WorldWideScience

Sample records for bolsa chica-2 reactor

  1. Bolsa de objectos de aprendizagem

    OpenAIRE

    Dinis, Patrícia Alexandra de Sousa Castanheira

    2007-01-01

    Enquadrado na área das tecnologias de suporte ao ensino e aprendizagem são analisados vários repositórios de objectos de aprendizagem (OA) em termos das suas funcionalidades, com o intuito de identificar as suas características mais relevantes, boas práticas emergentes, e também limitações ou constrangimentos. Neste âmbito, é proposto o sistema “Bolsa de Objectos de Aprendizagem” (BOA), o qual é desenvolvido de acordo com a metáfora da bolsa de valores, e que introduz uma abordagem i...

  2. Brazil : Assessment of the Bolsa Escola Programs

    OpenAIRE

    World Bank

    2001-01-01

    The report assesses the "Bolsa Escola" programs in Brazil, which are poverty-targeted social assistance programs, that provide cash grants to poor families with school-age children between the ages of seven to fourteen. These programs aim at increasing educational attainment, to reduce current, and future poverty, as well as child labor, and, implicitly, to act as a partial safety net. The...

  3. Bolsa Escola: Breaking the Cycle of Poverty, Child Labour and School Disaffection in Brazil

    Science.gov (United States)

    Denes, Christian Andrew

    2004-01-01

    The Bolsa Escola program in Brazil presents a clear break from the economic growth models and supply-side based strategies of the past. Founded on the assumption that the supplemental income generated by child labour outweighs the potential benefits of primary education, Bolsa Escola attempts to address the demand-side component of high dropout…

  4. Clustering aplicado à Bolsa de Valores de Lisboa

    OpenAIRE

    Jesus, Carla Sofia Sousa

    2015-01-01

    O objetivo desta dissertação foi estudar um conjunto de empresas cotadas na bolsa de valores de Lisboa, para identificar aquelas que têm um comportamento semelhante ao longo do tempo. Para isso utilizamos algoritmos de Clustering tais como K-Means, PAM, Modelos hierárquicos, Funny e C-Means tanto com a distância euclidiana como com a distância de Manhattan. Para selecionar o melhor número de clusters identificado por cada um dos algoritmos testados, recorremos a alguns índices ...

  5. Costo de capital para firmas no transadas en bolsa

    Directory of Open Access Journals (Sweden)

    Ignacio Vélez Pareja

    2002-01-01

    Full Text Available En esta nota se hace un breve repaso de las principales estadísticas de las firmas no transadas en bolsa, tanto en los Estados Unidos como en Colombia, como un ejemplo de un mercado emergente o en desarrollo. Se presentan algunas alternativas para calcular el costo del patrimonio o capital propio cuando no existe información suficiente. Algunas de ellas utilizan el Capital Assets Pricing Model (CAPM, otras utilizan información contable o, simplemente, una apreciación subjetiva del riesgo.

  6. Costos de transacci??n asociados a la liquidez en la bolsa de valores de Colombia

    OpenAIRE

    Agudelo Rueda, Diego Alonso

    2011-01-01

    En una bolsa de valores, los principales costos de transacci??n asociados a la liquidez son el margen entre oferta y demanda, para las transacciones menores, y el impacto en el precio, para las transacciones de mayor volumen. En este art??culo se estiman ambos indicadores con datos a nivel intradiario siguiendo una reconstrucci??n del libro de ??rdenes y en Goyenko et al. (2009) y Hasbrouck (2009). Utilizando la base de datos de ??rdenes de la Bolsa de Valores de Colombia se estiman los costo...

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

    Directory of Open Access Journals (Sweden)

    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

  8. Gamesa: Energía eólica y aeronáutica en Bolsa

    OpenAIRE

    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.

  9. Fish and bivalves at Bolsa Chica Marsh re-establishment project; Progress report III

    OpenAIRE

    Knaggs, Eric H.; Mall, Rolf E.

    1980-01-01

    The objectives of our fish and bivalve study are: 1. Determine changes in the number of species of fish and bivalves before Phase I and during Phase 1 at Bolsa Chica Marsh. 2. Determine if California Department of Fish and Game's predicted benefits in Phase I were achieved by increases in fish species. 3. Determine influences of water management practices upon fish and bivalve composition. Thirteen species of fish and five species of bivalves were collected from ...

  10. Caracterización y modelado de redes: el caso de la Bolsa Mexicana de Valores

    OpenAIRE

    Linda Margarita Medina Herrera; José Benito Díaz Hernández

    2011-01-01

    We review the main tools which allow for statistical and topological characterization of financial networks. We present a case study in the Mexican stock market (Bolsa Mexicana de Valores) displaying dynamic trees over a period of 10 years and analyzes the significant changes that have made the movements of the stock, impacting the length, center of mass and clusters (economic sectors). The construction and telecommunications sectors are the most important within the network

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

    Directory of Open Access Journals (Sweden)

    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.

  12. O programa Bolsa Família: evolução e efeitos sobre a pobreza The Brazilian Bolsa-Familia Program: evolution and impacts on poverty

    Directory of Open Access Journals (Sweden)

    Sonia Rocha

    2011-04-01

    Full Text Available Depois de um breve retrospecto da evolução das transferências de renda focalizadas nos pobres no Brasil, este artigo analisa a evolução recente do programa Bolsa Família no que diz respeito à focalização e cobertura da sua população alvo, utilizando informações do suplemento das PNADs 2004 e 2006. Apesar de o programa ter atingido sua meta de atendimento de 11 milhões de domicílios ao final de 2006, há evidências de que cerca de 3,4 milhões de domicílios elegíveis ainda se encontram a descoberto. Simulações evidenciam que garantir a cobertura de todos os domicílios elegíveis tem maior impacto sobre os indicadores de pobreza que conceder o novo benefício, criado em 2008, aos jovens nos domicílios já atendidos pelo programa.After a brief retrospective of the evolution of income transfer programs in Brazil, this article uses information from the 2004 and 2006 official national household survey (PNAD in order to analyze the recent evolution of the Bolsa Familia program regarding targeting and coverage. Despite the fact that the BF met its goal of assisting 11 million households by the end of 2006, still around 3.4 million eligible households do not receive the transfer benefit. Simulations show that guaranteeing the basic income transfer to all eligible households has a stronger impact on poverty indicators than to grant the new benefit - created in 2008 - to youngsters who live in the already assisted households.

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

    Directory of Open Access Journals (Sweden)

    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.

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

    OpenAIRE

    Cecilia Montero Mórtola

    2011-01-01

    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...

  15. A Bolsa de Valores Sociais enquanto agente de renovação da economia social

    OpenAIRE

    Meira, Deolinda Aparício

    2013-01-01

    Este artigo visa contribuir para o conhecimento da Bolsa de Valores Sociais (BVS), recentemente criada em Portugal, cuja finalidade foi, primacialmente, a de permitir a obtenção de meios de financiamento às entidades da Economia Social que se dediquem a projectos nas áreas da educação e do empreendedorismo. Reflectir-se-á sobre a qualificação jurídica dos vários tipos de entidades cotadas na BVS, sobre o conceito de investidor social e a protecção de que este beneficia, com as consequentes ex...

  16. Desempenho de estimadores de volatilidade na Bolsa de Valores de São Paulo

    OpenAIRE

    Bernardo de Sá Mota; Marcelo Fernandes

    2002-01-01

    O objetivo deste trabalho 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....

  17. Uma metodologia para simular o Programa Bolsa Família

    OpenAIRE

    Pedro H. G. F. Souza; Osorio, Rafael G.; Sergei S. D. Soares

    2011-01-01

    Este artigo descreve detalhadamente como simular os impactos sobre a pobreza de mudanças nas regras de elegibilidade e nos valores do Programa Bolsa Família (PBF). Isto é desafio especialmente delicado na medida em que não existe pergunta específica na Pesquisa Nacional por Amostra de Domicílios (PNAD), do Instituto Brasileiro de Geografia e Estatística (IBGE), sobre a renda do PBF e, mais grave, existe discrepância de 2,4 milhões de famílias entre os registros administrativos do programa (Ca...

  18. PRONÓSTICO Y VOLATILIDAD DEL IPyC DE LA BOLSA MEXICANA DE VALORES

    OpenAIRE

    Sergio Hernández Mejía

    2009-01-01

    Con el objetivo de determinar cuál es el modelo que permite explicar con una mayor precisión el comportamiento histórico del Índice de Precios y Cotizaciones de la Bolsa Mexicana de Valores, durante el periodo 2000-2008, se aplican los modelos de la familia ARCH. Se analiza la volatilidad del mercado, se comparan los modelos GARCH, EGARCH, TARCH de acuerdo a los criterios tradicionales de evaluación y se concluye que el modelo EGARCH(1,1) tiene la mejor capacidad predictiva.

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

    Directory of Open Access Journals (Sweden)

    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.

  20. Modelos multicriterio para la selección de portafolios en la Bolsa de Madrid

    OpenAIRE

    Pla Santamaría, David

    2009-01-01

    En este trabajo se aplican modernas técnicas multicriterio para la selección de carteras, partiendo de información empírica muy amplia proveniente de la Bolsa de Madrid. En efecto, el número de títulos-valores considerados asciende a 104 durante un reciente período de cinco años, habiéndose recogido rendimientos por plusvalías, dividendos y ampliaciones de capital con periodicidad mensual a lo largo del periodo histórico. Basándose en este material estadístico, se han obtenido doce fronteras ...

  1. Programación de un sistema semi-automático para operar en bolsa

    OpenAIRE

    Collado Ciprés, José

    2015-01-01

    El objetivo de este proyecto es el de desarrollar un sistema para invertir en bolsa a medio plazo, que demuestre haber sido rentable en el pasado y al mismo tiempo requiera poco tiempo de dedicación a los mercados por parte del usuario. Se trata de un sistema con las condiciones de entrada en valores, así como las de salida, completamente definidas. De este modo se desecha por completo la discrecionalidad por parte del usuario en el proceso de toma de decisiones. Los métodos para lograr...

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

    OpenAIRE

    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...

  3. Incidencia del Mercado Integrado Latinoamericano (MILA) en cada una de las bolsas de valores que lo componen

    OpenAIRE

    Vargas Sierra, Carlos Arturo; Castaño Calle, Catherine

    2015-01-01

    Este documento tiene como propósito establecer la incidencia que tiene el Mercado Integrado Latinoamericano (MILA) sobre las bolsas que la componen (Chile, Perú y Colombia) -- Para el desarrollo del trabajo se corren modelos econométricos que evidenciarán si los rendimientos de las bolsas de valores de los países que conforman esta integración bursátil se han visto influenciados por los rendimientos del MILA, así como también determinarán si la ocurrencia de la integración genera algún cambio...

  4. Medidas intradiarias de liquidez y de costos de transacción asociados en la Bolsa de Valores de Colombia

    OpenAIRE

    Agudelo, Diego Alonso

    2011-01-01

    Los dos principales costos de transacción asociados a la liquidez en una bolsa de valores son el margen entre la oferta y la demanda (“bid-ask spread”), para transacciones menores, y el impacto en el precio (“price impact”) para transacciones de mayor volumen. Presentamos un procedimiento que permite emplear ambos tipos de medidas de liquidez a nivel intradiario, empleando la base de datos de órdenes de la Bolsa de Valores de Colombia (BVC). De esta forma se logran estimativos ...

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

    OpenAIRE

    Ibarra Alfaraz, J.A.; Tolmos Rodriguez–Piñero ,P.; Garrido Abia, R.; Aparicio Rozas, A.

    1999-01-01

    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 es...

  6. Reactors

    International Nuclear Information System (INIS)

    Purpose: To provide a spray cooling structure wherein the steam phase in a bwr reactor vessel can sufficiently be cooled and the upper cap and flanges in the vessel can be cooled rapidly which kept from direct contaction with cold water. Constitution: An apertured shielding is provided in parallel spaced apart from the inner wall surface at the upper portion of a reactor vessel equipped with a spray nozzle, and the lower end of the shielding and the inner wall of the vessel are closed to each other so as to store the cooling water. Upon spray cooling, cooling water jetting out from the nozzle cools the vapor phase in the vessel and then hits against the shielding. Then the cooling water mostly falls as it is, while partially enters through the apertures to the back of the shielding plate, abuts against stoppers and falls down. The stoppers are formed in an inverted L shape so that the spray water may not in direct contaction with the inner wall of the vessel. (Horiuchi, T.)

  7. Un árbol de expansión mínima en la Bolsa Mexicana de Valores

    OpenAIRE

    Linda Margarita Medina Herrera; Ricardo Mansilla Corona

    2007-01-01

    This paper exhibits the economic taxonomy of a minimal spanning tree constructed from the correlation matrix of daily returns of 65 stocks traded at the Bolsa Mexicana de Valores during an eight-year trading period. This paper also makes a classification of the risk and returns of these stocks depending on their distances in the tree to the central vertex (mass center)

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

    OpenAIRE

    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...

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

    Directory of Open Access Journals (Sweden)

    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.

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

    Directory of Open Access Journals (Sweden)

    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.

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

    Directory of Open Access Journals (Sweden)

    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.

  12. Efeitos do Programa Bolsa Família na fecundidade das beneficiárias

    Directory of Open Access Journals (Sweden)

    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.

  13. Percepções sobre o Programa Bolsa Família na sociedade brasileira

    Directory of Open Access Journals (Sweden)

    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.

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

    OpenAIRE

    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? (?)

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

    Directory of Open Access Journals (Sweden)

    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

  16. 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.

  17. 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.

  18. 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.

  19. 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

  20. 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.

  1. 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.

  2. 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 ...

  3. Las previsiones financieras de las PYME en su proceso de salida a bolsa: realidad o ficción

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    María-José Palacín Sánchez

    2015-01-01

    Full Text Available Este artículo valora el proceso de previsión financiera de las pequeñas y medianas empresas (PYME en sus salidas a bolsa. Específicamente, se analiza la calidad de las previsiones de beneficios realizadas y se exploran los factores que determinan la precisión de tales previsiones. Este estudio considera todas las empresas que han salido a cotizar al Mercado Alternativo Bursátil español (MAB. Los resultados muestran que los directivos de las empresas del MAB han sido mayoritariamente optimistas y altamente imprecisos en la estimación de los beneficios futuros.

  4. Impacto de Expectativas Políticas en los Retornos del Indice General de la Bolsa de Valores de Lima

    OpenAIRE

    Gabriel Rodríguez; Alfredo Vargas

    2011-01-01

    El presente documento analiza el impacto de las expectativas políticas sobre los retornos del índice general de la Bolsa de Valores de Lima (IGBVL) utilizando información para los periodos electorales de 1995 y 2000. La variable explicativa principal es una medida de la probabilidad de que un candidato gane las elecciones. Así, la hipótesis a veri?car es si el grado de incertidumbre sobre las el resultado de las elecciones presidenciales afecta los retornos del IGBVL. Se usan otras variables ...

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

    OpenAIRE

    Raúl de Jesús Gutiérrez; Edgar Ortiz

    2013-01-01

    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 duran...

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

    OpenAIRE

    Verónica Patricia Rodríguez Vázquez; Maribel Ávila Espinosa; Alejandra Torres González

    2009-01-01

    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...

  7. FATORES CONDICIONANTES DO VOLUME DE CONTRATOS FUTUROS DE SOJA NEGOCIADOS NA BOLSA DE MERCADORIAS & FUTUROS (BM & FBOVESPA)

    OpenAIRE

    Castro Junior, Luiz Gonzaga de; Guimaraes, Rogerio de Souza; Safadi, Thelma

    2012-01-01

    O mercado futuro é um instrumento de proteção e administração de risco imprescindível, mas ainda pouco explorado na Bolsa de Mercadorias & Futuros (BM&FBOVESPA), no que diz respeito ao contrato futuro de soja. Isso é notado quando se visualiza o volume de negócios, que é uma essencial medida de liquidez do mercado. Assim, este trabalho teve como objetivos identificar e avaliar os fatores condicionantes do volume de contratos futuros de soja negociados na BM&FBOVESPA. A metodologia englobou um...

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

    OpenAIRE

    Antônio André Cunha Callado; Aldo Leonardo Cunha Callado; Carla Renata Silva Leitão

    2014-01-01

    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, Ín...

  9. Una propuesta para un sistema de análisis técnico para compra y venta de acciones en la Bolsa Mexicana de Valores

    OpenAIRE

    Alfredo Díaz Mata

    2005-01-01

    Se presenta el procedimiento y el conjunto de herramientas del análisis técnico que utiliza un sistema computarizado que se está construyendo con el propósito de tomar decisiones de compra y venta de acciones en la Bolsa Mexicana de Valores (BMV), así como también los resultados alcanzados en 14 meses. El sistema consiste, básicamente, en realizar simulaciones y evaluaciones sobre los precios de 29 acciones de alta bursatilidad de la Bolsa Mexicana de Valores (BMV) y sobre l...

  10. La Bolsa como fórmula de transformación de los medios de comunicación en España

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    Medel Vicente, Aurelio

    2009-01-01

    El propósito de este trabajo de investigación es realizar un estudio exhaustivo sobre la estructura de propiedad de los medios de comunicación en España, del cual se concluye que a comienzos del siglo XXI sigue siendo mayoritariamente familiar, así como de los cambios que en ellos implica el hecho de que buena parte de ellos haya decidido cotizar en Bolsa. Esta investigación pone de manifiesto que la cotización en Bolsa está produciendo una transformación en los medios de comunicación. Somete...

  11. Algumas reflexões a propósito da bolsa de valores sociais enquanto promotora da responsabilidade social da empresa

    OpenAIRE

    Meira, Deolinda Maria Moreira Aparício

    2010-01-01

    Centrando-se na cooperativa, esta comunicação subordinada ao tema «Algumas reflexões a propósito da Bolsa de Valores Sociais enquanto promotora da Responsabilidade Social da Empresa» pretende reflectir sobre a Bolsa de Valores Sociais (BVS), recentemente criada em Portugal, cuja finalidade foi, primacialmente, a de permitir a obtenção de meios de financiamento às organizações da Economia Social que se dediquem a projectos nas áreas da educação e do empreendedorismo. Reflexamente, a BVS promov...

  12. BOLSA FAMÍLIA OU DESEMPENHO DA ECONOMIA? DETERMINANTES DA REELEIÇÃO DE LULA EM 2006

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    MAURICIO CANÊDO-PINHEIRO

    2015-03-01

    Full Text Available ResumoEste artigo investiga os determinantes dos resultados das eleições presidenciais brasileiras de 2006, em particular o papel do programa Bolsa Família e do desempenho econômico na migração da base eleitoral de Lula para regiões menos desenvolvidas. Os resultados indicam que, entre eleitores habituais de Lula, a participação no programa não aumenta a probabilidade de voto nesse candidato em 2006. Entre eleitores habituais de outros candidatos, esse efeito é positivo. Além disso, um maior crescimento econômico somente significou votos adicionais para Lula entre os eleitores mais ricos. Por fim, o impacto do programa Bolsa Família se mostrou bastante superior ao do desempenho econômico. No entanto, nenhum dos dois fatores foi capaz de explicar satisfatoriamente toda a extensão da mudança observada em 2006.

  13. 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.

  14. Análise da evolução da liquidez no mercado acionista português : o impacto da fusão das bolsas e entrada na Euronext

    OpenAIRE

    Ribeiro, Miguel Valgôde

    2015-01-01

    O objetivo deste trabalho é estudar o impacto da fusão da Bolsa de Valores de Lisboa e da Bolsa de Derivados do Porto em 2000, e da entrada da resultante Bolsa de Valores de Lisboa e Porto na rede internacional NYSE Euronext 2002, nos níveis de liquidez do mercado financeiro português. Para este fim são utilizados os dados relativos a 16 empresas cotadas, com maior valor de mercado para o período de 1995 a 2010, para criar índices de Amihud, spread bid-ask relativos, e rácios de turnover, com...

  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

    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...

  16. 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.

  17. 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

    OpenAIRE

    Doraliza Auxiliadora Abranches Monteiro; Marco Aurélio Marques Ferreira; Karla Maria Damiano Teixeira

    2009-01-01

    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 di...

  18. 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.

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

    OpenAIRE

    Luis Antonio Winck Cechin; André Carraro; Felipe Garcia Ribeiro; Rodrigo Nobre Fernandez

    2015-01-01

    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 ...

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

    OpenAIRE

    Barata Rita Barradas; Goldbaum Moisés

    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 ...

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

    Directory of Open Access Journals (Sweden)

    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.

  2. Mujer directiva y salida a bolsa de empresas de alta tecnología: un estudio del mercado de valores estadounidense

    OpenAIRE

    Quintana García, Cristina; Marchante Lara, Macarena; Benavides Velasco, Carlos A.

    2015-01-01

    Este trabajo examina la relación entre la presencia de la mujer en los equipos de alta dirección y el éxito de las empresas de alta tecnología en su salida a bolsa. Asimismo, analiza cómo indicadores específicos de capacidad de innovación pueden mediar dicha relación. Una investigación empírica de una muestra de empresas biotecnológicas que salieron a bolsa en el mercado de valores estadounidense, indica un efecto negativo y significativo de la proporción de mujeres en la dirección ejecutiva,...

  3. 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

    Directory of Open Access Journals (Sweden)

    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

  4. DISEÑO DE UN SISTEMA EXPERTO DIFUSO: EVALUACIÓN DE RIESGOCREDITICIO EN FIRMAS COMISIONISTAS DE BOLSA PARA EL OTORGAMIENTO DE RECURSOS FINANCIEROS

    OpenAIRE

    Santiago Medina Hurtado; Oscar Oswaldo Manco

    2007-01-01

    Esta investigación estudia y modelaun sistema de asignación de recursosfinancieros a compañías comisionistasde bolsa, con el fin de que dichosrecursos sean invertidos a nombrede la empresa (inversionista), de talforma que se disminuya el riesgode impago del capital asignado yademás; que estos capitales generenrendimientos adicionales para laempresa. El modelo planteado basadoen Sistemas Expertos Difusospermite soportar estas decisiones deasignación de recursos financieros.Inicialmente se desc...

  5. A influência do sexo e da idade na prevalência de bolsas periodontais The influence of gender and age on the prevalence of periodontal pockets

    Directory of Open Access Journals (Sweden)

    Luciana MACHION

    2000-03-01

    Full Text Available Este trabalho teve como objetivo avaliar a influência dos fatores de risco na prevalência de bolsas periodontais em pacientes atendidos na clínica do terceiro e quarto anos da Faculdade de Odontologia de Piracicaba - Unicamp. Foram avaliados 100 pacientes através do levantamento dos dados contidos nas fichas clínico-anamnésicas, sendo consideradas bolsas de profundidade: 3 mm, 5 mm, 7 mm e 10 mm, de acordo com o sistema diagnóstico WS (SALLUM; SALLUM27, 1996. Os resultados foram comparados entre as profundidades de sondagem e as variáveis idade, sexo, bem como sua distribuição por sextantes. Observou-se maior prevalência de bolsas periodontais no sexo masculino, bem como maior profundidade de sondagem em pacientes acima de 31 anos. A distribuição de bolsas periodontais entre os sextantes foi homogênea.The aim of this study was to evaluate the influence of risk factors on the prevalence of periodontal pockets in patients attending the clinic of the School of Dentistry of Piracicaba - Unicamp. The sample consisted of 100 patients attended by the students from the third and fourth years of undergraduation. The data were taken from anamneses and clinical - periodontal records. Probing depths were considered to be 3, 5, 7 and 10 mm, according to the WS diagnosis system (SALLUM, 1996. The results were compared regarding pockets depths and the risk factors age and gender. Also, the distribution of pockets among the sextants was observed. This study indicated a major prevalence of periodontal pockets in men and an increase in probing depth in patients older than 31 years. The distribution of pockets among the sextants was relatively uniform in all studied groups.

  6. 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...

  7. 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

  8. 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

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    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.

  9. 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.

  10. 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

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

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    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.

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

    Directory of Open Access Journals (Sweden)

    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.

  13. 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.

  14. 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

  15. Experimental dermatophytosis in hamsters inoculated with Trichophyton mentagrophytes in the cheek pouch Dermatofitose experimental do hamster inoculado com Trychophyton mentagrophytes na bolsa jugal

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    Maria Sueli Parreira de ARRUDA

    2001-02-01

    Full Text Available This study presents the results of T. mentagrophytes inoculation in the cheek pouch of the hamster, an immunologically privileged site. Forty two animals were used: 21 inoculated with 10(6 fungi in the cheek pouch (group 1 and 21 inoculated initially with 10(6 fungi in the foot pad and 15 days later in the cheek pouch, with the same amount of fungi (group 2. Animals were sacrificed at 20 hours, 3, 7, 14, 30, 60, and 120 days; samples from inoculated cheek pouch, and foot pads submitted to the foot pad test (FPT, were collected. Independent of group and time of evolution of infection, animals did not develop delayed hypersensitivity evaluated through the FPT. The pre-inoculation of fungi in the foot pad did not change the morphology of lesions induced in the cheek pouch. Therefore, in animals of group 1 and 2, the introduction of the fungus in the cheek pouch resulted in focal lesion composed of a sterile acute inflammatory infiltrate, with abscess formation that evolved to a macrophagic reaction, and later to resolution even in the absence of immune response detectable by FPT. Our results indicate that in spite of the important role of the immune response in the spontaneous regression of dermatophytosis, other factors are also an integral part in the defense against this fungal infection.Esse estudo apresenta os resultados obtidos quando da inoculação de Trychophyton mentagrophytes na bolsa jugal do hamster, local imunologicamente privilegiado. Foram utilizados 42 animais: 21 inoculados com 10(6 fungos na bolsa jugal (grupo 1 e, 21 inicialmente inoculados com 10(6 fungos no coxim plantar e, 15 dias após, na bolsa jugal com a mesma quantidade fúngica (grupo 2. Os animais foram sacrificados às 20 h, 3, 7, 14, 30, 60 e 120 dias; foram coletadas amostras da bolsa jugal inoculada, e das patas submetidas ao teste do coxim plantar (TCP. Independente do grupo e do tempo de evolução da infecção, os animais não desenvolveram hipersensibilidade

  16. 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.

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

    Directory of Open Access Journals (Sweden)

    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.

  18. 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.

  19. 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...

  20. 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...

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

    OpenAIRE

    J Noda; J ULLOA; C L Perera; G Jara; Cuello, S.; E. Rodríguez

    2005-01-01

    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 chileno...

  2. 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...

  3. Programa Bolsa Família: impacto das transferências sobre os gastos com alimentos em famílias rurais

    Directory of Open Access Journals (Sweden)

    Gisléia Benini Duarte

    2009-12-01

    Full Text Available Programas de transferência condicionada de renda são políticas sociais correntemente empregadas para combater e reduzir a pobreza em diversos países. No curto prazo, esses programas visam aliviar os problemas decorrentes da situação de pobreza, sendo que, no longo prazo, o objetivo é investir no capital humano, quebrando o ciclo intergeracional da pobreza. Estudos têm sido realizados para avaliar os impactos desses programas sobre variáveis como freqüência escolar, trabalho infantil, gastos com alimentação, entre outros. Este trabalho avalia o impacto da transferência de renda do Programa Bolsa Família sobre os gastos com alimentos de famílias rurais. As estimações foram feitas com base no método de Propensity Score Matching (PSM, que corrige para o viés de seleção amostral. Os resultados mostram que o valor médio das despesas anuais para as famílias beneficiárias supera em R$ 246 os gastos totais das famílias não-participantes. Considerando que a média anual recebida por essas famílias é de R$ 278, pode-se inferir que 88% desse valor é utilizado para consumo de alimento. Portanto, o programa de transferência condicionada Bolsa Família exerce um impacto positivo sobre o consumo de alimentos dessas famílias selecionadas.Conditional income transfer programs are social policies currently adopted to reduce poverty in several countries. These conditional transfer schemes have a goal to alleviate some of the consequences of poverty in the short run and increase human capital in the long run changing the intergenerational poverty cycle. Several papers evaluate the impact of income transfer on school attendance, child work and food expenses, among others. This paper analyzes the impact of the Bolsa Família Program on food expenses of rural families. The Propensity Score Method was used to correct sample selection bias. Results show that annual food expenses increased 246 reais in relation to non participant families

  4. Teoría de matrices aleatorias y correlación de series financieras: el caso de la Bolsa Mexicana de Valores

    OpenAIRE

    Linda Margarita Medina Herrera; Ricardo Mansilla Corona

    2008-01-01

    In this paper we apply random matrix theory (RMT) to the analysis of cross-correlation matrix C constructed from daily returns of 65 stocks traded at the Bolsa Mexicana de Valores during a trading period of eighth years. We find that the statistics of most of the eigenvalues in the spectrum of C agrees with the prediction of RMT, but there are deviations for a few of the larger eigenvalues. We show that C has the universal properties of the Gaussian orthogonal ensemble of random matrices. Fur...

  5. Custo do financiamento bancário e qualidade da informação financeira: estudos para empresas sem valores cotados em Bolsa

    OpenAIRE

    Carmo, Cecília Margarita Rendeiro do

    2013-01-01

    A Tese é constituída por três estudos distintos mas ligados pela temática do custo do financiamento bancário e da qualidade da informação financeira, em empresas sem valores cotados em bolsa. No primeiro estudo analisa-se a relação entre o custo do financiamento bancário e a qualidade da informação financeira nas empresas portuguesas. A qualidade da informação financeira é entendida como sinónimo de qualidade dos resultados e é medida através do valor absoluto dos accruals ...

  6. An??lisis de la Bolsa Mexicana de Valores a trav??s de m??todos estad??sticos = Analysis of Mexican Stock Exchange through statistical methods

    OpenAIRE

    Mu??oz Trapote, Rub??n

    2014-01-01

    El objeto de estudio de este Trabajo de Fin de Grado, consiste en estudiar y analizar el comportamiento del mercado mexicano de valores mediante una serie de m??todos estad??sticos. El estudio se apoya en la metodolog??a correspondiente a estas t??cnicas para la aplicaci??n del an??lisis emp??rico. El prop??sito principal es comprobar que variables macroecon??micas influyen de manera m??s notable en el mercado burs??til, as?? como la clasificaci??n de las empresas que cotizan en la Bolsa M...

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

    OpenAIRE

    Ruth Leticia Hidalgo Gallardo; Emma García Meca

    2009-01-01

    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 empres...

  8. Impacto de expectativas políticas en los retornos del Índice General de la Bolsa de Valores de Lima

    OpenAIRE

    Gabriel Rodríguez; Alfredo Vargas

    2012-01-01

    El presente documento analiza el impacto de las expectativas políticas (medida como la probabilidad de que un candidato gane las elecciones) sobre los retornos del índice general de la Bolsa de Valores de Lima (IGBVL) utilizando información para los períodos electorales de 1995 y 2000. La hipótesis a verificar es si el grado de incertidumbre sobre el resultado de las elecciones presidenciales afecta los retornos del IGBVL. Se usan otras variables explicativas como el tipo de cambio, la inflac...

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

    OpenAIRE

    Vinicius de Castro Scottá dos Passos; Juliano Lima Pinheiro

    2010-01-01

    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 a...

  10. 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 ...

  11. 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...

  12. IMPACTO DO FECHAMENTO DA BOLSA DE VALORES DE NOVA YORK (NYSE) SOBRE O RISCO DE MERCADO DAS EMPRESAS NEGOCIADAS NA BM&FBOVESPA: UM ESTUDO SOBRE A ÓTICA DA INTERDEPENDENCIA ENTRE MERCADOS

    OpenAIRE

    Josilene da Silva Barbosa; Flávio Ribeiro; Silvia Consoni; Rodrigo Oliveira Soares; José Roberto Frega

    2016-01-01

    Na última semana de outubro de 2012, devido ao fenômeno climático Sandy, a Bolsa de Valores de Nova York (NYSE) suspendeu suas operações por dois dias consecutivos (29 e 30 de outubro). Concomitantemente, a Bolsa de Valores de São Paulo (BM&FBovespa) teve seu volume de negociações reduzido, o que pode estar relacionado à integração entre mercados. O objetivo desta pesquisa consiste em verificar se o fechamento da NYSE, nos dias 29 e 30 de outubro de 2012, alterou o risco de mercado das empres...

  13. 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

  14. [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. PMID:22124825

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

    Directory of Open Access Journals (Sweden)

    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.

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

    Directory of Open Access Journals (Sweden)

    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.

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

    Directory of Open Access Journals (Sweden)

    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.

  18. Abertis Infraestructuras S.A. y su valor en bolsa. Análisis del mercado bursátil español y simulación de análisis en las decisiones de inversión en Abertis Infraestructuras S.A.

    OpenAIRE

    Mihai, Andreea-Madalina

    2016-01-01

    Durante mucho tiempo, invertir en bolsa era una actividad que se miraba desde fuera y a la que solamente se dedicaba aquellas personas con un gran conocimiento en la materia, o profesionales de los mercados financieros. La aparición de internet y el acceso por parte de todos a una cantidad de información cada vez mayor han hecho que la bolsa gane popularidad. Es evidente que los que queremos entrar en el juego de la Bolsa lo estamos haciendo para ganar dinero, pero sabemos ¿en qué, como, y...

  19. 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.

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

    Directory of Open Access Journals (Sweden)

    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

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

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    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.

  2. Le programme Bolsa Família (Bourse familiale) : analyse du programme brésilien de transfert conditionnel de revenus

    OpenAIRE

    Luciana Mourão; Anderson Macedo de Jesus

    2012-01-01

    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 fai...

  3. 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...

  4. Notas preliminares de uma crítica feminista aos programas de transferência direta de renda: o caso do Bolsa Família no Brasil = Preliminary notes of a feminist critique to income transference programs: the case of “Bolsa Familia” in Brazil

    Directory of Open Access Journals (Sweden)

    Gomes, Simone da Silva Ribeiro

    2011-01-01

    Full Text Available Nos últimos anos, os programas de “luta contra a pobreza” e transferência direta de renda estão presentes na maioria dos países latino-americanos. A partir do primeiro ano de governo do presidente Lula (2003, o Brasil enfatiza esta forma de política social, ao unificar diferentes modelos de transferência do governo anterior (1995-2002 em um só programa: o Bolsa Família. O artigo em questão busca expor a crítica da regulação da pobreza e o impacto das condicionalidades referentes a esta lógica de intervenção na reprodução social de um grupo específico. A relação entre o Estado e as mulheres – responsáveis únicas pelo sustento financeiro de suas casas e, majoritariamente, as maiores beneficiárias destes programas – é caracterizada por atravessamentos em termos de classe social, gênero e raça. Ao apresentar a perspectiva feminista, o artigo procura abrir uma série de questões ao analisar como as condicionalidades impostas pelo Programa Bolsa Família tendem a naturalizar o papel reprodutivo das mulheres na sociedade brasileira, limitando seu espaço de agenciamento e emancipação.

  5. 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...

  6. 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.

  7. 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

  8. 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...

  9. 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...

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. Reactor Physics

    International Nuclear Information System (INIS)

    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

  17. Reactor Physics

    International Nuclear Information System (INIS)

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

  18. 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.

  19. 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

  20. 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

  1. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Martens, Frederick H. [Argonne National Laboratory; Jacobson, Norman H.

    1968-09-01

    This booklet discusses research reactors - reactors designed to provide a source of neutrons and/or gamma radiation for research, or to aid in the investigation of the effects of radiation on any type of material.

  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

    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...

  3. 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)

  4. 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

  5. Research reactors

    International Nuclear Information System (INIS)

    There are currently 284 research reactors in operation, and 12 under construction around the world. Of the operating reactors, nearly two-thirds are used exclusively for research, and the rest for a variety of purposes, including training, testing, and critical assembly. For more than 50 years, research reactor programs have contributed greatly to the scientific and educational communities. Today, six of the world's research reactors are being shut down, three of which are in the USA. With government budget constraints and the growing proliferation concerns surrounding the use of highly enriched uranium in some of these reactors, the future of nuclear research could be impacted

  6. Reactor container

    International Nuclear Information System (INIS)

    Object: To provide a jet and missile protective wall of a configuration being inflated toward the center of a reactor container on the inside of a body of the reactor container disposed within a biological shield wall to thereby increase safety of the reactor container. Structure: A jet and missile protective wall comprised of curved surfaces internally formed with a plurality of arch inflations filled with concrete between inner and outer iron plates and shape steel beam is provided between a reactor container surrounded by a biological shield wall and a thermal shield wall surrounding the reactor pressure vessel, and an adiabatic heat insulating material is filled in space therebetween. (Yoshino, Y.)

  7. 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.

  8. Le programme Bolsa Família (Bourse familiale : analyse du programme brésilien de transfert conditionnel de revenus

    Directory of Open Access Journals (Sweden)

    Luciana Mourão

    2012-01-01

    Full Text Available 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 présentés pour chacun de ces aspects, et tout résultat considéré comme convergent ou divergent a fait l'objet d'une discussion. La conclusion générale est que le programme a généré des résultats significatifs pour le pays, mais qu'il existe encore des problèmes à prendre en considération, notamment les facteurs conditionnels et la gestion intégrée du programme.

  9. 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.

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

    OpenAIRE

    Mariano Luque Gallego; Mercedes González Lozano; Rafael Caballero Fernández; Rafael Rodríguez Avilés.

    2004-01-01

    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 cua...

  11. The hamster cheek pouch: an immunologically privileged site suitable to the study of granulomatous infections A bolsa jugal do hamster: um local imunologicamente privilegiado, apropriado para o estudo das ¡nfecções granulomatosas

    Directory of Open Access Journals (Sweden)

    M. S. P. de Arruda

    1995-08-01

    Full Text Available The hamster check pouch is an invagination of oral mucosa, characterized histologically as skin-like. In this paper we describe anatomical, histological and embriological features of the pouch and coment on the pouch as an immunologically privileged site since it lacks lymphatic drainage and has few Langerhans cells. We present the review from literature and our observations after inoculation in the pouch of mycobacteriae (BCG, Mycobacterium tuberculosis and Mycobacterium leprae and a fungus (Paracoccidioides brasiliensis. Lesions in the pouch were granulomatous but smaller and long lasting; even granulomatous, the reaction was inefficient to control the proliferation of agents compared with inoculation in other sites, except for BCG. Appearance of immunity was also delayed or absent and, when it was detected, a sharp decrease in number of agents in pouch lesions was observed. These observations make the pouch an interesting site for the study of the role of immune system in infeccious diseases and in granuloma formation.A bolsa jugal do hamster (BJH é uma invaginação da mucosa oral, caracterizada histologicamente como semelhante a pele. Nesse estudo nós descrevemos algumas de suas características anatômicas, histológicas e embriológicas e comentamos sobre sua propriedade como local imunologicamente privilegiado, considerando a ausência de drenagem linfática e o reduzido número de células de Langerhans. Apresentamos também os resultados obtidos quando da inoculação de micobacterias (BCG, Mycobacterium tuberculosis e Mycobacterium leprae e do fungo Paracoccidioides brasiliensis na bolsa jugal. Comparada com as lesões provocadas em outras localizações e, à exceção do BCG, as lesões induzidas na bolsa são menores e de maior duração e, mesmo quando granulomatosas, incapazes de controlar a multiplicação do agente; nos casos em que houve o desenvolvimento da resposta imune, ele se fez tardiamente e foi acompanhado pela redu

  12. 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

    OpenAIRE

    G Bazzano; Parodi, R.; S Tabares; Sembaj, A

    2012-01-01

    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)...

  13. 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 ...

  14. 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 ...

  15. 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...

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

    OpenAIRE

    Edila E. Herrera R.

    2013-01-01

    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 ...

  17. 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...

  18. 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...

  19. 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

    OpenAIRE

    Juan David Velásquez Henao; Mario Alberto Aldana Dumar

    2007-01-01

    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...

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

    OpenAIRE

    Felipe J. HEVIA

    2011-01-01

    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 l...

  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

    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; ...

  2. 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

    OpenAIRE

    Armando V. Verceze; Newton L. Pereira; Everton J. Buzzo

    2006-01-01

    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, u...

  3. 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 ...

  4. 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)

  5. Heterogeneous reactors

    International Nuclear Information System (INIS)

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

  6. 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.

  7. Plasma reactor

    OpenAIRE

    Molina Mansilla, Ricardo; Erra Serrabasa, Pilar; Bertrán Serra, Enric

    2008-01-01

    [EN] A plasma reactor that can operate in a wide pressure range, from vacuum and low pressures to atmospheric pressure and higher pressures. The plasma reactor is also able to regulate other important settings and can be used for processing a wide range of different samples, such as relatively large samples or samples with rough surfaces.

  8. Reactor physics

    International Nuclear Information System (INIS)

    Progress in research on reactor physics in 1997 at the Belgian Nuclear Research Centre SCK/CEN is described. Activities in the following four domains are discussed: core physics, ex-core neutron transport, experiments in Materials Testing Reactors, international benchmarks

  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. 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

  12. 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.

  13. 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.

  14. Nuclear reactors

    International Nuclear Information System (INIS)

    This draft chart contains graphical symbols from which the type of (nuclear) reactor can be seen. They will serve as illustrations for graphical sketches. Important features of the individual reactor types are marked out graphically. The user can combine these symbols to characterize a specific reactor type. The basic graphical symbol is a square with a point in the centre. Functional groups can be depicted for closer specification. If two functional groups are not clearly separated, this is symbolized by a dotted line or a channel. Supply and discharge lines for coolant, moderator and fuel are specified in accordance with DIN 2481 and can be further specified by additional symbols if necessary. The examples in the paper show several different reactor types. (orig./AK)

  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. Multifunctional reactors

    OpenAIRE

    Westerterp, K.R.

    1992-01-01

    Multifunctional reactors are single pieces of equipment in which, besides the reaction, other functions are carried out simultaneously. The other functions can be a heat, mass or momentum transfer operation and even another reaction. Multifunctional reactors are not new, but they have received much emphasis in research in the last decade. A survey is given of modern developments and the first successful applications on a large scale. It is explained why their application in many instances is ...

  17. 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)

  18. 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)

  19. Breeder reactors

    International Nuclear Information System (INIS)

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components

  20. 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

  1. 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

  2. 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...

  3. 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...

  4. 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 ...

  5. 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

    OpenAIRE

    Paolo Saona Hoffmann

    2009-01-01

    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 Índ...

  6. Research reactors - an overview

    Energy Technology Data Exchange (ETDEWEB)

    West, C.D.

    1997-03-01

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

  7. 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

  8. Reactor utilization

    International Nuclear Information System (INIS)

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel

  9. Reactor Neutrinos

    CERN Document Server

    Lasserre, T; Lasserre, Thierry; Sobel, Henry W.

    2005-01-01

    We review the status and the results of reactor neutrino experiments, that toe the cutting edge of neutrino research. Short baseline experiments have provided the measurement of the reactor neutrino spectrum, and are still searching for important phenomena such as the neutrino magnetic moment. They could open the door to the measurement of coherent neutrino scattering in a near future. Middle and long baseline oscillation experiments at Chooz and KamLAND have played a relevant role in neutrino oscillation physics in the last years. It is now widely accepted that a new middle baseline disappearance reactor neutrino experiment with multiple detectors could provide a clean measurement of the last undetermined neutrino mixing angle theta13. We conclude by opening on possible use of neutrinos for Society: NonProliferation of Nuclear materials and Geophysics.

  10. Nuclear reactors

    International Nuclear Information System (INIS)

    A nuclear reactor has a large prompt negative temperature coefficient of reactivity. A reactor core assembly of a plurality of fluid-tight fuel elements is located within a water-filled tank. Each fuel element contains a solid homogeneous mixture of 50-79 w/o zirconium hydride, 20-50 w/o uranium and 0.5-1.5 W erbium. The uranium is not more than 20 percent enriched, and the ratio of hydrogen atoms to zirconium atoms is between 1.5:1 and 7:1. The core has a long lifetime, E.G., at least about 1200 days

  11. Nuclear reactors

    International Nuclear Information System (INIS)

    In a liquid cooled nuclear reactor, the combination is described for a single-walled vessel containing liquid coolant in which the reactor core is submerged, and a containment structure, primarily of material for shielding against radioactivity, surrounding at least the liquid-containing part of the vessel with clearance therebetween and having that surface thereof which faces the vessel make compatible with the liquid, thereby providing a leak jacket for the vessel. The structure is preferably a metal-lined concrete vault, and cooling means are provided for protecting the concrete against reaching a temperature at which damage would occur. (U.S.)

  12. 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.

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    In an improved reactor core for a high conversion BWR reactor, Pu-breeding type BWR type reactor, Pu-breeding type BWR type rector, FEBR type reactor, etc., two types of fuel assemblies are loaded such that fuel assemblies using a channel box of a smaller irradiation deformation ratio are loaded in a high conversion region, while other fuel assemblies are loaded in a burner region. This enables to suppress the irradiation deformation within an allowable limit in the high conversion region where the fast neutron flux is high and the load weight from the inside of the channel box due to the pressure loss is large. At the same time, the irradiation deformation can be restricted within an allowable limit without deteriorating the neutron economy in the burner region in which fast neutron flux is low and the load weight from the inside of the channel box is small since a channel box with smaller neutron absorption cross section or reduced wall thickness is charged. As a result, it is possible to prevent structural deformations such as swelling of the channel box, bending of the entire assemblies, bending of fuel rods, etc. (K.M.)

  14. 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

  15. 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.)

  16. Reactor building

    International Nuclear Information System (INIS)

    The present invention concerns a structure of ABWR-type reactor buildings, which can increase the capacity of a spent fuel storage area at a low cost and improved earthquake proofness. In the reactor building, the floor of a spent fuel pool is made flat, and a depth of the pool water satisfying requirement for shielding is ensured. In addition, a depth of pool water is also maintained for a equipment provisionally storing pool for storing spent fuels, and a capacity for a spent fuel storage area is increased by utilizing surplus space of the equipment provisionally storing pool. Since the flattened floor of the spent fuel pool is flushed with the floor of the equipment provisionally storing pool, transfer of horizontal loads applied to the building upon occurrence of earthquakes is made smooth, to improve earthquake proofness of the building. (T.M.)

  17. Nuclear reactors

    International Nuclear Information System (INIS)

    Disclosed is a nuclear reactor cooled by a freezable liquid has a vessel for containing said liquid and comprising a structure shaped as a container, and cooling means in the region of the surface of said structure for effecting freezing of said liquid coolant at and for a finite distance from said surface for providing a layer of frozen coolant on and supported by said surface for containing said liquid coolant. In a specific example, where the reactor is sodium-cooled, the said structure is a metal-lined concrete vault, cooling is effected by closed cooling loops containing NaK, the loops extending over the lined surface of the concrete vault with outward and reverse pipe runs of each loop separated by thermal insulation, and air is flowed through cooling pipes embedded in the concrete behind the metal lining. 7 claims, 3 figures

  18. 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.

  19. Nuclear reactor

    International Nuclear Information System (INIS)

    The liquid metal (sodium) cooled fast breeder reactor has got fuel subassemblies which are bundled and enclosed by a common can. In order to reduce bending of the sides of the can because of the load caused by the coolant pressure the can has got a dodecagon-shaped crosssection. The surfaces of the can may be of equal width. One out of two surfaces may also be convex towards the center. (RW)

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    A detector having high sensitivity to fast neutrons and having low sensitivity to thermal neutrons is disposed for reducing influences of neutron detector signals on detection values of neutron fluxes when the upper end of control rod pass in the vicinity of the neutron flux detector. Namely, the change of the neutron fluxes is greater in the thermal neutron energy region while it is smaller in the fast neutron energy region. This is because the neutron absorbing cross section of B-10 used as neutron absorbers of control rods is greater in the thermal neutron region and it is smaller in the fast neutron region. As a result, increase of the neutron detection signals along with the local neutron flux change can be reduced, and detection signals corresponding to the reactor power can be obtained. Even when gang withdrawal of operating a plurality of control rods at the same time is performed, the reactor operation cycle can be measured accurately, thereby enabling to shorten the reactor startup time. (N.H.)

  1. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    In a BWR type nuclear reactor, the number of first fuel assemblies (uranium) loaded in a reactor core is smaller than that of second fuel assemblies (mixed oxide), the average burnup degree upon take-out of the first fuel assemblies is reduced to less than that of the second fuel assemblies, and the number of the kinds of the fuel rods constituting the first fuel assemblies is made smaller than that of the fuel rods constituting the second fuel assemblies. As a result, the variety of the plutonium enrichment degree is reduced to make the distribution of the axial enrichment degree uniform, thereby enabling to simplify the distribution of the enrichment degree. Then the number of molding fabrication steps for MOX fuel assemblies can be reduced, thereby enabling to reduce the cost for molding and fabrication. (N.H.)

  2. 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.

  3. Fundamentales empresariales y económicos en la valoración de acciones: el caso de la bolsa colombiana Business and economic foundations in valuation of shares: the Colombian stock exchange

    Directory of Open Access Journals (Sweden)

    César Attilio Ferrari

    2007-06-01

    Full Text Available El presente trabajo desarrolla un modelo del comportamiento adoptado por inversionistas que no logran diversificar sus riesgos en la bolsa local, dada la poca profundidad del mercado; por ello emplean la compra de divisas como instrumentos alternativos de inversión. El modelo se verificó econométricamente para la economía colombiana. Se concluye que los fuertes incrementos de precios de las acciones ocurridos en el 2005 en la Bolsa colombiana no se explican de forma plena por los fundamentos de la valoración: el desempeño de las empresas medido por sus dividendos y la percepción de riesgo medido por las tasas de descuento. Las pruebas econométricas arrojan datos respecto a la importante incidencia de los vaivenes en el mercado cambiario y en el comportamiento monetario sobre la determinación de los precios de las acciones. También hay hallazgos de burbujas racionales en el mercado colombiano de renta variable cuando existen fuertes expectativas de revaluación del peso o políticas monetarias expansivas.This work develops a model of the comportment adopted by investors who have succeeded in diversifying their risks in the local stock market, given the relative shallowness of that market. Therefore, they purchase currency as an alternative instrument of investment. The model was econometrically verified for the Colombian economy. The conclusion was that while strong increases in share prices occurred in 2005 in the Colombian stock exchange, they are not entirely explained by the basis of valuation; corporate performance measured by dividends and the perception of risk measured by discount rates. Econometric tests provide data with regard to the important effect of the fluctuations of the exchange market, and the monetary situation as a factor in the determination of share prices. At the same time, there are findings of rational bubbles in the Colombian variable-income market, where there are strong expectations of a revaluation of the

  4. 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.

  5. 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.

  6. Types of Nuclear Reactors

    International Nuclear Information System (INIS)

    The presentation is based on the following areas: Types of Nuclear Reactors, coolant, moderator, neutron spectrum, fuel type, pressurized water reactor (PWR), boiling water reactor (BWR) reactor pressurized heavy water (PHWR), gas-cooled reactor, RBMK , Nuclear Electricity Generation,Challenges in Nuclear Technology Deployment,EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR.

  7. 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

  8. 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.)

  9. 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

  10. Nuclear reactor

    International Nuclear Information System (INIS)

    Cover gas spaces for primary coolant vessel, such as a reactor container, a pump vessel and an intermediate heat exchanger vessel are in communication with each other by an inverted U-shaped pressure conduit. A transmitter and a receiver are disposed to the pressure conduit at appropriate positions. If vibration frequencies (pressure vibration) from low frequency to high frequency are generated continuously from the transmitter to the inside of the communication pipe, a resonance phenomenon (air-column resonance oscillation) is caused by the inherent frequency or the like of the communication pipe. The frequency of the air-column resonance oscillation is changed by the inner diameter and the clogged state of the pipelines. Accordingly, by detecting the change of the air-column oscillation characteristics by the receiver, the clogged state of the flow channels in the pipelines can be detected even during the reactor operation. With such procedures, steams of coolants flowing entrained by the cover gases can be prevented from condensation and coagulation at a low temperature portion of the pipelines, otherwise it would lead clogging in the pipelines. (I.N.)

  11. 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

  12. 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.

  13. 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.

  14. 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.

  15. A prática do trabalho infantil entre os beneficiários do Programa Bolsa-Escola Belo Horizonte: um estudo sobre os determinantes sociodemográficos

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    Michelle dos Santos Diniz

    2012-03-01

    Full Text Available O trabalho infantil atinge mais de cinco milhões de crianças e adolescentes no Brasil e é atribuído principalmente à pobreza. Este artigo tem por objetivo estudar as características das famílias com e sem registro de trabalho infantil inscritas no Programa Bolsa-Escola de Belo Horizonte e comparar os dois grupos para se detectar fatores possivelmente associados ao trabalho infantil. Foi realizado estudo transversal com 9.252 famílias participantes do programa, de 2003 a 2006, com enfoque nas características do domicílio, da mãe e da família. Entre as 9.252 famílias estudadas, 1.293 (13,9% apresentaram registro de trabalho infantil. Observou-se relação positiva entre a ocorrência de trabalho infantil e o maior número de pessoas na casa, ausência do cônjuge no domicílio, baixa escolaridade da mãe e inserção trabalhista da mãe. Apesar da consolidação do programa, o trabalho infantil continua presente entre os bolsistas. Além da pobreza, outros fatores podem contribuir para o trabalho infantil.

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

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    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".

  17. Sobrepeso e obesidade em crianças de cinco a dez anos de idade beneficiárias do Programa Bolsa Família no estado de Sergipe, Brasil Sobrepeso y obesidad en niños de cinco a diez años de edad beneficiarias del programa «Bolsa Família» en la provincia de Sergipe, Brasil Overweight and obesity in five- to ten-year-old children benefited from Bolsa Família Program in the State of Sergipe, Brazil

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    Diego Augusto S. Silva

    2011-12-01

    Full Text Available OBJETIVO: Estimar a prevalência de sobrepeso e obesidade em crianças beneficiárias do Programa Bolsa Família (PBF durante os anos de 2008 a 2010, de acordo com o sexo e com as regionais de saúde do estado de Sergipe. MÉTODOS: Estudo epidemiológico descritivo, conduzido com banco de dados secundário do Datasus/Sisvan. Foram obtidos 79.795 registros de crianças de cinco a dez anos de idade beneficiárias do PBF no estado de Sergipe, sendo 20.338 de 2008 (9.848 do sexo feminino e 10.490 do masculino, 27.106 de 2009 (13.092 do sexo feminino e 14.014 do masculino e 32.351 de 2010 (15.963 do sexo feminino e 16.388 do masculino. Foram mensuradas as variáveis de massa corporal e estatura, calculando-se o índice de massa corpórea (IMC, o qual foi analisado por meio dos valores do escore Z das tabelas normativas da Organização Mundial de Saúde. RESULTADOS: A prevalência de sobrepeso nos sexos feminino e masculino, respectivamente, no ano de 2008 foi de 12,2 e 12,4%; em 2009, de 13,2 e 13,2% e em 2010, de 13,1 e 13,3%. A prevalência de obesidade em 2008 foi de 11,0 e 13,5%; em 2009, de 11,9 e 15,1%; e em 2010, de 11,2 e 14,5%, respectivamente, para o sexo feminino e masculino. O sobrepeso e a obesidade foram mais prevalentes em crianças de municípios com menor Índice de Desenvolvimento Humano. CONCLUSÕES: Recomenda-se a criação de uma política nacional nutricional que dê subsídios para os beneficiários do PBF se alimentarem com qualidade.OBJETIVO: Estimar la prevalencia de sobrepeso y obesidad en niños beneficiarios del Programa «Bolsa Família» (PBF durante los años de 2008 a 2010, conforme al sexo y con las regionales de salud de la provincia de Sergipe. MÉTODOS: Estudio epidemiológico descriptivo, conducido con base de datos secundaria del Datasus/Sisvan. Se obtuvo 79.795 registros de niños entre cinco y diez años de edad beneficiarias del PBF en la provincia de Sergipe, siendo 20.338 el año de 2008 (9.848 del sexo

  18. 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.)

  19. Survey of research reactors

    International Nuclear Information System (INIS)

    A survey of reasearch reactors based on the IAEA Nuclear Research Reactor Data Base (RRDB) was done. This database includes information on 273 operating research reactors ranging in power from zero to several hundred MW. From these 273 operating research reactors 205 reactors have a power level below 5 MW, the remaining 68 reactors range from 5 MW up to several 100 MW thermal power. The major reactor types with common design are: Siemens Unterrichtsreaktors, 1.2 Argonaut reactors, Slowpoke reactors, the miniature neutron source reactors, TRIGA reactors, material testing reactors and high flux reactors. Technical data such as: power, fuel material, fuel type, enrichment, maximum neutron flux density and experimental facilities for each reactor type as well as a description of their utilization in physics and chemistry, medicine and biology, academic research and teaching, training purposes (students and physicists, operating personnel), industrial application (neutron radiography, silicon neutron transmutation doping facilities) are provided. The geographically distribution of these reactors is also shown. As conclusions the author discussed the advantages (low capital cost, low operating cost, low burn up, simple to operate, safe, less restrictive containment and sitting requirements, versatility) and disadvantages (lower sensitivity for NAA, limited radioisotope production, limited use of neutron beams, limited access to the core, licensing) of low power research reactors. 24 figs., refs. 15, Tab. 1 (nevyjel)

  20. Department of reactor technology

    International Nuclear Information System (INIS)

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  1. RB reactor noise analysis

    International Nuclear Information System (INIS)

    Statistical fluctuations of reactivity represent reactor noise. Analysis of reactor noise enables determining a series of reactor kinetic parameters. Fluctuations of power was measured by ionization chamber placed next to the tank of the RB reactor. The signal was digitized by an analog-digital converter. After calculation of the mean power, 3000 data obtained by sampling were analysed

  2. 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

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    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

  3. 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

  4. 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

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    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.

  5. 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

  6. Introduction of Nuclear Reactor Engineering

    International Nuclear Information System (INIS)

    This book introduces development, status, supply and demand and resource of nuclear reactor. It deals with basic knowledge of nuclear reactor, which are reactor system, heat recovery in reactor core, structural feature in reactor, materials of structure in reactor, shielding of gamma ray, shielding of reactor, safety and environmental problem of nuclear power plant, nuclear fuel and economical efficiency of nuclear energy.

  7. 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.

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

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    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.

  9. 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

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    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.

  10. Desarrollo y aplicaci??n de modelo neuroborroso para la predicci??n del precio de la acci??n de Ecopetrol en la Bolsa de Valores de Colombia mediante la utilizaci??n de indicadores t??cnicos y fundamentales y variables macroecon??micas

    OpenAIRE

    Rend??n G??mez, Camilo

    2015-01-01

    Los modelos de predicci??n de precios de activos financieros han captado la atenci??n de investigadores e inversionistas debido a las posibles rentabilidades que se podr??an obtener en caso de estimar valores acertados -- El presente trabajo presenta un modelo neuroborroso en el cual se combinan indicadores t??cnicos y fundamentales y variables macroecon??micas, comprendidas entre enero de 2010 y febrero de 2015, para predecir el precio de la acci??n de Ecopetrol en la Bolsa de Valores de Col...

  11. 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

  12. Research nuclear reactors

    International Nuclear Information System (INIS)

    Since the divergence of the first nuclear reactor in 1942, about 600 research or test reactors have been built throughout the world. Today 255 research reactors are operating in 57 countries and about 70% are over 25 years old. Whereas there are very few reactor types for power plants because of rationalization and standardisation, there is a great diversity of research reactors. We can divide them into 2 groups: heavy water cooled reactors and light water moderated reactors. Heavy water cooled reactors are dedicated to the production of high flux of thermal neutrons which are extracted from the core by means of neutronic channels. Light water moderated reactors involved pool reactors and slightly pressurized closed reactors, they are polyvalent but their main purposes are material testing, technological irradiations, radionuclide production and neutron radiography. At the moment 8 research reactors are being built in Canada, Germany, Iran, Japan, Kazakhstan, Morocco, Russia and Slovakia and 8 others are planned in 7 countries (France, Indonesia, Nigeria, Russia, Slovakia, Thailand and Tunisia. Different research reactors are described: Phebus, Masurca, Phenix and Petten HFR. The general principles of nuclear safety applied to test reactors are presented. (A.C.)

  13. Nuclear reactor building

    International Nuclear Information System (INIS)

    Purpose: To prevent seismic vibrations of external buildings from transmitting to the side walls of a reactor container in a tank type FBR reactor building. Constitution: The reactor building is structured such that the base mat for a reactor container chamber and a reactor container is separated from the base mat for the walls of building, and gas-tight material such as silicon rubber is filled in the gap therebetween. With such a constitution, even if the crane-supporting wall vibrates violently upon occurrence of earthqualkes, the seismic vibrations do not transmit toward the reactor container chamber. (Horiuchi, T.)

  14. Reactor Physics Programme

    International Nuclear Information System (INIS)

    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

  15. 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.)

  16. 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

  17. Process heat reactors

    International Nuclear Information System (INIS)

    The consumption of heat, for industrial and domestic needs, takes up half of the national energy supply; direct utilization of the heat produced by nuclear reactors could therefore contribute to reduce the deficit in the energetic results. The restraints proper to heat consumption (dispersal and variety of consumers, irregular demand) involve the development of the heat transport system structures and adequate nuclear reactors. With this in view, the Commissariat a l'Energie Atomique and Technicatome are developing the CAS reactor series, pressurized water reactors (PWR), (CAS 3G reactor with a power of 420 MW.th.), and the Thermos reactor (100 MW.th.), directly conceived to produce heat at 1200C and whose technology derives from the experimental pool reactors type. In order to prove the value of the Thermos design, an experimental reactor should soon be constructed in the Saclay nuclear research centre

  18. 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

  19. Nuclear Reactor RA Safety Report, Vol. 11, Reactor operation

    International Nuclear Information System (INIS)

    This volume includes the following chapters describing: Organisation of reactor operation (including operational safety, fuel management, and regulatory rules for RA reactor operation); Control and maintenance of reactor components (reactor core, nuclear fuel, heavy water and cover gas systems, mechanical structures, electric power supply system, reactor instrumentation); Quality assurance and Training of the reactor personnel

  20. The Chernobylsk reactor accident

    International Nuclear Information System (INIS)

    The construction, the safety philosophy, the major reactor physical parameters of RBMK-1000 type reactor units and the detailed description of the Chernobylsk-4 reactor accident, its causes and conclusions, the efforts to reduce the consequences on the reactor site and in the surroundings are discussed based on different types of Soviet documents including the report presented to the IAEA by the Soviet Atomic Energy Agency in August 1986. (V.N.)

  1. Zero energy reactor 'RB'

    International Nuclear Information System (INIS)

    In 1958 the zero energy reactor RB was built with the purpose of enabling critical experiments with various reactor systems to be carried out. The first core assembly built in this reactor consists of heavy water as moderator and natural uranium metal as fuel. In order to be able to obtain very accurate results when measuring the main characteristics of the assembly the reactor was built as a completely bare system. (author)

  2. High solids fermentation reactor

    Science.gov (United States)

    Wyman, Charles E.; Grohmann, Karel; Himmel, Michael E.; Richard, Christopher J.

    1993-01-01

    A fermentation reactor and method for fermentation of materials having greater than about 10% solids. The reactor includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The reactor and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.

  3. 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)

  4. Fusion reactor studies

    International Nuclear Information System (INIS)

    A review is given of fusion reactor systems studies, the objectives of these studies are outlined and some recent conceptual reactor designs are described. The need for further studies in greater depth is indicated so that progress towards a commercial fusion reactor may be consolidated. (U.K.)

  5. Reactor power measuring device

    International Nuclear Information System (INIS)

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

  6. 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

    OpenAIRE

    Silvia Regina Dias Médici Saldiva; Luiz Fernando Ferraz Silva; Paulo Hilário Nascimento Saldiva

    2010-01-01

    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 cria...

  7. 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

  8. 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.)

  9. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around the nuclear reactors. The curricula of the courses contain also the subject material of chemistry. With reference to the foreign curricula, a plan of educational subject material of chemistry in the Nuclear Engineering School of JAERI was considered, and the fundamental part of reactor chemistry was reviewed in this report. Since the students of the Nuclear Engineering School are not chemists, the knowledge necessary in and around the nuclear reactors was emphasized in order to familiarize the students with the reactor chemistry. The teaching experience of the fundamentals of reactor chemistry is also given. (author)

  10. 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

  11. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPRTM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENATM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENATM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  12. The Maple reactor project

    International Nuclear Information System (INIS)

    MDS Nordion supplies the majority of the world's reactor-produced medical isotopes. These isotopes are currently produced in the NRU reactor at AECL's Chalk River Laboratories (CRL). Medical isotopes and related technology are relied upon around the world to prevent, diagnose and treat disease. The NRU reactor, which has played a key role in supplying medical isotopes to date, has been in operation for over 40 years. Replacing this aging reactor has been a priority for MDS Nordion to assure the global nuclear medicine community that Canada will continue to be a dependable supplier of medical isotopes. MDS Nordion contracted AECL to construct two MAPLE reactors dedicated to the production of medical isotopes. The MDS Nordion Medical Isotope Reactor (MMIR) project started in September 1996. This paper describes the MAPLE reactors that AECL has built at its CRL site, and will operate for MDS Nordion. (author)

  13. High temperature reactors

    International Nuclear Information System (INIS)

    With the advent of high temperature reactors, nuclear energy, in addition to producing electricity, has shown enormous potential for the production of alternate transport energy carrier such as hydrogen. High efficiency hydrogen production processes need process heat at temperatures around 1173-1223 K. Bhabha Atomic Research Centre (BARC), is currently developing concepts of high temperature reactors capable of supplying process heat around 1273 K. These reactors would provide energy to facilitate combined production of hydrogen, electricity, and drinking water. Compact high temperature reactor is being developed as a technology demonstrator for associated technologies. Design has been also initiated for a 600 MWth innovative high temperature reactor. High temperature reactor development programme has opened new avenues for research in areas like advanced nuclear fuels, high temperature and corrosion resistant materials and protective coatings, heavy liquid metal coolant technologies, etc. The paper highlights design of these reactors and their material related requirements

  14. 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.

  15. Reactor Safety: Introduction

    International Nuclear Information System (INIS)

    The programme of the Reactor Safety Division focuses on the development of expertise on materials behaviour under irradiation for fission and fusion oriented applications. Furthermore, as nuclear energy needs international public acceptance with respect to safety and efficient management of natural resources and wants to reduce the burden of nuclear waste, the Reactor Safety Division enhanced its efforts to develop the MYRRHA project. MYRRHA, an accelerator driven sub-critical system, might have the potential to cope in Europe with the above mentioned constraints on acceptability and might serve as a technological platform for GEN IV reactor development, in particular the Liquid Metal Fast Reactor.The Reactor Safety Division gathers three research entities that are internationally recognised: the Reactor Materials Research department, the Reactor Physics and MYRRHA department and the Instrumentation department.The objectives of Reactor Materials Research are: to evaluate the integrity and behaviour of structural materials and nuclear fuels used in present and future nuclear power industry; to perform research to unravel and understand the parameters that determine the material and fuel behaviour under or after irradiation; to contribute to the interpretation and modelling of the materials and fuels behaviour in order to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the Reactor Materials Research department concentrate on four distinct disciplines: Reactor Pressure Vessel Steel embrittlement Stress corrosion cracking in reactor coolant environment, including Irradiation Assisted Stress Corrosion Cracking; Nuclear Fuel characterisation and development of new fuel types for commercial and test reactors. Development of materials for Fusion and advanced nuclear fission reactors. The safe operation of present nuclear power plants relies primarily on the integrity of the reactor pressure vessel

  16. Research reactors in Argentina

    International Nuclear Information System (INIS)

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

  17. Thai research reactor

    International Nuclear Information System (INIS)

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

  18. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

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

  19. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

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

  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. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

  2. Evaluation of research reactors

    International Nuclear Information System (INIS)

    The present status of research reactors with highly enriched (93%) uranium fuel at JAERI, JRR-2 and JMTR is described. JRR-2 is a heterogeneous type of reactor, using heavy water as moderator and coolant. It uses both MTR type and cylindrical type of fuel elements. The maximum thermal power and the thermal neutron flux are 10 MW and 2x1014 n/cm2 see respectively. The reactor has been used for various experiments such as solid state physics, material irradiation, reactor fuel irradiation and radioisotope production. The JMTR is a multi-purpose tank type material testing reactor, and light water moderator and coolant, operated at 50 MW. The evaluation of lower enriched fuel and its consequences for both reactors is considered more especially

  3. 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

  4. The nuclear soliton reactor

    International Nuclear Information System (INIS)

    The basic reactor physics of a completely novel nuclear fission reactor design - the soliton-reactor - is presented on the basis of a simple model. In such a reactor, the neutrons in the critical region convert either fertile material in the adjacent layers into fissile material or reduce the poisoning of fissile material in such a manner that successively new critical regions emerge. The result is an autocatalytically driven burn-up wave which propagates throughout the reactor. Thereby, the relevant characteristic spatial distributions (neutron flux, specific power density and the associated particle densities) are solitons - wave phenomena resulting from non-linear partial differential equations which do not change their shape during propagation. A qualitativley new kind of harnessing nuclear fission energy may become possible with fuel residence times comparable with the useful lifetime of the reactor system. In the long run, fast breeder systems which exploit the natural uranium and thorium resources, without any reprocessing capacity are imaginable. (orig.)

  5. 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...

  6. Fusion reactor research

    International Nuclear Information System (INIS)

    This work covers four separate areas: (1) development of technology for processing liquid lithium from blankets, (2) investigation of hydrogen isotope permeation in candidate structural metals and alloys for near-term fusion reactors, (3) analytical studies encompassing fusion reactor thermal hydraulics, tritium facility design, and fusion reactor safety, and (4) studies involving dosimetry and damage analysis. Recent accomplishments in each of these areas are summarized

  7. 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

  8. The replacement research reactor

    International Nuclear Information System (INIS)

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  9. PFBR reactor protection

    International Nuclear Information System (INIS)

    Design philosophy adopted for Prototype Fast breeder Reactor (PFBR) is a classical one and has the following features: triplicated sensors for measuring important safety parameters; two independent reactor protection Logic Systems based on solid state devices; reactivity control achieved by control rods; gas equipped modules at the core blanket interface providing negative reactivity. Design verification of these features showed that safety of the reactor can be achieved by a traditional approach since the inherent features of LMFBR make this easy

  10. Reactor BR2

    International Nuclear Information System (INIS)

    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

  11. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

  12. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of four main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents, the development of an expert system for the aid to diagnosis; the development and application of a probabilistic reactor dynamics method. Main achievements in 1999 are reported

  13. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

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

  14. 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)

  15. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

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

  16. New reactor concepts

    International Nuclear Information System (INIS)

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

  17. Reactor construction steels

    International Nuclear Information System (INIS)

    The basic functions of light water reactor components are shown on the example of a pressurized water reactor and the requirements resulting therefrom for steel, the basic structural material, are derived. A detailed analysis of three main groups of reactor steels is presented and the applications are indicated of low-alloyed steels, high-alloyed austenitic steels, and steels with a high content of Ni and of alloying additions for steam generator pipes. An outline is given of prospective fast breeder reactor steels. (J.K.)

  18. Commercialization of fast reactors

    International Nuclear Information System (INIS)

    Comparative analysis has been performed of capital and fuel cycle costs for fast BN-type and pressurized light water VVER-type reactors. As a result of materials demand and components costs comparison of NPPs with VVER-1000 and BN-600 reactors, respectively, conclusion was made, that under equal conditions of the comparison, NPP with fast reactor had surpassed the specific capital cost of NPP with VVER by about 30 - 40 %. Ways were determined for further decrease of this difference, as well as for the fuel cycle cost reduction, because at present it is higher than that of VVER-type reactors. (author)

  19. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

  20. Natural convection type reactor

    International Nuclear Information System (INIS)

    In a natural convection type nuclear reactor, a reactor core is disposed such that the top of the reactor core is always situated in a flooded position even if pipelines connected to the pressure vessel are ruptured and the level at the inside of the reactor vessel is reduced due to flashing. Further, a lower dry well situated below the pressure vessel is disposed such that it is in communication with a through hole to a pressure suppression chamber situated therearound and the reactor core is situated at the level lower than that of the through hole. If pipelines connected to the pressure vessel are ruptured to cause loss of water, although the water level is lowered after the end of the flashing, the reactor core is always flooded till the operation of a pressure accummulation water injection system to prevent the top of the reactor core even from temporary exposure. Further, injected water is discharged to the outside of the pressure vessel, transferred to the lower dry well, and flows through the through hole to the pressure control chamber and cools the surface of the reactor pressure vessel from the outside. Accordingly, the reactor core is cooled to surely and efficiently remove the after-heat. (N.H.)

  1. INVAP's Research Reactor Designs

    International Nuclear Information System (INIS)

    INVAP, an Argentine company founded more than three decades ago, is today recognized as one of the leaders within the research reactor industry. INVAP has participated in several projects covering a wide range of facilities, designed in accordance with the requirements of our different clients. For complying with these requirements, INVAP developed special skills and capabilities to deal with different fuel assemblies, different core cooling systems, and different reactor layouts. This paper summarizes the general features and utilization of several INVAP research reactor designs, from subcritical and critical assemblies to high-power reactors IAEA safety

  2. Reactor power control device

    International Nuclear Information System (INIS)

    The present invention provides a control device which can conduct scram and avoid lowering of the power of a nuclear power plant upon occurrence of earthquakes. Namely, the device of the present invention comprises, in addition to an existent power control device, (1) an earthquake detector for detecting occurrence and annihilation of earthquakes and (2) a reactor control device for outputting control rod operation signals and reactor core flow rate control signals depending on the earthquake detection signals from the detector, and reactor and plant information. With such a constitution, although the reactor is vibrated by earthquakes, the detector detects slight oscillations of the reactor by initial fine vibration waves as premonitory symptoms of serious earthquakes. The earthquake occurrence signals are outputted to the reactor control device. The reactor control device, receiving the signals, changes the position of control rods by way of control rod driving mechanisms to make the axial power distribution in the reactor core to a top peak type. As a result, even if the void amount in the reactor core is reduced by the subsequent actual earthquakes, since the void amount is moved, effects on the increase of neutron fluxes by the actual earthquakes is small. (I.S.)

  3. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  4. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    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. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

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

  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. 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.)

  8. Reactor Materials Research

    International Nuclear Information System (INIS)

    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)

  9. The fusion reactor

    International Nuclear Information System (INIS)

    Basic principles of the fusion reactor are outlined. Plasma heating and confinement schemes are described. These confinement systems include the linear Z pinch, magnetic mirrors and Tokamaks. A fusion reactor is described and a discussion is given of its environmental impact and its fuel situation. (R.L.)

  10. Polymerization Reactor Engineering.

    Science.gov (United States)

    Skaates, J. Michael

    1987-01-01

    Describes a polymerization reactor engineering course offered at Michigan Technological University which focuses on the design and operation of industrial polymerization reactors to achieve a desired degree of polymerization and molecular weight distribution. Provides a list of the course topics and assigned readings. (TW)

  11. 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)

  12. Gas-cooled reactors

    International Nuclear Information System (INIS)

    The present study is the second part of a general survey of Gas Cooled Reactors (GCRs). In this part, the course of development, overall performance and present development status of High Temperature Gas Cooled Reactors (HTCRs) and advances of HTGR systems are reviewed. (author)

  13. 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.

  14. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of two main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents. Main achievements in 1999 are reported

  15. Light water type reactor

    International Nuclear Information System (INIS)

    The nuclear reactor of the present invention prevents disruption of a reactor core even in a case of occurrence of entire AC power loss event, and even if a reactor core disruption should occur, it prevents a rupture of the reactor container due to excess heating. That is, a high pressure water injection system and a low pressure water injection system operated by a diesel engine are disposed in the reactor building in addition to an emergency core cooling system. With such a constitution, even if an entire AC power loss event should occur, water can surely be injected to the reactor thereby enabling to prevent the rupture of the reactor core. Even if it should be ruptured, water can be sprayed to the reactor container by the low pressure water injection system. Further, if each of water injection pumps of the high pressure water injection system and the low pressure water injection system can be driven also by motors in addition to the diesel engine, the pump operation can be conducted more certainly and integrally. (I.S.)

  16. 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

  17. Naval propulsion reactors

    International Nuclear Information System (INIS)

    This article deals with the design and exploitation of naval propulsion reactors, mainly of PWR-type. The other existing or conceivable types of reactors are also presented: 1 - specificities of nuclear propulsion (integration in the ship, marine environment, maneuverability, instantaneous availability, conditions of exploitation-isolation, nuclear safety, safety authority); 2 - PWR-type reactor (stable operation, mastered technology, general design, radiation protection); 3 - other reactor types; 4 - compact or integrated loops architecture; 5 - radiation protection; 6 - reactor core; 7 - reactivity control (core lifetime, control means and mechanisms); 8 - core cooling (natural circulation, forced circulation, primary flow-rate program); 9 - primary loop; 10 - pressurizer; 11 - steam generators and water-steam secondary loop; 12 - auxiliary and safety loops; 13 - control instrumentation; 14 - operation; 15 - nuclear wastes and dismantling. (J.S.)

  18. Iris reactor conceptual design

    International Nuclear Information System (INIS)

    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)

  19. 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

  20. Reactor core monitoring method

    Energy Technology Data Exchange (ETDEWEB)

    Mori, Michitsugu [Tokyo Electric Power Co., Inc. (Japan); Kanemoto, Shigeru; Enomoto, Mitsuhiro; Ebata, Shigeo

    1998-05-06

    The present invention provides a method of monitoring the state of coolant flow in a reactor of a BWR power plant. Namely, a plurality of local power region monitors (LPRM) are disposed to the inside of the reactor core for monitoring a power distribution. Signals of at least two optional LPRM detectors situated at positions different in axial or radial positions of the reactor core are obtained. General fluctuation components which nuclear hydrothermally fluctuate in overall reactor core are removed from the components of the signals. Then, correlational functions between these signals are determined. The state of coolant flow in the reactor is monitored based on the correlational function. When the axial flowing rate and radial flow interference are monitored, the accuracy upon monitoring axial and radial local behaviors of coolants can be improved by thus previously removing the general fluctuation components from signals of LPRM detectors and extracting local void information near to LPRM detectors at high accuracy. (I.S.)

  1. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    This manual covers all the aspects of the science of neutron transport in nuclear reactors and can be used with great advantage by students, engineers or even reactor experts. It is composed of 18 chapters: 1) basis of nuclear physics, 2) the interactions of neutrons with matter, 3) the interactions of electromagnetic radiations and charged-particles with matter, 4) neutron slowing-down, 5) resonant absorption, 6) Doppler effect, 7) neutron thermalization, 8) Boltzmann equation, 9) calculation methods in neutron transport theory, 10) neutron scattering, 11) reactor reactivity, 12) theory of the critical homogenous pile, 13) the neutron reflector, 14) the heterogeneous reactor, 15) the equations of the fuel cycle, 16) neutron counter-reactions, 17) reactor kinetics, and 18) calculation methods in neutron scattering

  2. 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

  3. FBR type reactor

    International Nuclear Information System (INIS)

    A circular neutron reflector is disposed vertically movably so as to surround the outer circumference of a reactor core barrel. A reflector driving device comprises a driving device main body attracted to the outer wall surface of the reactor barrel by electromagnetic attraction force and an inertia body disposed above the driving device main body vertically movably. A reflector is connected below the reactor driving device. At the initial stage, a spontaneous large current is supplied to upper electromagnetic repulsion coils of the reflector driving device, impact electromagnetic repulsion force is caused between the inertia body and the reflector driving device, so that the driving device main body moves downwardly by a predetermined distance and stopped. The reflector driving device can be lowered in a step-like manner to an appropriate position suitable to restart the reactor during stoppage of the reactor core by conducting spontaneous supply of current repeatedly to the upper electromagnetic repulsion coils. (I.N.)

  4. 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.)

  5. 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.

  6. 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.

  7. 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

  8. Multi-purpose reactor

    International Nuclear Information System (INIS)

    The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MWth, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co60) production capacity is 50000 Ci/yr, 200Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

  9. The CAREM reactor and present currents in reactor design

    International Nuclear Information System (INIS)

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

  10. 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)

  11. 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)

  12. 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.)

  13. 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.

  14. 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.

  15. Fourth Generation Reactor Concepts

    International Nuclear Information System (INIS)

    Concerns over energy resources availability, climate changes and energy supply security suggest an important role for nuclear energy in future energy supplies. So far nuclear energy evolved through three generations and is still evolving into new generation that is now being extensively studied. Nuclear Power Plants are producing 16% of the world's electricity. Today the world is moving towards hydrogen economy. Nuclear technologies can provide energy to dissociate water into oxygen and hydrogen and to production of synthetic fuel from coal gasification. The introduction of breeder reactors would turn nuclear energy from depletable energy supply into an unlimited supply. From the early beginnings of nuclear energy in the 1940s to the present, three generations of nuclear power reactors have been developed: First generation reactors: introduced during the period 1950-1970. Second generation: includes commercial power reactors built during 1970-1990 (PWR, BWR, Candu, Russian RBMK and VVER). Third generation: started being deployed in the 1990s and is composed of Advanced LWR (ALWR), Advanced BWR (ABWR) and Passive AP600 to be deployed in 2010-2030. Future advances of the nuclear technology designs can broaden opportunities for use of nuclear energy. The fourth generation reactors are expected to be deployed by 2030 in time to replace ageing reactors built in the 1970s and 1980s. The new reactors are to be designed with a view of the following objectives: economic competitiveness, enhanced safety, minimal radioactive waste production, proliferation resistance. The Generation IV International Forum (GIF) was established in January 2000 to investigate innovative nuclear energy system concepts. GIF members include Argentina, Brazil, Canada, Euratom, France Japan, South Africa, South Korea, Switzerland, United Kingdom and United States with the IAEA and OECD's NEA as permanent observers. China and Russia are expected to join the GIF initiative. The following six systems

  16. 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

  17. Empresas brasileiras revelam as informações ambientais? Evidências de declarações financeiras publicadas no ‘New York Securities Exchange’ (NYSE e na Bolsa de Valores de São Paulo (BOVESPA = Do Brazilian Corporations Disclose Environmental Information? Evidences from Financial Statements Published in the New York Securities Exchange (NYSE and in the Bolsa de Valores de São Paulo (BOVESPA

    Directory of Open Access Journals (Sweden)

    José Alonso Borba

    2008-11-01

    Full Text Available O presente estudo, de caráter exploratório-descritivo, tem como objetivo examinar a divulgação de informações ambientais pelas empresas brasileiras, tanto no âmbito nacional(BOVESPA quanto no âmbito norte-americano (NYSE. Para isso, analisaram-se as demonstrações contábeis durante o período de 2002-2004. A amostra do estudo é composta pelas empresas listadas na Bolsa de Valores de Nova York, pertencentes a setores de médio e alto impacto ambiental segundo a Lei 10.165/2000, que trata das Políticas Nacionais de Meio Ambiente. Das três hipóteses inicialmente formuladas, apenas uma se confirmou: as empresas analisadas estão evidenciando um maior volume de informações relacionadas ao meio ambiente. Contudo, percebe-se que existem diferenças entre as informações divulgadas no Brasil e nos Estados Unidos. As empresas analisadas evidenciaram um maior volume de informação no âmbito internacional. Com relação aos passivos ambientais, apenas duas empresas evidenciaram informações específicas. Embora poucas empresas tenham sido analisadas, os resultados levantam questões sobre a credibilidade das informações de caráter ambiental e alertam para a possibilidade de gerenciamento do que é divulgado pelas empresas.This study adopts an exploratory-descriptive approach in order to examine environmentalinformation published by Brazilian corporations. A comparison between the environmentalinformation disclosured in the Brazilian Market (BOVESPA and the United States Market(NYSE was conducted. A content analysis has been carried out in corporate financialstatements for the period of 2002-2004. The sample was composed by Brazilian corporationslisted in the New York Stock Exchange that were members of industries (sectors with highand medium pollution potential according to the Brazilian Law 10.165/2000. Of the threehypotheses initially formulated, only one was confirmed: the amount of environmentalinformation disclosured by

  18. 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)

  19. 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)

  20. 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.

  1. FBR type reactor

    International Nuclear Information System (INIS)

    The present invention provides an FBR type reactor in which the combustion of reactor core fuels is controlled by reflectors, and the position of a reflector driving device can be controlled even during shut down of the reactor. Namely, the reflector driving device is attracted to the outer wall surface of a reactor core barrel by electromagnetic attraction force. An inertia body is disposed vertically movably to the upper portion of the reflector driving device. Magnetic repulsive coils generate instantaneous magnetic repulsive force between the inertia body and the reflector driving device. With such a constitution, the reflector driving device can be driven by using magnetic repulsion of the electromagnetic repulsive coils and inertia of the inertia body. As a result, not only the reflectors can be elevated at an ultraslow speed during normal reactor operation, but also fine position adjustment for the reflector driving device, as well as fine position adjustment of the reflectors required upon restart of the reactor can be conducted by lowering the reflector driving device during shut down of the reactor. (I.S.)

  2. Reactor water sampling device

    International Nuclear Information System (INIS)

    The present invention concerns a reactor water sampling device for sampling reactor water in an in-core monitor (neutron measuring tube) housing in a BWR type reactor. The upper end portion of a drain pipe of the reactor water sampling device is attached detachably to an in-core monitor flange. A push-up rod is inserted in the drain pipe vertically movably. A sampling vessel and a vacuum pump are connected to the lower end of the drain pipe. A vacuum pump is operated to depressurize the inside of the device and move the push-up rod upwardly. Reactor water in the in-core monitor housing flows between the drain pipe and the push-up rod and flows into the sampling vessel. With such a constitution, reactor water in the in-core monitor housing can be sampled rapidly with neither opening the lid of the reactor pressure vessel nor being in contact with air. Accordingly, operator's exposure dose can be reduced. (I.N.)

  3. 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

  4. Advanced reactor licensing issues

    International Nuclear Information System (INIS)

    In July 1986 the US Nuclear Regulatory Commission issued a Policy Statement on the Regulation of Advanced Nuclear Power Plants. As part of this policy advanced reactor designers were encouraged to interact with NRC early in the design process to obtain feedback regarding licensing requirements for advanced reactors. Accordingly, the staff has been interacting with the Department of Energy (DOE) and its contractors on the review of three advanced reactor conceptual designs: one modular High Temperature Gas-Cooled Reactor (MHTGR) and two Liquid Metal Reactors (LMRs). As a result of these interactions certain safety issues associated with these advanced reactor designs have been identified as key to the licensability of the designs as proposed by DOE. The major issues in this regard are: (1) selection and treatment of accident scenarios; (2) selection of siting source term; (3) performance and reliability of reactor shutdown and decay heat removal systems; (4) need for conventional containment; (5) need for conventional emergency evacuation; (6) role of the operator; (7) treatment of balance of plant; and (8) modular approach. This paper provides a status of the NRC review effort, describes the above issues in more detail and provides the current status and approach to the development of licensing guidance on each

  5. Nuclear reactor power monitor

    International Nuclear Information System (INIS)

    The device of the present invention monitors phenomena occurred in a nuclear reactor more accurately than usual case. that is, the device monitors a reactor power by signals sent from a great number of neutron monitors disposed in the reactor. The device has a means for estimating a phenomenon occurred in the reactor based on the relationship of a difference of signals between each of the great number of neutron monitors to the positions of the neutron monitors disposed in the reactor. The estimation of the phenomena is conducted by, for example, conversion of signals sent from the neutron monitors to a code train. Then, a phenomenon is estimated rapidly by matching the code train described above with a code train contained in a data base. Further. signals sent from the neutron monitors are processed statistically to estimate long term and periodical phenomena. As a result, phenomena occurred in the reactor are monitored more accurately than usual case, thereby enabling to improve reactor safety and operationability. (I.S.)

  6. Reactor Sharing Program

    International Nuclear Information System (INIS)

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

  7. Determination of research reactor safety parameters by reactor calculations

    International Nuclear Information System (INIS)

    Main research reactor safety parameters such as power density peaking factors, shutdown margin and temperature reactivity coefficients are treated. Reactor physics explanation of the parameters is given together with their application in safety evaluation performed as part of research reactor operation. Reactor calculations are presented as a method for their determination assuming use of widely available computer codes. (author)

  8. Reactor de plasma

    OpenAIRE

    Erra Serrabasa, Pilar; Molina Mansilla, Ricardo; Beltrán Serra, Eric

    2008-01-01

    Reactor de plasma. Se trata de un reactor de plasma que puede trabajar en un amplio rango de presión, desde el vacío y presiones reducidas hasta la presión atmosférica y presiones superiores. Adicionalmente el reactor de plasma tiene la capacidad de regular otros parámetros importantes y permite su uso para el tratamiento de muestras de tipología muy diversa, como por ejemplo las de tamaño relativamente grande o de superficie rugosa.

  9. Integral nuclear reactor

    International Nuclear Information System (INIS)

    The invention deals with an inprovement of the design of an integral pressurized water nuclear reactor. A typical embodyment of the invention includes a generally cylindrical pressure vessel that is assembled from three segments which are bolted together at transverse joints to form a pressure tight unit that encloses the steam generator and the reactor. The new construction permits primary to secondary coolant heat exchange and improved control rod drive mecanisms which can be exposed for full service access during reactor core refueling, maintenance and inspection

  10. 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.

  11. 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

  12. First Algerian research reactor

    International Nuclear Information System (INIS)

    In 1985, both the Algerian Commissariat of New Energies and the Argentine National Atomic Energy Commission plus the firm INVAP S.E., started a series of mutual visits aimed at defining the mechanisms for cooperation in the nuclear field. Within this framework, a commercial contract was undersigned covering the supply of a low-power reactor (RUN), designed for basic and applied research in the fields of reactor physics and nuclear engineering. The reactor may also be used for performing experiences with neutron beams, for the irradiation of several materials and for the training of technicians, scientists and operators

  13. 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.

  14. 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

  15. Nuclear reactor theory

    International Nuclear Information System (INIS)

    This textbook is composed of two parts. Part 1 'Elements of Nuclear Reactor Theory' is composed of only elements but the main resource for the lecture of nuclear reactor theory, and should be studied as common knowledge. Much space is therefore devoted to the history of nuclear energy production and to nuclear physics, and the material focuses on the principles of energy production in nuclear reactors. However, considering the heavy workload of students, these subjects are presented concisely, allowing students to read quickly through this textbook. (J.P.N.)

  16. 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.)

  17. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the behaviour of fusion reactor materials and components during and after irradiation. Ongoing projects include: the study of the mechanical behaviour of structural materials under neutron irradiation; the investigation of the characteristics of irradiated first wall material such as beryllium; the detection of abrupt electrical degradation of insulating ceramics under high temperature and neutron irradiation; and the study of dismantling and waste disposal strategy for fusion reactors. Progress and achievements in these areas in 2000 are discussed

  18. International tokamak reactor

    International Nuclear Information System (INIS)

    Since 1978, the US, the European Communities, Japan, and the Soviet Union have collaborated on the definition, conceptual design, data base assessment, and analysis of critical technical issues for a tokamak engineering test reactor, called the International Tokamak Reactor (INTOR). During 1985-1986, this activity has been expanded in scope to include evaluation of concept innovations that could significantly improve the tokamak as a commercial reactor. The purposes of this paper are to summarize the present INTOR design concept and to summarize the work on concept innovations

  19. Joyo experimental reactor tour

    International Nuclear Information System (INIS)

    JAEA cooperation in remote monitoring focuses on the Joyo Experimental Reactor at the O'arai Research and Development Center. Joyo performs irradiation of test fuels to support development of the fast reactor cycle in Japan, both in international cooperation and in support of the Monju fast reactor, which is now undergoing reconstruction. The tour included an introduction at the model, a visit to the control room, entry into the containment vessel, and viewing of remote monitoring equipment in the Fresh Fuel Storage and at one of the Spent Fuel Ponds. (author)

  20. 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.

  1. 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

  2. Nuclear reactor internal structures

    International Nuclear Information System (INIS)

    The upper internal structures of the reactor are connected to the closing head so as to be readily removed with the latter and a skirt connected to the lower portion of said upper structures so as to surround the latter, extends under the control rods when they are removed from the reactor core. Through such an arrangement the skirt protects the control rods and supports the vessel closing-head and the core upper structures, whenever the head is severed from the vessel and put beside the latter in order to discharge the reactor

  3. Reactor monitoring system

    International Nuclear Information System (INIS)

    The present invention concerns a device for monitoring the inside of an FBR type reactor which can not be monitored by a usual optical camera. An ultrasonic camera having an excellent propagating property in a liquid metal sodium is scanned, and reflected waves of the ultrasonic waves are received as signals. The signals are processed by using a virtual realistic feeling (VR) technique such as a head mounting type image display (HMD) and a three dimensional pointing device. With such procedures, the inside of the FBR type reactor can be observed with such a realistic feeling that the inside of the FBR type reactor were seen directly. (I.S.)

  4. Research reactor support

    International Nuclear Information System (INIS)

    Research reactors (RRs) have been used in a wide range of applications including nuclear power development, basic physics research, education and training, medical isotope production, geology, industry and other fields. However, many research reactors are fuelled with High Enriched Uranium (HEU), are underutilized and aging, and have significant quantities of spent fuel. HEU inventories (fresh and spent) pose security risks Unavailability of a high-density-reprocessable fuel hinders conversion and limits back-end options and represents a survival dilemma for many RRs. Improvement of interim spent fuel storage is required at some RRs. Many RRs are under-utilized and/or inadequately funded and need to find users for their services, or permanently shut down and eventually decommission. Reluctance to decommission affect both cost and safety (loss of experienced staff ) and many shut down but not decommissioned RR with fresh and/or spent fuel at the sites invoke serious concern. The IAEA's research reactor support helps to ensure that research reactors can be operated efficiently with fuels and targets of lower proliferation and security concern and that operators have appropriate technology and options to manage RR fuel cycle issues, especially on long term interim storage of spent research reactor fuel. Availability of a high-density-reprocessable fuel would expand and improve back end options. The International Atomic Energy Agency provides assistance to Member States to convert research reactors from High Enriched Uranium fuel and targets (for medical isotope production) to qualified Low Enriched Uranium fuel and targets while maintaining reactor performance levels. The assistance includes provision of handbooks and training in the performance of core conversion studies, advice for the procurement of LEU fuel, and expert services for LEU fuel acceptance. The IAEA further provides technical and administrative support for countries considering repatriation of its

  5. Study of power reactor dynamics by stochastic reactor oscillator method

    International Nuclear Information System (INIS)

    Stochastic reactor oscillator and cross correlation method were used for determining reactor dynamics characteristics. Experimental equipment, fast reactor oscillator (BOR-1) was activated by random pulses from the GBS-16 generator. Tape recorder AMPEX-SF-300 and data acquisition tool registered reactor response to perturbations having different frequencies. Reactor response and activation signals were cross correlated by digital computer for different positions of stochastic oscillator and ionization chamber

  6. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    An improved nuclear power reactor fuel element is described which consists of fuel rods, rod guide tubes and an end plate. The system allows direct access to an end of each fuel rod for inspection purposes. (U.K.)

  7. Reactor power control device

    International Nuclear Information System (INIS)

    The present invention concerns a method of controlling reactor power to shift it into a partial power operation upon occurrence of recycling pump tripping or loss of generator load. Operation state of a reactor is classified into a plurality of operation states based on values of the reactor core flow rate and the reactor power. Different insertion patterns for selected control rods are determined on every classified operation states. Then, an insertion pattern corresponding to the operation state upon occurrence of recycling pump tripping or loss of power generator load is carried out to shift into partial power operation. The operation is shifted to a load operation solely in the station while avoiding risks such as TPM scram. Then neutron fluxes are suppressed upon transient to increase margin of fuel integrity. Selected control rod pattern of the optimum reactivity is set to each of operation regions, thereby enabling to conduct flexible countermeasure so as to attain optimum operationability. (N.H.)

  8. 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

  9. 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.

  10. 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.

  11. Reactor parameter simulation system

    International Nuclear Information System (INIS)

    A reactor parameter simulation system (RPSS) has been built with the capability of analyzing any reactor signals, decomposing those signals into their deterministic and stochastic components, then reconstructing new, simulated signals that possess the same statistical and correlation structure as the original plant variables. Important uses of the RPSS are for integration with reactor simulation software to provide tools for plant control strategy development, and for safety-study investigations of scenarios that can arise involving signal faults generated from degraded sensors. A third use of the RPSS is for frequency-domain filtering of reactor process variables contaminated with serially correlated noise, which is important for our ongoing development of expert systems for sensor-operability surveillance. 5 refs., 4 figs., 3 tabs

  12. 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.

  13. 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).

  14. Nuclear reactor fuel assembly

    International Nuclear Information System (INIS)

    A fuel assembly construction for liquid metal cooled fast breeder reactors is described in which the sub-assemblies carry a smaller proportion of parasitic material than do conventional sub-assemblies. (U.K.)

  15. Ageing of research reactors

    International Nuclear Information System (INIS)

    Historically, many of the research institutions were centred on a research reactor facility as main technological asset and major source of neutrons for research. Important achievements were made in time in these research institutions for development of nuclear materials technology and nuclear safety for nuclear energy. At present, ageing of nuclear research facilities among these research reactors and ageing of staff are considerable factors of reduction of competence in research centres. The safe way of mitigation of this trend deals with ageing management by so called, for power reactors, Plant Life Management and new investments in staff as investments in research, or in future resources of competence. A programmatic approach of ageing of research reactors in correlation with their actual and future utilisation, will be used as a basis for safety evaluation and future spending. (author)

  16. 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)

  17. Dossier: research reactors

    International Nuclear Information System (INIS)

    Research reactors are used at the CEA (the French atomic energy commission) since many years. Their number has been reduced but they remain unique tools that CEA valorize continuously. The results of the programs involving such reactors are of prime importance for the operation of Electricite de France (EdF) park of existing power plants but also for the design of future nuclear power plants and future research reactors. This dossier presents three examples of research reactors in use at the CEA: Osiris and Orphee (CEA-Saclay), devoted to nuclear energy and fundamental research, respectively, and the critical mockups Eole, Minerve and Masurca (CEA-Cadarache) devoted to nuclear data libraries and neutronic calculation. (J.S.)

  18. Reactor vessel sealing plug

    International Nuclear Information System (INIS)

    This invention relates to an apparatus and method for sealing the cold leg nozzles of a nuclear reactor pressure vessel from a remote location during maintenance and inspection of associated steam generators and pumps while the pressure vessel and refueling canal are filled with water. The apparatus includes a sealing plug for mechanically sealing the cold leg nozzle from the inside of a reactor pressure vessel. The sealing plugs include a primary and a secondary O-ring. An installation tool is suspended within the reactor vessel and carries the sealing plug. The tool telescopes to insert the sealing plug within the cold leg nozzle, and to subsequently remove the plug. Hydraulic means are used to activate the sealing plug, and support means serve to suspend the installation tool within the reactor vessel during installation and removal of the sealing plug

  19. Future Reactor Experiments

    CERN Document Server

    He, Miao

    2013-01-01

    The measurement of the neutrino mixing angle $\\theta_{13}$ opens a gateway for the next generation experiments to measure the neutrino mass hierarchy and the leptonic CP-violating phase. Future reactor experiments will focus on mass hierarchy determination and the precision measurement of mixing parameters. Mass hierarchy can be determined from the disappearance of reactor electron antineutrinos based on the interference effect of two separated oscillation modes. Relative and absolute measurement techniques have been explored. A proposed experiment JUNO, with a 20 kton liquid scintillator detector of $3%/$$\\sqrt{E(MeV)}$ energy resolution, $\\sim$ 53 km far from reactors of $\\sim$ 36 GW total thermal power, can reach to a sensitivity of $\\Delta\\chi^{2}>16$ considering the spread of reactor cores and uncertainties of the detector response. Three of mixing parameters are expected to be measured to better than 1% precision. There are multiple detector options for JUNO under investigation. The technical challenges...

  20. Reactor hot spot analysis

    Energy Technology Data Exchange (ETDEWEB)

    Vilim, R.B.

    1985-08-01

    The principle methods for performing reactor hot spot analysis are reviewed and examined for potential use in the Applied Physics Division. The semistatistical horizontal method is recommended for future work and is now available as an option in the SE2-ANL core thermal hydraulic code. The semistatistical horizontal method is applied to a small LMR to illustrate the calculation of cladding midwall and fuel centerline hot spot temperatures. The example includes a listing of uncertainties, estimates for their magnitudes, computation of hot spot subfactor values and calculation of two sigma temperatures. A review of the uncertainties that affect liquid metal fast reactors is also presented. It was found that hot spot subfactor magnitudes are strongly dependent on the reactor design and therefore reactor specific details must be carefully studied. 13 refs., 1 fig., 5 tabs.

  1. 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

  2. Research Reactor Benchmarks

    International Nuclear Information System (INIS)

    A criticality benchmark experiment performed at the Jozef Stefan Institute TRIGA Mark II research reactor is described. This experiment and its evaluation are given as examples of benchmark experiments at research reactors. For this reason the differences and possible problems compared to other benchmark experiments are particularly emphasized. General guidelines for performing criticality benchmarks in research reactors are given. The criticality benchmark experiment was performed in a normal operating reactor core using commercially available fresh 20% enriched fuel elements containing 12 wt% uranium in uranium-zirconium hydride fuel material. Experimental conditions to minimize experimental errors and to enhance computer modeling accuracy are described. Uncertainties in multiplication factor due to fuel composition and geometry data are analyzed by sensitivity analysis. The simplifications in the benchmark model compared to the actual geometry are evaluated. Sample benchmark calculations with the MCNP and KENO Monte Carlo codes are given

  3. Nuclear reactor (1960)

    International Nuclear Information System (INIS)

    The first French plutonium-making reactors G1, G2 and G3 built at Marcoule research center are linked to a power plant. The G1 electrical output does not offset the energy needed for operating this reactor. On the contrary, reactors G2 and G3 will each generate a net power of 25 to 30 MW, which will go into the EDF grid. This power is relatively small, but the information obtained from operation is great and will be helpful for starting up the power reactor EDF1, EDF2 and EDF3. The paper describes how, previous to any starting-up operation, the tests performed, especially those concerned with the power plant and the pressure vessel, have helped to bring the commissioning date closer. (author)

  4. 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.

  5. 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

  6. Reactor fueling of BWR type reactors

    International Nuclear Information System (INIS)

    Purpose: To enable the pattern exchange for control rods during burning in Control Cell Core type BWR reactors. Constitution: A plurality of control cells are divided into a plurality of groups such that the control cells is aparted from each other by way of at least two fuel assemblies other than the control cells with respect to the vertical and lateral directions of the reactor core cross section, as well as they are in adjacent with control cells of other groups with respect to the orthogonal direction. This enables to perform the pattern exchange for the control rods during burning in the control cell core with ease, and the control blade and the story effect harmful to the mechanical soundness of fuels can thus be suppressed. (Moriyama, K.)

  7. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in fiscal 1974 in Reactor Engineering Division of eight laboratories and computing center are described. Works in the division are closely related with the development of a multi-purpose High-temperature Gas Cooled Reactor, the development of a Liquid Metal Fast Breeder Reactor in Power Reactor and Nuclear Fuel Development Corporation, and engineering of thermonuclear fusion reactors. They cover 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 aspects of the computing center. (auth.)

  8. 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.

  9. The replacement research reactor

    International Nuclear Information System (INIS)

    The contract for the design, construction and commissioning of the Replacement Research Reactor was signed in July 2000. This was followed by the completion of the detailed design and an application for a construction licence was made in May 2001. This paper will describe the main elements of the design and their relation to the proposed applications of the reactor. The future stages in the project leading to full operation are also described

  10. 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

  11. 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)

  12. Small reactor return

    International Nuclear Information System (INIS)

    Current state of the development of present-day small reactors in different countries is performed. Various designs of low and middle power reactors, among which are CAREM (25 MW, PWR), KLT-40 (40 MW, PWR), MRX (30 MW, PWR), IRIS (50 MW, PWR), SMART (1000 MW, PWR), Modular SBWR (50 MW, BWR), PBMR (120 MW, HTGR), GT-HMR (285 MW, HTGR), are discussed

  13. Reactor lattice transport calculations

    International Nuclear Information System (INIS)

    The present lecture is a continuation of the lecture on Introduction to the Neutron Transport Phenomena. It comprises three aspects of lattice calculations. First the idea of a reactor lattice is introduced. Then the main definitions used in reactor lattice analysis are given, and finally two basic methods applied for solution of the transport equations are defined. Several remarks on secondary results from lattice transport calculations are added. (author)

  14. Thermal or epithermal reactor

    International Nuclear Information System (INIS)

    In a thermal or epithermal heavy-water reactor of the pressure tube design the reactivity is to be increased by different means: replacement of the moderator by additional rods with heavy metal in the core or in the reflector; separation of the moderator (heavy water) from the coolant (light water) by means of shroud tubes. In light-water reactor types neutron losses are to be influenced by using the heavy elements in different configurations. (orig./PW)

  15. Future reactor experiments

    International Nuclear Information System (INIS)

    The non-zero neutrino mixing angle θ13 has been discovered and precisely measured by the current generation short-baseline reactor neutrino experiments. It opens the gate of measuring the leptonic CP-violating phase and enables the neutrino mass ordering. The JUNO and RENO-50 proposals aim at resolving the neutrino mass ordering using reactors. The experiment design, physics sensitivity, technical challenges as well as the progresses of those two proposed experiments are reviewed in this paper

  16. Water cooled nuclear reactor

    International Nuclear Information System (INIS)

    The description is given of a water cooled nuclear reactor comprising a core, cooling water that rises through the core, vertical guide tubes located inside the core and control rods vertically mobile in the guide tubes. In this reactor the cooling water is divided into a first part introduced at the bottom end of the core and rising through it and a second part introduced at the top end of the guide tubes so as to drop in them

  17. 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...

  18. 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.)

  19. Future reactor experiments

    Science.gov (United States)

    Wen, Liangjian

    2015-07-01

    The non-zero neutrino mixing angle θ13 has been discovered and precisely measured by the current generation short-baseline reactor neutrino experiments. It opens the gate of measuring the leptonic CP-violating phase and enables the neutrino mass ordering. The JUNO and RENO-50 proposals aim at resolving the neutrino mass ordering using reactors. The experiment design, physics sensitivity, technical challenges as well as the progresses of those two proposed experiments are reviewed in this paper.

  20. 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....

  1. AVR reactor physics

    International Nuclear Information System (INIS)

    A process for reactivity control was developed and used for fuelling the AVR reactor core, which is largely based on experimentally determined values. By adding fuel elements with different quantities of heavy metals paired with various experimental requirements, great demands were made of reactivity control. Although only a small range of control was available, this was sufficient to operate the reactor and to shut it down safely in the required power and temperature range. (orig.)

  2. 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.

  3. 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.)

  4. Emergency reactor scram system

    International Nuclear Information System (INIS)

    The present invention provides an emergency reactor scram system capable of shut down a reactor safely upon occurrence of pump trip by improving a passive scram performance for an FBR-type reactor. Namely, a driving motor and an electric generator are connected to a main pump of a primary system. An AC/DC convertor is connected to the electric generator. A shielding plug is disposed to the upper end opening of a reactor container, a control rod drive mechanism is erected on the shielding plug, and an extension pipe is attached to scram magnets of the control rod drive mechanism. The extension pipe is connected to a control rod. The rotation of the shaft of the pump is used as a direct rotator to provide an integrated-type electric generator. The electric generator is electrically connected with the power source of a scram magnet of the emergency scram system. Accordingly, the control rod of the emergency scram system is automatically and rapidly inserted to the reactor core using the power source of the electric generator upon trip of the main pump thereby enabling to scram the reactor safely. (I.S.)

  5. A modular reactor plant

    International Nuclear Information System (INIS)

    This paper describes a new concept in liquid metal reactors that is being developed by General Electric under contract to the Department of Energy. This concept is called the Modular Reactor Plant. While this effort is not expected to have a near-term impact, it is directed toward three principal issues currently affecting nuclear power in the United States. First, plant costs have escalated to the point where the startup of new plants require large electric rate increases. Second, the cost of new plants coming on-line today vary by as much as a factor of three. And, third, nuclear construction times often exceed the utilities prudent planning cycle. This paper describes how General Electric's Modular Reactor Plant addreses these issues through shop fabrication and assembly, rail shipment to the site for rapid installation of nuclear components and inherent reactor protection. In addition, it is expected the modular reactor plant will reduce the current cost of development and demonstration of liquid metal reactors to an affordable level

  6. New fission reactor designs

    International Nuclear Information System (INIS)

    A number of critical challenges to the expanded or continued use of nuclear power have developed. These can be categorized as: regulatory restrictions and complications; negative public attitudes; plant complexity; plant life, operations, and maintenance; uncertain load growth, financing; waste management. Solutions to these challenges through advanced reactor design centre around four key technical responses. Passive safety systems are being introduced which use the laws of physics to provide emergency reactor coding, control and shutdown thus eliminating the possibility of human error. Modular construction promises cuts in costs and construction time by shifting the major part of component manufacture from the site to the factory. Standardization also cuts capital costs and in addition operations and repair costs and expedites reactor licensing. Improvements to the fuel cycle include improved fuel types, designs and fabrication, and the reprocessing of and recycling spent fuel back into energy production, thus extending uranium resources and offering a partial solution to the problem of waste disposal. Examples of evolutionary and advanced water-cooled reactors, modular high temperature gas-cooled reactors, and advanced liquid metal cooled fast breeder reactors which are being developed round the world are presented. (author)

  7. 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

  8. Reactor power measuring device

    International Nuclear Information System (INIS)

    The device of the present invention efficiently calibrates a fixed type gamma ray thermometer of a reactor power measuring device of a BWR type reactor. Namely, the device of the present invention calculates peripheral fuel rod power distribution by calibrating the reactor power distribution by heat generation amount, the reactor power distribution being obtained by a calculation based on a reactor model for converting the signals of a plurality of the gamma ray thermometers in the reactor core based on a conversion formula. In this case, the conversion formula is a relational formula between the power of a thermocouple of the gamma ray thermometer, gamma ray heat generation amount, thermocouple zero power sensitivity relative to a temperature coefficient. A conversion efficient calculation means makes a calibration heater to generate heat at a predetermined power, and the thermocouple zero power sensitivity and the temperature coefficient are obtained based on the output of the gamma ray thermometer in this case. The calibration means updates to conversion type thermocouple zero power sensitivity and temperature coefficient. A calibration execution means executes the operations described above successively, and when the thermocouple zero power sensitivity and the temperature coefficient are out of an allowable range, the means informs it and eliminates the corresponding gamma ray thermometer from the measuring meters. (I.S.)

  9. Reactor safety engineering

    International Nuclear Information System (INIS)

    The concept of the work is such that the basic safety philosophy for nuclear power plants as well as the safety features of both types of light water reactors, pressurized and boiling water reactors, and of the fast breeder reactor are dealt with. With the pressurized and boiling water reactors also variations, due to different supplies are mentioned. The state of development considered is characterized by the results of the American reactor safety study having very much influenced the way of presentation and the validity of the information contained. In the introduction the attentive reader is made familiar with the basic traits of safety engineering, the traditional deterministic way of proceeding being supplemented by a detailed illustration of probabilistic means used in the safety analysis. Added to this are comparative descriptions of the individual safety features, their design and mode of operation. There are, e.g., detailed discussion of the emergency core cooling systems, the power supply systems, the reactor protection system, and the containment. Special chapters are attributed to transients with and without the fast shutdown system working and to loss of coolant. The so-called external events are treated somewhat shortly whereas much space is given to core melting problems. The treatment of important events from the safety point of view, including the section on Harrisburg added for reasons of immediate interest, is limited to phenomenological description. (orig.)

  10. Regulations for RA reactor operation

    International Nuclear Information System (INIS)

    Regulations for RA reactor operation are written in accordance with the legal regulations defined by the Law about radiation protection and related legal acts, as well as technical standards according to the IAEA recommendations. The contents of this book include: fundamental data about the reactor; legal regulations for reactor operation; organizational scheme for reactor operation; general and detailed instructions for operation, behaviour in the reactor building, performing experiments; operating rules for operation under steady state and accidental conditions

  11. The reactor Cabri

    International Nuclear Information System (INIS)

    It has become necessary to construct in France a reactor which would permit the investigation of the conditions of functioning of future installations, the choice, the testing and the development of safety devices to be adopted. A water reactor of a type corresponding to the latest CEA constructions in the field of laboratory or university reactors was decided upon: it appeared important to be able to evaluate the risks entailed and to study the possibilities of increasing the power, always demanded by the users; on the other hand, it is particularly interesting to clarify the phenomena of power oscillation and the risks of burn out. The work programme for CABRI will be associated with the work carried out on the American Sperts of the same type, during its construction, very useful contacts were made with the American specialists who designed the se reactors. A brief description of the reactor is given in the communication as well as the work programme for the first years with respect to the objectives up to now envisaged. Rough description of the reactor. CABRI is an open core swimming-pool reactor without any lateral protection, housed in a reinforced building with controlled leakage, in the Centre d'Etudes Nucleaires de Cadarache. It lies alone in the middle of an area whose radius is 300 meters long. Control and measurements equipment stand out on the edge of that zone. It consumes MTR fuel elements. The control-safety rods are propelled by compressed air. The maximum flow rate of cooling circuit is 1500 m3/h. Transient measurements are recorded in a RW330 unit. Aims and work programme. CABRI is meant for: - studies on the safety of water reactors - for the definition of the safety margins under working conditions: research of maximum power at which a swimming-pool reactor may operate with respect to a cooling accident, of local boiling effect on the nuclear behaviour of the reactor, performances of the control and safety instruments under exceptional

  12. REACTOR GROUT THERMAL PROPERTIES

    Energy Technology Data Exchange (ETDEWEB)

    Steimke, J.; Qureshi, Z.; Restivo, M.; Guerrero, H.

    2011-01-28

    Savannah River Site has five dormant nuclear production reactors. Long term disposition will require filling some reactor buildings with grout up to ground level. Portland cement based grout will be used to fill the buildings with the exception of some reactor tanks. Some reactor tanks contain significant quantities of aluminum which could react with Portland cement based grout to form hydrogen. Hydrogen production is a safety concern and gas generation could also compromise the structural integrity of the grout pour. Therefore, it was necessary to develop a non-Portland cement grout to fill reactors that contain significant quantities of aluminum. Grouts generate heat when they set, so the potential exists for large temperature increases in a large pour, which could compromise the integrity of the pour. The primary purpose of the testing reported here was to measure heat of hydration, specific heat, thermal conductivity and density of various reactor grouts under consideration so that these properties could be used to model transient heat transfer for different pouring strategies. A secondary purpose was to make qualitative judgments of grout pourability and hardened strength. Some reactor grout formulations were unacceptable because they generated too much heat, or started setting too fast, or required too long to harden or were too weak. The formulation called 102H had the best combination of characteristics. It is a Calcium Alumino-Sulfate grout that contains Ciment Fondu (calcium aluminate cement), Plaster of Paris (calcium sulfate hemihydrate), sand, Class F fly ash, boric acid and small quantities of additives. This composition afforded about ten hours of working time. Heat release began at 12 hours and was complete by 24 hours. The adiabatic temperature rise was 54 C which was within specification. The final product was hard and displayed no visible segregation. The density and maximum particle size were within specification.

  13. Materials for nuclear reactors

    International Nuclear Information System (INIS)

    The improved performance of present generation nuclear reactors and the realization of advanced reactor concepts, both, require development of better materials. Physical metallurgy/materials science principles which have been exploited in meeting the exacting requirements of nuclear reactor materials (fuels and structural materials), are outlined citing a few specific examples. While the incentive for improvement of traditional fuels (e.g., UO2 fuel) is primarily for increasing the average core burn up, the development of advanced fuels (e.g., MOX, mixed carbide, nitride, silicide and dispersion fuels) are directed towards better utilization of fissile and fertile inventories through adaptation of innovative fuel cycles. As the burn up of UO2 fuel reaches higher levels, a more detailed and quantitative understanding of the phenomena such as fission gas release, fuel restructuring induced by radiation and thermal gradients and pellet-clad interaction is being achieved. Development of zirconium based alloys for both cladding and pressure tube applications is discussed with reference to their physical metallurgy, fabrication techniques and in-reactor degradation mechanisms. The issue of radiation embrittlement of reactor pressure vessels (RPVs) is covered drawing a comparison between the western and eastern specifications of RPV steels. The search for new materials which can stand higher rates of atomic displacement due to radiation has led to the development of swelling resistant austenitic and ferritic stainless steels for fast reactor applications as exemplified by the development of the D-9 steel for Indian fast breeder reactor. The presentation will conclude by listing various materials related phenomena, which have a strong bearing on the successful development of future nuclear energy systems. (author)

  14. 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

  15. 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.

  16. 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

  17. 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

  18. 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.)

  19. HTGR type reactor

    International Nuclear Information System (INIS)

    A reactor core is disposed at the center of a reactor container, a reflector is disposed on the outer side thereof, a steam generator is disposed further outer side thereof coaxially, and they are constituted as an integrated one container. A gas circulator and control rod drives are protruded at the outer side of the lower portion of the integrated container. Heat insulators are disposed on the inner side of the container wall in the upper portion of the reactor container. Helium gas risen in the reactor core and heated to a high temperature descends in a circular steam generator and undergoes heat exchange with water, and is then pressurized in the gas circulator after the lowering of the temperature, and returned to the inlet of the reactor core from the lower central portion of the container. With such procedures, the helium gas as primary coolants circulates only in the container to improve confinement. The device can be reduced in the size and the cost. (I.N.)

  20. Reactor container spray device

    International Nuclear Information System (INIS)

    Purpose: To enable decrease in the heat and the concentration of radioactive iodine released from the reactor vessel into the reactor container in the spray device of BWR type reactors. Constitution: A plurality of water receiving trays are disposed below the spray nozzle in the dry well and communicated to a pressure suppression chamber by way of drain pipeways passing through a diaphragm floor. When the recycling system is ruptured and coolants in the reactor vessel and radioactive iodine in the reactor core are released into the dry well, spray water is discharged from the spray nozzle to eliminate the heat and the radioactive iodine in the dry well. In this case, the receiving trays collect the portions of spray water whose absorption power for the heat and radioactive iodine is nearly saturated and falls them into the pool water of the pressure suppression chamber. Consequently, other portions of the spray water that still possess absorption power can be jetted with no hindrance, to increase the efficiency for the removal of the heat and iodine of the spray droplets. (Horiuchi, T.)

  1. PROTEUS research reactor

    International Nuclear Information System (INIS)

    The PROTEUS zero power reactor at the Paul Scherrer Institute (PSI) in Switzerland achieved first criticality in 1968 and since then has been operated as an experimental tool for reactor physics research on test lattices representative of a wide range of reactor concepts. Reactor design codes and their associated data libraries are validated on the basis of the experimental results obtained. PROTEUS is normally configured as a driven system, in which a subcritical test zone is made critical by the surrounding driver zones. The advantages of driven systems can be summarized as follows: - Smaller amount of test fuel is required; - Large range of test zone conditions (including k∞ < 1 states) can be investigated by changes in the driver loading alone, thus avoiding undesirable perturbations to the test zone which would influence the measurement conditions and thus affect the interpretability of the results; - Necessary reactor control and instrumentation equipment (usually perturbing from the experimental viewpoint) can be located in the outer driver regions, thereby avoiding disturbance of the test lattice

  2. 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)

  3. China experimental fast reactor

    International Nuclear Information System (INIS)

    The Chinese experimental fast reactor (CEFR) is a pool-type sodium-cooled fast reactor whose short term purposes are: -) the validation of computer codes, -) the check of the relevance of standards, and -) the gathering of experimental data on fast reactors. On the long term the expectations will focus on: -) gaining experience in fast reactor operations, -) the testing of nuclear fuels and materials, and -) the study of sodium compounds. The main technical features of CEFR are: -) thermal power output: 65 MW (electrical power output: 20 MW), -) size of the core: height: 45 cm, diameter: 60 cm, -) maximal linear output: 430 W/cm, -) neutron flux: 3.7*1015 n/cm2/s, -) input/output sodium temperature: 360 / 530 Celsius degrees, -) 2 loops for the primary system and 2 loops for the secondary system. The temperature coefficient and the power coefficient are settled to stay negative for any change in the values of the core parameters. The installation of the reactor vessel will be completed by mid 2007. The first criticality of CEFR is expected during the first semester of 2010. (A.C.)

  4. 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

  5. Modern research reactors in the world and RA research reactor

    International Nuclear Information System (INIS)

    This paper covers the following topics: fundamentals of research reactors, thermal neutron flux density, classification of research reactors in the world, properties of research reactors of higher power in the world according to IAEA data for 1995, their application, and trend of development, experimental feasibility and status of RA reactor. Trend of research reactors development in the world (after 1980) is directed towards increasing the neutron production quality factor, i.e. ratio between thermal neutron flux density and reactor power, which is achieved by designing compact reactor cores. With the aim of renewal of RA reactor (without analysis of reactor components and staff aging, possibility of restart and commercialization), according to the analysis in this paper, it can be concluded: there is very few reactors under construction in the world, all the important countries in Europe have research reactors; RA reactor is not very interesting for development of reactor physics; nowadays RA reactor is in the group of reactors which are 30-40 years old; its inventories of fuel and heavy water are enough for about 20 years of operation; it has achieved high quality factor of neutron production with low and highly enriched fuel; core transfer from low highly enriched to low enriched fuel should be carefully studies from operation, experimental and economical point of view; it is necessary to use the advantages of RA reactor (minimum investment): volume of the core and reflector which enables availability of neutron flux for the users (numerous experimental loops), fuel in shape of slugs enabling efficient fuel management and flexible neutron flux distribution in the core in the reflector, reactor operation should be directed towards commercial applications. Bibliography of more than 140 relevant papers used is included in this paper

  6. Sodium-cooled nuclear reactors

    International Nuclear Information System (INIS)

    This book first explains the choice of sodium-cooled reactors by outlining the reasons of the choice of fast neutron reactors (fast neutrons instead of thermal neutrons, recycling opportunity for plutonium, full use of natural uranium, nuclear waste optimization, flexibility of fast neutron reactors in nuclear material management, fast neutron reactors as complements of water-cooled reactors), and by outlining the reasons for the choice of sodium as heat-transfer material. Physical, chemical, and neutron properties of sodium are presented. The second part of the book first presents the main design principles for sodium-cooled fast neutron reactors and their core. The third part proposes an historical overview and an assessment of previously operated sodium-cooled fast neutron reactors (French reactors from Rapsodie to Superphenix, other reactors in the world), and an assessment of the main incidents which occurred in these reactors. It also reports the experience and lessons learned from the dismantling of various sodium-cooled fast breeder reactors in the world. The next chapter addresses safety issues (technical and safety aspects related to the use of sodium) and environmental issues (dosimetry, gaseous and liquid releases, solid wastes, and cooling water). Then, various technological aspects of these reactors are addressed: the energy conversion system, main components, sodium chemistry, sodium-related technology, advances in in-service inspection, materials used in reactors and their behaviour, and fuel system. The next chapter addresses the fuel cycle in these reactors: its integrated specific character, report of the French experience in fast neutron reactor fuel processing, description of the transmutation of minor actinides in these reactors. The last chapter proposes an overview of reactors currently projected or under construction in the world, presents the Astrid project, and gives an assessment of the economy of these reactors. A glossary and an index

  7. 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...

  8. 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.

  9. 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

  10. 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)

  11. RB research reactor Safety Report

    International Nuclear Information System (INIS)

    This RB reactor safety report is a revised and improved version of the Safety report written in 1962. It contains descriptions of: reactor building, reactor hall, control room, laboratories, reactor components, reactor control system, heavy water loop, neutron source, safety system, dosimetry system, alarm system, neutron converter, experimental channels. Safety aspects of the reactor operation include analyses of accident causes, errors during operation, measures for preventing uncontrolled activity changes, analysis of the maximum possible accident in case of different core configurations with natural uranium, slightly and highly enriched fuel; influence of possible seismic events

  12. 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

  13. Chernobyl reactor accident

    International Nuclear Information System (INIS)

    On April 26, 1986, an explosion occurred at the newest of four operating nuclear reactors at the Chernobyl site in the USSR. The accident initiated an international technical exchange of almost unprecedented magnitude; this exchange was climaxed with a meeting at the International Atomic Energy Agency in Vienna during the week of August 25, 1986. The meeting was attended by more than 540 official representatives from 51 countries and 20 international organizations. Information gleaned from that technical exchange is presented in this report. A description of the Chernobyl reactor, which differs significantly from commercial US reactors, is presented, the accident scenario advanced by the Russian delegation is discussed, and observations that have been made concerning fission product release are described

  14. 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

  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. 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

  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. 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. Colliding Beam Fusion Reactors

    Science.gov (United States)

    Rostoker, Norman; Qerushi, Artan; Binderbauer, Michl

    2003-06-01

    The recirculating power for virtually all types of fusion reactors has previously been calculated [1] with the Fokker-Planck equation. The reactors involve non-Maxwellian plasmas. The calculations are generic in that they do not relate to specific confinement devices. In all cases except for a Tokamak with D-T fuel the recirculating power was found to exceed the fusion power by a large factor. In this paper we criticize the generality claimed for this calculation. The ratio of circulating power to fusion power is calculated for the Colliding Beam Reactor with fuels D-T, D-He3 and p-B11. The results are respectively, 0.070, 0.141 and 0.493.

  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. 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)

  1. 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

  2. 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.

  3. Reactor accidents in perspective

    International Nuclear Information System (INIS)

    In each of the three major reactor accidents which have led to significant releases to the environment, and discussed in outline in this note, the reactor has been essentially destroyed - certainly Windscale and Chernobyl reactors will never operate and the cleanup operation for Three Mile Island is currently estimated to have cost in excess of US Pound 500 000 000. In each of the accidents there has not been any fatality off site in the short term and any long-term health detriment is unlikely to be seen in comparison with the natural cancer incidence rate. At Chernobyl, early fatalities did occur amongst those concerned with fighting the incident on site and late effects are to be expected. The assumption of a linear non-threshold risk, and hence no level of zero risk is the main problem in communication with the public, and the author calls for simplification of the presentation of the concepts of radiological protection. (U.K.)

  4. 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.)

  5. 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

  6. Reactor protection system

    International Nuclear Information System (INIS)

    The report describes the reactor protection system (RPS-II) designed for use on Babcock and Wilcox 145-, later 177-, and 205-fuel assembly pressurized water reactors. In this system, relays in the trip logic have been replaced by solid state devices. A calculating module for the low DNBR, pump status, and offset trip functions has replaced the overpower trip (based on flow and imbalance), the power/RC pump trip, and the variable low-pressure trip. Included is a description of the changes from the present Oconee-type reactor protection system (RPS-I), a functional and hardware description of the calculating module, a description of the software programmed in the calculating module, and a discussion of the qualification program conducted to ensure that the degree of protection provided by RPS-II is not less than that provided by previously licensed systems supplied by B and W

  7. 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)

  8. MERCHANT MARINE SHIP REACTOR

    Science.gov (United States)

    Mumm, J.F.; North, D.C. Jr.; Rock, H.R.; Geston, D.K.

    1961-05-01

    A nuclear reactor is described for use in a merchant marine ship. The reactor is of pressurized light water cooled and moderated design in which three passes of the water through the core in successive regions of low, intermediate, and high heat generation and downflow in a fuel region are made. The foregoing design makes a compact reactor construction with extended core life. The core has an egg-crate lattice containing the fuel elements confined between a lower flow baffle and upper grid plate, with the latter serving also as part of a turn- around manifold from which the entire coolant is distributed into the outer fuel elements for the second pass through the core. The inner fuel elements are cooled in the third pass.

  9. 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)

  10. Study of future reactors

    International Nuclear Information System (INIS)

    Today, more than 420 large reactors with a gross output of close to 350 GWe supply 20 percent of world electricity needs, accounting for less than 5 percent of primary energy consumption. These figures are not expected to change in the near future, due to suspended reactor construction in many countries. Nevertheless, world energy needs continue to grow: the planet's population already exceeds five billion and is forecast to reach ten billion by the middle of the next century. Most less developed countries have a very low rate of energy consumption and, even though some savings can be made in industrialized countries, it will become increasingly difficult to satisfy needs using fossil fuels only. Furthermore, there has been no recent breakthrough in the energy landscape. The physical feasibility of the other great hope of nuclear energy, fusion, has yet to be proved; once this has been done, it will be necessary to solve technological problems and to assess economic viability. Although it is more ever necessary to pursue fusion programs, there is little likelihood of industrial applications being achieved in the coming decades. Coal and fission are the only ways to produce massive amounts of energy for the next century. Coal must overcome the pollution problems inherent in its use; fission nuclear power has to gain better public acceptance, which is obviously colored by safety and waste concerns. Most existing reactors were commissioned in the 1970s; reactor lifetime is a parameter that has not been clearly established. It will certainly be possible to refurbish some to extend their operation beyond the initial target of 30 or 40 years. But normal advances in technology and safety requirements will make the operation of the oldest reactors increasingly difficult. It becomes necessary to develop new generations of nuclear reactors, both to replace older ones and to revive plant construction in their countries that are not yet equipped or that have halted their

  11. 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)

  12. Operating US power reactors

    International Nuclear Information System (INIS)

    This update, which appears regularly in each issue of Nuclear Safety, surveys the operations of those power reactors in the US which have been issued operating licenses. Table 1 shows the number of such reactors and their net capacities as of Dec. 31, 1986, the end of the three-month period covered in this report. Table 2 lists the unit capacity and forced outage rate for each licensed reactor for each of the three months (October, November, and December 1986) covered in this report and the cumulative values of these parameters since the beginning of commercial operation. They are defined as follows: In addition to the tabular data, this article discusses significant occurrences and developments that affected licensed US power reactors during this reporting period. It includes, but is not limited to, changes in operating status, regulatory actions and decisions, and legal actions involving the status of power reactors. We do not have space here for routine problems of operation and maintenance, but such information is available at the Nuclear Regulatory Commission (NRC) Public Document Room, 1717 H Street, NW, Washington, DC 20555. Some significant operating events are summarized elsewhere in this section in the article ''Selected Safety-Related Events,'' and a report on activities relating to facilities still in the construction process is given in the article ''Status of Power-Reactor Projects Undergoing Licensing Review'' in the last section of each issue of this journal. The reader's attention is also called to the regular feature ''General Administrative Activities,'' which deals with more general aspects of regulatory and legal matters that are not covered elsewhere in the journal

  13. 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.

  14. 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)

  15. Experimental reactor physics

    International Nuclear Information System (INIS)

    Neutronic experiments in moderators, subcritical assemblies, critical assemblies, and nuclear reactors are described, as well as the techniques of radiation measurements necessary to perform these experiments. Previously dispersed data from government reports, journal articles, and specialized monographs are codified. Original information drawn from the author's experience is included, especially on the pulsed source technique, spectrum measurements, research reactors, and exponential assemblies. The book provides the essential information for carrying out, analyzing, and understanding the experiments. Theory is kept to a minimum. Emphasis is placed on the physics of the situation, and the importance of estimating error as well as the mean value of a measured quantity

  16. 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.

  17. 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

  18. Clinch River Breeder Reactor

    International Nuclear Information System (INIS)

    Mr. Baron says the administration's effort to terminate the Clinch River Breeder Reactor (CRBR) project is symptomatic; they have also placed restrictions on fusion, coal, solar, and other areas of energy development in which technological advances are held back in order to force conservation. Because the breeder reactor, unlike solar and fusion energy, is both economically and technically feasible, a demonstration plant is needed. The contentions that the CRBR design is obsolete, that its proposed size is inappropriate, or that plutonium can be diverted for weapons proliferation are argued to be invalid. Failure to complete the CRBR will have both economic and national security repercussions

  19. Netherlands Interuniversity Reactor Institut

    International Nuclear Information System (INIS)

    This is the annual report of the Interuniversity Reactor Institute in the Netherlands for the Academic Year 1977-78. Activities of the general committee, the daily committee and the scientific advice board are presented. Detailed reports of the scientific studies performed are given under five subjects - radiation physics, reactor physics, radiation chemistry, radiochemistry and radiation hygiene and dosimetry. Summarised reports of the various industrial groups are also presented. Training and education, publications and reports, courses, visits and cooperation with other institutes in the area of scientific research are mentioned. (C.F.)

  20. 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

  1. 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.

  2. 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

  3. Decay of reactor neutrinos

    OpenAIRE

    Vogel, P.

    1984-01-01

    We consider the decay of massive neutrinos which couple to electrons and are, therefore, produced in nuclear reactors. Lifetime limits for the γ and electron-positron decay modes of these neutrinos are deduced from the experimental limit on the singles count rate in the detector used to study neutrino oscillations at the Gösgen reactor. The dominantly coupled neutrinos are light, and their invariant-lifetime limit tc.m. / mν is 1-3 sec/eV. The subdominantly coupled heavy neutrinos with mass 1...

  4. 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

  5. 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.

  6. 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)

  7. Reactor PIK construction

    International Nuclear Information System (INIS)

    The construction work at the 100 MW researches reactor PIK in year 2002 was in progress. The main activity was concentrated on mechanical, ventilation and electrical equipment. Some systems and subsystems are under adjustment. Hydraulic driving gear for beam shutters are finished in installation, rinsing, and adjusting. Regulating rods test assembling was done. On the critical assembly the first reactor fueling was tested to evaluate the starting neutron source intensity and a sufficiency of existing control and instrument board. Mainline of the PIK facility design and neutron parameters are presented. (author)

  8. Reactor pressure vessel materials

    International Nuclear Information System (INIS)

    As a result of the popularity of the Agencies report 'Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels' of 1975, it was decided that another report on this broad subject would be of use. In this report, background and contemporary views on specially identified areas of the subject are considered as self-contained chapters, written by experts. Chapter 3 offers a detailed treatment of the selection criteria and properties of reactor pressure vessel materials. The main attention is directed towards steel and ingot making and the subsequent material processing

  9. 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

  10. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    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

  11. Space-time reactor kinetics for heterogeneous reactor structure

    International Nuclear Information System (INIS)

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

  12. 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.

  13. 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

  14. New fast-reactor approach

    International Nuclear Information System (INIS)

    The design parameters for a 1000 MW LMFBR type reactor are presented. The design requires the multiple primary coolant pumps and heat exchangers to be located around the core within the reactor vessel

  15. 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)

  16. 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.

  17. 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

  18. 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...

  19. The IR-8 reactor operation

    Energy Technology Data Exchange (ETDEWEB)

    Ryazantsev, E.P.; Egorenkov, P.M.; Yashin, A.F. [Reactor Technology and Materials Research Inst. of RRC ' KI' , Moscow (Russian Federation)

    1997-07-01

    At the Russian Research Center 'Kurchatov Institute' (RRC 'KI') the IR-8 reactor commissioning was carried out in 1981. The reactor was developed in return for earlier existing at RRC 'KI' of the IRT-M reactor (modernized IRT reactor, constructed in 1957). The IRT-M reactor was used for investigations in nuclear physics, solid state physics, radiation chemistry, biology as well as to produce isotopes. Under developing the IR-8 reactor the IRT biological shielding with beam tubes and its process systems were used. The IR-8 reactor creation was founded on application developed by then new fuel assemblies (FA) of IRT-3M type, having two times as great surface of heat transfer and 1.75 times higher U-235 load than the FA of the IRT-2M type, which were used in IRT-M reactor. (author)

  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 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)

  2. 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)

  3. VVER and RBMK reactors

    International Nuclear Information System (INIS)

    The safety of VVER and RBMK reactors has been discussed a lot after Chernobyl accident. Some improvements have been performed since that especially in RBMK-reactors and extensive programmes for backfitting have been planned and are partly underway. There are two different sizes of VVER reactors, 440 MW and 1000 MW. The design bases and designs itself vary inside the family of two size classes depending on the age of the plant. The oldest VVER-440 is called model 230 and the newest model 213. The oldest VVER-1000 units (two units) are prototypes that have some unique, nonfavorable features. The next stage of VVER-1000 developement (three units) is model V-302 and the remaining 15 plants in operation are model V-320, but even within this latest model there are some differences. The design bases and designs vary also inside the family of the RBMK reactors exactly the same way as in VVERs. The most important design bases of nuclear power plants designed in the former Soviet Union is presented in this paper. Also some safety advantages and disadvantages of these NPPs are discussed. (au). (5 figs.)

  4. 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.

  5. 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

  6. 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

  7. 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.

  8. 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

  9. Nuclear reactor container

    International Nuclear Information System (INIS)

    In a container of a BWR type reactor, spray water is stored in a pedestal cavity. A perforated hole is formed on the side wall of the pedestal, and a stirrer is disposed in the pedestal cavity to stir the stored spray water. During reactor operation, the door on the side wall of the pedestal is closed to prevent discharge of fission products to the dry well when a severe accident should occur. During periodical inspection for the plant, the door is opened to enable an operator to access to the inside of the pedestal. When a molten reactor core should drop to the pedestal cavity, fission products generated from the failed reactor core left in a pressure vessel pass through the spray water in the pedestal cavity. Then, most of the fission products are held in the spray water by a scrubbing effect when they pass through the spray water. In addition, the stored spray water is stirred by the stirrer to enhance the scrubbing effect thereby enabling to further decrease the amount of the fission products discharged to the dry well. (N.H.)

  10. ICF tritium production reactor

    International Nuclear Information System (INIS)

    The conceptual design of an ICF tritium production reactor is described. The chamber design uses a beryllium multiplier and a liquid lithium breeder to achieve a tritium breeding ratio of 2.08. The annual net tritium production of this 532 MW/sub t/ plant is 16.9 kg, and the estimated cost of tritium is $8100/g

  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. 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.

  13. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    A method of constructing a radiation shielding plug for use in the roof of the coolant containment vault of liquid metal cooled fast breeder reactors is described. The construction allows relative movement of that part of service cables and pipes which are carried by the fixed roof and that part which is carried by the rotatable plug. (U.K.)

  14. 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.)

  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. 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.)

  17. 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.

  18. 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

  19. 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

  20. 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.

  1. 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

  2. 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

  3. 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)

  4. 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.)

  5. 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

  6. 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.)

  7. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    The general design, characteristics and parameters of TRIGA reactors and fuel are described. This is a training module with the learning objectives: to understand the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and realize the differences between TRIGA fuels and other more traditional. 10 figs., 6 tabs. (nevyjel)

  8. SNAP Nuclear Space Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Corliss, William R

    1966-01-01

    This booklet describes the principles of nuclear-reactor space power plants and shows how they will contribute to the exploration and use of space. It compares them with chemical fuels, solar cells, and systems using energy from radioisotopes. The SNAP (Systems for Nuclear Auxiliary Power) Program, begun in 1955, is described.

  9. Fast breeder reactor

    International Nuclear Information System (INIS)

    This paper outlined the present status of FBR development in six countries and reviewed Japanese activities on FBR development. Joyo experimental FBR has accumulated a lot of technical data including irradiation tests of advanced fuels and was now long shut down due to the partial obstruction of rotating plug movement. Monju prototype FBR reactor experienced a sodium leakage in its secondary heat transfer system during performance tests in December 1995 and had been shut down until May 2010. Feasibility study on commercialized FBR cycle system ended in March 2006 and proposed the concept of commercialized FBR cycle technologies. In order to plan a demonstration reactor, research and development of innovative technologies are conducted as the FaCT (Fast Reactor Cycle Technology Development) Project. In connection with the results of this research and development, a 5-party council of Japan was established to discuss processes of demonstration and commercialization of FBR cycle systems in Japan. Joint efforts were made for a demonstration reactor to be committed in 2015, in addition to start operation around 2025 aiming at the commercialization of FBR before 2050. (T. Tanaka)

  10. 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)

  11. 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. The concept evolved in the 1960's with the objective of developing a reactor design which could be used for a wide range of mobile power generation systems including both Brayton and Rankine power conversion cycles. High temperature thermal cycling tests and in-reactor irradiation tests using cermet fuel were carried out by General Electric in the 1960's as part of the 710 Development Program and by Argonne National laboratory in a subsequent activity. Cermet fuel development programs are currently underway at Argonne National laboratory and Pacific Northwest Laboratory as part of the Multi-Megawatt Space Power Program. 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, there 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

  12. Reactor power measuring device

    International Nuclear Information System (INIS)

    The device of the present invention comprises a γ-thermometer disposed in a BWR type reactor, a first amplifier for amplifying the output thereof, a fission ionization chamber disposed in the reactor separately from the γ-thermometer, a second amplifier for amplifying the output thereof, a differential circuit for differentiating the output signal of the second amplifier and a first adding circuit for adding an output signal of the differential circuit and an output signal of the first amplifier. Alternatively, a γ-ray self-powered neutron detector may be disposed instead of the fission ionization chamber. A second adding circuit is also disposed for adding the output signals of plurality of differentiation circuits and inputting the result to the first adding circuit. A sensitivity controller is disposed upstream of the first adder for controlling the sensitivity of the fission ionization chamber. Then, even if time delay should be caused in the γ-thermometer, output signals with good time response characteristic can be obtained by using signals of LPRM or SPND, and currently changing output of the reactor can be measured accurately to provide an effect on the improvement of the safety and operation controllability of the reactor. (N.H.)

  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. Nuclear reactor with control rods

    International Nuclear Information System (INIS)

    The invention relates to liquid cooled nuclear reactors. In particular, it concerns reactors with mobile control rods in a straight line and guide tubes to guide these control rods through the internal upper components of the reactor vessel and in the aligned fuel assemblies of the core

  16. 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

  17. Reactor regulating and protection system for a light water reactor

    International Nuclear Information System (INIS)

    Microprocessor based systems are developed for reactor regulation and protection of LWR. A triple modular redundancy approach is followed for the design of this system. This system is functionally partitioned into two sub-systems - Reactor Regulating System (RRS) and Reactor Trip Logic System (RTLS). RRS controls the reactor power as per demand and RTLS generates the reactor trip on abnormal process conditions. This paper describes the details of RRS and RTLS system architecture and fault tolerant and fail-safe features used in the system design. (author)

  18. The reactor Pegase

    International Nuclear Information System (INIS)

    The reactor Pegase is designed for testing fuel elements for gas-cooled power reactors. Experience has shown that the classical multi-purpose test reactors are not well adapted to these tests. On another side, the introduction of these test elements into the existing power reactors involves numerous problems, which limits their interest. Pegase, which is designed to satisfy these experimental needs, is composed of a parallelepipedal core of enriched Uranium, moderated and cooled by pressurized water. This core is used as a neutron source for eight autonomous loops, containing the elements to be tested, and situated around the core. The core and the eight loops are immersed in a irradiation pool. The loops are placed on the bottom of the pool so, it is possible to move a loop away from the core, or to remove it from the pool without interfering with the operation of the other loops. The irradiation conditions are adjusted, making the synthesis of the following development works. - Experimental studies on Peggy, a zero power critical facility, mock up of Pegase in operation since 1961: measurements of neutron flux level, radial and axial fly distributions on the experiments. Effect of burnable poisons and of movements of the control rods; adjustment of devices (reflectors, screens etc..) needed for optimum performances. - Experimental work on two prototype autonomous loops, heated electrically to the nominal operating power (in operation since 1961): development of the thermodynamic measurements, thermal balances parameters for control of the operating conditions, natural convection. - Studies on Pegase operating under power; thermodynamic measurements on the core circuits on the independent loop circuits; neutronic measurements, etc... The reactor Pegase went critical on the 4. of April 1963 and reached the nominal power of 30 MW on the 28. of May 1963. (authors)

  19. 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.

  20. 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)

  1. 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

  2. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    This report summarizes main research achievements in the 48th fiscal year which were made by Reactor Engineering Division consisted of eight laboratories and Computing Center. The major research and development projects, with which the research programmes in the Division are associated, are development of High Temperature Gas Cooled Reactor for multi-purpose use, development of Liquid Metal Fast Breeder Reactor conducted by Power Reactor and Nuclear Fuel Development Corporation, and Engineering Research Programme for Thermonuclear Fusion Reactor. Many achievements are reported in various research items such as 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 Computing Center. (auth.)

  3. Methanogenesis in Thermophilic Biogas Reactors

    DEFF Research Database (Denmark)

    Ahring, Birgitte Kiær

    1995-01-01

    Methanogenesis in thermophilic biogas reactors fed with different wastes is examined. The specific methanogenic activity with acetate or hydrogen as substrate reflected the organic loading of the specific reactor examined. Increasing the loading of thermophilic reactors stabilized the process...... as indicated by a lower concentration of volatile fatty acids in the effluent from the reactors. The specific methanogenic activity in a thermophilic pilot-plant biogas reactor fed with a mixture of cow and pig manure reflected the stability of the reactor. The numbers of methanogens counted by the most...... 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...

  4. 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

  5. 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.)

  6. Feasible reactor power cutback logic development for an integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Han, Soon-Kyoo [KHNP Co., Ltd., Uljin-gun, Gyeong-buk (Korea, Republic of); Lee, Chung-Chan; Choi, Suhn; Kang, Han-Ok [Korea Atomic Energy Research Institute (KAERI), Daedeokdaero, Yuseong, Daejeon (Korea, Republic of)

    2013-07-15

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

  7. Feasible reactor power cutback logic development for an integral reactor

    International Nuclear Information System (INIS)

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

  8. 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

  9. Selecting reactor operator trainees

    International Nuclear Information System (INIS)

    Reactor operator trainee selection tends to be more effective if tailored to a utility's unique needs, and offers the organization a better chance for compliance with Federal regulations than if selection methods are adopted without benefit of local research. The costs of operator training range from $50,000 to $100,000. The test validity relative to a variety of training grades and performance measures is reviewed. Of interest is the degree to which tests differentiate reactor operators with respect to simulator training grades and performance in simulator operation; forms of evaluation which have become fairly standard throughout the power industry. The tests administered to each individual were selected because of their presumed relevance to training grades, and the aptitude measures are intended to assess an individual's potential to benefit from training. Tests, availability, form, the abilities they measure, and the time limit are described. (MCW)

  10. Embattled breeder reactor

    International Nuclear Information System (INIS)

    A commercial fuel-cloning machine, a nuclear breeder reactor, is yet to produce electricity in the United States. It is expensive in capital and fuel costs, its fuel that must be reprocessed can become a link to nuclear weapons manufacture, and its safety is no greater than conventional nuclear reactors. The breeder has had on-again/off-again administrative support from Washington. Opponents worry about escalating costs and failure to develop alternatives like solar energy. Proponents say fossil-fuel depletion will eventually force long-term renewable resources such as the breeder anyway. Some who share parts of both views oppose present policy regarding the Clinch River Breeder demonstration plant specifically. The correct choices on breeder concept development and commercialization will be known in 2050. 3 figures

  11. Robot for reactor dismantling

    International Nuclear Information System (INIS)

    Purpose: To enable to attain the operation on a cylindrical coordinate system thereby performing dismantling operation exactly and at a high reliability. Constitution: A reactor dismantling robot is suspended by ropes by an elevating device to the inside of reactor shielding walls. The robot has a fixed portion having a plurality of legs abutting against the inner surface of the shieling walls while extending and shrinking radially in the horizontal direction and an arm portion having an operation arm disposed with a shielding wall breaking operation device. The arm portion is disposed with a mechanism for vertically moving the operation arm and a mechanism for forwarding and backwarding the operation arm in the horizontal direction and the arm portion itself is constituted so as to be rotatable around a vertical axis. (Seki, T.)

  12. 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.

  13. The Pegase reactor loops

    International Nuclear Information System (INIS)

    After 4 years operation, experimentation and maintenance of the gas loops built especially for the nuclear fuel testing reactor Pegase, it appears desirable not only to gather together in a single document the essential characteristics and particularities of these devices and of their associated equipment, but also to give the reasons for the technical modifications and the way in which they were carried out; this is done here by the persons themselves who were responsible, day after day, for operating these loops. This essentially practically experience thus complements the careful research and preliminary testing carried out on these loops or on their prototypes. It should be of interest to those who deal with problems concerned with the design or operation of irradiation loops in experimental reactors or of similar equipment. (authors)

  14. Spherical torus fusion reactor

    Science.gov (United States)

    Peng, Yueng-Kay M.

    1989-01-01

    A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.

  15. Decay of reactor neutrinos

    International Nuclear Information System (INIS)

    We consider the decay of massive neutrinos which couple to electrons and are, therefore, produced in nuclear reactors. Lifetime limits for the γ and electron-positron decay modes of these neutrinos are deduced from the experimental limit on the singles count rate in the detector used to study neutrino oscillations at the Goesgen reactor. The dominantly coupled neutrinos are light, and their invariant-lifetime limit t/sup c.m.//m/sub ν/ is 1--3 sec/eV. The subdominantly coupled heavy neutrinos with mass 1--4 MeV could decay into electron-positron pairs. These pairs were not observed, and from the absence of such a signal we deduce restrictions on the corresponding mixing parameters

  16. Advanced boiling water reactor

    International Nuclear Information System (INIS)

    In the Boiling Water Reactor (BWR) system, steam generated within the nuclear boiler is sent directly to the main turbine. This direct cycle steam delivery system enables the BWR to have a compact power generation building design. Another feature of the BWR is the inherent safety that results from the negative reactivity coefficient of the steam void in the core. Based on the significant construction and operation experience accumulated on the BWR throughout the world, the ABWR was developed to further improve the BWR characteristics and to achieve higher performance goals. The ABWR adopted 'First of a Kind' type technologies to achieve the desired performance improvements. The Reactor Internal Pump (RIP), Fine Motion Control Rod Drive (FMCRD), Reinforced Concrete Containment Vessel (RCCV), three full divisions of Emergency Core Cooling System (ECCS), integrated digital Instrumentation and Control (I and C), and a high thermal efficiency main steam turbine system were developed and introduced into the ABWR. (author)

  17. Fast reactor database

    International Nuclear Information System (INIS)

    This publication contains detailed data on liquid metal cooled fast reactors (LMFRs), specifically plant parameters and design details. Each LMFR power plant is characterized by about 400 parameters, by design data and by relevant materials. The report provides general and detailed design characteristics including structural materials, data on experimental, demonstration, prototype and commercial size LMFRs. The focus is on practical issues that are useful to engineers, scientists, managers and university students and professors. The report includes updated information contained in IAEA previous publications on LMFR plant parameters: IWGRF/51 (1985) and IWGFR/80 (1991) and reflects experience gained from two consultants meetings held in Vienna (1993,1994). This compilation of data was produced by members of the IAEA International Working Group on Fast Reactors (IWGFR)

  18. 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

  19. Gaseous fuel reactor research

    Science.gov (United States)

    Thom, K.; Schneider, R. T.

    1977-01-01

    The paper reviews studies dealing with the concept of a gaseous fuel reactor and describes the structure and plans of the current NASA research program of experiments on uranium hexafluoride systems and uranium plasma systems. Results of research into the basic properties of uranium plasmas and fissioning gases are reported. The nuclear pumped laser is described, and the main results of experiments with these devices are summarized.

  20. Neutrino physics at reactors

    International Nuclear Information System (INIS)

    Reviewing experiments with neutrinos from reactors seems at first to be a simple task, since there were only few. But almost all of them address fundamental questions in particle physics and are of great relevance. This paper reports on these experiments which made use of some of the most sophisticated techniques available at the time they were designed. In these two respects new proposed experiments re in the tradition of the older ones