select the likely future reactor systems. This analysis is based on 4 independent criteria: the basic construction cost, the construction time, the operation and maintenance costs and the fuel cycle cost. This analysis leads to the evaluation of the global cost of electricity generation and of the total investment required for each of the reactor system. The former defines the economic competitiveness in a de-regulated energy market while the latter is linked to the financial risk taken by the investor. It appears, within the limits of the assumptions and models used, that generation 4 reactors will be characterized by a better competitiveness and an equivalent financial risk when compared with the previous generation. (A.C.)

  9. OECD Halden reactor project

    International Nuclear Information System (INIS)

    This report summarizes the activities of the OECD Halden Reactor Project for the year 1976. The main items reported on are: a) the process supervision and control which have focused on core monitoring and control, and operator-process communication; b) the fuel performance and safety behavior which have provided data and analytical descriptions of the thermal, mechanical and chemical behavior of fuel under various operating conditions; c) the reactor operations and d) the administration and finance

  10. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    A nuclear reactor fuel element comprising a column of vibration compacted fuel which is retained in consolidated condition by a thimble shaped plug. The plug is wedged into gripping engagement with the wall of the sheath by a wedge. The wedge material has a lower coefficient of expansion than the sheath material so that at reactor operating temperature the retainer can relax sufficient to accommodate thermal expansion of the column of fuel. (author)

  11. Department of Reactor Technology

    DEFF Research Database (Denmark)

    Risø National Laboratory, Roskilde

    The general development of the Department of Reactor Technology at Risø during 1981 is presented, and the activities within the major subject fields are described in some detail. Lists of staff, publications, and computer programs are included.......The general development of the Department of Reactor Technology at Risø during 1981 is presented, and the activities within the major subject fields are described in some detail. Lists of staff, publications, and computer programs are included....

  12. Moon base reactor system

    Science.gov (United States)

    Chavez, H.; Flores, J.; Nguyen, M.; Carsen, K.

    1989-01-01

    The objective of our reactor design is to supply a lunar-based research facility with 20 MW(e). The fundamental layout of this lunar-based system includes the reactor, power conversion devices, and a radiator. The additional aim of this reactor is a longevity of 12 to 15 years. The reactor is a liquid metal fast breeder that has a breeding ratio very close to 1.0. The geometry of the core is cylindrical. The metallic fuel rods are of beryllium oxide enriched with varying degrees of uranium, with a beryllium core reflector. The liquid metal coolant chosen was natural lithium. After the liquid metal coolant leaves the reactor, it goes directly into the power conversion devices. The power conversion devices are Stirling engines. The heated coolant acts as a hot reservoir to the device. It then enters the radiator to be cooled and reenters the Stirling engine acting as a cold reservoir. The engines' operating fluid is helium, a highly conductive gas. These Stirling engines are hermetically sealed. Although natural lithium produces a lower breeding ratio, it does have a larger temperature range than sodium. It is also corrosive to steel. This is why the container material must be carefully chosen. One option is to use an expensive alloy of cerbium and zirconium. The radiator must be made of a highly conductive material whose melting point temperature is not exceeded in the reactor and whose structural strength can withstand meteor showers.

  13. BWR type nuclear reactor

    International Nuclear Information System (INIS)

    Purpose: To simplify the structure of an emergency core cooling system while suppressing the flow out of coolants upon rapture accidents in a coolant recycling device of BWR type reactors. Constitution: Recirculation pumps are located at a position higher than the reactor core in a pressure vessel, and the lower plenum is bisected vertically by a partition plate. Further, a gas-liquid separator is surrounded with a wall and the water level at the outer side of the wall is made higher than the water level in the inside of the wall. In this structure, coolants are introduced from the upper chamber in the lower plenum into the reactor core, and the steams generated in the reactor core are separated in the gas-liquid separator, whereby the separated liquid is introduced as coolants by way of the inner chamber into the lower chamber of the lower plenum and further sent by way of the outer chamber into the reactor core. Consequently, idle rotation of the recycling pumps due to the flow-in of saturated water is prevented and loss of coolants in the reactor core can also be prevented upon raptures in the pipeway and the driving section of the pump connected to the pressure vessel and in the bottom of the pressure vessel. (Horiuchi, T.)

  14. OECD Halden reactor project

    International Nuclear Information System (INIS)

    This is the nineteenth annual Report on the OECD Halden Reactor Project, describing activities at the Project during 1978, the last year of the 1976-1978 Halden Agreement. Work continued in two main fields: test fuel irradiation and fuel research, and computer-based process supervision and control. Project research on water reactor fuel focusses on various aspects of fuel behavior under normal, and off-normal transient conditions. In 1978, participating organisations continued to submit test fuel for irradiation in the Halden boiling heavy-water reactor, in instrumented test assemblies designed and manufactured by the Project. Work included analysis of the impact of fuel design and reactor operating conditions on fuel cladding behavior. Fuel performance modelling included characterization of thermal and mechanical behavior at high burn-up, of fuel failure modes, and improvement of data qualification procedures to reduce and quantify error bands on in-reactor measurements. Instrument development yielded new or improved designs for measuring rod temperature, internal pressure, axial neutron flux shape determination, and for detecting cladding defects. Work on computer-based methods of reactor supervision and control included continued development of a system for predictive core surveillance, and of special mathematical methods for core power distribution control

  15. Reactor physics and economic aspects of the CANDU reactor system

    International Nuclear Information System (INIS)

    A history of the development of the CANDU system is given along with a fairly detailed description of the 600 MW(e) CANDU reactor. Reactor physics calculation methods are described, as well as comparisons between calculated reactor physics parameters and those measured in research and power reactors. An examination of the economics of CANDU in the Ontario Hydro system and a comparison between fossil fuelled and light water reactors is presented. Some physics, economics and resources aspects are given for both low enriched uranium and thorium-fuelled CANDU reactors. Finally the RβD program in Advanced Fuel Cycles is briefly described

  16. Reactor Safety Planning for Prometheus Project, for Naval Reactors Information

    Energy Technology Data Exchange (ETDEWEB)

    P. Delmolino

    2005-05-06

    The purpose of this letter is to submit to Naval Reactors the initial plan for the Prometheus project Reactor Safety work. The Prometheus project is currently developing plans for cold physics experiments and reactor prototype tests. These tests and facilities may require safety analysis and siting support. In addition to the ground facilities, the flight reactor units will require unique analyses to evaluate the risk to the public from normal operations and credible accident conditions. This letter outlines major safety documents that will be submitted with estimated deliverable dates. Included in this planning is the reactor servicing documentation and shipping analysis that will be submitted to Naval Reactors.

  17. Fast breeder reactor research

    International Nuclear Information System (INIS)

    Full text: The meeting was attended by 15 participants from seven countries and two international organizations. The Eighth Annual Meeting of the International Working Group on Fast Reactors (IWGFR) was attended by representatives from France, Fed. Rep. Germany, Italy, Japan, United Kingdom, Union of Soviet Socialist Republics and the United States of America - countries that have made significant progress in developing the technology and physics of sodium cooled fast reactors and have extensive national programmes in this field - as well as by representatives of the Commission of the European Communities and the IAEA. The design of fast-reactor power plants is a more difficult task than developing facilities with thermal reactors. Different reactor kinetics and dynamics, a hard neutron spectrum, larger integral doses of fuel and structural material irradiation, higher core temperatures, the use of an essentially novel coolant, and, as a result of all these factors, the additional reliability and safety requirements that are imposed on the planning and operation of sodium cooled fast reactors - all these factors pose problems that can be solved comprehensively only by countries with a high level of scientific and technical development. The exchange of experience between these countries and their combined efforts in solving the fundamental problems that arise in planning, constructing and operating fast reactors are promoting technical progress and reducing the relative expenditure required for various studies on developing and introducing commercial fast reactors. For this reason, the meeting concentrated on reviewing and discussing national fast reactor programmes. The situation with regard to planning, constructing and operating fast experimental and demonstration reactors in the countries concerned, the experience accumulated in operating them, the difficulties arising during operation and ways of over-coming them, the search for optimal designs for the power

  18. BR2 Reactor: Introduction

    International Nuclear Information System (INIS)

    The irradiations in the BR2 reactor are in collaboration with or at the request of third parties such as the European Commission, the IAEA, research centres and utilities, reactor vendors or fuel manufacturers. The reactor also contributes significantly to the production of radioisotopes for medical and industrial applications, to neutron silicon doping for the semiconductor industry and to scientific irradiations for universities. Along the ongoing programmes on fuel and materials development, several new irradiation devices are in use or in design. Amongst others a loop providing enhanced cooling for novel materials testing reactor fuel, a device for high temperature gas cooled fuel as well as a rig for the irradiation of metallurgical samples in a Pb-Bi environment. A full scale 3-D heterogeneous model of BR2 is available. The model describes the real hyperbolic arrangement of the reactor and includes the detailed 3-D space dependent distribution of the isotopic fuel depletion in the fuel elements. The model is validated on the reactivity measurements of several tens of BR2 operation cycles. The accurate calculations of the axial and radial distributions of the poisoning of the beryllium matrix by 3He, 6Li and 3T are verified on the measured reactivity losses used to predict the reactivity behavior for the coming decades. The model calculates the main functionals in reactor physics like: conventional thermal and equivalent fission neutron fluxes, number of displacements per atom, fission rate, thermal power characteristics as heat flux and linear power density, neutron/gamma heating, determination of the fission energy deposited in fuel plates/rods, neutron multiplication factor and fuel burn-up. For each reactor irradiation project, a detailed geometry model of the experimental device and of its neighborhood is developed. Neutron fluxes are predicted within approximately 10 percent in comparison with the dosimetry measurements. Fission rate, heat flux and

  19. Scaleable, High Efficiency Microchannel Sabatier Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — A Microchannel Sabatier Reactor System (MSRS) consisting of cross connected arrays of isothermal or graded temperature reactors is proposed. The reactor array...

  20. Estudo físico e físico-químico de diferentes filmes de bolsas de sangue visando a segurança frente ao processamento hemoterapêutico Physical and physicochemical study of different blood bag films in respect to safety during hemotherapeutic processing

    Directory of Open Access Journals (Sweden)

    Armando V. Verceze

    2006-06-01

    Full Text Available Muitas rupturas de bolsas de sangue no processamento e armazenamento levam à abertura do sistema e à perda do conteúdo, com prejuízos econômicos, riscos biológicos e aspectos sociais pela doação voluntária (dados levantados junto a serviços de hemoterapia pelo autor. O propósito foi avaliar "in vitro", por meio de teste cego, diferentes filmes de bolsas de poli (cloreto de vinila-PVC para coleta de sangue disponíveis no mercado nacional, sendo três produzidas no Brasil e duas no exterior, utilizando parâmetros físico e físico-químico. Estas bolsas possuem características especiais como: composição química conforme a Farmacopéia Européia, flexibilidade para enchimento com sangue e resistência a diferentes condições de temperatura e tempo de centrifugação. A fabricação das bolsas ocorre por soldagem por radiofreqüência. A área definida de solda ou costura entre os filmes tem sido apontada como o principal ponto vulnerável a micro-rupturas, durante a centrifugação. Os parâmetros estudados foram: absorção no infravermelho (IR-FT e análise mecânica de tensão-elongação/ruptura, realizados no corpo da bolsa e na solda ou costura. Os espectros (IR-FT foram semelhantes, porém diferentes resultados foram observados na análise mecânica quando comparados entre si. Evidenciamos dois grupos de comportamentos quanto à concentração de grupamentos químicos no infravermelho. Não obtivemos informações da concentração química, do processamento e possíveis diferenças de técnicas empregadas. Os resultados nos permitem concluir que existem diferenças entre as cinco bolsas. Estas propriedades são tão importantes quanto as características biológicas ou bioquímicas. Não encontramos na literatura valores que possam caracterizar qual bolsa seria mais ou menos eficiente frente ao processamento ao qual são submetidas em toda sua cadeia desde a indústria até a transfusão.Many ruptures of blood bags used

  1. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Shimizu, Takeshi; Iida, Masaaki; Moriki, Yasuyuki

    1994-10-18

    A reactor core is divided into a plurality of coolants flowrate regions, and electromagnetic pumps exclusively used for each of the flowrate regions are disposed to distribute coolants flowrates in the reactor core. Further, the flowrate of each of the electromagnetic pumps is automatically controlled depending on signals from a temperature detector disposed at the exit of the reactor core, so that the flowrate of the region can be controlled optimally depending on the burning of reactor core fuels. Then, the electromagnetic pumps disposed for every divided region are controlled respectively, so that the coolants flowrate distribution suitable to each of the regions can be attained. Margin for fuel design is decreased, fuels are used effectively, as well as an operation efficiency can be improved. Moreover, since the electromagnetic pump has less flow resistance compared with a mechanical type pump, and flow resistance of the reactor core flowrate control mechanism is eliminated, greater circulating flowrate can be ensured after occurrence of accident in a natural convection using a buoyancy of coolants utilizable for after-heat removal as a driving force. (N.H.).

  2. Reactor coolant cleanup facility

    International Nuclear Information System (INIS)

    A depressurization device is disposed in pipelines upstream of recycling pumps of a reactor coolant cleanup facility to reduce a pressure between the pressurization device and the recycling pump at the downstream, thereby enabling high pressure coolant injection from other systems by way of the recycling pumps. Upon emergency, the recycling pumps of the coolant cleanup facility can be used in common to an emergency reactor core cooling facility and a reactor shutdown facility. Since existent pumps of the emergency reactor core cooling facility and the reactor shutdown facility which are usually in a stand-by state can be removed, operation confirmation test and maintenance for equipments in both of facilities can be saved, so that maintenance and reliability of the plant are improved and burdens on operators can also be mitigated. Moreover, low pressure design can be adopted for a non-regenerative heat exchanger and recycling coolant pumps, which enables to improve the reliability and economical property due to reduction of possibility of leakage. (N.H.)

  3. EBT reactor analysis

    International Nuclear Information System (INIS)

    This report summarizes the results of a recent ELMO Bumpy Torus (EBT) reactor study that includes ring and core plasma properties with consistent treatment of coupled ring-core stability criteria and power balance requirements. The principal finding is that constraints imposed by these coupling and other physics and technology considerations permit a broad operating window for reactor design optimization. Within this operating window, physics and engineering systems analysis and cost sensitivity studies indicate that reactors with approx. 6 to 10%, P approx. 1200 to 1700 MW(e), wall loading approx. 1.0 to 2.5 MW/m2, and recirculating power fraction (including ring-sustaining power and all other reactors auxiliaries) approx. 10 to 15% are possible. A number of concept improvements are also proposed that are found to offer the potential for further improvement of the reactor size and parameters. These include, but are not limited to, the use of: (1) supplementary coils or noncircular mirror coils to improve magnetic geometry and reduce size, (2) energetic ion rings to improve ring power requirements, (3) positive potential to enhance confinement and reduce size, and (4) profile control to improve stability and overall fusion power density

  4. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    From Zoe, the first nuclear reactor, till the current EPR, the French nuclear industry has always advanced by profiting from the feedback from dozens of years of experience and operations, in particular by drawing lessons from the most significant events in its history, such as the Fukushima accident. The new generations of reactors must improve safety and economic performance so that the industry maintain its legitimacy and its share in the production of electricity. This article draws the history of nuclear power in France, gives a brief description of the pressurized water reactor design, lists the technical features of the different versions of PWR that operate in France and compares them with other types of reactors. The feedback experience concerning safety, learnt from the major nuclear accidents Three Miles Island (1979), Chernobyl (1986) and Fukushima (2011) is also detailed. Today there are 26 third generation reactors being built in the world: 4 EPR (1 in Finland, 1 in France and 2 in China); 2 VVER-1200 in Russia, 8 AP-1000 (4 in China and 4 in the Usa), 8 APR-1400 (4 in Korea and 4 in UAE), and 4 ABWR (2 in Japan and 2 in Taiwan)

  5. Reactor Structural Materials: Reactor Pressure Vessel Steels

    Energy Technology Data Exchange (ETDEWEB)

    Chaouadi, R

    2000-07-01

    The objectives of SCK-CEN's R and D programme on Rector Pressure Vessel (RPV) Steels are:(1) to complete the fracture toughness data bank of various reactor pressure vessel steels by using precracked Charpy specimens that were tested statically as well as dynamically; (2) to implement the enhanced surveillance approach in a user-friendly software; (3) to improve the existing reconstitution technology by reducing the input energy (short cycle welding) and modifying the stud geometry. Progress and achievements in 1999 are reported.

  6. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    The Ohio State University research reactor (OSURR) is undergoing improvements in its research and educational capabilities. A computer-based digital data acquisition system, including a reactor system mimic, will be installed as part of these improvements. The system will monitor the reactor system parameters available to the reactor operator either in digital parameters available to the reactor operator either in digital or analog form. The system includes two computers. All the signals are sent to computer 1, which processes the data and sends the data through a serial port to computer 2 with a video graphics array VGA monitor, which is utilized to display the mimic system of the reactor

  7. Methanation assembly using multiple reactors

    Science.gov (United States)

    Jahnke, Fred C.; Parab, Sanjay C.

    2007-07-24

    A methanation assembly for use with a water supply and a gas supply containing gas to be methanated in which a reactor assembly has a plurality of methanation reactors each for methanating gas input to the assembly and a gas delivery and cooling assembly adapted to deliver gas from the gas supply to each of said methanation reactors and to combine water from the water supply with the output of each methanation reactor being conveyed to a next methanation reactor and carry the mixture to such next methanation reactor.

  8. MINT research reactor safety program

    Energy Technology Data Exchange (ETDEWEB)

    Mohamad Idris bin Taib [Division of Special Project, Malaysian Institute for Nuclear Technology Research (MINT), Bangi (Malaysia)

    2000-11-01

    Malaysian Institute for Nuclear Technology Research (MINT) Research Reactor Safety Program has been done along with Reactor Power Upgrading Project, Reactor Safety Upgrading Project and Development of Expert System for On-Line Nuclear Process Control Project. From 1993 up to date, Neutronic and Thermal-hydraulics analysis, Probabilistic Safety Assessment as well as installation of New 2 MW Secondary Cooling System were done. Installations of New Reactor Building Ventilation System, Reactor Monitoring System, Updating of Safety Analysis Report and Upgrading Primary Cooling System are in progress. For future activities, Reactor Modeling will be included to add present activities. (author)

  9. Thermionic Reactor Design Studies

    Energy Technology Data Exchange (ETDEWEB)

    Schock, Alfred

    1994-08-01

    Paper presented at the 29th IECEC in Monterey, CA in August 1994. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their (thermionic reactor) performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling.

  10. International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    An international design team comprised of members from Canada, Europe, Japan, the Soviet Union, and the United States of America, are designing an experimental fusion test reactor. The engineering and testing objectives of this International Thermonuclear Experimental Reactor (ITER) are to validate the design and to demonstrate controlled ignition, extended burn of a deuterium and tritium plasma, and achieve steady state using technology expected to be available by 1990. The concept maximizes flexibility while allowing for a variety of plasma configurations and operating scenarios. During physics phase operation, the machine produces a 22 MA plasma current. In the technology phase, the machine can be reconfigured with a thicker shield and a breeding blanket to operate with an 18 MA plasma current at a major radius of 5.5 meters. Canada's involvement in the areas of safety, facility design, reactor configuration and maintenance builds on our internationally recognized design and operational expertise in developing tritium processes and CANDU related technologies

  11. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  12. Licensed operating reactors

    International Nuclear Information System (INIS)

    THE OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US

  13. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  14. Reactor safety equipments

    International Nuclear Information System (INIS)

    Purpose: To positively recover radioactive substances discharged in a dry well at the time of failure of a reactor. Constitution: In addition to the emergency gas treating system fitted to a reactor building, a purification system connected through a pipeline to the dry well is arranged in the reactor building. This purification system is connected through pipes fitted to the dry well to forced circulation device, heat exchanger, and purification device. The atmosphere of high pressure steam gases in the dry well is derived to the heat exchanger for cooling, and then radioactive substances which are contained in the gases are removed by filter sets charged with the HEPA filters and the HECA filters. At last, there gases are returned to dry well by circulation pump, repeat this process. (Kamimura, M.)

  15. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  16. Welding and reactor safety

    International Nuclear Information System (INIS)

    The high safety requirements which must be demanded of the quality of the welded joints in reactor technique have so far not been fulfilled in all cases. The errors occuring have caused considerable loss of availability and high material costs. They were not, however, so serious that one need have feared any immediate danger to the personnel or to the environment. The safety devices of reactor plants were only called upon in a few cases and to these they responded perfectly. The intensive efforts to complete and improve the specifications are to contribute to that in future, the reactor plants can be counted even more so as one of the safest technical plants ever. (orig./LH)

  17. Backfitting swimming pool reactors

    International Nuclear Information System (INIS)

    Calculations based on measurements in a critical assembly, and experiments to disclose fuel element surface temperatures in case of accidents like stopping of primary coolant flow during full power operation, have shown that the power of the swimming pool type research reactor FRG-2 (15 MW, operating since 1967) might be raised to 21 MW within the present rules of science and technology, without major alterations of the pool buildings and the cooling systems. A backfitting program is carried through to adjust the reactor control systems of FRG-2 and FRG-1 (5 MW, housed in the same reactor hall) to the present safety rules and recommendations, to ensure FRG-2 operation at 21 MW for the next decade. (author)

  18. Reactor operation experience

    International Nuclear Information System (INIS)

    Since the TRIGA Users Conference in Helsinki 1970 the TRIGA reactor Vienna was in operation without any larger undesired shutdown. The integrated thermal power production by August 15 1972 accumulated to 110 MWd. The TRIGA reactor is manly used for training of students, for scientific courses and research work. Cooperation with industry increased in the last two years either in form of research or in performing training courses. Close cooperation is also maintained with the IAEA, samples are irradiated and courses on various fields are arranged. Maintenance work was performed on the heat exchanger and to replace the shim rod magnet. With the view on the future power upgrading nine fuel elements type 110 have been ordered recently. Experiments, performed currently on the reactor are presented in details

  19. The MNSR reactor

    International Nuclear Information System (INIS)

    This tank-in-pool reactor is based on the same design concept as the Canadian Slowpoke. The core is a right circular cylinder, 24 cm diameter by 25 cm long, containing 411 fuel pin positions. The pins are HEU-Aluminium alloy, 0.5 cm in diameter. Critical mass is about 900 g. The reactor has a single cadmium control rod. The back-up shutdown system is the insertion of a cadmium capsule in a core position. Excess reactivity is limited to 3.5mk. In both the MNSR and Slowpoke, the insertion of the maximum excess reactivity results in a power transient limited by the coolant/moderator temperature to safe values, independent of any operator action. This reactor is used primarily in training and neutron activation analysis. Up to 64 elements have been analyzed in a great variety of different disciplines. (author)

  20. Nuclear Rocket Engine Reactor

    CERN Document Server

    Lanin, Anatoly

    2013-01-01

    The development of a nuclear rocket engine reactor (NRER ) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

  1. Fusion reactor materials

    International Nuclear Information System (INIS)

    This is the fifteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; Special purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the U.S. Department of Energy. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

  2. Safety systems of heavy water reactors and small power reactors

    International Nuclear Information System (INIS)

    After introductional descriptions of heavy water reactors and natural circulation boiling water reactors the safety philosophy and safety systems like ECCS, residual heat removal, protection systems etc., are described. (RW)

  3. AREVA's nuclear reactors portfolio

    International Nuclear Information System (INIS)

    A reasonable assumption for the estimated new build market for the next 25 years is over 340 GWe net. The number of prospect countries is growing almost each day. To address this new build market, AREVA is developing a comprehensive portfolio of reactors intended to meet a wide range of power requirements and of technology choices. The EPR reactor is the flagship of the fleet. Intended for large power requirements, the four first EPRs are being built in Finland, France and China. Other countries and customers are in view, citing just two examples: the Usa where the U.S. EPR has been selected as the technology of choice by several U.S utilities; and the United Kingdom where the Generic Design Acceptance process of the EPR design submitted by AREVA and EDF is well under way, and where there is a strong will to have a plant on line in 2017. For medium power ranges, the AREVA portfolio includes a boiling water reactor and a pressurized water reactor which both offer all of the advantages of an advanced plant design, with excellent safety performance and competitive power generation cost: -) KERENA (1250+ MWe), developed in collaboration with several European utilities, and in particular with Eon; -) ATMEA 1 (1100+ MWe), a 3-loop evolutionary PWR which is being developed by AREVA and Mitsubishi. AREVA is also preparing the future and is deeply involved into Gen IV concepts. It has developed the ANTARES modular HTR reactor (pre-conceptual design completed) and is building upon its vast Sodium Fast Reactor experience to take part into the development of the next prototype. (author)

  4. Oscillatory flow chemical reactors

    Directory of Open Access Journals (Sweden)

    Slavnić Danijela S.

    2014-01-01

    Full Text Available Global market competition, increase in energy and other production costs, demands for high quality products and reduction of waste are forcing pharmaceutical, fine chemicals and biochemical industries, to search for radical solutions. One of the most effective ways to improve the overall production (cost reduction and better control of reactions is a transition from batch to continuous processes. However, the reactions of interests for the mentioned industry sectors are often slow, thus continuous tubular reactors would be impractically long for flow regimes which provide sufficient heat and mass transfer and narrow residence time distribution. The oscillatory flow reactors (OFR are newer type of tube reactors which can offer solution by providing continuous operation with approximately plug flow pattern, low shear stress rates and enhanced mass and heat transfer. These benefits are the result of very good mixing in OFR achieved by vortex generation. OFR consists of cylindrical tube containing equally spaced orifice baffles. Fluid oscillations are superimposed on a net (laminar flow. Eddies are generated when oscillating fluid collides with baffles and passes through orifices. Generation and propagation of vortices create uniform mixing in each reactor cavity (between baffles, providing an overall flow pattern which is close to plug flow. Oscillations can be created by direct action of a piston or a diaphragm on fluid (or alternatively on baffles. This article provides an overview of oscillatory flow reactor technology, its operating principles and basic design and scale - up characteristics. Further, the article reviews the key research findings in heat and mass transfer, shear stress, residence time distribution in OFR, presenting their advantages over the conventional reactors. Finally, relevant process intensification examples from pharmaceutical, polymer and biofuels industries are presented.

  5. Microorganismos inusuales en surcos y bolsas periodontales

    Directory of Open Access Journals (Sweden)

    Carlos Cruz

    2006-03-01

    Full Text Available Introducción: Los microorganismos de la familia Enterobacteriaceae, los bacilos Gram negativos no fermentadores y ciertas especies de Candida se han considerado como inusuales en quienes sufren enfermedad periodontal, y en ellos el tratamiento mecánico o antimicrobiano puede ser poco efectivo para resolver o controlar la progresión de la enfermedad. Objetivos: Analizar los perfiles microbiológicos en individuos sanos y en pacientes con diagnóstico de periodontitis crónica y periodontitis agresiva, determinar la frecuencia de los microorganismos inusuales y las posibles asociaciones con algunos microorganismos periodontopáticos en la base de datos del laboratorio de microbiología oral y periodontal en Cali. Materiales y métodos: Se estudiaron los informes microbiológicos de 356 pacientes en un período de 41 meses. Las variables analizadas fueron: diagnóstico periodontal, recuento total de colonias, porcentaje de aislamiento de diez microorganismos periodontopáticos y de otros inusuales como miembros de la familia Enterobacteriaceae, bacilos Gram negativos no fermentadores y levaduras. Resultados: Se analizaron 202 (56.7% informes de pacientes con periodontitis crónica, 139 (39.1% de periodontitis agresiva y 15 (4.2% de individuos periodontalmente sanos. La presencia de microorganismos inusuales de tipo entérico fue 36% y la prevalencia de levaduras 7% en las personas con periodontitis. No se encontraron diferencias significantes entre los tres diagnósticos clínicos con respecto a la presencia de microorganismos entéricos y levaduras. La mayor prevalencia de organismos entéricos correspondió a los géneros Klebsiella, Enterobacter y a bacilos Gram negativos no fermentadores. Se encontraron asociaciones estadísticamente significativas entre la presencia o ausencia de microorganismos infrecuentes con la de algunos microorganismos periodontopáticos en los individuos con enfermedad periodontal. Discusión y conclusiones: La microbiota inusuales de los pacientes incluidos en este estudio presentó una mayor proporción de bacilos Gram negativos entéricos. Las bacterias entéricas encontradas se caracterizan por ser agentes oportunistas para el hombre. Se requieren más estudios para determinar el papel que los microorganismos inusuales pueden tener en la patogénesis y/o progresión de la enfermedad periodontal.

  6. Microorganismos inusuales en surcos y bolsas periodontales.

    Directory of Open Access Journals (Sweden)

    Marisol Betancourth

    2009-11-01

    Full Text Available Introducción: Los microorganismos de la familia Enterobacteriaceae, los bacilos Gram negativos no fermentadores y ciertas especies de Candida se han considerado como inusuales en quienes sufren enfermedad periodontal, y en ellos el tratamiento mecánico o antimicrobiano puede ser poco efectivo para resolver o controlar la progresión de la enfermedad. Objetivos: Analizar los perfiles microbiológicos en individuos sanos y en pacientes con diagnóstico de periodontitis crónica y periodontitis agresiva, determinar la frecuencia de los microorganismos inusuales y las posibles asociaciones con algunos microorganismos periodontopáticos en la base de datos del laboratorio de microbiología oral y periodontal en Cali. Materiales y métodos: Se estudiaron los informes microbiológicos de 356 pacientes en un período de 41 meses. Las variables analizadas fueron: diagnóstico periodontal, recuento total de colonias, porcentaje de aislamiento de diez microorganismos periodontopáticos y de otros inusuales como miembros de la familia Enterobacteriaceae, bacilos Gram negativos no fermentadores y levaduras. Resultados: Se analizaron 202 (56.7% informes de pacientes con periodontitis crónica, 139 (39.1% de periodontitis agresiva y 15 (4.2% de individuos periodontalmente sanos. La presencia de microorganismos inusuales de tipo entérico fue 36% y la prevalencia de levaduras 7% en las personas con periodontitis. No se encontraron diferencias significantes entre los tres diagnósticos clínicos con respecto a la presencia de microorganismos entéricos y levaduras. La mayor prevalencia de organismos entéricos correspondió a los géneros Klebsiella, Enterobacter y a bacilos Gram negativos no fermentadores. Se encontraron asociaciones estadísticamente significativas entre la presencia o ausencia de microorganismos infrecuentes con la de algunos microorganismos periodontopáticos en los individuos con enfermedad periodontal. Discusión y conclusiones: La microbiota inusuales de los pacientes incluidos en este estudio presentó una mayor proporción de bacilos Gram negativos entéricos. Las bacterias entéricas encontradas se caracterizan por ser agentes oportunistas para el hombre. Se requieren más estudios para determinar el papel que los microorganismos inusuales pueden tener en la patogénesis y/o progresión de la enfermedad periodontal.

  7. Microorganismos inusuales en surcos y bolsas periodontales

    OpenAIRE

    Marisol Betancourth; Roger Mauricio Arce; Javier Botero; Adriana Jaramillo; Carlos Cruz; Adolfo Contreras

    2006-01-01

    Introducción: Los microorganismos de la familia Enterobacteriaceae, los bacilos Gram negativos no fermentadores y ciertas especies de Candida se han considerado como inusuales en quienes sufren enfermedad periodontal, y en ellos el tratamiento mecánico o antimicrobiano puede ser poco efectivo para resolver o controlar la progresión de la enfermedad. Objetivos: Analizar los perfiles microbiológicos en individuos sanos y en pacientes con diagnóstico de periodontitis crónica y periodontitis agre...

  8. Reactor Materials Research

    International Nuclear Information System (INIS)

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel

  9. Nuclear reactor simulator

    International Nuclear Information System (INIS)

    The Nuclear Reactor Simulator was projected to help the basic training in the formation of the Nuclear Power Plants operators. It gives the trainee the opportunity to see the nuclear reactor dynamics. It's specially indicated to be used as the support tool to NPPT (Nuclear Power Preparatory Training) from NUS Corporation. The software was developed to Intel platform (80 x 86, Pentium and compatible ones) working under the Windows operational system from Microsoft. The program language used in development was Object Pascal and the compiler used was Delphi from Borland. During the development, computer algorithms were used, based in numeric methods, to the resolution of the differential equations involved in the process. (author)

  10. Diagnostics for hybrid reactors

    International Nuclear Information System (INIS)

    The Hybrid Reactor(HR) can be considered an attractive actinide-burner or a fusion assisted transmutation for destruction of transuranic(TRU) nuclear waste. The hybrid reactor has two important subsystems: the tokamak neutron source and the blanket which includes a fuel zone where the TRU are placed and a tritium breeding zone. The diagnostic system for a HR must be as simple and robust as possible to monitor and control the plasma scenario, guarantee the protection of the machine and monitor the transmutation.

  11. Small mirror fusion reactors

    International Nuclear Information System (INIS)

    Basic requirements for the pilot plants are that they produce a net product and that they have a potential for commercial upgrade. We have investigated a small standard mirror fusion-fission hybrid, a two-component tandem mirror hybrid, and two versions of a field-reversed mirror fusion reactor--one a steady state, single cell reactor with a neutral beam-sustained plasma, the other a moving ring field-reversed mirror where the plasma passes through a reaction chamber with no energy addition

  12. Reactor neutron dosimetry

    International Nuclear Information System (INIS)

    An analysis of requirements and possibilities for experimental neutron spectrum determination during the reactor pressure vessel surveil lance programme is given. Fast neutron spectrum and neutron dose rate were measured in the Fast neutron irradiation facility of our TRIGA reactor. It was shown that the facility can be used for calibration of neutron dosimeters and for irradiation of samples sensitive to neutron radiation. The investigation of the unfolding algorithm ITER was continued. Based on this investigations are two specialized unfolding program packages ITERAD and ITERGS written this year. They are able to unfold data from activation detectors and NaI(T1) gamma spectrometer respectively

  13. Perspectives on reactor safety

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  14. Perspectives on reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  15. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    A nuclear reactor construction comprising a reactor core submerged in a pool of liquid metal coolant in a primary vessel which is suspended from the roof structure of a containment vault. Control rods supported from the roof structure are insertable in the core which is carried on a support structure from the wall of the primary vessel. To prevent excessive relaxation of the support structure whereby the control rods would be displaced relative to the core, the support structure incorporates a normally inactive secondary structure designed to become effective in bracing the primary structure against further relaxation beyond a predetermined limit. (author)

  16. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2000-07-01

    SCK-CEN's research and development programme on fusion reactor materials includes: (1) the study of the mechanical behaviour of structural materials under neutron irradiation (including steels, inconel, molybdenum, chromium); (2) the determination and modelling of the characteristics of irradiated first wall materials such as beryllium; (3) the detection of abrupt electrical degradation of insulating ceramics under high temperature and neutron irradiation; (4) the study of the dismantling and waste disposal strategy for fusion reactors.; (5) a feasibility study for the testing of blanket modules under neutron radiation. Main achievements in these topical areas in the year 1999 are summarised.

  17. Reactor gamma spectrometry: status

    International Nuclear Information System (INIS)

    Current work is described for Compton Recoil Gamma-Ray Spectrometry including developments in experimental technique as well as recent reactor spectrometry measurements. The current status of the method is described concerning gamma spectromoetry probe design and response characteristics. Emphasis is given to gamma spectrometry work in US LWR and BR programs. Gamma spectrometry in BR environments are outlined by focussing on start-up plans for the Fast Test Reactor (FTR). Gamma spectrometry results are presented for a LWR pressure vessel mockup in the Poolside Critical Assembly (PCA) at Oak Ridge National Laboratory

  18. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2002-04-01

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel.

  19. Risk prevention during reactor shutdown

    International Nuclear Information System (INIS)

    During reactor shutdown potential risks are issued of a number of maintenance operations. In this text we analyse these operations and give the modifications of technical specifications to ameliorate the reactor safety. 4 figs

  20. Power calibrations for TRIGA reactors

    International Nuclear Information System (INIS)

    The purpose of this paper is to establish a framework for the calorimetric power calibration of TRIGA reactors so that reliable results can be obtained with a precision better than ± 5%. Careful application of the same procedures has produced power calibration results that have been reproducible to ± 1.5%. The procedures are equally applicable to the Mark I, Mark II and Mark III reactors as well as to reactors having much larger reactor tanks and to TRIGA reactors capable of forced cooling up to 3 MW in some cases and 15 MW in another case. In the case of forced cooled TRIGA reactors, the calorimetric power calibration is applicable in the natural convection mode for these reactors using exactly the same procedures as are discussed below for the smaller TRIGA reactors (< 2 MW)

  1. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1982 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. Since fiscal 1982, Systematic research and development work on safeguards technology has been added to the activities of the Department. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  2. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors

  3. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

    Haselow, J.S.; Price, V.; Stephenson, D.E.; Bledsoe, H.W.; Looney, B.B.

    1989-12-01

    The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimal impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.

  4. High Flux Isotope Reactor (HFIR)

    Data.gov (United States)

    Federal Laboratory Consortium — The HFIR at Oak Ridge National Laboratory is a light-water cooled and moderated reactor that is the United States’ highest flux reactor-based neutron source. HFIR...

  5. Concepções de conhecimento escolar: potencialidades do Programa Institucional de Bolsa de Iniciação à Docência Concepts of school knowledge: potentialities of the Institutional Program of Teaching Initiation Scholarships

    Directory of Open Access Journals (Sweden)

    Andréa Rosana Fetzner

    2012-09-01

    Full Text Available Considerando-se as possibilidades abertas por meio do Programa Institucional de Bolsa de Iniciação à Docência (PIBID, o presente artigo discute as concepções de conhecimento escolar e os desafios de um projeto de transformação da escola básica em uma instituição que assuma perspectivas interculturais em relação ao conhecimento escolar. Nesse sentido, compreende-se que ainda é um desafio, para muitas escolas de ensino fundamental, reconhecer e trabalhar com conhecimentos que sejam significativos para a população que as frequenta. Apoiado pela CAPES, no âmbito do PIBID, este trabalho apresenta os resultados iniciais de um estudo sobre as concepções de conhecimento escolar que permeiam os saberes da docência de professores de escolas públicas e de bolsistas de iniciação à docência envolvidos no projeto. O desenvolvimento da pesquisa deu-se mediante o estudo da interculturalidade e de seus desafios contemporâneos, o acompanhamento do trabalho desenvolvido nas escolas e a aplicação de questionários a estudantes bolsistas de iniciação à docência da Universidade Federal do Estado do Rio de Janeiro (UNIRIO, que desenvolvem um projeto por meio do referido programa. Observamos, até o presente momento, que a concepção de conhecimento escolar tem oscilado entre perspectivas conservadoras e perspectivas emancipatórias, sendo estas últimas entendidas como aquelas que, compartilhando do conceito de bem viver, procuram integrar-se às necessidades das comunidades e compartilhar de princípios que envolvem a relacionalidade, a correspondência e a complementariedade, tal como salienta Catherine Walsh.Considering the possibilities resulting from the Institutional Program of Teaching Initiation Scholarships (PIBID, this paper discusses the concepts of school knowledge and the challenges of project to transform basic schooling into an institution that takes intercultural perspectives in relation to school knowledge. Thus, it is

  6. Perfil dos pesquisadores com bolsa de produtividade em pesquisa do CNPq da área de saúde coletiva A profile of researchers in public health with productivity grants from the Brazilian National Research Council (CNPq

    Directory of Open Access Journals (Sweden)

    Rita Barradas Barata

    2003-12-01

    Full Text Available O artigo analisa, com base nas informações do currículo Lattes, o perfil dos pesquisadores com bolsa de produtividade em pesquisa do CNPq na área de Saúde Coletiva. A análise levou em conta a formação graduada e pós-graduada, área de atuação, produção e divulgação científica. As comparações são feitas entre as classes de pesquisadores e com dados do diretório de grupos de pesquisa. A maioria dos pesquisadores (70% são formados em Ciências da Saúde, principalmente em Medicina, ou em Ciências Humanas (18%, principalmente Sociologia. Sessenta por cento fizeram mestrado e doutorado em Saúde Coletiva, mas há entre 20 e 30% de pesquisadores, dependendo da classe, sem formação específica na área. A maioria atua em Epidemiologia. A produção científica, expressa em produtos bibliográficos, varia de 10,56 produtos/ano de obtenção do doutorado para os pesquisadores 2C a 6,60 produtos/ano para os pesquisadores 1A. Para artigos completos publicados em periódicos os valores são 3,56 e 2,87, respectivamente. A produção é divulgada principalmente em periódicos A internacional e, A e B nacional. Os periódicos que concentram a publicação são Cadernos de Saúde Pública e Revista de Saúde Pública.Based on information provided by the Lattes curriculum, this study analyzes the profile of researchers in public health with productivity grants from the Brazilian National Research Council (CNPq. The analysis considered the researcher’s undergraduate and graduate degrees, field of expertise, scientific output, and publications. The article discusses comparisons between different categories of researchers and data provided by the CNPq Research Group Directory. Most of the researchers (70% received their undergraduate degrees either in health sciences, mainly medicine, or the humanities (18%, mainly sociology. 60% have Master’s or PhDs in collective health, but some 20 to 30% of researchers, depending on the category

  7. Reactor operation safety information document

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  8. Reactor safety in Eastern Europe

    International Nuclear Information System (INIS)

    The papers presented to the GRS colloquium refer to the cooperative activities for reactor accident analysis and modification of the GRS computer codes for their application to reactors of the Russian design types of WWER or RBMK. Another topic is the safety of RBMK reactors in particular, and the current status of investigations and studies addressing the containment of unit 4 of the Chernobyl reactor station. All papers are indexed separately in report GRS--117. (HP)

  9. Fast reactor programme

    International Nuclear Information System (INIS)

    This progress report summarizes the fast reactor research carried out by ECN during the period covering the year 1980. This research is mainly concerned with the cores of sodium-cooled breeders, in particular the SNR-300, and its related safety aspects. It comprises six items: A programme to determine relevant nuclear data of fission- and corrosion-products; A fuel performance programme comprising in-pile cladding failure experiments and a study of the consequences of loss-of-cooling and overpower; Basic research on fuel; Investigation of the changes in the mechanical properties of austenitic stainless steel DIN 1.4948 due to fast neutron doses, this material has been used in the manufacture of the reactor vessel and its internal components; Study of aerosols which could be formed at the time of a fast reactor accident and their progressive behaviour on leaking through cracks in the concrete containment; Studies on heat transfer in a sodium-cooled fast reactor core. As fast breeders operate at high power densities, an accurate knowledge of the heat transfer phenomena under single-phase and two-phase conditions is sought. (Auth.)

  10. Thermal Reactor Safety

    International Nuclear Information System (INIS)

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods

  11. NEUTRONIC REACTOR FUEL ELEMENT

    Science.gov (United States)

    Picklesimer, M.L.; Thurber, W.C.

    1961-01-01

    A chemically nonreactive fuel composition for incorporation in aluminum- clad, plate type fuel elements for neutronic reactors is described. The composition comprises a mixture of aluminum and uranium carbide particles, the uranium carbide particles containing at least 80 wt.% UC/sub 2/.

  12. Stabilized Spheromak Fusion Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Fowler, T

    2007-04-03

    The U.S. fusion energy program is focused on research with the potential for studying plasmas at thermonuclear temperatures, currently epitomized by the tokamak-based International Thermonuclear Experimental Reactor (ITER) but also continuing exploratory work on other plasma confinement concepts. Among the latter is the spheromak pursued on the SSPX facility at LLNL. Experiments in SSPX using electrostatic current drive by coaxial guns have now demonstrated stable spheromaks with good heat confinement, if the plasma is maintained near a Taylor state, but the anticipated high current amplification by gun injection has not yet been achieved. In future experiments and reactors, creating and maintaining a stable spheromak configuration at high magnetic field strength may require auxiliary current drive using neutral beams or RF power. Here we show that neutral beam current drive soon to be explored on SSPX could yield a compact spheromak reactor with current drive efficiency comparable to that of steady state tokamaks. Thus, while more will be learned about electrostatic current drive in coming months, results already achieved in SSPX could point to a productive parallel development path pursuing auxiliary current drive, consistent with plans to install neutral beams on SSPX in the near future. Among possible outcomes, spheromak research could also yield pulsed fusion reactors at lower capital cost than any fusion concept yet proposed.

  13. Reactors. Nuclear propulsion ships

    International Nuclear Information System (INIS)

    This article has for object the development of nuclear-powered ships and the conception of the nuclear-powered ship. The technology of the naval propulsion P.W.R. type reactor is described in the article B.N.3 141 'Nuclear Boilers ships'. (N.C.)

  14. Pressure tube type reactor

    International Nuclear Information System (INIS)

    Heretofore, a pressure tube type reactor has a problem in that the evaluation for the reactor core performance is complicate and no sufficient consideration is made for the economical property, to increase the size of a calandria tank and make the cost expensive. Then, in the present invention, the inner diameter of a pressure tube is set to greater than 50% of the lattice gap in a square lattice like arrangement, and the difference between the inner and the outer diameters of the calandria tube is set smaller than 20% of the lattice gap. Further, the inner diameter of the pressure tube is set to greater than 40% and the difference between the inner and the outer diameters of the calandria tube is set smaller than 30% of the lattice gap in a triangle lattice arrangement. Then, heavy water-to-fuel volume ratio can be determined appropriately and the value for the coolant void coefficient is made more negative side, to improve the self controllability inherent to the reactor. In particular, when 72 to 90 fuel rods are arranged per one pressure tube, the power density per one fuel rod is can be increased by about twice. Accordingly, the number of the pressure tubes can be reduced about to one-half, thereby enabling to remarkably decrease the diameter of the reactor core and to reduce the size of the calandria, which is economical. (N.H.)

  15. Fusion reactor materials

    International Nuclear Information System (INIS)

    At the Belgian Nuclear Research Centre SCK-CEN, activities related to fusion focus on environmental tolerance of opto-electronic components. The objective of this program is to contribute to the knowledge on the behaviour, during and after neutron irradiation, of fusion-reactor materials and components. The main scientific activities for 1997 are summarized

  16. Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

  17. Nuclear reactor building

    Science.gov (United States)

    Gou, Perng-Fei; Townsend, Harold E.; Barbanti, Giancarlo

    1994-01-01

    A reactor building for enclosing a nuclear reactor includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed thereabove. The wetwell and containment vessel define a drywell surrounding the reactor. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the reactor during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define therebetween an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin.

  18. Studies on reactor physics

    International Nuclear Information System (INIS)

    Most of the peaceful applications of atomic energy are inherently dependent on advances in the science and technology of nuclear reactors, and aspects of this development are part of a major programme of the International Atomic Energy Agency. The most useful role that the Agency can play is as a co-ordinating body or central forum where the trends can be reviewed and the results assessed. Some of the basic studies are carried out by members of the Agency's own scientific staff. The Agency also convenes groups of experts from different countries to examine a particular problem in detail and make any necessary recommendations. Some of the important subjects are discussed at international scientific meetings held by the Agency. One of the subjects covered by such studies is the physics of nuclear reactors and a specific topic recently discussed was Codes for Reactor Computations, on which a seminar was held in Vienna in April this year. Another The members of the Panel described the development of heavy water reactors, the equipment and methods of research currently used, and plans for further development in their respective countries meeting of Panel of Experts on Heavy Water Lattices was held in Vienna in August 1959

  19. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    The purpose of this book is to explain the physical working conditions of nuclear reactors for the benefit of non-specialized engineers and engineering students. One of the leading ideas of this course is to distinguish between two fundamentally different concepts: - a science which could be called neutrodynamics (as distinct from neutron physics which covers the knowledge of the neutron considered as an elementary particle and the study of its interactions with nuclei); the aim of this science is to study the interaction of the neutron gas with real material media; the introduction will however be restricted to its simplified expression, the theory and equation of diffusion; - a special application: reactor physics, which is introduced when the diffusing and absorbing material medium is also multiplying. For this reason the chapter on fission is used to introduce this section. In practice the section on reactor physics is much longer than that devoted to neutrodynamics and it is developed in what seemed to be the most relevant direction: nuclear power reactors. Every effort was made to meet the following three requirements: to define the physical bases of neutron interaction with different materials, to give a correct mathematical treatment within the limit of necessary simplifying hypotheses clearly explained; to propose, whenever possible, numerical applications in order to fix orders of magnitude

  20. Cermet fuel reactors

    Energy Technology Data Exchange (ETDEWEB)

    Cowan, C.L.; Palmer, R.S.; Van Hoomissen, J.E.; Bhattacharyya, S.K.; Barner, J.O.

    1987-09-01

    Cermet fueled nuclear reactors are attractive candidates for high performance space power systems. The cermet fuel consists of tungsten-urania hexagonal fuel blocks characterized by high strength at elevated temperatures, a high thermal conductivity and resultant high thermal shock resistance. Key features of the cermet fueled reactor design are (1) the ability to achieve very high coolant exit temperatures, and (2) thermal shock resistance during rapid power changes, and (3) two barriers to fission product release - the cermet matrix and the fuel element cladding. Additionally, thre is a potential for achieving a long operating life because of (1) the neutronic insensitivity of the fast-spectrum core to the buildup of fission products and (2) the utilization of a high strength refractory metal matrix and structural materials. These materials also provide resistance against compression forces that potentially might compact and/or reconfigure the core. In addition, the neutronic properties of the refractory materials assure that the reactor remains substantially subcritical under conditions of water immersion. It is concluded that cermet fueled reactors can be utilized to meet the power requirements for a broad range of advanced space applications. 4 refs., 4 figs., 3 tabs.

  1. Cermet fuel reactors

    International Nuclear Information System (INIS)

    Cermet fueled nuclear reactors are attractive candidates for high performance space power systems. The cermet fuel consists of tungsten-urania hexagonal fuel blocks characterized by high strength at elevated temperatures, a high thermal conductivity and resultant high thermal shock resistance. Key features of the cermet fueled reactor design are (1) the ability to achieve very high coolant exit temperatures, and (2) thermal shock resistance during rapid power changes, and (3) two barriers to fission product release - the cermet matrix and the fuel element cladding. Additionally, thre is a potential for achieving a long operating life because of (1) the neutronic insensitivity of the fast-spectrum core to the buildup of fission products and (2) the utilization of a high strength refractory metal matrix and structural materials. These materials also provide resistance against compression forces that potentially might compact and/or reconfigure the core. In addition, the neutronic properties of the refractory materials assure that the reactor remains substantially subcritical under conditions of water immersion. It is concluded that cermet fueled reactors can be utilized to meet the power requirements for a broad range of advanced space applications. 4 refs., 4 figs., 3 tabs

  2. The Chernobyl reactor accident

    International Nuclear Information System (INIS)

    The documentation abstracted contains a complete survey of the broadcasts transmitted by the Russian wire service of the Deutsche Welle radio station between April 28 and Mai 15, 1986 on the occasion of the Chernobyl reactor accident. Access is given to extracts of the remarkable eastern and western echoes on the broadcasts of the Deutsche Welle. (HP)

  3. SRP reactor safety evolution

    International Nuclear Information System (INIS)

    The Savannah River Plant reactors have operated for over 100 reactor years without an incident of significant consequence to on or off-site personnel. The reactor safety posture incorporates a conservative, failure-tolerant design; extensive administrative controls carried out through detailed operating and emergency written procedures; and multiple engineered safety systems backed by comprehensive safety analyses, adapting through the years as operating experience, changes in reactor operational modes, equipment modernization, and experience in the nuclear power industry suggested. Independent technical reviews and audits as well as a strong organizational structure also contribute to the defense-in-depth safety posture. A complete review of safety history would discuss all of the above contributors and the interplay of roles. This report, however, is limited to evolution of the engineered safety features and some of the supporting analyses. The discussion of safety history is divided into finite periods of operating history for preservation of historical perspective and ease of understanding by the reader. Programs in progress are also included. The accident at Three Mile Island was assessed for its safety implications to SRP operation. Resulting recommendations and their current status are discussed separately at the end of the report. 16 refs., 3 figs

  4. Fusion reactor materials

    International Nuclear Information System (INIS)

    This paper discuses the following topics on fusion reactor materials: irradiation, facilities, test matrices, and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; fundamental mechanical behavior; radiation effects; development of structural alloys; solid breeding materials; and ceramics

  5. Thermal Reactor Safety

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods.

  6. Department of reactor technology

    International Nuclear Information System (INIS)

    The activities of the Department of Reactor Technology at Risoe during 1980 are described. The work is presented in three chapters: General Information on the Department, Summary of the Department's Development during 1980, and Activities of the Department. Lists of staff, publications, computer programs, and test facilities are included. (author)

  7. The AP1000 reactor

    International Nuclear Information System (INIS)

    The design of the AP1000 reactor began 20 years ago when Westinghouse launched the AP600 reactor project. In fact by re-assessing AP600's safety margins Westinghouse realized that the its power output could be raised without putting at risk its safety standard. The AP1000 was born, it yields 1100 MWe. The main AP1000's design features is its passive safety (particularly after the Fukushima accident) and its modularity. The passive safety of the AP1000 implies: -) no humane intervention needed for 72 hours at least after the incident; -) no necessity for redundant complex safety systems. The modularity means that the plant, the reactor and other buildings are constructed from a choice of 300 modular units. These units can be built off-site and fit together on site. The modularity allows more construction activities to be led simultaneously and more chances to cope with the construction schedule. The NRC has approved the operation license for 30 years of the first AP1000 being built in the Usa (Vogtle plant in Georgia). 4 AP1000 are being built in China (Sanmen and Haiyang sites) and 6 others are planned in the Usa. Westinghouse is convinced that the AP1000's passive safety makes it more attractive. Let us not forget that Westinghouse was at the origin of the concept of pressurized water reactors, an idea adopted for half the nuclear power stations in the world and for all the plants now active in France. (A.C.)

  8. Fast reactor programme

    International Nuclear Information System (INIS)

    This progress report summarises the fast reactor research carried out at the Netherlands Energy Research Centre during the year 1981. The neutron and fission product cross sections of various isotopes have been evaluated. In the fuel performance programme, some preliminary results are given and irradiation facilities described. Creep experiments on various stainless steel components are reported

  9. Nuclear rocket engine reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lanin, Anatoly

    2013-07-01

    Covers a new technology of nuclear reactors and the related materials aspects. Integrates physics, materials science and engineering Serves as a basic book for nuclear engineers and nuclear physicists. The development of a nuclear rocket engine reactor (NRER) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

  10. Nuclear Reactors and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Cason, D.L.; Hicks, S.C. [eds.

    1992-01-01

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  11. Fusion reactor materials

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1989-01-01

    This paper discuses the following topics on fusion reactor materials: irradiation, facilities, test matrices, and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; fundamental mechanical behavior; radiation effects; development of structural alloys; solid breeding materials; and ceramics.

  12. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis

  13. Fast reactors: potential for power

    International Nuclear Information System (INIS)

    The subject is discussed as follows: basic facts about conventional and fast reactors; uranium economy; plutonium and fast reactors; cooling systems; sodium coolant; safety engineering; handling and recycling plutonium; safeguards; development of fast reactors in Britain and abroad; future progress. (U.K.)

  14. Reactor physics problems on HCPWR

    International Nuclear Information System (INIS)

    Reactor physics problems on high conversion pressurized water reactors (HCPWRs) are discussed. Described in this report are outline of the HCPWR, expected accuracy for the various reactor physical qualities, and method for K-effective calculation in the resonance energy area. And requested further research problems are shown. The target value of the conversion ratio are also discussed. (author)

  15. ADHERENCE LEVEL OF PROJECTS SUPPORTED BY BRAZILIAN RESEARCH AND TECHNOLOGY COUNCIL (CNPq, RESEARCH PRODUCTIVITY SCHOLARSHIP PROGRAM AND MILK TECHNOLOGIC PLATAFORM PROJECT ADERÊNCIA DOS PROJETOS APOIADOS PELO CONSELHO NACIONAL DE DESENVOLVIMENTO CIENTÍFICO E TECNOLÓGICO - CNPq, BOLSAS DE PRODUTIVIDADE EM PESQUISA E O PROJETO PLATAFORMA TECNOLÓGICA DO LEITE

    Directory of Open Access Journals (Sweden)

    Rui da Silva Verneque

    2007-12-01

    Full Text Available

    The objective of this work was to determine the adherence level of the CNPq supporting projects, using the Research Productivity Scholarship Program (RPSP, in to the Veterinary Medicine, Animal Science, Food Science, and the sub area Rural Technology Transference, concerned to the Milk-Chain activities, with the solution propose to the technologic problems presents in the Milk Technologic Platform Project (MTPP. A content analysis, based in key-words, was conduced to group the RPSP. The study was done in the industrial and production segments. The results suggest a good correlation among the Research Productivity Scholarship Program and the solution pro-pose by the Platform Project. Wherever, there are strategic areas to the national development that presented inexpres-sive adherence among RPS and MTPP solution proposes. Each region showed its particularity, as to industrial as to production segment, suggesting a different politics strategies between the segments.

    Key-words: Adherence levels, public politics,  technological limitations.

    O trabalho foi realizado com o objetivo de analisar a aderência dos projetos financiados pelo CNPq, por meio de bolsas de Produtividade em Pesquisa (Pq, nos Programas de Medicina Veterinária, Zootecnia, Ciência dos Alimentos e subárea Extensão Rural, voltadas à cadeia agroalimentar do leite, com as soluções para os gargalos tecnológicos apontados no Projeto Plataforma Tecnológica do Leite (PL. A finalidade é agrupar as bolsas de produtividade em pesquisa concedidas pelo CNPq, limitadas ao título dos projetos, temas e propostas de solução do projeto Plataforma Tecnológica do Leite nos segmentos da produção e indústria da cadeia produtiva do leite, por região geoeconômica, criando uma escala de aderência. Verificou-se que, de modo geral, as bolsas de produtividade em pesquisa financiadas pelo CNPq estão adequadas às propostas de solu

  16. O direito de participar da riqueza da nação: do Programa Bolsa Família à Renda Básica de Cidadania The right to share in the nation's wealth: from the Family Allowance Program to Basic Citizenship Income

    Directory of Open Access Journals (Sweden)

    Eduardo Matarazzo Suplicy

    2007-12-01

    Full Text Available O trabalho apresenta os resultados positivos do Programa Bolsa Família no combate à fome e a erradicação da pobreza, ressaltando que o Bolsa Família constituí-se na primeira etapa para a implantação da Renda Básica de Cidadania - RBC, no Brasil, conforme previsto pela Lei 10.835 de 2004. A RBC será instituída por etapas, a critério do Poder Executivo, começando pelos mais necessitados. Será o direito de todas as pessoas, incondicionalmente, receberem uma renda que, na medida do possível, será suficiente para atender as suas necessidades vitais. Não se trata de uma caridade ou uma assistência, mas de um direito de todos participarem da riqueza da nação. A racionalidade deste instrumento para garantir real liberdade e dignidade a todos é também aqui analisada.This paper presents the positive outcomes of Brazil's Family Allowance Program, in terms of combating hunger and eradicating poverty, stressing that this is the first step towards introducing a Basic Income for Citizenship (RBC - Renda Básica de Cidadania in Brazil, as established in 2004 through Law N° 10,835. This Basic Income for Citizenship will be phased in by stages at the discretion of the Executive Branch, starting with the neediest segments of the population. Everyone will be endowed with the unconditional right to receive an income that will be sufficient - as far as possible - to cover vital requirements. This is not a matter of charity or welfare, but rather an across-the-board right to share in the wealth of the nation. The rationality of this tool for ensuring real freedom and dignity for all is also examined here.

  17. Alternative approaches to fusion. [reactor design and reactor physics for Tokamak fusion reactors

    Science.gov (United States)

    Roth, R. J.

    1976-01-01

    The limitations of the Tokamak fusion reactor concept are discussed and various other fusion reactor concepts are considered that employ the containment of thermonuclear plasmas by magnetic fields (i.e., stellarators). Progress made in the containment of plasmas in toroidal devices is reported. Reactor design concepts are illustrated. The possibility of using fusion reactors as a power source in interplanetary space travel and electric power plants is briefly examined.

  18. Integração do enxerto heterólogo de pele humana no subepitélio da bolsa jugal do hamster (Mesocricetus auratus Integration of human skin heterologous graft into hamster (Mesocricetus auratus cheek pouch sub-epithelium

    Directory of Open Access Journals (Sweden)

    Bernardo Hochman

    2003-10-01

    Full Text Available OBJETIVO: Descrever a integração de enxertos de pele total humana no subepitélio da bolsa jugal do hamster (Mesocricetus auratus. MÉTODOS: A amostragem consistiu de 18 hamsters machos, exogâmicos, com 10 a 14 semanas de idade. Fragmentos de pele humana normal foram obtidos de pele excedente de mastoplastia redutora de paciente parda. Cada hamster foi enxertado em ambas as bolsas com fragmentos de pele, perfazendo um total de 36 fragmentos enxertados. Os animais foram distribuídos, em 6 grupos, para exame dos fragmentos enxertados com 5, 12, 21, 42, 84 e 168 dias. Uma avaliação macroscópica foi realizada comparando a bolsa contendo o fragmento enxertado em cada período com a mesma bolsa no pós-operatório imediato, mediante fotografias padronizadas. Na avaliação microscópica foi adotado como critério de integração a presença de vasos sangüíneos na derme dos enxertos. Observou-se também a presença de queratina, melanócitos, infiltrado celular e aspecto do tecido conjuntivo. RESULTADOS: Na avaliação macroscópica foi observada uma reação vascular em torno dos fragmentos até 12 dias do implante, e a presença de pigmentação castanho-escura a partir de 42 dias. À microscopia, integraram-se 80,64% dos fragmentos enxertados, inclusive no grupo de 168 dias. Observou-se infiltrado celular inflamatório até 12 dias, a presença de melanócitos a partir de 42 dias e uma hialinização do tecido conjuntivo após 84 dias. CONCLUSÕES: Fragmentos de pele humana integram-se no tecido celular subcutâneo da bolsa jugal do hamster, mantêm-se vascularizados por 168 dias, e conservam o epitélio íntegro até 21 dias. O subepitélio da bolsa representa modelo experimental de investigação da fisiologia de pele humana ex vivo.PURPOSE: To describe the integration of total human skin into hamster (Mesocricetus auratus cheek pouch. METHODS: The sample was formed by 18 male hamsters, outbred, aging between 10 and 14 weeks. Fragments of

  19. Reactor vessel support system. [LMFBR

    Science.gov (United States)

    Golden, M.P.; Holley, J.C.

    1980-05-09

    A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

  20. Reactor monitoring using antineutrino detectors

    Science.gov (United States)

    Bowden, N. S.

    2011-08-01

    Nuclear reactors have served as the antineutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Measurements made with antineutrino detectors could therefore offer an alternative means for verifying the power history and fissile inventory of a reactor as part of International Atomic Energy Agency (IAEA) and/or other reactor safeguards regimes. Several efforts to develop this monitoring technique are underway worldwide.

  1. Reactor physics activities in Japan

    International Nuclear Information System (INIS)

    This report reviews the research activity in reactor physics field in Japan during July, 1992 - July, 1993. The review was performed in the following fields : nuclear data evaluation, calculational method development, fast reactor physics, thermal reactor physics, advanced core design, fusion reactor neutronics, nuclear criticality safety, shielding, incineration of radioactive nuclear wastes, noise analysis and control and national programs. The main references were taken from journals and reports published during this period. The research committee of reactor physics is responsible for the review work. (author)

  2. Advanced reactor experimental facilities

    International Nuclear Information System (INIS)

    For many years, the NEA has been examining advanced reactor issues and disseminating information of use to regulators, designers and researchers on safety issues and research needed. Following the recommendation of participants at an NEA workshop, a Task Group on Advanced Reactor Experimental Facilities (TAREF) was initiated with the aim of providing an overview of facilities suitable for carrying out the safety research considered necessary for gas-cooled reactors (GCRs) and sodium fast reactors (SFRs), with other reactor systems possibly being considered in a subsequent phase. The TAREF was thus created in 2008 with the following participating countries: Canada, the Czech Republic, Finland, France, Germany, Hungary, Italy, Japan, Korea and the United States. In a second stage, India provided valuable information on its experimental facilities related to SFR safety research. The study method adopted entailed first identifying high-priority safety issues that require research and then categorizing the available facilities in terms of their ability to address the safety issues. For each of the technical areas, the task members agreed on a set of safety issues requiring research and established a ranking with regard to safety relevance (high, medium, low) and the status of knowledge based on the following scale relative to full knowledge: high (100%-75%), medium (75 - 25%) and low (25-0%). Only the issues identified as being of high safety relevance and for which the state of knowledge is low or medium were included in the discussion, as these issues would likely warrant further study. For each of the safety issues, the TAREF members identified appropriate facilities, providing relevant information such as operating conditions (in- or out-of reactor), operating range, description of the test section, type of testing, instrumentation, current status and availability, and uniqueness. Based on the information collected, the task members assessed prospects and priorities

  3. Reactor simulator development. Workshop material

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in reactor operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. This publication consists of course material for workshops on development of such reactor simulators. Participants in the workshops are provided with instruction and practice in the development of reactor simulation computer codes using a model development system that assembles integrated codes from a selection of pre-programmed and tested sub-components. This provides insight and understanding into the construction and assumptions of the codes that model the design and operational characteristics of various power reactor systems. The main objective is to demonstrate simple nuclear reactor dynamics with hands-on simulation experience. Using one of the modular development systems, CASSIMtm , a simple point kinetic reactor model is developed, followed by a model that simulates the Xenon/Iodine concentration on changes in reactor power. Lastly, an absorber and adjuster control rod, and a liquid zone model are developed to control reactivity. The built model is used to demonstrate reactor behavior in sub-critical, critical and supercritical states, and to observe the impact of malfunctions of various reactivity control mechanisms on reactor dynamics. Using a PHWR simulator, participants practice typical procedures for a reactor startup and approach to criticality. This workshop material consists of an introduction to systems used for developing reactor simulators, an overview of the dynamic simulation

  4. Reactor water spontaneous circulation structure in reactor pressure vessel

    International Nuclear Information System (INIS)

    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.)

  5. Safety review, assessment and inspection on research reactors, experimental reactors, nuclear heating reactors and critical facilities

    International Nuclear Information System (INIS)

    In 1998, the NNSA organized to complete the nuclear safety review on the test loop in-reactor operation of the High-flux Engineering Experimental Reactor (HFEER) and the re-operation of the China Pulsed Reactor and the Uranium-water Criticality Facility. The NNSA conducted the nuclear safety review on the CP application of the China Experimental Fast Reactor (CEFR) and the siting of China Advanced Research Reactor (CARR), and carried out the construction supervision on HTR-10, and dealt with the event about the technological tube breakage of HWRR and other events

  6. Compact fusion reactors

    CERN Document Server

    CERN. Geneva

    2015-01-01

    Fusion research is currently to a large extent focused on tokamak (ITER) and inertial confinement (NIF) research. In addition to these large international or national efforts there are private companies performing fusion research using much smaller devices than ITER or NIF. The attempt to achieve fusion energy production through relatively small and compact devices compared to tokamaks decreases the costs and building time of the reactors and this has allowed some private companies to enter the field, like EMC2, General Fusion, Helion Energy, Lawrenceville Plasma Physics and Lockheed Martin. Some of these companies are trying to demonstrate net energy production within the next few years. If they are successful their next step is to attempt to commercialize their technology. In this presentation an overview of compact fusion reactor concepts is given.

  7. Elk River Reactor dismantling

    International Nuclear Information System (INIS)

    The dismantling program was carried out in three overlapping phases: the planning phase which included the preliminary planning and selection of the dismantling approach, the dismantling phase which included all work performed to remove the reactor facility and restore the site to its pre-reactor condition, and the closeout phase which included the final site survey and efforts necessary to terminate the AEC license and contract. Of particular interest was the use of a remotely operated plasma cutting torch to section the pressure vessel internals, the pressure vessel and the outer thermal shield, the use of explosives in removal of the biological shield and the method of establishment of the criteria for material disposal

  8. REACTOR MODERATOR STRUCTURE

    Science.gov (United States)

    Greenstreet, B.L.

    1963-12-31

    A system for maintaining the alignment of moderator block structures in reactors is presented. Integral restraining grids are placed between each layer of blocks in the moderator structure, at the top of the uppermost layer, and at the bottom of the lowermost layer. Slots are provided in the top and bottom surfaces of the moderator blocks so as to provide a keying action with the grids. The grids are maintained in alignment by vertical guiding members disposed about their peripheries. (AEC)

  9. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    SCK-CEN's programme on fusion reactor materials includes studies (1) to investigate fracture mechanics of neutron-irradiated beryllium; (2) to describe the helium behaviour in irradiated beryllium at atomic scale; (3) to define the kinetics of beryllium reacting with air or steam; (3) to perform a feasibility study for the testing of integrated blanket modules under neutron irradiation. Progress and achievements in 1997 are reported

  10. Decommissioning of research reactors

    International Nuclear Information System (INIS)

    Research reactors of WWR-S type were built in countries under Soviet influence in '60, last century and consequently reached their service life. Decommissioning implies removal of all radioactive components, processing, conditioning and final disposal in full safety of all sources on site of radiological pollution. The WWR-S reactor at Bucuresti-Magurele was put into function in 1957 and operated until 1997 when it was stopped and put into conservation in view of decommissioning. Presented are three decommissioning variants: 1. Reactor shut-down for a long period (30-50 years) what would entail a substantial decrease of contamination with lower costs in dismantling, mechanical, chemical and physical processing followed by final disposal of the radioactive wastes. The drawback of this solution is the life prolongation of a non-productive nuclear unit requiring funds for personnel, control, maintenance, etc; 2. Decommissioning in a single stage what implies large funds for a immediate investment; 3. Extending the operation on a series of stages rather phased in time to allow a more convenient flow of funds and also to gather technical solutions, better than the present ones. This latter option seems to be optimal for the case of the WWR-S Research at Bucharest-Magurele Reactor. Equipment and technologies should be developed in order to ensure the technical background of the first operations of decommissioning: equipment for scarification, dismantling, dismemberment in a highly radioactive environment; cutting-to-pieces and disassembling technologies; decontamination modern technologies. Concomitantly, nuclear safety and quality assurance regulations and programmes, specific to decommissioning projects should be implemented, as well as a modern, coherent and reliable system of data acquisition, recording and storing. Also the impact of decommissioning must be thoroughly evaluated. The national team of specialists will be assisted by IAEA experts to ensure the

  11. Nuclear reactor container

    International Nuclear Information System (INIS)

    Upon reactor accident, hydrogen and oxygen are generated by water-zirconium reaction and radiolysis of water, which are accumulated in the reactor. If the concentration of hydrogen and oxygen exceeds a burning limit, there is a possibility of hydrogen burning to cause a danger of deteriorating the integrity of the reactor container and the equipments therein. The limit for the occurrence of the detonation is determined by a relationship between the scale of a detonation cell and the size of the container, and if the scale is greater than the container, the detonation does not occur. The scale of the cell is determined by a gas combustion rate and, if the combustion reaction is suppressed, detonation does not occur even in a large container. Then, an appropriate diluent is added to increase heat capacity of a gas mixture to thereby suppress the temperature elevation of the gas. Incombustible gases having a great heat capacity are preferred for the diluent, and CO2 is used. As the concentration of the CO2 gas to be added is increased, the detonation cell is made greater. Thus, occurrence of detonation due to combustion of the accumulated hydrogen can be prevented. (N.H.)

  12. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    In the middle of 21st century, the population on the earth is expected to double, and the energy that mankind consumes to triple. The nuclear fusion which is said the ultimate energy source for mankind is expected to solve this energy problem. As for fusion reactors, fuel materials exist inexhaustibly, distributing evenly, they have high safety in principle, the product of burning is harmless nonradioactive substance that does not require the treatment and disposal, and the attenuation of induced radioactivity due to neutrons is quick and the effect to global environment is little. The basic plan of second stage nuclear fusion research and development was decided in 1975, aiming at attaining the critical plasma condition. JT-60 has attained it in 1987. The project of international thermonuclear fusion experimental reactor (ITER) was started, and the conceptual design was carried out. Under such background, the third stage basic plan was decided in 1992, and its objective is self ignition condition, long time burning and the basis of the reactor engineering technology. The engineering design of the ITER is investigated. (K.I.)

  13. High temperature gas reactor

    International Nuclear Information System (INIS)

    The present invention provides a reflector block structure of a high temperature gas reactor in which graphite blocks are not failed even a containing cylinder loaded to a fuel exchanger collides against to secured reflectors upon loading and withdrawing fuel constitutional elements. Namely, a protection plate made of a metal material such as stainless steel is covered on the secured reflector blocks disposed to the upper most step among secured graphite reflector blocks constituting the reactor core. In addition, positioning guide grooves are formed on the protection plate for guiding the containing cylinder loaded to the fuel exchanger to the column of the reactor core constitutional elements. With such a constitution, even if the containing cylinder of fuel exchanger is hoisted down and collided against the inner circumferential edge of the secured reflector blocks due to deviation of the position and the direction upon exchange of fuels, the reflector blocks are not failed since the above-mentioned portion is covered with the metal protection plate. In addition, the positioning guide grooves lead the fuel exchanger to a predetermined column correctly. (I.S.)

  14. BWR type reactor

    International Nuclear Information System (INIS)

    In a coolant circulation in BWR type reactors, since the mixed stream of steam fluid undergoes a great resistance, the pressure loss due to the flow rate distribution when the coolants flow from the upper plenum into the stand pipe is increased upon passing stand pipe. Also in the spontaneous recycling reactor, pressure loss is still left upon passing the swirling blade of a gas-liquid separator. In view of the above, a plurality of vertical members each having a lower end opened to a gas-liquid two phase boundary and an upper end directly suspended from a steam dryer to the gas-liquid separator. The liquid droplets from the 2-phase boundary heated in the reactor core and formed into a mixed gas-liquid 2-phase stream is directed in the vertical direction accompanied with the steam. The liquid droplets spontaneously fallen by gravity from greater ones successively and the droplets in the steam abutted against the vertical member are fallen as a liquid membrane. Thus, the gas-liquid separation is conducted, the dry steam is directly flown into the steam dryer, thereby capable of providing a gas-liquid separator having gas-liquid separation performance with lower loss than usual. (N.H.)

  15. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  16. Fusion reactor safety

    International Nuclear Information System (INIS)

    Nuclear fusion could soon become a viable energy source. Work in plasma physics, fusion technology and fusion safety is progressing rapidly in a number of Member States and international collaboration continues on work aiming at the demonstration of fusion power generation. Safety of fusion reactors and technological and radiological aspects of waste management are important aspects in the development and design of fusion machines. In order to provide an international forum to review and discuss the status and the progress made since 1983 in programmes related to operational safety aspects of fusion reactors, their waste management and decommissioning concepts, the IAEA had organized the Technical Committee on ''Fusion Reactor Safety'' in Culham, 3-7 November 1986. All presentations of this meeting were divided into four sessions: 1. Statements on National-International Fusion Safety Programmes (5 papers); 2. Operation and System Safety (15 papers); 3. Waste Management and Decommissioning (5 papers); 4. Environmental Impacts (6 papers). A separate abstract was prepared for each of these 31 papers. Refs, figs, tabs

  17. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units are provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  18. OECD Halden Reactor Project

    International Nuclear Information System (INIS)

    The OECD Halden Reactor project is an agreement between OECD member countries. It was first signed in 1958 and since then regularly renewed every third year. The activities at the Project is centred around the Halden heavy water rector, the HBWR. The reseach programme comprizes studies of fuel performance under various operating conditions, and the application of computers for process control. The HBWR is equipped for exposing fuel rods to temperatures and pressures, and at heat ratings met in modern BWR's and PWR's. A range of in-core instruments are available, permitting detailed measurements of the reactions of the fuel, including mechanical deformations, thermal behaviour, fission gas release, and corrosion. In the area of computer application, the studies of the communication between operator and process, and the surveillance and control of the reactor core, are of particular interst for reactor operation. 1988 represents the 30th year since the Project was started, and this publication is produced to mark this event. It gives and account of the activities and achievements of the Project through the years 1958-1988

  19. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  20. Chernobyl reactor transient simulation study

    International Nuclear Information System (INIS)

    This paper deals with the Chernobyl nuclear power station transient simulation study. The Chernobyl (RBMK) reactor is a graphite moderated pressure tube type reactor. It is cooled by circulating light water that boils in the upper parts of vertical pressure tubes to produce steam. At equilibrium fuel irradiation, the RBMK reactor has a positive void reactivity coefficient. However, the fuel temperature coefficient is negative and the net effect of a power change depends upon the power level. Under normal operating conditions the net effect (power coefficient) is negative at full power and becomes positive under certain transient conditions. A series of dynamic performance transient analysis for RBMK reactor, pressurized water reactor (PWR) and fast breeder reactor (FBR) have been performed using digital simulator codes, the purpose of this transient study is to show that an accident of Chernobyl's severity does not occur in PWR or FBR nuclear power reactors. This appears from the study of the inherent, stability of RBMK, PWR and FBR under certain transient conditions. This inherent stability is related to the effect of the feed back reactivity. The power distribution stability in the graphite RBMK reactor is difficult to maintain throughout its entire life, so the reactor has an inherent instability. PWR has larger negative temperature coefficient of reactivity, therefore, the PWR by itself has a large amount of natural stability, so PWR is inherently safe. FBR has positive sodium expansion coefficient, therefore it has insufficient stability it has been concluded that PWR has safe operation than FBR and RBMK reactors

  1. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The purpose of this technical paper is to provide status of the United State domestic Research Reactor Infrastructure (RRI) Program at the Idaho National Laboratory. This paper states the purpose of the program, lists the universities operating TRIGA reactors that are supported by the program, identifies anticipated fresh fuel needs for the reactor facilities, discusses spent fuel activities associated with the program, and addresses successes and planned activities for the program. (author)

  2. Thermionic Reactor Design Studies

    Energy Technology Data Exchange (ETDEWEB)

    Schock, Alfred

    1994-06-01

    During the 1960's and early 70's the author performed extensive design studies, analyses, and tests aimed at thermionic reactor concepts that differed significantly from those pursued by other investigators. Those studies, like most others under Atomic Energy Commission (AEC and DOE) and the National Aeronautics and Space Administration (NASA) sponsorship, were terminated in the early 1970's. Some of this work was previously published, but much of it was never made available in the open literature. U.S. interest in thermionic reactors resumed in the early 80's, and was greatly intensified by reports about Soviet ground and flight tests in the late 80's. This recent interest resulted in renewed U.S. thermionic reactor development programs, primarily under Department of Defense (DOD) and Department of Energy (DOE) sponsorship. Since most current investigators have not had an opportunity to study all of the author's previous work, a review of the highlights of that work may be of value to them. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling. Where the author's concepts differed from the later Topaz-2 design was in the relative location of the emitter and the collector. Placing the fueled emitter on the outside of the cylindrical diodes permits much higher axial conductances to reduce ohmic

  3. Applications of Research Reactors

    International Nuclear Information System (INIS)

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property'. The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The purpose of the earlier publication, The Application of Research Reactors, IAEA-TECDOC-1234, was to present descriptions of the typical forms of research reactor use. The necessary criteria to enable an application to be performed were outlined for each one, and, in many cases, the minimum as well as the desirable requirements were given. This revision of the publication over a decade later maintains the original purpose and now specifically takes into account the changes in service requirements demanded by the relevant stakeholders. In particular, the significant improvements in

  4. Reactor technology: power conversion systems and reactor operation and maintenance

    International Nuclear Information System (INIS)

    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-He3 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

  5. Nuclear Reactor RA Safety Report, Vol. 4, Reactor

    International Nuclear Information System (INIS)

    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

  6. The research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    Paper dwells upon the design and the operation of one of the German test reactors, namely, the TRIGA Mainz one (TRIGA: Training Research Isotope Production General Atomic). The TRIGA reactor is a pool test reactor the core of which contains a graphite reflector and is placed into 2 m diameter and 6.25 m height aluminum vessel. There are 75 fuel elements in the reactor core, and any of them contains about 36 g of 235U. The TRIGA reactors under the stable operation enjoy wide application to ensure tests and irradiation, namely: neutron activation analysis, radioisotope production, application of a neutron beam to ensure the physical, the chemical and the medical research efforts. Paper presents the reactor basic experimental program lines

  7. Spiral-shaped disinfection reactors

    KAUST Repository

    Ghaffour, Noreddine

    2015-08-20

    This disclosure includes disinfection reactors and processes for the disinfection of water. Some disinfection reactors include a body that defines an inlet, an outlet, and a spiral flow path between the inlet and the outlet, in which the body is configured to receive water and a disinfectant at the inlet such that the water is exposed to the disinfectant as the water flows through the spiral flow path. Also disclosed are processes for disinfecting water in such disinfection reactors.

  8. Industrializing the liquid metal reactor

    International Nuclear Information System (INIS)

    Commercial acceptance of the liquid metal reactor had its beginning with the Fermi reactor, over two decades ago. The pattern of industrialization since that time is discussed, contrasting domestic and foreign experience. The recent termination of the Clinch River reactor project marks a watershed in the U.S. approach towards commercialization. The increased emphasis on achieving cost competitive designs reflects an awareness that barriers to industrialization are institutional and financial, and not technological

  9. Acceptability of reactors in space

    Energy Technology Data Exchange (ETDEWEB)

    Buden, D.

    1981-04-01

    Reactors are the key to our future expansion into space. However, there has been some confusion in the public as to whether they are a safe and acceptable technology for use in space. The answer to these questions is explored. The US position is that when reactors are the preferred technical choice, that they can be used safely. In fact, it dies not appear that reactors add measurably to the risk associated with the Space Transportation System.

  10. Hydrogen Production in Fusion Reactors

    OpenAIRE

    Sudo, S.; Tomita, Y.; Yamaguchi, S.; Iiyoshi, A.; Momota, H.; Motojima, O.; Okamoto, M; Ohnishi, M.; Onozuka, M.; Uenosono, C.

    1993-01-01

    As one of methods of innovative energy production in fusion reactors without having a conventional turbine-type generator, an efficient use of radiation produced in a fusion reactor with utilizing semiconductor and supplying clean fuel in a form of hydrogen gas are studied. Taking the candidates of reactors such as a toroidal system and an open system for application of the new concepts, the expected efficiency and a concept of plant system are investigated.

  11. Fast reactor programme in India

    Indian Academy of Sciences (India)

    P Chellapandi; P R Vasudeva Rao; Prabhat Kumar

    2015-09-01

    Role of fast breeder reactor (FBR) in the Indian context has been discussed with appropriate justification. The FBR programme since 1985 till 2030 is highlighted focussing on the current status and future direction of fast breeder test reactor (FBTR), prototype fast breeder reactor (PFBR) and FBR-1 and 2. Design and technological challenges of PFBR and design and safety targets with means to achieve the same are the major highlights of this paper.

  12. Turning points in reactor design

    International Nuclear Information System (INIS)

    This article provides some historical aspects on nuclear reactor design, beginning with PWR development for Naval Propulsion and the first commercial application at Yankee Rowe. Five turning points in reactor design and some safety problems associated with them are reviewed: (1) stability of Dresden-1, (2) ECCS, (3) PRA, (4) TMI-2, and (5) advanced passive LWR designs. While the emphasis is on the thermal-hydraulic aspects, the discussion is also about reactor systems

  13. Optimal control of nuclear reactors

    International Nuclear Information System (INIS)

    The modern control theory is applied to the design of control systems for experimental nuclear reactors that do not belong to power reactors, the component forms of optimal control systems for nuclear reactors are demonstrated. The adoption of output quadratic integral criterion and incomplete state feedback technique can make these systems both efficient and economical. Moreover, approximate handling methods are given so as to simplify the calculations in design. In addition, the adoptable reference values of parameters are given in the illustration

  14. Turning points in reactor design

    Energy Technology Data Exchange (ETDEWEB)

    Beckjord, E.S.

    1995-09-01

    This article provides some historical aspects on nuclear reactor design, beginning with PWR development for Naval Propulsion and the first commercial application at Yankee Rowe. Five turning points in reactor design and some safety problems associated with them are reviewed: (1) stability of Dresden-1, (2) ECCS, (3) PRA, (4) TMI-2, and (5) advanced passive LWR designs. While the emphasis is on the thermal-hydraulic aspects, the discussion is also about reactor systems.

  15. Acceptability of reactors in space

    International Nuclear Information System (INIS)

    Reactors are the key to our future expansion into space. However, there has been some confusion in the public as to whether they are a safe and acceptable technology for use in space. The answer to these questions is explored. The US position is that when reactors are the preferred technical choice, that they can be used safely. In fact, it does not appear that reactors add measurably to the risk associated with the Space Transportation System

  16. Advanced Fission Reactor Program objectives

    International Nuclear Information System (INIS)

    The objective of an advanced fission reactor program should be to develop an economically attractive, safe, proliferation-resistant fission reactor. To achieve this objective, an aggressive and broad-based research and development program is needed. Preliminary work at Brookhaven National Laboratory shows that a reasonable goal for a research program would be a reactor combining as many as possible of the following features: (1) initial loading of uranium enriched to less than 15% uranium 235, (2) no handling of fuel for the full 30-year nominal core life, (3) inherent safety ensured by core physics, and (4) utilization of natural uranium at least 5 times as efficiently as light water reactors

  17. Reactor safety - an international task

    International Nuclear Information System (INIS)

    The dimensions and the significance of the task of ensuring reactor safety can be defined on the basis of experiences gained from Harrisburg and Chernobyl. The countries that use nuclear energy are tied together to a community by virtue of the risk they share. Therefore the GRS is working in close cooperation with the EC, OECD, IAEO and COMECON. This results in safety examinations of the Greifswald reactor, safety analyses of nuclear reactors in Germany, France and the USA and also considerations on the safety demands to be placed on new reactor concepts. (DG)

  18. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  19. Integrated modular water reactor: IMR

    International Nuclear Information System (INIS)

    The Mitsubishi Heavy Industries, Ltd. Has investigated on a concept on small scale reactor with economical efficiency comparable with large scale one. Aims of development on the integrated modular water reactor (IMR) of a small scale reactor plant concept consist in large construction cost reduction through adoption of technique specific to the small scale reactor and integrated production of plural units and in establishment of high safety target without reality in a large scale reactor to realize reduction of operation and maintenance costs by this reduction to simplification of operation and maintenance. Its concrete developmental targets are to make an integrated reactor with vessel size actually producible and the largest output, to remove feasibility of coolant loss accident (LOCA), to remove an accident with feasibility related to fuel fracture, to remove feasibility of nuclear reactor coolant to leak out from a storage vessel, to secure safety of plant without necessity of human and physical assistances from other plants at all on an accident, to make numbers of operators per unit output equal to those of large scale reactor, and to make working amounts at maintenance per unit output equal to large scale reactor by simplification of apparatus practice of rotation on main apparatus such as SG, and so on. Here were described on design concept and plan to realization. (G.K.)

  20. 3. Interindustry conference on reactor materials science

    International Nuclear Information System (INIS)

    This document contains abstracts on papers presented at the Third Interindustry Conference on Reactor Materials Science (Dimitrovgrad, 27-30 October 1992). The subject scope of the papers is a follows: fuel and fuel elements of power reactors; structural materials of fast breeder reactors and thermonuclear reactors; structural materials of WWER and RBMK type reactors; absorbers and moderators

  1. Helias reactor studies

    International Nuclear Information System (INIS)

    The Helias reactor is an upgraded version of the Wendelstein 7-X experiment. The magnetic field has 5 field periods and the main optimization principle is the reduction of the Pfirsch-Schlueter currents and the Shafranov shift, which has been verified by computations with the NEMEC and MFBE-codes. The modular coil system comprises 50 coils, which are constructed using NbTi-superconducting cables. The basic dimensions are: major radius 22 m, average plasma radius 1.8 m, magnetic field on axis 5 T, maximum field on the coils 10 T. Forces and stresses in the coil system have been investigated with the aid of the ANSYS code, which found maximum stress values of about 650 MPa in the coil casing. Helias configurations with 4 and 3 field periods have been constructed by starting from the 5-period case and by eliminating one or two periods while the shape of the coils is kept nearly invariant. In a first survey blanket concepts, developed for the DEMO tokamak, have been adapted to the Helias geometry, in particular, the solid breeder concept developed by FZK (Karlsruhe) has been extrapolated to the Helias geometry identifying the drawbacks and advantages of this concept. Furthermore, the liquid breeder concept using Li7-Pb83 and water-cooling is an interesting alternative for the Helias reactor. Maintenance of blanket and plasma facing components is possible through the portholes between modular coils. Numerical simulations of the start-up phase of the Helias reactor using the TOTAL-P code have confirmed the zero-dimensional modeling of the fusion plasma with the aid of empirical scaling laws. (author)

  2. Reactor coolant pump flywheel

    Science.gov (United States)

    Finegan, John Raymond; Kreke, Francis Joseph; Casamassa, John Joseph

    2013-11-26

    A flywheel for a pump, and in particular a flywheel having a number of high density segments for use in a nuclear reactor coolant pump. The flywheel includes an inner member and an outer member. A number of high density segments are provided between the inner and outer members. The high density segments may be formed from a tungsten based alloy. A preselected gap is provided between each of the number of high density segments. The gap accommodates thermal expansion of each of the number of segments and resists the hoop stress effect/keystoning of the segments.

  3. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the errata page

  4. FUEL ASSAY REACTOR

    Science.gov (United States)

    Spinrad, B.I.; Sandmeier, H.A.; Martens, F.H.

    1962-12-25

    A reactor having maximum sensitivity to perturbations is described comprising a core consisting of a horizontally disposed, rectangular, annular fuel zone containing enriched uranium dioxide dispersed in graphite, the concentration of uranium dioxide increasing from the outside to the inside of the fuel zone, an internal reflector of graphite containing an axial test opening disposed within the fuel zone, an external graphite reflector, means for changing the neutron spectrum in the test opening, and means for measuring perturbations in the neutron flux caused by the introduction of different fuel elements into the test opening. (AEC)

  5. Shutting down two reactors

    International Nuclear Information System (INIS)

    Nuclear power will be phased out of the swedish energy system during the first decades of the next century. Commissioned by the swedish government, the National Energy Administration reports a study on the possibilities for, and consequences of, an earlier shut down (1994-1996) of two of the twelve swedish power reactors. Some of the questions studied are: How much will the electricity price raise ?; How will the electricity consumption be affected ?; What are the alternatives to nuclear power ?; What will the cost be ? and What will the environmental effects be ?. (L.E.)

  6. Measurement in nuclear reactors

    International Nuclear Information System (INIS)

    A nuclear reactor construction has a flux detector comprising a bundle of fibre optics each having a bead incorporating a substance which scintillates on being struck by neutrons or gamma radiations. The other ends of the fibre optics terminate at an image intensifier. The optical fibres may be of glass made from a mixture of silica, alkaline earth metal oxide, cerous oxide and alkali metal oxide. The beads may be incorporated in a disc forming a detector head, which is in a protective guide tube, through which an inert gas may be passed. (author)

  7. TRIGA reactor operating experience

    International Nuclear Information System (INIS)

    The Oregon State TRIGA Reactor (OSTR) has been in operation 3 years. Last August it was upgraded from 250 kW to 1000 kW. This was accomplished with little difficulty. During the 3 years of operation no major problems have been experienced. Most of the problems have been minor in nature and easily corrected. They came from lazy susan (dry bearing), Westronics Recorder (dead spots in the range), The Reg Rod Magnet Lead-in Circuit (a new type lead-in wire that does not require the lead-in cord to coil during rod withdrawal hss been delivered, much better than the original) and other small corrections

  8. Reactor system safety assurance

    International Nuclear Information System (INIS)

    The philosophy of reactor safety is that design should follow established and conservative engineering practices, there should be safety margins in all modes of plant operation, special systems should be provided for accidents, and safety systems should have redundant components. This philosophy provides ''defense in depth.'' Additionally, the safety of nuclear power plants relies on ''safety systems'' to assure acceptable response to design basis events. Operating experience has shown the need to study plant response to more frequent upset conditions and to account for the influence of operators and non-safety systems on overall performance. Defense in depth is being supplemented by risk and reliability assessment

  9. The Oklo reactors

    International Nuclear Information System (INIS)

    The Oklo reactors comprise up to nine 235-U depleted zones in an uranium ore in the Republic of Gabon in West Africa. The depletion in fissile U-235 has been proved to have caused by nuclear chain reactions. The study of the Oklo phenomenon indicates that very efficient retardation mechanisms may operate in nature - at least under special conditions. A closer study of these processes ought to be made to establish the limitations to their occurrence. The Oklo sandstone formation today would probably be considered unacceptable as a host rock for a repository. (EG)

  10. Licensed reactor nuclear safety criteria applicable to DOE reactors

    Energy Technology Data Exchange (ETDEWEB)

    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.

  11. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    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

  12. Virtual nuclear reactor for education of nuclear reactor physics

    International Nuclear Information System (INIS)

    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)

  13. Reactor Physics Analysis Models for a CANDU Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hang Bok

    2007-10-15

    Canada deuterium uranium (CANDU) reactor physics analysis is typically performed in three steps. At first, macroscopic cross-sections of the reference lattice is produced by modeling the reference fuel channel. Secondly macroscopic cross-sections of reactivity devices in the reactor are generated. The macroscopic cross-sections of a reactivity device are calculated as incremental cross-sections by subtracting macroscopic cross-sections of a three-dimensional lattice without reactivity device from those of a three-dimensional lattice with a reactivity device. Using the macroscopic cross-sections of the reference lattice and incremental cross-sections of the reactivity devices, reactor physics calculations are performed. This report summarizes input data of typical CANDU reactor physics codes, which can be utilized for the future CANDU reactor physics analysis.

  14. Reactor system on barge

    International Nuclear Information System (INIS)

    Floating electrical power plants or power plant barges add new dimensions to utility planners and agencies in the world. Intrinsically safe and economical reactors (ISER) employ steel reactor pressure vessels, which significantly reduce the weight as compared with PIUS, and provide siting versatility including barge-mounted plants. In this paper, the outline of power plant barges and barge-mounted ISERs is described. Besides their mobility, power plant barges have the salient advantages such as short delivery time and better quality control due to the outfitting in shipyards. These power plant barges may be temporarily moored or permanently grounded in shallow water at the centers of industrial complexes or the suitable areas adjacent to them, and satisfy the increasing needs for electric power. A cost-effective and technically perfect barge positioning system should be designed to meet the specific requirement for the location and its condition. Offshore siting away from coast may be applicable only to large plants of 1,000 MWe or more, and inshore siting and coastal or river siting are considered for an ISER-200 barge-mounted plant. The system of a barge-mounted ISER plant is discussed in the case of a floating type and the type on a seismic base isolator. (Kako, I.)

  15. Tokamak experimental power reactor

    International Nuclear Information System (INIS)

    A tokamak experimental power reactor has been designed that is capable of producing net electric power over a wide range of possible operating conditions. A net production of 81 MW of electricity is expected from the design reference conditions that assume a value of 0.07 for beta-toroidal, a maximum toroidal magnetic field of 9 T and a thermal conversion efficiency of 30%. Impurity control is achieved through the use of a low-Z first wall coating. This approach allows a burn time of 60 seconds without the incorporation of a divertor. The system is cooled by a dual pressurized water/steam system that could potentially provide thermal efficiencies as high as 39%. The first surface facing the plasma is a low-Z coated water cooled panel that is attached to a 20 cm thick blanket module. The vacuum boundary is removed a total of 22 cm from the plasma, thereby minimizing the amount of radiation damage in this vital component. Consideration is given in the design to the possible use of the EPR as a materials test reactor. It is estimated that the total system could be built for less than 550 million dollars

  16. The EPR reactor NDE

    International Nuclear Information System (INIS)

    In May 2006, Electricite de France decided to launch the building of the first EPRR Reactor on the Flamanville site in Normandy. The 'Flamanville 3' EPR unit is the first one to be subjected to the French Ministerial Orders of the 10 November 1999 and of the 13 December 2005 from the design phase. According to these orders, the non destructive examination (NDE) planned for the in service inspection (ISI) and for the pre service inspection (PSI) must be operational with a compulsory formal qualification. The PSI is a complete inspection of the main primary and secondary systems. The PSI's objective is to perform before the first core loading all the NDE planned for the future ISI in the same conditions, in order to have a reliable reference for the detection or for the evaluation of the possible damages during the ISI. The 'Flamanville 3' PSI is planned to start end 2010. The program consists of the development and the qualification of the NDE compatible with this new generation reactor's challenges. The paper is about: - the main EPR's objectives and the technological evolutions, - the main component modifications (which have an impact on the NDE), - the place of ISI in the general safety demonstration, - the main inspection objectives, - the NDE qualification process, - the approach to set up the ISI program, - the ISI program. (authors)

  17. Status of Japanese university reactors

    Energy Technology Data Exchange (ETDEWEB)

    Fujita, Yoshiaki [Research Reactor Institute, Kyoto Univ., Kumatori, Osaka (Japan)

    1999-08-01

    Status of Japanese university reactors, their role and value in research and education, and the spent fuel problem are presented. Some of the reactors are now faced by severe difficulties in continuing their operation services. The point of measures to solve the difficulties is suggested. (author)

  18. Brookhaven leak reactor to close

    CERN Multimedia

    MacIlwain, C

    1999-01-01

    The DOE has announced that the High Flux Beam Reactor at Brookhaven is to close for good. Though the news was not unexpected researchers were angry the decision had been taken before the review to assess the impact of reopening the reactor had been concluded (1 page).

  19. Reactor Neutrino Physics -- An Update

    OpenAIRE

    Boehm, Felix

    1999-01-01

    We review the status and the results of reactor neutrino experiments. Long baseline oscillation experiments at Palo Verde and Chooz have provided limits for the oscillation parameters while the recently proposed Kamland experiment at a baseline of more than 100km is now in the planning stage. We also describe the status of neutrino magnetic moment experiments at reactors.

  20. Chemical-vapor-deposition reactor

    Science.gov (United States)

    Chern, S.

    1979-01-01

    Reactor utilizes multiple stacked trays compactly arranged in paths of horizontally channeled reactant gas streams. Design allows faster and more efficient deposits of film on substrates, and reduces gas and energy consumption. Lack of dead spots that trap reactive gases reduces reactor purge time.

  1. Cooling system for reactor container

    International Nuclear Information System (INIS)

    Purpose: To effectively cool a reactor container upon reactor shutdown with no intrusion of metal corrosion products in coolants into the main steam pipe in a BWR type reactor. Constitution: A clean up system comprising a pipeway, a recycling pump, a non-regenerative heat exchanger and a primary coolant purifier and a regenerative heat exchanger is provided branched from a residual heat removing system and the clean up system is connected by way of a valve to a feedwater pipeway, as well as connected by way of the pipeway to the main steam pipeway at the midway of two main steam separation valves outside of the reactor container. This enables to prevent metal corrosion products floating on the surface of reactor water from introducing into the main steam pipe when the pressure vessel is filled with water. Then, since the pressure vessel is filled with primary coolants, the pressure vessel can be cooled uniformly in a short time. (Ikeda, J.)

  2. Engineering reactors for catalytic reactions

    Indian Academy of Sciences (India)

    Vivek V Ranade

    2014-03-01

    Catalytic reactions are ubiquitous in chemical and allied industries. A homogeneous or heterogeneous catalyst which provides an alternative route of reaction with lower activation energy and better control on selectivity can make substantial impact on process viability and economics. Extensive studies have been conducted to establish sound basis for design and engineering of reactors for practising such catalytic reactions and for realizing improvements in reactor performance. In this article, application of recent (and not so recent) developments in engineering reactors for catalytic reactions is discussed. Some examples where performance enhancement was realized by catalyst design, appropriate choice of reactor, better injection and dispersion strategies and recent advances in process intensification/ multifunctional reactors are discussed to illustrate the approach.

  3. Directions in advanced reactor technology

    International Nuclear Information System (INIS)

    Successful nuclear power plant concepts must simultaneously performance in terms of both safety and economics. To be attractive to both electric utility companies and the public, such plants must produce economical electric energy consistent with a level of safety which is acceptable to both the public and the plant owner. Programs for reactor development worldwide can be classified according to whether the reactor concept pursues improved safety or improved economic performance as the primary objective. When improved safety is the primary goal, safety enters the solution of the design problem as a constraint which restricts the set of allowed solutions. Conversely, when improved economic performance is the primary goal, it is allowed to be pursued only to an extent which is compatible with stringent safety requirements. The three major reactor coolants under consideration for future advanced reactor use are water, helium and sodium. Reactor development programs focuses upon safety and upon economics using each coolant are being pursued worldwide. These programs are discussed

  4. Simulator for materials testing reactors

    International Nuclear Information System (INIS)

    A real-time simulator for both reactor and irradiation facilities of a materials testing reactor, “Simulator of Materials Testing Reactors”, was developed for understanding reactor behavior and operational training in order to utilize it for nuclear human resource development and to promote partnership with developing countries which have a plan to introduce nuclear power plant. The simulator is designed based on the JMTR (Japan Materials Testing Reactor), and it simulates operation, irradiation tests and various kinds of anticipated operational transients and accident conditions caused by the reactor and irradiation facilities. The development of the simulator was sponsored by the Japanese government as one of the specialized projects of advanced research infrastructure in order to promote basic as well as applied researches. This report summarizes the simulation components, hardware specification and operation procedure of the simulator. (author)

  5. Antineutrino Monitoring of Thorium Reactors

    CERN Document Server

    Akindele, Oluwatomi A; Norman, Eric B

    2015-01-01

    Various groups have demonstrated that antineutrino monitoring can be successful in assessing the plutonium content in water-cooled nuclear reactors for nonproliferation applications. New reactor designs and concepts incorporate nontraditional fuels types and chemistry. Understanding how these properties affect the antineutrino emission from a reactor can extend the applicability of antineutrino monitoring.Thorium molten salt reactors (MSR) breed U-233, that if diverted constitute an IAEA direct use material. The antineutrino spectrum from the fission of U-233 has been determined, the feasibility of detecting the diversion of a significant quantity, 8 kg of U-233, within the IAEA timeliness goal of 30 days has been evaluated. The antineutrino emission from a thorium reactor operating under normal conditions is compared to a diversion scenario at a 25 meter standoff by evaluating the daily antineutrino count rate and the energy spectrum of the detected antineutrinos. It was found that the diversion of a signifi...

  6. Fast reactors and nuclear nonproliferation

    International Nuclear Information System (INIS)

    Problems are discussed with regard to nuclear fuel cycle resistance in fast reactors to nuclear proliferation risk due to the potential for use in military programs of the knowledge, technologies and materials gained from peaceful nuclear power applications. Advantages are addressed for fast reactors in the creation of a more reliable mode of nonproliferation in the closed nuclear fuel cycle in comparison with the existing fully open and partially closed fuel cycles of thermal reactors. Advantages and shortcomings are also discussed from the point of view of nonproliferation from the start with fast reactors using plutonium of thermal reactor spent fuel and enriched uranium fuel to the gradual transition using their own plutonium as fuel. (author)

  7. Automated reactor records evaluation framework

    International Nuclear Information System (INIS)

    The only truly reliable method for core physics code validation is comparison against experimental data – and for power nuclear reactors, the only reasonably acquirable kind of experimental data are the reactor records. However, the amount of the data coming from the reactor operation is often so vast that it can be discouraging for the code developers to use it properly. Thus, the validation package is further reduced because the data is hard to use. This paper presents an elaborate, fully automated framework, which was designed and implemented in our institute, for reactor records processing and its use for core physics code validation. The workflow, implemented as a Web 2.0 application, provides a practical and painless solution for use of reactor records data for code development and validation. (author)

  8. A implementação do programa Bolsa Família: as experiências de São Francisco de Itabapoana e Duque de Caxias Implementation of Brazil's Family Allowance Program: experiences at São Francisco de Itabapoana and Duque de Caxias

    Directory of Open Access Journals (Sweden)

    Rosana Magalhães

    2007-12-01

    Full Text Available O artigo discute os resultados da pesquisa "Implementação do Programa Bolsa Família no Estado do Rio de Janeiro: as experiências de São Francisco de Itabapoana e Duque de Caxias" realizada durante os anos de 2004 e 2005 com o apoio do CNPQ e que envolveu pesquisadores e alunos da ENSP/FIOCRUZ, UFF e UERJ. O objetivo do estudo foi analisar a implementação e a gestão local do programa Bolsa Família, identificando os principais contornos desta intervenção pública nos municípios selecionados. A aproximação com a dinâmica política e institucional local e com os mecanismos de responsabilização dos gestores, conformação de coordenações integradas e intersetoriais, oferta e acompanhamento das ações de saúde e educação e definição dos papéis dos diferentes entes federativos na operacionalização do programa contribuiu para identificar as principais tensões e os desafios ligados ao alcance de maior eqüidade e justiça social no campo das políticas de transferência condicionada de renda no país.This paper discuss the findings of a study examining the Implementation of Brazil's Family Allowance Program in Rio de Janeiro at São Francisco de Itabapoana and Duque de Caxias, conducted in 2004 - 2005 with the support of the Brazilian Science and Technology Research and Development Council (CNPq and collaboration among ENSP-FIOCRUZ, UFF and UERJ. Its purpose is to analyze this implementation process and local management practices, identifying the main contours of this program. An examination of its political and institutional dynamics, accountability mechanisms, intersectoral arenas, investments in healthcare and education, and intergovernmental arrangements helps outline some of the conflicts, tensions and challenges associated with conditional cash transfers as a core policy in the battle against poverty and social inequalities.

  9. Strategic planning for research reactors. Guidance for reactor managers

    International Nuclear Information System (INIS)

    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

  10. Neutrino Experiments at Reactors

    Science.gov (United States)

    Reines, F.; Gurr, H. S.; Jenkins, T. L.; Munsee, J. H.

    1968-09-09

    A description is given of the electron-antineutrino program using a large fission reactor. A search has been made for a neutral weak interaction via the reaction (electron antineutrino + d .> p + n + electron antineutrino), the reaction (electron antineutrino + d .> n + n + e{sup +}) has now been detected, and an effort is underway to observe the elastic scattering reaction (electron antineutrino + e{sup -} .> electron antineutrino + e{sup -}) as well as to measure more precisely the reaction (electron antineutrino + p .> n + e{sup+}). The upper limit on the elastic scattering reaction which we have obtained with our large composite NaI, plastic, liquid scintillation detector is now about 50 times the predicted value.

  11. Licensed operating reactors

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission's annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar 1990) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  12. Reactor safety systems

    International Nuclear Information System (INIS)

    The spectrum of possible accidents may become characterized by the 'maximum credible accident', which will/will not happen. Similary, the performance of safety systems in a multitude of situations is sometimes simplified to 'the emergency system will/will not work' or even 'reactors are/ are not safe'. In assessing safety, one must avoid this fallacy of reducing a complicated situation to the simple black-and-white picture of yes/no. Similarly, there is a natural tendency continually to improve the safety of a system to assure that it is 'safe enough'. Any system can be made safer and there is usually some additional cost. It is important to balance the increased safety against the increased costs. (orig.)

  13. Reactor control rod

    International Nuclear Information System (INIS)

    Object: To enable quick descent of a control rod body even when some relative phase deviation between upper drive means and wrapper tube is produced, while permitting a coolant to effectively flow into a protective tube irrespective of the position of the control rod body. Structure: In a control rod used for a nuclear reactor such as a fast breeder, an orifice which dispenses with a cylindrical guide tube and has a greater inner diameter than the outer diameter of the protective tube of the control rod body is provided on the inner side of a wrapper tube, thus permitting smooth operation of the control rod body and also permitting the coolant to effectively flow into the protective tube irrespective of the control rod body. (Horiuchi, T.)

  14. Nuclear reactor spacer assembly

    International Nuclear Information System (INIS)

    A fuel assembly for a nuclear reactor is disclosed wherein the fuel element receiving and supporting grid is comprised of a first metal, the guide tubes which pass through the grid assembly are comprised of a second metal and the grid is supported on the guide tubes by means of expanded sleeves located intermediate the grid and guide tubes. The fuel assembly is fabricated by inserting the sleeves, of initial outer diameter commensurate with the guide tube outer diameters, through the holes in the grid assembly provided for the guide tubes and thereafter expanding the sleeves radially outwardly along their entire length such that the guide tubes can subsequently be passed through the sleeves. The step of radial expansion, as a result of windows provided in the sleeves having dimensions commensurate with the geometry of the grid, mechanically captures the grid and simultaneously preloads the sleeve against the grid whereby relative motion between the grid and guide tube will be precluded

  15. Nuclear reactor measurement system

    International Nuclear Information System (INIS)

    An instrument to detect the temperature and flow-rate of the liquid metal current of a coolant fluid sample from adjacent sub-assemblies of a liquid metal-cooled nuclear reactor is described. It includes three thermocouple hot junctions mounted in series, each intended for exposure to a sample-current from a single sub-assembly, electromagnetic coils being mounted around an induction core which detects variations in the liquid metal flow-rate by deformation of the lines of flux. The instrument may also include a thermocouple to detect the mean temperature of the sample-current of coolant fluid from several sources, the result being that the temperature of the coolant fluid current in a sub-assembly may be inferred from the three temperature readings associated with this sub-assembly

  16. OECD: Halden reactor project

    International Nuclear Information System (INIS)

    The work at the Project has continued in the two main fields: test fuel irradiation and fuel research, and computer based process supervision and control. Organizations participating in the Project continue to have their fuel irradiated in the Halden Reactor in instrumented test assemblies designed and manufactured by the Project. The Project's fuel studies continue to focus on specific subjects such as fuel pellet/cladding interaction and heat transfer, fission product release and fuel behavior under loss of coolant conditions. The work on process control and supervision continues in the highly relevant fields of core control and operator-process communication. A system for predictive core control is being developed while special mathematical methods for core power distribution control are being studied. Operator-process communication studies comprise use of computer simulation on colour display as important ingredients, while the work on developing a system for interactive plant disturbance analysis continues

  17. Tokamak fusion reactor exhaust

    International Nuclear Information System (INIS)

    This report presents a compilation of papers dealing with reactor exhaust which were produced as part of the TIGER Tokamak Installation for Generating Electricity study at Culham. The papers are entitled: (1) Exhaust impurity control and refuelling. (2) Consideration of the physical problems of a self-consistent exhaust and divertor system for a long burn Tokamak. (3) Possible bundle divertors for INTOR and TIGER. (4) Consideration of various magnetic divertor configurations for INTOR and TIGER. (5) A appraisal of divertor experiments. (6) Hybrid divertors on INTOR. (7) Refuelling and the scrape-off layer of INTOR. (8) Simple modelling of the scrape-off layer. (9) Power flow in the scrape-off layer. (10) A model of particle transport within the scrape-off plasma and divertor. (11) Controlled recirculation of exhaust gas from the divertor into the scrape-off plasma. (U.K.)

  18. Safety review, assessment and inspection on research reactors, experimental reactors, nuclear heating reactors and critical facilities

    International Nuclear Information System (INIS)

    The NNSA organized mainly in 1999 to complete the verification loop in core of the high flux experimental reactor with the 2000 kW fuel elements, the re-starting of China Pulsed Reactor, review and assessment on nuclear safety for the restarting of the Uranium-water critical Facility and treat the fracture event with the fuel tubes in the HWRR

  19. Power Reactors. Appendix VIII

    International Nuclear Information System (INIS)

    Decommissioning of nuclear facilities in many countries has evolved into a mature industry that has benefited from experience gained from previous projects and decommissioning costs can now be estimated to a good degree of accuracy. As a result of lessons learned, future decommissioning projects can be performed with higher levels of efficiency. Decommissioning of old power reactors is in progress in several countries. In some cases, decommissioning has been completed (i.e. plant sites have been released from regulatory control), while in other countries decommissioning is still in progress. Several large power reactors have been successfully decommissioned since 1995. The key areas of particular importance for decommissioning are decontamination, radiation protection, dismantling and demolition. The technologies which can be used for these tasks are commonly available on the market, but effective decommissioning still depends on an optimal choice of technologies, including site specific developments. It is not possible to recommend the use of a single specific technology for dismantling, demolition, segmentation or decontamination; rather, it is good practice to take into account as much information as possible from other decommissioning projects and to draw comparisons between various techniques in order to choose the one with the best performance in a particular situation. The exchange of information on all types of decommissioning experience, including decommissioning techniques and their applicability as well as disadvantages for specific tasks, is taking place on various levels, such as: — Collaborative working groups established by international organizations such as the IAEA, the OECD Nuclear Energy Agency and the European Commission and the publication of technical reports by such organizations; — National and international conferences; — Bilateral or multilateral cooperation and information exchange between organizations with responsibilities for

  20. Advanced fusion reactor

    Energy Technology Data Exchange (ETDEWEB)

    Tomita, Yukihiro [National Inst. for Fusion Science, Toki, Gifu (Japan)

    2003-04-01

    The main subjects on fusion research are now on D-T fueled fusion, mainly due to its high fusion reaction rate. However, many issues are still remained on the wall loading by the 14 MeV neutrons. In the case of D-D fueled fusion, the neutron wall loading is still remained, though the technology related to tritium breeding is not needed. The p-{sup 6}Li and p-{sup 11}B fueled fusions are not estimated to be the next generation candidate until the innovated plasma confinement technologies come in useful to achieve the high performance plasma parameters. The fusion reactor of D-{sup 3}He fuels has merits on the smaller neutron wall loading and tritium handling. However, there are difficulties on achieving the high temperature plasma more than 100 keV. Furthermore the high beta plasma is needed to decrease synchrotron radiation loss. In addition, the efficiency of the direct energy conversion from protons coming out from fusion reaction is one of the key parameters in keeping overall power balance. Therefore, open magnetic filed lines should surround the plasma column. In this paper, we outlined the design of the commercial base reactor (ARTEMIS) of 1 GW electric output power configured by D-{sup 3}He fueled FRC (Field Reversed Configuration). The ARTEMIS needs 64 kg of {sup 3}He per a year. On the other hand, 1 million tons of {sup 3}He is estimated to be in the moon. The {sup 3}He of about 10{sup 23} kg are to exist in gaseous planets such as Jupiter and Saturn. (Y. Tanaka)

  1. Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Following the accident at Chernobyl nuclear reactor, WHO organized on 6 May 1986 in Copenhagen a one day consultation of experts with knowledge in the fields of meteorology, radiation protection, biological effects, reactor technology, emergency procedures, public health and psychology in order to analyse the development of events and their consequences and to provide guidance as to the needs for immediate public health action. The present report provides detailed information on the transportation and dispersion of the radioactive material in the atmosphere, especially volatile elements, during the release period 26 April - 5 May. Presented are the calculated directions and locations of the radioactive plume over Europe in the first 5 days after the accident, submitted by the Swedish Meteorological and Hydrological Institute. The calculations have been made for two heights, 1500m and 750m and the plume directions are grouped into five periods, covering five European areas. The consequences of the accident inside the USSR and the radiological consequences outside the USSR are presented including the exposure routes and the biological effects, paying particular attention to iodine-131 effects. Summarized are the first reported measured exposure rates above background, iodine-131 deposition and concentrations in milk and the remedial actions taken in various European countries. Concerning the cesium-137 problem, based on the UNSCEAR assessment of the consequences of the nuclear fallout, one concludes that the cesium contamination outside the USSR is not likely to cause any serious problems. Finally, the conclusions and the recommendations of the meeting, taking into account both the short-term and longer term considerations are presented

  2. Nuclear reactor fuelling machine

    International Nuclear Information System (INIS)

    The refuelling machine described comprises a rotatable support structure having a guide tube attached to it by a parellel linkage mechanism, whereby the guide tube can be displaced sideways from the support structure. A gripper unit is housed within the guide tube for gripping the end of a fuel assembly or other reactor component and has means for maintenance in the engaging condition during travel of the unit along the guide tube, except for a small portion of the travel at one end of the guide tube, where the inner surface of the guide tube is shaped so as to maintain the gripper unit in a disengaging condition. The gripper unit has a rotatable head, means for moving it linearly within the guide tube so that a component carried by the unit can be housed in the guide tube, and means for rotating the head of the unit through 1800 relative to its body, to effect rotation of a component carried by the unit. The means for rotating the head of the gripper unit comprises ring and pinion gearing, operable through a series of rotatable shafts interconnected by universal couplings. The reason for provision for 1800 rotation is that due to the variation in the neutron flux across the reactor core the side of a fuel assembly towards the outside of the core will be subjected to a lower neutron flux and therefore will grow less than the side of the fuel assembly towards the inside of the core. This can lead to bowing and possible jamming of the fuel assemblies. Full constructional details are given. See also BP 1112384. (U.K.)

  3. Reliability of reactor materials

    International Nuclear Information System (INIS)

    This report is the final technical report of the fracture mechanics part of the Reliability of Reactor Materials Programme, which was carried out at the Technical Research Centre of Finland (VTT) through the years 1981 to 1983. Research and development work was carried out in five major areas, viz. statistical treatment and modelling of cleavage fracture, crack arrest, ductile fracture, instrumented impact testing as well as comparison of numerical and experimental elastic-plastic fracture mechanics. In the area of cleavage fracture the critical variables affecting the fracture of steels are considered in the frames of a statistical model, so called WST-model. Comparison of fracture toughness values predicted by the model and corresponding experimental values shows excellent agreement for a variety of microstructures. different posibilities for using the model are discussed. The development work in the area of crack arrest testing was concentrated in the crack starter properties, test arrangement and computer control. A computerized elastic-plastic fracture testing method with a variety of test specimen geometries in a large temperature range was developed for a routine stage. Ductile fracture characteristics of reactor pressure vessel steel A533B and comparable weld material are given. The features of a new, patented instrumented impact tester are described. Experimental and theoretical comparisons between the new and conventional testers indicated clearly the improvements achieved with the new tester. A comparison of numerical and experimental elastic-plastic fracture mechanics capabilities at VTT was carried out. The comparison consisted of two-dimensional linear elastic as well as elastic-plastic finite element analysis of four specimen geometries and equivalent experimental tests. (author)

  4. Licensed reactor nuclear safety criteria applicable to DOE reactors

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards.

  5. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards

  6. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  7. On reactor type comparisons for the next generation of reactors

    International Nuclear Information System (INIS)

    In this paper, we present a broad comparison of studies for a selected set of parameters for different nuclear reactor types including the next generation. This serves as an overview of key parameters which provide a semi-quantitative decision basis for selecting nuclear strategies. Out of a number of advanced reactor designs of the LWR type, gas cooled type, and FBR type, currently on the drawing board, the Advanced Light Water Reactors (ALWR) seem to have some edge over other types of the next generation of reactors for the near-term application. This is based on a number of attributes related to the benefit of the vast operating experience with LWRs coupled with an estimated low risk profile, economics of scale, degree of utilization of passive systems, simplification in the plant design and layout, modular fabrication and manufacturing. 32 refs., 1 fig., 3 tabs

  8. Ageing management for research reactors

    International Nuclear Information System (INIS)

    During the past several years, ageing of research reactor facilities continues to be an important safety issue. Despite the efforts exerted by operating organizations and regulatory authorities worldwide to address this issue, the need for an improved strategy as well as the need for establishing and implementing a systematic approach to ageing management at research reactors was identified. This paper discusses, on the basis of the IAEA Safety Standards, the effect of ageing on the safety of research reactors and presents a proactive strategy for ageing management. A systematic approach for ageing management is developed and presented together with its key elements, along with practical examples for their application. (author)

  9. Fueling of tandem mirror reactors

    International Nuclear Information System (INIS)

    This paper summarizes the fueling requirements for experimental and demonstration tandem mirror reactors (TMRs), reviews the status of conventional pellet injectors, and identifies some candidate accelerators that may be needed for fueling tandem mirror reactors. Characteristics and limitations of three types of accelerators are described; neutral beam injectors, electromagnetic rail guns, and laser beam drivers. Based on these characteristics and limitations, a computer module was developed for the Tandem Mirror Reactor Systems Code (TMRSC) to select the pellet injector/accelerator combination which most nearly satisfies the fueling requirements for a given machine design

  10. Concept for LEU Burst Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Klein, Steven Karl [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kimpland, Robert Herbert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-03-07

    Design and performance of a proposed LEU burst reactor are sketched. Salient conclusions reached are the following: size would be ~1,500 kg or greater, depending on the size of the central cavity; internal stresses during burst require split rings for relief; the reactor would likely require multiple control and safety rods for fine control; the energy spectrum would be comparable to that of HEU machines; and burst yields and steady-state power levels will be significantly greater in an LEU reactor.

  11. Random processes in nuclear reactors

    CERN Document Server

    Williams, M M R

    1974-01-01

    Random Processes in Nuclear Reactors describes the problems that a nuclear engineer may meet which involve random fluctuations and sets out in detail how they may be interpreted in terms of various models of the reactor system. Chapters set out to discuss topics on the origins of random processes and sources; the general technique to zero-power problems and bring out the basic effect of fission, and fluctuations in the lifetime of neutrons, on the measured response; the interpretation of power reactor noise; and associated problems connected with mechanical, hydraulic and thermal noise sources

  12. Safety of VVER-440 reactors

    CERN Document Server

    Slugen, Vladimir

    2011-01-01

    Safety of VVER-440 Reactors endeavours to promote an increase in the safety of VVER-440 nuclear reactors via the improvement of fission products limitation systems and the implementation of special non-destructive spectroscopic methods for materials testing. All theoretical and experimental studies performed the by author over the last 25 years have been undertaken with the aim of improving VVER-440 defence in depth, which is one of the most important principle for ensuring safety in nuclear power plants. Safety of VVER-440 Reactors is focused on the barrier system through which the safety pri

  13. BR2 reactor neutron beams

    International Nuclear Information System (INIS)

    The use of reactor neutron beams is becoming increasingly more widespread for the study of some properties of condensed matter. It is mainly due to the unique properties of the ''thermal'' neutrons as regards wavelength, energy, magnetic moment and overall favorable ratio of scattering to absorption cross-sections. Besides these fundamental reasons, the impetus for using neutrons is also due to the existence of powerful research reactors (such as BR2) built mainly for nuclear engineering programs, but where a number of intense neutron beams are available at marginal cost. A brief introduction to the production of suitable neutron beams from a reactor is given. (author)

  14. Nuclear reactor PBMR and cogeneration; Reactor nuclear PBMR y cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J. R.; Alonso V, G., E-mail: ramon.ramirez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    In recent years the nuclear reactor designs for the electricity generation have increased their costs, so that at the moment costs are managed of around the 5000 US D for installed kw, reason for which a big nuclear plant requires of investments of the order of billions of dollars, the designed reactors as modular of low power seek to lighten the initial investment of a big reactor dividing the power in parts and dividing in modules the components to lower the production costs, this way it can begin to build a module and finished this to build other, differing the long term investment, getting less risk therefore in the investment. On the other hand the reactors of low power can be very useful in regions where is difficult to have access to the electric net being able to take advantage of the thermal energy of the reactor to feed other processes like the water desalination or the vapor generation for the processes industry like the petrochemical, or even more the possible hydrogen production to be used as fuel. In this work the possibility to generate vapor of high quality for the petrochemical industry is described using a spheres bed reactor of high temperature. (Author)

  15. Reactor Safety Commission Code of Practice for Pressurized Water Reactors

    International Nuclear Information System (INIS)

    The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

  16. Breeder Reactors, Understanding the Atom Series.

    Science.gov (United States)

    Mitchell, Walter, III; Turner, Stanley E.

    The theory of breeder reactors in relationship to a discussion of fission is presented. Different kinds of reactors are characterized by the cooling fluids used, such as liquid metal, gas, and molten salt. The historical development of breeder reactors over the past twenty-five years includes specific examples of reactors. The location and a brief…

  17. FASTER test reactor preconceptual design report summary

    Energy Technology Data Exchange (ETDEWEB)

    Grandy, C. [Argonne National Lab. (ANL), Argonne, IL (United States); Belch, H. [Argonne National Lab. (ANL), Argonne, IL (United States); Brunett, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Heidet, F. [Argonne National Lab. (ANL), Argonne, IL (United States); Hill, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Hoffman, E. [Argonne National Lab. (ANL), Argonne, IL (United States); Jin, E. [Argonne National Lab. (ANL), Argonne, IL (United States); Mohamed, W. [Argonne National Lab. (ANL), Argonne, IL (United States); Moisseytsev, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Passerini, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Sienicki, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Sumner, T. [Argonne National Lab. (ANL), Argonne, IL (United States); Vilim, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Hayes, Steven [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-02-29

    The FASTER reactor plant is a sodium-cooled fast spectrum test reactor that provides high levels of fast and thermal neutron flux for scientific research and development. The 120MWe FASTER reactor plant has a superheated steam power conversion system which provides electrical power to a local grid allowing for recovery of operating costs for the reactor plant.

  18. Research reactors: design, safety requirements and applications

    International Nuclear Information System (INIS)

    There are two types of reactors: research reactors or power reactors. The difference between the research reactor and energy reactor is that the research reactor has working temperature and fuel less than the power reactor. The research reactors cooling uses light or heavy water and also research reactors need reflector of graphite or beryllium to reduce the loss of neutrons from the reactor core. Research reactors are used for research training as well as testing of materials and the production of radioisotopes for medical uses and for industrial application. The difference is also that the research reactor smaller in terms of capacity than that of power plant. Research reactors produce radioactive isotopes are not used for energy production, the power plant generates electrical energy. In the world there are more than 284 reactor research in 56 countries, operates as source of neutron for scientific research. Among the incidents related to nuclear reactors leak radiation partial reactor which took place in three mile island nuclear near pennsylvania in 1979, due to result of the loss of control of the fission reaction, which led to the explosion emitting hug amounts of radiation. However, there was control of radiation inside the building, and so no occurred then, another accident that lead to radiation leakage similar in nuclear power plant Chernobyl in Russia in 1986, has led to deaths of 4000 people and exposing hundreds of thousands to radiation, and can continue to be effect of harmful radiation to affect future generations. (author)

  19. Conceptual design study of JSFR reactor building

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, T.; Katoh, A.; Chikazawa, Y. [Japan Atomic Energy Agency (JAEA), 4002 Narita, Oarai, Ibaraki 311-1393 (Japan); Ohya, T.; Iwasaki, M.; Hara, H.; Akiyama, Y. [Mitsubishi FBR Systems, Inc. MFBR, 34-17, Jingumae 2-chome, Shibuya, Tokyo 150-0001 (Japan)

    2012-07-01

    Japan Sodium-cooled Fast Reactor (JSFR) is planning to adopt the new concepts of reactor building. One is that the steel plate reinforced concrete is adopted for containment vessel and reactor building. The other is the advanced seismic isolation system. This paper describes the detail of new concepts for JSFR reactor building and engineering evaluation of the new concepts. (authors)

  20. FASTER test reactor preconceptual design report summary

    International Nuclear Information System (INIS)

    The FASTER reactor plant is a sodium-cooled fast spectrum test reactor that provides high levels of fast and thermal neutron flux for scientific research and development. The 120MWe FASTER reactor plant has a superheated steam power conversion system which provides electrical power to a local grid allowing for recovery of operating costs for the reactor plant.

  1. Light water reactor safety research

    International Nuclear Information System (INIS)

    As the technology of light water reactors (LWR) was being commercialized, the German Federal Government funded the reactor safety research program, which was conducted by national research centers, universities, and industry, and which led to the establishment, in early 1972, of the Nuclear Safety Project in Karlsruhe. In the seventies, the PNS project mainly studied the loss-of-coolant accident. Numerous experiments were run and computer codes developed for this purpose. In the eighties, the Karlsruhe Nuclear Research Center contributed to the German Risk Study, investigating especially core meltdown accidents under the impact of the events at Three Mile Island-2 and Chernobyl-4. Safety research in the nineties is concentrated on the requirements of future reactor generations, such as the European Pressurized Water Reactor (EPR) or potential approaches which, at the present time, are discernible only as tentative theoretical designs. (orig.)

  2. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, L.R.; Hayes, D.W.; Hunter, C.H.; Marter, W.L.; Moyer, R.A.

    1989-12-01

    This volume is a reactor operation environmental information document for the Savannah River Plant. Topics include meteorology, surface hydrology, transport, environmental impacts, and radiation effects. 48 figs., 56 tabs. (KD)

  3. Fuel for advanced CANDU reactors

    International Nuclear Information System (INIS)

    The CANDU reactor system has proven itself to be a world leader in terms of station availability and low total unit energy cost. In 1985 for example, four of the top ten reactor units in the world were CANDU reactors operating in South Korea and Canada. This excellent operating record requires an equivalent performance record of the low-cost, natural uranium fuel. Future CANDU reactors will be an evolution of the present design. Engineering work is under way to refine the existing CANDU 600 and to incorporate state-of-the-art technology, reducing the capital cost and construction schedule. In addition, a smaller CANDU 300 plant has been designed using proven CANDU 600 technology and components but with an innovative new plant layout that makes it cost competitive with coal fired plants. For the long term, work on advanced fuel cycles and major system improvements is underway ensuring that CANDU plants will stay competitive well into the next century

  4. Conceptual design of RFC reactor

    International Nuclear Information System (INIS)

    A parametic analysis and a preliminary conceptual design for RFC reactor (including cusp field) with and without alpha particle heating are described. Steady state operations can be obtained for various RF ponderomotive potential in cases of alpha particle heating. (author)

  5. Methanogenesis in Thermophilic Biogas Reactors

    DEFF Research Database (Denmark)

    Ahring, Birgitte Kiær

    1995-01-01

    against Methanothrix soehngenii or Methanothrix CALS-I in any of the thermophilic biogas reactors examined. Studies using 2-14C-labeled acetate showed that at high concentrations (more than approx. 1 mM) acetate was metabolized via the aceticlastic pathway, transforming the methyl-group of acetate...... microorganism into methane. In thermophilic biogas reactors,, acetate oxidizing cultures occupied the niche of Methanothrix species, aceticlastic methanogens which dominate at low acetate concentrations in mesophilic systems. Normally, thermophilic biogas reactors are operated at temperatures from 52 to 560 C....... Experiments using biogas reactors fed with cow manure showed that the same biogas yield found at 550 C could be obtained at 610 C after a long adaptation period. However, propionate degradation was inhibited by increasing the temperature....

  6. Teaching About Nature's Nuclear Reactors

    CERN Document Server

    Herndon, J M

    2005-01-01

    Naturally occurring nuclear reactors existed in uranium deposits on Earth long before Enrico Fermi built the first man-made nuclear reactor beneath Staggs Field in 1942. In the story of their discovery, there are important lessons to be learned about scientific inquiry and scientific discovery. Now, there is evidence to suggest that the Earth's magnetic field and Jupiter's atmospheric turbulence are driven by planetary-scale nuclear reactors. The subject of planetocentric nuclear fission reactors can be a jumping off point for stimulating classroom discussions about the nature and implications of planetary energy sources and about the geomagnetic field. But more importantly, the subject can help to bring into focus the importance of discussing, debating, and challenging current thinking in a variety of areas.

  7. RA reactor operation and maintenance

    International Nuclear Information System (INIS)

    This volume includes the final report on RA reactor operation and utilization of the experimental facilities in 1962, detailed analysis of the system for heavy water distillation and calibration of the system for measuring the activity of the air

  8. Technique of nuclear reactors controls

    International Nuclear Information System (INIS)

    This report deal about 'Techniques of control of the nuclear reactors' in the goal to achieve the control of natural uranium reactors and especially the one of Saclay. This work is mainly about the measurement into nuclear parameters and go further in the measurement of thermodynamic variables,etc... putting in relief the new features required on behalf of the detectors because of their use in the thermal neutrons flux. In the domain of nuclear measurement, we indicate the realizations and the results obtained with thermal neutron detectors and for the measurement of ionizations currents. We also treat the technical problem of the start-up of a reactor and of the reactivity measurement. We give the necessary details for the comprehension of all essential diagrams and plans put on, in particular, for the reactor of Saclay. (author)

  9. Jules Horowitz Reactor, basic design

    Energy Technology Data Exchange (ETDEWEB)

    Bergamaschi, Y.; Bouilloux, Y.; Chantoin, P.; Guigon, B.; Bravo, X.; Germain, C.; Rommens, M.; Tremodeux, P

    2003-07-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it. It has the ambition to provide the necessary nuclear data and maintain a fission research capacity in Europe after 2010. This capacity should be service-oriented. It will be established in Cadarache. The Jules Horowitz reactor will also: - represent a significant step in term of performances and experimental capabilities, - be designed with a high flexibility, in order to satisfy the current demand from European industry, research and be able to accommodate future requirements, - reach a high level of safety, according to the best current practice. This paper will present the main functionalities and the design options resulting from the 'preliminary design' studies. (authors)

  10. Unique features of space reactors

    Science.gov (United States)

    Buden, David

    Space reactors are designed to meet a unique set of requirements; they must be sufficiently compact to be launched in a rocket to their operational location, operate for many years without maintenance and servicing, operate in extreme environments, and reject heat by radiation to space. To meet these restrictions, operating temperatures are much greater than in terrestrial power plants, and the reactors tend to have a fast neutron spectrum. Currently, a new generation of space reactor power plants is being developed. The major effort is in the SP-100 program, where the power plant is being designed for seven years of full power, and no maintenance operation at a reactor outlet operating temperature of 1350 K.

  11. Advanced Catalytic Hydrogenation Retrofit Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Reinaldo M. Machado

    2002-08-15

    Industrial hydrogenation is often performed using a slurry catalyst in large stirred-tank reactors. These systems are inherently problematic in a number of areas, including industrial hygiene, process safety, environmental contamination, waste production, process operability and productivity. This program proposed the development of a practical replacement for the slurry catalysts using a novel fixed-bed monolith catalyst reactor, which could be retrofitted onto an existing stirred-tank reactor and would mitigate many of the minitations and problems associated with slurry catalysts. The full retrofit monolith system, consisting of a recirculation pump, gas/liquid ejector and monolith catalyst, is described as a monolith loop reactor or MLR. The MLR technology can reduce waste and increase raw material efficiency, which reduces the overall energy required to produce specialty and fine chemicals.

  12. Advanced Carbothermal Electric Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — ORBITEC proposes to develop the Advanced Carbothermal Electric (ACE) reactor to efficiently extract oxygen from lunar regolith. Unlike state-of-the-art carbothermal...

  13. Advanced Carbothermal Electric Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The overall objective of the Phase 1 effort was to demonstrate the technical feasibility of the Advanced Carbothermal Electric (ACE) Reactor concept. Unlike...

  14. Gas-cooled fast breeder reactor

    International Nuclear Information System (INIS)

    Almost all the R D works of gas-cooled fast breeder reactor in the world were terminated at the end of the year 1980. In order to show that the R D termination was not due to technical difficulties of the reactor itself, the present paper describes the reactor plant concept, reactor performances, safety, economics and fuel cycle characteristics of the reactor, and also describes the reactor technologies developed so far, technological problems remained to be solved and planned development schedules of the reactor. (author)

  15. Solid State Reactor Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Mays, G.T.

    2004-03-10

    The Solid State Reactor (SSR) is an advanced reactor concept designed to take advantage of Oak Ridge National Laboratory's (ORNL's) recently developed graphite foam that has enhanced heat transfer characteristics and excellent high-temperature mechanical properties, to provide an inherently safe, self-regulated, source of heat for power and other potential applications. This work was funded by the U.S. Department of Energy's Nuclear Energy Research Initiative (NERI) program (Project No. 99-064) from August 1999 through September 30, 2002. The initial concept of utilizing the graphite foam as a basis for developing an advanced reactor concept envisioned that a suite of reactor configurations and power levels could be developed for several different applications. The initial focus was looking at the reactor as a heat source that was scalable, independent of any heat removal/power conversion process. These applications might include conventional power generation, isotope production and destruction (actinides), and hydrogen production. Having conducted the initial research on the graphite foam and having performed the scoping parametric analyses from neutronics and thermal-hydraulic perspectives, it was necessary to focus on a particular application that would (1) demonstrate the viability of the overall concept and (2) require a reasonably structured design analysis process that would synthesize those important parameters that influence the concept the most as part of a feasible, working reactor system. Thus, the application targeted for this concept was supplying power for remote/harsh environments and a design that was easily deployable, simplistic from an operational standpoint, and utilized the new graphite foam. Specifically, a 500-kW(t) reactor concept was pursued that is naturally load following, inherently safe, optimized via neutronic studies to achieve near-zero reactivity change with burnup, and proliferation resistant. These four major areas

  16. Material test reactor fuel research at the BR2 reactor

    International Nuclear Information System (INIS)

    The construction of new, high performance material test reactor or the conversion of such reactors' core from high enriched uranium (HEU) to low enriched uranium (LEU) based fuel requires several fuel qualification steps. For the conversion of high performance reactors, high density dispersion or monolithic fuel types are being developed. The Uranium-Molybdenum fuel system has been selected as reference system for the qualification of LEU fuels. For reactors with lower performance characteristics, or as medium enriched fuel for high performance reactors, uranium silicide dispersion fuel is applied. However, on the longer term, the U-Mo based fuel types may offer a more efficient fuel alternative and-or an easier back-end solution with respect to the silicide based fuels. At the BR2 reactor of the Belgian nuclear research center, SCK-CEN in Mol, several types of fuel testing opportunities are present to contribute to such qualification process. A generic validation test for a selected fuel system is the irradiation of flat plates with representative dimensions for a fuel element. By flexible positioning and core loading, bounding irradiation conditions for fuel elements can be performed in a standard device in the BR2. For fuel element designs with curved plates, the element fabrication method compatibility of the fuel type can be addressed by incorporating a set of prototype fuel plates in a mixed driver fuel element of the BR2 reactor. These generic types of tests are performed directly in the primary coolant flow conditions of the BR2 reactor. The experiment control and interpretation is supported by detailed neutronic and thermal-hydraulic modeling of the experiments. Finally, the BR2 reactor offers the flexibility for irradiation of full size prototype fuel elements, as 200mm diameter irradiation channels are available. These channels allow the accommodation of various types of prototype fuel elements, eventually using a dedicated cooling loop to provide the

  17. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Iwashige, Kengo

    1996-06-21

    In an LMFBR type reactor, partitions are disposed to a coolant channel at positions lower than the free liquid level, and the width of the partitions is adapted to have a predetermined condition. Namely, when low temperature fluid overflowing the wall of the coolant channel, flows down and collided against the free liquid surface in the coolant channel, since the dropping speed thereof is reduced abruptly, large pressure waves are caused by kinetic force of the low temperature fluid. However, if appropriate numbers of partitions having an appropriate shape are formed, the dropping speed of the low temperature fluid is moderated to reduce the pressure waves. In addition, since the pressure waves are dispersed to the circumferential and lateral directions of the coolant flow channel respectively, the propagation of the pressure waves can be prevented effectively. Further, when the flow of the low temperature fluid is changed to the circumferential direction, for example, by earthquakes, since the partitions act as members resisting against the circumferential change of the low temperature fluid, the change of the direction can be suppressed. (N.H.)

  18. Natural convection type reactor

    International Nuclear Information System (INIS)

    In a natural convection type nuclear reactor, recycling flow rate of coolants is increased and the amount of entrained bubbles are increased as the driving force is increased, so that bubbles are not separated completely even if a stagnation region is disposed. Then, a space opened only at the upper portion is disposed at the outer circumference of the upper end of a riser for storing overflown coolants temporarily. The flow of coolants incorporating steam bubbles uprising in the riser turns into the horizontal direction at the upper end of the riser wall and flows into the coolant reservoir. In the coolant reservoir, since the momentum of the coolants is lost and the flow is stagnated, the bubbles are easily released to the upper space. Coolants, after releasing the bubbles, further overflow and descend in the downcomer. Then, the bubbles can be separated undergoing no influence of the driving force caused as the sum of the uprising force in the riser and the water head pressure in the downcomer, to prevent increase of carry under due to increase of the driving force. (N.H.)

  19. Reactor Simulator Testing Overview

    Science.gov (United States)

    Schoenfeld, Michael P.

    2013-01-01

    Test Objectives Summary: a) Verify operation of the core simulator, the instrumentation & control system, and the ground support gas and vacuum test equipment. b) Examine cooling & heat regeneration performance of the cold trap purification. c) Test the ALIP pump at voltages beyond 120V to see if the targeted mass flow rate of 1.75 kg/s can be obtained in the RxSim. Testing Highlights: a) Gas and vacuum ground support test equipment performed effectively for operations (NaK fill, loop pressurization, and NaK drain). b) Instrumentation & Control system effectively controlled loop temperature and flow rates or pump voltage to targeted settings and ramped within prescribed constraints. It effectively interacted with reactor simulator control model and defaulted back to temperature control mode if the transient fluctuations didn't dampen. c) Cold trap design was able to obtain the targeted cold temperature of 480 K. An outlet temperature of 636 K was obtained which was lower than the predicted 750 K but 156 K higher than the minimum temperature indicating the design provided some heat regeneration. d) ALIP produce a maximum flow rate of 1.53 kg/s at 800 K when operated at 150 V and 53 Hz.

  20. Reactor Simulator Testing

    Science.gov (United States)

    Schoenfeld, Michael P.; Webster, Kenny L.; Pearson, Boise J.

    2013-01-01

    As part of the Nuclear Systems Office Fission Surface Power Technology Demonstration Unit (TDU) project, a reactor simulator test loop (RxSim) was design & built to perform integrated testing of the TDU components. In particular, the objectives of RxSim testing was to verify the operation of the core simulator, the instrumentation and control system, and the ground support gas and vacuum test equipment. In addition, it was decided to include a thermal test of a cold trap purification design and a pump performance test at pump voltages up to 150 V since the targeted mass flow rate of 1.75 kg/s was not obtained in the RxSim at the originally constrained voltage of 120 V. This paper summarizes RxSim testing. The gas and vacuum ground support test equipment performed effectively in NaK fill, loop pressurization, and NaK drain operations. The instrumentation and control system effectively controlled loop temperature and flow rates or pump voltage to targeted settings. The cold trap design was able to obtain the targeted cold temperature of 480 K. An outlet temperature of 636 K was obtained which was lower than the predicted 750 K but 156 K higher than the cold temperature indicating the design provided some heat regeneration. The annular linear induction pump (ALIP) tested was able to produce a maximum flow rate of 1.53 kg/s at 800 K when operated at 150 V and 53 Hz.

  1. Novel Catalytic Membrane Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Stuart Nemser, PhD

    2010-10-01

    There are many industrial catalytic organic reversible reactions with amines or alcohols that have water as one of the products. Many of these reactions are homogeneously catalyzed. In all cases removal of water facilitates the reaction and produces more of the desired chemical product. By shifting the reaction to right we produce more chemical product with little or no additional capital investment. Many of these reactions can also relate to bioprocesses. Given the large number of water-organic compound separations achievable and the ability of the Compact Membrane Systems, Inc. (CMS) perfluoro membranes to withstand these harsh operating conditions, this is an ideal demonstration system for the water-of-reaction removal using a membrane reactor. Enhanced reaction synthesis is consistent with the DOE objective to lower the energy intensity of U.S. industry 25% by 2017 in accord with the Energy Policy Act of 2005 and to improve the United States manufacturing competitiveness. The objective of this program is to develop the platform technology for enhancing homogeneous catalytic chemical syntheses.

  2. OECD Halden Reactor Project

    International Nuclear Information System (INIS)

    The OECD Halden Reactor Project is both the oldest and the only one still in operation of the three major joint undertakings established at the inception of the OECD Nuclear Energy Agency. This publication has been printed in connection with its twenty-fifth anniversary as an international project. After presentation of the history and organization of the project, a thorough description of the past and present activities in the field of fuel performance and process control and surveillance is given. The projects's fuel testing programme is now focuessed on an investigation to define safety margins under normal operations as well as under various kinds of accident situations. Fuel research is also concerned with the characterisation of long term effects with regard to efficiency, operational safety and mapping of reliability and durability in the case of accidents with loss of coolant. In the field of process control and surveillance, research work is directly linked to the use of computers and colour graphics as tools in the control room. A fullscale simulator-based model and experimental control room has been constructed. The first experiments to be carried out in this laboratory will investigate the advantage of analysing alarms before they are presented to the operator. (RF)

  3. Nuclear reactor container

    International Nuclear Information System (INIS)

    A gas containing vessel has a water pool which is in communication with a dry well containing a reactor pressure vessel by way of a communication pipe is disposed. A capacity of a gas phase portion of the gas containing chamber, a capacity of the dry well, a water depth of a bent tube communicating the dry well with a pressure suppression pool of a pressure suppression chamber and a water depth of the communication pipe are determined so as to satisfy specific conditions. Since the water depth of the communication pipe is less than the water depth of the bent tube, incondensible gases and steams in the dry well flow into the water pool of the gas containing chamber at the initial stage of loss of coolant accident. Subsequently, steams in the dry well flow into the pressure suppression pool of the pressure suppression chamber by way of the bent tube. Accordingly, since the incondensible gases in the dry well do not flow into the pressure suppression chamber, pool swelling phenomenon in the pressure suppression chamber is not caused even if the water depth of the bent tube which leads to the pressure suppression chamber is great. Further, pressure increase due to transfer of the incondensible gases is decreased. (I.N.)

  4. OECD Halden reactor project

    International Nuclear Information System (INIS)

    A major part of the current research programme is devoted to irradiation experiments with a wide variety of heavily instrumented test fuel assemblies, in order to study the thermal and mechanical behavior of fuel rods through in-core measurements, in particular various forms of deformation of cladding and fuel as related to operational conditions and fuel rod design parameters. From these measurements mathematical models are being developed to explain quantitatively the deformation behavior, as well as the thermal properties of the fuel. During 1974, fifty-six instrumented fuel assemblies were irradiated in these experiments. Another major part of the Halden programme is aimed at the development and demonstration of advanced computer-based methods for plant and reactor core control, for safety and protection, and for overall supervision of nuclear power stations. Both the control methods themselves and the associated measurement and control apparatus are being elaborated, and during the year particular progress was made with the ''OPCOM'' process operator communication system

  5. MOLTEN FLUORIDE NUCLEAR REACTOR FUEL

    Science.gov (United States)

    Barton, C.J.; Grimes, W.R.

    1960-01-01

    Molten-salt reactor fuel compositions consisting of mixtures of fluoride salts are reported. In its broadest form, the composition contains an alkali fluoride such as sodium fluoride, zirconium tetrafluoride, and a uranium fluoride, the latter being the tetrafluoride or trifluoride or a mixture of the two. An outstanding property of these fuel compositions is a high coeffieient of thermal expansion which provides a negative temperature coefficient of reactivity in reactors in which they are used.

  6. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.)

  7. Fractals in Power Reactor Noise

    International Nuclear Information System (INIS)

    In this work the non- lineal dynamic problem of power reactor is analyzed using classic concepts of fractal analysis as: attractors, Hausdorff-Besikovics dimension, phase space, etc. A new non-linear problem is also analyzed: the discrimination of chaotic signals from random neutron noise signals and processing for diagnosis purposes. The advantages of a fractal analysis approach in the power reactor noise are commented in details

  8. Stellarator fusion reactors - an overview

    International Nuclear Information System (INIS)

    The stellarator system offers a distinct alternative to the mainline approaches to magnetic fusion power and has several potentially major advantages. Since the first proposal of the stellarator concept many reactor studies have been published and these studies reflect the large variety of stellarator configurations. The main representatives are the continuous-coil configurations and the modular-coil configurations. As a continuation of the LHD experiment two reactor configurations, FFHR1 and FFHR2, have been investigated, which use continuous helical windings for providing the magnetic field. The modular coil concept has been realized in the MHH-reactor study (USA 1997) and in the Helias reactor. The Helias reactor combines the principle of plasma optimisation with a modular coil system. The paper also discusses the issues associated with the blanket and the maintenance process. Stellarator configurations with continuous coils such as LHD possess a natural helical divertor, which can be used favourably for impurity control. In advanced stellarators with modular coils the same goal can be achieved by the island divertor. Plasma parameters in the various stellarator reactors are computed on the basis of presently known scaling laws showing that confinement is sufficiently good to provide ignition and self-sustained burn. (author)

  9. Materials requirements for fusion reactors

    International Nuclear Information System (INIS)

    Once the physics of fusion devices is understood, one or more experimental power reactors (EPR) are planned which will produce net electrical power. The structural material for the device will probably be a modification of an austenitic stainless steel. Unlike fission reactors, whose pressure boundaries are subjected to no or only light irradiation, the pressure boundary of a fusion reactor is subjected to high atomic displacement-damage and high production rates of transmutation products, e.g., helium and hydrogen. The design data base must include irradiated materials. Since in situ testing to obtain tensile, fatigue, creep, crack-growth, stress-rupture, and swelling data is currently impossible for fusion reactor conditions, a program of service-temperature irradiations in fission reactors followed by postirradiation testing, simulation of fusion conditions, and low-fluence 14 MeV neutron-irradiation tests are planned. For the Demonstration Reactor (DEMO) expected to be built within ten years after theEPR, higher heat fluxes may require the use of refractory metals, at least for the first 20 cm. A partial data base may be provided by high-flux 14 MeV neutron sources being planned. Many materials other than those for structural components will be required in the EPR and DEMO. These include superconducting magnets, insulators, neutron reflectors and shields, and breeding materials. The rest of the device should utilize conventional materials except that portion involved in tritium confinement and recovery

  10. The safety of light water reactors

    International Nuclear Information System (INIS)

    The book describes the principles and practices of reactor safety as applied to the design, regulation and operation of both pressurized water reactors and boiling water reactors. The central part of the book is devoted to methods and results of safety analysis. Some significant events are described, notably the Three Mile Island accident. The book concludes with a chapter on the PIUS principle of inherent reactor safety as applied to the SECURE type of reactor developed in Sweden. (G.B.)

  11. Three dimensional diffusion calculations of nuclear reactors

    International Nuclear Information System (INIS)

    This work deals with the three dimensional calculation of nuclear reactors using the code TRITON. The purposes of the work were to perform three-dimensional computations of the core of the Soreq nuclear reactor and of the power reactor ZION and to validate the TRITON code. Possible applications of the TRITON code in Soreq reactor calculations and in power reactor research are suggested. (H.K.)

  12. ICONE-4: Proceedings. Volume 2: Advanced reactors

    International Nuclear Information System (INIS)

    The proceedings for this conference are contained in 5 volumes. This volume is divided into the following areas: advanced reactor requirements; advanced reactor design and analysis; arrangement and construction; specific reactor designs; demonstration testing; safety systems and analysis; component demonstration testing; advanced reactor containment design; licensing topics and updates; accelerator applications and spallation sources; and advanced reactor development. Separate abstracts were prepared for most papers in this volume

  13. Molten-Salt Depleted-Uranium Reactor

    OpenAIRE

    Dong, Bao-Guo; Dong, Pei; Gu, Ji-Yuan

    2015-01-01

    The supercritical, reactor core melting and nuclear fuel leaking accidents have troubled fission reactors for decades, and greatly limit their extensive applications. Now these troubles are still open. Here we first show a possible perfect reactor, Molten-Salt Depleted-Uranium Reactor which is no above accident trouble. We found this reactor could be realized in practical applications in terms of all of the scientific principle, principle of operation, technology, and engineering. Our results...

  14. Calculation of reactor antineutrino spectra in TEXONO

    CERN Document Server

    Chen Dong Liang; Mao Ze Pu; Wong, T H

    2002-01-01

    In the low energy reactor antineutrino physics experiments, either for the researches of antineutrino oscillation and antineutrino reactions, or for the measurement of abnormal magnetic moment of antineutrino, the flux and the spectra of reactor antineutrino must be described accurately. The method of calculation of reactor antineutrino spectra was discussed in detail. Furthermore, based on the actual circumstances of NP2 reactors and the arrangement of detectors, the flux and the spectra of reactor antineutrino in TEXONO were worked out

  15. Analysis of higher power research reactors' parameters

    International Nuclear Information System (INIS)

    The objective of this monograph was to analyze and compare parameters of different types of research reactors having higher power. This analysis could be used for decision making and choice of a reactor which could possibly replace the existing ageing RA reactor in Vinca. Present experimental and irradiation needs are taken into account together with the existing reactors operated in our country, RB and TRIGA reactor

  16. Impact of proposed research reactor standards on reactor operation

    International Nuclear Information System (INIS)

    A Standards Committee on Operation of Research Reactors, (ANS-15), sponsored by the American Nuclear Society, was organized in June 1971. Its purpose is to develop, prepare, and maintain standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training. Of the 15 original members, six were directly associated with operating TRIGA facilities. This committee developed a standard for the Development of Technical Specifications for Research Reactors (ANS-15.1), the revised draft of which was submitted to ANSI for review in May of 1973. The Committee then identified 10 other critical areas for standards development. Nine of these, along with ANS-15.1, are of direct interest to TRIGA owners and operators. The Committee was divided into subcommittees to work on these areas. These nine areas involve proposed standards for research reactors concerning: 1. Records and Reports (ANS-15.3) 2. Selection and Training of Personnel (ANS-15.4) 3. Effluent Monitoring (ANS-15.5) 4. Review of Experiments (ANS-15.6) 5. Siting (ANS-15.7) 6. Quality Assurance Program Guidance and Requirements (ANS-15.8) 7. Restrictions on Radioactive Effluents (ANS-15.9) 8. Decommissioning (ANS-15.10) 9. Radiological Control and Safety (ANS-15.11). The present status of each of these standards will be presented, along with their potential impact on TRIGA reactor operation. (author)

  17. Prometheus Project Reactor Module Final Report, For Naval Reactors Information

    International Nuclear Information System (INIS)

    The Naval Reactors Prime Contractor Team (NRPCT) led the development of a power plant for a civilian nuclear electric propulsion (NEP) system concept as part of the Prometheus Project. This report provides a summary of the facts, technical insights, and programmatic perspectives gained from this two-year program. The Prometheus Project experience has been extensively documented to better position the US for future space reactor development. Major Technological and engineering challenges exist to develop a system that provides useful electric power from a nuclear fission heat source operating in deep space. General issues include meeting mission requirements in a system that has a mass low enough to launch from earth while assuring public safety and remaining safely shutdown during credible launch accidents. These challenges may be overcome in the future if there is a space mission with a compelling need for nuclear power to drive development. Past experience and notional mission requirements indicate that any useful space reactor system will be unlike past space reactors and existing terrestrial reactors

  18. Repairing liner of the reactor; Reparacion del liner del reactor

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2001-07-15

    Due to the corrosion problems of the aluminum coating of the reactor pool, a periodic inspections program by ultrasound to evaluate the advance grade and the corrosion speed was settled down. This inspections have shown the necessity to repair some areas, in those that the slimming is significant, of not making it can arrive to the water escape of the reactor pool. The objective of the repair is to place patches of plates of 1/4 inch aluminum thickness in the areas of the reactor 'liner', in those that it has been detected by ultrasound a smaller thickness or similar to 3 mm. To carry out this the fuels are move (of the core and those that are decaying) to a temporary storage, the structure of the core is confined in a tank that this placed inside the pool of the reactor, a shield is placed in the thermal column and it is completely extracted the water for to leave uncover the 'liner' of the reactor. (Author)

  19. Operating experiences of the research reactors

    International Nuclear Information System (INIS)

    Nuclear research reactors are devices of wide importance, being used for different scientific research tasks, for testing and improving reactor systems and components, for the production of radioisotopes, for the purposes of defence, for staff training and for other purposes. There are three research reactors in Yugoslavia: RA, RB and TRIGA. Reactors RA and RB at the 'Boris Kidric' Institute of Nuclear Sciences are of heavy water type power being 6500 and 10 kW, and maximum thermal neutron flux of 1014 and 1011(n/cm2s), respectively. TRIGA reactor at the 'Jozef Stefan' Institute in Ljubljana is of 250 kW power and maximum thermal neutron flux of 1013(n/cm2s). Reactors RA and RB use soviet fuel in the form of uranium dioxide (80% enriched) and metallic uranium (2%). Besides, RB reactor operates with natural uranium too. TRIGA reactor uses american uranium fuel 70% and 20% enriched, uranium being mixed homogeneously with moderator (ZrH). Experiences in handling and controlling the fuel before irradiation in the reactor, in reactor and after it are numerous and valuable, involving either the commercial arrangements with foreign producers, or optimal burn up in reactor or fuel treatment after the reactor irradiation. Twenty years of operating experience of these reactors have great importance especially having in mind the number of trained staff. Maintenance of reactors systems and fluids in continuous operation is valuable experience from the point of view of water reactor utilization. The case of the RA reactor primary cycle cobalt decontamination and other events connected with nuclear and radiation security for all three reactors are also specially emphasized. Owing to our research reactors, numerous theoretical, numerical and experimental methods are developed for nuclear and other analyses and design of research and power reactors,as well as methods for control and protection of radiation. (author)

  20. Establishment of licensing process for development reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik (and others)

    2006-02-15

    A study on licensing processes for development reactors has been performed to prepare the licensing of development reactors developed in Korea. The contents and results of the study are summarized as follows. The licensing processes for nuclear reactors in Korea, U.S.A., Japan, France, U.K., Canada, and IAEA were surveyed and analyzed to obtain technical bases necessary for establishing licensing processes applicable to development reactors in Korea. Based on the technical bases obtained the above analysis, the purpose, power output, and design characteristics of development reactors were analyzed in detail. The analysis results suggested that development reactors should be classified as a new reactor category (called as 'development reactor') separated from the current reactor categories such as the research reactor and the power reactor. Therefore, it is proposed to establish a new reactor category classified as 'development reactor' for the development reactors. And licensing processes, including licensing technical requirements, licensing document requirements, and other regulatory requirements, were also proposed for the development reactors. In order to institutionalize the licensing processes developed in this study, it is necessary to revise the current laws. Therefore, draft provisions of Atomic Energy Act, Enforcement Decree of the Atomic Energy Act, and Enforcement Regulation of the Atomic Energy Act have been developed for the preparation of the future legalization of the licensing processes proposed for the development reactors. Conclusively, a proposal of licensing processes and draft provisions of laws have been developed for the development reactors. The results proposed in this study can be applied directly to the licensing of the future development reactors. Furthermore, they will also contribute to establishing successfully the licensing processes of the development reactors.

  1. Nordic study on reactor waste

    International Nuclear Information System (INIS)

    In 1981, 14 nuclear power reactors are in operation and 2 under construction in the Nordic countries. So far, the reactor waste originating from day-to-day operation of these plants has been stored in solidified form at the reactor sites. Within a few years a satisfactory disposal procedure needs to be established. While the main R and D effects in the waste field have earlier been devoted to the question of irradiated fuel and waste from reprocessing, there is therefore now an increased interest in reactor waste with its much lower radioactivity but somewhat larger volumes. Since 1977, efforts have been made in a joint Nordic study to examine which facts need to be known in order to perform a comprehensive safety assessment of a reactor waste management system. In the present study a Reference system related to the waste generated over 30 years from six 500 MW-reactors is examined. The dominating radionuclides during storage and transportation accident scenarios are Cs-134, Cs-137 and Co-60. For most of the release scenarios from repositories Cs-137 and Sr-90 are dominating. Some scenarios are, however, dominated by the very longlived nuclides I-129 and C-14. A closer examination of the concentration in the waste of these nuclides and of their leaching properties indicates that their small - but significant - influence, as calculated, is probably grossly overestimated. The mechanical stability obtained in routine solidification processes of reactor waste products in conjunction with the outer container (steel drum, transport container, etc.) turns out to be sufficient. Difficulties were encountered in applying ICRP methodology and available dose calculation methods to calculation of population doses due to small activity releases, and effects extending into the far future. (EG)

  2. When reactors reach old age

    International Nuclear Information System (INIS)

    While the battle over whether to build new nuclear plants has quieted in recent times, a second struggle is shaping up in the United States as reactors approach a new stage of life: retirement. Four decades into the nuclear power age, questions of how best to dismantle and dispose of a nuclear power plant remain largely unanswered. The debates have been mainly academic until now - although reactors have operated for 25 years, decommissioning retired reactors has simply not been fully planned in this country. But the Shippingport Atomic Power Station in Pennsylvania, the first large-scale power reactor to be retired, is now being decommissioned. The work has rekindled the debates in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. Virtually all groups involved in decommissioning a reactor in the United States - the utility, the Nuclear Regulatory Commission, the U.S. Department of Energy, the U.S. Environmental Protection Agency, state public service commissions, and citizen organizations - agree that for the most part the technology to dismantle and dispose of a reactor safely is available. They disagree, however, on which technical option is the safest or cheapest and on who should pay for dismantlement. And there are further complications: Which regulations must be complied with. How much radiation exposure for workers and the public is acceptable. Even with answers to these questions, uncertainty about where to dispose of the radioactive waste and about how much residual radiation can be left at a former reactor site plagues the architects of decommissioning. This article discusses these questions

  3. Market introduction of innovative reactors

    International Nuclear Information System (INIS)

    Besides the development of evolutionary and passive LWR, also that of innovative reactors is attractive, because other applications (new markets) besides base load electricity generation can be thought of, and interesting new features on the area of safety or waste incineration can be shown. For market introduction however, a (partial) new infrastructure and a demonstration plant are required. Taking the abundance of fossil fuels and the accompanying low fuel prices today and in the near future into account, the funds to finance this will only become available when 1)the projected energy generating costs will be substantially lower than those of today, and 2)the costs of market introduction (i.e. the demonstration plant and the required infrastructure) will be limited. Generally speaking, there are two ways to seek competitiveness of a reactor type: 1)application of economy of scale, and 2)simplification. In this paper, an example of the second possibility is pursued for an innovative reactor type. The HR1 is a 40 MWth high temperature gas cooled reactor for heat and power cogeneration, a simplified version of the German HTR Module. The power level is chosen so small that additional safety features become apparent. For example, after a total loss of coolant the fuel remains fully intact, even if the reactor shutdown system fails and the reactor goes critical again after a number of hours. These safety features are used to omit certain components, like the emergency core cooling system, or to select a cheaper version of components, e.g. replacing the containment building by a confinement. Moreover, degradation of the safety class of certain components comes within the realm of possibilities. The cost reduction offered by these two measures are used to more than offset the economy-of-scale disadvantage of this small reactor system. (author)

  4. Análise da relação risco e retorno em carteiras compostas por índices de bolsa de valores de países desenvolvidos e de países emergentes integrantes do bloco econômico BRIC Analysis of the relationship between risk and return in portfolios comprising stock exchange indexes from developed and emerging countries members of BRICs economic bloc

    Directory of Open Access Journals (Sweden)

    José Odálio dos Santos

    2010-12-01

    Full Text Available O objetivo deste trabalho foi analisar se a formação de carteiras de investimentos compostas por ativos internacionais pode proporcionar relações de risco e retorno mais vantajosas para o investidor. Paralelamente, analisou-se o estágio de integração entre as economias dos países selecionados por meio do modelo desenvolvido por Securato (1997, denominado Nível de Globalização Restritra (NGR. A pesquisa foi aplicada em dois períodos: 1996 a 2000, quando se intensifica a abertura de importantes mercados emergentes, e de 2003 a 2007 para a comparação dos resultados. Para analisar a contribuição da diversificação internacional, calculou-se o risco e o retorno de quatro carteiras assim formadas: 1. índices de bolsa de valores dos países desenvolvidos (Reino Unido, EUA e Japão e dos países que integram o BRIC; 2. índices de bolsa de valores dos EUA e dos países que integram o BRIC; 3. índices de bolsa de valores dos países que integram o BRIC e 4. índices de bolsa de valores dos países desenvolvidos. Os resultados empíricos sugerem que o investidor obteria melhores resultados, caso optasse por carteiras compostas pelos índices do mercado acionário dos Estados Unidos e dos países integrantes do BRIC. A adição desses ativos na carteira geraria menores índices de covariância, ou seja, a menor exposição de risco por unidade de retorno. Por outro lado, embora tenha aumentado o nível de globalização entre os mercados no período mais recente da pesquisa (2003-2007, constatou-se a necessidade de maior integração entre as economias dos países selecionados (NGR The aim of this study was to examine whether the formation of portfolios composed of international assets can provide risk and return more advantageous for the investor. In parallel, we analyzed the stage of integration between the economies of selected countries through the model developed by Securato (1997, called Restricted Globalization Level (NGR. The

  5. University of Florida training reactor. Annual progress report, September 1, 1984-August 31, 1985

    International Nuclear Information System (INIS)

    This annual progress report of the University of Florida Training Reactor discusses: reactor operation; personnel; modifications made to the reactors; reactor maintenance; and testing of reactor systems

  6. Reactivity determination in accelerator driven reactors using reactor noise analysis

    Directory of Open Access Journals (Sweden)

    Kostić Ljiljana 1

    2002-01-01

    Full Text Available Feynman-alpha and Rossi-alpha methods are used in traditional nuclear reactors to determine the subcritical reactivity of a system. The methods are based on the measurement of the mean value, variance and the covariance of detector counts for different measurement times. Such methods attracted renewed attention recently with the advent of the so-called accelerator driven reactors (ADS proposed some time ago. The ADS systems, intended to be used either in energy generation or transuranium transmutation, will use a subcritical core with a strong spallation source. A spallation source has statistical properties that are different from those traditionally used by radioactive sources. In such reactors the monitoring of the subcritical reactivity is very important, and a statistical method, such as the Feynman-alpha method, is capable of resolving this problem.

  7. Fast Reactor Development Strategy in China

    International Nuclear Information System (INIS)

    As one of the largest developing countries, China needs a reliable energy supplement. At the same time, China should improve the energy structure to decrease CO2 emissions. Nuclear and renewable energies are the main solutions to these issues. According to the research results, the nuclear capacity should increase to 400 GW(e) up to 2050. Fast reactors must be developed considering the limitation of uranium resources. In order to deploy fast reactor technology, the ‘experimental reactor, demonstration reactor and commercial reactor’ strategy has been suggested. China has finished the construction of the China Experimental Fast Reactor (CEFR) and gained necessary experience about fast reactors. The China Institute of Atomic Energy (CIAE) has begun to design the CFR-600, a 600 MW(e) demonstration fast reactor. This reactor will be put into operation before 2025. After that, a larger commercial reactor will be constructed. Besides fast reactors, all of other key sectors of fuel cycle will be developed at the same time such as reprocessing, fast reactor fuel, etc. There are two main tasks of fast reactors, one of which is to raise the utility ratio of uranium, and the other one is to transmute the long life waste of light water reactors. The fast reactor will be designed as a breeder and burner, respectively. (author)

  8. Inherently safe light water reactors

    International Nuclear Information System (INIS)

    Today's large nuclear power reactors of world-wise use have been designed based on the philosophy. It seems that recent less electricity demand rates, higher capital cost and the TMI accident let us acknowledge relative small and simplified nuclear plants with safer features, and that Chernobyl accident in 1983 underlines the needs of intrinsic and passive safety characteristics. In such background, several inherently safe reactor concepts have been presented abroad and domestically. First describing 'Can inherently safe reactors be designed,' then I introduce representative reactor concepts of inherently safe LWRs advocated abroad so far. All of these innovative reactors employ intrinsic and passive features in their design, as follows: (1) PIUS, an acronym for Process Inherent Ultimate Safety, or an integral PWR with passive heat sink and passive shutdown mechanism, advocated by ASEA-ATOM of Sweden. (2) MAP(Minimum Attention Plant), or a self-pressurized, natural circulation integral PWR, promoted by CE Inc. of the U.S. (3) TPS(TRIGA Power System), or a compact PWR with passive heat sink and inherent fuel characteristics of large prompt temperature coefficient, prompted by GA Technologies Inc. of the U.S. (4) PIUS-BWR, or an inherently safe BWR employing passively actuated fluid valves, in competition with PIUS, prompted by ORNL of the U.S. Then, I will describe the domestic trends in Japan and the innovative inherently safe LWRs presented domestically so far. (author)

  9. Utilization of nuclear research reactors

    International Nuclear Information System (INIS)

    Full text: Report on an IAEA interregional training course, Budapest, Hungary, 5-30 November 1979. The course was attended by 19 participants from 16 Member States. Among the 28 training courses which the International Atomic Energy Agency organized within its 1979 programme of technical assistance was the Interregional Training Course on the Utilization of Nuclear Research Reactors. This course was held at the Nuclear Training Reactor (a low-power pool-type reactor) of the Technical University, Budapest, Hungary, from 5 to 30 November 1979 and it was complemented by a one-week Study Tour to the Nuclear Research Centre in Rossendorf near Dresden, German Democratic Republic. The training course was very successful, with 19 participants attending from 16 Member States - Bangladesh, Bolivia, Czechoslovakia, Ecuador, Egypt, India, Iraq, Korean Democratic People's Republic, Morocco, Peru, Philippines, Spain, Thailand, Turkey, Vietnam and Yugoslavia. Selected invited lecturers were recruited from the USA and Finland, as well as local scientists from Hungarian institutions. During the past two decades or so, many research reactors have been put into operation around the world, and the demand for well qualified personnel to run and fully utilize these facilities has increased accordingly. Several developing countries have already acquired small- and medium-size research reactors mainly for isotope production, research in various fields, and training, while others are presently at different stages of planning and installation. Through different sources of information, such as requests to the IAEA for fellowship awards and experts, it became apparent that many research reactors and their associated facilities are not being utilized to their full potential in many of the developing countries. One reason for this is the lack of a sufficient number of trained professionals who are well acquainted with all the capabilities that a research reactor can offer, both in research and

  10. Thermonuclear Reflect AB-Reactor

    CERN Document Server

    Bolonkin, Alexander

    2008-01-01

    The author offers a new kind of thermonuclear reflect reactor. The remarkable feature of this new reactor is a three net AB reflector, which confines the high temperature plasma. The plasma loses part of its energy when it contacts with the net but this loss can be compensated by an additional permanent plasma heating. When the plasma is rarefied (has a small density), the heat flow to the AB reflector is not large and the temperature in the triple reflector net is lower than 2000 - 3000 K. This offered AB-reactor has significantly less power then the currently contemplated power reactors with magnetic or inertial confinement (hundreds-thousands of kW, not millions of kW). But it is enough for many vehicles and ships and particularly valuable for tunnelers, subs and space apparatus, where air to burn chemical fuel is at a premium or simply not available. The author has made a number of innovations in this reactor, researched its theory, developed methods of computation, made a sample computation of typical pr...

  11. Heterogeneous Transmutation Sodium Fast Reactor

    Energy Technology Data Exchange (ETDEWEB)

    S. E. Bays

    2007-09-01

    The threshold-fission (fertile) nature of Am-241 is used to destroy this minor actinide by capitalizing upon neutron capture instead of fission within a sodium fast reactor. This neutron-capture and its subsequent decay chain leads to the breeding of even neutron number plutonium isotopes. A slightly moderated target design is proposed for breeding plutonium in an axial blanket located above the active “fast reactor” driver fuel region. A parametric study on the core height and fuel pin diameter-to-pitch ratio is used to explore the reactor and fuel cycle aspects of this design. This study resulted in both non-flattened and flattened core geometries. Both of these designs demonstrated a high capacity for removing americium from the fuel cycle. A reactivity coefficient analysis revealed that this heterogeneous design will have comparable safety aspects to a homogeneous reactor of comparable size. A mass balance analysis revealed that the heterogeneous design may reduce the number of fast reactors needed to close the current once-through light water reactor fuel cycle.

  12. Water shielding nuclear reactor container

    International Nuclear Information System (INIS)

    The reactor container of the present invention contains a reactor pressure vessel, and has double steel plate walls endurable to elevated inner pressure and keeping airtightness, and shielding water is filled inside from a water injection port. It is endurable to a great inner pressure satisfactorily and keep airtightness by the two spaced relatively thin steel plates. It exhibits radiation shielding effect by filling water substantially the same as that of a conventional reactor container made of iron reinforced concretes. Then, it is no more necessary to use concretes for the construction of the reactor container, which shortens the term of the construction, and saves the construction cost. In addition, a cooling effect for the reactor container is provided. Syphons are disposed contiguously to a water injection port and the top end of the syphon is immersed in an equipment temporarily storage pool, and further, pipelines are connected to the double steel plate walls or the syphons for supplying shielding water to enhance the cooling effect. (N.H.)

  13. Moving ring reactor 'Karin-1'

    International Nuclear Information System (INIS)

    The conceptual design of a moving ring reactor ''Karin-1'' has been carried out to advance fusion system design, to clarify the research and development problems, and to decide their priority. In order to attain these objectives, a D-T reactor with tritium breeding blanket is designed, a commercial reactor with net power output of 500 MWe is designed, the compatibility of plasma physics with fusion engineering is demonstrated, and some other guideline is indicated. A moving ring reactor is composed mainly of three parts. In the first formation section, a plasma ring is formed and heated up to ignition temperature. The plasma ring of compact torus is transported from the formation section through the next burning section to generate fusion power. Then the plasma ring moves into the last recovery section, and the energy and particles of the plasma ring are recovered. The outline of a moving ring reactor ''Karin-1'' is described. As a candidate material for the first wall, SiC was adopted to reduce the MHD effect and to minimize the interaction with neutrons and charged particles. The thin metal lining was applied to the SiC surface to solve the problem of the compatibility with lithium blanket. Plasma physics, the engineering aspect and the items of research and development are described. (Kako, I.)

  14. Economic analysis of nuclear reactors

    International Nuclear Information System (INIS)

    The report presents several methods for estimating the power costs of nuclear reactors. When based on a consistent set of economic assumptions, total power costs may be useful in comparing reactor alternatives. The principal items contributing to the total power costs of a nuclear power plant are: (1) capital costs, (2) fuel cycle costs, (3) operation and maintenance costs, and (4) income taxes and fixed charges. There is a large variation in capital costs and fuel expenses among different reactor types. For example, the standard once-through LWR has relatively low capital costs; however, the fuel costs may be very high if U3O8 is expensive. In contrast, the FBR has relatively high capital costs but low fuel expenses. Thus, the distribution of expenses varies significantly between these two reactors. In order to compare power costs, expenses and revenues associated with each reactor may be spread over the lifetime of the plant. A single annual cost, often called a levelized cost, may be obtained by the methods described. Levelized power costs may then be used as a basis for economic comparisons. The paper discusses each of the power cost components. An exact expression for total levelized power costs is derived. Approximate techniques of estimating power costs will be presented

  15. Simplifying Microbial Electrosynthesis Reactor Design

    Directory of Open Access Journals (Sweden)

    Cloelle G.S. Giddings

    2015-05-01

    Full Text Available Microbial electrosynthesis, an artificial form of photosynthesis, can efficiently convert carbon dioxide into organic commodities; however, this process has only previously been demonstrated in reactors that have features likely to be a barrier to scale-up. Therefore, the possibility of simplifying reactor design by both eliminating potentiostatic control of the cathode and removing the membrane separating the anode and cathode was investigated with biofilms of Sporomusa ovata, which reduces carbon dioxide to acetate. In traditional ‘H-cell’ reactors, where the anode and cathode chambers were separated with a proton-selective membrane, the rates and columbic efficiencies of microbial electrosynthesis remained high when electron delivery at the cathode was powered with a direct current power source rather than with a poteniostat-poised cathode utilized in previous studies. A membrane-less reactor with a direct-current power source with the cathode and anode positioned to avoid oxygen exposure at the cathode, retained high rates of acetate production as well as high columbic and energetic efficiencies. The finding that microbial electrosynthesis is feasible without a membrane separating the anode from the cathode, coupled with a direct current power source supplying the energy for electron delivery, is expected to greatly simplify future reactor design and lower construction costs.

  16. Spherical tokamak research for fusion reactor

    International Nuclear Information System (INIS)

    Between ITER and the commercial fusion reactor, there are many technological problems to be solved such as cost, neutron and steady-state operation. In the conceptual design of VECTOR and Slim CS reactors it was shown that the key is 'low aspect ratio'. The spherical tokamak (ST) has been expected as the base for fusion reactors. In US, ST is considered as a non-superconducting reactor for use in the neutron irradiation facility. Conceptual design of the superconducting ST reactor is conducted in Japan and Korea independently. In the present article, the prospect of the ST reactor design is discussed. (author)

  17. Fast breeder reactors an engineering introduction

    CERN Document Server

    Judd, A M

    1981-01-01

    Fast Breeder Reactors: An Engineering Introduction is an introductory text to fast breeder reactors and covers topics ranging from reactor physics and design to engineering and safety considerations. Reactor fuels, coolant circuits, steam plants, and control systems are also discussed. This book is comprised of five chapters and opens with a brief summary of the history of fast reactors, with emphasis on international and the prospect of making accessible enormous reserves of energy. The next chapter deals with the physics of fast reactors and considers calculation methods, flux distribution,

  18. Utilisation of thorium in reactors

    Science.gov (United States)

    Anantharaman, K.; Shivakumar, V.; Saha, D.

    2008-12-01

    India's nuclear programme envisages a large-scale utilisation of thorium, as it has limited deposits of uranium but vast deposits of thorium. The large-scale utilisation of thorium requires the adoption of closed fuel cycle. The stable nature of thoria and the radiological issues associated with thoria poses challenges in the adoption of a closed fuel cycle. A thorium fuel based Advanced Heavy Water Reactor (AHWR) is being planned to provide impetus to development of technologies for the closed thorium fuel cycle. Thoria fuel has been loaded in Indian reactors and test irradiations have been carried out with (Th-Pu) MOX fuel. Irradiated thorium assemblies have been reprocessed and the separated 233U fuel has been used for test reactor KAMINI. The paper highlights the Indian experience with the use of thorium and brings out various issues associated with the thorium cycle.

  19. Thermochemical data for reactor materials

    International Nuclear Information System (INIS)

    This report describes a computer database of thermochemical properties of nuclear reactor materials to be used for source term calculations in reactor accident codes. In the first part, the structure and the content of the computer file is described. In the second part a set of thermochemical data is presented pertaining to chemical reactions occurring during severe nuclear reactor accidents and involving fuel (uranium dioxide), fission products and structural materials. These data are complementary to those collected in the databook recently published by Cordfunke and Potter after a study supported by the Commission of the European Communities. The present data were collected from review articles and databanks and follow a discussion on the uncertainties and errors involved in the calculation of complex chemical equilibria in the extrapolated temperature range

  20. Reactor vessel stud thread protector

    International Nuclear Information System (INIS)

    This patent describes a stud thread protector for a nuclear reactor pressure vessel. The vessel has a removable closure head, the closure head being sealingly engaged with the pressure vessel by a plurality of stud bolts, an upper end thereof having a threaded section for threadingly engaging a nut and a vertical bore being disposed within the stud bolt. The stud thread protector encloses the exposed upper portion of the bolt and associated nut projecting above the closure head. The reactor vessel stud thread protector is comprised of: a tubular wall portion being opened at its lower end and substantially closed at its upper end; a drip pan associated with the outer surface of the protector, the drip pan being disposed radially inwardly with respect to the outer periphery of the vessel head, whereby the drip pan collects any fluid being emitted from the reactor vessel; and means for fastening the stud thread protector to an associated stud

  1. Coolant recirculation device for reactors

    International Nuclear Information System (INIS)

    Purpose: To surely remove gases in coolants by the provision of a gas separator having a coolant stay chamber in the midway of coolant flow circuit. Constitution: In an LMFBR type reactor, a gas separator for taking out incompressible gases contained in coolants is provided in the midway of coolant flow circuit comprising a coolant flowing pipeway connected to a reactor, a heat exchange and a coolant recycling pump. The gas separator comprises a vessel-shaped coolant stay chamber, inlet and exit ports of coolants opened to the stay chamber, and a take out port for taking out gases separated from the coolants in the stay chamber. Since the incompressible gases in the coolants have lower density than the coolants, they are collected in the upper cover gas plenum and can surely be eliminated to thereby prevent the gases from flowing into the reactor. (Kawakami, Y.)

  2. The Extrap fusion reactor concept

    International Nuclear Information System (INIS)

    ABSTRACT A study has recently been initiated to assess the fusion reactor potential of the Extrap high-beta toroidal z-pinch concept. A reactor model is defined that fullfills certain economic and operational criteria that are characteristic of compact toroidal systems, including moderately large electric power output, high power density, high first wall loading, and simple construction. This model is applied to Extrap, and a 1000 MWe reference reactor having a first wall neutron loading of 10 MW/m2 is outlined. The minor plasma radius is 1.5 m, the major radius 4.5 m and the pinch current 10 MA. A 0.7 m thick blanket/refletor/shield is chosen to achieve sufficient breeding of tritium, good energy multiplication, and shielding of normal copper coils. (author). 12 refs.; 3 figs.; 1 tab

  3. On fast reactor kinetics studies

    Energy Technology Data Exchange (ETDEWEB)

    Seleznev, E. F.; Belov, A. A. [Nuclear Safety Inst. of the Russian Academy of Sciences IBRAE (Russian Federation); Matveenko, I. P.; Zhukov, A. M.; Raskach, K. F. [Inst. for Physics and Power Engineering IPPE (Russian Federation)

    2012-07-01

    The results and the program of fast reactor core time and space kinetics experiments performed and planned to be performed at the IPPE critical facility is presented. The TIMER code was taken as computation support of the experimental work, which allows transient equations to be solved in 3-D geometry with multi-group diffusion approximation. The number of delayed neutron groups varies from 6 to 8. The code implements the solution of both transient neutron transfer problems: a direct one, where neutron flux density and its derivatives, such as reactor power, etc, are determined at each time step, and an inverse one for the point kinetics equation form, where such a parameter as reactivity is determined with a well-known reactor power time variation function. (authors)

  4. Integral fast reactor safety features

    International Nuclear Information System (INIS)

    The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents

  5. Research reactor education and training

    International Nuclear Information System (INIS)

    CORYS T.E.S.S. and TECHNICATOME present in this document some of the questions that can be rightfully raised concerning education and training of nuclear facilities' staffs. At first, some answers illustrate the tackled generic topics: importance of training, building of a training program, usable tools for training purposes. Afterwards, this paper deals more specifically with research reactors as an actual training tool. The pedagogical advantages they can bring are illustrated through an example consisting in the description of the AZUR facility training capabilities followed by the detailed experiences CORYS T.E.S.S. and TECHNICATOME have both gathered and keeps on gaining using research reactors for training means. The experience shows that this incomparable training material is not necessarily reserved to huge companies or organisations' numerous personnel. It offers enough flexibility to be adapted to the specific needs of a thinner audience. Thus research reactor staffs can also take advantages of this training method. (author)

  6. Prospects for toroidal fusion reactors

    International Nuclear Information System (INIS)

    Work on the International Thermonuclear Experimental Reactor (ITER) tokamak has refined understanding of the realities of a deuterium-tritium (D-T) burning magnetic fusion reactor. An ITER-like tokamak reactor using ITER costs and performance would lead to a cost of electricity (COE) of about 130 mills/kWh. Advanced tokamak physics to be tested in the Toroidal Physics Experiment (TPX), coupled with moderate components in engineering, technology, and unit costs, should lead to a COE comparable with best existing fission systems around 60 mills/kWh. However, a larger unit size, ∼2000 MW(e), is favored for the fusion system. Alternative toroidal configurations to the conventional tokamak, such as the stellarator, reversed-field pinch, and field-reversed configuration, offer some potential advantage, but are less well developed, and have their own challenges

  7. A tubular focused sonochemistry reactor

    Institute of Scientific and Technical Information of China (English)

    ZHOU GuangPing; LIANG ZhaoFeng; LI ZhengZhong; ZHANG YiHui

    2007-01-01

    This paper presents a new sonochemistry reactor, which consists of a cylindrical tube with a certain length and piezoelectric transducers at tube's end with the longitudinal vibration. The tube can effectively transform the longitudinal vibration into the radial vibration and thereby generates ultrasound. Furthermore, ultrasound can be focused to form high-intensity ultrasonic field inside tube. The reactor boasts of simple structure and its whole vessel wall can radiate ultrasound so that the electroacoustic transfer efficiency is high. The focused ultrasonic field provides good condition for sonochemical reaction. The length of the reactor can be up to 2 meters, and liquids can pass through it continuously, so it can be widely applied in liquid processing such as sonochemistry.

  8. Nuclear Reactor Engineering Analysis Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Carlos Chavez-Mercado; Jaime B. Morales-Sandoval; Benjamin E. Zayas-Perez

    1998-12-31

    The Nuclear Reactor Engineering Analysis Laboratory (NREAL) is a sophisticated computer system with state-of-the-art analytical tools and technology for analysis of light water reactors. Multiple application software tools can be activated to carry out different analyses and studies such as nuclear fuel reload evaluation, safety operation margin measurement, transient and severe accident analysis, nuclear reactor instability, operator training, normal and emergency procedures optimization, and human factors engineering studies. An advanced graphic interface, driven through touch-sensitive screens, provides the means to interact with specialized software and nuclear codes. The interface allows the visualization and control of all observable variables in a nuclear power plant (NPP), as well as a selected set of nonobservable or not directly controllable variables from conventional control panels.

  9. Nuclear reactors and fuel cycle

    International Nuclear Information System (INIS)

    The Center for Nuclear Engineering has shown expertise in the field of nuclear and energy systems ad correlated areas. Due to the experience obtained over decades in research and technological development at Brazilian Nuclear Program personnel has been trained and started to actively participate in the design of the main system that will compose the Brazilian Multipurpose Reactor (RMB) which will make Brazil self-sufficient in the production of radiopharmaceuticals. The institution has participated in the monitoring and technical support concerning the safety, licensing and modernization of the research reactors IPEN/MB-01 and IEA-R1. The Nuclear Fuel Center is responsible for the production of the nuclear fuel necessary for the continuous operation of the IEA-R1 research reactor. Development of new fuel technologies is also a permanent concern

  10. Plasma reactor waste management systems

    Science.gov (United States)

    Ness, Robert O., Jr.; Rindt, John R.; Ness, Sumitra R.

    1992-01-01

    The University of North Dakota is developing a plasma reactor system for use in closed-loop processing that includes biological, materials, manufacturing, and waste processing. Direct-current, high-frequency, or microwave discharges will be used to produce plasmas for the treatment of materials. The plasma reactors offer several advantages over other systems, including low operating temperatures, low operating pressures, mechanical simplicity, and relatively safe operation. Human fecal material, sunflowers, oats, soybeans, and plastic were oxidized in a batch plasma reactor. Over 98 percent of the organic material was converted to gaseous products. The solids were then analyzed and a large amount of water and acid-soluble materials were detected. These materials could possibly be used as nutrients for biological systems.

  11. A compact Tokamak transmutation reactor

    Institute of Scientific and Technical Information of China (English)

    QiuLi-Jian; XiaoBing-Jia

    1997-01-01

    The low aspect ration tokamak is proposed for the driver of a transmutation reactor.The main parameters of the reactor core,neutronic analysis of the blanket are given>the neutron wall loading can be lowered from the magnitude order of 1 MW/m2 to 0.5MW/m2 which is much easier to reach in the near future,and the transmutation efficiency (fission/absorption ratio)is raised further.The blanket power density is about 200MW/m3 which is not difficult to deal with.The key components such as diverter and center conductor post are also designed and compared with conventional TOkamak,Finally,by comparison with the other drivers such as FBR,PWR and accelerator,it can be anticipated that the low aspect ratio transmutation reactor would be one way of fusion energy applications in the near future.

  12. Research Reactors Types and Utilization

    International Nuclear Information System (INIS)

    A nuclear reactor, in gross terms, is a device in which nuclear chain reactions are initiated, controlled, and sustained at a steady rate. The nuclei of fuel heavy atoms (mostly 235U or 239Pu), when struck by a slow neutron, may split into two or more smaller nuclei as fission products,releasing energy and neutrons in a process called nuclear fission. These newly-born fast neutrons then undergo several successive collisions with relatively low atomic mass material, the moderator, to become thermalized or slow. Normal water, heavy water, graphite and beryllium are typical moderators. These neutrons then trigger further fissions, and so on. When this nuclear chain reaction is controlled, the energy released can be used to heat water, produce steam and drive a turbine that generates electricity. The fission process, and hence the energy release, are controlled by the insertion (or extraction) of control rods through the reactor. These rods are strongly neutron absorbents, and thus only enough neutrons to sustain the chain reaction are left in the core. The energy released, mostly in the form of heat, should be continuously removed, to protect the core from damage. The most significant use of nuclear reactors is as an energy source for the generation of electrical power and for power in some military ships. This is usually accomplished by methods that involve using heat from the nuclear reaction to power steam turbines. Research reactors are used for radioisotope production and for beam experiments with free neutrons. Historically, the first use of nuclear reactors was the production of weapons grade plutonium for nuclear weapons. Currently all commercial nuclear reactors are based on nuclear fission. Fusion power is an experimental technology based on nuclear fusion instead of fission.

  13. Spatial Kinetics in Fast Reactors

    International Nuclear Information System (INIS)

    Reactor neutronic calculations designed for calculating of unsteady processes in a real 3D geometry require processing of a large amount of information. They cannot consist of simple models, as they should reflect the processes of variations of all local reactor characteristics. The model complexity and the significant time needed for numerical solution of neutron-transport equations limit the choice of methods that can achieve the required accuracy. Thus there is an urgent need for the development of various methods enabling the solution of unsteady neutron-transport equations and estimates of their errors, spent time and consistency with the experimental data. (author)

  14. STARFIRE: a commercial tokamak reactor

    International Nuclear Information System (INIS)

    The purpose of this document is to provide an interim status report on the STARFIRE project for the period of May to September 1979. The basic objective of the STARFIRE project is to develop a design concept for a commercial tokamak fusion electric power plant based on the deuterium/tritium/lithium fuel cycle. The key technical objective is to develop the best embodiment of the tokamak as a power reactor consistent with credible engineering solutions to design problems. Another key goal of the project is to give careful attention to the safety and environmental features of a commercial fusion reactor

  15. PITR: Princeton Ignition Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-01

    The principal objectives of the PITR - Princeton Ignition Test Reactor - are to demonstrate the attainment of thermonuclear ignition in deuterium-tritium, and to develop optimal start-up techniques for plasma heating and current induction, in order to determine the most favorable means of reducing the size and cost of tokamak power reactors. This report describes the status of the plasma and engineering design features of the PITR. The PITR geometry is chosen to provide the highest MHD-stable values of beta in a D-shaped plasma, as well as ease of access for remote handling and neutral-beam injection.

  16. Fundamentals of Nuclear Reactor Physics

    CERN Document Server

    Lewis, E E

    2008-01-01

    This new streamlined text offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation. The book includes numerous worked-out examples and end-of-chapter questions to help reinforce the knowledge presented. This textbook offers an engineering-oriented introduction to nuclear physics, with a particular focus on how those physics are put to work in the service of generating nuclear-based power, particularly the importance of neutron reactions and neutron behavior. Engin

  17. Reactor production of Thorium-229.

    Science.gov (United States)

    Hogle, Susan; Boll, Rose Ann; Murphy, Karen; Denton, David; Owens, Allison; Haverlock, Tamara J; Garland, Marc; Mirzadeh, Saed

    2016-08-01

    Limited availability of (229)Th for clinical applications of (213)Bi necessitates investigation of alternative production routes. In reactor production, (229)Th is produced from neutron transmutation of (226)Ra, (228)Ra, (227)Ac and (228)Th. Irradiations of (226)Ra, (228)Ra, and (227)Ac targets at the Oak Ridge National Laboratory High Flux Isotope Reactor result in yields of (229)Th at 26 days of 74.0±7.4MBq/g, 260±10MBq/g, and 1200±50MBq/g, respectively. Intermediate radionuclide yields and cross sections are also studied. PMID:27163437

  18. Space reactor preliminary mechanical design

    International Nuclear Information System (INIS)

    An analysis was performed on the SABRE reactor space power system to determine the effect of the number and size of heat pipes on the design parameters of the nuclear subsystem. Small numbers of thin walled heat pipes were found to give a lower subsystem mass, but excessive fuel swelling resulted. The SP-100 preliminary design uses 120 heat pipes because of acceptable fuel swelling and a minimum nuclear subsystem mass of 1875 kg. Salient features of the reactor preliminary design are: individual fuel modules, ZrO2 block core mounts, bolted collar fuel module restraints, and a BeO central plug

  19. Reactor shutdown delays medical procedures

    Science.gov (United States)

    Gwynne, Peter

    2008-01-01

    A longer-than-expected maintenance shutdown of the Canadian nuclear reactor that produces North America's entire supply of molybdenum-99 - from which the radioactive isotopes technetium-99 and iodine-131 are made - caused delays to the diagnosis and treatment of thousands of seriously ill patients last month. Technetium-99 is a key component of nuclear-medicine scans, while iodine-131 is used to treat cancer and other diseases of the thyroid. Production eventually resumed, but only after the Canadian government had overruled the Canadian Nuclear Safety Commission (CNSC), which was still concerned about the reactor's safety.

  20. Power Reactor Information System (PRIS)

    International Nuclear Information System (INIS)

    The IAEA has been collecting Operating Experience data for Nuclear Power Plants of the IAEA Member States since 1970. In order to facilitate an analysis of nuclear power plant performance as well as to produce relevant publications, all previously collected data supplied from the questionnaires were computerized in 1980 and the Power Reactor Information System was implemented. PRIS currently contains production records for the years up to and including 1990 and about 98% of the reactors-years operating experience in the world is contained in PRIS. (orig.)

  1. Small intrinsically safe reactor implications

    International Nuclear Information System (INIS)

    Reviewing the history of nuclear power, it is found that peaceful uses of nuclear power are children of the war-like atom. Importance of special growth in a shielded environment is emphasized to exploit fully the advantages of nuclear power. Nuclear power reactors must be safe for their assimilation into society from the points of view of both technology and social psychology. ISR/ISER is identified as a missing link in the development of nuclear power reactors from this perspective and advocated for international development and utilization, being unleashed from the concerns of politicization, safety, and proliferation

  2. Research reactor modernization and refurbishment

    International Nuclear Information System (INIS)

    Many recent, high profile research reactor unplanned shutdowns can be directly linked to different challenges which have evolved over time. The concept of ageing management is certainly nothing new to nuclear facilities, however, these events are highlighting the direct impact unplanned shutdowns at research reactors have on various stakeholders who depend on research reactor goods and services. Provided the demand for these goods and services remains strong, large capital projects are anticipated to continue in order to sustain future operation of many research reactors. It is within this context that the IAEA organized a Technical Workshop to launch a broader Agency activity on research reactor modernization and refurbishment (M and R). The workshop was hosted by the operating organization of the HOR Research Reactor in Delft, the Netherlands, in October 2006. Forty participants from twenty-three countries participated in the meeting: with representation from Africa, Asia Pacific, Eastern Europe, North America, South America and Western Europe. The specific objectives of this workshop were to present facility reports on completed, existing and planned M and R projects, including the project objectives, scope and main characteristics; and to specifically report on: - the project impact (planned or actual) on the primary and key supporting motivation for the M and R project; - the project impact (planned or actual) on the design basis, safety, and/or regulatory-related reports; - the project impact (planned or actual) on facility utilization; - significant lessons learned during or following the completion of M and R work. Contributions from this workshop were reviewed by experts during a consultancy meeting held in Vienna in December 2007. The experts selected final contributions for inclusion in this report. Requests were also distributed to some authors for additional detail as well as new authors for known projects not submitted during the initial 2006 workshop

  3. Liquid-cooled nuclear reactor

    International Nuclear Information System (INIS)

    Hydrogen can be added to nuclear reactors with a liquid hydrogen-containing coolant on the suction side of a high pressure pump in the purification system. According to the invention this is performed by means of a liquid jet condenser which uses the coolant as liquid and which is preferably charged from the pressure side of the high pressure pump and conveys the liquid to a mixer connected in series with the high pressure pump. The invention is to be used especially in pressurized water reactors. (orig.)

  4. Safety of thermal water reactors

    International Nuclear Information System (INIS)

    This book reports on the latest European research into the safety of thermal water reactors, based on the presentation and evaluation of results obtained from research projects undertaken in different national laboratories of the European Community. Information is included under the following areas of research: 1.) The loss of coolant accident (LOCA) and the functioning and performance of the emergency core cooling system; 2.) The protection of nuclear power plants against external gas cloud explosions; and 3.) The release and distribution of radioactive fission products in the atmosphere following a reactor accident

  5. Power reactor information system (PRIS)

    International Nuclear Information System (INIS)

    Since the very beginning of commercial operation of nuclear power plants, the nuclear power industry worldwide has accumulated more than 5000 reactor years of experience. The IAEA has been collecting Operating Experience data for Nuclear Power Plants since 1970 which were computerized in 1980. The Agency has undertaken to make Power Reactor Information System (PRIS) available on-line to its Member States. The aim of this publication is to provide the users of PRIS from their terminals with description of data base and communication systems and to show the methods of accessing the data

  6. Evaluación clínica, microbio lógica e inmuológica de la ozonoterapia en pacientes con bolsas periodontales moderadas-severas Clinical, microbiological and inmunological evaluation of the ozone's therapy in patients with moderate-severe periodontal pockets

    Directory of Open Access Journals (Sweden)

    J. Ripollés de Ramón

    2004-04-01

    Full Text Available INTRODUCCIÓN. En los últimos años se ha producido un progreso importante en el conocimiento de la enfermedad periodontal, desde su etiología multifactorial, la microbiología responsable, la respuesta inmunológica local, así como múltiples aspectos en relación con su epidemiología, etiopatogenia y su proceso evolutivo. Dado el mayor conocimiento en estos campos, se desarrollan nuevas técnicas, productos farmacológicos y técnicas que tratan de detener la enfermedad periodontal y preservar la salud bucal. OBJETIVOS. Analizar las respuestas periodontales desde un punto de vista clínico, microbiológico e inmunológico de una población con bolsas periodontales moderadas severas y su comparación, tras la ozonoterapia, con la técnica del raspado y alisado radicular. MATERIAL Y MÉTODO. Se estudiaron un total de 72 cuadrantes maxilares con al menos 4dientes en dichos cuadrantes y 6mm de profundidad de sondaje (bolsa periodontal moderada-severa en una población con una media de edad de 43 años. Para establecer las comparaciones entre ambos grupos se realizó un estudio a boca partida en el que la mitad de los cuadrantes fueron tratados con ozono y la otra restante con una técnica de raspado y alisado radicular. Se evaluarón las variables respuestas: clínico-microbiológico e inmunológico mediante análisis estadisticos descriptivo y ANOVA. CONCLUSIÓN. Podemos establecer de forma preliminar, que el tratamiento periodontal con ozono (PrimoLogO3 produce una reducción estadísticamente significativa en el índice de sangrado gingival de Lindhe, en la microbiología patógena periodontal así como de los patrones inmunológicos de la Ik1-b y el TNF-alfa, sin embargo no produce variación alguna en relación al nivel de inserción periodontal y de la profundidad de la bolsa periodontal que requiere su remoción mecánica con el raspado y alisado radicular. Asimismo se requiere de un mayor numero de estudios que corroboren estos

  7. Advanced fuels for fast reactors

    International Nuclear Information System (INIS)

    Full text: In addition to traditional fast reactor fuels that contain Uranium and Plutonium, the advanced fast reactor fuels are likely to include the minor actinides [Neptunium (Np), Americium (Am) and Curium (Cm)]. Such fuels are also referred to as transmutation fuels. The goal of transmutation fuel development programs is to develop and qualify a nuclear fuel system that performs all of the functions of a traditional fast spectrum nuclear fuel while destroying recycled actinides. Oxide, metal, nitride, and carbide fuels are candidates under consideration for this application, based on historical knowledge of fast reactor fuel development and specific fuel tests currently being conducted in international transmutation fuel development programs. Early fast reactor developers originally favored metal alloy fuel due to its high density and potential for breeder operation. The focus of pressurized water reactor development on oxide fuel and the subsequent adoption by the commercial nuclear power industry, however, along with early issues with low burnup potential of metal fuel (now resolved), led later fast reactor development programs to favor oxide fuels. Carbide and nitride fuels have also been investigated but are at a much lower state of development than metal and oxide fuels, with limited large scale reactor irradiation experience. Experience with both metal and oxide fuels has established that either fuel type will meet performance and reliability goals for a plutonium fueled fast spectrum test reactor, both demonstrating burnup capability of up to 20 at.% under normal operating conditions, when clad with modified austenitic or ferritic martensitic stainless steel alloys. Both metal and oxide fuels have been shown to exhibit sufficient margin to failure under transient conditions for successful reactor operation. Summary of selected fuel material properties taken are provided in the paper. The main challenge for the development of transmutation fast reactor

  8. Imperial College Reactor Centre annual report 1983

    International Nuclear Information System (INIS)

    The report covers the following matters: research topics (reactor engineering; neutron and gamma dosimetry; nuclear physics; stable and radiotracer studies; neutron activation analysis (medicine; the environment; archaeology; geology)); personnel; publications; overseas visits; research contracts; teaching; reactor operations. (U.K.)

  9. Safety issues at the defense production reactors

    International Nuclear Information System (INIS)

    The United States produces plutonium and tritium for use in nuclear weapons at the defense production reactors - the N Reactor in Washington and the Savannah River reactors in South Carolina. This report reaches general conclusions about the management of those reactors and highlights a number of safety and technical issues that should be resolved. The report provides an assessment of the safety management, safety review, and safety methodology employed by the Department of Energy and the private contractors who operate the reactors for the federal government. This report examines the safety objective established by the Department of Energy for the production reactors and the process the Department of its contractors use to implement the objective; focuses on a variety of uncertainties concerning the production reactors, particularly those related to potential vulnerabilities to severe accidents; and identifies ways in which the DOE approach to management of the safety of the production reactors can be improved

  10. Research nuclear reactor RA - Annual Report 2000

    International Nuclear Information System (INIS)

    Activities related to revitalisation of the RA reactor started in 1986 were fulfilled except the exchange of the complete reactor instrumentation. Since 1992, due to economic and political reasons, RA reactor is in a difficult situation. The old RA reactor instrumentation was dismantled. Decision about the future status of the reactor should be made because the aging of all the components is becoming dramatic. Control and maintenance of the reactor components was done regularly and efficiently. The most important activity and investment in 1998 was improvement of conditions for spent fuel storage in the existing pools at the RA reactor. Russian company ENTEK and IAEA are involved in this activity which was initiated 1997. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. Research reactor RA Annual report for year 2000 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection

  11. Research nuclear reactor RA - Annual Report 1998

    International Nuclear Information System (INIS)

    Activities related to revitalisation of the RA reactor started in 1986 were fulfilled except the exchange of the complete reactor instrumentation. Since 1992, due to economic and political reasons, RA reactor is in a difficult situation. The old RA reactor instrumentation was dismantled. Decision about the future status of the reactor should be made because the aging of all the components is becoming dramatic. Control and maintenance of the reactor components was done regularly and efficiently. The most important activity and investment in 1998 was improvement of conditions for spent fuel storage in the existing pools at the RA reactor. Russian company ENTEK and IAEA are involved in this activity which was initiated 1997. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. Research reactor RA Annual report for year 1998 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection

  12. Health requirements for nuclear reactor operators

    International Nuclear Information System (INIS)

    The health prerequisites established for the qualification of nuclear reactor operators according to CNEN-NE-1.01 Guidelines Licensing of nuclear reactor operators, CNEN-12/79 Resolution, are described. (M.A.)

  13. Annual report 1986 Interfacultary Reactor Institute

    International Nuclear Information System (INIS)

    In this annual report of the Dutch Interfacultary Reactor Institute, summary- and detailed reports are presented of Current research during 198? of the departments radiochemistry, radiation chemistry, radiation physics, and reactor physics. (H.W.). refs.; figs.; tabs

  14. Oregon State University TRIGA Reactor annual report

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, T.V.; Johnson, A.G.; Bennett, S.L.; Ringle, J.C.

    1979-08-31

    The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included.

  15. Status of national programmes on fast reactors

    International Nuclear Information System (INIS)

    Based on the International Working Group on Fast reactors (IWGFR) members' request, the IAEA organized a special meeting on Fast Reactor Development and the Role of the IAEA in May 1993. The purpose of the meeting was to review and discuss the status and recent development, to present major changes in fast reactor programmes and to recommend future activities on fast reactors. The IWGFR took note that in some Member States large prototypes have been built or are under construction. However, some countries, due to their current budget constraints, have reduced the level of funding for research and development programmes on fast reactors. The IWGFR noted that in this situation the international exchange of information and cooperation on the development of fast reactors is highly desirable and stressed the importance of the IAEA's programme on fast reactors. These proceedings contain important and useful information on national programmes and new developments in sodium cooled fast reactors in Member States. Refs, figs and tabs

  16. Oregon State University TRIGA Reactor annual report

    International Nuclear Information System (INIS)

    The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included

  17. 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 JPL

    Energy Technology Data Exchange (ETDEWEB)

    D. Kokkinos

    2005-04-28

    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.

  18. Monolithic reactor: higher yield, less energy

    OpenAIRE

    Mols, B.

    2004-01-01

    The production of margarine, the desulphurisation of crude oil, and the manufacture of synthetic diesel fuel, these are only three of the many industrial processes in which a three-phase reactor is used. Traditionally, this type of reactor is rather ill-defined. Success with a lab scale set-up is no guarantee that a large commercial reactor will work. Scalability is less than perfect, one might say. Researchers at the Reactor & Catalysis Engineering epartment of the Chemical Technology facult...

  19. Real time simulator for material testing reactor

    International Nuclear Information System (INIS)

    Japan Atomic Energy Agency (JAEA) is now developing a real time simulator for a material testing reactor based on Japan Materials Testing Reactor (JMTR). The simulator treats reactor core system, primary and secondary cooling system, electricity system and irradiation facility systems. Possible simulations are normal reactor operation, unusual transient operation and accidental operation. The developed simulator also contains tool to revise/add facility in it for the future development. (author)

  20. European simplified boiling water reactor (ESBWR) plant

    International Nuclear Information System (INIS)

    This paper covers innovative ideas which made possible the redesign of the US 660-MW Simplified Boiling Water Reactor (SBWR) Reactor Island for a 1,200-MW size reactor while actually reducing the building cost. This was achieved by breaking down the Reactor Island into multiple buildings separating seismic-1 from non-seismic-1 areas, providing for better space utilization, shorter construction schedule, easier maintainability and better postaccident accessibility