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Sample records for bolsa chica-1 reactor

  1. The Brazilian Bolsa Escola

    Directory of Open Access Journals (Sweden)

    Rachel Cassidy

    2008-12-01

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

  2. [Quality of food: perceptions of 'Bolsa Familia' program participants].

    Science.gov (United States)

    Uchimura, Kátia Yumi; Bosi, Maria Lúcia Magalhães; Lima, Flávia Emília Leite de; Dobrykopf, Vanessa França

    2012-03-01

    This study deals with perceptions of beneficiaries of the 'Bolsa Familia' Program, in Curitiba, southern Brazil, about their feeding habits. To understand the perceptions of participants of the 'Bolsa Família' Program on the quality of their food. A qualitative study based on the critical-interpretive tradition, which used individual interviews as a technique for gathering empirical data from the informants. The study included 38 individuals, members of families included in the program. The discursive content was recorded on digital media and, thereafter, transcribed and analyzed. After categorization, three main themes emerged: a description of food, quality of food, and feelings and experiences of individuals enrolled in the program. the acknowledgement of social vulnerability and consequent feeding habit insecurity to which such groups are subject was the main finding, as well as feelings of resignation.

  3. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

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

  4. Reactor

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  5. La Nueva Bolsa de Londres - Gran Bretaña

    Directory of Open Access Journals (Sweden)

    Llewellyn-Davies, Richard

    1974-06-01

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

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

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    Maria do Rosário de Fátima Franco Batista

    2011-12-01

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

  7. O Bolsa Família na berlinda? Os desafios atuais dos programas de transferência de renda

    Directory of Open Access Journals (Sweden)

    Renata Mirandola Bichir

    2010-07-01

    Full Text Available O artigo explora alguns pontos de discussão em torno do Programa Bolsa Família, partindo de uma caracterização dos desenhos institucionais dos programas de transferência de renda no Brasil, desde as experiências municipais até os programas federais Bolsa Escola e Bolsa Família. Ao final, discutem-se os principais desafios na sustentabilidade futura do programa.The article explores issues related to Programa Bolsa Família, taking as its starting point a characterization of the institutional designs of cash transfer programs in Brazil, from municipal-level experiences to the federal-level programs Bolsa Escola and Bolsa Família. It ends by taking issue with the main challenges lying ahead of those programs.

  8. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

    Object: To provide a boiling water reactor which can enhance a quake resisting strength and flatten power distribution. Structure: At least more than four fuel bundles, in which a plurality of fuel rods are arranged in lattice fashion which upper and lower portions are supported by tie-plates, are bundled and then covered by a square channel box. The control rod is movably arranged within a space formed by adjoining channel boxes. A spacer of trapezoidal section is disposed in the central portion on the side of the channel box over substantially full length in height direction, and a neutron instrumented tube is disposed in the central portion inside the channel box. Thus, where a horizontal load is exerted due to earthquake or the like, the spacers come into contact with each other to support the channel box and prevent it from abnormal vibrations. (Furukawa, Y.)

  9. Reactor

    International Nuclear Information System (INIS)

    Evans, R.M.

    1976-01-01

    Disclosed is a neutronic reactor having a moderator, coolant tubes traversing the moderator from an inlet end to an outlet end, bodies of material fissionable by neutrons of thermal energy disposed within the coolant tubes, and means for circulating water through said coolant tubes characterized by the improved construction wherein the coolant tubes are constructed of aluminum having an outer diameter of 1.729 inches and a wall thickness of 0.059 inch, and the means for circulating a liquid coolant through the tubes includes a source of water at a pressure of approximately 350 pounds per square inch connected to the inlet end of the tubes, and said construction including a pressure reducing orifice disposed at the inlet ends of the tubes reducing the pressure of the water by approximately 150 pounds per square inch. 1 claim, 16 figures

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

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    Carvalho, Cleusení Hermelina de

    2014-01-01

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

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

    NARCIS (Netherlands)

    L. Mourao (Luciana); A. Macedo de Jesus (Anderson)

    2012-01-01

    markdownabstract__Abstract__ 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

  12. Income transfer policies and the impacts on the immunization of children: the Bolsa Família Program.

    Science.gov (United States)

    Andrade, Mônica Viegas; Chein, Flávia; Souza, Laetícia Rodrigues de; Puig-Junoy, Jaume

    2012-07-01

    This paper investigates the impact of the Bolsa Família Program on the immunization of children from 0 to 6 years of age in Brazil and its regions. The Bolsa Família program is a conditional cash transfer program. One of its conditionalities is the compliance of children with the immunization schedule ordered by the Ministry of Health. The evaluation was performed using the Propensity Score Matching technique. We used data from a survey conducted in 2005 evaluating the program - Pesquisa de Avaliação de Impacto do Programa Bolsa Família. The main findings suggest that the Bolsa Família Program does not affect the immunization status of children.

  13. Estructura de portafolios de inversión en acciones, caso Bolsa Mexicana de Valores, BMV

    OpenAIRE

    Landazuri Aguilera, Yara; Instituto Tecnológico de Sonora; Ruiz Pérez, Roberto; Instituto Tecnológico de Sonora; Valenzuela Reynaga, Rodolfo; Instituto Tecnológico de Sonora; Chávez Rivera, Mirna Yudit; Instituto Tecnológico de Sonora

    2012-01-01

    en los ultimos anos, los mercados de valores han adquirido una mayor importancia dentro de la economia; cada vez es mayor el numero de personas interesadas en su funcionamiento y que centran su atencion en el mercado de capitales. Las empresas especializadas se dirigen a las bolsas de valores a demandar fondos o a invertirlos; los inversionistas independientes tambien han acudido frecuentemente a buscar mejores rendimientos para sus inversiones. Por todo lo anterior, este estudio muestra la e...

  14. Provision of Oral Health Care to Children under Seven Covered by Bolsa Família Program. Is This a Reality?

    Science.gov (United States)

    Petrola, Krishna Andréia Feitosa; Bezerra, Ítalo Barroso; de Menezes, Érico Alexandro Vasconcelos; Calvasina, Paola; Saintrain, Maria Vieira de Lima; Pimentel G F Vieira-Meyer, Anya

    2016-01-01

    Over the last decade, there has been a great improvement in the oral health of Brazilians. However, such a trend was not observed among five-year-old children. Dental caries are determined by the interplay between biological and behavioral factors that are shaped by broader socioeconomic determinants. It is well established that dental disease is concentrated in socially disadvantaged populations. To reduce social and health inequalities, the Brazilian government created Family Health Program (ESF), and the Bolsa Família Program, the Brazilian conditional cash transfer program (Bolsa Família Program). The aim of this study was to examine the oral health care and promotion provided by the Family Health Teams to children and caregivers covered by the Bolsa Família Program. Data was collected through interviews with three groups of participants: 1) dentists working for the Family Health Program; 2) Family Health Program professionals supervising the Bolsa Família Program health conditionalities (Bolsa Família Program supervisors); and 3) parents/caregivers of children covered by the Bolsa Família Program. A pretested questionnaire included sociodemographic, Bolsa Família Program, oral health promotion, dental prevention and dental treatment questions. The results showed that most dentists performed no systematic efforts to promote oral health care to children covered by the Bolsa Família Program (93.3%; n = 69) or to their parents/caregivers (74.3%; n = 55). Many dentists (33.8%) did not provide oral health care to children covered by the Bolsa Família Program because they felt it was beyond their responsibilities. Nearly all Bolsa Família Program supervisors (97.3%; n = 72) supported the inclusion of oral health care in the health conditionality of the Bolsa Família Program, but 82.4% (n = 61) stated they did not promote oral health activities to children covered by the Bolsa Família Program. Children in the routine care setting were more often referred

  15. 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.

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

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    Carin Klein

    2005-04-01

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

  17. Consumo alimentar de beneficiários do programa Bolsa Família

    OpenAIRE

    Alan Giovanini de Oliveira Sartori

    2014-01-01

    A expansão do consumo de alimentos submetidos a elevado grau de processamento em países em desenvolvimento é notória. Em paralelo, observa-se o aumento na prevalência de excesso de peso e de comorbidades associadas. O fenômeno também tem sido observado em famílias consideradas pobres que recebem benefício financeiro de programa federal de transferência condicionada de renda. O objetivo geral foi analisar o consumo alimentar de beneficiários do Programa Bolsa Família (PBF). Foi elaborado um si...

  18. Uso de osteocoral como material de implante en bolsas infraóseas de dientes Monorradiculares

    OpenAIRE

    . Yamilé Hernández Alemán,; Nereyda Riesgo Lobaina; Gladys Rodríguez Méndez; Natividad Alfonso Betancourt

    1999-01-01

    Se evaluó la eficacia del osteocoral como material de implante en el tratamiento de bolsas infraóseas de dientes monorradiculares. Se realizaron 18 injertos en 17 dientes con defectos angulares, en 6 pacientes de ambos sexos; 9 implantes correspondieron al grupo control con hidroxiapatita y 9 al grupo de estudio que fue implantado con osteocoral. Se realizó preparación inicial que incluyó: remoción de cálculos y pulido de las superficies dentarias, educación y motivación sobre el tratamiento ...

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

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    Bernardo de Sá Mota

    2004-09-01

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

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

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    Maria Luiza Souza Caetano

    2016-07-01

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

  1. Diseño, fabricación y comercialización de bolsas biodegradables

    OpenAIRE

    Díaz Cajiao, Samuel Fernando; Hurtatiz Hernández, Alvaro Roosvel

    2012-01-01

    El plástico y sus derivados, son productos de inmensa utilidad, esto se puede evidenciar en sus aplicaciones en la medicina, la tecnología y en la conveniencia que ofrecen en muchas actividades cotidianas. El problema radica en el uso que se le da, así como la forma como se desecha después de su uso, tal es el caso de las bolsas plásticas usadas en los supermercados. Desarrollar un plan de negocio con miras a determinar y evaluar la viabilidad de crear una empresa cuyo producto estrella s...

  2. La Bolsa de Valores de México durante el porfiriato y la revolución, 1885-1934

    OpenAIRE

    Javier Moreno-Lázaro

    2017-01-01

    En este artículo se sostiene que la Bolsa de México sólo contribuyó a la financiación empresarial desde su fundación hasta el inicio de la revolución. Allí encontraron fuentes de financiación empresarios mineros, banqueros e industriales. Pero desde entonces, particularmente desde la aplicación de la doctrina de Carranza en 1916, la Bolsa se convirtió en un mero instrumento financiero del Estado y sirvió entonces casi exclusivamente para la suscripción de deuda. Para demostrar esta hipótesis ...

  3. UM SERVIÇO BASEADO EM ALGORITMOS GENÉTICOS PARA PREDIÇÃO DA BOLSA DE VALORES

    OpenAIRE

    THIAGO PINHEIRO DO NASCIMENTO

    2015-01-01

    A predição da bolsa de valores é um problema complexo, pois envolve uma série de variáveis obscuras, que devem ser capazes de representar, desde o sentimento de cada participante do mercado, até uma catástrofe natural. Esse motivo faz com que vários investidores percam dinheiro e acabem desistindo de investir no mercado de capitais. Como tentativa de contornar essa situação, o presente trabalho propõe o desenvolvimento de um serviço capaz de estimar o preço futuro de ativos na bolsa de valore...

  4. A articulação entre PRONATEC e bolsa família : a execução do bolsa-formação trabalhador para os beneficiários do bolsa família no vale do urucuia, noroeste de minas

    OpenAIRE

    Macedo, Aelejancer Barbosa

    2016-01-01

    Realizou-se, neste estudo, a análise da articulação entre o Programa Nacional de Acesso ao Ensino Técnico e Emprego – Pronatec – e o Bolsa Família: a execução do Bolsa-Formação Trabalhador para os beneficiários do Bolsa Família no Vale do Urucuia. Nesse contexto, elegeu-se o IFNMG, Campus Arinos, como lócus desta pesquisa. Os resultados evidenciaram que a condição de agente ou empoderamento pode ser verificada nos seguintes elementos que implicam situação favorável à inclusão social no vale d...

  5. Influence of the Bolsa Família program on nutritional status and food frequency of schoolchildren

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    Ariene Silva do Carmo

    2016-07-01

    Conclusion: The study found increased consumption of soft drinks among BFP participants. The high rate of overweight and poor eating habits denote the need to develop actions to promote healthy eating, especially for the beneficiaries of the Bolsa Família program, to promote improvements in nutritional status and prevent chronic diseases throughout life.

  6. Influence of the Bolsa Família program on nutritional status and food frequency of schoolchildren.

    Science.gov (United States)

    do Carmo, Ariene Silva; de Almeida, Lorena Magalhães; de Oliveira, Daniela Rodrigues; Dos Santos, Luana Caroline

    2016-01-01

    To evaluate the food frequency and nutritional status among students according to participation in the Bolsa Família program funded by the government. Cross-sectional study carried out with students from the fourth grade of elementary school in the municipal capital of the southeastern region of Brazil. Food consumption and anthropometry were investigated by a questionnaire administered in school, while participation in the Bolsa Família program and other socio-economic information was obtained through a protocol applied to mothers/guardians. Statistical analysis included the Mann-Whitney test, the chi-squared test, and Poisson regression with robust variance, and the 5% significance level was adopted. There were 319 children evaluated; 56.4% were male, with a median of 9.4 (8.6-11.9) years, and 37.0% were beneficiaries of Bolsa Família program. Between the two groups, there was high prevalence of regular soda consumption (34.3%), artificial juice (49.5%), and sweets (40.3%), while only 54.3% and 51.7% consumed fruits and vegetables regularly, respectively. Among participants of Bolsa Família program, a prevalence 1.24 times higher in the regular consumption of soft drinks (95% CI: 1.10-1.39) was identified compared to non-beneficiaries. The prevalence of overweight was higher in the sample (32.9%), with no difference according to participation in the program. The study found increased consumption of soft drinks among BFP participants. The high rate of overweight and poor eating habits denote the need to develop actions to promote healthy eating, especially for the beneficiaries of the Bolsa Família program, to promote improvements in nutritional status and prevent chronic diseases throughout life. Copyright © 2016 Sociedade Brasileira de Pediatria. Published by Elsevier Editora Ltda. All rights reserved.

  7. Volatilidade De Renda E A Cobertura Do Programa Bolsa Família

    OpenAIRE

    Sergei Soares

    2009-01-01

    Este texto argumenta que há uma incompatibilidade entre os critérios de concessão do benefício Programa Bolsa Família (PBF) e a metodologia usada para definir suas metas de cobertura. Enquanto as regras de concessão rezam que os beneficiários, na ausência de grandes variações positivas na renda, têm direito ao benefício por um período de dois anos, as metas são estimadas com base em pesquisas domiciliares transversais ? ou seja, aquelas que não seguem seus entrevistados ao longo do tempo. Na ...

  8. O Bolsa Família Visto pela Lente da Agenda de Trabalho Decente

    OpenAIRE

    Ana Flávia Machado; Gustavo Geaquinto Fontes; Mariangela Furlan Antigo; Roberto Henrique Gonzalez; Fabio Veras Soares

    2012-01-01

    Programa Bolsa Família (PBF) é um programa de transferência condicionada de renda (PTC), que visa garantir um nível mínimo de renda para as famílias pobres e, ao mesmo tempo, promover o acesso das crianças beneficiárias aos serviços de educação e saúde e fornecer assistência social às famílias beneficiárias que dela necessitem. Este One Pager sustenta que o PBF contribui para a Agenda de Trabalho Decente de várias formas; o Trabalho Decente é definido pela OIT como ?trabalho produtivo em cond...

  9. Um olhar neoinstitucionalista para o Programa Bolsa Família

    Directory of Open Access Journals (Sweden)

    Luísa de Azevedo Nazareno

    2015-03-01

    Full Text Available O Programa Bolsa Família (PBF é um programa de transferência condicionada de renda que vem sendo implementado no Brasil desde 2003 e atinge hoje milhões de famílias, tendo trazido inovações importantes tanto no desenho do programa como em sua gestão. Seus impactos sociais positivos têm sido amplamente discutidos pela literatura, contudo, o PBF também deve ser analisado sob o ponto de vista de inovações institucionais. Neste trabalho, partimos do neoinstitucionalismo histórico para discutir a gestão do PBF e algumas de suas inovações, tais como a criação do Cadastro Único e a gestão compartilhada e descentralizada.

  10. Efeitos do Programa Bolsa Família na fecundidade das beneficiárias

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    Patrícia Simões

    2012-12-01

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

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

    Science.gov (United States)

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

    2009-01-01

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

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

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    Cecilia Montero Mórtola

    2011-01-01

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

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

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    Celia Lessa Kerstenetzky

    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.

  14. DESAFIOS PARA A COORDENAÇÃO INTERGOVERNAMENTAL DO PROGRAMA BOLSA FAMÍLIA

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    Claudia Regina Baddini Curralero

    2011-08-01

    Full Text Available The paper examines the intergovernmental coordination of the Bolsa Família Program (PBF, given its goal to tackle poverty in acountry with deep social and regional inequality. It seeks to qualify the debate on the centralization of cash transfer programs in Brazil through the analysis of intergovernmental relations adopted under the three main dimensions of the PBF - cash transfer, monitoring of conditionalities and articulation of complementary programs - considering the federative implications derived from the intersectoral perspective that drives the Program. Two categories of challenges are highlighted. The first one relates to the need for greater investment in space and opportunities for intergovernmental negotiation, especially in the dimension of income transfer, which initially was characterized by centralization. In the second, the intergovernmental matter demands the organization of a coordinated national strategy for the articulation of complementary programs, suggesting greater involvement of states in the regional coordination of the Program

  15. Percepções sobre o Programa Bolsa Família na sociedade brasileira

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    Henrique Carlos de Oliveira de Castro

    2009-11-01

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

  16. FACTIBILIDAD DE ALMACENAMIENTO DE SEMILLAS DE AJONJOLÍ (Sesamum indicum L. EN BOLSAS SILOBAG

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    YESID ALEJANDRO MARRUGO-LIGARDO

    Full Text Available El objetivo de esta investigación fue empacar semillas de ajonjolí (Sesamum indicum en bolsas de silobag, evaluando sus características bromatológicas iníciales y después de los treinta y sesenta días de almacenadas a condiciones ambientales y en bodega a 30°C. Las pruebas se hicieron por triplicado, siguiendo los métodos oficiales de análisis; se reportaron los valores promedios. El análisis estadístico indicó que no hubo diferencias significativas respecto a los valores iníciales y los evaluados después de treinta días de almacenado en condiciones ambientales, en cuanto al contenido de fibra (3,98 ± 0,06 vs 4,16 ± 0,13, proteínas (18,86 ± 0,07 vs 19,71 ± 0,89, humedad (5,96 ± 0,06 vs 6,11 ± 0,11, grasa (38,58 ± 0,58 vs 37,49 ± 0,27 y carbohidratos (31,6 ± 0,14 vs 30,76± 0,68. Si se observó algunas variaciones a medida que avanzó el tiempo de la prueba. Se concluyó que las bolsas silobag, se pueden recomendar para empacar ajonjolí y almacenarlo en bodega o dejarlo a la intemperie, dado que protegen al producto contra agentes externos, conservando sus características básicas iníciales, lo cual representa una solución con posibles beneficios económicos para la conservación de este alimento.

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

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    Fabiana de Cássia Carvalho Oliveira

    2011-07-01

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

  18. 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.

  19. La Bolsa de Valores de México durante el porfiriato y la revolución, 1885-1934

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    Javier Moreno-Lázaro

    2017-01-01

    Full Text Available En este artículo se sostiene que la Bolsa de México sólo contribuyó a la financiación empresarial desde su fundación hasta el inicio de la revolución. Allí encontraron fuentes de financiación empresarios mineros, banqueros e industriales. Pero desde entonces, particularmente desde la aplicación de la doctrina de Carranza en 1916, la Bolsa se convirtió en un mero instrumento financiero del Estado y sirvió entonces casi exclusivamente para la suscripción de deuda. Para demostrar esta hipótesis se presentan series cuantitativas inéditas que miden los efectos de la actividad bursátil en el desarrollo económico del país, al margen de los aspectos específicamente financieros.

  20. 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.

  1. 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.

  2. [Barriers to the search for female sterilization among women in the Bolsa Família Program].

    Science.gov (United States)

    Quadros, Marion Teodósio de; Santos, Giselle Maria Nanes Correia Dos

    2017-06-01

    Poor women in the Bolsa Família program are accused of having more children in order to enroll or remain in the program. In an ethnographic study (2012-2014), we analyzed reports by five beneficiaries of the program and found exactly the opposite. The women reported that they had gone to public health services in Recife, Pernambuco State, Brazil, in hopes of avoiding more children, but that they had encountered various obstacles. Such barriers included difficulties in obtaining reversible contraception and restrictions in the supply of sterilization in these services, which increases the demand for cesarean sections. Their argument that they are beneficiaries of Bolsa Família aims to emphasize their poverty and increase the odds of obtaining sterilization (not always successful). Only two of the women had succeeded in obtaining sterilization, which they attributed to "luck" and "the grace of God" rather than as a right. The study's findings suggest that poor women increase their offspring not because they are enrolled in Bolsa Família, but due to the lack of access to reproductive rights.

  3. 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

  4. [Bolsa Família Program and child nutritional status: strategic challenges].

    Science.gov (United States)

    Oliveira, Fabiana de Cássia Carvalho; Cotta, Rosângela Minardi Mitre; Sant'Ana, Luciana Ferreira da Rocha; Priore, Silvia Eloíza; Franceschini, Sylvia do Carmo Castro

    2011-07-01

    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 evaluation included analysis of weight and height parameters through weight/age, weight/height, height/age and Body Mass Index/age indexes and hemoglobin levels, using the Hemocue. The prevalence of anemia, short stature and obesity were 22.6, 6.3 and 5.2%, respectively, and there were no statistical differences between beneficiaries and non-beneficiaries. The beneficiary group initially had worse socio-economic conditions, but with the BFP it managed to financially match the non-beneficiary group. It is possible that the similarity between the two groups, also in the nutritional status, can be attributed to the program benefits, due to the financial funding as well as to the nutritional monitoring required as a condition of the program.

  5. Female Empowerment of Amazonian Riverine Beneficiaries of the Bolsa Família Program

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    Thamyris Maués dos Santos

    2017-06-01

    Full Text Available Today, policies of combat to poverty prioritize women as owners in programs of income transference, among them, Bolsa Família Program. Considering that women empowerment is influenced by this social policy, this research aimed to identify the dimensions of the process of empowerment achieved by riparian women, beneficiary of the program. The research was performed at Combú Island, Belém do Pará. Four riparian mothers took part in the study. For data collection, the Sociodemographic Inventory and semi structured interviews were used. As procedure of organization of information, content analysis was used. The categories, which appeared from the beneficiary perceptions were adapted from literature and defined as economic, family, social and psychological empowerment. The results showed that after the entrance in BFP the notion of a owned income and bigger control of resources were obtained by a parcel of the participants, providing a partial economic empowerment. The befit increased the purchase power, and gave to these women grater management over family decision-making. The ownership of the program’s card made them to feel benefited when following-up children, providing social visibility to these mothers, when not depending completely of the husbands’ intermediation. Lastly, the benefit generated in the participants a feeling of stability, for having money, security for the family monthly needs. The empowerment that riparian women achieved shows that they passed to interfere in the dynamics and providing of the family before the lack or not of their husbands’ income.

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

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    Luciana Mourão

    2012-06-01

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

  7. [Bolsa-Família Program: diet quality of adult population in Curitiba, Paraná].

    Science.gov (United States)

    Lima, Flávia Emília Leite de; Fisberg, Regina Mara; Uchimura, Kátia Yumi; Picheth, Telma

    2013-03-01

    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 test and ANOVA test were performed to compare the means of the index according to the socio-economic variables, considering a significance level of 5%. The sample comprised 91.4% of women and 8.6% of men. The average age of the population was 36.4 ± 13.3 years, with 75% having completed elementary school. The mean HEI was 51 points, which features a diet that needs improvement. The population has a monotonous diet with an adequate intake of legumes, but low for fruits, vegetables and dairy products. Comparing the categories of diet quality of individuals, all components, except sodium, showed statistically different median score (p < 0.01). Studies that evaluate the quality of the diet are essential to support the implementation of nutrition education programs targeted to the core of the problem in the populations studied.

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

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    Guillermo Buenaventura Vera

    2004-01-01

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

  9. Competencia Legislativa del Municipio en Materia Ambiental: El Caso de las Bolsas Plásticas

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    Wilson Antônio Steinmetz

    2015-12-01

    Full Text Available Este artículo se centra en el problema de la definición y los límites de las competencias legislativas del municipio en materia de ambiente. El marco regulatorio es la Constitución Federal de 1988. La referencia empírica son las leyes locales que rigen el uso de bolsas de plástico, con la finalidad y justificación de la protección del medio ambiente, y las decisiones judiciales acerca de la constitucionalidad de las leyes. Se argumenta que, si bien no existe una disposición expresa en la Constitución brasileña, el principio de subsidiariedad puede ser deducido del modelo federativo esbozado en la Constitución, por lo que es un principio clave para orientar la función legislativa del Municipio en el ámbito ambiental. Adopta una metodología analítica y sistemática, que comprende los aspectos conceptuales, normativos y empíricos del problema.

  10. Uso de osteocoral como material de implante en bolsas infraóseas de dientes Monorradiculares

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    . Yamilé Hernández Alemán,

    1999-12-01

    Full Text Available Se evaluó la eficacia del osteocoral como material de implante en el tratamiento de bolsas infraóseas de dientes monorradiculares. Se realizaron 18 injertos en 17 dientes con defectos angulares, en 6 pacientes de ambos sexos; 9 implantes correspondieron al grupo control con hidroxiapatita y 9 al grupo de estudio que fue implantado con osteocoral. Se realizó preparación inicial que incluyó: remoción de cálculos y pulido de las superficies dentarias, educación y motivación sobre el tratamiento recibido, corrección del cepillado igual o mayor al 80 % en la remoción de placa dentobacteriana. Se realizó el implante mediante operación a colgajo, con sutura y colocación de apósito periodontal. Se realizaron radiografías de control a los 14 días, a los 3 y 6 meses. Se controló sistemáticamente la higiene bucal. A los 6 meses se registraron nuevamente los indicadores clínicos. El análisis final de los resultados mostró una disminución estadísticamente significativa en el índice gingival, profundidad de la bolsa al sondeo y movilidad dentaria para ambos materiales implantológicos. No se reportaron grandes diferencias entre éstos para este tamaño de muestra, no hubo reacciones adversas y se logró la permanencia del implante de osteocoral, por lo que se consideró efectivo el tratamiento.Effectivenes of osteocoral as implant material was assessed to treat infraosseous pockets of multirooted teeth. 18 grafts were inserted in 17 teeth with angular defects in 6 patients of both sexes; 9 implants corresponded to control group (hydroxiapatite and 9 corresponded to study group (osteocoral. Initial preparation included: removal of calculus and polishing of dental surface, education and motivation about treatment applied, correction of tooth-brushing equal or greater 80 % in removal of dentobacterial plaque. Implant was inserted by flap surgery using suture and placement of periodontal dresssing. Control X-rays were made within 14 days

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

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    Carla Gavilan Carvalho

    2012-06-01

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

  12. ADR-IPO latinoamericanos registrados en la Bolsa de Comercio de Nueva York

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    Franco Parisi

    2008-01-01

    Full Text Available El objetivo de este trabajo es estudiar el desempeño de corto y largo plazo de los retornos accionarios de las empresas latinoamericanas que realizaron una oferta inicial de acciones (IPO por medio de American Depositary Receipts (ADR en la Bolsa de Comercio de Nueva York (NYSE. Los resultados señalan una subvaloración estadísticamente significativa de 9,22% para las ADR-IPOs que componen la cartera, y un rendimiento al finalizar el tercer año de 3,75%, estadísticamente significativo. Ambos comportamientos fueron confirmados por la metodología Block Bootstrap, y obtuvieron -en promedio- 11,33% para la subvaloración inicial y 3,92% para el tercer año posregistro. Estos resultados son esperados y de acuerdo a lo indicado por la bibliografía financiera internacional. Al estudiar estos activos latinoamericanos, comparando su rentabilidad con las carteras de mercado locales, la subvaloración inicial es de –0,51% y de 2,95% al cabo de tres años, ambos resultados no son estadísticamente significativos. Por lo anterior, los inversionistas estadounidenses son los que se ven más beneficiados con este tipo de emisión por sobre los inversionistas locales. Llama la atención que los ADR-IPOs no presenten un rendimiento anormal negativo al cabo de tres años de la emisión, hecho que es contrario a lo indicado por la bibliografía financiera.

  13. Focus and coverage of Bolsa Família Program in the Pelotas 2004 birth cohort

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    Kelen H Schmidt

    Full Text Available ABSTRACT OBJECTIVE To describe the focalization and coverage of Bolsa Família Program among the families of children who are part of the 2004 Pelotas birth cohort (2004 cohort. METHODS The data used derives from the integration of information from the 2004 cohort and the Cadastro Único para Programas Sociais do Governo Federal (CadÚnico – Register for Social Programs of the Federal Government, in the 2004-2010 period. We estimated the program coverage (percentage of eligible people who receive the benefit and its focus (proportion of eligible people among the beneficiaries. We used two criteria to define eligibility: the per capita household income reported in the cohort follow-ups and belonging to the 20% poorest families according to the National Economic Indicator (IEN, an asset index. RESULTS Between 2004 and 2010, the proportion of families in the cohort that received the benefit increased from 11% to 34%. We observed an increase in all wealth quintiles. In 2010, by income and wealth quintiles (IEN, 62%-72% of the families were beneficiaries among the 20% poorest people, 2%-5% among the 20% richest people, and about 30% of families of the intermediate quintile. According to household income (minus the benefit 29% of families were eligible in 2004 and 16% in 2010. By the same criteria, the coverage of the program increased from 43% in 2004 to 71% in 2010. In the same period, by the wealth criterion (IEN, coverage increased from 29% to 63%. The focalization of the program decreased from 78% in 2004 to 32% in 2010 according to income, and remained constant (37% according to the IEN. CONCLUSIONS Among the families of the 2004 cohort, there was a significant increase in the program coverage, from its inception until 2010, when it was near 70%. The focus of the program was below 40% in 2010, indicating that more than half of the beneficiaries did not belong to the target population.

  14. Perda de matéria seca em grãos de milho armazenados em bolsas herméticas

    OpenAIRE

    Santos,Silmara Bispo dos; Martins,Marcio Arêdes; Faroni,Lêda Rita D'Antonino; Brito Junior,Valfrido Rodrigues de

    2012-01-01

    O objetivo deste estudo foi avaliar a qualidade e a perda de matéria seca em grãos de milho armazenados em bolsas herméticas sob diferentes temperaturas. Para isso, grãos de milho com teor de água inicial de 14,8 e 17,9% foram acondicionados em bolsas de polietileno lacradas e armazenados em temperaturas de 15; 25 e 35 ºC. Ao longo de 150 dias, em intervalos de 30 dias, as concentrações de oxigênio (O2) e dióxido de carbono (CO2) nas bolsas foram medidas e amostras dos grãos foram retiradas p...

  15. BOLSA FAMÍLIA: IMPORTANTE DETERMINANTE PARA A EDUCAÇÃO E CRESCIMENTO SOCIOECONÔMICO DO BRASIL

    OpenAIRE

    Ferreira, Luiz Antonio

    2012-01-01

    Esta dissertação trata de um tema relativamente novo, com literatura escassa, praticamente sem estudos teóricos que o abordem. Referenciais são encontrados em publicações feitas em seminários e palestras bem como em artigos e notas jornalísticas. Esta dissertação se trata de trabalho exploratório, analítico descritivo com base documental. O Programa Bolsa Família, tema central deste trabalho, é uma ferramenta para distribuição de renda que funciona de forma simples e tem sido efetiva para o a...

  16. El acceso de la mujer a cargos de toma de decisiones en las empresas colombianas que cotizan en bolsa

    OpenAIRE

    Lina Marrugo-Salas

    2016-01-01

    En este artículo se analiza el fenómeno del techo de cristal y se presenta un panorama de la proporción de mujeres en los más altos cargos directivos de 76 empresas colombianas que cotizan en bolsa. La investigación fue de carácter documental mediante la recolección, procesamiento y análisis de la información pública disponible. Los resultados muestran la baja participación de las mujeres en dichos puestos de responsabilidad, por lo que se propone aumentar el rol que tie...

  17. Evaluación del osteocoral como material de implante en bolsas infraóseas de dientes multirradiculares

    OpenAIRE

    Tania Sotomayor Marín; María E. Acosta Navarro

    1999-01-01

    Se evalúa la eficacia del osteocoral como material de implante en el tratamiento de bolsas infraóseas en dientes multirradiculares. Se analizaron 14 pacientes que se dividieron en 2 grupos: el primero incluyó a 6 pacientes con un total de 12 defectos, los cuales se evaluaron hasta los 6 meses. El segundo, con 8 pacientes y 16 defectos, que se reevaluaron a los 12 y 24 meses. En los 2 grupos se incluyeron pacientes de ambos sexos, que fueron implantados con osteocoral (grupo estudio) y con hid...

  18. Vacunación asistida por serología para la enfermedad infecciosa de la bolsa

    OpenAIRE

    Carmen L. Perera; Julia Noda; Sandra Cuello;, P. Alfonso;; V. Espinosa ; A. Merino;

    2005-01-01

    El control efectivo contra enfermedad Infecciosa de la bolsa se basa en las medidas de bioseguridad y en la aplicación de un programa de vacunación efectivo, donde la selección adecuada del momento óptimo de aplicación de la primera dosis de vacuna está determinado por los niveles de anticuerpos maternos (vacunación asistida).En este trabajo se estudió la declinación de los anticuerpos maternos en el tiempo en 40 pollitos de la raza Leghorn desde un día hasta los 31 días por sueroneutralizaci...

  19. Percepções de gênero entre casais beneficiários do Programa Bolsa Família

    Directory of Open Access Journals (Sweden)

    Mani Tebet

    2012-04-01

    Full Text Available Este artigo pretende perceber em que medida o Programa Bolsa Família modifica as relações de gênero, poder e interesse entre os casais beneficiários, tema que tem despertado pouco interesse do debate público e acadêmico. Pretende ainda sinalizar ecompreender os efeitos morais e simbólicos que a política pode produzir sobre a família e as relações de gênero; os critérios de justiça apontados pelos casais para “merecer” o Bolsa Família; e a lógica que se encontra na base dessa noção de merecimento. Paratanto, entrevistamos casais beneficiários do bairro de Nova Cidade, no município de Itaboraí, na Região Metropolitana do Rio de Janeiro. Gender Perceptions between Couples Benefiting from the ‘Bolsa Família’ Program intends to ascertain to what extent the ‘Bolsa Família’ allowance program modifies the gender, power and interest relations between couples who receive benefits from the scheme; a topic that has aroused very little interest in public and academic debate. It also attempts to identify and understand the moral and symbolic effects that the policy can produce on the family and gender relations; the criteria of justice put forward by the couples for “deserving” the Bolsa Família; and the rationale that underlies this notion of deserving. Interviews were conducted with couples in a district in the metropolitan region of Rio de Janeiro.Keywords: poverty, gender, family, ‘Bolsa Família’ Allowance Program, income transfer

  20. Empoderamento ou mudança de situação financeira? Um estudo com beneficiárias do Programa Bolsa Família

    OpenAIRE

    Barros, Valeria Rezende Freitas; Faculdade Novos Horizontes; Melo, Marlene Catarina de Oliveira Lopes; Faculdade Novos Horizontes

    2016-01-01

    Looking at Brazilian public policies on empowerment in the context of gender relations, we sought to examine whether the Bolsa Família Program impacts the empowerment of female beneficiaries in a mining town through how they are perceived. This research can be characterized as a descriptive field study with a qualitative approach, with the unit of analysis being female beneficiaries of the Bolsa Família Program and the research subjects being 12 beneficiaries. It was found that the changes tr...

  1. Nos limites do viver e do sobreviver:  o programa Bolsa Família, modos de vida e desenvolvimento social no contexto urbano

    OpenAIRE

    Marilene Alberini

    2010-01-01

    O programa Bolsa Família, instituído pelo governo federal em 2003, foi estudado a partir do contexto dos beneficiários moradores na favela São Judas, localizada na periferia da cidade de Guarulhos. A pesquisa objetivou caracterizar, do ponto de vista socioeconômico e cultural, famílias atendidas pelo programa Bolsa Família, assim como identificar mudanças na dinâmica familiar e os significados assumidos pelo programa como modo diferenciado de vida. O estudo pretendeu, ainda, analisar os alcan...

  2. Gênero e combate à pobreza: programa bolsa família Gender and poverty fight: the family donation program

    Directory of Open Access Journals (Sweden)

    Silvana Aparecida Mariano

    2009-12-01

    Full Text Available A política de assistência social brasileira orienta-se pela perspectiva de ações de combate à pobreza, com prioridade aos programas de transferência condicionada de renda. Esses são programas que priorizam o repasse de renda às mulheres e envolvem-nas em uma rede de obrigações e condicionalidades, a exemplo do Programa Bolsa Família. A prática encerrada no Programa Bolsa Família coloca em evidência algumas contradições entre as ações estatais e as demandas feministas, notadamente no que diz respeito à problematização acerca da maternidade. Esse é, então, um ponto central para o diálogo entre o feminismo e as políticas sociais estatais de combateThe Brazilian social assistance policy is guided by the perspective of poverty fight efforts, which prioritize the conditioned income transfer. These programs privilege the income transfer to women and involve them in a net of obligations and conditions, as it is done in the Family Donation Program. The practice within Family Donation Program highlights some contradictions between the State actions and the feminist demands, especially those concerning the motherhood problem. This is thus a core question for the dialogue between the feminism and the social policies sponsored by the State

  3. Qualidade de grãos de milho armazenados em silos bolsa Quality of corn grain stored in silo bags

    Directory of Open Access Journals (Sweden)

    André Rodrigues da Costa

    2010-06-01

    Full Text Available A utilização de bolsas seladas hermeticamente é uma alternativa aos métodos tradicionais de armazenagem de grãos em nível de fazenda. Em vista disso, objetivou-se com este trabalho avaliar a qualidade de milho armazenado hermeticamente em silos bolsa. O produto, com teores de água de 14,5 e 18,0% b.u, foi acondicionado em mini-bolsas devidamente seladas nas temperaturas de 25; 30 e 35 ºC. Foram realizadas análises de teor de água, de classificação dos grãos, de massa específica aparente, de percentual de germinação e de condutividade elétrica, no início do armazenamento e após 30; 60; 90; 135 e 180 dias. Verificou-se que não houve variação do teor de água dos grãos de milho armazenados nos silos bolsa. Os grãos de milho foram classificados como Tipo 1 ao longo do período de armazenamento, exceto para os com 18,0% (b.u. de teor de água na temperatura de 35 ºC. Não houve decréscimo significativo da massa especifica aparente do produto ao longo do armazenamento. Em geral, ocorreu decréscimo do percentual de germinação dos grãos de milho armazenados úmidos e secos e acréscimo da condutividade elétrica da solução que continha os grãos, exceto para os armazenados com 14,5% nas temperaturas de 25 e 30 ºC. Conclui-se que é possível armazenar milho em silos bolsa, durante 180 dias, grãos com teor de água de 14,5% (b.u. nas temperaturas de 25; 30 e 35 ºC e grãos com teor de água de 18,0% por 180 dias nas temperaturas de 25 e 30 ºC.Airtight storage in sealed bags provides an alternative to traditional methods for on-farm grain storage. The objective of this work was therefore to evaluate the quality of corn stored in airtight sealed bags. Grain with moisture content (m.c. of about 14.5 and 18.0% (w.b. was properly stored in sealed mini-bags at 25; 30; and 35 ºC. Analyses included moisture content, grain classification, apparent specific mass, percentage of germination and electrical conductivity at the

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

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

  5. FENESTRAÇÃO VIDEOENDOSCÓPICA DO SEPTO MEDIAL DA BOLSA GUTURAL E RETIRADA DE CONDRÓIDES EM UM EQUINO – RELATO DE CASO

    Directory of Open Access Journals (Sweden)

    Carla Faria Orlandini

    2014-07-01

    Full Text Available As bolsas guturais são divertículos da tuba auditiva, divididas em compartimentos lateral e medial, possuindo função termorregulatória. Suas mais frequentes afecções são empiema, micose e timpanismo. O empiema é o que ocorre com maior frequência, tendo como principal agente causador o Streptococcus equi. Animais acometidos apresentam secreção nasal e quando crônico, há espessamento deste material, resultando em concreções duras, os condróides. O objetivo deste trabalho é relatar a utilização do acesso cirúrgico através do triângulo de Viborg, fenestração videoendoscópica do septo mediano e retirada de condróides da bolsa gutural. Relata-se o caso de um equino que apresentava secreção nasal, apatia e anorexia. Através de endoscopia observou-se secreção purulenta principalmente na bolsa direita, caracterizando empiema. Realizou-se coleta deste material para realização de exame microbiológico. Foi instituído o tratamento clínico, porém sem resultados satisfatórios. Realizou-se, sob anestesia geral, a fenestração do septo mediano e acesso à bolsa pelo triângulo de Viborg no lado esquerdo, com implantação de sonda de Foley até a entrada da bolsa direita. Sem sucesso no tratamento pós-cirúrgico foi realizada nova endoscopia onde verificou-se a presença de condróides os quais foram retirados por novo procedimento cirúrgico, desta vez pelo lado direito. Conclui-se com este relato que a técnica de acesso à bolsa gutural pelo triângulo de Viborg mostra-se muito eficaz na remoção de condróides, que a fenestração do septo potencializa a limpeza diária das bolsas e que o exame endoscópico é a principal forma de diagnóstico do empiema, podendo este ser causado por Pseudomonas aeruginosa.

  6. 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

    Directory of Open Access Journals (Sweden)

    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.

  7. Evolução do Programa Bolsa Família: Brasil e estados do Nordeste 2004-2009

    OpenAIRE

    Queiroz, Silvana Nunes de; Remy, Maria Alice Pestana de Aguiar; Pereira, Júlia Modesto Pinheiro Dias; Silva, Luis Abel da

    2010-01-01

    Este artigo analisa a evolução no número de beneficiários e no valor do repasse do Programa Bolsa Família (PBF). Para tanto, são feitas considerações sobre o conceito de pobreza e as principais alterações na concepção do PBF. O estudo tem como recorte temporal os anos de 2004 a 2009, e recorte espacial o Nordeste brasileiro, região com os piores indicadores sociais e demográficos do país. A fonte de dados foi a Matriz de Informação Social do MDS (Ministério do Desenvolvimento Social), que apo...

  8. Bolsa Família : avaliação do impacto do programa sobre a pobreza no Brasil

    OpenAIRE

    Costa, Rosita Soares Pereira

    2015-01-01

    O objetivo do presente estudo é avaliar o impacto do Programa Bolsa Família (PBF) sobre a redução da pobreza no Brasil no período de 2004 a 2012. Este trabalho parte da hipótese de que o PBF teve influência na redução da pobreza no Brasil no período analisado. Além do PBF, foram incluídas no modelo outras variáveis, tais como crescimento econômico, emprego, analfabetismo, domicílios com saneamento adequado e com energia elétrica, taxa de homicídios e mortalidade infantil, para diminuir distor...

  9. Poverty and education from the Programa Bolsa Família book lets, guides and manuals (2006 – 2014

    Directory of Open Access Journals (Sweden)

    Marcela Bruna Nappi Alvares

    2017-09-01

    Full Text Available The objective of this study was to analyze the education and poverty conceptions present in material published from 2006 and 2014 that speak directly to beneficiaries of the ProgramaBolsaFamília (PBF, a Brazilian federal cash transfer program. The assumption of the survey was that the wordings are composed of material, cultural, historical and socialaspects. Publications understand poverty by multiple dimensions, such as lack of access to healthy food and denial of rights.Education has been recognized as an important means to overcome the socio-economic vulnerabilities. The discursive genre of the material includes a prescriptive and disciplinarian character; however, this feature has been losing strength over the publications.

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

    Directory of Open Access Journals (Sweden)

    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.

  11. El acceso de la mujer a cargos de toma de decisiones en las empresas colombianas que cotizan en bolsa

    Directory of Open Access Journals (Sweden)

    Lina Marrugo-Salas

    2016-01-01

    Full Text Available En este artículo se analiza el fenómeno del techo de cristal y se presenta un panorama de la proporción de mujeres en los más altos cargos directivos de 76 empresas colombianas que cotizan en bolsa. La investigación fue de carácter documental mediante la recolección, procesamiento y análisis de la información pública disponible. Los resultados muestran la baja participación de las mujeres en dichos puestos de responsabilidad, por lo que se propone aumentar el rol que tienen en las empresas mediante el desarrollo de programas de responsabilidad social.

  12. Aspectos diferenciais da inserção de mulheres negras no Programa Bolsa Família

    Directory of Open Access Journals (Sweden)

    Silvana Aparecida Mariano

    2013-08-01

    Full Text Available O artigo discute resultados de uma pesquisa realizada com mulheres titulares do Programa Bolsa Família (PBF em Uberlândia-MG e Londrina-PR, de modo a analisar possíveis variações relacionadas à condição de desigualdade, levando-se em consideração o quesito cor/raça das respondentes. Uma análise interna sobre o público atendido pelo Programa Bolsa Família (PBF, nesses municípios brasileiros, nos permite constatar as diferenças existentes, mesmo estando todas essas pessoas em situação de pobreza. As situações de pobreza são multifacetadas e o seu caráter multidimensional envolve situações como aquelas que podem ser explicadas pela variável raça/etnia. Este trabalho trata sociologicamente de algumas das tessituras da vida social de mulheres negras que vivem em situação de pobreza e de extrema pobreza, com experiências marcadas pela condição de gênero e de cor/raça. Nossos resultados indicam que o PBF exerce mais influência no cotidiano das mulheres negras, em comparação com as brancas. Contudo, tal influência não gera o impacto de equalizar a situação entre esses dois grupos de mulheres.

  13. 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.

  14. H Reactor

    Data.gov (United States)

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

  15. 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

  16. Iniquidades em saúde bucal: escolares beneficiários do Bolsa Família são mais vulneráveis?

    OpenAIRE

    Oliveira, Luísa Jardim Corrêa de; Correa, Marcos Britto; Nascimento, Gustavo Giacomelli; Goettems, Marília Leão; Tarquínio, Sandra Beatriz Chaves; Torriani, Dione Dias; Demarco, Flávio Fernando

    2013-01-01

    OBJETIVO : Analisar a associação entre ser beneficiário do Programa Bolsa Família e condições de saúde bucal entre escolares. MÉTODOS : Estudo transversal com 1.107 escolares entre oito e 12 anos de idade, provenientes de 20 escolas públicas e particulares da cidade de Pelotas, RS, em 2010. Os beneficiários do Programa Bolsa Família foram verificados por meio de lista fornecida pelas escolas participantes do estudo. Informações demográficas, socioeconômicas, de uso de serviço odontológico e...

  17. Programa Bolsa Família e Geração "Nem-Nem": Evidências para o Brasil

    Directory of Open Access Journals (Sweden)

    Andressa Mielke Vasconcelos

    Full Text Available O presente estudo investiga a relação entre o Programa Bolsa Família e a probabilidade de que jovens adultos entre 18 e 29 anos pertençam à geração "nem-nem". Para atingir este objetivo, é construído um modelo teórico que considera os microfundamentos da escolha do beneficiário entre trabalho, lazer e estudo. Empiricamente, utilizam-se os dados do Censo Demográfico de 2010 combinados com a estratégia metodológica de Imbens (2015 e o método Propensity Score Matching. Os resultados obtidos indicam que o Programa Bolsa Família reduz a probabilidade de que os jovens sejam "nem-nem".

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

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    Rosa Maria Marques

    2009-03-01

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

  19. Society-State relationships, citizen participation and political clientelism inside programs that combat poverty. The case of «Bolsa Familia» in Brazil

    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.

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

    Directory of Open Access Journals (Sweden)

    Carin Klein

    2007-12-01

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

  1. Adolescente masculino beneficiário do programa bolsa família: conhecimento sobre o programa na família assistida

    Directory of Open Access Journals (Sweden)

    Núbia Maria Uchôa Barbosa

    2016-06-01

    Full Text Available Objetivo: Identificar o conhecimento do adolescente masculino sobre o Programa Bolsa Família e o seu impacto na família assistida. Métodos: Trata-se de um estudo descritivo, exploratório, com abordagem qualitativa, realizado entre julho e setembro de 2014, em uma escola pública no município de Fortaleza, Ceará, BR, com 12 adolescentes beneficiários do Programa Bolsa Família. Para a coleta de dados, foi utilizada a entrevista semiestruturada e técnica de grupo focal. Os dados foram analisados por meio da análise de conteúdo, emergindo quatro categorias temáticas: Atendimento de pessoas de baixa renda; freqüência escolar como principal estratégia; falta de priorização na promoção da saúde e prevenção de doenças; Programa Bolsa Família: impacto nas famílias assistidas. Resultados: Os resultados apontaram que os adolescentes reconhecem os efeitos positivos do programa nas famílias de baixa renda melhorando o poder aquisitivo, além de levar ao aumento da freqüência escolar, diminuindo a evasão, porém em nenhum momento mencionaram que o programa objetiva a promoção da saúde e o apoio de políticas complementares. Conclusão: Verifica-se a necessidade de incrementar a saúde do adolescente masculino vinculado ao Programa Bolsa Família com foco na Promoção da Saúde de forma consolidada numa perspectiva de previsibilidade na agenda multiprofissional da Atenção Primária à Saúde.

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

    Directory of Open Access Journals (Sweden)

    Ernesto Friedrich de Lima Amaral

    2013-09-01

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

  3. Ensayos físico químicos para el estudio de la degradación de bolsas de supermercado

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    Luis Latrónica

    2011-05-01

    Full Text Available Este trabajo describe y analiza la variación de algunas propiedades físicas y químicas que las bolsas de supermercado (polietileno experimentan durante su degradación. Se estudian estas propiedades para las “bolsas camiseta” que contienen y para las que no contienen aditivos para acelerar su degradación. Las muestras se colocan en un equipo de simulación de radiación solar con temperatura y humedad controladas en equipo Weather-o-meter. Durante la exposición a las diferentes condiciones ambientales se extrajeron muestras con una frecuencia de 50 horas y se realizaron ensayos de tracción, elongación, desgarro y de espectroscopía infrarroja (FTIR. Los valores indican que las bolsas quecontienen aditivo oxi-biodegradable muestran pérdidas apreciables de sus propiedades físicas y químicas en la mitad del tiempoque aquellas que no contienen el aditivo.

  4. Impact of the Bolsa Família Program on energy, macronutrient, and micronutrient intakes: Study of the Northeast and Southeast

    Directory of Open Access Journals (Sweden)

    Naiara SPERANDIO

    Full Text Available ABSTRACT Objective: To assess the impact of the Bolsa Família Program on the energy and nutrient intakes of beneficiaries from the Brazilian Northeast and Southeast regions. Methods: The study used data from the 2008-2009 Pesquisa de Orçamento Famíliar, which assessed individual food intake on two nonconsecutive days of individuals aged more than 10 years. Based the personal information booklet, food intake values were transformed into nutritional values (energy and nutrients. Analysis of the impact measure was preceded by propensity score matching, a technique that matches some socioeconomic characteristics of beneficiaries and nonbeneficiaries. Once the score was calculated, the impact of the Bolsa Família Program was estimated by nearest neighbor matching. Results: The program increased energy and macronutrient intakes and decreased calcium and vitamin A, D, E, and C intakes of adolescent beneficiaries in both regions. Adult beneficiaries from the Southeast region increased their fiber, iron, and selenium intakes, and those from the Northeast region decreased their energy, lipid, added sugar, sodium, zinc, vitamin E, and pyridoxine intakes. Conclusion: The results show a positive impact of the program on the energy and macronutrient intakes, and a negative impact on the intakes of most study micronutrients, especially in adolescents, which reinforce the importance of implementing intersectoral actions to improve the nutritional quality of the Bolsa Família Program beneficiaries' diet.

  5. O Programa Bolsa Família: lições da experiência alemã

    Directory of Open Access Journals (Sweden)

    Clóvis Roberto Zimmermann

    2009-07-01

    Full Text Available

    Esse artigo tece uma comparação do Bolsa Família com a experiência internacional, argumentando que os programas de transferência de renda brasileiros jamais podem ser visto como “barbaridade”, e de forma alguma “assombram o Brasil”, assim como também não contribuem para manter e tornar operativa a “pobreza brasileira”. Conforme demonstramos no artigo, programas de transferência de renda similares ao Bolsa Família, porém mais justos e generosos, existem em muitos países da Europa, não sendo encarados como “barbaridade”. Além disso, não existe a intenção política de se extinguir tais programas, pois contribuem para reduzir a fome e diminuir consideravelmente os níveis de

  6. 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.

  7. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

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

  8. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

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

  9. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

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

  10. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

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

  11. Programa Bolsa Família e violência doméstica contra a mulher no Brasil

    Directory of Open Access Journals (Sweden)

    Gustavo Carvalho Moreira

    Full Text Available Resumo A violência contra as mulheres implica custos diretos e indiretos ao indivíduo, à família e à sociedade, atingindo principalmente as classes de baixa renda. Diante dessa realidade, o presente estudo procurou analisar como uma política pública de transferência de renda condicionada - Programa Bolsa Família (PBF é capaz de influenciar tal fenômeno. Os resultados encontrados apresentam evidências de que o PBF possui efeito de aumentar a violência contra a mulher. Ademais, aquelas domiciliadas no meio rural, com baixa escolaridade e com rendimentos relativamente menores aos do cônjuge são as que merecem maior atenção, uma vez que este grupo possui maior risco de sofrer violência. Como sugestão, as políticas públicas deveriam expandir a condicionalidade da saúde para a mulher por meio de ações educativas, como o acompanhamento da situação intrafamiliar, que é fornecido pela assistência social do Serviço de Proteção e Atendimento Integral à Família - PAIF.

  12. The “Bolsa Familia” program and the matter of gender: Challenges and perceptions for the role of occupational therapists

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    Késia Maria Maximiano de Melo

    2014-04-01

    Full Text Available This article proposes a critical reflection and analyzes the factors that build, naturalize and reproduce social inequalities in the structuring and development of the current Brazilian society. Specifically, it faces this challenge through perceptions of maintenance on the relationships between women’s roles, based on the relationship between the matter of gender, the social protection system, and the role of power. This paper uses a privileged field for this reflection - the analysis of women beneficiary of the “Bolsa Familia” program as a locus of challenge for the action of Occupational Therapy - considering the historical and social consequences of the scenario in which these women are included and the consequent fragility with relational ties. It also analyzes the objectives proposed by the program and its possible contributions to the empowerment of women in the social context, besides being guided by the recent inclusion of the occupational therapist in the Unified Social Assistance System (SUAS, legitimizing its practice in the social field and opening possibilities for action in this system.

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

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    Caroline Sousa Cabral

    2014-02-01

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

  14. 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.

  15. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

    Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)

  16. Reactor Neutrinos

    OpenAIRE

    Kim, Soo-Bong; Lasserre, Thierry; Wang, Yifang

    2013-01-01

    We review the status and the results of reactor neutrino experiments. Short-baseline experiments have provided the measurement of the reactor neutrino spectrum, and their interest has been recently revived by the discovery of the reactor antineutrino anomaly, a discrepancy between the reactor neutrino flux state of the art prediction and the measurements at baselines shorter than one kilometer. Middle and long-baseline oscillation experiments at Daya Bay, Double Chooz, and RENO provided very ...

  17. BOILING REACTORS

    Science.gov (United States)

    Untermyer, S.

    1962-04-10

    A boiling reactor having a reactivity which is reduced by an increase in the volume of vaporized coolant therein is described. In this system unvaporized liquid coolant is extracted from the reactor, heat is extracted therefrom, and it is returned to the reactor as sub-cooled liquid coolant. This reduces a portion of the coolant which includes vaporized coolant within the core assembly thereby enhancing the power output of the assembly and rendering the reactor substantially self-regulating. (AEC)

  18. Reactor vessel

    NARCIS (Netherlands)

    Makkee, M.; Kapteijn, F.; Moulijn, J.A.

    1999-01-01

    A reactor vessel (1) comprises a reactor body (2) through which channels (3) are provided whose surface comprises longitudinal inwardly directed parts (4) and is provided with a catalyst (6), as well as buffer bodies (8, 12) connected to the channels (3) on both sides of the reactor body (2) and

  19. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

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

  20. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

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

  1. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

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

  2. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Nagatomi, Shozo.

    1976-01-01

    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.)

  3. 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

    Directory of Open Access Journals (Sweden)

    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

  4. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

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

  5. Evaluación del osteocoral como material de implante en bolsas infraóseas de dientes multirradiculares

    Directory of Open Access Journals (Sweden)

    Tania Sotomayor Marín

    1999-12-01

    Full Text Available Se evalúa la eficacia del osteocoral como material de implante en el tratamiento de bolsas infraóseas en dientes multirradiculares. Se analizaron 14 pacientes que se dividieron en 2 grupos: el primero incluyó a 6 pacientes con un total de 12 defectos, los cuales se evaluaron hasta los 6 meses. El segundo, con 8 pacientes y 16 defectos, que se reevaluaron a los 12 y 24 meses. En los 2 grupos se incluyeron pacientes de ambos sexos, que fueron implantados con osteocoral (grupo estudio y con hidroxiapatita (grupo control. Se realizó reparación inicial que incluyó remoción de cálculo y pulido de la superficie dentaria, educación y motivación y evaluación del cepillado, que debía mostrar valores iguales o mayores del 80 % en la remoción de placa dentobacteriana. Posteriormente se realizó el implante mediante operación a colgajo. Se realizaron radiografías de control a los 14 días, 6 meses (para el primer grupo y 12 y 24 meses (para el segundo grupo. Se controló sistemáticamente la higiene bucal en ambos grupos. Se controlaron nuevamente los indicadores clínicos a los 6 meses para el primer grupo, y a los 12 y 24 meses para el segundo. Se observó una disminución estadísticamente significativa en el índice gingival, profundidad de la bolsa y movilidad dentaria para ambos materiales implantológicos, sin que se reportaran grandes diferencias entre éstos. Radiográficamente se observó la presencia de relleno en el defecto original, y no hubo reacciones locales adversas, por lo que se consideró efectivo el tratamiento.Effectiveness of osteocoral was assessed as material for implants at infraosseous pockets of multirooted teeth. 14 analised patients were divided into 2 groups: first, included 6 cases and 16 defects, which were evaluated ultil 6 months. Second, included 8 cases and 16 defects, evaluated at 12 and 24 months. In both groups, males and women, were included underwent to implants with osteocoral (study group and

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

    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.

  7. A relação entre pobreza e renda do programa bolsa família:O Que mudou na legislação entre 2004 e 2013? (The relationship between poverty and income of the bolsa família program: What changed in legislation between 2004 and 2013? Doi: 10.5212/Emancipacao.

    Directory of Open Access Journals (Sweden)

    Roberta Rezende Oliveira

    2016-03-01

    Full Text Available Resumo: O presente artigo objetiva discutir as principais mudanças ocorridas no Programa de transferência de renda Bolsa Família quanto ao escopo proposto em seu desenho, referente à superação da pobreza enquanto insuficiência de renda. Com base na análise da legislação federal produzida entre 2004 e 2013, verificamos modificações que resultaram em incremento na incorporação de famílias mediante: o aumento do teto no valor da renda per capita máxima; modificações nos critérios de inclusão vinculados à composição familiar e; incorporação de outros programas assistenciais federais. Nas conclusões discutimos a adequação destas alterações, frente ao perfil e às características da pobreza brasileira.Palavras-chave: Programa Bolsa Família. Pobreza. Transferência de Renda.Abstract: This article objects to discuss the main changes that happened in the ‘Bolsa Família’ Program of income transfer in terms of the scope proposed, that refers to the overcome of poverty as inadequacies of income. Based on the federal legislation analysis produced between 2004 and 2013, we observed changes that resulted in an increment in the family’s incorporation by means of: increasing the ceiling on the value of the maximum per capita income; changes in the criteria of inclusion bound to family composition and; incorporation of other federal assistance programs. In the conclusions we talked about the adequacy of these changes, face to the profile and aspects of the Brazilian poverty.Keywords: Bolsa Família Program. Poverty. Income transfer.

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

    Directory of Open Access Journals (Sweden)

    Luis Román Ardila Núñez

    1999-05-01

    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 de ácidos, 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.

  9. O significado da educação para as mães do programa bolsa família na grande Curitiba

    OpenAIRE

    Esmanhoto, Marialda

    2010-01-01

    Resumo: A presente pesquisa tem como objetivo investigar o significado da educação para os inscritos no Programa Bolsa Família sob o enfoque da Psicologia Social Comunitária. A escolha do referido tema se deu a partir da prática e observação da pesquisadora junto a famílias economicamente desfavorecidas, em um Município da Grande Curitiba, tendo em vista que a pesquisadora desenvolve atividades há mais de dois anos na gestão pública municipal, e tem acesso aos dados reais sobre o funcionament...

  10. 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

  11. Evaluación de la terapia mecánica periodontal en bolsas profundas: Respuesta clínica y bacteriológica

    OpenAIRE

    Bazzano,G; Parodi,R; Tabares,S; 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)...

  12. Confección de cartera de inversión para un cliente institucional de INS Valores Puesto de Bolsa S.A. con instrumentos financieros internacionales

    OpenAIRE

    Fonseca Villalobos, Oscar Guillermo

    2013-01-01

    Tesis de maestría -- Universidad de Costa Rica. Posgrado en Administración y Dirección de Empresas. Maestría Profesional en Administración y Dirección de Empresas con énfasis en Finanzas, 2013 El objetivo general de este trabajo, es conformar una cartera de inversión con instrumentos financieros internacionales para un cliente institucional de INS VALORES PUESTO DE BOLSA S.A. La organización investigada se dedica a la oferta de servicios bursátiles. Fue creada el 5 de julio de 1993 y ...

  13. BRIC (Brasil, Rússia, Índia e China): uma análise da volatilidade da bolsa de valores – jan/2005 a mar/2010

    OpenAIRE

    Machado, Cléia Duarte

    2011-01-01

    O presente estudo analisa a volatilidade da Bolsa de Valores para os países do BRIC entre janeiro de 2005 a março de 2010. A pesquisa tem a finalidade de verificar a existência do efeito contágio entre esses emergentes. Foram utilizados diversos modelos de volatilidade determinística da família GARCH, tanto univariado, quanto multivariado. Também foi investigado até que ponto a crise financeira de 2008 resultou em mudanças na relação entre esses países. Para tanto, foram feitas estimativas pa...

  14. Dos casos de muerte debida a sofocación por bolsa de plástico Two cases of death due to plastic bag suffocation

    OpenAIRE

    E. Barbería Marcalain; CJ. Correas Soto; F. Miró García

    2004-01-01

    La muerte debida a sofocación por bolsa de plástico (SBP), reconoce diferentes etiologías medico-legales (suicida, homicida, accidental). Aunque en la actualidad es poco frecuente en nuestro medio, es un método tendente a aumentar su frecuencia, especialmente el de etiología suicida, según la bibliografía revisada. En el presente trabajo se describen dos casos de SBP con la finalidad de determinar similitudes y diferencias entre ellos, así como el grado de correspondencia con el cuadro descri...

  15. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

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

  16. Heterogeneous reactors

    International Nuclear Information System (INIS)

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

    1979-08-01

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

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    Mysels, K.J.; Shenoy, A.S.

    1976-01-01

    A nuclear reactor is described in which the core consists of a number of fuel regions through each of which regulated coolant flows. The coolant from neighbouring fuel regions is combined in a manner which results in an averaging of the coolant temperature at the outlet of the core. By this method the presence of hot streaks in the reactor is reduced. (UK)

  18. Bolsa Família e assimetrias de gênero: reforço ou mitigação?

    Directory of Open Access Journals (Sweden)

    Luana Passos

    Full Text Available Resumo Este artigo tem por objetivo investigar se o programa Bolsa Família contribui para o processo de individualização das mulheres pobres. Para tanto, foi utilizada a técnica de pareamento por escore de propensão, a fim de identificar mulheres e homens não atendidos pelo programa comparáveis a mulheres e homens atendidos. Com base na Pesquisa Nacional por Amostra de Domicílio de 2006, estimaram-se a jornada de trabalho doméstico, a participação no mercado de trabalho e as horas de trabalho remunerado de homens e mulheres. Os resultados não foram conclusivos para participação no mercado de trabalho. Para a jornada de trabalho remunerado, há indícios de que o Programa Bolsa Família reduza as horas trabalhadas de homens e mulheres. Para a jornada de trabalho doméstico, há indicativos de aumento de tempo de cuidado doméstico para mulheres e redução para homens. Os resultados da pesquisa sugerem que o programa reforçaria papéis tradicionais de gênero, não contribuindo para a individualização das mulheres pobres.

  19. 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.

  20. A eficácia das transferências de renda: as tendências da desigualdade antes e depois do Programa Bolsa Família

    Directory of Open Access Journals (Sweden)

    Carlos Rosano Peña

    2015-08-01

    Full Text Available Ao propor a utilização dos métodos cadeia de Markov e diferenças em diferenças na análise da eficácia do Programa Bolsa Família este trabalho buscou contribuir para o estado da arte na temática de estudos aplicados das políticas públicas de transferência de renda. Fez-se uso combinado desses métodos em dois períodos: antes da implantação do Programa e após sua implantação. Os resultados revelaram que, após a implantação do Bolsa Família, o "ciclo da pobreza" apresentou sinais de ruptura, devido a uma tendência de convergência para níveis de renda mais elevados e probabilidade de mitigar a pobreza nas classes de renda menos favorecidas da população brasileira. Assim, no longo prazo, vislumbra-se a possibilidade de alterar e combater a dinâmica do ciclo da pobreza e exclusão social.

  1. [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.

  2. 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.

  3. Causalidad del precio futuro de la Bolsa de Chicago sobre los precios físicos de maíz blanco en México

    Directory of Open Access Journals (Sweden)

    José Alberto Godínez Placencia

    2007-01-01

    Full Text Available Desde 1993 el gobierno federal mexicano, a través de Apoyos y Servicios a laComercialización Agropecuaria (ASERCA,ha estado utilizando los futuros y opciones de la Bolsa de Chicago de los Estados Unidos como instrumentos paracubrir el riesgo de movimientos adversosde los precios físicos al productor y almayoreo de maíz blanco. El objetivo delpresente trabajo es validar, para el casodel maíz blanco, la pertinencia de usar lascoberturas de los EEUUpara cubrir el riesgo de los precios físicos en México. El conjunto de procedimientos econométricos del vector auto regresivo (función impulso-respuesta, descomposición de la varianza y la causalidad de Granger rechaza la hipótesis de que el precio futuro delmaíz amarillo US #2 de la Bolsa deChicago mantiene una relación de causalidad sobre los precios físicos semanalesde maíz blanco en México para el periodo 1998-2005, por lo que la cobertura internacional no es pertinente.

  4. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

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

  5. SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Evans, D.J.R.; Downs, W.E.

    1974-01-01

    The SLOWPOKE reactor is described, which is a small pool type with thermal neutron fluxes ranging from 10 11 -10 12 n cm -2 sec -1 . It differs in many ways from conventional pool type, namely small critical mass, beryllium reflector and a closed reactor container. The reactor is designed as small and simply as possible, and consistently with safety and good operating practice. Access to the present model is via pneumatic irradiation tubes only, which limits the use of the facility to activation analysis, tracer production and training. (Mori, K.)

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

    The reactor core of nuclear reactors usually is composed of individual elongated fuel elements that may be vertically arranged and through which coolant flows in axial direction, preferably from bottom to top. With their lower end the fuel elements gear in an opening of a lower support grid forming part of the core structure. According to the invention a locking is provided there, part of which is a control element that is movable along the fuel element axis. The corresponding locking element is engaged behind a lateral projection in the opening of the support grid. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  7. O Programa Bolsa Família e os Pobres "Não Merecedores": poder discricionário e os limites da consolidação de direitos sociais

    NARCIS (Netherlands)

    Eiró de Oliveira, F.H.

    2017-01-01

    Sendo o maior programa de transferência condicionada de renda do mundo (em número absoluto de pessoas assistidas), o impacto do Programa Bolsa Família (PBF) vai além da redução de vulnerabilidades materiais. Em minhas pesquisas, constatei que o programa pode representar o único contato positivo das

  8. 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.

  9. Reactor Neutrinos

    Directory of Open Access Journals (Sweden)

    Soo-Bong Kim

    2013-01-01

    Full Text Available We review the status and the results of reactor neutrino experiments. Short-baseline experiments have provided the measurement of the reactor neutrino spectrum, and their interest has been recently revived by the discovery of the reactor antineutrino anomaly, a discrepancy between the reactor neutrino flux state of the art prediction and the measurements at baselines shorter than one kilometer. Middle and long-baseline oscillation experiments at Daya Bay, Double Chooz, and RENO provided very recently the most precise determination of the neutrino mixing angle θ13. This paper provides an overview of the upcoming experiments and of the projects under development, including the determination of the neutrino mass hierarchy and the possible use of neutrinos for society, for nonproliferation of nuclear materials, and geophysics.

  10. REACTOR SHIELD

    Science.gov (United States)

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  11. 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.

  12. Chemical Reactors.

    Science.gov (United States)

    Kenney, C. N.

    1980-01-01

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

  13. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

    This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

  14. Propulsion reactors

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    A nuclear reactor equips the recently constructed French aircraft- carrier Charles-De-Gaulle, in a few months the second nuclear submarine (SNLE) of new generation will be operational. In last october the government launched the program Barracuda which consists of 6 submarines (SNA) whose series head will be operational in 2010. The main asset of nuclear propulsion is to allow an almost unlimited autonomy: soft water, air are produced inside the submarine and the maximum time spent underwater is only limited by human capacity to cope with confinement. CEA has 3 missions concerning country defence. First the designing, the fabrication and the maintenance of weapons, secondly the supplying of fissile materials and thirdly the nuclear propulsion. A new generation of propulsion reactors is being studied and a ground installation involving a test reactor equivalent to that on board is being built. This test reactor (RES) will simulate any type of on-board reactors by adjusting temperature, pressure, flowrate and even equipment such as steam generator. This reactor will validate the technological choices for the Barracuda program. (A.C.)

  15. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

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

  16. Os efeitos do Programa Bolsa Família sobre a duração do emprego formal dos indivíduos de baixa renda

    OpenAIRE

    Santos, Danilo Braun; Leichsenring, Alexandre Ribeiro; Menezes Filho, Naercio; Mendes-Da-Silva, Wesley

    2017-01-01

    Resumo Neste artigo utilizamos microdados do Cadastro Único combinados com dados da Relação Anual de Informações Sociais (Rais) para examinar a duração do emprego entre indivíduos de famílias beneficiárias do Programa Bolsa Família. Para tanto, estimamos modelos de riscos proporcionais de Cox para comparar a duração no emprego entre beneficiários e não beneficiários do programa utilizando uma base de dados com mais de três milhões de indivíduos pertencentes a famílias de baixa renda. Os resul...

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

    Directory of Open Access Journals (Sweden)

    Michelle Costa Marques dos Santos

    2014-12-01

    Full Text Available 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 qualidade de vida da sua família. Contudo, observaram-se falhas na percepção de alguns objetivos do programa, principalmente relacionados com a emancipação sustentada das famílias.

  18. Corte de bolsa de sangue e medição de elasticidade de hemácias com laser infravermelho

    OpenAIRE

    MOURA, Diógenes Soares

    2016-01-01

    O presente trabalho explora a utilização de lasers na região do infravermelho do espectro eletromagnético em aplicações biomédicas. O uso dos lasers na indústria, para processamento de materiais e em aplicações médicas, como a realização de cirurgias, têm atraído grande interesse nas últimas décadas. Neste trabalho, laser infravermelho foi explorado no corte de bolsas de sangue e no desenvolvimento de sistema de avaliação de elasticidade de hemácias baseado em técnica de aprisionamento óptico...

  19. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1978-01-01

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given. (UK)

  20. Reactor utilization

    International Nuclear Information System (INIS)

    Zecevic, V.

    1963-01-01

    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

  1. Bioconversion reactor

    Science.gov (United States)

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  2. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Araki, Takao; Saito, Yasushi.

    1987-01-01

    Purpose: To reduce the seismic wave responsivity of an exhaust duct shields thereby preventing the release of tritium in an evacuating device due to failures upon earthquakes. Constitution: The ends on the cutting side of upper outer exhaust duct shields of a thermonuclear reactor are connected with a plurality of support beams. In a case where seismic vibrations are exerted to such a thermonuclear reactor, since the ends on the cutting side are coupled with the support beams, vibrations of the upper outer exhaust duct shields are greatly restricted. Thus, since there is no more such a possibility, for example, that an exhaust duct connected to the upper portion of a reactor main body is greatly distorted due to the seismic response of the upper outside exhaust duct shields to result in the failure of the connection portion with a vacuum pump, the release of tritium due to failure of the evacuating device can be prevented. (Yoshino, Y.)

  3. 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

  4. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

    An improved cover structure for liquid metal cooled fast breeder type reactors is described which it is claimed reduces the temperature differential across the intermediate grid plate of the core cover structure and thereby reduces its subjection to thermal stresses. (UK)

  5. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    The method of operating a water-cooled neutronic reactor having a graphite moderator is described which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40--60 volume percent of the mixture, in contact with the graphite moderator. 2 claims, 4 figures

  6. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

  7. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  8. Neutronic reactor

    International Nuclear Information System (INIS)

    Carleton, J.T.

    1977-01-01

    A graphite-moderated nuclear reactor includes channels between blocks of graphite and also includes spacer blocks between adjacent channeled blocks with an axis of extension normal to that of the axis of elongation of the channeled blocks to minimize changes in the physical properties of the graphite as a result of prolonged neutron bombardment. 3 claims, 6 figures

  9. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  10. O BOLSA FAMÍLIA NO BRASIL: problematizando a transferência de renda condicionada focalizada em famílias pobres no contexto da América Latina

    Directory of Open Access Journals (Sweden)

    Maria Ozanira da Silva e Silva

    2012-01-01

    Full Text Available The Bolsa Família, created in 2003, is a national targeting and conditional direct monetary transfer program to poor families. It is the major program in the Social Protection System in Brazil nowadays. It has been implemented in ali the 5,565 Brazilian municipalities and in the Federal District, since 2006. The program has as beneficiaries more than 12 million of families. It is discussed in this paper the following aspects: contextualization and characterization of the Bolsa Família; profile of the beneficiary families: who they are? how do they Iive? What do they do? As conclusion, it is presented preliminary reflection about some aspects as reference to develop comparison among the conditional direct monetary transfer programs in Latin America.

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    Gibbons, J.F.; McLaughlin, D.J.

    1978-01-01

    In the pressure vessel of the water-cooled nuclear reactor there is provided an internal flange on which the one- or two-part core barrel is hanging by means of an external flange. A cylinder is extending from the reactor vessel closure downwards to a seat on the core cupport structure and serves as compression element for the transmission of the clamping load from the closure head to the core barrel (upper guide structure). With the core barrel, subject to tensile stress, between the vessel internal flange and its seat on one hand and the compression of the cylinder resp. hold-down element between the closure head and the seat on the other a very strong, elastic sprung structure is obtained. (DG) [de

  12. Nuclear reactor

    International Nuclear Information System (INIS)

    Aleite, W.; Bock, H.W.; Struensee, S.

    1976-01-01

    The invention concerns the use of burnable poisons in a nuclear reactor, especially in PWRs, in order to improve the controllability of the reactor. An unsymmetrical arrangement in the lattice is provided, if necessary also by insertion of special rods for these additions. It is proposed to arrange the burnable poisons in fuel elements taken over from a previous burn-up cycle and to distribute them, going out from the side facing the control rods, over not more than 20% of the lenth of the fuel elements. It seems sufficient, for the burnable poisons to bind an initial reactivity of only 0.1% and to become ineffective after normal operation of 3 to 4 months. (ORU) [de

  13. Reactor container

    International Nuclear Information System (INIS)

    Otsuka, Hiroaki; Yoshida, Takashi.

    1979-01-01

    Purpose: To prevent rain water falling along the outer wall of the container during the construction work of an atomic power plant from making ingress into the inner part of a reactor container through a large size material carry-in port. Constitution: A weir for preventing the ingress of rain water is provided on the border between the foot floor of a large material carry-in port provided on the side surface at the bottom part of the reactor container and the floor surface of the building. This weir is of a semi-circular plate shape, and formed so that the lower semi-circular part of the carry-in port is tightly closed. (Kamimura, M.)

  14. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Saba, Kazuhisa.

    1979-01-01

    Purpose: To improve the earthquake resistance as well as reduce the size of a container for a nuclear reactor with no adverse effects on the decrease of impact shock to the container and shortening of construction step. Constitution: Reinforcing profile steel materials are welded longitudinally and transversely to the inner surface of a container, and inner steel plates are secured to the above profile steel materials while keeping a gap between the materials and the container. Reactor shielding wall planted to the base concrete of the container is mounted to the pressure vessel, and main steam pipeways secured by the transverse beams and led to the outside of container is connected. This can improve the rigidity earthquake strength and the safetiness against the increase in the inside pressure upon failures of the container. (Yoshino, Y.)

  15. Reactor container

    International Nuclear Information System (INIS)

    Oyamada, Osamu; Furukawa, Hideyasu; Uozumi, Hiroto.

    1979-01-01

    Purpose: To lower the position of an intermediate slab within a reactor container and fitting a heat insulating material to the inner wall of said intermediate slab, whereby a space for a control rod exchanging device and thermal stresses of the inner peripheral wall are lowered. Constitution: In the pedestal at the lower part of a reactor pressure vessel there is formed an intermediate slab at a position lower than diaphragm floor slab of the outer periphery of the pedestal thereby to secure a space for providing automatic exchanging device of a control rod driving device. Futhermore, a heat insulating material is fitted to the inner peripheral wall at the upper side of the intermediate slab part, and the temperature gradient in the wall thickness direction at the time of a piping rupture trouble is made gentle, and thermal stresses at the inner peripheral wall are lowered. (Sekiya, K.)

  16. 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.

  17. Neutronic reactor

    International Nuclear Information System (INIS)

    Lewis, W.R.

    1978-01-01

    Disclosed is a graphite-moderated, water-cooled nuclear reactor including a plurality of rectangular graphite blocks stacked in abutting relationship in layers, alternate layers having axes which are normal to one another, alternate rows of blocks in alternate layers being provided with a channel extending through the blocks, said channeled blocks being provided with concave sides and having smaller vertical dimensions than adjacent blocks in the same layer, there being nuclear fuel in the channels

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1979-01-01

    Purpose: To prevent cladding tube injuries due to thermal expansion of each of the pellets by successively extracting each of the control rods loaded in the reactor core from those having less number of notches, as well as facilitate the handling work for the control rods. Constitution: A recycle flow control device is provided to a circulation pump for forcibly circulating coolants in the reactor container and an operational device is provided for receiving each of the signals concerning number of notches for each of the control rods and flow control depending on the xenon poisoning effect obtained from the signals derived from the in-core instrument system connected to the reactor core. The operational device is connected with a control rod drive for moving each of the control rods up and down and a recycle flow control device. The operational device is set with a pattern for the aimed control rod power and the sequence of extraction. Upon extraction of the control rods, they are extracted successively from those having less notch numbers. (Moriyama, K.)

  19. Reactor building

    International Nuclear Information System (INIS)

    Ebata, Sakae.

    1990-01-01

    At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

  20. O Programa Institucional de Bolsas de Iniciação à Docência (PIBID e as relações público/privadas no ensino superior

    Directory of Open Access Journals (Sweden)

    Margarita Victoria Rodríguez

    2017-04-01

    Full Text Available O objeto deste trabalho é o Programa Institucional de Bolsas de Iniciação à Docência (PIBID, sendo seu objetivo analisar a regulamentação e a aprovação de bolsas e subprojetos do PIBID, sob a perspectiva da relação público/privada no ensino superior. Para tal, o procedimento metodológico utilizado foi a análise da legislação do Programa, bem como os dados disponibilizados nos relatórios do PIBID. Isto posto, é evidenciado que, embora pese o caráter neoliberal na organização do Programa, com relação à parceria público/privada, o maior volume de bolsas e projetos aprovados ainda estavam com o setor público, até 2013. Algumas tensões são apresentadas nessa perspectiva, mas elas também evidenciam a precarização do ensino superior privado e a característica assistencialista do programa.

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

    Directory of Open Access Journals (Sweden)

    Anne Caroline Costa Resende

    2008-01-01

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

  2. O Programa Bolsa Família a partir do território: O trabalho social com as famílias beneficiárias

    Directory of Open Access Journals (Sweden)

    Tatiana de Oliveira Stechi

    2013-12-01

    Full Text Available O presente artigo tem como objetivo apresentar algumas reflexões sobre o trabalho social com famílias beneficiárias do Programa Bolsa Família (PBF a partir do território, eixo estruturante da Política Nacional de Assistência Social (PNAS. Considerando a experiência prática bem como a atuação profissional, se faz necessário uma compreensão do trabalho social realizado com essas famílias enquanto possibilidade de uma intervenção qualificada nas necessidades e demandas apresentadas pelos beneficiários, tendo como parâmetro o aumento das políticas sociais de transferência de renda e o seu enfrentamento à pobreza.  Neste sentido, contextualiza o programa federal de transferência de renda, bem como discorre sobre seus objetivos e critérios. Logo em seguida o situa no trabalho desenvolvido pelos Centros de Referência de Assistência Social (CRAS, bem como as orientações dadas pela PNAS enquanto público prioritário das ações às famílias beneficiárias do programa. A partir das orientações dadas pelas legislações e teorias que direcionam a prática e atuação do assistente social com essas famílias é necessário que seja desenvolvido um trabalho em rede articulado com as demais políticas no território bem como de que as necessidades das famílias e intervenções profissionais considerem o local em que as famílias vivem.Palavras-chave: Programa Bolsa Família. Território. Família. Centro de Referência da Assistência Social. Proteção Social Básica.

  3. Nuclear research reactors

    International Nuclear Information System (INIS)

    1985-01-01

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

  4. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    Baeten, P.

    2006-01-01

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

  5. Photocatalytic reactor

    Science.gov (United States)

    Bischoff, Brian L.; Fain, Douglas E.; Stockdale, John A. D.

    1999-01-01

    A photocatalytic reactor for processing selected reactants from a fluid medium comprising at least one permeable photocatalytic membrane having a photocatalytic material. The material forms an area of chemically active sites when illuminated by light at selected wavelengths. When the fluid medium is passed through the illuminated membrane, the reactants are processed at these sites separating the processed fluid from the unprocessed fluid. A light source is provided and a light transmitting means, including an optical fiber, for transmitting light from the light source to the membrane.

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Anthony, A.J.; Gruber, E.A.

    1979-01-01

    A nuclear reactor with control rods in channels between fuel assemblies wherein the fuel assemblies incorporate guide rods which protrude outwardly into the control rod channels to prevent the control rods from engaging the fuel elements. The guide rods also extend back into the fuel assembly such that they are relatively rigid members. The guide rods are tied to the fuel assembly end or support plates and serve as structural members which are supported independently of the fuel element. Fuel element spacing and support means may be attached to the guide rods. 9 claims

  7. The impact of the Bolsa Família Program on food consumption: a comparative study of the southeast and northeast regions of Brazil.

    Science.gov (United States)

    Sperandio, Naiara; Rodrigues, Cristiana Tristão; Franceschini, Sylvia do Carmo Castro; Priore, Silvia Eloiza

    2017-06-01

    The aim of this study was to evaluate the impact of the Bolsa Família Program (PBF) on food consumption in the northeast and southeast regions of Brazil. The database was obtained from the individual food consumption module of the Household Budget Survey conducted in 2008-09. Consumption was assessed through two food records. The food was categorized into four groups: fresh or minimally processed food; culinary ingredients; processed food; and ultra-processed food. To analyze the impact, the propensity score matching method was used, which compares the individual recipients and non-recipients of the PBF in relation to a group of socioeconomic characteristics. After the propensity score was calculated, the impact of the PBF was estimated through the nearest-neighbor matching algorithm. In both regions, more than 60% of the daily total calories consumed by PBF recipients came from foods that had not undergone industrial processing. The recipients of PBF had a low level of consumption of processed and ultra-processed food in both regions, and an increased level of consumption of fresh or minimally processed food in the northeast. The results indicate the importance of adopting intersectoral policies in parallel to the PBF in order to strengthen healthy eating practices.

  8. 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.

  9. O Programa Bolsa Família e as condicionalidades de saúde: desafios da coordenação intergovernamental e intersetorial

    Directory of Open Access Journals (Sweden)

    Verena Duarte de Moraes

    Full Text Available RESUMO A existência de condicionalidades de saúde em programas de transferência de renda é controversa e exige coordenação entre áreas sociais. O objetivo do estudo foi discutir as condicionalidades de saúde do Programa Bolsa Família, considerando as diretrizes nacionais, as relações intergovernamentais e intersetoriais. Envolveu revisão bibliográfica, análise documental, análise de dados secundários e realização de 20 entrevistas. Observaram-se fragilidades nas relações entre esferas de governo e setores na gestão do programa. Não houve evidências de que a existência e o acompanhamento das condicionalidades da saúde per se contribuam para o direito à saúde e interrupção do ciclo de pobreza.

  10. 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.

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

    Directory of Open Access Journals (Sweden)

    Fábio Guilherme Campos

    2009-12-01

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

  12. The Impact of the Expansion of the Bolsa Família Program on the Time Allocation of Youths and Their Parents

    Directory of Open Access Journals (Sweden)

    Lia Chitolina

    2016-06-01

    Full Text Available This paper evaluates the impact of the expansion of the Bolsa Família program to families with youths aged 16 to 17 years on the time allocation of youths and on the labor supply of their parents. A differences-in-differences intention to treat estimator was used to compare poor households with 16-year-old youths with households with 15-year-old adolescents before and after the expansion. The results show that granting the benefit had a positive and significant impact on school enrollment and on the decision of young people to study and work at the same time. The results evince that the impact seems to be absent in urban areas but it is quite high for youths living in rural areas. When the sample is stratified by region, positive effects were found on young people's school enrollment especially in the Northeast (in both urban and rural areas and in the Southeast (only in the urban area. The econometric results also showed that the program hardly impacted the parents' labor supply decisions.

  13. 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.

  14. Perfil socioeconômico, nutricional e de ingestão alimentar de beneficiários do Programa Bolsa Família

    Directory of Open Access Journals (Sweden)

    Marcela Jardim Cabral

    2013-01-01

    Full Text Available Foram estudados beneficiários do Programa Bolsa Família de Maceió (AL e encontrada alta prevalência de desnutrição nas crianças (18% e adolescentes (20%; mas excesso de peso nos adultos (51%. As mulheres beneficiárias tiveram quatro vezes mais chance de ter obesidade abdominal em relação aos outros adultos. A maioria das famílias (92% apresentou Insegurança Alimentar (IA, sendo em 33% grave. Houve associação entre IA e maior número de pessoas na casa e desemprego. Entre as obesas houve aumento no consumo de alimentos ricos em carboidratos e lipídios em relação à outra população não beneficiária. Encontrou-se ingestão inadequada de cálcio, folato, vitamina E, magnésio, vitamina C, zinco, riboflavina, tiamina e fibra. Esses achados demonstram a necessidade de ações integradas entre políticas de educação/saúde e os programas de transferência de renda.

  15. Impacto do Programa “Bolsa Família” sobre a qualidade da dieta das famílias de Pernambuco no Brasil

    Directory of Open Access Journals (Sweden)

    Pedro Lima Coelho

    Full Text Available Resumo Este artigo analisa o impacto do Programa Bolsa Família (PBF sobre a qualidade da dieta dos domicílios do estado de Pernambuco utilizando dados da Pesquisa de Orçamento Familiar (POF-IBGE entre 2008-2009. O método Propensity Score Matching, que corrige o viés de seleção amostral, foi utilizado para realizar a comparação entre as famílias beneficiárias e as não beneficiárias do Programa. Os resultados mostram que o valor médio do Índice de Qualidade da Dieta (IQD para as famílias beneficiárias do Programa supera em 9,05 o valor médio do IQD das famílias não participantes do PBF. Os resultados corroboram a eficácia do PBF em elevar a qualidade da dieta das famílias, principalmente quanto à redução de gordura e sódio, e aumento da variedade.

  16. D and DR Reactors

    Data.gov (United States)

    Federal Laboratory Consortium — The world's second full-scale nuclear reactor was the D Reactor at Hanford which was built in the early 1940's and went operational in December of 1944.D Reactor ran...

  17. Reactor core fuel management

    International Nuclear Information System (INIS)

    Silvennoinen, P.

    1976-01-01

    The subject is covered in chapters, entitled: concepts of reactor physics; neutron diffusion; core heat transfer; reactivity; reactor operation; variables of core management; computer code modules; alternative reactor concepts; methods of optimization; general system aspects. (U.K.)

  18. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T [Huntington Beach, CA; Sahimi, Muhammad [Altadena, CA; Fayyaz-Najafi, Babak [Richmond, CA; Harale, Aadesh [Los Angeles, CA; Park, Byoung-Gi [Yeosu, KR; Liu, Paul K. T. [Lafayette Hill, PA

    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.

  19. Reactor container

    International Nuclear Information System (INIS)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-01-01

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.)

  20. Reactor container

    Energy Technology Data Exchange (ETDEWEB)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-09-07

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.).

  1. Reactor monitor

    International Nuclear Information System (INIS)

    Takada, Tamotsu.

    1992-01-01

    The device of the present invention monitors a reactor so that each of the operations for the relocation of fuel assemblies and the withdrawal and the insertion of control rods upon exchange of fuel assemblies and control rods in the reactor. That is, when an operator conducts relocating operation by way of a fuel assembly operation section, the device of the present invention judges whether the operation indication is adequate or not, based on the information of control rod arrangement in a control rod memory section. When the operation indication is wrong, a stop signal is sent to a fuel assembly relocating device. Further, when the operator conducts control rod operation by way of a control rod operation section, the device of the present invention judges in the control rod withdrawal judging section, as to whether the operation indication given by the operator is adequate or not by comparing it with fuel assembly arrangement information. When the operation indication is wrong, a stop signal is sent to control rod drives. With such procedures, increase of nuclear heating upon occurrence of erroneous operation can be prevented. (I.S.)

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    Schabert, H.P.; Weber, R.; Bauer, A.

    1975-01-01

    The refuelling of a PWR power reactor of about 1,200 MWe is performed by a transport pipe in the containment leading from an external to an internal fuel pit. A wagon to transport the fuel elements can go from a vertical loading position to an also vertical deloading position in the inner fuel pit via guide rollers. The necessary horizontal movement is effected by means of a cable line through the transport pipe which is inclined at least 10 0 . Gravity thus helps in the movement to the deloading position. The cable line with winch is fastened outside the containment. Swivelling devices tip the wagon from the horizontal to the vertical position or vice versa. Loading and deloading are done laterally. (TK/LH) [de

  3. NEUTRONIC REACTOR

    Science.gov (United States)

    McGarry, R.J.

    1958-04-22

    Fluid-cooled nuclear reactors of the type that utilize finned uranium fuel elements disposed in coolant channels in a moderater are described. The coolant channels are provided with removable bushings composed of a non- fissionable material. The interior walls of the bushings have a plurality of spaced, longtudinal ribs separated by grooves which receive the fins on the fuel elements. The lands between the grooves are spaced from the fuel elements to form flow passages, and the size of the now passages progressively decreases as the dlstance from the center of the core increases for the purpose of producing a greater cooling effect at the center to maintain a uniform temperature throughout the core.

  4. Nuclear reactor

    International Nuclear Information System (INIS)

    Schweiger, F.; Glahe, E.

    1976-01-01

    In a nuclear reactor of the kind which is charged with spherical reaction elements and in which control rods are arranged to be thrust directly into the charge, each control rod has at least one screw thread on its external surface so that as the rod is thrust into the charge it is caused to rotate and thus make penetration easier. The length of each control rod may have two distinct portions, a latter portion which carries a screw thread and a lead-in portion which is shorter than the latter portion and which may carry a thread of greater pitch than that on the latter portion or may have a number of axially extending ribs instead of a thread

  5. Nuclear reactor neutron shielding

    Science.gov (United States)

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

    2017-09-12

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

  6. Department of reactor technology

    International Nuclear Information System (INIS)

    1980-01-01

    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)

  7. Survey of research reactors

    International Nuclear Information System (INIS)

    Boek, H.; Villa, M.

    2004-06-01

    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)

  8. FBR type reactor

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  9. Aspectos teóricos das políticas de cidadania: uma aproximação ao Bolsa Família

    Directory of Open Access Journals (Sweden)

    Walquiria Leão Rego

    2008-01-01

    Full Text Available O artigo visa a três objetivos. O primeiro, destacar muito rapidamente a história recente das teorias dos direitos e da cidadania. O segundo é uma tentativa de compreender o sentido das tensões existentes nas relações entre o Estado e a sociedade civil, a participação política, o mercado e a justiça distributiva. Este conjunto problemático será examinado no âmbito mais amplo da questão democrática. Finalmente, estabelecer as conexões entre as bases normativas de algumas teorias da cidadania para construir o quadro conceitual de uma pesquisa em curso sobre a atual política de transferência de renda focada nas pessoas mais pobres, pelo Programa Bolsa Família cujo foco são as mulheres pobres.This article has three objectives. The first is to point out very briefly the recent history of the rights and citizenship theories. The second is an attempt to understand the meaning of the tensions between the State and civil society, and political participation, market and distributive justice. This problematic whole is seen from the wider range of the democratic question. Finally, the article sets out the connections between the normative basis of some citizenship theories in order to build up a framework for a research in course about the Brazilian government income program (the "Family Grant" whose focus is poor women.

  10. 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.

  11. 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.

  12. Estado nutricional dos beneficiários do Programa Bolsa Família no Brasil - uma revisão sistemática

    Directory of Open Access Journals (Sweden)

    Miriam Regina Wolf

    2014-05-01

    Full Text Available Diversos programas de combate à desnutrição foram implementados ao longo dos anos no Brasil. A partir de 2001 cabe ao Programa Bolsa Família (PBF esta responsabilidade. Apesar da expansão do PBF ainda são pouca as avaliações que aquilatam os avanços e os desafios a serem enfrentados, bem como os impactos nas condições de saúde e nutrição da população. Ainda que o acompanhamento do estado nutricional seja uma das condicionalidades para a manutenção do recebimento do benefício, quando se buscam estes dados, há uma grande dificuldade em obtê-los. O objetivo desta revisão sistemática é obter informações do estado nutricional dos beneficiários do PBF, para conhecer a realidade nacional no que diz respeito a esta situação, bem como avaliar se o programa causou impacto sobre o perfil nutricional da população atendida. Foi realizada uma busca através da Medline, Bireme, Scielo, Lilacs, Sistema de Bibliotecas Universitárias (SBU e ferramenta Google. A busca inclui artigos originais e teses de março 2002 até maio de 2012. Encontrou-se aproximadamente 100 trabalhos. Após a exclusão pelo título restaram 23 artigos e após a leitura dos resumos, ficaram 13. Os trabalhos revisados sugererem que o Programa não está modificando o estado nutricional dos beneficiários.

  13. 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.

  14. Novos instrumentos de coordenação federativa: reflexões a partir do Programa Bolsa Família

    Directory of Open Access Journals (Sweden)

    Renata Mirandola Bichir

    2016-08-01

    Full Text Available Um dos grandes desafios da gestão pública atual é garantir não somente o acesso da população às políticas sociais, mas também a qualidade dos serviços, benefícios e programas ofertados. Esse desafio ganha proporções ainda maiores no caso de políticas e programas sociais nacionais, inseridos em complexas teias de interrelações entre governo federal e unidades subnacionais. Garantir parâmetros nacionais mínimos de implementação de políticas e programas, reduzindo desigualdades nos resultados das políticas que derivam, inclusive, da grande heterogeneidade de capacidades institucionais locais para gestão dos mesmos –, é um dos objetivos de uma série de instrumentos de política pública que vem sendo desenvolvidos no âmbito dos sistemas nacionais de políticas sociais. Em diálogo com essa discussão mais ampla, esse artigo analisa dois instrumentos específicos de política pública, o Cadastro Único de Programas Sociais e o Índice de Gestão Descentralizada (IGD, e argumenta que estes são importantes mecanismos para compreender o processo de coordenação federativa e consolidação institucional do Programa Bolsa Família (PBF.

  15. Fast breeder reactors

    International Nuclear Information System (INIS)

    Heinzel, V.

    1975-01-01

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

  16. Determining Reactor Neutrino Flux

    OpenAIRE

    Cao, Jun

    2011-01-01

    Flux is an important source of uncertainties for a reactor neutrino experiment. It is determined from thermal power measurements, reactor core simulation, and knowledge of neutrino spectra of fuel isotopes. Past reactor neutrino experiments have determined the flux to (2-3)% precision. Precision measurements of mixing angle $\\theta_{13}$ by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understa...

  17. Nuclear reactor coolant channels

    International Nuclear Information System (INIS)

    Macbeth, R.V.

    1978-01-01

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

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Irion, L.; Tautz, J.; Ulrych, G.

    1976-01-01

    This additional patent complements the arrangement of non-return valves to prevent loss of cooling water on fracture of external tubes in the main coolant circuit (according to PS 24 24 427.7) by ensuring that the easily movable valves only operate in case of a fault, but do not flutter in operation, because the direction of flow is not the same at each location where they are installed. The remedy for this undesirable effect consists of allocating 1 non-return valve unit with 5 to 10 valves to each (of several) ducts for the cooling water intake. These units are installed in the annular space between the reactor vessel and the pressure vessel below the inlet of the ducts. Due to flow guidance surfaces in the same space, the incoming cooling water is deflected downwards and as the guiding surfaces are closed at the sides, must pass parallel to the valves of the non-return valve unit. On fracture of the external cooling water inlet pipe concerned, all valves of this unit close due to reversal of flow on the outlet side. (TK) [de

  19. Reactor container

    International Nuclear Information System (INIS)

    Kagawa, Tatsuo; Yanai, Ryoichi.

    1976-01-01

    Object: To provide a reactor container which is free from water shock action or condensing vibrations and cannot be readily broken by a missile from a pump impeller, pipe whipping, steam jet reaction, etc., and which also quickly condenses issuing steam and possesses a large vibration-proof strength. Structure: A high pressure containment vessel accommodating a pressure container includes a plurality of pressurized water tanks arranged along its inner periphery, and a pneumatic valve is provided in a lower portion of each of these pressurized water tanks. If an accident occurs, vapor is caused to issue from the pressure container into the vessel. When a certain value is reached, the pneumatic valves are opened, whereby the gas within the pressurized water tanks causes pressurized water to flow through the pipe and be ejected from spray nozzles to cause condensation of water within the vessel. Further, water of a pool within the container is circulated to allow heat release to the outside. (Horiuchi, T.)

  20. Educação Corporativa e Desenvolvimento Humano: análise do programa de bolsas de estudos para professores e funcionários de uma instituição de ensino superior do Distrito Federal

    OpenAIRE

    Fernanda Tavares Pacheco

    2012-01-01

    A presente pesquisa teve por objetivo analisar a visão que gestores e colaboradores têm em relação ao Programa de Bolsas de Estudo para Professores e Funcionários (PBPF), de uma Instituição de Ensino Superior (IES) privada do Distrito Federal. A amostra da pesquisa constituiu-se por docentes e funcionários beneficiados pelo PBPF. Para tal utilizou-se o paradigma qualitativo e estudo de caso, a coleta de dados realizou-se por meio de análise documental, entrevistas semi-estruturadas e question...

  1. 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

  2. Transferências de Renda Condicionada na América Latina e Bolsa Família no Brasil: uma discussão sobre desenvolvimentos da política social

    Directory of Open Access Journals (Sweden)

    Carolina Alves Vestena

    2016-12-01

    Full Text Available Resumo Nos últimos, transformações têm sido observadas no espectro político latino-americano, o que se reflete também na condução das políticas sociais na região. Exemplo disso, no caso brasileiro, são as recentes mudanças no programa Bolsa Família, uma das políticas mais reconhecidas internacionalmente neste âmbito. Nesse sentido, o presente artigo tem por objetivo apresentar uma análise do perfil do programa em sua elaboração e no interior do contexto latino-americano das políticas de transferência de renda. Assim, permite refletir sobre o paradigma de política social presente no continente e suas influências no modelo brasileiro. A partir de levantamento teórico sobre as políticas sociais na região e de dados empíricos sobre seus impactos, são destacadas as tendências de desenvolvimento observadas e discute-se o papel desempenhado pela política social hegemônica nos últimos anos no Brasil. Palavras-chaves: Bolsa Família, transferência de renda condicionada, América Latina, política social. *** Las Transferencias de Renta Condicionadas en América Latina y Bolsa Familia en Brasil: una discusión sobre los desarrollos de la política social Resumen En los últimos, se han observado cambios en el espectro político de América Latina, lo que se refleja también en la gestión de las políticas sociales en la región. Ejemplo, en Brasil, son los recientes cambios en el programa Bolsa Familia, una de las políticas más reconocidas internacionalmente en este ámbito. En este sentido, este artículo tiene por objetivo presentar un análisis del perfil del programa en su preparación y en el contexto latinoamericano de las políticas de transferencia de renta. Así, que permite reflexionar sobre el paradigma de la política social en el continente y sus influencias en el modelo brasileño. De la investigación teórica sobre las políticas sociales de la región y los datos empíricos sobre su impacto se ponen de

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

    Directory of Open Access Journals (Sweden)

    Vera Lúcia Conceição de Gouveia Santos

    2000-07-01

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

  4. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

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

  5. The fast breeder reactor

    International Nuclear Information System (INIS)

    Collier, J.

    1990-01-01

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

  6. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

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

  7. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

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

  8. Estado nutricional de população adulta beneficiária do Programa Bolsa Família no município de Curitiba, PR Nutritional Status of the adult population in the Bolsa Família Program in Curitiba, State of Paraná, Brazil

    Directory of Open Access Journals (Sweden)

    Flávia Emília Leite de Lima

    2011-06-01

    Full Text Available INTRODUÇÃO: O Programa Bolsa Família é o maior programa de transferência condicionada de renda do Brasil, e tem como um dos principais objetivos reverter o quadro atual de insegurança alimentar, porém ainda são escassos os estudos que mostram o estado nutricional de população dessa população. OBJETIVO: O presente trabalho teve como objetivo descrever o estado nutricional da população adulta inscrita no Programa Bolsa Família, no Município de Curitiba, PR. MÉTODOS: Trata-se de um estudo transversal, de base populacional, aplicado nos distritos sanitários do município de Curitiba, Paraná, no período de julho de 2006 a julho de 2007. Foram entrevistados 747 adultos a partir dos 18 anos de idade, de ambos os sexos, residentes nas áreas de abrangência das unidades básicas de saúde do município. Para avaliação do estado nutricional dessa população foram aferidos peso (kg, altura (cm e circunferência da cintura (cc, e calculado o índice de massa corpórea; foram questionados ainda quanto à idade, estado civil, ocupação, número de moradores no domicílio, procedência, escolaridade do entrevistado e do chefe da família. A associação entre excesso de peso, circunferência da cintura e as co-variáveis sociodemográficas foi avaliada por meio da técnica de regressão logística. RESULTADOS: Cerca de 40% da população foi considerada eutrófica e 27,1% obesa, segundo padrões de IMC. Avaliando-se os dados de circunferência da cintura, 48,2% da população possuem medidas que denotam risco muito aumentado para o desenvolvimento de doenças cardiovasculares. Houve uma associação estatisticamente significativa entre o aumento do IMC e a idade (OR = 2,16; IC 95%: 1,57-2,96, sexo (OR = 0,57; IC 95%: 0,33-0,97 e estado marital(OR = 1,40; IC 95% : 1,03-1,88. Para a circunferência da cintura observou-se uma associação significativa apenas com a idade (OR = 2,93; IC 95%: 2,13-4,02 e o sexo. CONCLUSÃO: Grande parte dos

  9. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

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

  10. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

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

  11. 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.

  12. Política de assistência social no Brasil e Programa Bolsa Família: apontamentos críticos

    Directory of Open Access Journals (Sweden)

    Haidée de Caez-Pedroso- Rodrigues

    2015-06-01

    Full Text Available O presente artigo versa sobre a política de assistência social no Brasil. Tem como fundamento a teoria social crítica e traz como ponto de partida reflexões sobre a relação entre acumulação do capital e o surgimento da questão social. Considerando a formação social brasileira e a correlação de forças entre as classes sociais, buscamos apresentar historicamente como se constituíram os direitos sociais no país. No debate contemporâneo são analisadas as principais determinações sociais, políticas e econômicas que mediaram a implementação das políticas sociais na conjuntura de reformas neoliberais na década de 1990, quando passam a se destacar os programas de transferência de renda enquanto estratégias de combate à pobreza. Com o ingresso do Partido dos Trabalhadores à frente do governo federal, algumas mudanças ocorreram principalmente no âmbito da gestão da política de assistência social, mas ainda observamos permanecer o caráter liberal-conservador das políticas sociais, e em especial, às ações preconizadas no Programa Bolsa Família. Tais elementos apontam desafios para os dos profissionais que atuam na gestão e execução dessas políticas sociais que estão comprometidos com os interesses da classe trabalhadora, tanto no que se refere à sua formação quanto ao seu exercício profissional. 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

  13. EL PROGRAMA BOLSA DE FAMILIA: Las percepciones de los beneficiarios sobre la educación y el “futuro de sus hijos

    Directory of Open Access Journals (Sweden)

    Angélica Lima Da Silva

    2017-04-01

    Full Text Available O Programa Bolsa Família (PBF é um programa de transferência de renda condicionada do governo federal brasileiro destinado a famílias em situação de pobreza e extrema pobreza. Na área da educação, exige-se a frequência escolar mínima de 85% para crianças entre 6 e 15 anos e de 75% para jovens entre 16 e 17 anos. De acordo com os formuladores do programa, o cumprimento das condicionalidades seria um fator importante para romper com a chamada transmissão intergeracional da pobreza. O artigo analisa como a exigência de frequência escolar mínima para beneficiários do PBF, com idades entre 6 e 17 anos, é percebida pelas titulares do benefício residentes na região sul de Campinas, (São Paulo, Brasil. Para isso, foram realizadas vinte entrevistas semiestruturadas com beneficiárias do PBF com filhos matriculados em uma escola pública na região sul deste município. Os resultados mostram que a condicionalidade relacionada à educação é considerada positiva na percepção das beneficiárias, mas elas não acreditam que a frequência escolar seja fator decisivo para romper com a pobreza no futuro. Para as beneficiárias, não basta manter seus filhos na escola sem levarem consideração a qualidade do ensino que lhes é oferecido. Ao final, refletimos sobre os limites e possibilidades da exigência de frequência escolar mínima como fator de enfrentamento da pobreza, assim como desafios suscitados pela análise das falas das entrevistadas que classificam a educação como “defasada”, mas, mesmo assim, mantêm seus filhos na escola pública, uma vez que não podem arcar com os custos de uma educação privada.

  14. Research reactor instrumentation

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2001-02-01

    This is a textbook on research reactor instrumentation for training purposes, it gives a survey on research reactor instrumentation requirements and eight exercises covering the major aspects of this topic are presented. (author)

  15. Nuclear reactors; graphical symbols

    International Nuclear Information System (INIS)

    1987-11-01

    This standard contains graphical symbols that reveal the type of nuclear reactor and is used to design graphical and technical presentations. Distinguishing features for nuclear reactors are laid down in graphical symbols. (orig.) [de

  16. Hybrid plasmachemical reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lelevkin, V. M., E-mail: lelevkin44@mail.ru; Smirnova, Yu. G.; Tokarev, A. V. [Kyrgyz-Russian Slavic University (Kyrgyzstan)

    2015-04-15

    A hybrid plasmachemical reactor on the basis of a dielectric barrier discharge in a transformer is developed. The characteristics of the reactor as functions of the dielectric barrier discharge parameters are determined.

  17. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    Fribourg, Ch.

    2002-01-01

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

  18. Fusion reactor design studies

    International Nuclear Information System (INIS)

    Emmert, G.A.; Kulcinski, G.L.; Santarius, J.F.

    1990-01-01

    This report discusses the following topics on the ARIES tokamak: systems; plasma power balance; impurity control and fusion ash removal; fusion product ripple loss; energy conversion; reactor fueling; first wall design; shield design; reactor safety; and fuel cost and resources

  19. Reactor shutdown method

    International Nuclear Information System (INIS)

    Nishino, Yoshitaka; Sawa, Toshio; Matsumoto, Takayuki; Osumi, Katsumi; Usui, Naoshi.

    1991-01-01

    A device for injecting a hydrogen gas, a chelating agent or a reducing agent is disposed in a reactor water recycling system. Upon reactor shutdown, the hydrogen gas, the chelating agent or the reducing agent is injected to primary coolants. With such a procedure, radioactive ions formed by the dissolution of oxide layers at the surface of pipelines and equipments in a reactor water recycling system and a reactor water cleanup system are removed from the primary coolants by a reactor water cleanup device. Accordingly, since the dose rate at the surface of the pipelines can be reduced, the operator's radiation dose can be reduced upon periodical inspection for a power plant. Further, the inner pressure of the reactor is kept higher than the saturated steam pressure at the reactor water temperature to suppress boiling of the reactor water. This can suppress the peeling of cruds deposited to the surface of the fuel cladding tube. (I.N.)

  20. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  1. Reactor System Design

    International Nuclear Information System (INIS)

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

    2006-08-01

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

  2. Nuclear reactor shutdown system

    International Nuclear Information System (INIS)

    Mangus, J.D.; Cooper, M.H.

    1982-01-01

    An improved nuclear reactor shutdown system is described comprising a temperature sensitive device connected to control the electric power supply to a magnetic latch holding a body of a neutron absorbing material. The temperature sensitive device is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause deenergization of the magnetic latch to allow the body of neutron absorbing material to enter the reactor core. (author)

  3. PUSPATI TRIGA Reactor

    International Nuclear Information System (INIS)

    Masood, Z.

    2016-01-01

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

  4. Reactor power measuring device

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  5. Ulysse, mentor reactor

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  6. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    1993-11-01

    The results of nuclear fusion researches in JAERI are summarized. In this report, following themes are collected: the concept of fusion reactor (including ITER), fusion reactor safety, plasma confinement, fusion reactor equipment, and so on. Includes glossary. (J.P.N.)

  7. Refuelling nuclear reactors

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  8. The Jules Horowitz reactor

    International Nuclear Information System (INIS)

    2003-01-01

    The Jules Horowitz reactor is the future european reactor for irradiation. It will be used for materials and new fuels irradiation. Experiments for the safety and the validation of neutronics calculation will be also realized. This paper presents the design and the performance of the reactor and the schedule of the remaining design studies. (A.L.B.)

  9. Thorium fueled reactor

    Science.gov (United States)

    Sipaun, S.

    2017-01-01

    Current development in thorium fueled reactors shows that they can be designed to operate in the fast or thermal spectrum. The thorium/uranium fuel cycle converts fertile thorium-232 into fissile uranium-233, which fissions and releases energy. This paper analyses the characteristics of thorium fueled reactors and discusses the thermal reactor option. It is found that thorium fuel can be utilized in molten salt reactors through many configurations and designs. A balanced assessment on the feasibility of adopting one reactor technology versus another could lead to optimized benefits of having thorium resource.

  10. 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

  11. 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

  12. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1981-12-01

    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)

  13. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    2010-03-01

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

  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 power monitoring device

    International Nuclear Information System (INIS)

    Dogen, Ayumi; Ozawa, Michihiro.

    1983-01-01

    Purpose: To significantly improve the working efficiency of a nuclear reactor by reflecting the control rod history effect on thermal variants required for the monitoring of the reactor operation. Constitution: An incore power distribution calculation section reads the incore neutron fluxes detected by neutron detectors disposed in the reactor to calculate the incore power distribution. A burnup degree distribution calculation section calculates the burnup degree distribution in the reactor based on the thus calculated incore power distribution. A control rod history date store device supplied with the burnup degree distribution renews the stored control rod history data based on the present control rod pattern and the burnup degree distribution. Then, thermal variants of the nuclear reactor are calculated based on the thus renewed control rod history data. Since the control rod history effect is reflected on the thermal variants required for the monitoring of the reactor operation, the working efficiency of the nuclear reactor can be improved significantly. (Seki, T.)

  16. Reactor power control device

    International Nuclear Information System (INIS)

    Ishii, Yoshihiko; Arita, Setsuo; Miyamoto, Yoshiyuki; Fukazawa, Yukihisa; Ishii, Kazuhiko

    1998-01-01

    The present invention provides a reactor power control device capable of enhancing an operation efficiency while keeping high reliability and safety in a BWR type nuclear power plant. Namely, the device of the present invention comprises (1) a means for inputting a set value of a generator power and a set value of a reactor power, (2) a means for controlling the reactor power to either smaller one of the reactor power corresponding to the set value of the generator power and the set value of the reactor power. With such procedures, even if the nuclear power plant is set so as to operate it to make the reactor power 100%, when the generator power reaches the upper limit, the reactor power is controlled with a preference given to the upper limit value of the generator power. Accordingly, safety and reliability are not deteriorated. The operation efficiency of the plant can be improved. (I.S.)

  17. One piece reactor removal

    International Nuclear Information System (INIS)

    Chia, Wei-Min; Wang, Song-Feng

    1993-01-01

    The strategy of Taiwan Research Reactor Renewal plan is to remove the old reactor block with One Piece Reactor Removal (OPRR) method for installing a new research reactor in original building. In this paper, the engineering design of each transportation works including the work method, the major equipments, the design policy and design criteria is described and discussed. In addition, to ensure the reactor block is safety transported for storage and to guarantee the integrity of reactor base mat is maintained for new reactor, operation safety is drawn special attention, particularly under seismic condition, to warrant safe operation of OPRR. ALARA principle and Below Regulatory Concern (BRC) practice were also incorporated in the planning to minimize the collective dose and the total amount of radioactive wastes. All these activities are introduced in this paper. (J.P.N.)

  18. Programa Bolsa Família e segurança alimentar e nutricional no Brasil: revisão crítica da literatura The Bolsa Família cash transfer program and food and nutrition security in Brazil: a critical review of the literature

    Directory of Open Access Journals (Sweden)

    Rosângela Minardi Mitre Cotta

    2013-01-01

    Full Text Available OBJETIVO: Revisar criticamente os estudos que avaliaram os impactos do Programa Bolsa Família (PBF na promoção da segurança alimentar e nutricional no Brasil. MÉTODOS: Foram consultadas as bases de dados Biblioteca Cochrane, LILACS, Medline e SciELO, bem como os portais de organizações públicas. Foram selecionados os estudos que utilizaram dados primários e excluídos estudos baseados em dados secundários, artigos de revisão, estudos que não permitiram estabelecer uma associação entre PBF e segurança alimentar e nutricional, bem como os estudos que avaliaram a segurança do alimento no que se refere apenas à qualidade sanitária. RESULTADOS Foram selecionados 10 estudos, dos quais cinco concluíram que o PBF teve um impacto positivo na segurança alimentar e nutricional das famílias beneficiárias. Entretanto, três estudos constataram um aumento do consumo de alimentos de maior densidade calórica e baixo valor nutritivo. Essa mudança no hábito alimentar é um fator de risco para o desenvolvimento do sobrepeso, obesidade e das doenças crônicas não transmissíveis. CONCLUSÕES: A garantia de segurança alimentar e nutricional exige programas que contemplem tanto o combate à desnutrição quanto ao sobrepeso e à obesidade. Programas de distribuição de renda, como o PBF, podem contribuir mais efetivamente para o bem-estar nutricional dos beneficiários quando combinados com outros tipos de intervenções, como ações de promoção de alimentação saudável.OBJECTIVE: To critically review studies evaluating the impact of Bolsa Família (PBF, a federal cash transfer program, for food and nutrition security in Brazil. METHODS: The Cochrane Library, LILACS, Medline and SciELO databases were searched, as well as public organization websites. All studies based on primary data were selected. The following were excluded: studies using secondary data, review articles, studies that did now allow the establishment of associations

  19. A habitação como determinante social da saúde: percepções e condições de vida de famílias cadastradas no programa Bolsa Família Habitation as a social determinant of health: perceptions and conditions of families registered under the "Bolsa Família" program

    Directory of Open Access Journals (Sweden)

    Kelly Alves Magalhães

    2013-03-01

    Full Text Available Objetivou-se avaliar as condições de habitação e de saneamento de famílias cadastradas no Programa Bolsa Família (PBF, bem como analisar os significados dos sujeitos entrevistados sobre sua moradia. Trata-se de um estudo transversal, de abordagem quanti-qualitativa, realizado entre agosto e setembro de 2007, no município de Paula Candido, MG. Foram entrevistados 116 indivíduos cadastrados no programa, selecionados aleatoriamente, por meio de questionário semiestruturado. Os dados quantitativos foram analisados utilizando-se o software SPSS for Windows e os qualitativos, pela técnica de análise temática. Verificou-se que ambos os grupos - beneficiário e não beneficiário - enfrentam condições adversas que limitam sua inserção e emancipação social, como baixas escolaridade e qualificação para o trabalho; trabalho informal e mal remunerado; serviços ainda insuficientes de abastecimento e tratamento da água, além de esgotamento sanitário e coleta de lixo, especialmente entre as famílias residentes na zona rural. Quanto ao significado da moradia para os entrevistados, os relatos denotam o sonho por uma casa melhor e/ou a casa própria, a aquisição de bens e eletrodomésticos básicos que possam compor o espaço da habitação, espaço este que ultrapassa a dimensão física e material, configurando-se como lugar onde se estabelecem as relações e laços sociais entre a família e de acolhimento do outro. Faz-se necessária a articulação entre as ações e políticas públicas de saúde, habitação, meio ambiente e infraestrutura, bem como com os programas de combate à pobreza - como o PBF - , tendo em vista o conjunto de vulnerabilidades às quais estão submetidas as populações mais pobres.The objective of this study was to evaluate housing and sanitation conditions of families registered in the "Bolsa Família" Program (BFP, as well as to analyze the meaning of housing for the interviewees. It is a transversal

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

    Directory of Open Access Journals (Sweden)

    Jorginete de Jesus Damião Trevisani

    2012-06-01

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

  2. Avaliação de bolsas de produtividade em pesquisa do CNPq e medidas bibliométricas: correlações para todas as grandes áreas

    Directory of Open Access Journals (Sweden)

    Jacques Wainer

    Full Text Available Este trabalho estuda as correlações entre decisões tomadas no fim de 2009, sobre renovação ou não de bolsas de produtividade em pesquisa do CNPq e medidas bibliométricas. Para cada nível da bolsa e para cada subárea, calculamos a correlação da decisão em subir o pesquisador de nível, mantê-lo no nível original ou rebaixá-lo, com várias medidas bibliométricas, como produção total (artigos, conferências, livros e capítulos de livros, produção nos últimos 5 anos, produção indexada no Web of Science, citações recebidas por artigo, citações recebidas por artigo escrito nos últimos 5 anos, índice H, etc. Os dados de citações foram extraídos tanto do Google Scholar como do Web of Science. As correlações de cada subárea são agrupadas em cada uma das 8 grandes áreas do CNPq (Ciências Agrícolas, Ciências Biológicas, Ciências Exatas, Ciências Humanas, Ciências da Saúde, Ciências Sociais, Engenharia e Artes. Indicamos quais são as métricas bibliométricas com maior correlação, com as decisões do CNPq para cada nível e para cada uma das grandes áreas. Discutimos algumas grandes áreas nas quais parece haver uma maior coerência, através dos vários níveis da bolsa entre as métricas mais correlacionadas com as decisões.

  3. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

    The invention deals with disengaging the coupling of a reactor coolant pump of a nuclear reactor feeding pressurized coolant. The disengaging coupling has two parts joined by bolts, at least one of them containing a driving agent within a bore. This is provided with a speed-depending ignition device in such manner that, if the critical speed is reached, the driving charge is ignited and the coupling is disengaged by destroying the bolts. (UWI) [de

  4. Neutron fluxes in test reactors

    Energy Technology Data Exchange (ETDEWEB)

    Youinou, Gilles Jean-Michel [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-01-01

    Communicate the fact that high-power water-cooled test reactors such as the Advanced Test Reactor (ATR), the High Flux Isotope Reactor (HFIR) or the Jules Horowitz Reactor (JHR) cannot provide fast flux levels as high as sodium-cooled fast test reactors. The memo first presents some basics physics considerations about neutron fluxes in test reactors and then uses ATR, HFIR and JHR as an illustration of the performance of modern high-power water-cooled test reactors.

  5. Thai research reactor

    International Nuclear Information System (INIS)

    Aramrattana, M.

    1987-01-01

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

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

    Directory of Open Access Journals (Sweden)

    Giselle Lavinas Monnerat

    2007-12-01

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

  7. Hybrid reactors. [Fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Moir, R.W.

    1980-09-09

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

  8. 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...

  9. Multipurpose research reactors

    International Nuclear Information System (INIS)

    1988-01-01

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

  10. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Matsuura, Shojiro; Nakahara, Yasuaki; Takano, Hideki

    1982-09-01

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

  11. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1985-08-01

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

  12. Spectral shift reactor control method

    International Nuclear Information System (INIS)

    Impink, A.J. Jr.

    1981-01-01

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

  13. Análise da gestao educacional e inclusâo social mediante a concessâo de Bolsas de Estudo na Faculdade Salesiana Dom Bosco de Manaus

    OpenAIRE

    Ramos Ribeiro, Aparecida

    2011-01-01

    Trata-se de uma investigação sobre a tríade ensino superior, gestão educacional e inclusão social, a partir da análise do referencial teórico e da pesquisa de campo. A pesquisa teve como objetivo principal fazer uma análise sobre a gestão educacional e a inclusão social de estudantes com carência socioeconômica no Ensino Superior mediante a concessão de bolsas de Estudos. O campo de investigação foi uma Instituição de Ensino Superior, particular, confessional, filantrópica, em ...

  14. DIEZ AÑOS DEL PROGRAMA FEDERAL “BOLSA ATLETA”: UNA DESCRIPCIÓN DE LAS MODALIDADES PARALÍMPICAS (2005-2014 (versión traducida al español

    Directory of Open Access Journals (Sweden)

    Rafael Estevam Reis

    2016-05-01

    Full Text Available El presente artículo tiene como objetivo realizar una descripción del programa del gobierno federal denominado "Bolsa-Atleta". Las fuentes utilizadas en los análisis fueron las listas de los atletas incluidos, disponibles en el portal del Ministerio del Deporte; se delimitó el estudio a los años entre 2005 y 2014. De estas listas se utilizó para los análisis solamente la información referente a las modalidades Paralímpicas, para un total de 7815 becas concedidas. A manera de conclusión, la investigación señala que el programa "Beca-Atleta" le da prioridad a aquellos deportistas con un desempeño más elevado, a los de sexo masculino y a los de las regiones más desarrolladas económicamente.

  15. Trabalho e reprodução das famílias de trabalhadores beneficiários do Bolsa Família em Campos dos Goytacazes/RJ

    Directory of Open Access Journals (Sweden)

    Érica Vieira Almeida

    2015-02-01

    Full Text Available O artigo apresenta um perfil das famílias beneficiárias do Programa Bolsa Família em Campos dos Goytacazes e do seu processo de reprodução social. Ao contrário de muitas assertivas, a pesquisa reafirma a condição de trabalhador desses beneficiários, em sua maioria, precarizados, mal remunerados e superexplorados. A crise da economia açucareira no município mudou o perfil do mercado de trabalho, sobretudo para os trabalhadores empobrecidos. Atualmente a cana não aparece mais entre as principais ocupações desse segmento. Merece atenção o índice de famílias monoparentais femininas, um arranjo que reduz as estratégias defensivas à precarização e ao desemprego, e aumenta a dependência ao Programa.

  16. A FORMAÇÃO DO PROFESSOR DE MATEMÁTICA EM INTERFACE COM O PIBID – PROGRAMA INSTITUCIONAL DE BOLSA DE INICIAÇÃO À DOCÊNCIA: AS REPRESENTAÇÕES DE LICENCIANDOS E SUPERVISORES

    OpenAIRE

    PUCETTI, SILVANA

    2016-01-01

    A presente tese investiga o processo de formação inicial de professores de Matemática, tendo como referência discussões e análises aprofundadas sobre o percurso acerca desta formação no Brasil, sobre as políticas públicas de formação de professores de Matemática em interface com a crise das licenciaturas e, também, sobre as concepções e ações que embasam o PIBID – Programa Institucional de Bolsa de Iniciação à Docência e as representações das experiências com este Programa, de licenciandos e ...

  17. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The aim of this invention is the provision of improved seals for reactor vessels in which fuel assemblies are located together with inlets and outlets for the circulation of a coolant. The object is to provide a seal arrangement for the rotatable plugs of nuclear reactor closure heads which has good sealing capacities over a wide gap during operation of the reactor but which also permits uninhibited rotation of the plugs for maintenance. (U.K.)

  18. Power reactors operational diagnosis

    International Nuclear Information System (INIS)

    Dach, K.; Pecinka, L.

    1976-01-01

    The definition of reactor operational diagnostics is presented and the fundamental trends of research are determined. The possible sources of power reactor malfunctions, the methods of defect detection, the data evaluation and the analysis of the results are discussed in detail. In view of scarcity of a theoretical basis and of insufficient in-core instrumentation, operational diagnostics cannot be as yet incorporated in a computer-aided reactor control system. (author)

  19. Pressurised water reactor operation

    International Nuclear Information System (INIS)

    Birnie, S.; Lamonby, J.K.

    1987-01-01

    The operation of a pressurized water reactor (PWR) is described with respect to the procedure for a unit start-up. The systems details and numerical data are for a four loop PWR station of the design proposed for Sizewell-'B', United Kingdom. A description is given of: the initial conditions, filling the reactor coolant system (RCS), heat-up and pressurisation of the RCS, secondary system preparations, reactor start-up, and reactivity control at power. (UK)

  20. Reactor BR2

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

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

  1. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

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

  2. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    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)

  3. The replacement research reactor

    International Nuclear Information System (INIS)

    Cameron, R.

    1999-01-01

    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

  4. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1988-01-01

    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

  5. A condicionalidade de educação dos programas de transferência de renda: uma análise crítica do programa Bolsa Família

    Directory of Open Access Journals (Sweden)

    Bruna Cristina Neves Carnelossi

    2014-04-01

    Full Text Available http://dx.doi.org/10.5007/2175-795X.2014v32n1p285 O presente artigo analisa a relação de dependência entre educação e transferência de renda objetivada no Programa Bolsa Família, sobretudo entre sua proposta central de redução da pobreza e a contrapartida exigida na área da educação. A tese da eficácia de tal condicionalidade é posta aqui em questão, a partir do desenvolvimento de um esquema interpretativo que faz crítica aos reais limites da condicionalidade da educação quanto à sua contribuição no enfrentamento à pobreza no Brasil. A educação na execução do programa é investigada a partir da exposição teórica que questiona sua função e importância, enquanto instrumento capaz de intervir efetivamente no enfrentamento à pobreza. Entende-se que programas de transferência de renda atrelados à educação devem se fundamentar em uma proposta mais consistente sobre seu papel na contribuição do processo educativo das famílias beneficiárias do Programa Bolsa Família, portanto, sobre sua real influência no enfrentamento massivo da pobreza que acercam milhões de brasileiros.

  6. Evaluación de bolsa atmósfera modificada y concentraciones de anhídrido sulfuroso aplicadas sobre frutos de arándano alto (Vaccinium corymbosum L. cv. Emerald

    Directory of Open Access Journals (Sweden)

    Mario Rodríguez Beraud

    2015-01-01

    Full Text Available Con el objetivo de evaluar las técnicas de atmósfera modificada y aplicación de anhídrido sulfuroso sobre parámetros de calidad de postcosecha en frutos de arándanos (Vaccinium corymbosum L. cv. Emerald, se realizó un experimento de seis tratamientos, dados por la combinación de dos factores, atmósfera modificada (con y sin, y diferentes concentraciones de anhídrido sulfuroso (generadas por 0, 1 y 2 g de metabisulfito de sodio durante 7, 14, 21 y 28 días a 0 °C. Con la dosis de 2 g de metabisulfito de sodio en atmósfera modificada no se presentaron pudriciones, a diferencia del tratamiento testigo que presentó un 4,86% luego de 28 días de almacenaje. Los resultados indican que la incidencia de pudrición gris disminuyó significativamente (p ≤ 0,05 con anhídrido sulfuroso en bolsa atmósfera modificada, existiendo un efecto de interacción entre ambos factores, no obstante, el gas causó daños de blanqueamiento de frutos, el que correspondió a un 11,66% con una dosis de 2 g de metabisulfito de sodio, luego de 28 días de almacenaje. El uso de bolsa de atmósfera modificada redujo significativamente (p ≤ 0,05 la pérdida de peso por deshidratación (en promedio un 4% respecto a los tratamientos donde esta tecnología no fue utilizada. La concentración de sólidos solubles no fue influenciada por los tratamientos, manteniéndose entre 13 y 14%.

  7. New reactor concepts

    International Nuclear Information System (INIS)

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

    1998-11-01

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

  8. Remote Reactor Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Bernstein, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dazeley, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dobie, Doug [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Marleau, Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brennan, Jim [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gerling, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sumner, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sweany, Melinda [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-10-21

    The overall goal of the WATCHMAN project is to experimentally demonstrate the potential of water Cerenkov antineutrino detectors as a tool for remote monitoring of nuclear reactors. In particular, the project seeks to field a large prototype gadolinium-doped, water-based antineutrino detector to demonstrate sensitivity to a power reactor at ~10 kilometer standoff using a kiloton scale detector. The technology under development, when fully realized at large scale, could provide remote near-real-time information about reactor existence and operational status for small operating nuclear reactors out to distances of many hundreds of kilometers.

  9. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    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

  10. Multi purpose research reactor

    International Nuclear Information System (INIS)

    Raina, V.K.; Sasidharan, K.; Sengupta, Samiran; Singh, Tej

    2006-01-01

    At present Dhruva and Cirus reactors provide the majority of research reactor based facilities to cater to the various needs of a vast pool of researchers in the field of material sciences, physics, chemistry, bio sciences, research and development work for nuclear power plants and production of radio isotopes. With a view to further consolidate and expand the scope of research and development in nuclear and allied sciences, a new 20 MWt multi purpose research reactor is being designed. This paper describes some of the design features and safety aspects of this reactor

  11. Trench reactor: an overview

    International Nuclear Information System (INIS)

    Spinrad, B.I.; Rohach, A.F.; Razzaque, M.M.; Sankoorikal, J.T.; Schmidt, R.S.; Lofshult, J.; Ramin, T.; Sokmen, N.; Lin, L.C.

    1988-01-01

    Recent fast, sodium-cooled reactor designs reflect new conditions. In nuclear energy these conditions are (a) emphasis on maintainability and operability, (b) design for more transparent safety, and (c) a surplus of uranium and enrichment availability that eases concerns about light water reactor fueling costs. In utility practice the demand is for less capital exposure, short construction time, smaller new unit sizes, and low capital cost. The PRISM, SAFR, and integral fast reactor (IFR) concepts are responses to these conditions. Fast reactors will not soon be deployed commercially, so more radical designs can be considered. The trench reactor is the product of such thinking. Its concepts are intended as contributions to the literature, which may be picked up by one of the existing programs or used in a new experimental project. The trench reactor is a thin-slab, pool-type reactor operated at very low power density and- for sodium-modest temperature. The thin slab is repeated in the sodium tank and the reactor core. The low power density permits a longer than conventional core height and a large-diameter fuel pin. Control is by borated steel slabs that can be lowered between the core and lateral sodium reflector. Shutdown is by semaphore slabs that can be swung into place just outside the control slabs. The paper presents major characteristics of the trench reactor that have been changed since the last report

  12. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2002-01-01

    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. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  14. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Moir, R.W.

    1978-01-01

    We have carried out conceptual design studies 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 fission fuel for fission reactors. We have designed a large commercial hybrid based on standard mirror confinement, and also a small pilot plant hybrid. 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

  15. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    Frisch, E.; Andrews, H.N.

    1976-01-01

    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

  16. Reactor core monitor for nuclear reactor

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

    The device of the present invention provides a various information of a wide adaptability, such as a power distribution, to an operator by determining a reactor core performance of the reactor by a performance calculation with improved accuracy. That is, a calculation means determines a neutron flux distribution of the reactor and coolant temperature based on the neutron flux distribution. A measuring means measures a cooled temperature of a reactor core inlet and a temperature at the exit of a fuel assembly. The result of coolant temperature by the measuring means and the result of the calculation by the calculation means are compared. The result of the calculation for the neutron flux distribution obtained by the calculation means is corrected based on the result of the comparison. The calculation means introduces calculation at higher accuracy by adopting two-dimensional balance in the fuel assembly. Further, a more accurate three-dimensional neutron diffusion calculation model is introduced in an on-line computer. Then, the accuracy of the calculation for the neutron flux distribution, power distribution, temperature distribution, etc. is improved. In view of the above, adaptability of a reactor core monitor is widened. (I.S.)

  17. 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.

  18. RB Research nuclear reactor RB reactor, Annual report for 2000

    International Nuclear Information System (INIS)

    Milosevic, M.

    2000-12-01

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

  19. Technical specifications, Hanford production reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gilbert, W.D. [comp.

    1962-06-25

    These technical specifications are applicable to the eight operating production reactor facilities, B, C, D, DR, F, H, KE, and KW. Covered are operating and performance restrictions and administrative procedures. Areas covered by the operating and performance restrictions are reactivity, reactor control and safety elements, power level, temperature and heat flux, reactor fuel loadings, reactor coolant systems, reactor confinement, test facilities, code compliance, and reactor scram set points. Administrative procedures include process control procedures, training programs, audits and inspections, and reports and records.

  20. A nuclear power reactor

    International Nuclear Information System (INIS)

    Borrman, B.E.; Broden, P.; Lundin, N.

    1979-12-01

    The invention consists of shock absorbing support beams fastened to the underside of the reactor tank lid of a BWR type reactor, whose purpose is to provide support to the steam separator and dryer unit against accelerations due to earthquakes, without causing undue thermal stresses in the unit due to differential expansion. (J.I.W.)

  1. Reactor cost driving items

    International Nuclear Information System (INIS)

    Spears, W.R.

    1987-01-01

    Assuming that the design solutions presently perceived for NET can be extrapolated for use in a power reactor, and using costing experience with present day fusion experiments and with fission power plants, the major components of the cost of a tokamak fusion power reactor are described. The analysis shows the emphasis worth placing on various areas of plant design to reduce costs

  2. Reactor Materials Research

    International Nuclear Information System (INIS)

    Van Walle, E.

    2001-01-01

    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)

  3. CAREM 25 nuclear reactor

    International Nuclear Information System (INIS)

    Rossini, A.A.; Ordonez, J.P.; Rajoy, J.E.; Durione, C.

    1990-01-01

    This work describes the CAREM project reactor, its design philosophy, its main characteristics and its advantages with respect to similar reactors. The main objective is to use the nuclear energy at lower costs than those applied up to now. (Author) [es

  4. Molten salt reactor concept

    International Nuclear Information System (INIS)

    Sood, D.D.

    1980-01-01

    Molten salt reactor is an advanced breeder concept which is suited for the utilization of thorium for nuclear power production. This reactor is based on the use of solutions of uranium or plutonium fluorides in LiF-BeF 2 -ThF 4 as fuel. Unlike the conventional reactors, no external coolant is used in the reactor core and the fuel salt itself is circulated through heat exchangers to transfer the fission produced heat to a secondary salt (NaF-NaBF 4 ) for steam generation. A part of the fuel stream is continuously processed to isolate 233 Pa, so that it can decay to fissile 233 U without getting converted to 234 Pa, and for the removal of neutron absorbing fission products. This on-line processing scheme makes this reactor concept to achieve a breeding ratio of 1.07 which is the highest for any thermal breeder reactor. Experimental studies at the Bhabha Atomic Research Centre, Bombay, have established the use of plutonium as fuel for this reactor. This molten salt reactor concept is described and the work conducted at the Bhabha Atomic Research Centre is summarised. (auth.)

  5. International thermal reactor development

    International Nuclear Information System (INIS)

    Zebroski, E.L.

    1977-01-01

    The worldwide development of nuclear power plants is reviewed. Charts are presented which show the commitment to light-water reactor capacity construction with breakdown by region and country. Additional charts show the major nuclear research centers which have substantial scope in light water reactor development and extensive international activities

  6. The fusion reactor

    International Nuclear Information System (INIS)

    Brennan, M.H.

    1974-01-01

    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.)

  7. Advanced converter reactors

    International Nuclear Information System (INIS)

    Kasten, P.R.

    1979-01-01

    Advanced converter reactors (ACRs) of primary US interest are those which can be commercialized within about 20 years, and are: Advanced Light-Water Reactors, Spectral-Shift-Control Reactors, Heavy-Water Reactors (CANDU type), and High-Temperature Gas-Cooled Reactors. These reactors can operate on uranium, thorium, or uranium-thorium fuel cycles, but have the greatest fuel utilization on thorium type cycles. The water reactors tend to operate more economically on uranium cycles, while the HTGR is more economical on thorium cycles. Thus, the HTGR had the greatest practical potential for improving fuel utilization. If the US has 3.4 to 4 million tons U 3 O 8 at reasonable costs, ACRs can make important contributions to maintaining a high nuclear power level for many decades; further, they work well with fast breeder reactors in the long term under symbiotic fueling conditions. Primary nuclear data needs of ACRs are integral measurements of reactivity coefficients and resonance absorption integrals

  8. 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)

  9. Space Nuclear Reactor Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Poston, David Irvin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-03-06

    We needed to find a space reactor concept that could be attractive to NASA for flight and proven with a rapid turnaround, low-cost nuclear test. Heat-pipe-cooled reactors coupled to Stirling engines long identified as the easiest path to near-term, low-cost concept.

  10. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.; Lineberry, M.J.

    1990-01-01

    Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 5 refs., 3 figs

  11. Nuclear reactor instrumentation method

    International Nuclear Information System (INIS)

    Handa, Hiroyuki; Hayashi, Katsumi; Nemesawa, Shigeki; Nemoto, Yuji; Ohashi, Masahisa.

    1993-01-01

    The present invention can appropriately monitor the state of a reactor core in an FBR type reactor which has a system of storing spent fuel assemblies in a reactor container while reducing the weight and making the structure compact in the reactor. That is, a fuel assembly having a shield lacking portion in upper axial shields is disposed. The shield lacking portion defines neutrons' leaking path from the reactor core. The leakage of neutrons from the path is detected by a neutron monitor disposed just above the fuel assembly. With such a constitution, influence of neutrons from stored spent fuel assemblies disposed to the out side of the radial shields can be reduced by a shielding effect of the existent radial shields around the reactor core. Further, if a shield lacking portion is locally disposed in the region of the upper axial shields just below the neutron monitor, neutrons from the reactor core can be monitored while suppressing excessive neutron leakage. As a result, it is unnecessary to dispose shields on the outer side of the spent fuel assembly disposed in the reactor core. (I.S.)

  12. Reactor building for a nuclear reactor

    International Nuclear Information System (INIS)

    Haidlen, F.

    1976-01-01

    The invention concerns the improvement of the design of a liner, supported by a latticed steel girder structure and destined for guaranteeing a gastight closure for the plant compartments in the reactor building of a pressurized water reactor. It is intended to provide the steel girder structure on their top side with grates, being suited for walking upon, and to hang on their lower side diaphragms in modular construction as a liner. At the edges they may be sealed with bellows in order to avoid thermal stresses. The steel girder structure may at the same time serve as supports for parts of the steam pipe. (RW) [de

  13. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

    An improvement is proposed concerning the easier disengagement of the coupling at the reactor coolant pump for a nuclear reactor transporting a pressurized coolant. According to the invention the disengaging coupling consists of two parts separated by screws. At least one of the screws contains a propellent charge ananged within a bore and provided with a speed-dependent ignition device in such a way that by separation of the screws at overspeeds the coupling is disengaged. The sub-claims are concerned with the kind of ignition ot the propellent charge. (UWI) [de

  14. Mirror reactor surface study

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, A. L.; Damm, C. C.; Futch, A. H.; Hiskes, J. R.; Meisenheimer, R. G.; Moir, R. W.; Simonen, T. C.; Stallard, B. W.; Taylor, C. E.

    1976-09-01

    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.

  15. Iris reactor conceptual design

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  16. Reactor control device

    International Nuclear Information System (INIS)

    Fukami, Haruo; Morimoto, Yoshinori.

    1981-01-01

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

  17. Mirror reactor surface study

    International Nuclear Information System (INIS)

    Hunt, A.L.; Damm, C.C.; Futch, A.H.; Hiskes, J.R.; Meisenheimer, R.G.; Moir, R.W.; Simonen, T.C.; Stallard, B.W.; Taylor, C.E.

    1976-01-01

    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

  18. 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.

  19. Reactor power control device

    International Nuclear Information System (INIS)

    Kobayashi, Akira.

    1980-01-01

    Purpose: To prevent misoperation in a control system for the adjustment of core coolant flow rate, and the increase in the neutron flux density caused from the misoperation in BWR type reactors. Constitution: In a reactor power control system adapted to control the reactor power by the adjustment of core flow rate, average neutron flux signals of a reactor core, entire core flow rate signals and operation state signals for coolant recycling system are inputted to a microcomputer. The outputs from the computer are sent to a recycling MG set speed controller to control the reactor core flow rate. The computer calculates the change ratio with time in the average neutron flux signals, correlation between the average neutron flux signals and the entire core flow rate signals, change ratio with time in the operation state signals for the coolant recycling system and the like and judges the abnormality in the coolant recycling system based on the calculated results. (Ikeda, J.)

  20. Status of French reactors

    International Nuclear Information System (INIS)

    Ballagny, A.

    1997-01-01

    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 3 . The OSIRIS reactor has already been converted to LEU. It will use U 3 Si 2 as soon as its present stock of UO 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

  1. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1984-08-01

    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)

  2. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Hirota, Jitsuya; Asaoka, Takumi; Suzuki, Tomoo; Mitani, Hiroshi; Akino, Fujiyoshi

    1977-09-01

    Research activities in the Division of Reactor Engineering in fiscal 1976 are described. Works of the division concern mainly the development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and the development of Liquid Metal Fast Breeder Reactor in 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 activities of the Committee on Reactor Physics. (auth.)

  3. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1976-09-01

    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.)

  4. Mirror reactor studies

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  5. Multi-purpose reactor

    International Nuclear Information System (INIS)

    1991-05-01

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

  6. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    Hicks, D.

    1970-04-01

    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.

  7. Reactor scram device for FBR type reactor

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  8. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1993-09-01

    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)

  9. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    1990-09-01

    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)

  10. Reactor water sampling device

    International Nuclear Information System (INIS)

    Sakamaki, Kazuo.

    1992-01-01

    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.)

  11. Reactor safety protection system

    International Nuclear Information System (INIS)

    Nishi, Hiroshi; Yokoyama, Tsuguo.

    1989-01-01

    A plurality of neutron detectors are disposed around a reactor core and detection signals from optional two neutron detectors are inputted into a ratio calculation device. If the ratio between both of the neutron flux level signals exceeds a predetermined value, a reactor trip signal is generated from an alarm setting device. Further, detection signals from all of the neutron detection devices are inputted into an average calculation device and the reactor trip signal is generated also in a case where the average value exceeds a predetermined set value. That is, when the reactor core power is increased locally, the detection signal from the neutron detector nearer to the point of power increase is greater than the increase rate for the entire reactor core power, while the detection signal from the neutron detector remote from the point of power increase is smaller. Thus, the local power increase ratio in the FBR reactor core can be detected efficiently by calculating the ratio for the neutron flux level signals from two neutron detectors, thereby enabling to exactly recognize the local power increase rate in the reactor core. (N.H.)

  12. Reactor power control device

    International Nuclear Information System (INIS)

    Imaruoka, Hiromitsu.

    1994-01-01

    A high pressure water injection recycling system comprising injection pipelines of a high pressure water injection system and a flow rate control means in communication with a pool of a pressure control chamber is disposed to a feedwater system of a BWR type reactor. In addition, the flow rate control means is controlled by a power control device comprising a scram impossible transient event judging section, a required injection flow rate calculation section for high pressure water injection system and a control signal calculation section. Feed water flow rate to be supplied to the reactor is controlled upon occurrence of a scram impossible transient event of the reactor. The scram impossible transient event is judged based on reactor output signals and scram operation demand signals and injection flow rate is calculated based on a predetermined reactor water level, and condensate storage tank water or pressure control chamber pool water is injected to the reactor. With such procedures, water level can be ensured and power can be suppressed. Further, condensate storage tank water of low enthalpy is introduced to the pressure suppression chamber pool to directly control elevation of water temperature and ensure integrity of the pressure vessel and the reactor container. (N.H.)

  13. Nuclear reactor containing facility

    International Nuclear Information System (INIS)

    Hidaka, Masataka; Murase, Michio.

    1994-01-01

    In a reactor containing facility, a condensation means is disposed above the water level of a cooling water pool to condensate steams of the cooling water pool, and return the condensated water to the cooling water pool. Upon occurrence of a pipeline rupture accident, steams generated by after-heat of a reactor core are caused to flow into a bent tube, blown from the exit of the bent tube into a suppression pool and condensated in a suppression pool water, thereby suppressing the pressure in the reactor container. Cooling water in the cooling water pool is boiled by heat conduction due to the condensation of steams, then the steams are exhausted to the outside of the reactor container to remove the heat of the reactor container to the outside of the reactor. In addition, since cooling water is supplied to the cooling water pool quasi-permanently by gravity as a natural force, the reactor container can be cooled by the cooling water pool for a long period of time. Since the condensation means is constituted with a closed loop and interrupted from the outside, radioactive materials are never released to the outside. (N.H.)

  14. Reactor Safety Research Programs

    Energy Technology Data Exchange (ETDEWEB)

    Edler, S. K.

    1981-07-01

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  15. The integral fast reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1987-01-01

    On April 3rd, 1986, two demonstrations of the inherent capability of sodium-cooled fast reactors to survive unprotected loss of cooling accidents were carried out on the experimental sodium-cooled power reactor, EBR-II, on the Idaho site of Argonne National Laboratory. Transients potentially of the most serious kind, one an unprotected loss of flow, the other an unprotected loss of heat sink, both initiated from full power. In both cases the reactor quietly shut itself down, without damage of any kind. These tests were a part of the on-going development program at Argonne to develop an advanced reactor with significant new inherent safety characteristics. Called the integral fast reactor, or IFR, the basic thrust is to develop everything that is needed for a complete nuclear power system - reactor, closed fuel cycle, and waste processing - as a single optimized entity, and, for simplicity in concept, as an integral part of a single plant. The particular selection of reactor materials emphasizes inherent safety characteristics also makes possible a simplified close fuel cycle and waste process improvements. The paper describes the IFR concept, the inherent safety, tests, and status of IFR development today

  16. Water cooled nuclear reactors

    International Nuclear Information System (INIS)

    Donaldson, A.J.

    1989-01-01

    In order to reduce any loss of primary water coolant from around a reactor core of a water cooled nuclear reactor caused by any failure of a pressure vessel, an inner vessel is positioned within and spaced from the pressure vessel. The reactor core and main portion of the primary water coolant circuit and a heat exchanger are positioned within the inner vessel to maintain some primary water coolant around the reactor core and to allow residual decay heat to be removed from the reactor core by the heat exchanger. In the embodiment shown an aperture at the upper region of the inner vessel is dimensioned configured and arranged to prevent steam from a steam space of an integral pressurised water cooled nuclear reactor for a ship entering the main portion of the primary water coolant circuit in the inner vessel if the longitudinal axis of the nuclear reactor is displaced from its normal substantially vertical position to an abnormal position at an angle to the vertical direction. Shields are integral with the inner vessel. (author)

  17. 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.

  18. Reactor monitoring device

    International Nuclear Information System (INIS)

    Kono, Shigehiro.

    1996-01-01

    The device of the present invention monitors the stability of a power of a BWR type reactor by using each of recycling flow rates in addition to a reactor core flow rate to improve monitoring accuracy. Namely, a set value registering means is disposed for registering reactor core flow rate set values corresponding to the number of recycling flow rates not reaching a reference value for each of the recycling flow rates. A reactor flow rate take-out means judges whether each of the recycling flow rates reaches the reference value or not. The set values of the set value registering means are taken out based on the number of each of the recycling flow rate signals not reaching the reference values. The taken out set value and calculated reactor core flow rate value are compared by an abnormal alarm means. When calculated value is smaller than the set value, abnormality is informed. The accuracy for the monitoring is improved by monitoring the reactor power by using each of recycling flow rates in addition to the reactor core flow rate. (I.S.)

  19. Nuclear reactor control column

    International Nuclear Information System (INIS)

    Bachovchin, D.M.

    1982-01-01

    The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest crosssectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor

  20. The integral fast reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1987-01-01

    On April 3rd, 1986, two dramatic demonstrations of the inherent capability of sodium-cooled fast reactors to survive unprotected loss of cooling accidents were carried out on the experimental sodium-cooled power reactor, EBR-II, on the Idaho site of Argonne National Laboratory. Transients potentially of the most serious kind, one an unprotected loss of flow, the other an unprotected loss of heat sink, both initiated from full power. In both cases the reactor quietly shut itself down, without damage of any kind. These tests were a part of the on-going development program at Argonne to develop an advanced reactor with significant new inherent safety characteristics. Called the Integral Fast Reactor, or IFR, the basic thrust is to develop everything that is needed for a complete nuclear power system - reactor, closed fuel cycle, and waste processing - as a single optimized entity, and, for simplicity in concept, as an integral part of a single plant. The particular selection of reactor materials emphasizes inherent safety characteristics and also makes possible a simplified closed fuel cycle and waste process improvements

  1. Reactor container cooling device

    Energy Technology Data Exchange (ETDEWEB)

    Ando, Koji; Kinoshita, Shoichiro

    1995-11-10

    The device of the present invention efficiently lowers pressure and temperature in a reactor container upon occurrence of a severe accident in a BWR-type reactor and can cool the inside of the container for a long period of time. That is, (1) pipelines on the side of an exhaustion tower of a filter portion in a filter bent device of the reactor container are in communication with pipelines on the side of a steam inlet of a static container cooling device by way of horizontal pipelines, (2) a back flow check valve is disposed to horizontal pipelines, (3) a steam discharge valve for a pressure vessel is disposed closer to the reactor container than the joint portion between the pipelines on the side of the steam inlet and the horizontal pipelines. Upon occurrence of a severe accident, when the pressure vessel should be ruptured and steams containing aerosol in the reactor core should be filled in the reactor container, the inlet valve of the static container cooling device is closed. Steams are flown into the filter bent device of the reactor container, where the aerosols can be removed. (I.S.).

  2. Reactor safety device

    International Nuclear Information System (INIS)

    Okada, Yasumasa.

    1987-01-01

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

  3. Inherently safe reactors

    International Nuclear Information System (INIS)

    Maartensson, Anders

    1992-01-01

    A rethinking of nuclear reactor safety has created proposals for new designs based on inherent and passive safety principles. Diverging interpretations of these concepts can be found. This article reviews the key features of proposed advanced power reactors. An evaluation is made of the degree of inherent safety for four different designs: the AP-600, the PIUS, the MHTGR and the PRISM. The inherent hazards of today's most common reactor principles are used as reference for the evaluation. It is concluded that claims for the new designs being inherently, naturally or passively safe are not substantiated by experience. (author)

  4. Reactor safety assessment system

    International Nuclear Information System (INIS)

    Sebo, D.E.; Bray, M.A.; King, M.A.

    1987-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSA is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

  5. Fast breeder reactors

    International Nuclear Information System (INIS)

    1978-01-01

    The subject of this invention is a liquid metal cooled nuclear reactor construction in which a concrete pit is lagged to protect it from the heat radiated from the reactor in normal operation but in which the efficiency of the lagging is reduced in case of emergency to allow the excess heat generated by the reactor to be dissipated throughout the pit. The lagging is in two layers, the first covering the internal surface of the pit wall is impermeable to the liquid metal, whilst the second layer over the first is permeable [fr

  6. Reactor shutdown device

    International Nuclear Information System (INIS)

    Masuda, Hiroyuki.

    1983-01-01

    Purpose : To provide a reactor shutdown device suitable to the low temperature shutdown of a heavy water-moderated type nuclear reactor and capable of ensuring an adequate shutdown margin. Constitution : Xenon reactivity is calculated based on the detection signals for reactor neutrons, the temperature reactivity is calculated based on the temperature of the moderators and of the coolants and, further, poisons in the moderators are detected. Injection amount of the poisons is calculated based on the result of the calculation and the detection, and the calculated amount of poisons is injected into the moderators. (Kamimura, M.)

  7. Mirror machine reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Moir, R.W.

    1976-01-01

    Recent mirror reactor conceptual design studies are described. Considered in detail is the design of ''standard'' Yin-Yang fusion power reactors with classical and enhanced confinement. It is shown that to be economically competitive with estimates for other future energy sources, mirror reactors require a considerable increase in Q, or major design simplifications, or preferably both. These improvements may require a departure from the ''standard'' configuration. Two attractive possibilities, both of which would use much of the same physics and technology as the ''standard'' mirror, are the field reversed mirror and the end-stoppered mirror

  8. Reactor flux calculations

    Energy Technology Data Exchange (ETDEWEB)

    Lhuillier, D. [Commissariat à l' Énergie Atomique et aux Énergies Alternatives, Centre de Saclay, IRFU/SPhN, 91191 Gif-sur-Yvette (France)

    2013-02-15

    The status of the prediction of reactor anti-neutrino spectra is presented. The most accurate method is still the conversion of total β spectra of fissionning isotopes as measured at research reactors. Recent re-evaluations of the conversion process led to an increased predicted flux by few percent and were at the origin of the so-called reactor anomaly. The up to date predictions are presented with their main sources of error. Perspectives are given on the complementary ab-initio predictions and upcoming experimental cross-checks of the predicted spectrum shape.

  9. Reactor pressure tank

    International Nuclear Information System (INIS)

    Dorner, H.; Scholz, M.; Jungmann, A.

    1975-01-01

    In a reactor pressure tank for a nuclear reactor, self-locking hooks engage a steel ring disposed over the removable cover of the steel vessel. The hooks exert force upon the cover to maintain the cover in a closed position during operation of the reactor pressure tank. The force upon the removal cover is partly the result of the increasing temperature and thermal expansion of the steel vessel during operation. The steel vessel is surrounded by a reinforced-concrete tank. (U.S.)

  10. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-04-01

    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

  11. Reactor BR2: Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. A safety audit was conduced by the IAEA, the conclusions of which demonstrated the excellent performance of the plant in terms of operational safety. In 1999, the CALLISTO facility was extensively used for various programmes involving LWR pressure vessel materials, IASCC of LWR structural materials, fusion reactor materials and martensic steels for use in ADS systems. In 1999, BR2's commercial programmes were further developed

  12. Nuclear reactor theory

    International Nuclear Information System (INIS)

    Sekimoto, Hiroshi

    2007-09-01

    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.)

  13. Power reactor design trends

    International Nuclear Information System (INIS)

    Hogan, W.J.

    1985-01-01

    Cascade and Pulse Star represent new trends in ICF power reactor design that have emerged in the last few years. The most recent embodiments of these two concepts, and that of the HYLIFE design with which they will compare them, are shown. All three reactors depend upon protecting structural elements from neutrons, x rays and debris by injecting massive amounts of shielding material inside the reaction chamber. However, Cascade and Pulse Star introduce new ideas to improve the economics, safety, and environmental impact of ICF reactors. They also pose different development issues and thus represent technological alternatives to HYLIFE

  14. Reactor power control system

    International Nuclear Information System (INIS)

    Tomisawa, Teruaki.

    1981-01-01

    Purpose: To restore reactor-power condition in a minimum time after a termination of turbine bypass by reducing the throttling of the reactor power at the time of load-failure as low as possible. Constitution: The transient change of the internal pressure of condenser is continuously monitored. When a turbine is bypassed, a speed-control-command signal for a coolant recirculating pump is generated according as the internal pressure of the condenser. When the signal relating to the internal pressure of the condenser indicates insufficient power, a reactor-control-rod-drive signal is generated. (J.P.N.)

  15. Research reactor support

    International Nuclear Information System (INIS)

    2005-01-01

    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

  16. Reactors of the world

    International Nuclear Information System (INIS)

    1971-01-01

    Basic data relating to 127 power reactors in 15 countries which are expected to be in operation at the end of this year, with a total installed electrical generating capacity of 35 340.15 MW(e), and a listing of 361 research reactors in 46 countries are given in the 1971 edition of the IAEA handbook, Power and Research Reactors in Member States, which has just been published. This edition, the fourth, was prepared especially for the Fourth International Conference on the Peaceful Uses of Atomic Energy. (author)

  17. Elmo Bumpy Torus Reactor

    International Nuclear Information System (INIS)

    McAlees, D.G.; Uckan, N.A.; Lidsky, L.M.

    1976-01-01

    In the Elmo Bumpy Torus Reactor (EBTR) study the feasibility of achieving a fusion power plant based on the EBT confinement concept was evaluated. If the present understanding of the physics can be extrapolated to reactor scale devices the reactor could operate at high beta, high power density, and at steady state. The high aspect ratio of the device eases the accessibility, structural design and remote maintenance problems which are common to low aspect ratio machines. A version of the EBTR reference design described here could be constructed with only minor extrapolations in available technology

  18. Nuclear reactor safety system

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1983-01-01

    The invention provides a safety system for a nuclear reactor which uses a parallel combination of computer type look-up tables each of which receives data on a particular parameter (from transducers located in the reactor system) and each of which produces the functional counterpart of that particular parameter. The various functional counterparts are then added together to form a control signal for shutting down the reactor. The functional counterparts are developed by analysis of experimental thermal and hydraulic data, which are used to form expressions that define safe conditions

  19. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2001-01-01

    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

  20. First Algerian research reactor

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    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 [es

  1. Fast Breeder Reactor studies

    International Nuclear Information System (INIS)

    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

  2. NUCLEAR REACTOR FUEL SYSTEMS

    Science.gov (United States)

    Thamer, B.J.; Bidwell, R.M.; Hammond, R.P.

    1959-09-15

    Homogeneous reactor fuel solutions are reported which provide automatic recombination of radiolytic gases and exhibit large thermal expansion characteristics, thereby providing stability at high temperatures and enabling reactor operation without the necessity of apparatus to recombine gases formed by the radiolytic dissociation of water in the fuel and without the necessity of liquid fuel handling outside the reactor vessel except for recovery processes. The fuels consist of phosphoric acid and water solutions of enriched uranium, wherein the uranium is in either the hexavalent or tetravalent state.

  3. 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.

  4. Fusion reactor radioactive waste management

    International Nuclear Information System (INIS)

    Kaser, J.D.; Postma, A.K.; Bradley, D.J.

    1976-01-01

    Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and fission reactor wastes are comparable, the radionuclides in fusion reactor wastes are less hazardous and have shorter half-lives. Areas requiring further research are discussed

  5. Special lecture on nuclear reactor

    International Nuclear Information System (INIS)

    Jo, Nam Jin

    1993-08-01

    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.

  6. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1975-11-01

    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.)

  7. RA Reactor applications, Annex A

    International Nuclear Information System (INIS)

    Cupac, S.; Vukadin, Z.

    2000-01-01

    Full text: In 2000 Ra reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor [sr

  8. RA Reactor applications, Annex A

    International Nuclear Information System (INIS)

    Cupac, S.; Vukadin, Z.

    1998-01-01

    Full text: In 1998 Ra reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor [sr

  9. RA Reactor applications, Annex A

    International Nuclear Information System (INIS)

    Cupac, S.; Vukadin, Z.

    1996-01-01

    Full text: In 2000 Ra reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor [sr

  10. Nuclear reactor container

    International Nuclear Information System (INIS)

    Takahashi, Hiroyuki.

    1987-01-01

    Purpose: To improve the earthquake proofness and also increase the safety to a nuclear reactor container by preventing bucklings upon earthquake. Constitution: A device for absorbing the deformation exerted from nuclear reactor buildings is disposed to a suppression chamber constituting a reactor container. When a nclear power plant encounters earthquakes, the entire reactor buildings are shaken and deformations of buildings are transmitted by way of building shell walls to a container and the forcive deforming forces are absorbed in the deformation absorbing device. That is, bellows are formed at the base of the container, which are deformed by the deforming forces to absorb the forcive deforming amount to moderate the stresses resulted to the suppression chamber. Thus, the rigidity to the bending of the container can be reduced and allowable displacement to the bucklings can be increased to prevent the buckling, by which earthquake proofness is improved and the safety is increased. (Kamimura, M.)

  11. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1981-01-01

    An array of rods comprising zirconium alloy sheathed nuclear fuel pellets assembled to form a fuel element for a pressurised water reactor is claimed. The helium gas pressure within each rod differs substantially from that of its closest neighbours

  12. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1984-01-01

    The fuel elements for a pressurised water reactor comprise arrays of rods of zirconium alloy sheathed nuclear fuel pellets. The helium gas pressure within each rod differs substantially from that of its closest neighbours

  13. Nuclear reactor (1960)

    International Nuclear Information System (INIS)

    Maillard, M.L.

    1960-01-01

    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) [fr

  14. Backfitting of research reactors

    International Nuclear Information System (INIS)

    Delrue, R.; Noesen, T.

    1985-01-01

    The backfitting of research reactors covers a variety of activities. 1. Instrumentation and control: Control systems have developed rapidly and many reactor operators wish to replace obsolete equipment by new systems. 2. Pool liners: Some pools are lined internally with ceramic tiles. These may become pervious with time necessitating replacement, e.g. by a new stainless steel liner. 3. Heat removal system: Deficiencies can occur in one or more of the cooling system components. Upgrading may require modifications of the system such as addition of primary loops, introduction of deactivation tanks, pump replacement. Recent experience in such work has shown that renewal, backfitting and upgrading of an existing reactor is economically attractive since the related costs and delivery times are substantially lower than those required to install a new research reactor

  15. Ageing of research reactors

    International Nuclear Information System (INIS)

    Ciocanescu, M.

    2001-01-01

    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. Integrated nuclear reactor

    International Nuclear Information System (INIS)

    Pales, I.; Hasko, V.

    1984-01-01

    The reactor is provided with an integrated circuit of primary medium circulation with hydraulic pump drive. The pump drive which is a blade hydraulic facility is placed in the reactor vessel together with the pump. The primary medium flows through the core and enters the inter-tube space of the secondary circuit heat exchanger. The secondary circuit medium is supplied under the bottom tube plate with a supply pipe. From it the flow of secondary medium is directed to the blades of the hydraulic facility, e.g. the turbine. The turbine drives the pump which transports the primary medium to the reactor core. The secondary medium enters the heat exchanger tubes and through their walls receives the heat from the primary medium. This design reduces capital costs of the reactor and increases its safety. (E.S.)

  17. 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.

  18. Inertial thermonuclear reactors

    International Nuclear Information System (INIS)

    Madarame, Haruki; Oomura, Hiroshi; Nakamura, Norio.

    1984-01-01

    Purpose: To improve the durability of the first wall. Constitution: A reactor cavity for performing inertial thermofusion is defined within a vessel of a thermonuclear reactor, and the first wall of a tubular structure flowing coolants for taking out thermonuclear energy generated in the reactor cavity as the heat energy to the outside of the reactor is disposed, in which jet nozzles are disposed to the inside of the first wall that pulse-width jet coolants to form coolant membranes on the inner circumferential surface of the first wall to thereby surround the fire ball by the membrane of the coolants. Thus, the energy of the fire ball can be reduced by the membrane of the coolants, whereby the thermal loads and impact loads to the first wall can be moderated to substantially increase the working life and improve the safety of the first wall for which the greatest stress load is expected. (Yoshihara, H.)

  19. Reactor pressure vessel support

    International Nuclear Information System (INIS)

    Butti, J.P.

    1978-01-01

    A link and pin support system provides the primary vertical and lateral support for a nuclear reactor pressure vessel without restricting thermally induced radial and vertical expansion and contraction

  20. Pressure tube reactor

    International Nuclear Information System (INIS)

    Matsumoto, Tomoyuki; Fujino, Michihira.

    1980-01-01

    Purpose: To equalize heavy water flow distribution by providing a nozzle for externally injecting heavy water from a vibration preventive plate to the upper portion to feed the heavy water in a pressure tube reactor and swallowing up heavy water in a calandria tank to supply the heavy water to the reactor core above the vibration preventive plate. Constitution: A moderator injection nozzle is mounted on the inner wall of a calandria tank. Heavy water is externally injected above the vibration preventive plate, and heavy water in the calandria tank is swallowed up to supply the heavy water to the core reactor above the vibration preventive plate. Therefore, the heavy water flow distribution can be equalized over the entire reactor core, and the distribution of neutron absorber dissolved in the heavy water is equalized. (Yoshihara, H.)

  1. Nuclear reactor core catcher

    International Nuclear Information System (INIS)

    1977-01-01

    A nuclear reactor core catcher is described for containing debris resulting from an accident causing core meltdown and which incorporates a method of cooling the debris by the circulation of a liquid coolant. (U.K.)

  2. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1985-01-01

    During the past two years, scientists from Argonne have developed an advanced breeder reactor with a closed self contained fuel cycle. The Integral Fast Reactor (IFR) is a new reactor concept, adaptable to a variety of designs, that is based on a fuel cycle radically different from the CRBR line of breeder development. The essential features of the IFR are metal fuel, pool layout, and pyro- and electro-reprocessing in a facility integral with the reactor plant. The IFR shows promise to provide an inexhaustible, safe, economic, environmentally acceptable, and diversion resistant source of nuclear power. It shows potential for major improvement in all of the areas that have led to concern about nuclear power

  3. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2002-01-01

    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

  4. 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.

  5. 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.

  6. Reactor vessel sealing plug

    International Nuclear Information System (INIS)

    Dooley, R.A.

    1986-01-01

    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

  7. Small reactor operating mode

    International Nuclear Information System (INIS)

    Snell, V.G.

    1997-01-01

    There is a potential need for small reactors in the future for applications such as district heating, electricity production at remote sites, and desalination. Nuclear power can provide these at low cost and with insignificant pollution. The economies required by the small scale application, and/or the remote location, require a review of the size and location of the operating staff. Current concepts range all the way from reactors which are fully automatic, and need no local attention for days or weeks, to those with reduced local staff. In general the less dependent a reactor is on local human intervention, the greater its dependence on intrinsic safety features such as passive decay heat removal, low-stored energy and limited reactivity speed and depth in the control systems. A case study of the design and licensing of the SLOWPOKE Energy System heating reactor is presented. (author)

  8. 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).

  9. Pulsed fusion reactors

    International Nuclear Information System (INIS)

    1975-01-01

    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

  10. Pressurized water reactor systems

    International Nuclear Information System (INIS)

    Meyer, P.J.

    1975-01-01

    Design and mode of operation of the main PWR components are described: reactor core, pressure vessel and internals, cooling systems with pumps and steam generators, ancillary systems, and waste processing. (TK) [de

  11. K-Reactor readiness

    International Nuclear Information System (INIS)

    Rice, P.D.

    1991-01-01

    This document describes some of the more significant accomplishments in the reactor restart program and details the magnitude and extent of the work completed to bring K-Reactor to a state of restart readiness. The discussion of restart achievements is organized into the three major categories of personnel, programs, and plant. Also presented is information on the scope and extent of internal and external oversight of the efforts, as well as some details on the startup plan

  12. Polymeric Membrane Reactors

    OpenAIRE

    José M. Sousa; Luís M. Madeira; João C. Santos; Adélio Mendes

    2008-01-01

    The aim of this chapter is the study of membrane reactors with polymeric membranes, particularly catalytic polymeric membranes. After an introduction where the main advantages and disadvantages of the use of polymeric membranes are summarised, a review of the main areas where they have been applied, integrated in chemical reactors, is presented. This excludes the field of bio-membranes processes, which is analysed in a specific chapter of this book. Particular attention is then given to model...

  13. Alternative breeder reactor technologies

    International Nuclear Information System (INIS)

    Spinrad, B.I.

    1978-01-01

    The significance of employing breeder reactors to stretch the world resources of nuclear fuels is briefly discussed, and the various types of breeder concepts are described. General descriptions, advantages, and disadvantages of the liquid metal cooled fast breeder, gas cooled fast breeder, molten salt breeder, thermal breeders, and spectral-shift control reactors are presented. Aspects of safeguarding fissile material connected with breeder operation are examined. 31 references

  14. Reactor Neutron Sources

    International Nuclear Information System (INIS)

    Aksenov, V.L.

    1994-01-01

    The present status and the prospects for development of reactor neutron sources for neutron scattering research in the world are considered. The fields of application of neutron scattering relative to synchrotron radiation, the creation stages of reactors (steady state and pulsed) and their position in comparison with spallation neutron sources at present and in the foreseen future are discussed. (author). 15 refs.; 8 figs.; 3 tabs

  15. KS-150 reactor control

    International Nuclear Information System (INIS)

    Wagner, K.

    1974-01-01

    A thorough description is presented of the control and protection system of the Bohunice A-1 reactor. The system including auxiliary facilities was developed, manufactured and installed at the reactor by the SKODA Works, Plzen. The system parameters are listed and a brief account is also given of the development efforts and of the physical and power start-up of the A-1 nuclear power plant. (L.O.)

  16. The replacement research reactor

    International Nuclear Information System (INIS)

    Cameron, R.; Horlock, K.

    2001-01-01

    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

  17. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Butterfield, C.E.; Waite, E.

    1982-01-01

    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)

  18. OECD Halden reactor project

    International Nuclear Information System (INIS)

    1978-01-01

    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

  19. Generation IV reactors: economics

    International Nuclear Information System (INIS)

    Dupraz, B.; Bertel, E.

    2003-01-01

    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.)

  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. Regulations for RA reactor operation

    International Nuclear Information System (INIS)

    1980-09-01

    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 [sr

  2. Reactor of the XXI century

    International Nuclear Information System (INIS)

    Zhotabaev, Zh.R.; Solov'ev, Yu.A.

    2001-01-01

    The advantages of both molten salt reactors (MSR) and homogenous molten salt reactors (HMSR) are illuminated. It is noted that the MSR possess accident probability A=10 -6 1/reactor.years and the HMSR with integral configuration has A=10 -7 1/reactor.years. The methods for these reactors technological problems solution - tritium removal, salt melt circulation and capacity pick up - are discussed

  3. Licensing of nuclear reactor operators

    International Nuclear Information System (INIS)

    1979-09-01

    Recommendations are presented for the licensing of nuclear reactor operators in units licensed according to the legislation in effect. They apply to all physical persons designated by the Operating Organization of the nuclear reactor or reactors to execute any of the following functional activities: a) to manipulate the controls of a definite reactor b) to direct the authorized activities of the reactor operators licesed according to the present recommendations. (F.E.) [pt

  4. Reactor power measuring device

    International Nuclear Information System (INIS)

    Ichige, Masayuki; Ishige, Takanori.

    1997-01-01

    The present invention provides a device for measuring a power such as of a nuclear fission reactor or a thermonuclear reactor by utilizing a light emitting phenomenon by radiation rays of gases. Namely, a measuring vessel sealed with a gas scintillator is inserted to the inside of a reactor. The measuring vessel is optically connected to a photoelectric convertor. The photoelectric convertor is electrically connected with a signal processing device. With such a constitution, gases sealed in the measuring vessel are ionized by radiation rays released in proportion to the power of the reactor to cause scintillation emission. The light is converted into electric signals by the photoelectric convertor. Reactor power can be monitored by the signal processing device having the electric signals as an input. According to the present invention, since the gas scintillation detector is used, the device is simplified and time responsiveness can be improved. As a result, the function of the reactor power measuring device can be improved. (I.S.)

  5. Materials for fusion reactors

    International Nuclear Information System (INIS)

    Ehrlich, K.; Kaletta, D.

    1978-03-01

    The following report describes five papers which were given during the IMF seminar series summer 1977. The purpose of this series was to discuss especially the irradiation behaviour of materials intended for the first wall of future fusion reactors. The first paper deals with the basic understanding of plasma physics relating to the fusion reactor and presents the current state of art of fusion technology. The next two talks discuss the metals intended for the first wall and structural components of a fusion reactor. Since 14 MeV neutrons play an important part in the process of irradiation damage their role is discussed in detail. The question which machines are presently available to simulate irradiation damage under conditions similar to the ones found in a fusion reactor are investigated in the fourth talk which also presents the limitations of the different methods of simulation. In this context also discussed is the importance future intensive neutron sources and materials test reactors will have for this problem area. The closing paper has as a theme the review of the present status of research of metallic and non-metallic materials in view of the quite different requirements for different fusion systems; a closing topic is the world supply on rare materials required for fusion reactors. (orig) [de

  6. Fast breeder reactors

    International Nuclear Information System (INIS)

    Waltar, A.E.; Reynolds, A.B.

    1981-01-01

    This book describes the major design features of fast breeder reactors and the methods used for their design and analysis. The foremost objective of this book is to fulfill the need for a textbook on Fast Breeder Reactor (FBR) technology at the graduate level or the advanced undergraduate level. It is assumed that the reader has an introductory understanding of reactor theory, heat transfer, and fluid mechanics. The book is expected to be used most widely for a one-semester general course on fast breeder reactors, with the extent of material covered to vary according to the interest of the instructor. The book could also be used effectively for a two-quarter or a two-semester course. In addition, the book could serve as a text for a course on fast reactor safety since many topics other than those appearing in the safety chapters relate to FBR safety. Methodology in fast reactor design and analysis, together with physical descriptions of systems, is emphasized in this text more than numerical results. Analytical and design results continue to change with the ongoing evolution of FBR design whereas many design methods have remained fundamentally unchanged for a considerable time

  7. Nuclear reactors to come

    International Nuclear Information System (INIS)

    Lung, M.

    2002-01-01

    The demand for nuclear energy will continue to grow at least till 2050 because of mainly 6 reasons: 1) the steady increase of the world population, 2) China, India and Indonesia will reach higher social standard and their energy consumption will consequently grow, 3) fossil energy resources are dwindling, 4) coal will be little by little banned because of its major contribution to the emission of green house effect gas, 5) renewable energies need important technological jumps to be really efficient and to take the lead, and 6) fusion energy is not yet ready to take over. All these reasons draw a promising future for nuclear energy. Today 450 nuclear reactors are operating throughout the world producing 17% of the total electrical power demand. In order to benefit fully of this future, nuclear industry has to improve some characteristics of reactors: 1) a more efficient use of uranium (it means higher burnups), 2) a simplification and automation of reprocessing-recycling chain of processes, 3) efficient measures against proliferation and against any misuse for terrorist purposes, and 4) an enhancement of safety for the next generation of reactors. The characteristics of fast reactors and of high-temperature reactors will likely make these kinds of reactors the best tools for energy production in the second half of this century. (A.C.)

  8. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1988-01-01

    Purpose: To inhibit the lowering of the neutron moderation effect due to voids in the upper portion of the reactor core, thereby flatten the axial power distribution. Constitution: Although it has been proposed to enlarge the diameter at the upper portion of a water rod thereby increasing the moderator in the upper portion, since the water rod situates within the channel box, the increase in the capacity thereof is has certain limit. In the present invention, it is designed such that the volume of the region at the outside of the channel box for the fuel assembly to which non-boiling water in the non-boiling water region can enter is made greater in the upper portion than in the lower portion of the reactor core. Thus, if the moderator density in the upper portion of the reactor core should be decreased due to the generation of the voids, the neutron moderating effect in the upper portion of the reactor core is not lowered as compared with the lower portion of the reactor core and, accordingly, the axial power distribution can be flattening more as compared with that in the conventional nuclear reactors. (Takahashi, M.)

  9. Reactor operation method

    International Nuclear Information System (INIS)

    Osumi, Katsumi; Miki, Minoru.

    1979-01-01

    Purpose: To prevent stress corrosion cracks by decreasing the dissolved oxygen and hydrogen peroxide concentrations in the coolants within a reactor container upon transient operation such as at the start-up or shutdown of bwr type reactors. Method: After a condensate has been evacuated, deaeration operation is conducted while opening a main steam drain line, as well as a main steam separation valve and a by-pass valve in a turbine by-pass line connecting the main steam line and the condenser without by way of a turbine, and the reactor is started-up by the extraction of control rods after the concentration of dissolved oxygen in the cooling water within a pressure vessel has been decreased below a predetermined value. Nuclear heating is started after the reactor water has been increased to about 150 0 C by pump heating after the end of the deaeration operation for preventing the concentration of hydrogen peroxide and oxygen in the reactor water from temporarily increasing immediately after the start-up. The corrosive atmosphere in the reactor vessel can thus be moderated. (Horiuchi, T.)

  10. LMFBR type reactor

    International Nuclear Information System (INIS)

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

    1988-01-01

    Purpose: To flatten the power distribution while maintaining the flattening in the axial power distribution in LMFBR type reactors. Constitution: Main system control rods are divided into control rods used for the operation and starting rods used for the starting of the reactor, and the starting rods are disposed in the radial periphery of the reactor core, while the control rods are disposed to the inside of the starting rods. With such a constitution, adjusting rods can be disposed in the region where the radial power peaking is generated to facilitate the flattening of the power distribution even in such a design that the ratio of the number of control rods to that of fuel assemblies is relatively large. That is, in this reactor, the radial power peaking is reduced by about 10% as compared with the conventional reactor core. As a result, the maximum linear power density during operation is reduced by about 10% to increase the thermal margin of the reactor core. If the maximum linear power density is set identical, the number of the fuel assemblies can be decreased by about 10%, to thereby reduce the fuel production cost. (K.M.)

  11. OECD Halden reactor project

    International Nuclear Information System (INIS)

    1979-01-01

    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

  12. The reactor antineutrino anomalies

    Energy Technology Data Exchange (ETDEWEB)

    Haser, Julia; Buck, Christian; Lindner, Manfred [Max-Planck-Institut fuer Kernphysik, Heidelberg (Germany)

    2016-07-01

    Major discoveries were made in the past few years in the field of neutrino flavour oscillation. Nuclear reactors produce a clean and intense flux of electron antineutrinos and are thus an essential neutrino source for the determination of oscillation parameters. Most currently the reactor antineutrino experiments Double Chooz, Daya Bay and RENO have accomplished to measure θ{sub 13}, the smallest of the three-flavour mixing angles. In the course of these experiments two anomalies emerged: (1) the reanalysis of the reactor predictions revealed a deficit in experimentally observed antineutrino flux, known as the ''reactor antineutrino anomaly''. (2) The high precision of the latest generation of neutrino experiments resolved a spectral shape distortion relative to the expected energy spectra. Both puzzles are yet to be solved and triggered new experimental as well as theoretical studies, with the search for light sterile neutrinos as most popular explanation for the flux anomaly. This talk outlines the two reactor antineutrino anomalies. Discussing possible explanations for their occurrence, recent and upcoming efforts to solve the reactor puzzles are highlighted.

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

    Directory of Open Access Journals (Sweden)

    Flávia Biroli

    2010-06-01

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

  14. 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.

  15. The reactor Cabri

    International Nuclear Information System (INIS)

    Ailloud, J.; Millot, J.P.

    1964-01-01

    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 m 3 /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

  16. SM-2 reactor potentialities for investigation of fusion reactor materials

    International Nuclear Information System (INIS)

    Tsykanov, V.A.; Samsonov, B.V.; Markina, N.V.; Polyakov, Yu.N.; Sluzhaev, V.I.; Losev, N.P.; Lobanov, G.P.

    1981-01-01

    The possibility of utilization of the SM-2 type reactors for fusion reactor (FR) materials testing is discussed. The measuring and calculational results, while estimating irradiation conditions in the SM-2 reactor channels, are given. The basic characteristics, necessary for correct simulation of FR parameters in fission reactors such as neutron flux density, radiation damage in the shift per atom values, gas accumulation, are considered. The characteristics of existing and tested in the SM-2 reactor investigational methods for studying structural and isolation materials are given. The conclusion about the possibility of SM-2 reactor utilization for the FR materials testing is made [ru

  17. Materials for nuclear reactors

    International Nuclear Information System (INIS)

    Banerjee, S.; Kamath, H.S.

    2005-01-01

    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., UO 2 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 UO 2 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)

  18. Method of operating a reactor

    International Nuclear Information System (INIS)

    Oosumi, Katsumi; Yamamoto, Michiyoshi.

    1980-01-01

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

  19. Sodium-cooled nuclear reactors

    International Nuclear Information System (INIS)

    Berthoud, Georges; Ducros, Gerard; Feron, Damien; Guerin, Yannick; Latge, Christian; Limoge, Yves; Santarini, Gerard; Seiler, Jean-Marie; Vernaz, Etienne; Guidez, Joel; Andrieux, Catherine; Baque, Francois; Bonin, Bernard; Boullis, Bernard; Cabet, Celine; Carre, Frank; Dufour, Philippe; Gauche, Francois; Grouiller, Jean-Paul; Jeannot, Jean-Philippe; Le Flem, Marion; Le Coz, Pierre; Martin, Laurent; Masson, Michel; Mathonniere, Gilles; Nokhamzon, Jean-Guy; Pelletier, Michel; Rodriguez, Gilles; Saez, Manuel; Seran, Jean-Louis; Varaine, Frederic; Zaetta, Alain; Behar, Christophe; Provitina, Olivier; Lecomte, Michael; Forestier, Alain; Bender, Alexandra; Parisot, Jean-Francois; Finot, Pierre

    2014-01-01

    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

  20. BR2 Reactor: Introduction

    International Nuclear Information System (INIS)

    Moons, F.

    2007-01-01

    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 3 He, 6 Li 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

  1. 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.

  2. Contribuições do programa bolsa alfabetização na formação inicial do professor: o que evidenciam os relatos reflexivos produzidos por alunos de pedagogia

    Directory of Open Access Journals (Sweden)

    Ana Silvia Moço Aparicio

    2017-02-01

    Full Text Available No presente artigo, apresentamos e discutimos os resultados de uma pesquisa em que buscamos compreender o processo de formação docente de alunos de Pedagogia participantes do Programa Bolsa Alfabetização, implantado pelo governo do Estado de São Paulo. Como objeto de análise foram considerados os relatos reflexivos produzidos por esses alunos, a partir de suas observações e intervenções realizadas na sala de aula de alfabetização em que atuavam junto ao professor regente. Para as análises, adotamos como referenciais teórico-metodológicos as contribuições do Interacionismo Sociodiscursivo. Os resultados apontam que a inserção dos licenciandos no cotidiano da sala de aula, ao propiciar a familiarização desse futuro professor com o processo de ensino e aprendizagem na alfabetização nas diferentes situações didáticas que emergem nesse contexto, contribuem para a reconstrução do foco de observação pelos licenciandos e para a reelaboração de suas crenças e concepções de ensino e aprendizagem.

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

    Directory of Open Access Journals (Sweden)

    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.

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

    Directory of Open Access Journals (Sweden)

    Maurício Gregianin Testa

    2013-12-01

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

  5. Radiation detectors for reactors

    International Nuclear Information System (INIS)

    Balagi, V.

    2005-01-01

    Detection and measurement of radiation plays a vital role in nuclear reactors from the point of view of control and safety, personnel protection and process control applications. Various types of radiation are measured over a wide range of intensity. Consequently a variety of detectors find use in nuclear reactors. Some of these devices have been developed in Electronics Division. They include gas-filled detectors such as 10 B-lined proportional counters and chambers, fission detectors and BF 3 counters are used for the measurement of neutron flux both for reactor control and safety, process control as well as health physics instrumentation. In-core neutron flux instrumentation employs the use detectors such as miniature fission detectors and self-powered detectors. In this development effort, several indigenous materials, technologies and innovations have been employed to suit the specific requirement of nuclear reactor applications. This has particular significance in view of the fact that several new types of reactors such as P-4, PWR and AHWR critical facilities, FBTR, PFBR as well as the refurbishment of old units like CIRUS are being developed. The development work has sought to overcome some difficulties associated with the non-availability of isotopically enriched neutron-sensing materials, achieving all-welded construction etc. The present paper describes some of these innovations and performance results. (author)

  6. Reactors PMT backlog

    International Nuclear Information System (INIS)

    Olson, H.P.

    1986-01-01

    The overall backlog of action items within the Reactors Priority Maintenance Tracking Systems (PMT) is similar to that resulting from Reactor Incident Reports. At least 1000 open action items are being tracked (excluding procedure revisions); the exact number is not obvious because some items are being tracked in more than one tracking document. About 20 to 25% of the incomplete items are directly related to reactor safety. About 70% of these were initiated within the last two years. A few of the remaining 30% date back to the 1977-1980 time frame. The tracking systems that are in place serve particular needs but they are unconnected and do not provide a means to understand and manage the overall Reactors PMT backlog. Shortcomings are summarized. Several initiatives are in progress or planned by Reactors PMT to facilitate improved tracking of backlog items with computer software systems. Under consideration is the Integrated Living Schedule (ILS) approach to prioritize work items and schedule resources to manage the backlog in the most effective way. ILS systems are being used effectively by a number of nuclear power utilities. 6 refs., 6 figs., 1 tab

  7. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    Jaouen, C.; Beroux, P.

    2012-01-01

    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)

  8. Mirror reactor studies

    International Nuclear Information System (INIS)

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

    1976-01-01

    Design studies of a fusion mirror reactor, a fusion-fission mirror reactor, and two small mirror reactors are summarized. The fusion reactor uses 150-keV neutral-beam injectors based on the acceleration of negative ions. The injectors provide over 1 GW of continuous power at an efficiency greater than 80 percent. The fusion reactor has three-stage, modularized, Venetian blind, plasma direct converter with a predicted efficiency of 59 percent and a new concept for removal of the lune-shaped blanket: a crane is brought between the two halves of the Yin-Yang magnet, which are separated by a float. The design has desirable features such as steady-state operation, minimal impurity problems, and low first-wall thermal stress. The major disadvantage is low Q resulting in high recirculating power and hence high cost of electrical power. However, the direct capital cost per unit of gross electrical power is reasonable [$1000/kW(e)

  9. Reactor core control device

    International Nuclear Information System (INIS)

    Sano, Hiroki

    1998-01-01

    The present invention provides a reactor core control device, in which switching from a manual operation to an automatic operation, and the control for the parameter of an automatic operation device are facilitated. Namely, the hysteresis of the control for the operation parameter by an manual operation input means is stored. The hysteresis of the control for the operation parameter is collected. The state of the reactor core simulated by an operation control to which the collected operation parameters are manually inputted is determined as an input of the reactor core state to the automatic input means. The record of operation upon manual operation is stored as a hysteresis of control for the operation parameter, but the hysteresis information is not only the result of manual operation of the operation parameter. This is results of operation conducted by a skilled operator who judge the state of the reactor core to be optimum. Accordingly, it involves information relevant to the reactor core state. Then, it is considered that the optimum automatic operation is not deviated greatly from the manual operation. (I.S.)

  10. Reactor physics computations

    International Nuclear Information System (INIS)

    Shapiro, A.

    1977-01-01

    Those reactor-core calculations which provide the effective multiplication factor (or eigenvalue) and the stationary (or fundamental mode) neutron-flux distribution at selected times during the lifetime of the core are considered. The multiplication factor is required to establish the nuclear composition and configuration which satisfy criticality and control requirements. The steady-state flux distribution must be known to calculate reaction rates and power distributions which are needed for the thermal, mechanical and shielding design of the reactor, as well as for evaluating refueling requirements. The calculational methods and techniques used for evaluating the nuclear design information vary with the type of reactor and with the preferences and prejudices of the reactor-physics group responsible for the calculation. Additionally, new methods and techniques are continually being developed and made operational. This results in a rather large conglomeration of methods and computer codes which are available for reactor analysis. The author provides the basic calculational framework and discusses the more prominent techniques which have evolved. (Auth.)

  11. Nuclear reactor apparatus

    International Nuclear Information System (INIS)

    Braun, H.E.; Bonnet, H.P.

    1978-01-01

    The reactor and its containment, instead of being supported on a solid concrete pad, are supported on a truss formed of upper and lower reinforced horizontal plates and vertical walls integrated into a rigid structure. The plates and walls from chambers within which the auxiliary components of the reactor, such as valves, pumping equipment and various tanks, are disposed. Certain of the chambers are also access passages for personnel, pipe chases, valve chambers and the like. In particular the truss includes an annular chamber. This chamber is lined and sealed by a corrosion-resistant liner and contains coolant and serves as a refueling cooling storage tank. This tank is directly below the primary-coolant conductor loops which extend from the reactor above the upper plate. The upper plate includes a sump connected to the tank through which coolant flows into the tank in the event of the occurrence of a loss-of-coolant accident. The truss extends beyond the containment and has chambers in the extending annulus. Pumps for circulating the coolant between the refueling coolant storage tank and the reactor are provided in certain of these chambers. The pumps are connected to the reactor by relatively short coolant conductors. Access to these pumps is readily afforded through hatches in the extending annulus

  12. Reactor power control device

    International Nuclear Information System (INIS)

    Nishiyama, Hiroyuki.

    1991-01-01

    The device of the present invention prevents unnecessary automatic reactor shutdown, without increasing operator's burden by automatic insertion of selected control rods in case if a recycling pump in a BWR reaction should stop. That is, the device of the present invention comprises (1) a means for detecting that at least one recycling pump stops, (2) a means for judging region for inserting the selected control rods based on the reactor power and the recycling flowrate of driving water, and (3) a means for calculating a logic product of output signals sent from both of the means described above and outputting a selected control rod insertion signal. With such a constitution, if at least one recycling pump stops, the means (1) detects it. Further, the means (2) judges the regions for inserting the selected control rods. Then, the means (3) outputs a signal for inserting the selected control rods. As a result, since a group of control rods selected previously are inserted into the reactor rapidly, the reactor power is suppressed, to avoid the automatic reactor shutdown. (I.N.)

  13. Tandem mirror reactors

    International Nuclear Information System (INIS)

    Logan, B.G.; Barr, W.L.; Bender, D.J.

    1978-01-01

    We have made preliminary designs of tandem mirror fusion reactors burning D-T fuel and of fusion-fission (hybrid) tandem mirrors producing both fissile fuel and electricity. For the hybrid reactor, we find that by using stream-stabilized, 2XIIB-like plugs and by injecting 200-keV deuterium beams into a tritium-plasma target confined electrostatically in the solenoid (two-component operation), we obtain a useful Q (fusion power/injection power) near unity. The D-T tandem reactor parameters are optimized to obtain the minimum capital cost per kW(e) net. For $200/kW(e) of 1200-keV neutral beam injection power in the plugs and a solenoid cost of about $3 million per metre length, the optimum Q is near 5. To allow for more expensive injector costs, a higher D-T reactor Q of 10 is obtainable with either increased power output or decreased neutron wall loading. Fokker--Planck calculations show steady-state Q approximately 5 for D-D tandem reactors burning only deuterium fuel and its reaction products, with most of the charged-particle fusion power recovered in a direct converter

  14. Reactor shutdown device

    International Nuclear Information System (INIS)

    Matsumiya, Hirohito; Endo, Hiroshi; Tsuboi, Yasushi.

    1993-01-01

    The present invention concerns a reactor shutdown device capable of suppressing change of a core insertion amount relative to temperature change during normal operation and having a great extension amount due to thermal expansion and high mechanical strength. A control rod main body is contained vertically movably in a guide tube disposed in a reactor core. An extension member extends upward from the upper end of a control rod main body and suspends the control rod main body. A shrinkable member intervenes at a midway of the extension member and is made shrinkable. A temperature sensitive member contains coolants at the inside and surrounds the shrinkable member. Thus, if the temperature of external coolants rises abruptly, the shrinkable member is extended by thermal expansion of the coolants in the temperature sensitive member. Upon usual reactor startup, the coolants in the temperature sensitive member cause no substantial thermal expansion by temperature elevation from a cold shutdown temperature to a rated power operation temperature, and the shrinkable member maintains its original state, so that the control rod main body is not inserted into the reactor core. However, upon abrupt temperature elevation, the control rod main body is inserted into the reactor core. (I.S.)

  15. FBR type reactors

    International Nuclear Information System (INIS)

    Maemoto, Junko.

    1985-01-01

    Purpose: To moderate abrupt temperature change near the inner walls of a suspended body thereby prevent thermal shocks and thermal deformations to structural materials. Constitution: High temperature coolants during ordinary operation of the nuclear reactor flow from the reactor core through the flow holes of the suspended body and from the upper plenum into an intermediate heat exchanger. The temperature of the coolants is lowered with heat exchanging effect with secondary coolants in the heat exchange and the coolants are then flow through the lower plenum into the reactor core and heated again. Upon generation of reactor scram, the temperature of the coolants at the exit of the reactor core is reduced abruptly and the flow rate is lowered due to the pump coast down. However, mixing of the coolants in the suspended body is accelerated by the coolants at high temperature flowing out of the flow holes and the coolants at the low temperature flowing from the flow hole group, to reduce the temperature difference and moderate the stratification flow forming an abrupt temperature slope. (Yoshihara, H.)

  16. RB research reactor Safety Report

    International Nuclear Information System (INIS)

    Sotic, O.; Pesic, M.; Vranic, S.

    1979-04-01

    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

  17. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    Lu, Hong; Miller, D.W.

    1991-01-01

    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

  18. 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

    Directory of Open Access Journals (Sweden)

    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

  19. Reactor Structural Materials: Reactor Pressure Vessel Steels

    Energy Technology Data Exchange (ETDEWEB)

    Chaouadi, R

    2000-07-01

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

  20. Reactor Structural Materials: Reactor Pressure Vessel Steels

    International Nuclear Information System (INIS)

    Chaouadi, R.

    2000-01-01

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

  1. Reactor safety analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

    Risk assessments of nuclear installations require accurate safety and reliability analyses to estimate the consequences of accidental events and their probability of occurrence. The objective of the work performed in this field at the Belgian Nuclear Research Centre SCK-CEN is to develop expertise in probabilistic and deterministic reactor safety analysis. The four main activities of the research project on reactor safety analysis are: (1) the development of software for the reliable analysis of large systems; (2) the development of an expert system for the aid to diagnosis; (3) the development and the application of a probabilistic reactor-dynamics method, and (4) to participate in the international PHEBUS-FP programme for severe accidents. Progress in research during 1997 is described

  2. Reactor for exothermic reactions

    Science.gov (United States)

    Smith, L.A. Jr.; Hearn, D.; Jones, E.M. Jr.

    1993-03-02

    A liquid phase process is described for oligomerization of C[sub 4] and C[sub 5] isoolefins or the etherification thereof with C[sub 1] to C[sub 6] alcohols wherein the reactants are contacted in a reactor with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120 to 300 F. Wherein the improvement is the operation of the reactor at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the reactor is controlled.

  3. Refueling of nuclear reactors

    International Nuclear Information System (INIS)

    Meuschke, R.E.

    1987-01-01

    This patent describes the unrodded refueling of a nuclear reactor having fuel assemblies and upper internals with apparatus including a lifting rig and a lift plate. The upper internals of the reactor are secured to the lifting rig. A method is given of reinserting in the fuel assemblies of the reactor the rods which penetrate into the fuel assemblies, such as control rods and/or coolant-displacement rods. The penetrating rods are connected to drive rods, the drive rods and penetrating rods being suspended from the lift plate, the lift plate and the drive rods and penetrating rods suspended therefrom being supported on a removable support in an upper position on the lifting rig

  4. Nuclear reactor safety device

    Science.gov (United States)

    Hutter, Ernest

    1986-01-01

    A safety device is disclosed for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of an upward thermal excursion. Such safety device comprises a laminated helical ribbon configured as a tube-like helical coil having contiguous helical turns with slidably abutting edges. The helical coil is disclosed as a portion of a drive member connected axially to the control rod. The laminated ribbon is formed of outer and inner laminae. The material of the outer lamina has a greater thermal coefficient of expansion than the material of the inner lamina. In the event of an upward thermal excursion, the laminated helical coil curls inwardly to a smaller diameter. Such inward curling causes the total length of the helical coil to increase by a substantial increment, so that the control rod is axially repositioned by a corresponding amount to reduce the power output of the reactor.

  5. The nuclear reactor systems

    International Nuclear Information System (INIS)

    Bacher, P.

    2008-01-01

    This paper describes the various nuclear reactor systems, starting with the Generation II, then the present development of the Generation III and the stakes and challenges of the future Generation IV. Some have found appropriate to oppose reactor systems or generations one to another, especially by minimizing the enhancements of generation III compared to generation II or by expecting the earth from generation IV (meaning that generation III is already obsolete). In the first part of the document (chapter 2), some keys are given to the reader to develop its proper opinion. Chapter 3 describes more precisely the various reactor systems and generations. Chapter 4 discusses the large industrial manoeuvres around the generation III, and the last chapter gives some economical references, taking into account, for the various means of power generation, the impediments linked to climate protection

  6. Reactor control device

    International Nuclear Information System (INIS)

    Araki, Takao; Inoue, Toyokazu.

    1981-01-01

    Purpose: To protect the reactor floor by alleviating the shock imparted to the reactor floor by a dropped control rod when a wire rope accidentally breaks. Constitution: A control rod is hung by wire rope from a control rod drive, and shock absorbers are mounted at the upper and lower portions of the control rod. The outer diameter of the upper shock absorber is made larger than the inner diameter of a control rod inserting hole formed in the reactor core. If the control rod drops, the upper absorber is stopped at the upper tapered portion of the inserting hole. Thus, the dropping energy of the control rod can be sufficiently absorbed by the upper and lower shock absorbers. (Kamimura, M.)

  7. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-08-01

    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

  8. Nuclear reactor risk assessment

    International Nuclear Information System (INIS)

    Higson, D.J.

    1982-01-01

    Experience has shown that reactors can be operated safely. Accidents have occurred, but the probability of physical health detriment to members of the public has been negligible. Methods for the quantitative evaluation of the probabilities of serious accidents are described, and some results are quoted which show that the estimated frequency of harmful effects is small when compared with other risks already accepted by society. Attempts have been made to justify the acceptance of nuclear reactor risks by relating them to the benefits which are derived from reactor operation and comparing them quantitatively with the risks from alternative methods of deriving the same benefits. This approach takes no account of the perceptions which people have of risk

  9. Breazeale Reactor Modernization Program

    International Nuclear Information System (INIS)

    Davison, C. C.

    2003-01-01

    The Penn State Breazeale Nuclear Reactor is the longest operating licensed research reactor in the nation. The facility has played a key role in educating scientists, engineers and in providing facilities and services to researchers in many different disciplines. In order to remain a viable and effective research and educational institution, a multi-phase modernization project was proposed. Phase I was the replacement of the 25-year old reactor control and safety system along with associated wiring and hardware. This phase was fully funded by non-federal funds. Tasks identified in Phases II-V expand upon and complement the work done in Phase I to strategically implement state-of-the-art technologies focusing on identified national needs and priorities of the future

  10. Fusion reactor materials

    International Nuclear Information System (INIS)

    Rowcliffe, A.F.; Burn, G.L.; Knee', S.S.; Dowker, C.L.

    1994-02-01

    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

  11. 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.

  12. Utilization of research reactors

    International Nuclear Information System (INIS)

    1962-01-01

    About 200 research reactors are now in operation in different parts of the world, and at least 70 such facilities, which are in advanced stages of planning and construction, should be critical within the next two or three years. In the process of this development a multitude of problems are being encountered in formulating and carrying out programs for the proper utilization of these facilities, especially in countries which have just begun or are starting their atomic energy work. An opportunity for scientific personnel from different Member States to discuss research reactor problems was given at an international symposium on the Programing and Utilization of Research Reactors organized by the Agency almost immediately after the General Conference session. Two hundred scientists from 35 countries, as well as from the European Nuclear Energy Agency and EURATOM, attended the meeting which was held in Vienna from 16 to 21 October 1961

  13. Compact stellarators as reactors

    International Nuclear Information System (INIS)

    Lyon, J.F.; Valanju, P.; Zarnstorff, M.C.; Hirshman, S.; Spong, D.A.; Strickler, D.; Williamson, D.E.; Ware, A.

    2001-01-01

    Two types of compact stellarators are examined as reactors: two- and three-field-period (M=2 and 3) quasi-axisymmetric devices with volume-average =4-5% and M=2 and 3 quasi-poloidal devices with =10-15%. These low-aspect-ratio stellarator-tokamak hybrids differ from conventional stellarators in their use of the plasma-generated bootstrap current to supplement the poloidal field from external coils. Using the ARIES-AT model with B max =12T on the coils gives Compact Stellarator reactors with R=7.3-8.2m, a factor of 2-3 smaller R than other stellarator reactors for the same assumptions, and neutron wall loadings up to 3.7MWm -2 . (author)

  14. Reactor container facility

    International Nuclear Information System (INIS)

    Saito, Takashi; Nagasaka, Hideo.

    1990-01-01

    A dry-well pool for spontaneously circulating stored pool water and a suppression pool for flooding a pressure vessel by feeding water, when required, to a flooding gap by means of spontaneous falling upto the flooding position, thereby flooding the pressure vessel are contained at the inside of a reactor container. Thus, when loss of coolant accidents such as caused by main pipe rupture accidents should happen, pool water in the suppression pool is supplied to the flooding gap by spontaneously falling. Further, if the flooding water uprises exceeding a predetermined level, the flooding gap is in communication with the dry-well pool at the upper and the lower portions respectively. Accordingly, flooding water at high temperature heated by the after-heat of the reactor core is returned again into the flooding gap to cool the reactor core repeatedly. (T.M.)

  15. International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Blevins, J.D.; Stasko, R.R.

    1989-09-01

    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

  16. BWR type reactor system

    International Nuclear Information System (INIS)

    Morooka, Shin-ichi.

    1980-01-01

    Purpose: To reduce the internal structure in a reactor by rapidly and efficiently transferring heat generated in a reactor core out of the reactor and eliminating the danger of radiation exposure. Constitution: Steam generated in a pressure vessel is introduced into heat pipe group by inserting the heat pipe group into the steam dome of the pressure vessel. The introduced steam is condensed in the heat pipes to transfer the heat of the steam to the heat pipe group. The transferred heat is transmitted to a heat exchanger provided out of a containment vessel to generate steam to operate a turbine. Thus, it is not necessary to introduce the steam including radioactive substance externally and can remove only the heat so as to carry out the desired purpose. (Kamimura, M.)

  17. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-08-01

    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. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-01-01

    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

  19. Licensed operating reactors

    International Nuclear Information System (INIS)

    Hartfield, R.A.

    1990-03-01

    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

  20. Nuclear reactor containment device

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu.

    1980-01-01

    Purpose: To reduce the volume of a containment shell and decrease the size of a containment equipment for BWR type reactors by connecting the containment shell and a suppression pool with slanted vent tubes to thereby shorten the vent tubes. Constitution: A pressure vessel containing a reactor core is installed at the center of a building and a containment vessel for the nuclear reactor that contains the pressure vessel forms a cabin. To a building situated below the containment shell, is provided a suppression chamber in which cooling water is charged to form a suppression pool. The suppression pool is communicated with vent tubes that pass through the partition wall of the containment vessel. The vent tubes are slanted and their lower openings are immersed in coolants. Therefore, if accident is resulted and fluid at high temperature and high pressure is jetted from the pressure vessel, the jetting fluid is injected and condensated in the cooling water. (Moriyama, K.)

  1. 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.

  2. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Hoizumi, Atsushi.

    1986-01-01

    Purpose: To grasp the margin for the limit value of the power distribution peaking factor inside the reactor under operation by using the reactor power distribution monitor. Constitution: The monitor is composed of the 'constant' file, (to store in-reactor power distributions obtained from analysis), TIP and thermocouple, lateral output distribution calibrating apparatus, axial output distribution synthesizer and peaking factor synthesizer. The lateral output distribution calibrating apparatus is used to make calibration by comparing the power distribution obtained from the thermocouples to the power distribution obtained from the TIP, and then to provide the power distribution lateral peaking factors. The axial output distribution synthesizer provides the power distribution axial peaking factors in accordance with the signals from the out-pile neutron flux detector. These axial and lateral power peaking factors are synthesized with high precision in the three-dimensional format and can be monitored at any time. (Kamimura, M.)

  3. AREVA's nuclear reactors portfolio

    International Nuclear Information System (INIS)

    Marincic, A.

    2009-01-01

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

  4. Oscillatory flow chemical reactors

    Directory of Open Access Journals (Sweden)

    Slavnić Danijela S.

    2014-01-01

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

  5. Reactor Materials Research

    International Nuclear Information System (INIS)

    Van Walle, E.

    2002-01-01

    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. ARIES tokamak reactor study

    International Nuclear Information System (INIS)

    Steiner, D.; Embrechts, M.

    1990-07-01

    This is a status report on technical progress relative to the tasks identified for the fifth year of Grant No. FG02-85-ER52118. The ARIES tokamak reactor study is a multi-institutional effort to develop several visions of the tokamak as an attractive fusion reactor with enhanced economic, safety, and environmental features. The ARIES study is being coordinated by UCLA and involves a number of institutions, including RPI. The RPI group has been pursuing the following areas of research in the context of the ARIES-I design effort: MHD equilibrium and stability analyses; plasma-edge modeling and blanket materials issues. Progress in these areas is summarized herein

  7. Nuclear reactor core assembly

    International Nuclear Information System (INIS)

    Baxi, C.B.

    1978-01-01

    The object of the present invention is to provide a fast reactor core assembly design for use with a fluid coolant such as liquid sodium or carbon monoxide incorporating a method of increasing the percentage of coolant flow though the blanket elements relative to the total coolant flow through the blanket and fuel elements during shutdown conditions without using moving parts. It is claimed that deterioration due to reactor radiation or temperature conditions is avoided and ready modification or replacement is possible. (U.K.)

  8. Particle bed reactor modeling

    Science.gov (United States)

    Sapyta, Joe; Reid, Hank; Walton, Lew

    The topics are presented in viewgraph form and include the following: particle bed reactor (PBR) core cross section; PBR bleed cycle; fuel and moderator flow paths; PBR modeling requirements; characteristics of PBR and nuclear thermal propulsion (NTP) modeling; challenges for PBR and NTP modeling; thermal hydraulic computer codes; capabilities for PBR/reactor application; thermal/hydralic codes; limitations; physical correlations; comparison of predicted friction factor and experimental data; frit pressure drop testing; cold frit mask factor; decay heat flow rate; startup transient simulation; and philosophy of systems modeling.

  9. Advanced reactors: A retrospective

    International Nuclear Information System (INIS)

    Starr, C.

    1989-01-01

    The objectives for nuclear power have always emphasized competitive costs, reliability, and public safety. During its initial two decades, the nuclear reactor program was enthusiastically and generously supported by the public, government, and industry. In the subsequent decades this external support was substantially eroded by the growing public fears of catastrophic accidents, poor economic performance of many nuclear plants, regulatory constraints, and a plethora of engineering issues disclosed by plant operations. The technical and institutional histories are discussed with particular relevance to their influence on the framework for future development of the several proposed advance reactors

  10. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    Aspden, G.J.

    1980-01-01

    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)

  11. Reactor pressure vessel materials

    International Nuclear Information System (INIS)

    Suzuki, K.

    1998-01-01

    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

  12. Australia's new nuclear reactor

    International Nuclear Information System (INIS)

    Kemeny, L.

    2007-01-01

    On 19 and 20 April 2007, the Australian Nuclear Science and Technology Organisation (ANSTO) celebrated the recent commissioning of its new, world-class, OPAL (Open Pool Australian Lightwater) research reactor at the Lucas Heights. On the 19th, scientists, business leaders and academics were introduced to the reactor and its technical capacity for the manufacture of radiopharmaceuticals, its material science applications, its environmental services and its neutron scattering facilities for business applications. The formal OPAL opening function took place that evening and, on the 20th, Prime Minister John Howard visited ANSTO to be briefed about OPAL and to be shown the work being carried out at Lucas Heights

  13. Netherlands Interuniversity Reactor Institut

    International Nuclear Information System (INIS)

    1978-01-01

    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.)

  14. 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.

  15. Perspectives on reactor safety

    International Nuclear Information System (INIS)

    Haskin, F.E.

    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

  16. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2000-01-01

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

  17. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2000-07-01

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

  18. 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.

  19. Fast quench reactor method

    Science.gov (United States)

    Detering, B.A.; Donaldson, A.D.; Fincke, J.R.; Kong, P.C.; Berry, R.A.

    1999-08-10

    A fast quench reaction includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a means of rapidly expanding a reactant stream, such as a restrictive convergent-divergent nozzle at its outlet end. Metal halide reactants are injected into the reactor chamber. Reducing gas is added at different stages in the process to form a desired end product and prevent back reactions. The resulting heated gaseous stream is then rapidly cooled by expansion of the gaseous stream. 8 figs.

  20. Nuclear reactor pressure vessel

    International Nuclear Information System (INIS)

    McDonald, B.N.

    1976-01-01

    In nuclear power reactor systems which have a reactor core inside a pressure vessel, the feedwater inlet pipe and steam discharge nozzle usually require separate pressure vessel penetrations. This requirement involves a great deal of expensive high quality special machining, welding and weld joint testing. The invention overcomes most of these problems by nestling the feedwater inlet pipe inside the steam discharge nozzle. At the same time the individual heat exchanger modules are supported from the pressure vessel at the same location as the nested feedwater inlet pipe and steam discharge nozzle combination, thus eliminating the need to accomodate troublesome differential thermal expansion problems through special structures within the pressure vessel

  1. Computerized reactor monitor and control for research reactors

    International Nuclear Information System (INIS)

    Buerger, L.; Vegh, E.

    1981-09-01

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

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

    Directory of Open Access Journals (Sweden)

    Felipe J. HEVIA

    2011-06-01

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

    Relations between poor people and the government that creates the Programa Bolsa Familia at

  3. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-12-01

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

  4. The market for research reactors

    International Nuclear Information System (INIS)

    Roegler, H.J.

    1986-01-01

    The assay deals with some basic questions if there is an international market for research reactors at all, which influencing factors affect this market, and if research reactors have any effects on the future market for nuclear engineering. (UA) [de

  5. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Matsuura, S.; Nakahara, Y.; Takano, H.

    1983-09-01

    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)

  6. 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...

  7. Reactor operation safety information document

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

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

  8. Nuclear reactors for the future

    International Nuclear Information System (INIS)

    Vijayan, P.K.; Kamble, M.T.; Dulera, I.V.

    2013-01-01

    For the sustainable development of nuclear power plants with enhanced safety features, economic competitiveness, proliferation resistance and physical protection, several advanced reactor developments have been initiated world-wide. The major advanced reactor initiatives and the proposed advanced reactor concepts have been briefly reviewed along with their advantages and challenges. Various advanced reactor designs being pursued in India have also been briefly described in the paper. (author)

  9. Fusion reactor development: A review

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    This paper is a review of the current prospects for fusion reactor development based upon the present status in plasma physics research, fusion technology development and reactor conceptual design for the tokamak magnetic confinement concept. Recent advances in tokamak plasma research and fusion technology development are summarized. The direction and conclusions of tokamak reactor conceptual design are discussed. The status of alternate magnetic confinement concept research is reviewed briefly. A feasible timetable for the development of fusion reactors is presented

  10. Inertial confinement fusion reactor systems

    International Nuclear Information System (INIS)

    Frank, T.G.; Bohachevsky, I.O.; Pendergrass, J.H.

    1980-01-01

    A variety of reactor cavity concepts, drivers, and energy conversion mechanisms are being considered to realize commercial applications of ICF. Presented in this paper are: (1) a review of reactor concepts with estimates of practically achievable pulse repetition rates; (2) a survey of drivers with estimates of the requirements on reactor conditions imposed by beam propagation characteristics; and (3) an assessment of compatible driver-reactor combinations

  11. REACTOR FUEL ELEMENTS TESTING CONTAINER

    Science.gov (United States)

    Whitham, G.K.; Smith, R.R.

    1963-01-15

    This patent shows a method for detecting leaks in jacketed fuel elements. The element is placed in a sealed tank within a nuclear reactor, and, while the reactor operates, the element is sparged with gas. The gas is then led outside the reactor and monitored for radioactive Xe or Kr. (AEC)

  12. Engineering reactors for catalytic reactions

    Indian Academy of Sciences (India)

    ... improvements in reactor performance. In this article, application of recent (and not so recent) developments in engineering reactors for catalytic reactions is discussed. Some examples where performance enhancement was realized by catalyst design, appropriate choice of reactor, better injection and dispersion strategies ...

  13. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-04-01

    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

  14. Fast reactors: potential for power

    International Nuclear Information System (INIS)

    1983-02-01

    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.)

  15. Digital control of research reactors

    International Nuclear Information System (INIS)

    Crump, J.C. III.; Richards, W.J.; Heidel, C.C.

    1991-01-01

    Research reactors provide an important service for the nuclear industry. Developments and innovations used for research reactors can be later applied to larger power reactors. Their relatively inexpensive cost allows research reactors to be an excellent testing ground for the reactors of tomorrow. One area of current interest is digital control of research reactor systems. Digital control systems offer the benefits of implementation and superior system response over their analog counterparts. At McClellan Air Force Base in Sacramento, California, the Stationary Neutron Radiography System (SNRS) uses a 1,000-kW TRIGA reactor for neutron radiography and other nuclear research missions. The neutron radiography beams generated by the reactor are used to detect corrosion in aircraft structures. While the use of the reactor to inspect intact F-111 wings is in itself noteworthy, there is another area in which the facility has applied new technology: the instrumentation and control system (ICS). The ICS developed by General Atomics (GA) contains several new and significant items: (a) the ability to servocontrol on three rods, (b) the ability to produce a square wave, and (c) the use of a software configurator to tune parameters affected by the actual reactor core dynamics. These items will probably be present in most, if not all, future research reactors. They were developed with increased control and overall usefulness of the reactor in mind

  16. Reactor component automatic grapple

    International Nuclear Information System (INIS)

    Greenaway, P.R.

    1982-01-01

    A grapple for handling nuclear reactor components in a medium such as liquid sodium which, upon proper seating and alignment of the grapple with the component as sensed by a mechanical logic integral to the grapple, automatically seizes the component. The mechanical logic system also precludes seizure in the absence of proper seating and alignment. (author)

  17. LMFBR type reactor

    International Nuclear Information System (INIS)

    Kumaoka, Yoshio; Kawamura, Yutaka.

    1990-01-01

    A main vessel support skirt is supported by a base mat of reactor buildings and the base mat is supported by means of an earthquake-proof device on concretes of a lower raft disposed on ground rocks. The earthquake-proof device is constituted by alternately stacking, laminating and press-bonding thin steel plates together with thin rubber layers between an upper flange and a lower raft. Thus, for the horizontal seismic vibrations, the period of the swinging in the horizontal direction of the buildings is made greater than the swinging period of earthquakes by the earthquake-proof device to reduce the impact shocks of earthquakes. Further, for the vertical seismic vibrations, the input seismic movements are not amplified during transmission from the base mat of the buildings to the reactor structure by way of the support skirt of the main vessel, due to the shortened load transmission path and the seismic power design to the reactor structure can be moderated sufficiently. A safety LMFBR type reactor with reduced construction cost and improved reliability can be attained. (N.H.)

  18. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    Baddley, A.H.

    1981-01-01

    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.)

  19. The reactor vessel steels

    International Nuclear Information System (INIS)

    Bilous, W.; Hajewska, E.; Szteke, W.; Przyborska, M.; Wasiak, J.; Wieczorkowski, M.

    2005-01-01

    In the paper the fundamental steels using in the construction of pressure vessel water reactor are discussed. The properties of these steels as well as the influence of neutron irradiation on its degradation in the time of exploitation are also done. (authors)

  20. 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.

  1. Thermal Reactor Safety

    International Nuclear Information System (INIS)

    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

  2. Hydrodynamic Cavitation Reactors contd…

    Indian Academy of Sciences (India)

    First page Back Continue Last page Overview Graphics. Hydrodynamic Cavitation Reactors contd… Reservoir: 10 L capacity. Centrifugal Pump :1.5kW). Orifice plate (different configurations in terms of number and diameter of the holes). Bypass line (for controlling the inlet pressure and the flow rate into the cavitation ...

  3. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Sekimizu, Koichi

    1980-01-01

    Purpose: To improve the performance and secure the safety of a nuclear reactor by rapidly computing and display the power density in the nuclear reactor by using a plurality of processors. Constitution: Plant data for a nuclear reactor containing the measured values from a local power monitor LPRM are sent and recorded in a magnetic disc. They are also sent to a core performance computer in which burn-up degree distribution and the like are computed, and the results are sent and recorded in the magnetic disc. A central processors loads programs to each of the processors and applies data recorded in the magnetic disc to each of the processors. Each of the processors computes the corresponding power distribution in four fuel assemblies surrounding the LPRM string by the above information. The central processor compiles the computation results and displays them on a display. In this way, power distribution in the fuel assemblies can rapidly be computed to thereby secure the improvement of the performance and safety of the reactor. (Seki, T.)

  4. Reactor instrumentation and control

    International Nuclear Information System (INIS)

    Wach, D.; Beraha, D.

    1980-01-01

    The methods for measuring radiation are shortly reviewed. The instrumentation for neutron flux measurement is classified into out-of-core and in-core instrumentation. The out-of-core instrumentation monitors the operational range from the subcritical reactor to full power. This large range is covered by several measurement channels which derive their signals from counter tubes and ionization chambers. The in-core instrumentation provides more detailed information on the power distribution in the core. The self-powered neutron detectors and the aeroball system in PWR reactors are discussed. Temperature and pressure measurement devices are briefly discussed. The different methods for leak detection are described. In concluding the plant instrumentation part some new monitoring systems and analysis methods are presented: early failure detection methods by noise analysis, acoustic monitoring and vibration monitoring. The presentation of the control starts from an qualitative assessment of the reactor dynamics. The chosen control strategy leads to the definition of the part-load diagram, which provides the set-points for the different control systems. The tasks and the functions of these control systems are described. In additiion to the control, a number of limiting systems is employed to keep the reactor in a safe operating region. Finally, an outlook is given on future developments in control, concerning mainly the increased application of process computers. (orig./RW)

  5. Nuclear Reactor Sharing Program

    International Nuclear Information System (INIS)

    1994-01-01

    The Ohio State University Research Reactor (OSURR) is licensed to operate at a maximum power level of 500 kW. A pool-type reactor using flat-plate, low enriched fuel elements, the OSURR provides several experimental facilities including two 6-inch i.d. beam ports, a graphite thermal column, several graphite-isotope-irradiation elements, a pneumatic transfer system (Rabbit), various dry tubes, and a Central Irradiation Facility (CIF). The core arrangement and accessibility facilitates research programs involving material activation or core parameter studies. The OSURR control room is large enough to accommodate laboratory groups which can use control instrumentation for monitoring of experiments. The control instrumentation is relatively simple, without a large amount of duplication. This facilitates opportunities for hands-on experience in reactor operation by nuclear engineering students making reactor parameter measurements. For neutron activation analysis and analyses of natural environmental radioactivity, the NRL maintains the gamma ray spectroscopy system (GRSS). It is comprised of two PC-based 8192-channel multichannel analyzers (MCAs) with all the required software for quantitative analysis. A 3 double-prime x 3 double-prime NaI(Tl), a 14 percent Ge(Li), and a High Purity Germanium detector are currently available for use with the spectroscopy system

  6. The Chernobyl reactor accident

    International Nuclear Information System (INIS)

    1986-01-01

    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) [de

  7. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    Barjon, Robert

    1975-01-01

    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 [fr

  8. Reactor control system. PWR

    International Nuclear Information System (INIS)

    2009-01-01

    At present, 23 units of PWR type reactors have been operated in Japan since the start of Mihama Unit 1 operation in 1970 and various improvements have been made to upgrade operability of power stations as well as reliability and safety of power plants. As the share of nuclear power increases, further improvements of operating performance such as load following capability will be requested for power stations with more reliable and safer operation. This article outlined the reactor control system of PWR type reactors and described the control performance of power plants realized with those systems. The PWR control system is characterized that the turbine power is automatic or manually controlled with request of the electric power system and then the nuclear power is followingly controlled with the change of core reactivity. The system mainly consists of reactor automatic control system (control rod control system), pressurizer pressure control system, pressurizer water level control system, steam generator water level control system and turbine bypass control system. (T. Tanaka)

  9. Reactor vessel stud tensioner

    International Nuclear Information System (INIS)

    Malandra, L.J.; Beer, R.W.; Salton, R.B.; Spiegelman, S.R.; Cognevich, M.L.

    1982-01-01

    A quick-acting stud tensioner, for facilitating the loosening or tightening of a stud nut on a reactor vessel stud, has gripper jaws which when the tensioner is lowered into engagement with the upper end of the stud are moved inwards to grip the upper end and which when the tensioner is lifted move outward to release the upper end. (author)

  10. Fossil fuel furnace reactor

    Science.gov (United States)

    Parkinson, William J.

    1987-01-01

    A fossil fuel furnace reactor is provided for simulating a continuous processing plant with a batch reactor. An internal reaction vessel contains a batch of shale oil, with the vessel having a relatively thin wall thickness for a heat transfer rate effective to simulate a process temperature history in the selected continuous processing plant. A heater jacket is disposed about the reactor vessel and defines a number of independent controllable temperature zones axially spaced along the reaction vessel. Each temperature zone can be energized to simulate a time-temperature history of process material through the continuous plant. A pressure vessel contains both the heater jacket and the reaction vessel at an operating pressure functionally selected to simulate the continuous processing plant. The process yield from the oil shale may be used as feedback information to software simulating operation of the continuous plant to provide operating parameters, i.e., temperature profiles, ambient atmosphere, operating pressure, material feed rates, etc., for simulation in the batch reactor.

  11. Fast reactor programme

    International Nuclear Information System (INIS)

    Plakman, J.C.

    1982-01-01

    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.)

  12. Reactor operational transient analysis

    International Nuclear Information System (INIS)

    Shin, W.K.; Chae, S.K.; Han, K.I.; Yang, K.S.; Chung, H. D.; Kim, H.G.; Moon, H.J.; Ryu, Y.H.

    1983-01-01

    To build up efficient capability of safety review and inspection for the nuclear power plants, four area of studies have performed as follows: 1) In order to search the most optimized operating method during load follow operating schemes, automatic control and normal control, are compared each other under the CAOC condition. The analysis performed by DDID code has shown that the reactor has to be controlled by the operator manually during load follow operation. 2) Through the sensitivity analysis by COBRA code, the operating parameters, such as coolant pressure, flow rate, inlet temperature, and power distribution are shown to be important to the determination of DNBR. Expecially, inlet temperature of primary coolant system is appeared as the most senstive parameter on DNBR. 3) FRAPCON code is adapted to study the sensitivity of several operational parameters on the mechanical properties of reactor fuel rod. 4) The calculations procedure which is required to be obtained the neutron fluence at the reactor vessel and the spectrum at the surveillance capsule is established. The results of computation are conpared with those of FSAR and SWRI report and proved its applicability to reactor surveillance program. (Author)

  13. Fusion reactor materials

    International Nuclear Information System (INIS)

    Sethi, V.K.; Scholz, R.; Nolfi, F.V. Jr.; Turner, A.P.L.

    1980-01-01

    Data are given for each of the following areas: (1) effects of irradiation on fusion reactor materials, (2) hydrogen permeation and materials behavior in alloys, (3) carbon coatings for fusion applications, (4) surface damage of TiB 2 coatings under energetic D + and 4 He + irradiations, and (5) neutron dosimetry

  14. Reactor physics of CANFLEX

    International Nuclear Information System (INIS)

    Sim, K. S.; Min, Byung Joo.

    1997-07-01

    Characteristic of reactor physics for CANFLEX-NU fuel core were calculated using final fuel design data. The results of analysis showed that there was no impact on reactor operations and safety. The above results of calculations and analysis were described in the physics design for CANFLEX-NU core. Various fuel models were evaluated for selecting high burnup fuel using recovered uranium. It is judged to be worse effects for reactor safety. Hence, the use of graphite within fuel was proposed and its results showed to be better. The analysis system of reactor physics for design and analysis of high burnup fuel was evaluated. Lattice codes and core code were reviewed. From the results, the probability of WIMS-AECL and HELIOS is known to be high for analysis of high burnup fuel. For the core code, RFSP, it was evaluated that the simplified 2 group equation should be replaced by explicit 2 group equation. This report also describes about the status of critical assemblies in other countries. (author). 58 refs., 41 tabs., 126 figs

  15. WATER BOILER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1960-11-22

    As its name implies, this reactor utilizes an aqueous solution of a fissionable element salt, and is also conventional in that it contains a heat exchanger cooling coil immersed in the fuel. Its novelty lies in the utilization of a cylindrical reactor vessel to provide a critical region having a large and constant interface with a supernatant vapor region, and the use of a hollow sleeve coolant member suspended from the cover assembly in coaxial relation with the reactor vessel. Cool water is circulated inside this hollow coolant member, and a gap between its outer wall and the reactor vessel is used to carry off radiolytic gases for recombination in an external catalyst chamber. The central passage of the coolant member defines a reflux condenser passage into which the externally recombined gases are returned and condensed. The large and constant interface between fuel solution and vapor region prevents the formation of large bubbles and minimizes the amount of fuel salt carried off by water vapor, thus making possible higher flux densities, specific powers and power densities.

  16. Cermet fuel reactors

    International Nuclear Information System (INIS)

    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

  17. Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1993-06-01

    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

  18. Nuclear reactor vessels

    International Nuclear Information System (INIS)

    Sato, Yoshimi; Fukuda, Yoshio.

    1987-01-01

    Purpose: To improve the strength and reliability by moderating thermal stresses produced to the furnace walls of a reactor vessel by the thermal shocks upon reactor shutdown and tripping and reducing the generation of developing thermal ratchet strains produced upon repeating thermal shocks. Constitution: Upon occurrence of reactor shutdown or tripping, the temperature is detected and the pressure of the cover gas is controlled such that the axial temperature slope is decreased to displace the liquid surface in an annular vessel. Then, for attaining the stress reducing temperature, control is so conducted that the temperature of the lower portion is not higher than the upper portion in the axial temperature distribution of the reactor vessel. By controlling the pressure of the cover gas in the annular vessel in this way, the liquid level can be raised to a cover gas portion remaining at a high temperature state. Further, the temperature of the furnace wall can always be decreased to a temperature of the high temperature plenum thereby enabling to moderate the thermal stresses. (Yoshihara, H.)

  19. Studies on reactor physics

    International Nuclear Information System (INIS)

    1960-01-01

    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

  20. University Reactor Instrumentation Program

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1992-11-01

    Recognizing that the University Reactor Instrumentation Program was developed in response to widespread needs in the academic community for modernization and improvement of research and training reactors at institutions such as the University of Florida, the items proposed to be supported by this grant over its two year period have been selected as those most likely to reduce foreed outages, to meet regulatory concerns that had been expressed in recent years by Nuclear Regulatory Commission inspectors or to correct other facility problems and limitations. Department of Energy Grant Number DE-FG07-90ER129969 was provided to the University of Florida Training Reactor(UFTR) facility through the US Department of Energy's University Reactor Instrumentation Program. The original proposal submitted in February, 1990 requested support for UFTR facility instrumentation and equipment upgrades for seven items in the amount of $107,530 with $13,800 of this amount to be the subject of cost sharing by the University of Florida and $93,730 requested as support from the Department of Energy. A breakdown of the items requested and total cost for the proposed UFTR facility instrumentation and equipment improvements is presented