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Sample records for alto lazio-2 reactor

  1. A model of Alto Lazio boiling water reactor using the LEGO code balance of plant simulation

    International Nuclear Information System (INIS)

    Spelta, S.; Garbossa, G.B.

    1989-01-01

    An extensive effort has been made at the Italian National Electricity Board (ENEL) to construct and validate a LEGO model capable of simulating the operational transients of the Alto Lazio Nuclear Station, a two twin-units site with BWR/6 class reactors, rated at 2894 MWt and with Mark III containment. LEGO is a modular package developed at the Research and development Department of the Italian National Electricity Board (CRA-ENEL) for computer aided modeling of fossil-fired and nuclear steam power plants. In this paper a system analysis model capable of describing steady-state and transient performance of the Balance of Plant (BOP) of the Alto Lazio Power Station is presented. This is one of two companion papers devoted to the description of the overall plant model including both the Nuclear Steam Supply System (NSSS) and the BOP. In the paper, after a brief summary of the main LEGO characteristics, a description of the BOP lay-out is presented. The overall model, which has been set-up, including control systems and automation, is very detailed and consists of almost 2000 differential or algebraic equations. After a brief description of the mathematical model, two significant transients obtained using the overall model are presented and discussed

  2. Altos penachos de escarcha

    OpenAIRE

    Josa, Lola; Lambea, Mariano

    2008-01-01

    El documento contiene la composición titulada “Altos penachos de escarcha”, perteneciente al Manojuelo Poético-Musical de Nueva York, recopilación manuscrita de piezas poético-musicales de los siglos XVII y XVIII que se conserva en la biblioteca de The Hispanic Society of America (New York) bajo la signatura Ms. HC. 380/821a. Se ofrece la partitura con la transcripción musical a notación moderna, la edición anotada del poema y todos aquellos datos que ha sido posible averiguar sobre cada piez...

  3. y El Alto, Bolivia

    Directory of Open Access Journals (Sweden)

    León Darío Parra Bernal

    2013-01-01

    Full Text Available En el presente caso de estudio se analiza la empresarialidad informal como un reto de política pública y económica. Para ello, se efectuaron 20 entrevistas en profundidad a microempresarios y comerciantes del sector informal en las ciudades de La Paz y El Alto, en Bolivia en 2010, y a 3 funcionarios públicos de instituciones de apoyo al fomento empresarial en el mismo país. La principal reflexión giró en torno al establecimiento de que los empresarios informales poseen un elevado nivel de influencia en la efectividad de las políticas públicas implementadas para su sector, así como en los mecanismos que se han utilizado en Bolivia para incluirlos en el proceso.

  4. 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.)

  5. 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.)

  6. Reactors

    DEFF Research Database (Denmark)

    Shah, Vivek; Vaz Salles, Marcos António

    2018-01-01

    The requirements for OLTP database systems are becoming ever more demanding. Domains such as finance and computer games increasingly mandate that developers be able to encode complex application logic and control transaction latencies in in-memory databases. At the same time, infrastructure...... engineers in these domains need to experiment with and deploy OLTP database architectures that ensure application scalability and maximize resource utilization in modern machines. In this paper, we propose a relational actor programming model for in-memory databases as a novel, holistic approach towards......-level function calls. In contrast to classic transactional models, however, reactors allow developers to take advantage of intra-transaction parallelism and state encapsulation in their applications to reduce latency and improve locality. Moreover, reactors enable a new degree of flexibility in database...

  7. 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.)

  8. Altos custos financeiros do trauma vascular

    Directory of Open Access Journals (Sweden)

    Ricardo Costa-Val

    Full Text Available OBJETIVO: Demonstrar o custo e impacto financeiro referente à primeira abordagem cirúrgica das lesões vasculares em pacientes admitidos no Hospital João XXIII/FHEMIG, entre os anos de 2004 a 2006. MéTODOS: Trata-se de um estudo com aprovação ética, retrospectivo, de coorte e descritivo realizado a partir da auditoria de contas hospitalares referentes a 70 prontuários catalogados pelo Serviço de Trauma Cardiovascular. RESULTADOS: Cinco (7,14% prontuários foram excluídos por má qualidade técnica. O valor monetário repassado pelo Sistema Único de Saúde e pelo setor privado foram de R$ 103.614,96 (US$ 60.949,97 e de R$ 185.888,21 (US$ 109.346,0, respectivamente, implicando em defasagem potencial de 44%. Houve correlação direta entre custos e topografia anatômica das lesões e exponencial em relação às variáveis hemoderivados e próteses vasculares. CONCLUSÃO: Este estudo corrobora os altos custos do trauma vascular e fortalece a importância da auditoria de contas para as tomadas de decisões médicas.

  9. Criterios para identificar patolog?as de alto costo en Colombia

    OpenAIRE

    Cuenta de alto costo, MinSalud

    2010-01-01

    Al identificar posibles pacientes de alto costo se debe definir si existen caracter?sticas que determinan su comportamiento como pacientes de alto costo, para definir si dicha patolog?a puede considerarse como Enfermedad de Alto Costo en Colombia.

  10. Casas de altos en Concepción

    Directory of Open Access Journals (Sweden)

    Rodrigo Fischer Pérez

    1990-06-01

    Full Text Available La casa de altos es una construcción eminentemente urbana. Pareada junto a otras construcciones, va formando bordes continuos, cuyos primeros pisos son generalmente comerciales y los superiores habitacionales.

  11. Diseño de una Fuente de Alto Voltaje

    Directory of Open Access Journals (Sweden)

    José Enrique Eirez Izquierdo

    2013-10-01

    Full Text Available Este documento presenta las experiencias en el diseño de una fuente de alto voltaje, basada en multiplicadores de media onda. La fuente garantizará un voltaje de salida en el orden de 102 V y una corriente en el orden de 10-3 A. Se muestran y analizan resultados experimentales encaminados a su aplicación en la alimentación de un generador de pulsos de alto voltaje.

  12. Liderazgo servidor y equipos de alto desempeño

    OpenAIRE

    Mejía Villegas, Estefanía

    2015-01-01

    El objetivo de este ensayo es mostrar cómo el liderazgo servidor influye positivamente en el desarrollo de los equipos de alto desempeño. En el ensayo se desarrollan la temática del liderazgo servidor y su principal objetivo, a la vez que se describen las características de un equipo de alto desempeño y sus etapas de desarrollo, cómo son influenciadas por el liderazgo servidor y cómo este modelo puede cumplir con sus requerimientos. 

  13. Technical and scientific report of the Alto project; Rapport scientifique et technique du projet ALTO

    Energy Technology Data Exchange (ETDEWEB)

    Essabaa, S.; Gardes, D.; Grialou, D.; Ibrahim, F.; Le Scornet, J.C

    2002-07-01

    The Alto project means the installation of an electron linear accelerator inside the experimental area of the tandem accelerator of the nuclear physics institute of Orsay (IPNO, France). This linear accelerator comes from CERN where it was operating as a pre-injector for LEP. This equipment will allow IPNO'teams to perform fast kinetics studies in a domain different from that of ELYSE accelerator. The time resolution will not be as high as that of ELYSE (picosecond) but will be sufficient (microsecond) to produce free radicals in aqueous and gaseous media. The main expectations of this installation can be classified according 3 axis: 1) basic research (mainly the study of nuclear matter through photo-fission, 2) research and development of accelerators (by providing a test bench for new high frequency systems and superconducting components), and 3) applied research for industry concerning: biochemistry under irradiation, radiation sensibility, DNA breaking, food and drug sterilization and behaviour of electronic components under irradiation. This rapport details the research program that could be achieved with this equipment, describes its contributions in terms of economic development, cooperation with industry, student training, and specifies the needed investment and the operating and maintenance costs. (A.C.)

  14. CALIFA, the Calar alto legacy integral field area survey

    DEFF Research Database (Denmark)

    Husemann, B.; Jahnke, K.; Sánchez, S. F.

    2013-01-01

    We present the first public data release (DR1) of the Calar Alto Legacy Integral Field Area (CALIFA) survey. It consists of science-grade optical datacubes for the first 100 of eventually 600 nearby (0.005 < z < 0.03) galaxies, obtained with the integral-field spectrograph PMAS/PPak mounted on th...... the available interfaces and tools that allow easy access to this first publicCALIFA data at http://califa.caha.es/DR1....

  15. Amplificador de Potencia de Alto Rendimiento para Transmisores EER

    OpenAIRE

    Ortega González, Francisco Javier; Gimeno Martín, Alejandro; Pardo Martin, José Manuel; Benavente Peces, César

    2008-01-01

    Se presenta un amplificador de potencia de alto rendimiento específicamente diseñado para aplicaciones EER (Envelope Elimination Restoration) en transmisores de HF. El amplificador se compone de dos subsistemas: Un amplificador clase-E de banda ancha para HF (B = 40%, POUT = 50W @ 7.5 MHz, ηOV > 90%) excitado por un driver también de banda ancha que amplifica la componente de fase de la señal y un amplificador de envolvente derivado de un amplificador clase-D de audio (o clase-S) que presenta...

  16. Feminicidios en la frontera chilena: el caso de Alto Hospicio

    Directory of Open Access Journals (Sweden)

    Ainhoa Vásquez Mejías

    2016-01-01

    Full Text Available Entre 1999 y el 2001, varias adolescentes desaparecieron en el norte de Chile y, posteriormente, fueron encontradas muertas. La novela Alto Hospicio (2008, de Rodrigo Ramos Bañados, recrea estos feminicidios desde la visión del cómplice del único inculpado por estos crímenes. En el presente artículo se plantea que el escritor utiliza la noción de frontera como aparato crítico, con el fin de desestabilizar barreras espaciales, simbólicas y textuales que se agrupan en cuatro ejes: Bolivia-Chile, santas-putas, racionalidad-locura, ficción-realidad. Así, la novela cuestiona y deconstruye los límites para hablarnos de estos feminicidios desde un punto indeterminado, que funciona como espejo de la incertidumbre e irresolución de este caso en la justicia chilena.

  17. Technical and scientific report of the Alto project

    CERN Document Server

    Essabaa, S; Grialou, D; Ibrahim, F; Le Scornet, J C

    2002-01-01

    The Alto project means the installation of an electron linear accelerator inside the experimental area of the tandem accelerator of the nuclear physics institute of Orsay (IPNO, France). This linear accelerator comes from CERN where it was operating as a pre-injector for LEP. This equipment will allow IPNO'teams to perform fast kinetics studies in a domain different from that of ELYSE accelerator. The time resolution will not be as high as that of ELYSE (picosecond) but will be sufficient (microsecond) to produce free radicals in aqueous and gaseous media. The main expectations of this installation can be classified according 3 axis: 1) basic research (mainly the study of nuclear matter through photo-fission, 2) research and development of accelerators (by providing a test bench for new high frequency systems and superconducting components), and 3) applied research for industry concerning: biochemistry under irradiation, radiation sensibility, DNA breaking, food and drug sterilization and behaviour of electro...

  18. EL ALTO MAGDALENA- COLOMBIA DE LA MANO CON ENERGIAS ALTERNATIVAS

    Directory of Open Access Journals (Sweden)

    Barragán-Alturo, Ancízar

    2013-12-01

    Full Text Available El afán por destruir un paradigma, que mantiene encadenados a los habitantes de Girardot y la región, a una compañía de distribución de la energía eléctrica con sus altos precios para el kilowatt-hora, ha inspirado la investigación CUNDINAMARCA DE LA MANO DE LAS ENERGIAS ALTERNATIVAS, demostrando por diversos caminos que el montaje de paneles solares para generación de energía eléctrica en las cubiertas de las casas es la energía alternativa para la solución de diversos problemas, entre ellos: los costos elevados, las fluctuaciones de voltaje, los cortes de energía, los daños en los electrodomésticos

  19. The Alto Moxoto Terrain in Eastern Paraiba ('Caldas Brandao Massif')

    International Nuclear Information System (INIS)

    Neves, Benjamim Bley de Brito; Campos Neto, Mario da Costa; Souza, Solange Lucena de; Schmus, William Randall Van; Fernandes, Tania Maria Gomes

    2001-01-01

    The Alto Moxoto Terrane (TAM), at the east of Paraiba State is mostly composed of sheared ortho gneisses, porphyritic granodioritic gneisses and it bears an imbricated sheet of Al-rich (garnet-biotite-sillimanite) gneisses, deeply affected by migmatization phenomena. This litho-structural assemblage is drawing a regional asymmetric anti formal structure, with its axial zone running parallel to the B R-230 highway (E-W trending). It is limited in both, north (Alto Pajeu terrane) and south (Rio Capibaribe terrane) sides by important shear zones, which are feather faults connected with the development of the Pernambuco lineament, to the southwest. The adopted designation of 'terrane' is based upon its singular geological features, in terms of lithological and structural characteristics, Paleoproterozoic in age and sharp limits with the different confining terranes. TAM is here considered as a mega-fragment of the Atlantica Super continent, that was built up by the Paleoproterozoic Collage ('Transamazonian') and that was preserved in the framework of West Gondwana (Brasiliano/Pan African Collage) as a 'terrane'. This terrane shows conspicuous continuity to the far interior of the province, to the southwestern part of Pernambuco State, and so doing, it demonstrates that the former designation of 'Caldas Brandao Massif must be ruled out, as obsolete for many reasons. Geochronological determinations using Rb-Sr, Sm-Nd and U-Pb methods confirm the Paleoproterozoic age of this terrane, with the presence of some Archean protoliths as well as the various degrees of structural reworking and isotopic reseting promoted by the Brasiliano Cycle. This cycle was responsible for some intrusive granites, for most of the general geological features, like usual informal limits and even the present shape of the TAM, a typical reworked 'basement inlier'. (author)

  20. The Alto Tiberina Near Fault Observatory (northern Apennines, Italy

    Directory of Open Access Journals (Sweden)

    Lauro Chiaraluce

    2014-06-01

    Full Text Available The availability of multidisciplinary and high-resolution data is a fundamental requirement to understand the physics of earthquakes and faulting. We present the Alto Tiberina Near Fault Observatory (TABOO, a research infrastructure devoted to studying preparatory processes, slow and fast deformation along a fault system located in the upper Tiber Valley (northern Apennines, dominated by a 60 km long low-angle normal fault (Alto Tiberina, ATF active since the Quaternary. TABOO consists of 50 permanent seismic stations covering an area of 120 × 120 km2. The surface seismic stations are equipped with 3-components seismometers, one third of them hosting accelerometers. We instrumented three shallow (250 m boreholes with seismometers, creating a 3-dimensional antenna for studying micro-earthquakes sources (detection threshold is ML 0.5 and detecting transient signals. 24 of these sites are equipped with continuous geodetic GPS, forming two transects across the fault system. Geochemical and electromagnetic stations have been also deployed in the study area. In 36 months TABOO recorded 19,422 events with ML ≤ 3.8 corresponding to 23.36e-04 events per day per squared kilometres; one of the highest seismicity rate value observed in Italy. Seismicity distribution images the geometry of the ATF and its antithetic/synthetic structures located in the hanging-wall. TABOO can allow us to understand the seismogenic potential of the ATF and therefore contribute to the seismic hazard assessment of the area. The collected information on the geometry and deformation style of the fault will be used to elaborate ground shaking scenarios adopting diverse slip distributions and rupture directivity models.

  1. The Alto Paraguay Alkaline Province: petrographic, geochemical and geochronological characteristics

    International Nuclear Information System (INIS)

    Velazquez Fernandez, Victor

    1996-01-01

    The Alto Paraguay Province is located at the border of the State of Mato Grosso do Sul and Paraguay, between the coordinates 21 deg 10 ' to 23 deg 25 ' of Southern latitude and 57 deg 10 ' to 58 deg 00 ' , having the city of Porto Murtinho as the main reference point. The geotectonic domain of the area is governed by the precambric units of the Southern extreme of the Amazonic craton which developed a long and accentuated activity, giving rise to folds and important faults, that in several cases seem to have exerted an effective control of the magmatic manifestations. Radiometric data indicate that the emplacement of the syenitic bodies took place in the Permo-Triassic period, with a major incidence in the interval 260-240 Ma, representing thus, an important phase of alkaline magmatic affinity associated to the Parana Basin which is believed is to be unique, since the other known areas (Central, Amambay and Rio Apa Provinces, Paraguay, Velasco Province, Bolivia) are considerably younger (140-120 Ma). Syenitic rocks from the Alto Paraguay Province show wide variation in the ratio 87 Sr/ 86 Sr (0.703361 - 0.707734). Excluding the Cerro Boggiani rocks (0.703837-0.707734), values for the nepheline syenites (0.703361-0.703672) general lower than those of the other syenites types. Alkaline syenites cover the interval 0.703510- 0.703872, while quartz syenites and syenogranites are 0.704562 and 0.707076, respectively. geologic evidence, in addition to petrographic, geochemical and isotopic (Sr) data, suggest that the syenitic rocks have been derived from an unique mantelic parental liquid, by fractional crystallization and assimilation processes, which are assumed to be occurred during the emplacement of the magma in the crust. (author)

  2. ¿A qué atribuyen el alto rendimiento escolar los estudiantes de buen rendimiento escolar proveniente de liceos con altos indices de vulnerabilidad?

    OpenAIRE

    Morales, Mario; Sepúlveda, Martitza

    2016-01-01

    La presente investigación tiene como finalidad comprender desde las subjetividades de los participantes egresados de secundaria, provenientes de instituciones escolares con altos índices de vulnerabilidad, los principales factores que han contribuido en la obtención de su alto rendimiento escolar. Son varios los modelos que se han utilizados para explicar el abandono de los estudiantes en los primeros años de universidad (Ethington, 1990; St. John, Cabrera y Asker, 2000; Spady, 1970; Braxton,...

  3. The Alto Paraguay Alkaline Province: petrographic, geochemical and geochronological characteristics; Provincia alcalina Alto Paraguai: caracteristicas petrograficas, geoquimicas e geocronologicas

    Energy Technology Data Exchange (ETDEWEB)

    Velazquez Fernandez, Victor

    1996-12-31

    The Alto Paraguay Province is located at the border of the State of Mato Grosso do Sul and Paraguay, between the coordinates 21 deg 10{sup `}to 23 deg 25{sup `}of Southern latitude and 57 deg 10{sup `} to 58 deg 00{sup `}, having the city of Porto Murtinho as the main reference point. The geotectonic domain of the area is governed by the precambric units of the Southern extreme of the Amazonic craton which developed a long and accentuated activity, giving rise to folds and important faults, that in several cases seem to have exerted an effective control of the magmatic manifestations. Radiometric data indicate that the emplacement of the syenitic bodies took place in the Permo-Triassic period, with a major incidence in the interval 260-240 Ma, representing thus, an important phase of alkaline magmatic affinity associated to the Parana Basin which is believed is to be unique, since the other known areas (Central, Amambay and Rio Apa Provinces, Paraguay, Velasco Province, Bolivia) are considerably younger (140-120 Ma). Syenitic rocks from the Alto Paraguay Province show wide variation in the ratio {sup 87} Sr/{sup 86} Sr (0.703361 - 0.707734). Excluding the Cerro Boggiani rocks (0.703837-0.707734), values for the nepheline syenites (0.703361-0.703672) general lower than those of the other syenites types. Alkaline syenites cover the interval 0.703510- 0.703872, while quartz syenites and syenogranites are 0.704562 and 0.707076, respectively. geologic evidence, in addition to petrographic, geochemical and isotopic (Sr) data, suggest that the syenitic rocks have been derived from an unique mantelic parental liquid, by fractional crystallization and assimilation processes, which are assumed to be occurred during the emplacement of the magma in the crust. (author) 124 refs., 52 figs., 7 tabs.

  4. The Alto Paraguay Alkaline Province: petrographic, geochemical and geochronological characteristics; Provincia alcalina Alto Paraguai: caracteristicas petrograficas, geoquimicas e geocronologicas

    Energy Technology Data Exchange (ETDEWEB)

    Velazquez Fernandez, Victor

    1997-12-31

    The Alto Paraguay Province is located at the border of the State of Mato Grosso do Sul and Paraguay, between the coordinates 21 deg 10{sup `}to 23 deg 25{sup `}of Southern latitude and 57 deg 10{sup `} to 58 deg 00{sup `}, having the city of Porto Murtinho as the main reference point. The geotectonic domain of the area is governed by the precambric units of the Southern extreme of the Amazonic craton which developed a long and accentuated activity, giving rise to folds and important faults, that in several cases seem to have exerted an effective control of the magmatic manifestations. Radiometric data indicate that the emplacement of the syenitic bodies took place in the Permo-Triassic period, with a major incidence in the interval 260-240 Ma, representing thus, an important phase of alkaline magmatic affinity associated to the Parana Basin which is believed is to be unique, since the other known areas (Central, Amambay and Rio Apa Provinces, Paraguay, Velasco Province, Bolivia) are considerably younger (140-120 Ma). Syenitic rocks from the Alto Paraguay Province show wide variation in the ratio {sup 87} Sr/{sup 86} Sr (0.703361 - 0.707734). Excluding the Cerro Boggiani rocks (0.703837-0.707734), values for the nepheline syenites (0.703361-0.703672) general lower than those of the other syenites types. Alkaline syenites cover the interval 0.703510- 0.703872, while quartz syenites and syenogranites are 0.704562 and 0.707076, respectively. geologic evidence, in addition to petrographic, geochemical and isotopic (Sr) data, suggest that the syenitic rocks have been derived from an unique mantelic parental liquid, by fractional crystallization and assimilation processes, which are assumed to be occurred during the emplacement of the magma in the crust. (author) 124 refs., 52 figs., 7 tabs.

  5. Bird diversity and conservation of Alto Balsas (Southwestern Puebla, Mexico

    Directory of Open Access Journals (Sweden)

    Jorge E Ramírez-Albores

    2007-03-01

    Full Text Available Knowledge of the composition of the bird community in Alto Balsas (southwestern Puebla, Central Mexico is needed for management programs aiming at protection and conservation of bird species and their habitats I studied sites with tropical deciduous forest. Data were obtained during 1666 hours of field work in 238 days from March 1998 to September 2000. Six permanent transect (3.5 km long and 100 m wide; 30 to 40 ha in each transect were used to determine species richness in the study sites. The Shannon-Wiener diversity index was calculated for each site and Sorensen’s index was used to assess similarity between sites. One-way analysis of variance was used to test for differences between sites in species richness and diversity values. A total of 128 species were recorded, Tepexco (n = 75, H´= 3.76 and Puente Márquez (n = 61, H´= 3.62 were the sites that showed the greatest specific richness and diversity. However, species richness and diversity seasonally patterns were similar among sites (ANOVA p > 0.05, with highest diversity during the rainy season. Most species were resident; 42 were migrants. The avifauna was represented by 30 species associated with tropical deciduous forest and 12 from open habitats or heavily altered habitats. Insectivores were the best represented trophic category, followed by carnivores and omnivores. Rev. Biol. Trop. 55 (1: 287-300. Epub 2007 March. 31.Este estudio describe la diversidad avifaunística en sitios del Alto Balsas (suroeste de Puebla en el Centro de México y examina la variación en la diversidad de las especies de aves. El estudio fue llevado a cabo en sitios con presencia de bosque tropical caducifolio. Los datos fueron obtenidos durante 1666 horas de trabajo de campo en 238 días de Marzo 1998 a Septiembre 2000. Se realizaron seis transectos permanentes (de 3.5 km de longitud y 100 m de ancho; de 30 a 40 ha en cada transecto para determinar la riqueza de especies en los sitios de estudio. Se

  6. Ventaja de jugar en casa en voleibol de alto rendimiento

    Directory of Open Access Journals (Sweden)

    Rui Marcelino

    2009-01-01

    Full Text Available En este estudio se ha pretendido estudiar la ventaja en casa en el Voleibol de alto rendimiento, apoyándonos en las estadísticas de los partidos que más pueden explicar ese fenómeno. Se han analizado 65.949 acciones de juego seleccionadas de la Liga Mundial 2005. El instrumento de observación que se ha elaborado es una combinación de formato de campo con sistemas de categorías. Los datos se han obtenido mediante el "Volleyball Information System" y se han analizado mediante la prueba t de Student, y la prueba ji-cuadrado. Los resultados demuestran que hay ventaja en casa en Voleibol (57,5% de victorias jugando en casa. Las estadísticas del ataque (t= 2.49, p = 0.01, del servicio (t= -2.18, p= 0.03, de la recepción (t= 16.74, p<0.001 y de la distribución (t= 2.03, p= 0.04 muestran rendimientos superiores para los equipos que juegan en casa. No se han encontrado diferencias en el rendimiento del bloqueo (t= -0.25, p= 0.80 y la defensa (t= 0.11, p= 0.92 entre los juegos disputados en casa y los disputados fuera.

  7. Un centro ceremonial formativo en el Alto Piura

    Directory of Open Access Journals (Sweden)

    1989-01-01

    estilos diversos, cuya evolución temporal se puede seguir, tanto del punto de vista de las formas y técnicas decorativas como de la iconografía, abundante y diversificada. Estos datos, nuevos para la región, así como el análisis comparativo de los vestigios materiales, comprueban la existencia de contactos y relaciones con las demás zonas cercanas y particularmente la integración del Alto Piura a los sistemas ideológicos y religiosos más sureños. La implantación del sitio podría estar ligada a su ubicación geográfica, en el cruce de una vía de intercambio entre poblaciones costeras, andinas y selváticas, y de un camino norte-sur facilitando los contactos entre la costa norte peruana y la costa y los Andes ecuatorianos. Su ocupación parece testimoniar una situación original -caracterizada por la presencia de representantes de varias tradiciones culturales- que se mantendrá e igualmente singularizará este sector del Alto Piura durante las épocas posteriores. Research carried out since 1986 on the archaeological site of Cerro Ñañañique (Chulucanas, department of Piura has allowed the identification and description of a ceremonial complex, built and occupied between the Xth and the Vth centuries B.C.. Several phases of edification and widening of the complex have been recognized according to a general U shape plan. Several ceramic traditions of various styles and origins can be found contemporarily on the site, and their temporal evolution can be identified and followed from these points of view: forms, decorative techniques and iconography which is abundant and diverse. The data, new for this study area, and the comparative analysis of material remains demonstrate the existence of relations with nearby zones and, particularly, the integration of Alto Piura in Southern ideological and religious systems. The establishment of the site might be related to its geographic location, at the crossing of an exchange route between coastal, andean and amazonian

  8. Improved safety features in the design of Alto Lazio NPP

    International Nuclear Information System (INIS)

    Bava, G.; Cianciolo, T.; Del Nero, G.

    1988-01-01

    The ALTO LAZIO Nuclear Power Plant, two 1000Mwe units, is a BWR 6/MARK III located about 100 km north of Rome, on the Tyrrhenian Sea Coasts. The construction of the plant started in 1978, but it has recently been stopped by a Government decision following a national referendum, when the units were about 70% completed. This paper is mainly intended to illustrate the major safety features which have been implemented as result of specific requirements issued by the safety authority (ENEA DISP) during the construction permit stage or the subsequent licensing process. One of the tools used to identify the need for design modifications has been a comprehensive reliability analysis of safety system: in the paper the methods used and the major results obtained by this study are briefly presented. Also, the approach used in the investigation of severe accidents and major applications in the area of plant design and emergency procedures are briefly discussed; furthermore the trend toward a simpler mitigation concept is described

  9. Comercio e intercambio en la Hispania romana (Alto imperio

    Directory of Open Access Journals (Sweden)

    Genaro CHIC GARCÍA

    2010-02-01

    Full Text Available RESUMEN: Se muestra al Alto Imperio como una etapa de desarrollo del individualismo en relación con la formación de mercados impersonales dominados por la racionalidad económica, manifiesta en signos tales como la moneda y la escritura fonético- vocálica, que va desplazando a los sistemas de relación tradicionales basados en el prestigio social y los intercambios personalizados. La formación de un Estado burocrático centralizado, sin embargo, hará colapsar el incipiente liberalismo comercial.ABSTRACT: The Early Empire is shown as a stage of development of the individualism in relation to the formation of impersonal markets dominated by the economic rationality, wich becomes evident in signs such as the coin or the phonetic-vocalic writing, that is displacing the traditional systems of relation based on the social prestige and the personalized exchange. Nevertheless, the formation of a centralized bureaucratic state will cause the incipient commercial liberalism to collapse.

  10. TNO Photometry and Spectroscopy at ESO and Calar Alto

    Science.gov (United States)

    Boehnhardt, H.; Sekiguchi, T.; Vair, M.; Hainaut, O.; Delahodde, C.; West, R. M.; Tozzi, G. P.; Barrera, L.; Birkle, K.; Watanabe, J.; Meech, K.

    New photometry and spectroscopy of Transneptunian objects (TNO) has been obtained at ESO (VLT+FORS1, NTT+SOFI) and the Calar Alto (3.5m+MOSCA) observatory. BVRI photometry of more than 10 objects confirms the general colour-colour distribution of TNOs found previously. Quasi-simultaneous spectroscopy in the visible wavelength range of 5 TNOs did not reveal any spectral signature apart from the spetral gradients which are in agreement with the broadband colours. JHK filter photometry of 3 objects indicates that the reddening may only occur in the near-IR at least in some cases. Using new observations from the ESO VLT the lightcurve, colours and spectrum of 1996TO66 are investigated: the rotation period of 6.25h is confirmed, also the change in the lightcurve between 1997 and 1998 which indicates an exceptional behaviour in this object (temporary cometary activity ?). The 1999 photometry and spectroscopy in the visible revealed solar colours, no reddening and no spectral features. V-R colour changes over the rotation phase are not found. This works is done in colaboration with:

  11. Technical and scientific report of the Alto project

    International Nuclear Information System (INIS)

    Essabaa, S.; Gardes, D.; Grialou, D.; Ibrahim, F.; Le Scornet, J.C.

    2002-01-01

    The Alto project means the installation of an electron linear accelerator inside the experimental area of the tandem accelerator of the nuclear physics institute of Orsay (IPNO, France). This linear accelerator comes from CERN where it was operating as a pre-injector for LEP. This equipment will allow IPNO'teams to perform fast kinetics studies in a domain different from that of ELYSE accelerator. The time resolution will not be as high as that of ELYSE (picosecond) but will be sufficient (microsecond) to produce free radicals in aqueous and gaseous media. The main expectations of this installation can be classified according 3 axis: 1) basic research (mainly the study of nuclear matter through photo-fission, 2) research and development of accelerators (by providing a test bench for new high frequency systems and superconducting components), and 3) applied research for industry concerning: biochemistry under irradiation, radiation sensibility, DNA breaking, food and drug sterilization and behaviour of electronic components under irradiation. This rapport details the research program that could be achieved with this equipment, describes its contributions in terms of economic development, cooperation with industry, student training, and specifies the needed investment and the operating and maintenance costs. (A.C.)

  12. Dislipidemias en comunidades pehuenches de Alto Biobio chileno Dyslipidemias in Pehuenche communities from Chilean Alto Bio Bio

    Directory of Open Access Journals (Sweden)

    Claudia Navarrete Briones

    2013-01-01

    Full Text Available Se realizó un estudio descriptivo y transversal de 400 habitantes (mayores de 15 años de edad de las comunidades pehuenches de Alto Biobio en Chile, de mayo a octubre del 2011, a fin de determinar la prevalencia de dislipidemias en esta población. La información necesaria se recolectó sobre la base de la normativa y los criterios del Ministerio de Salud y como resultados generales de las concentraciones plasmáticas promedio y la prevalencia de dislipidemias figuraron: colesterol total de 169,20 ±26,36 mg/dL y 8,2 %; lipoproteínas de baja densidad de 89,93 ±23,31 mg/dL y 4,5 %; triglicéridos de 145,89 ±48,96 mg/dL y 53,0 %; y lipoproteínas de alta densidad de 50 ±8,87 mg/dL y 28,3 %. Las cifras fueron inferiores en el grupo etario de 15-24 años y en personas de ascendencia pehuenche, con una pobre asociación a sobrepeso u obesidad abdominal; en general, resultaron menores a las de los citadinos.A descriptive and cross-sectional study was carried out in 400 people (over 15 years from Pehuenche communities of the Chilean Alto Biobio, from May to October 2011, in order to determine the prevalence of dyslipidemias in this population. Necessary information was collected on the basis of regulations and criteria of the Ministry of Health, and as general results of average plasma levels and prevalence of dyslipìdemia were: total cholesterol 169.20 ± 26.36 mg/dL and 8.2%; low-density lipoproteins 89.93 ± 23.31 mg/dL and 4.5%; triglycerides 145.89 ± 48.96 mg/dL and 53.0%; and high-density lipoproteins 50 ±8.87 mg/dL and 28.3%. The values were lower in the age group of 15-24 years and in Pehuenche people with poor association with abdominal obesity or overweight; in general, they were lower than those of the city people.

  13. 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

  14. Busca de estruturas em grandes escalas em altos redshifts

    Science.gov (United States)

    Boris, N. V.; Sodré, L., Jr.; Cypriano, E.

    2003-08-01

    A busca por estruturas em grandes escalas (aglomerados de galáxias, por exemplo) é um ativo tópico de pesquisas hoje em dia, pois a detecção de um único aglomerado em altos redshifts pode por vínculos fortes sobre os modelos cosmológicos. Neste projeto estamos fazendo uma busca de estruturas distantes em campos contendo pares de quasares próximos entre si em z Â3 0.9. Os pares de quasares foram extraídos do catálogo de Véron-Cetty & Véron (2001) e estão sendo observados com os telescópios: 2,2m da University of Hawaii (UH), 2,5m do Observatório de Las Campanas e com o GEMINI. Apresentamos aqui a análise preliminar de um par de quasares observado nos filtros i'(7800 Å) e z'(9500 Å) com o GEMINI. A cor (i'-z') mostrou-se útil para detectar objetos "early-type" em redshifts menores que 1.1. No estudo do par 131046+0006/J131055+0008, com redshift ~ 0.9, o uso deste método possibilitou a detecção de sete objetos candidatos a galáxias "early-type". Num mapa da distribuição projetada dos objetos para 22 escala. Um outro argumento em favor dessa hipótese é que eles obedecem uma relação do tipo Kormendy (raio equivalente X brilho superficial dentro desse raio), como a apresentada pelas galáxias elípticas em z = 0.

  15. 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...

  16. Metallogenic aspects of the feldspars and micas geochemistry in pegmatite from Alto-Ligonha (Mocambique)

    International Nuclear Information System (INIS)

    Neves, J.M.C.

    1990-01-01

    This paper deals with metallogenic aspects concerning the huge Alto Ligonha pegmatite Province. The geological setting of the pegmatites is briefly reviewed and the metamorphic grade of the country rocks of the pegmatites, ranging from granulitic to greenschist facies, has been considered. The economically most interesting pegmatites are those emplaced within rocks with lighter metamorphism. The available geochronological data allow us to link, the most interesting pegmatites from Alto Ligonha, to the Pan-African granitoid magmatism, about 500 Ma ago. (author)

  17. Fístula de alto gasto High output fistula

    Directory of Open Access Journals (Sweden)

    Ricardo Almeida Varela

    2012-06-01

    Full Text Available Se presenta a un paciente de 37 años de edad que acude a nuestro Cuerpo de Guardia politraumatizado, con lesiones torácicas y abdominales, con síntomas y signos sugestivos de fracturas costales múltiples, con hemotórax derecho y hemoperitoneo, corroborado imaginológicamente y en la punción abdominal. Se realiza pleurostomía mínima intermedia y laparotomía exploratoria. Se le encuentran lesiones hepáticas de los segmentos VI, V, VIII y IV, con una profundidad mayor de 3 cm, además, deserosamientos en las asas delgadas intestinales y colon. Se realiza hepatorrafia y empaquetamiento hepático. Posteriormente van apareciendo complicaciones, por lo que tiene que ser reintervenido en más de 60 ocasiones. Entre ellas, la aparición de una fístula de alto gasto, que lo llevó a la desnutrición y a la permanencia con el abdomen expuesto durante 7 meses hasta el egreso. Se revisa la literatura correspondiente a estas entidades.A 37 years-old multi-traumatized male patient went to our emergency service. He had many injures in the thorax and the abdomen, together with symptoms and signs suggestive of multiple costal fractures, with right hemothorax and hemoperitoneum, all of which was confirmed by imaging techniques and by abdominal puncture. Minimal intermediate pleurostomy and exploratory laparoscopy were performed. We found hepatic lesions in the 6th, 5th, 8th and 4th segments, over 3 cm deep; additionally, the loss of serosa from the intestinal ansae and from the colon. Hepatorrhaphy and hepatic packing were also performed. Later on, more complications appeared, so he had to be re-operated more than 60 times. The occurrence of a high output fistula led him to malnutrition and his abdomen remained exposed for 7 months until he was finally discharged from hospital. This paper also presented a literature review on this topic.

  18. Pollution in coastal fog at Alto Patache, Northern Chile.

    Science.gov (United States)

    Sträter, Ellen; Westbeld, Anna; Klemm, Otto

    2010-11-01

    The Atacama Desert in Northern Chile is one of the most arid places on earth. However, fog occurs regularly at the coastal mountain range and can be collected at different sites in Chile to supply settlements at the coast with freshwater. This is also planned in the fog oasis Alto Patache (20°49'S, 70°09'W). For this pilot study, we collected fog water samples in July and August 2008 for chemical analysis to find indications for its suitability for domestic use. Fog water samples were taken with a cylindrical scientific fog collector and from the net and the storage tank of a Large Fog Collector (LFC). The pHs of advective fog, originating from the stratus cloud deck over the Eastern Pacific, varied between 2.9 and 3.5. Orographic fog, which was formed locally, exhibited a pH of 2.5. About 50% of the total ionic concentration was due to sea salt. High percentages of sulfate and very high enrichment factors (versus sea salt) of heavy metals were found. Both backward trajectories and the enrichment factors indicate that the high concentrations of ions and heavy metals in fog were influenced by anthropogenic activities along the Chilean Pacific Coast such as power plants, mining, and steel industry. We found no direct indication for the importance of other sources such as the emission of dimethyl sulfide from the ocean and subsequent atmospheric oxidation for acidity and sulfate or soil erosion for heavy metal concentrations. When fog water was collected by the LFC, it apparently picked up large amounts of dry deposition which accumulated on the nets during fog-free periods. This material is rinsed off the collector shortly after the onset of a fog event with the water collected first. During the first flush, some concentrations of acidity, nitrate, As, and Se, largely exceeded the Chilean drinking water limits. Before any use of fog water for domestic purpose, its quality should be checked on a regular basis. Strategies to mitigate fog water pollution are given.

  19. camarón del Alto Golfo de California

    Directory of Open Access Journals (Sweden)

    Homero R. Cabrera M.

    2006-01-01

    Full Text Available Actualmente la pesquería del camarón en el Alto Golfo de California genera preocupaciones referentes a su impacto sobre el medio ambiente, su viabilidad biológica y rentabilidad. Con el propósito de entender el manejo de esta pesquería y su productividad física, hemos examinado el comportamiento productivo de los barcos camaroneros de San Felipe, B.C. durante el periodo 1990-1993. Para ello usamos una función de producción frontera, flexible y no restringida, respecto a la cual estimamos la eficiencia técnica de cada una de las naves observadas. Nuestros resultados indican que la eficiencia promedio de la flota observada es del 80%, un valor de eficiencia cercano al mejor uso de la tecnología productiva y de los factores de la producción. Las naves más viejas resultaron menos eficientes, un resultado esperado; sin embargo, el tamaño de la cooperativa y calidad de su administración afectó positivamente los valores de eficiencia de las naves asociadas enmascarando con ello el efecto antes mencionado y favoreciendo el desarrollo de economías de escala. Los resultados indican también que el conocimiento acumulativo sobre la pesquería del camarón entre los productores es una variable importante, en términos de su efecto sobre la eficiencia productiva de las naves, mientras que la innovación tecnológica ha sido escasa, excepto por los excluidores de tortugas incorporados a su tecnología de captura durante 1996. Concluimos de nuestro análisis que la divulgación del conocimiento sobre la pesquería, como una variable social de cambio desincorporada a la función de producción, y el fortalecimiento de la calidad de los servicios administrativos, son dos aspectos fundamentales a promover para el desarrollo de esta pesquería. También argumentamos que la semejanza tecnológica y operativa entre ambas flotas, la de San Felipe, B.C. y el resto de la flota del camarón que pesca en el Golfo de California permite que nuestro an

  20. Bolivia. The new nuclear research center in El Alto

    International Nuclear Information System (INIS)

    Nogarin, Mauro

    2016-01-01

    Research reactors in Latin America have become a priority in public policy in the last decade. Bolivia wants to become the 8th country to implement peaceful nuclear technology in this area with the new Center for Research and Development in the Nuclear Technology. The Center will be the most advanced in Latin America. It will provide for a wide use of radiation technologies in agriculture, medicine, and industry. After several negotiations Bolivia and the Russian Federation signed the Intergovernmental Agreement on cooperation in the peaceful use of atomic energy and the construction of the Nuclear Research and Technology Center.

  1. Bolivia. The new nuclear research center in El Alto

    Energy Technology Data Exchange (ETDEWEB)

    Nogarin, Mauro

    2016-05-15

    Research reactors in Latin America have become a priority in public policy in the last decade. Bolivia wants to become the 8th country to implement peaceful nuclear technology in this area with the new Center for Research and Development in the Nuclear Technology. The Center will be the most advanced in Latin America. It will provide for a wide use of radiation technologies in agriculture, medicine, and industry. After several negotiations Bolivia and the Russian Federation signed the Intergovernmental Agreement on cooperation in the peaceful use of atomic energy and the construction of the Nuclear Research and Technology Center.

  2. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

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

  3. 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.

  4. 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.

  5. 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

  6. 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

  7. 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

  8. Processamento da rede neocognitron para reconhecimento facial em ambiente de alto desempenho GPU

    OpenAIRE

    Gustavo Poli Lameirão da Silva

    2007-01-01

    Neste trabalho é apresentada a implementação da Rede Neural Neocognitron, usando uma arquitetura de computação de alto desempenho baseada em GPU (Graphics Processing Unit). O Neocognitron é uma rede neural artificial, proposta por Fukushima e colaboradores, constituída de vários estágios de camadas de neurônios, organizados em matrizes bidimensionais denominadas planos celulares. Para o processamento de alto desempenho da aplicação de reconhecimento facial usando neocognitron foi utilizado o ...

  9. Modelización aplicada al diseño de sistemas de control en el horno alto

    Directory of Open Access Journals (Sweden)

    Rosal, R.

    1995-06-01

    Full Text Available The production of pig iron in blast furnaces resists automatic control strategies due to the lack of knowledge about physical and chemical phenomena taking place inside the reactor. High dimensions lead to important dead times and lags. As a consequence it is very difficult to quantify control actions from actual process measurements. A simplified multizonal mathematical model has been proposed that allowed the description of a given blast furnace excluding hearth. Parameters underlying the model have been identified and, under appropriate assumptions, temperature and composition profiles have been established. The analysis of model predictions has been illustrated with steady-state responses to typical control actions.

    El control del proceso de fabricación de arrabio en hornos altos resulta complejo debido a las condiciones de operación: conocimiento incompleto de la quimicofísica de los procesos que tienen lugar en el interior del homo, grandes dimensiones del reactor que se traducen en tiempos muertos considerables y constantes de tiempo elevadas que provocan una gran inercia a las acciones de control. En este trabajo, se ha planteado un modelo matemático por zonas que permite describir el comportamiento del homo excepto el crisol, se han identificado sus parámetros y se ha obtenido el perfil interno de temperaturas y composiciones. El análisis del modelo permite predecir los efectos de un cambio en cualquier variable del sistema así como desarrollar un algoritmo de control automático.

  10. 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.)

  11. Reactor decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1984-01-01

    A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

  12. RA Reactor

    International Nuclear Information System (INIS)

    1978-02-01

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

  13. Multiregion reactors

    International Nuclear Information System (INIS)

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

    1979-08-01

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

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

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

  15. 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.)

  16. 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)

  17. 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

  18. Los tambos Inca: el caso de Camata Tambo valle alto de Moquegua

    OpenAIRE

    Chacaltana Cortez, Sofía; Ministerio de Cultura

    2013-01-01

    Camata Tambo está ubicado en la parte alta del valle alto de Moquegua. Por este tambo pasa un camino Inca que viene del altiplano y continúa hacia el centro provincial de Sabaya ubicado a 1 km valle abajo.

  19. Motivación y equipos de alto desempeño

    OpenAIRE

    Olaya Gómez, Audrey Yazmin

    2015-01-01

    “Yo hago lo que usted no puede, y usted hace lo que yo no puedo. Juntos podemos hacer grandes cosas” (Teresa de Calcuta).El objetivo de este ensayo es reconocer que en un equipo de alto desempeño se requiere tanta motivación a nivel personal. 

  20. Schooling and Critical Citizenship: Pedagogies of Political Agency in El Alto, Bolivia

    Science.gov (United States)

    Lazar, Sian

    2010-01-01

    This article explores the formation of citizenship as social practice in a school in El Alto, Bolivia. I examine interactions between "banking" forms of education, students' responses, and embodied practices of belonging and political agency, and argue that the seemingly passive forms of knowledge transmission so criticized by critical…

  1. Esporte de alto rendimento: reflexões psicanalíticas e utópicas

    Directory of Open Access Journals (Sweden)

    Mariana Hollweg Dias

    2012-01-01

    Full Text Available Este artigo busca fazer uma análise a respeito do esporte de alto rendimento a partir dos referenciais teóricos da Psicanálise e dos Estudos Utópicos, partindo do princípio de que a lógica do esporte de alto rendimento na contemporaneidade reverbera a lógica do laço social. A exigência da "alta performance" sempre é uma das características de nossa época que estão fortemente presentes no discurso do esporte de alto rendimento e que muitas vezes são fonte de padecimento para os sujeitos, atletas ou não. Apesar disso, o esporte ainda tem muito a contribuir na nossa sociedade, e a aposta deste trabalho é no que foi chamado utopia esportiva, que preconiza o acento na busca da superação mais do que o resultado final necessariamente no lugar mais alto do pódio.

  2. Changes without changes: the Puebla's Alto Atoyac sub-basin case in Mexico

    NARCIS (Netherlands)

    Bressers, Johannes T.A.; Casiano Flores, Cesar Augusto

    2015-01-01

    Since the year 2000, actions at the three governmental levels have taken place to improve water quality in Mexico’s Puebla Alto Atoyac sub-basin. This paper reports a situation in which several policy actors have been striving for water quality improvement in that polluted sub-basin. However, when

  3. 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

  4. Reactor container

    International Nuclear Information System (INIS)

    Naruse, Yoshihiro.

    1990-01-01

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

  5. 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

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Garabedian, G.

    1988-01-01

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

  7. Nuclear reactor

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  8. 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

  9. Production and study of fission fragments, from Lohengrin to Alto; Production et etude des fragments de fission, de Lohengrin a Alto

    Energy Technology Data Exchange (ETDEWEB)

    Ibrahim, F

    2005-06-15

    The study of nuclei far from stability is constitutive of the history of nuclear physics at its very beginning and has been making considerable great strides since then. The study of these nuclei give the opportunity to reach new information on the nuclear structure and thus to measure the solidity of our knowledge on nuclear matter and its validity when it is pushed to its limits. The reaction selected for the production of exotic nuclei in the framework of the PARRNe program is the fission of uranium 238. The nuclei produced have an intermediate mass and are very rich in neutrons. The technique to recover them in order to accelerate them is the thick target method called also the Isol technique. The installation of the ancient Lep injector at the Tandem line in Orsay (IPN) is expected to increase by a factor 100 the production rate of exotic nuclei in the PARRNe program, it is the Alto project. The work presented here concerns studies carried out at the Lohengrin spectrometer installed at the ILL in Grenoble, and at the Tandem installation in Orsay. This document is divided into 4 parts: 1) in flight techniques at Lohengrin, 2) the Isol technique, 3) magic numbers in the domain N=50, and 4) the Alto project.

  10. Tromboembolismo pulmonar masivo de alto riesgo asociado a foramen oval permeable

    Directory of Open Access Journals (Sweden)

    Antonio Miranda

    2012-04-01

    Full Text Available La alta mortalidad de los pacientes con tromboembolismo pulmonar masivo de alto riesgo amerita un enfoque terapéutico enérgico e invasivo que incluya la embolectomía pulmonar quirúrgica en aquellos pacientes con contraindicación para trombolisis o trombolisis fallida. Describimos un caso de tromboembolismo pulmonar masivo de alto riesgo que recibió tratamiento quirúrgico en vez de trombolisis debido a que al momento del diagnóstico presentaba un trombo móvil a través de un foramen oval permeable con altísima posibilidad de embolismo paradójico arterial.

  11. Metodologia de avaliação e desenvolvimento de grupos de alto desempenho

    Directory of Open Access Journals (Sweden)

    Ana Cristina Carneiro

    2008-11-01

    Full Text Available Este artigo discute a fundamentação teórica do Projeto de Avaliação e Desenvolvimento de Grupos de Alto Desempenho, concebido com base na metodologia da Meta-aprendizagem, e no Modelo Evolutivo, estendido à luz da Teoria da Complexidade. Visa ao desenvolvimento e aplicação de uma metodologia de avaliação/constituição de grupos de alto desempenho no ambiente de pesquisa e pós-graduação. A metodologia proposta validada empiricamente teve base no aproveitamento das virtudes e potencialidades das teorias que lhe deram origem. É destinado aos docentes e pesquisadores de vários campos do conhecimento, bem como aos dirigentes de instituições de educação superior e de pesquisa.

  12. Event review: International Knapping Workshop, with Bruce Bradley, Fazenda Monte Alto, Dourado, SP (Brazil

    Directory of Open Access Journals (Sweden)

    Elisa Theodora Adriana van Veldhuizen

    2016-07-01

    Full Text Available The event took place from 3 till 8 July 2016 at Fazenda Monte Alto, Dourado, SP, Brazil. The aim of the course was to provide intensive knapping training in order to enhance analytical methods and procedures. This training was not only for students, but also professionals who were interested in the course. The course was given by Bruce Bradley (University of Exeter, who has extensive experience with Stone Age technologies and experimental archaeology. Mercedes Okumura (PPGArq, National Museum, Federal University of Rio de Janeiro and Astolfo G. M. Araujo (Museum of Archaeology and Ethnology, University of São Paulo organized the course, which was sponsored by Fazenda Monte Alto, Café Helena, and the British Academy, Newton Mobility Grants Scheme (NG140077. The workshop had 15 participants from Brazil, Uruguay, the Netherlands and Canada.

  13. El 'ayllu' reterritorializado, y su 'taypi'. La ciudad de El Alto.

    Directory of Open Access Journals (Sweden)

    Orlando Augusto Yépez Mariaca

    2010-05-01

    Twenty-five years a suburb of La Paz, now the city of El Alto, the heat of the capital's neoliberal policies, implodes in the urban area provided by flat topography as opposed to La Paz, to become today in a city with larger population and greater extent than its parent. With a population of mostly Aymara-Indian-moving and rich in its live, old traditions of the Andean Community institution like Ayllu and Aini, among others. On October 2003, the city of El Alto, the epicenter of a massive social upheaval, becoming the leader of the anti-globalization social movements. Will the 'pachakuti' "return" of the ancient traditions originate? The shop is above all 'live together', and perhaps a light at the end of the tunnel, a tunnel that big business has been built so arrogant and conceited, leaving cities now fragmented, unbalanced territories and a planet on the brink of collapse.

  14. Sonido espacial para una inmersión audiovisual de alto realismo

    Directory of Open Access Journals (Sweden)

    Basilio Pueo Ortega

    2012-04-01

    Full Text Available Los sistemas de vídeo y audio de alta inmersión tienen un auge impor-tante en entornos audiovisuales realistas. Las sensaciones visuales y sonoras que crean en el público se aproximan con un alto grado de similitud a lo percibido en el entorno real que pretenden recrear. Para ello, los estímulos deben contener toda la información necesaria, tanto espacial como temporal, que permita crear la ilusión de que el objeto audiovisual es real. En este artículo, se realiza un repaso de los sistemas audiovisuales que permiten esta recreación, con especial atención en los sistemas de audio envolvente. Se describe la técnica de audio 3D más prometedora, Wave Field Synthesis, junto con diversos campos de aplicación de entornos audiovisuales de alto realismo.

  15. Slurry reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    1979-08-01

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

  16. Reactor safety

    International Nuclear Information System (INIS)

    Butz, H.P.; Heuser, F.W.; May, H.

    1985-01-01

    The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

  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. Reactor container

    International Nuclear Information System (INIS)

    Kato, Masami; Nishio, Masahide.

    1987-01-01

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

  19. RA Reactor

    International Nuclear Information System (INIS)

    1989-01-01

    This chapter includes the following: General description of the RA reactor, organization of work, responsibilities of leadership and operators team, regulations concerning operation and behaviour in the reactor building, regulations for performing experiments, regulations and instructions for inserting samples into experimental channels [sr

  20. Reactor physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1998-01-01

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

  1. The Interactive Dimension of Communication: The Pragmatics of the Palo Alto Group

    OpenAIRE

    Codruţa Porcar; Cristian Hainic

    2011-01-01

    Our paper proposes to analyze from a semiotic perspective the process of communication as conceived within the Palo Alto Group. We will firstly show that, as a result of the Group's critiques and revisions of the linear or mechanistic theories of communication, new perspectives are brought about for the essential axes of transformation within communication: we do not communicate as from a distinct atom to another, through an isolated channel, but through parts which are equal to the whole, th...

  2. Reactor core

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

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

  3. Reactor container

    International Nuclear Information System (INIS)

    Fukazawa, Masanori.

    1991-01-01

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

  4. Reactor container

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  5. 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

  6. Reactor building

    International Nuclear Information System (INIS)

    Maruyama, Toru; Murata, Ritsuko.

    1996-01-01

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

  7. Reactor container

    International Nuclear Information System (INIS)

    Shibata, Satoru; Kawashima, Hiroaki

    1984-01-01

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

  8. Calidad de los servicios de anticoncepción en El Alto, Bolivia The quality of contraception services in El Alto, Bolivia

    Directory of Open Access Journals (Sweden)

    Carmen Velasco

    1999-06-01

    Full Text Available El presente estudio tuvo por objetivo evaluar la calidad de los servicios de anticoncepción en la ciudad de El Alto, Bolivia. En su diseño se han contemplado cuatro elementos: 1 las relaciones entre los proveedores de servicios y sus clientes, 2 la disponibilidad de métodos anticonceptivos, 3 las condiciones de los servicios, y 4 la satisfacción de las usuarias. También se han tenido en cuenta las opiniones de los proveedores y de las usuarias y no usuarias de estos servicios, quienes se clasificaron como gubernamentales o no gubernamentales, de acuerdo con la administración de la institución a la que pertenecían. Los datos provinieron de un análisis de la situación de dichos servicios y de testimonios obtenidos de las participantes durante 1995. En cuanto a las relaciones interpersonales, se encontró que los proveedores percibían el trato del médico más favorablemente que las clientas, en tanto que las no usuarias lo percibían desfavorablemente. La percepción de un trato igualitario se correlacionó positivamente con la vestimenta que usaban las clientas. En cuanto a la disponibilidad de los métodos anticonceptivos, 15 de las 36 instituciones encuestadas no disponían de métodos modernos, a pesar de la existencia de una política nacional para proveerlos a la población. La oferta de estos servicios a parejas y a adolescentes es escasa, principalmente en las instituciones gubernamentales. El análisis de las condiciones de los servicios demostró que en algunas instituciones había problemas graves en la provisión de una atención de mínima calidad. Finalmente, este trabajo describe cómo la mayoría de estas limitaciones en la prestación de servicios de anticoncepción en El Alto pueden subsanarse mediante estrategias de costo moderado.The objective of this study was to evaluate the quality of contraception services in the city of El Alto, Bolivia. In the study design, four components were considered: 1 interpersonal

  9. 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

  10. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    A nuclear reactor containment vessel faced internally with a metal liner is provided with thermal insulation for the liner, comprising one or more layers of compressible material such as ceramic fiber, such as would be conventional in an advanced gas-cooled reactor and also a superposed layer of ceramic bricks or tiles in combination with retention means therefor, the retention means (comprising studs projecting from the liner, and bolts or nuts in threaded engagement with the studs) being themselves insulated from the vessel interior so that the coolant temperatures achieved in a High-Temperature Reactor or a Fast Reactor can be tolerated with the vessel. The layer(s) of compressible material is held under a degree of compression either by the ceramic bricks or tiles themselves or by cover plates held on the studs, in which case the bricks or tiles are preferably bedded on a yielding layer (for example of carbon fibers) rather than directly on the cover plates

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    Miyashita, Akio.

    1981-01-01

    Purpose: To facilitate and accelerate a leakage test of valves of a main steam pipe by adding a leakage test partition valve thereto. Constitution: A leakage testing partition valve is provided between a pressure vessel for a nuclear reactor and the most upstream side valve of a plurality of valves to be tested for leakage, a testing branch pipe is communicated with the downstream side of the partition valve, and the testing water for preventing leakage is introduced thereto through the branch pipe. Since main steam pipe can be simply isolated by closing the partition valve in the leakage test, the leakage test can be conducted without raising or lowering the water level in the pressure vessel, and since interference with other work in the reactor can be eliminated, the leakage test can be readily conducted parallel with other work in the reactor in a short time. Clean water can be used without using reactor water as the test water. (Yoshihara, H.)

  12. Reactor container

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  13. 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.

  14. 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.

  15. Breeder reactors

    International Nuclear Information System (INIS)

    Gollion, H.

    1977-01-01

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

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Schulze, I.; Gutscher, E.

    1980-01-01

    The core contains a critical mass of UN or U 2 N 3 in the form of a noncritical solution with melted Sn being kept below a N atmosphere. The lining of the reactor core consists of graphite. If fission progresses part of the melted metal solution is removed and cleaned from fission products. The reactor temperatures lie in the range of 300 to 2000 0 C. (Examples and tables). (RW) [de

  17. 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.)

  18. Reactor containment

    International Nuclear Information System (INIS)

    Kawabe, Ryuhei; Yamaki, Rika.

    1990-01-01

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

  19. Fast reactors

    International Nuclear Information System (INIS)

    Vasile, A.

    2001-01-01

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

  20. Calidad del coque de Horno Alto en la Unión Europea

    Directory of Open Access Journals (Sweden)

    Alvarez, R.

    2002-10-01

    Full Text Available After a brief review of the coking technology at the beginning of the new millennium, blast furnace coke quality criteria of most of EU countries, presented by the European Blast Furnace Committee in the 4th European Coke and Ironmaking Congress, are compared with those used by the Spanish Steel Industry at Aceralia. Blast furnace coke quality is very high in EU's countries in order to meet the requirements of bigger blast furnaces commissioned in the last years. CSR index is the most important parameter in the control of coke quality in Europe.

    En el presente trabajo se ha llevado a cabo una breve revisión de las tecnologías de coquización existentes al comienzo del nuevo milenio. Los criterios de calidad del coque de Horno Alto de la mayoría de los países de la Unión Europea, recogidos por el European Blast Furnace Committee, y que fueron presentados en el 4th European Coke and Ironmaking Congress en París durante el año 2000, se comparan con los utilizados por la industria siderúrgica española Aceralia. Como consecuencia del sensible aumento experimentado en el tamaño de los modernos Hornos Altos durante los últimos años, se ha podido comprobar que, en la UE, los valores de los diversos parámetros de control de calidad del coque son bastante similares y con unos requerimientos muy elevados. Asimismo, en la UE el parámetro CSR se ha convertido en el más importante para el control de la calidad del coque de Horno Alto.

  1. Estudio microbiológico de los alimentos elaborados en comedores colectivos de alto riesgo

    Directory of Open Access Journals (Sweden)

    Pérez-Silva García Mª del Carmen

    1998-01-01

    Full Text Available FUNDAMENTO: Valorar los resultados del análisis microbiológico de los alimentos preparados en comedores colectivos de alto riesgo, con el fin de conocer el grado de contaminación de los alimentos, analizar las causas de dicha contaminación y mejorar la situación sanitaria de estos establecimientos. MÉTODOS: Estudio observacional descriptivo con los datos obtenidos de la inspección sanitaria en 44 comedores colectivos de alto riesgo, que incluyó el análisis microbiológico de 90 alimentos, así como la inspección sanitaria de los establecimientos. RESULTADOS: En los colegios los microorganismos mesófilos fueron los contaminantes más frecuentes; en las guarderías y residencias de ancianos predominaron los indicadores de higiene deficiente en la manipulación de alimentos. Los microorganismos mesófilos se encontraron durante los meses fríos en mayor proporción que durante los meses cálidos. Los indicadores de higiene deficiente aparecieron generalmente en los alimentos preparados en establecimientos en los que se observaron deficiencias. Los microorganismos psicrótrofos no se encontraron en ninguno de los alimentos recogidos en guarderías y sí en colegios y residencias de ancianos. CONCLUSIONES: Este estudio indica qué problemas predominan en cada tipo de comedor colectivo de alto riesgo. Los mesófilos aparecen en los alimentos elaborados en cocinas de tamaño grande, los indicadores de higiene deficiente se encontraron asociados a una manipulación de alimentos por personal no profesional y a establecimientos con deficiencias, y los psicrótrofos se detectaron en aquellos establecimientos que guardan la comida sobrante. Se sugieren recomendaciones para la eliminación de los problemas detectados.

  2. Rb-Sr measurements on metamorphic rocks from the Barro Alto Complex, Goias, Brazil

    International Nuclear Information System (INIS)

    Fuck, R.A.; Neves, B.B.B.; Cordani, U.G.; Kawashita, K.

    1988-01-01

    The Barro Alto Complex comprises a highly deformed and metamorphosed association of plutonic, volcanic, and sedimentary rocks exposed in a 150 x 25 Km boomerang-like strip in Central Goias, Brazil. It is the southernmost tip of an extensive yet discontinuous belt of granulite and amphibolite facies metamorphic rocks which include the Niquelandia and Cana Brava complexes to the north. Two rock associations are distinguished within the granulite belt. The first one comprises a sequence of fine-grained mafic granulite, hypersthene-quartz-feldspar granulite, garnet quartzite, sillimanite-garnet-cordierite gneiss, calc-silicate rock, and magnetite-rich iron formation. The second association comprises medium-to coarse-grained mafic rocks. The medium-grade rocks of the western/northern portion (Barro Alto Complex) comprise both layered mafic rocks and a volcanic-sedimentary sequence, deformed and metamorphosed under amphibolite facies conditions. The fine-grained amphibolite form the basal part of the Juscelandia meta volcanic-sedimentary sequence. A geochronologic investigation by the Rb-Sr method has been carried out mainly on felsic rocks from the granulite belt and gneisses of the Juscelandia sequence. The analytical results for the Juscelandia sequence are presented. Isotope results for rocks from different outcrops along the gneiss layer near Juscelandia are also presented. In conclusion, Rb-Sr isotope measurements suggest that the Barro Alto rocks have undergone at least one important metamorphic event during Middle Proterozoic times, around 1300 Ma ago. During that event volcanic and sedimentary rocks of the Juscelandia sequence, as well as the underlying gabbro-anorthosite layered complex, underwent deformation and recrystallization under amphibolite facies conditions. (author)

  3. Simulación clínica de alto realismo: una experiencia en el pregrado

    Directory of Open Access Journals (Sweden)

    Javier Riancho

    Full Text Available Introducción. La simulación con modelos de alto realismo se utiliza a menudo en la formación de los profesionales sanitarios. Sin embargo, son escasas las experiencias en el pregrado. El objetivo de este trabajo fue conocer la factibilidad y la aceptación de su aplicación con estudiantes de sexto curso de la licenciatura de Medicina. Materiales y métodos. Se diseñaron ocho escenarios que simulaban problemas clínicos frecuentes para su desarrollo con maniquíes de alto realismo. Los estudiantes se dividieron en grupos de 6-8 sujetos, cada uno de los cuales atendió dos casos durante 30 minutos. Posteriormente se llevó a cabo un análisis reflexivo durante 25-40 minutos. La actividad se repitió en dos años consecutivos. Al final se recabó la opinión de los estudiantes mediante encuestas anónimas. Resultados. La actividad fue valorada muy positivamente por los estudiantes, quienes la consideraron como "útil" (4,8 y 4,9 puntos sobre 5 e "interesante" (4,9 y 4,9 puntos. El tiempo preciso para preparar cada escenario fue de unas 3 horas. Fueron necesarias una jornada completa de un profesor, un técnico y un enfermero para que un colectivo de unos 40 estudiantes se expusiera a dos casos clínicos. Conclusiones. Esta experiencia piloto sugiere que la simulación de alto realismo es factible en el pregrado, supone un consumo razonable de recursos y tiene una elevada aceptación por parte de los estudiantes. No obstante, se necesitan otros estudios que confirmen la impresión subjetiva de que resulta útil para potenciar el aprendizaje de los alumnos y su competencia clínica.

  4. Generation IV reactors: reactor concepts

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  5. 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

  6. Estudio del balance energético en velocistas de alto rendimiento

    OpenAIRE

    Lorente Gutiérrez, Jesús

    2015-01-01

    El objetivo de este estudio fue evaluar el balance energético en tres atletas de alto rendimiento durante 28 días, que coincidieron con el periodo competitivo de pista cubierta. La ingesta energética fue estudiada a partir de registros alimentarios durante los 28 días. Del mismo modo, el gasto energético fue estimado por tres métodos, mediante registros de actividad durante 28 días, mediante el estudio del ritmo metabólico basal estudiado por calorimetría indirecta, aplicándole el fa...

  7. Manual de auditoría interna para Instituto de Altos Estudios Nacionales

    OpenAIRE

    Bungacho Lamar, Fredy, Dr.

    2010-01-01

    La Ley Orgánica de Administración Financiera y Control responsabiliza a cada institución del Estado la implementación y aplicación del Sistema de Control Interno con la finalidad de precautelar los recursos públicos. Este trabajo investigativo sirve como guía para unificar los procedimientos, en la ejecución de las Auditoría de los profesionales que integren la Unidad de auditoría Interna del Instituto de altos Estudios Nacionales. Este Manual de Auditoría Interna, se compone de 6 capí...

  8. Assessing impact of hunting mammals in Alto Itaya river basin, Peruvian Amazon

    OpenAIRE

    Aquino, Rolando; Terrones, C.; Navarro, R.; Terrones, Wagner

    2013-01-01

    En el presente trabajo se informa sobre la abundancia, presión de caza y el impacto de la caza en mamíferos que habitan los bosques de la cuenca del río Alto Itaya. La información procede de censos por transectos y registros de caza llevados a cabo en seis comunidades. Entre los mamíferos de caza, el choro (Lagothrix poeppigii Schinz) fue el más abundante con 15,4 individuos/km², mientras que el mono aullador (Alouatta seniculus Linnaeus) y el venado colorado (Mazama americana Erxleben) fuero...

  9. PARSJAD, il Parco Archeologico dell’Alto Adriatico: un luogo diffuso, unito dalla tecnologia

    Directory of Open Access Journals (Sweden)

    Emilia Buniotto

    2014-05-01

    Full Text Available Eight partners, coordinated by the Veneto Region, are working on an ambitious project with an innovative approach and tools, and with the ability to conserve content and exploit the immense archaeological heritage of the area concerned.This was the birth of the Parco Archeologico dell’Alto Adriatico (Upper Adriatic Archaeological Park, a project funded by the Italy‐Slovenia 2007-2013 Cooperation Programme, with the aim of tracing a unified and cross-border pathof knowledge running from the coast of Emilia to the one in Slovenia.

  10. Panstrongylus megistus em ecótopos artificiais de ilhas do Alto Rio Paraná

    Directory of Open Access Journals (Sweden)

    Guilherme Ana Lucia Falavigna

    2001-01-01

    Full Text Available Em resposta a denúncias de triatomíneos em ilhas do Alto Rio Paraná foram investigados 145 ecótopos artificiais e 4 (2,8% deles encontravam-se infestados: residência, "clube", ex-escola e monte de madeira. Foram analisados 17 de 35 P. megistus coletados; 12 (70,6% apresentavam-se infectados por Trypanosoma cruzi. Ave e roedor constituíram as fontes alimentares mais comuns. Todos os exames sorológicos (56 de humanos, 18 de cães e 10 de gatos foram negativos.

  11. Sentidos de Vitória/Derrota para os Pais Segundo Atletas do Alto Rendimento

    OpenAIRE

    Amblard, Isabela; Cruz, Fatima Leite

    2015-01-01

    Este estudo compreendeu as representações sociais da vitória/derrota para os pais segundo atletas-adolescentes do esporte de alto rendimento, na cidade do Recife. A adolescência é compreendida a partir da Psicologia Social-histórica, e o embasamento teórico-metodológico da Teoria das Representações Sociais abordou os sujeitos em diferentes contextos socioculturais, lugares de pertencimento, experiências, crenças, saberes e sentimentos compartilhados. Adotou-se a perspectiva pluri metodológica...

  12. Projeto : Plano de promoção para os roteiros municipais do Alto Alentejo

    OpenAIRE

    Dimas, Alicia

    2012-01-01

    Dissertação de Mestrado em Marketing e Promoção Turística apresentada à ESTM - Escola Superior de Turismo e Tecnologia do Mar do Instituto Politécnico de Leiria O presente projeto pretende delinear as linhas mestras de um plano de promoção para o produto Roteiros Municipais. O produto, cujo objetivo é auxiliar a atividade turística na região do Alto Alentejo (Portugal), foi colocado recentemente no mercado sem qualquer estratégia de marketing associada – este projeto pretende preencher ess...

  13. Invernaderos sostenibles para la producción de hortalizas en zonas alto andinas del Cusco

    OpenAIRE

    Zanabria Pacheco, Pedro Fortunato

    2015-01-01

    La investigación tiene como objetivo determinar la importancia en el uso de los invernaderos sostenibles para la producción de hortalizas en las zonas alto andinas del Curso. Para ello, se han diseñado y construido dos prototipos de invernaderos a 3330 msnm, variando la orientación y forma del techo, permitiendo la producción de hortalizas en la estación fría. A la vez está investigación servirá como base para aplicar el proyecto sobre la tecnología de producción sostenible de hortalizas bajo...

  14. Trastorno de espectro autista de alto funcionamiento y su relación con la familia

    OpenAIRE

    González Villafáñez, María Felisa

    2014-01-01

    El objetivo de este trabajo consiste en analizar las dificultades que tienen los adolescentes con Trastorno del Espectro Autista de Alto Funcionamiento (TEA-AF), en sus relaciones sociales y familiares. Este análisis ha requerido la revisión de las diversas definiciones y teorías explicativas del citado trastorno. A su vez también se describen las terapias conocidas hasta hoy para crear un programa de apoyo a los familiares (padres, hermanos, abuelos…) que se relacionan con dicho adolescente....

  15. Prevalencia de trastornos psicológicos en deportistas españoles de alto rendimiento

    OpenAIRE

    Marí Cortés, Josep; Pérez Recio, Guillermo

    1997-01-01

    El artículo compara la prevalencia de psicopatologías en una muestra de 1376 deportistas españoles de alto rendimiento con la incidencia de las mismas alteraciones psicológicas en la población general. Para explicar la prevalencia hallada en la muestra de deportistas, se sugieren y analizan tres hipótesis (la autoselección, el efecto psicológico beneficioso la práctica de actividad física y la generalización, a los conflictos personales, de las pautas de enfrentamiento que han resultado previ...

  16. Conservation and public presentation of the argaric site of Castellón Alto (Galera, Granada

    Directory of Open Access Journals (Sweden)

    Rodríguez-Ariza, M. Oliva

    2000-12-01

    Full Text Available The magnificent preservation of the archaeological site of Castellón Alto permitted reconstruction of the urbanism of this settlement and the life of its inhabitants. In addition to the necessary conservation, two interventions have been carried out with the principal objective of facilitating access, visiting, and the understanding of the site by the majority of the public. The first intervention happened in 1989 and the main task was centered on the consolidation, restoration, and delimiting of the archaeological bed. The second one happened in 1997 and was centered in the consolidation and reconstruction of both a hut and two tombs. With the opening of the Archaeological Museum of Galera, the cultural and touristic contribution of Castellón Alto will be complete. It will provide an interpretation of this prehistoric village, as well as the Argaric culture in general and all the other archaeological sites of the area.

    La magnífica conservación del registro arqueológico del Castellón Alto permitía reconstruir el urbanismo del poblado y la vida de estas poblaciones. Se han efectuado dos actuaciones con el objetivo principal de facilitar, además de la necesaria conservación, el acceso, la visita y la comprensión del poblado prehistórico por parte de un público mayoritario. La primera actuación se realizó en 1989 y los trabajos se centraron principalmente en la consolidación, restauración y cerramiento del área del yacimiento. La segunda se realizó en 1997 y se centró en el acondicionamiento y reconstrucción de una cabaña y dos sepulturas. La oferta turística y cultural que ofrece el Castellón Alto se completará con la próxima apertura del Museo Arqueológico de Galera, donde se efectuará una interpretación de este poblado y de la cultura argárica, así como del resto de yacimientos de la zona.

  17. Nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-05-10

    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.

  18. 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)

  19. 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.

  20. Grave number 121 of the argaric site of Castellón Alto (Galera, Granada

    Directory of Open Access Journals (Sweden)

    Molina, Fernando

    2003-06-01

    Full Text Available A new grave with partly mummified bodies was discovered during fieldwork to prepare the argaric site of Castellón Alto for public visits. Timber slabs and a dry stone wall seal the artificial cave preserving the interior. The human bones belong to one adult and one infant, both with preserved hair and skin fragments. The grave goods comprise several pottery vessels, one dagger, one ax with wooden handle, metal ornaments and fragments of flax and possibly wool.

    Recientes excavaciones en el yacimiento argárico de Castellón Alto con motivo de los trabajos de acondicionamiento para su visita publica han permitido descubrir una sepultura con restos humanos momificados en su interior. La sepultura de tipo covacha se encontraba sellada por tablones de madera y un muro de mampostería. En el interior aparecieron un individuo adulto y un infantil que conservan restos de pelo y piel. El ajuar se compone de varias vasijas cerámicas, un puñal, una azuela con mango de madera y adornos en metal, así como restos de lino y posiblemente lana.

  1. Litho-structural and geophysics features of the Alto Paranaiba Uplift

    International Nuclear Information System (INIS)

    Hasui, Y.

    1991-01-01

    The Alto Paranaiba Uplift (APU) is an almost elliptical tectonic feature of the Western Minas Gerais/Southern Goias region, which was active mostly during the Cretaceous. It separated the Parana Basin, during the formation of the Sao Bento, Uberaba and Bauru sequences, from the Alto-Sanfranciscana Basin, at the time of formation of the Areado, Patos, Capacete and Urucuia sequences. The Bouguer anomaly data indicate that the APU developed at the southwestern border of the ancient Brasilia crustal block and is represented by an almost elliptical gravity high of 15 mgal, locally disturbed by positive and negative the presence of important lineaments of a NW-SE set, mostly crossing the southwestern half of the APU. The APU development, the magmatism and the lateral basin formation involved reactivation of preexisting discontinuities and are related to a mantle plume. The tectonic development was aborted at the uplift stage during Cretaceous, after the deposition of the Bauru and Urucuia sequences, as is indicated by the Pratinha peneplane, now elevated at about 1.100 m altitude, which sculpture ended at the beginning of the Tertiary. The APU is one tectonic feature like other similar anomalies also aborted in the uplift stage or in the rift stage, which developed in Southern Brazil during the time of Atlantic Ocean opening. (author)

  2. Control Neuroborroso en Red. Aplicación al Proceso de Taladrado de Alto Rendimiento

    Directory of Open Access Journals (Sweden)

    Agustín Gajate

    2009-01-01

    Full Text Available Resumen: Este trabajo muestra el diseño y la implementación de un sistema neuroborroso para el modelado y control en red de un proceso de taladrado de alto rendimiento. El sistema neuroborroso considerado en este estudio es el conocido como Adaptive Network based Fuzzy Inference System (ANFIS, en el que las reglas borrosas se obtienen a partir de datos entrada/salida. Para el diseño del sistema de control se ha elegido el paradigma del control por modelo interno. Los resultados obtenidos son positivos tanto en la simulación como en la aplicación al control en red de la fuerza de corte. Desde el punto de vista técnico, se aumenta la tasa de arranque de material y al mismo tiempo se garantiza un aprovechamiento efectivo de la vida útil de la herramienta de corte. Este buen comportamiento del sistema de control neuroborroso basado en control por modelo interno se ha verificado por medio de varias cifras de mérito. Palabras clave: sistemas neuroborrosos, control por modelo interno, control en red, taladrado de alto rendimiento

  3. Structure of neutron rich nuclei of Germanium and Gallium beyond N equals 50 at Alto

    International Nuclear Information System (INIS)

    Lebois, M.

    2008-09-01

    The gamma rays following the beta decay of the following very neutron-rich isotopes: 82,83,84 Ga produced by photo-fission, have been studied at the newly built ISOL facility in Orsay: ALTO. In ALTO the interaction of an electron beam with U 238 target generates a continuous spectra of Bremsstrahlung gamma radiation that triggers U 238 fission. The fission fragments are then ionized, extracted and mass-separated. The analysis of the data has shown the existence of an isomer in 31 84 Ga 53 and has enabled us to confirm known results on 32 83 Ge 51 energy levels including the gamma transition between the 1/2+ state at 247,7 KeV and the fundamental state. We have also proposed the first energy level scheme for 33 84 As 51 . In order to understand the structure of the nucleus we have used the Thankappan and True model that gives a description of the coupling between the pair-pair core (half-magical) and the single nucleon. This model applied to the N=51 chain ( 38 89 Sr 51 , 36 87 Kr 51 , 34 85 Se 51 , 32 83 Ge 51 and 30 81 Zn 51 ) has allowed us to see the main features of odd isotope structure. We have also confirmed previous results concerning the nature of the states in the following decay 31 83 Ga 52 → 32 83 Ge 51

  4. Conservation and valorisation of Giovanni Boccaccio’s house museum in Certaldo Alto

    Directory of Open Access Journals (Sweden)

    Massimo Gennari

    2012-04-01

    Full Text Available The architectural restoration and functional redevelopment of Boccacio’s house in Certaldo Alto (Florence, has been carried out between 2006 and 2007 and finalized in 2011, including the reconstruction of the garden next to the house. The program which has been characterized by a strong civic, social and cultural involvement, is lead by the Ente Nazionale G. Boccaccio in partnership whit the local administration and aims at contributing to the valorization of the historical, architectural and cultural heritage of the historic center of Certaldo Alto. Valorization here is intended as a functional integration and synergy between predominantly cultural activities. The aim is to achieve the best results in terms of social development as well as intellectual growth within a virtuous economy, and therefore the construction of a complementary model for cultural assets in general. A model where the single cultural elements (museums, libraries, workrooms, exhibitions, auditorium, etc.. represent only the intersections of a wider net system established through the process of communication and exchange with the institutions, publics or privates, that operate in the sectors of research, experimentation, education and information. This means that the management of cultural assets will now aim mainly at the interaction between its components and nationals as well as international structures of education and research, institutes for the social and economical development and innovative business structures in the fields of communication and cultural and sustainable tourism. This establishes an additional value of his still underestimated significance.

  5. Saúde reprodutiva e mulheres indígenas do Alto Rio Negro

    Directory of Open Access Journals (Sweden)

    Marta Azevedo

    Full Text Available O presente artigo descreve e analisa as concepções próprias das mulheres indígenas do Alto Rio Negro sobre saúde reprodutiva, relacionando-as a indicadores de fecundidade. As informações qualitativas apontam para um conhecimento detalhado e complexo que as mulheres indígenas dessa região possuem sobre seu corpo e os cuidados com sua saúde. Os níveis e padrões etários da fecundidade estão relacionados com a etnia das mulheres, portanto, aos sistemas tradicionais de cuidados com a saúde desses povos. A pesquisa foi desenvolvida entre 1997 e 2003, na região de Iauaretê, Terra Indígena Alto Rio Negro (AM, e teve como primeira fonte de dados o Censo Indígena Autônomo do Rio Negro - CIARN-, levado a efeito pela Federação das Organizações Indígenas do Rio Negro - FOIRN - em 1992.

  6. Numerical modelling of Alto Verde landslide using the material point method

    Directory of Open Access Journals (Sweden)

    Marcelo Alejandro Llano-Serna

    2015-01-01

    Full Text Available Finalizando el año 2008 en la ciudad de Medellín, Colombia, ocurrió un deslizamiento de tierra en la urbanización Alto Verde provocando la muerte de doce personas y la destrucción de seis viviendas. Los deslizamientos se destacan por el elevado nivel de deformaciones en una masa de suelo. El presente trabajo utilizó el método del punto material (MPM, método basado en partículas que utiliza una doble discretización Lagrangiano-Euleriana. La doble discretización genera un marco numérico robusto que permite la simulación de grandes distorsiones. El modelo numérico planteó una simplificación de las condiciones geotécnicas, morfológicas y estructurales de las edificaciones envueltas en Alto Verde. El estado de deformación final de la simulación se acomodó satisfactoriamente a las características geométricas finales observadas en campo. Los resultados obtenidos generan aplicaciones como el diseño de barreras, análisis de riesgo o la determinación de la distancia mínima de retiro a una ladera susceptible de deslizamiento.

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    Scholz, M.

    1976-01-01

    An improvement of the accessibility of that part of a nuclear reactor serving for biological shield is proposed. It is intended to provide within the biological shield, distributed around the circumference of the reactor pressure vessel, several shielding chambers filled with shielding material, which are isolated gastight from the outside by means of glass panes with a given bursting strength. It is advantageous that, on the one hand, inspection and maintenance will be possible without great effort and, on the other, a large relief cross section will be at desposal if required. (UWI) [de

  8. NEUTRONIC REACTOR

    Science.gov (United States)

    Wigner, E.P.; Weinberg, A.W.; Young, G.J.

    1958-04-15

    A nuclear reactor which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The reactor is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.

  9. Aesthetic Communication and Intercultural Perspective. A Qualitative Analysis of Aesthetic Perceptions of the Brand "Südtirol/Alto Adige"

    Directory of Open Access Journals (Sweden)

    Vincenzo Bua

    2009-01-01

    Full Text Available In the qualitative study of mental associations with the brand picture "Südtirol/Alto Adige" different images of the region among German speaking, Italian speaking and bilingually grown up South Tyroleans were analysed. The research interest was focused on the communalities and differences in these associations in order to identify potentially conflicting positions between the two major language groups in Südtirol/Alto Adige. In this paper the method is demonstrated which was used to display and investigate the emotional and cognitive contents of the images to Südtirol/Alto Adige from the point of view of different socio-cultural groups. Additionally selected results connected to the perception of the brand in the multilingual province Südtirol/Alto Adige are shown. Against the background of the outlined study the following questions are dealt with in this article: How is the special design of the brand picture perceived among the different socio-cultural groups in Alto Adige/Südtirol with respect to intercultural communication processes? Which meaning can be attributed to the historical heritage of the language groups in the analysis? URN: urn:nbn:de:0114-fqs0901323

  10. 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

  11. 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

  12. Reactor facility

    International Nuclear Information System (INIS)

    Suzuki, Hiroaki; Murase, Michio; Yokomizo, Osamu.

    1997-01-01

    The present invention provides a BWR type reactor facility capable of suppressing the amount of steams generated by the mutual effect of a failed reactor core and coolants upon occurrence of an imaginal accident, and not requiring spacial countermeasures for enhancing the pressure resistance of the container vessel. Namely, a means for supplying cooling water at a temperature not lower by 30degC than the saturated temperature corresponding to the inner pressure of the containing vessel upon occurrence of an accident is disposed to a lower dry well below the pressure vessel. As a result, upon occurrence of such an accident that the reactor core should be melted and flown downward of the pressure vessel, when cooling water at a temperature not lower than the saturated temperature, for example, cooling water at 100degC or higher is supplied to the lower dry well, abrupt generation of steams by the mutual effect of the failed reactor core and cooling water is scarcely caused compared with a case of supplying cooling water at a temperature lower than the saturation temperature by 30degC or more. Accordingly, the amount of steams to be generated can be suppressed, and special countermeasure is no more necessary for enhancing the pressure resistance of the container vessel is no more necessary. (I.S.)

  13. 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)

  14. 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

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sekine, Katsuhisa.

    1987-01-01

    Purpose: To decrease the thickness of a reactor container and reduce the height and the height and plate thickness of a roof slab without using mechanical vibration stoppers. Constitution: Earthquake proofness is improved by filling fluids such as liquid metal between a reactor container and a secondary container and connecting the outer surface of the reactor container with the inner surface of the secondary container by means of bellows. That is, for the horizontal seismic vibrations, horizontal loads can be supported by the secondary container without providing mechanical vibration stoppers to the reactor container and the wall thickness can be reduced thereby enabling to simplify thermal insulation structure for the reduction of thermal stresses. Further, for the vertical seismic vibrations, verical loads can be transmitted to the secondary container thereby enabling to reduce the wall thickness in the same manner as for the horizontal load. By the effect of transferring the point of action of the container load applied to the roof slab to the outer circumferential portion, the intended purpose can be attained and, in addition, the radiation dose rate at the upper surface of the roof slab can be decreased. (Kamimura, M.)

  16. Reactor system

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Narabayashi, Naoshi.

    1990-01-01

    The represent invention concerns a reactor system with improved water injection means to a pressure vessel of a BWR type reactor. A steam pump is connected to a heat removing system pipeline, a high pressure water injection system pipeline and a low pressure water injection system pipeline for injecting water into the pressure vessel. A pump actuation pipeline is disposed being branched from a main steam pump or a steam relieaf pipeline system, through which steams are supplied to actuate the steam pump and supply cooling water into the pressure vessel thereby cooling the reactor core. The steam pump converts the heat energy into the kinetic energy and elevates the pressure of water to a level higher than the pressure of the steams supplied by way of a pressure-elevating diffuser. Cooling water can be supplied to the pressure vessel by the pressure elevation. This can surely inject cooling water into the pressure vessel upon loss of coolant accident or in a case if reactor scram is necessary, without using an additional power source. (I.N.)

  17. Reactor core

    International Nuclear Information System (INIS)

    Matsuura, Tetsuaki; Nomura, Teiji; Tokunaga, Kensuke; Okuda, Shin-ichi

    1990-01-01

    Fuel assemblies in the portions where the gradient of fast neutron fluxes between two opposing faces of a channel box is great are kept loaded at the outermost peripheral position of the reactor core also in the second operation cycle in the order to prevent interference between a control rod and the channel box due to bending deformation of the channel box. Further, the fuel assemblies in the second row from the outer most periphery in the first operation cycle are also kept loaded at the second row in the second operation cycle. Since the gradient of the fast neutrons in the reactor core is especially great at the outer circumference of the reactor core, the channel box at the outer circumference is bent such that the surface facing to the center of the reactor core is convexed and the channel box in the second row is also bent to the identical direction, the insertion of the control rod is not interfered. Further, if the positions for the fuels at the outermost periphery and the fuels in the second row are not altered in the second operation cycle, the gaps are not reduced to prevent the interference between the control rod and the channel box. (N.H.)

  18. New about research reactors

    International Nuclear Information System (INIS)

    Egorenkov, P.M.

    2001-01-01

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

  19. El deslizamiento de Palo Alto, Turrialba, Costa Rica : apuntes para su estudio

    Directory of Open Access Journals (Sweden)

    Peraldo Huertas, Giovanni

    2015-12-01

    Full Text Available En este trabajo se busca caracterizar, desde un punto de vista geomorfológico y geológico, el deslizamiento de Palo Alto, en el contexto de los megaprocesos de inestabilidad de laderas presentes en las laderas del río Reventazón. El corredor del río Reventazón, entre Turrialba y Siquirres, muestra una serie de procesos complejos de remoción en masa, que generan morfologías típicas de procesos de deslizamiento, tan continuas que dan una apariencia morfológica caótica, donde es difícil definir patrones de movimiento del terreno. El área de inestabilidad de Palo Alto se reconoce fácilmente incluso en el mapa topográfico correspondiente a escala 1:50 000, pues muestra una típica forma en herradura. Los límites del deslizamiento están bien marcados mediante escarpes bien definidos en campo, pero los extremos de las coronas laterales hacia el oeste se desdibujan debido, entre otras cosas, a que en esos sectores queda indefinido el límite al norte con el área de inestabilidad compleja de Bonilla y al sur con el área similar de Guayabo - Lajas. Se efectuó una fotointerpretación del área de estudio, mediante la revisión de fotos aéreas de la línea de vuelo Orosi-Pejibaye, escala 1:20 000 del año 1988, así como fotografías aéreas del proyecto Terra 1998, con el fin de observar posibles cambios en los procesos erosivos, así como en la forma del deslizamiento. Posteriormente, se realizó trabajo de campo para revisar la morfología fotointerpretada, analizar la conformación geológica a nivel de litología y estructura y así afinar la interpretación final de la geomorfología del área inestable de Palo Alto. Desde un punto de vista geológico, el área de estudio está compuesta por rocas sedimentarias del Neógeno, tales como la Fm. Uscari (Mioceno y las formaciones Suretka y Fm. Doán (Plioceno; además de aglomerados que posiblemente se relacionan al volcanismo holoceno de la cordillera volcánica Central. Mediante an

  20. Changing markets - Medicinal plants in the markets of La Paz and El Alto, Bolivia.

    Science.gov (United States)

    Bussmann, Rainer W; Paniagua Zambrana, Narel Y; Moya Huanca, Laura Araseli; Hart, Robbie

    2016-12-04

    Given the importance of local markets as a source of medicinal plants for both healers and the population, literature on market flows and the value of the plant material traded is rather scarce. This stands in contrast to wealth of available information for other components of Bolivian ethnobotany. The present study attempts to remedy this situation by providing a detailed inventory of medicinal plant markets in the La Paz-El Alto metropolitan area, hypothesizing that both species composition, and medicinal applications, have changed considerably over time. From October 2013-October 2015 semi-structured interviews were conducted with 39 plant vendors between October 2013 and October 2015 in the Mercado Rodriguez, Mercado Calle Santa Cruz, Mercado Cohoni, Mercado Cota Cota, and Mercado Seguencoma and Mercado El Alto in order to elucidate more details on plant usage and provenance. The results of the present study were then compared to previous inventories of medicinal plants in La Paz and El Alto studies to elucidate changes over time and impact of interview techniques. In this study we encountered 163 plant species belonging to 127 genera and 58 families. In addition, 17 species could not be identified. This species richness is considerably higher than that reported in previous studies (2005, 129 species of 55 families; 2015, 94 identified species). While the overall distribution of illness categories is in line with older reports the number of species used per application, as well as the applications per species, were much higher in the present study. Overall, informant consensus was relatively low, which might be explained by the large number of new species that have entered the local pharmacopoeia in the last decade, although some species might simply have been missed by previous studies. In course of the present study it became apparent that even well known species might often be replaced by other apparently similar but botanically unrelated species due to

  1. CALIFA, the Calar Alto Legacy Integral Field Area survey. IV. Third public data release

    Science.gov (United States)

    Sánchez, S. F.; García-Benito, R.; Zibetti, S.; Walcher, C. J.; Husemann, B.; Mendoza, M. A.; Galbany, L.; Falcón-Barroso, J.; Mast, D.; Aceituno, J.; Aguerri, J. A. L.; Alves, J.; Amorim, A. L.; Ascasibar, Y.; Barrado-Navascues, D.; Barrera-Ballesteros, J.; Bekeraitè, S.; Bland-Hawthorn, J.; Cano Díaz, M.; Cid Fernandes, R.; Cavichia, O.; Cortijo, C.; Dannerbauer, H.; Demleitner, M.; Díaz, A.; Dettmar, R. J.; de Lorenzo-Cáceres, A.; del Olmo, A.; Galazzi, A.; García-Lorenzo, B.; Gil de Paz, A.; González Delgado, R.; Holmes, L.; Iglésias-Páramo, J.; Kehrig, C.; Kelz, A.; Kennicutt, R. C.; Kleemann, B.; Lacerda, E. A. D.; López Fernández, R.; López Sánchez, A. R.; Lyubenova, M.; Marino, R.; Márquez, I.; Mendez-Abreu, J.; Mollá, M.; Monreal-Ibero, A.; Ortega Minakata, R.; Torres-Papaqui, J. P.; Pérez, E.; Rosales-Ortega, F. F.; Roth, M. M.; Sánchez-Blázquez, P.; Schilling, U.; Spekkens, K.; Vale Asari, N.; van den Bosch, R. C. E.; van de Ven, G.; Vilchez, J. M.; Wild, V.; Wisotzki, L.; Yıldırım, A.; Ziegler, B.

    2016-10-01

    This paper describes the third public data release (DR3) of the Calar Alto Legacy Integral Field Area (CALIFA) survey. Science-grade quality data for 667 galaxies are made public, including the 200 galaxies of the second public data release (DR2). Data were obtained with the integral-field spectrograph PMAS/PPak mounted on the 3.5 m telescope at the Calar Alto Observatory. Three different spectral setups are available: I) a low-resolution V500 setup covering the wavelength range 3745-7500 Å (4240-7140 Å unvignetted) with a spectral resolution of 6.0 Å (FWHM) for 646 galaxies, II) a medium-resolution V1200 setup covering the wavelength range 3650-4840 Å (3650-4620 Å unvignetted) with a spectral resolution of 2.3 Å (FWHM) for 484 galaxies, and III) the combination of the cubes from both setups (called COMBO) with a spectral resolution of 6.0 Å and a wavelength range between 3700-7500 Å (3700-7140 Å unvignetted) for 446 galaxies. The Main Sample, selected and observed according to the CALIFA survey strategy covers a redshift range between 0.005 and 0.03, spans the color-magnitude diagram and probes a wide range of stellar masses, ionization conditions, and morphological types. The Extension Sample covers several types of galaxies that are rare in the overall galaxy population and are therefore not numerous or absent in the CALIFA Main Sample. All the cubes in the data release were processed using the latest pipeline, which includes improved versions of the calibration frames and an even further improved image reconstruction quality. In total, the third data release contains 1576 datacubes, including ~1.5 million independent spectra. Based on observations collected at the Centro Astronómico Hispano Alemán (CAHA) at Calar Alto, operated jointly by the Max-Planck-Institut für Astronomie (MPIA) and the Instituto de Astrofísica de Andalucía (CSIC).The spectra are available at http://califa.caha.es/DR3

  2. Development of a new surface ion-source and ion guide in the ALTO project

    International Nuclear Information System (INIS)

    Cuong, P.V.

    2009-12-01

    The present work is dedicated to the ALTO project which is the production of neutron-rich gallium isotopes by the ISOL thick-target technique using photo-fission and a surface ion source. We aim at the study of the structure of 82 Ge, 83 Ge, 84 Ge via the β decay of 82 Ga, 83 Ga, and 84 Ga. We focus on the development of a new surface ion source made from materials with a high work function φ which can give high ionisation efficiencies for elements with low ionisation potentials, like alkaline as well as gallium and indium. Tungsten, rhenium and iridium are considered as good candidates for a surface ionizer because the Saha-Langmuir equation indicates high surface ionisation efficiencies for these materials. This has motivated us to equip the surface ion source at ALTO with rhenium and iridium-coated rhenium ionizer tubes of the same dimensions as the surface ion source at ISOLDE. We performed a test experiment to measure the ionisation efficiency for gallium. We also built a simulation code for the ionisation efficiency of the different surface ionisation sources (different materials and dimensions). On the other hand, for future nuclear structure studies of refractory elements such as cobalt or nickel, the ISOL technique with a thick target is no longer suitable. Indeed, the high melting point of these elements makes it difficult to volatilize and release them from a thick target. For such a situation, a technique based on thin targets is needed and the laser ion guide based on a gas cell to slow down, neutralize and stop the recoiling nuclear reaction products combined with a laser beam to re-ionize them selectively, seems a good choice. A code based on the Geant-4 tool-kit has been built to simulate the ionisation of the buffer gas. In this work, we also briefly show the results of the photo-fission yield measurements at ALTO. The fission fragments were ionized in a hot plasma ion source, mass separated and detected by germanium and scintillator detectors

  3. Fuel dynamics by using Landscape Ecology Indices in the Alto Mijares, Spain

    Science.gov (United States)

    Iqbal, J.; Garcia, C. V.

    2009-04-01

    Land abandonment in Mediterranean regions has brought about a number of management problems, being an increased wildfire activity prevalent among them. Agricultural neglect in highlands resulted in reduced anthropogenic disturbances and greater landscape homogeneity in areas such as the Alto Mijares in Spain. It is widely accepted that processes like forest fires, influence structure of the landscape and vice versa. Fire-prone Mediterranean flora is well adapted to this disturbance, exhibiting excellent succession capabilities; but higher fuel loads and homogeneous conditions may ally to promote vegetation recession when the fire regime is altered by land abandonment. Both succession and recession make changes to the landscape structure and configuration. However, these changes are difficult to quantify and characterize. If landscape restoration of these forests is a management objective, then developing a quantitative knowledge base for landscape fuel dynamics is a prerequisite. Four classified LandsatTM satellite images were compared to quantify changes in landscape structure between 1984 and 1998. An attempt is made to define landscape level dynamics for fuel development after reduced disturbance and fuel accumulation that leads to catastrophic fires by using landscape ecology indices. By doing so, indices that best describe the fuel dynamics are pointed. The results indicate that low-level disturbance increases heterogeneity, thus lowers fire hazard. No disturbance or severe disturbance increases homogeneity because of vegetation succession and may lead to devastating fires. These fires could be avoided by human induced disturbance like controlled burning, harvesting, mechanical works for fuel reduction and other silviculture measures; thus bringing in more heterogeneity in the region. The Alto Mijares landscape appears to be in an unstable equilibrium where succession and recession are at tug of war. The effects are evident in the general absence of the climax

  4. El chile poblano criollo en la cultura alimentaria del Alto Atoyac

    Directory of Open Access Journals (Sweden)

    Luis Joaquín Pérez Carrasco

    2017-01-01

    Full Text Available El chile poblano criollo producido en la re-gión Alto Atoyac en Puebla, forma parte de la cultura alimenticia de la población, junto con el maíz y el frijol. Ya sea en fresco o en seco es un componente fundamental en muy diver-sos platillos como: el mole poblano, los chiles en nogada, las rajas con huevo, por mencio-nar algunos. El objetivo del trabajo fue el en-tender las razones sociales y culturales de lo planteado e identificar la problemática del cultivo de chile poblano criollo y los factores que favorecen que los productores persistan en su cultivo en la región. Metodología. Se realizaron entrevistas estructuradas, siguien-do el método de muestreo por “bola de nieve” (Snowball, empleado frecuentemente en es-tudios con poblaciones marginales. Resulta-dos. El sistema de producción predominante en el Alto Atoyac, es el chile poblano criollo intercalado en árboles frutales, con superficies de siembra igual o menor a 100 m2, estrategia usada por los productores para diversificar el riesgo de las enfermedades del cultivo y con ello asegurar la sobrevivencia de sus tradicio-nes culinarias y la permanencia de su semilla con sus propias características. Limitaciones. El trabajo de investigación no pudo abarcar el rendimiento de chile poblano en la región y del perfil del productor. Conclusiones. El chi-le poblano criollo en el Alto Atoyac, se siem-bra en superficies pequeñas y condiciones de temporal, intercalado en árboles frutales y es afectado por la enfermedad pudrición radical o secadera. El productor continúa sembrando su semilla de chile poblano criollo, como estra-tegia para conservar sus tradiciones en la elabo-ración de los alimentos y mitigar en lo posible los daños ocasionados por las enfermedades.

  5. 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.)

  6. Valoración del deporte de alto rendimiento (gimnasia rítmica) en edades tempranas

    OpenAIRE

    Usero Gómez, Alba

    2014-01-01

    Comenzando por una introducción, en la cual se contextualiza el deporte y especialmente el de alto rendimiento, nos introduciremos en la cuestión de estudio, el deportista de élite y la preocupación por el comienzo en edades tempranas. Llevaremos a cabo este estudio, por medio de un análisis reflexivo de diversos autores y estudios que se sumergen en el deporte de alto rendimiento, especialmente en la infancia. Trataremos el objeto de estudio en relación a un deporte, la Gimnasia Rítmic...

  7. Eventos adversos relacionados à terapia ventilatória em recém-nascidos de alto risco

    OpenAIRE

    França, Débora Feitosa de

    2016-01-01

    Objetivou-se analisar os eventos adversos relacionados à terapia respiratória em recém-nascidos de alto risco de uma unidade neonatal. Trata-se de um estudo observacional, longitudinal e prospectivo, realizado em uma maternidade, unidade de referencia no Estado do Rio Grande do Norte para gravidez e nascimento de alto risco. Os dados foram coletados no período de abril a setembro 2016, após aprovação do projeto no Comitê de Ética em Pesquisa da UFRN com CAAE nº 51832415.0.0000.5537. A amostra...

  8. VIPRE modeling of VVER-1000 reactor core for DNB analyses

    Energy Technology Data Exchange (ETDEWEB)

    Sung, Y.; Nguyen, Q. [Westinghouse Electric Corporation, Pittsburgh, PA (United States); Cizek, J. [Nuclear Research Institute, Prague, (Czech Republic)

    1995-09-01

    Based on the one-pass modeling approach, the hot channels and the VVER-1000 reactor core can be modeled in 30 channels for DNB analyses using the VIPRE-01/MOD02 (VIPRE) code (VIPRE is owned by Electric Power Research Institute, Palo Alto, California). The VIPRE one-pass model does not compromise any accuracy in the hot channel local fluid conditions. Extensive qualifications include sensitivity studies of radial noding and crossflow parameters and comparisons with the results from THINC and CALOPEA subchannel codes. The qualifications confirm that the VIPRE code with the Westinghouse modeling method provides good computational performance and accuracy for VVER-1000 DNB analyses.

  9. La fiesta xita: patrimonio biocultural mazahua de San Pedro el Alto, México

    Directory of Open Access Journals (Sweden)

    Alicia Y. Vásquez González

    2016-01-01

    Full Text Available Ante la crisis ambiental y de la modernidad, se propone conservar la riqueza cultural y biológica de la humanidad como patrimonio. Así, se valora y revalora el patrimonio vivo, como es la relación entre culturas y biodiversidad, que se manifiestan en paisajes y territorios de los pueblos originarios. Se propone la fiesta xita (viejos como patrimonio biocultural de la milpa mazahua. El estudio etnográfico se realizó en San Pedro el Alto, México. La fiesta xita es parte del patrimonio biocultural mazahua, mediante la cual se entretejen agrobiodiversidad y cultura, lo que permite que los mazahuas mantengan y desarrollen sus actividades sociales y culturales que han sido heredadas de generación en generación.

  10. Niveles subjetivos de estrés-recuperación en deportistas Costarricenses de alto rendimiento

    OpenAIRE

    Sánchez Ureña, M.Sc. Braulio; Ureña Bonilla, Pedro; Calleja González, Julio

    2014-01-01

    El objetivo del presente estudio fue determinar los niveles estrés-recuperación en deportistas costarricenses de alto rendimiento. Metodología: participaron un total de 239 sujetos, con una media de edad de 25,4 ± 4,8 años y con un promedio de 6,4 ± 4,6 años de entrenamiento en la primera división de su disciplina deportiva. Se utilizó la versión española del Cuestionario de Estrés-Recuperación para deportistas Resultados: los valores promedio para las variables relacionadas a la recuperación...

  11. Estudio preliminar de la fauna Amphibia del valle de Sibundoy, Alto Putumayo, Colombia

    Directory of Open Access Journals (Sweden)

    Jonh Jairo Mueses-Cisneros

    2004-07-01

    (Valle de Sibundoy y por localidades muestreadas, se hace una comparación con las faunas realizadas en el transecto Napo en Ecuador y en el transecto Montañita-Alto Gabinete en Caquetá y se presenta una clave taxonómica y una serie de fotografías para facilitar su  reconocimiento. El estudio además aporta cinco especies nuevas para la ciencia, amplía el rango altitudinal de otras ocho y presenta tres más para ser incluidas al listado general de las especies de anfibios de Colombia, las cuales habían sido ya anteriormente reportadas para el país por otros autores, pero no habían sido tenidas en cuenta en el último listado.

  12. Textiles para turistas: tejedoras y comerciantes en los Altos de Chiapas

    Directory of Open Access Journals (Sweden)

    Eugenia Bayona Escat

    2013-01-01

    Full Text Available El presente trabajo indaga en el papel que ocupan las mujeres indígenas como productoras y vendedoras de piezas textiles, consideradas artesanales y de tradición indígena, con alta demanda en el mercado turístico de la región de los Altos de Chiapas, México. La presencia del turismo en la zona ha provocado la consolidación de un complejo mercado local de textiles en el que se entrelazan tejedoras, distribuidoras y comerciantes, cadenas mercantiles y múltiples espacios de venta. A través de este protagonismo femenino y de la comercialización de lo “indígena”, el trabajo indaga en un contexto local que permite a las mujeres indígenas tomar nuevas posiciones sociales a la vez que integra aspectos globales sobre mercancías e imaginarios sociales.

  13. Fragilidade ambiental na bacia hidrográfica do Alto Parnaíba

    OpenAIRE

    Alves de Melo, Nivaneide

    2007-01-01

    Esta pesquisa desenvolveu estudos integrados sobre a bacia hidrográfica do Alto Parnaíba, no Piauí, considerando a atuação das atividades humanas sobre o ambiente natural, a fim de determinar o grau de alteração desse ambiente, a partir da presença antrópica neste local, além de propor ações para restabelecimento de uma situação de equilíbrio ambiental. Pois, quando os eventos sobre a paisagem são de origem antrópica e de orientação econômica, os impactos poderão causar dano...

  14. 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

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Sasaki, Tomozo.

    1987-01-01

    Purpose: To improve the nuclear reactor availability by enabling to continuously exchange fuels in the natural-slightly enriched uranium region during operation. Constitution: A control rod is withdrawn to the midway of a highly enriched uranium region by means of control rod drives and the highly enriched uranium region is burnt to maintain the nuclear reactor always at a critical state. At the same time, fresh uranium-slightly enriched uranium is continuously supplied gravitationally from a fresh fuel reservoir through fuel reservoir to each of fuel pipes in the natural-slightly enriched uranium region. Then, spent fuels reduced with the reactivity by the burn up are successively taken out from the bottom of each of the fuel pipes through an exit duct and a solenoid valve to the inside of a spent fuel reservoir and the burn up in the natural-slightly enriched uranium region is conducted continuously. (Kawakami, Y.)

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Sakurai, Mikio; Yamauchi, Koki.

    1983-01-01

    Purpose: To improve the channel stability and the reactor core stability in a spontaneous circulation state of coolants. Constitution: A reactor core stabilizing device comprising a differential pressure automatic ON-OFF valve is disposed between each of a plurality of jet pumps arranged on a pump deck. The stabilizing device comprises a piston exerted with a pressure on the lower side of the pump deck by way of a pipeway and a valve for flowing coolants through the bypass opening disposed to the pump deck by the opening and closure of the valve ON-OFF. In a case where the jet pumps are stopped, since the differential pressure between the upper and the lower sides of the pump deck is removed, the valve lowers gravitationally into an opened state, whereby the coolants flow through the bypass opening to increase the spontaneous circulation amount thereby improve the stability. (Yoshino, Y.)

  17. 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

  18. 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.)

  19. 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.)

  20. PANIC: A General-purpose Panoramic Near-infrared Camera for the Calar Alto Observatory

    Science.gov (United States)

    Cárdenas Vázquez, M.-C.; Dorner, B.; Huber, A.; Sánchez-Blanco, E.; Alter, M.; Rodríguez Gómez, J. F.; Bizenberger, P.; Naranjo, V.; Ibáñez Mengual, J.-M.; Panduro, J.; García Segura, A. J.; Mall, U.; Fernández, M.; Laun, W.; Ferro Rodríguez, I. M.; Helmling, J.; Terrón, V.; Meisenheimer, K.; Fried, J. W.; Mathar, R. J.; Baumeister, H.; Rohloff, R.-R.; Storz, C.; Verdes-Montenegro, L.; Bouy, H.; Ubierna, M.; Fopp, P.; Funke, B.

    2018-02-01

    PANIC7 is the new PAnoramic Near-Infrared Camera for Calar Alto and is a project jointly developed by the MPIA in Heidelberg, Germany, and the IAA in Granada, Spain, for the German-Spanish Astronomical Center at Calar Alto Observatory (CAHA; Almería, Spain). This new instrument works with the 2.2 m and 3.5 m CAHA telescopes covering a field of view of 30 × 30 arcmin and 15 × 15 arcmin, respectively, with a sampling of 4096 × 4096 pixels. It is designed for the spectral bands from Z to K S , and can also be equipped with narrowband filters. The instrument was delivered to the observatory in 2014 October and was commissioned at both telescopes between 2014 November and 2015 June. Science verification at the 2.2 m telescope was carried out during the second semester of 2015 and the instrument is now at full operation. We describe the design, assembly, integration, and verification process, the final laboratory tests and the PANIC instrument performance. We also present first-light data obtained during the commissioning and preliminary results of the scientific verification. The final optical model and the theoretical performance of the camera were updated according to the as-built data. The laboratory tests were made with a star simulator. Finally, the commissioning phase was done at both telescopes to validate the camera real performance on sky. The final laboratory test confirmed the expected camera performances, complying with the scientific requirements. The commissioning phase on sky has been accomplished.

  1. Sentidos de Vitória/Derrota para os Pais Segundo Atletas do Alto Rendimento

    Directory of Open Access Journals (Sweden)

    Isabela Amblard

    Full Text Available Este estudo compreendeu as representações sociais da vitória/derrota para os pais segundo atletas-adolescentes do esporte de alto rendimento, na cidade do Recife. A adolescência é compreendida a partir da Psicologia Social-histórica, e o embasamento teórico-metodológico da Teoria das Representações Sociais abordou os sujeitos em diferentes contextos socioculturais, lugares de pertencimento, experiências, crenças, saberes e sentimentos compartilhados. Adotou-se a perspectiva pluri metodológica com variados recursos de coleta e análise progressiva de dados. Participaram 101 atletas-adolescentes do esporte de alto rendimento, nas modalidades natação e vôlei. Os instrumentos utilizados foram questionários de associação livre e entrevistas semidirigidas. Na análise dos dados, o software EVOC e as técnicas de análise temática de conteúdo de Bardin. Identificamos as representações de vitória para os pais, nas dimensões: pessoal e motivacional, e afetivo-emocional e, nas representações sociais da derrota para os pais, além destas, a dimensão técnica. O sentido de vitória para os pais apareceu ampliado: o contexto esportivo, a escolarização, e o crescimento pessoal e profissional na vida. A derrota para os pais é representada como oportunidade de aprendizado e superação para o atleta-adolescente, porém, eles mostraram que necessitam do apoio afetivo de sua família para lidar com a autoculpabilização nas situações de fracasso.

  2. Adesão ao Tratamento em Gestação de Alto Risco

    Directory of Open Access Journals (Sweden)

    Fabíola Langaro

    Full Text Available No Brasil, aproximadamente 15% das gestações são de alto risco, sendo os diagnósticos de diabetes gestacional e hipertensão as causas mais frequentes dessa condição. Para a efetividade dos tratamentos indicados nesses casos, bem como alcance de desfechos favoráveis, é essencial a adesão da paciente às recomendações fornecidas pelas equipes de saúde, o que torna fundamental a avaliação desse indicador. A pesquisa apresentada avaliou a adesão de participantes de um programa de atendimento interdisciplinar a gestantes de alto risco desenvolvido em um hospital geral privado por meio de três instrumentos: Questionário Morisky-Green de adesão ao uso de medicação, Questionário de Adesão ao Tratamento e Pergunta descritiva de avaliação qualitativa. Durante oito meses, 83 gestantes responderam aos questionários, que possibilitaram identificar níveis de adesão ao longo do tempo de participação no programa, situações de não adesão mais frequentes, bem como variáveis que interferem nas medidas de adesão ao uso de medicação e ao tratamento global. Considera-se que os índices levantados são passíveis de uso como indicadores clínicos e gerenciais, possibilitando a comprovação da efetividade e melhoria constante das rotinas de saúde. Tais mecanismos são úteis para definição de protocolos, discussão de casos clínicos e mesmo para feedbackàs próprias pacientes.

  3. 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

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Humphreys, P.; Davidson, D.F.; Thatcher, G.

    1980-01-01

    The cooling system of a liquid metal cooled fast breeder nuclear reactor of the pool kind is described. It has an intermediate heat exchange module comprising a tube-in-shell heat exchanger and an electromagnetic flow coupler in the base region of the module. Primary coolant is flowed through the heat exchanger being driven by electromagnetic interaction with secondary liquid metal coolant flow effected by a mechanical pump. (author)

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Jungmann, A.

    1975-01-01

    Between a PWR's reactor pressure vessel made of steel and the biological shield made of concrete there is a gap. This gap is filled up with a heat insulation facting the reactor pressure vessel, for example with insulating concrete segments jacketed with sheet steel and with an additional layer. This layer serves for smooth absorption of compressive forces originating in radial direction from the reactor pressure vessel. It consists of cylinder-segment shaped bricks made of on situ concrete, for instance. The bricks have cooling agent ports in one or several rows which run parallel to the wall of the pressure vessel and in alignment with superposed bricks. Between the layer of bricks and the biological shield or rather the heat insulation, there are joints which are filled, however, with injected mortar. That guarantees a smooth series of connected components resistant tom compression. Besides, a slip foil can be set between the heat insulation and the joining joint filled with mortar for the reduction of the friction at thermal expansions. (TK) [de

  6. 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.)

  7. Nuclear reactors

    International Nuclear Information System (INIS)

    Yoshioka, Michiko.

    1985-01-01

    Purpose: To obtain an optimum structural arrangement of IRM having a satisfactory responsibility to the inoperable state of a nuclear reactor and capable of detecting the reactor power in an averaged manner. Constitution: As the structural arrangement of IRM, from 6 to 16 even number of IRM are bisected into equial number so as to belong two trip systems respectively, in which all of the detectors are arranged at an equal pitch along a circumference of a circle with a radius rl having the center at the position of the central control rod in one trip system, while one detector is disposed near the central control rod and other detectors are arranged substantially at an equal pitch along the circumference of a circle with a radius r2 having the center at the position for the central control rod in another trip system. Furthermore, the radius r1 and r2 are set such that r1 = 0.3 R, r2 = 0.5 R in the case where there are 6 IRM and r1 = 0.4 R and R2 = 0.8 R where there are eight IRM where R represents the radius of the reactor core. (Kawakami, Y.)

  8. MLR reactor

    International Nuclear Information System (INIS)

    Ryazantsev, E.P.; Egorenkov, P.M.; Nasonov, V.A.; Smimov, A.M.; Taliev, A.V.; Gromov, B.F.; Kousin, V.V.; Lantsov, M.N.; Radchenko, V.P.; Sharapov, V.N.

    1998-01-01

    The Material Testing Loop Reactor (MLR) development was commenced in 1991 with the aim of updating and widening Russia's experimental base to validate the selected directions of further progress of the nuclear power industry in Russia and to enhance its reliability and safety. The MLR reactor is the pool-type one. As coolant it applies light water and as side reflector beryllium. The direction of water circulation in the core is upward. The core comprises 30 FA arranged as hexagonal lattice with the 90-95 mm pitch. The central materials channel and six loop channels are sited in the core. The reflector includes up to 11 loop channels. The reactor power is 100 MW. The average power density of the core is 0.4 MW/I (maximal value 1.0 MW/l). The maximum neutron flux density is 7.10 14 n/cm 2 s in the core (E>0.1 MeV), and 5.10 14 n/cm 2 s in the reflector (E<0.625 eV). In 1995 due to the lack of funding the MLR designing was suspended. (author)

  9. 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.)

  10. Reactor container

    International Nuclear Information System (INIS)

    Hidaka, Masataka; Hatamiya, Shigeo; Kawasaki, Terufumi; Fukui, Toru; Suzuki, Hiroaki; Kataoka, Yoshiyuki; Kawabe, Ryuhei; Murase, Michio; Naito, Masanori.

    1990-01-01

    In order to suppress the pressure elevation in a reactor container due to high temperature and high pressure steams jetted out upon pipeway rupture accidents in the reactor container, the steams are introduced to a pressure suppression chamber for condensating them in stored coolants. However, the ability for suppressing the pressure elevation and steam coagulation are deteriorated due to the presence of inactive incondensible gases. Then, there are disposed a vent channel for introducing the steams in a dry well to a pressure suppression chamber in the reactor pressure vessel, a closed space disposed at the position lower than a usual liquid level, a first channel having an inlet in the pressure suppression chamber and an exit in the closed space and a second means connected by way of a backflow checking means for preventing the flow directing to the closed space. The first paths are present by plurality, a portion of which constitutes a syphon. The incondensible gases and the steams are discharged to the dry well at high pressure by using the difference of the water head for a long cooling time after the pipeway rupture accident. Then, safety can be improved without using dynamic equipments as driving source. (N.H.)

  11. Reactor core in FBR type reactor

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  12. Identidades en movimiento: familias chilenas en la fruticultura del Alto Valle de Río Negro, Argentina Identities in movement: chilean families in the fruit production of the Alto Valle de Río Negro, Argentina

    Directory of Open Access Journals (Sweden)

    Verónica Trpin

    2007-12-01

    Full Text Available Este artículo, basado en el trabajo de campo realizado en áreas rurales del Alto Valle de Río Negro, Argentina, desde el año 1999, tiene como propósito presentar las relaciones en las cuales se insertan hombres y mujeres chilenas que residen y trabajan en "chacras" destinadas a la producción frutícola. Las diferentes actividades en las chacras se organizan según el sexo y la edad, definiéndose una segmentación del mercado de trabajo en la que se ven involucrados los diferentes miembros de la familia. Como desarrollaré, ser trabajadores chilenos en la fruticultura del Alto Valle de Río Negro reproduce una identidad étnica y nacional en el seno de la cotidianeidad familiar y laboral.This article, based on field work conducted in rural areas of the Alto Valle de Río Negro, Argentina, from 1999 on, analyzes the relations in which Chilean men and women who reside and work in small farms destined to fruit production are inserted. The different activities in the small farms are organized according to sex and age, circumscribing a segment of the labor market in which different members of the family are involved. As I will demonstrate, to be a Chilean worker in the fruit growing region of the Alto Valle is to reproduce an ethnic and national identity through work routines mediated by family relations.

  13. El período intermedio temprano en el Alto Piura: avances del proyecto arqueológico 'Alto Piura' (1987-1990

    Directory of Open Access Journals (Sweden)

    1991-01-01

    Full Text Available LA PERIODE DE L’INTERMEDIAIRE RECENT DANS LE HAUT PIURA : RESULTATS PRELIMINAIRES DU PROJET ARQUEOLOGIQUE “HAUT PIURA” (1987-1990. Ce travail présente les résultats préliminaires du projet arquéologique “Haut Piura” avec le concours de l’Université Catholique du Pérou et dirigé par l’auteur. L’accent est mis sur les informations concernant les séquences stratigraphiques et l’architecture. Les informations obtenues pour les analyses encore incomplètes du matériel céramique, métallurgique, osseux et végétal permettent d’établir la relation avec la problématique sur les styles Vicús et Vicús-Moche. Se presentan los resultados preliminares del Proyecto Arqueológico “Alto Piura”, auspiciado por la Pontificia Universidad Católica del Perú y dirigido por el autor. Se enfatizan los datos referentes a las secuencias estratigráficas y la arquitectura. Los datos obtenidos por análisis aún incompletos del material cerámico, metalúrgico, óseo y vegetal permiten la vinculación con la problemática referente a los estilos Vicús y Vicús-Moche. EARLY INTERMEDIATE PERIOD IN UPPER PIURA: “UPPER PIURA' ARCHAEOLOGICAL PROJECT (1987-1990. Preliminary results of the “Upper Piura” archaeological Project are introduced under the promotion of the Pontificia Universidad Católica del Perú, and the direction of the author. All data referred to stratigraphy sequences and architecture is enhanced on the just mencioned. The outcome obtained from the analysis, still uncompleted of pottery, metallurgy, osseous and botanical materials, allows the relationship when focusing the problematic regarding the Vicus and Vicus-Moche styles.

  14. Molten salt reactors: reactor cores

    International Nuclear Information System (INIS)

    1983-01-01

    In this critical analysis of the MSBR I project are examined the problems concerning the reactor core. Advantages of breeding depend essentially upon solutions to technological problems like continuous reprocessing or graphite behavior under neutron irradiation. Graphite deformation, moderator unloading, control rods and core instrumentation require more studies. Neutronics of the core, influence of core geometry and salt composition, fuel evolution, and thermohydraulics are reviewed [fr

  15. 77 FR 58203 - AER Energy Resources, Inc.; Alto Group Holdings, Inc.; Bizrocket.Com Inc.; Fox Petroleum, Inc...

    Science.gov (United States)

    2012-09-19

    ... SECURITIES AND EXCHANGE COMMISSION [File No. 500-1] AER Energy Resources, Inc.; Alto Group Holdings, Inc.; Bizrocket.Com Inc.; Fox Petroleum, Inc.; Geopulse Explorations Inc.; Global Technologies... accuracy of press releases concerning the company's revenues. 4. Fox Petroleum, Inc. is a Nevada...

  16. Entre aromas de incienso y pólvora : Los Altos de Jalisco, México, 1917-1940

    NARCIS (Netherlands)

    López Ulloa, José Luis

    2008-01-01

    This thesis focuses on the Mexican Revolution and on the opposition strategies followed by the opponents of the revolutionary regime who lived in the region known as Los Altos de Jalisco. In this particular region, the Catholic population, supported by the Clergy, was in constant conflict with the

  17. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

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

  18. 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

  19. 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

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Jolly, R.

    1979-01-01

    The support grid for the fuel rods of a liquid metal cooled fast breeder reactor has a regular hexagonal contour and contains a large number of unit cells arranged honeycomb fashion. The totality of these cells make up a hexagonal shape. The grid contains a number of strips of material, and there is a window in each of three sidewalls staggered by one sidewall. The other sidewalls have embossed protrusions, thus generating a guide lining or guide bead. The windows reduce the rigidity of the areas in the middle between the ends of the cells. (DG) [de

  1. 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

  2. Zoneamento ambiental do polo de desenvolvimento agroindustrial do Alto Piranhas, Estado da Paraíba

    Directory of Open Access Journals (Sweden)

    J. S. Almeida

    2015-12-01

    Full Text Available Este trabalho teve como objetivo zonear os níveis de deterioração ambiental na paisagem entre os anos de 2001 e 2012, adotando os critérios da ecodinâmica nos municípios que compõe o polo de desenvolvimento agroindustrial do Alto Piranhas. Foram realizadas análises envolvendo a dinâmica da paisagem e da vulnerabilidade ambiental. A metodologia utilizada na pesquisa foi baseada em localizações pontuais, que inclui o processo de selecionar e combinar, através de procedimento de álgebra de mapas disponíveis em um SIG, cada variável geográfica contém diferenciação espacial e a combinação entre elas promove a subdivisão do espaço geográfico em regiões equiproblemáticas. Tomando-se por base as superposições dos mapas geológico, geomorfológico e pedológico foi efetuado o mapa de zoneamento ambiental, com informações que permitiram identificar as condições do meio natural e suas aptidões. Esses fatores foram comparados entre si, conforme a importância atribuída a elas. Os resultados indicaram que as áreas centrais concentram as classes com maiores riscos ambientais, como as instáveis (risco ambiental entre 60 e 80%, e as de instabilidade emergente (risco maior que 80. Já nas áreas distribuídas em toda a área de estudo encontra-se as áreas com risco ambiental entre 40 e 60% (instabilidade moderada. Com base na análise, percebe-se que a área de estudo possui um tênue equilíbrio por estar localizado em ambiente semiárido que pode ser rompido com facilidade com a intensificação das atividades agroindustriais.Environmental zoning polo agro industry development of Alto Piranhas, Paraíba StateAbstract: This study aimed to zone the levels of environmental deterioration in the landscape between the years 2001 and 2012, adopting the criteria of ecodynamics municipalities that make up the hub of agro-industrial development of the Alto Piranhas. Analyzes involving the dynamics of landscape and environmental

  3. Nuclear reactors

    International Nuclear Information System (INIS)

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

    1979-01-01

    In a nuclear reactor (e.g. one having coolant down-flow through a core to a hearth below) thermal insulation (e.g. of a floor of the hearth) comprises a layer of bricks and a layer of tiles thereon, with smaller clearances between the tiles than between the bricks but with the bricks being of reduced cross-section immediately adjacent the tiles so as to be surrounded by interconnected passages, of relatively large dimensions, constituting a continuous chamber extending behind the layer of tiles. By this arrangement, lateral coolant flow in the inter-brick clearances is much reduced. The reactor core is preferably formed of hexagonal columns, supported on diamond-shaped plates each supported on a pillar resting on one of the hearth-floor tiles. Each plate has an internal duct, four upper channels connecting the duct with coolant ducts in four core columns supported by the plate, and lower channels connecting the duct to a downwardly-open recess common to three plates, grouped to form a hexagon, at their mutually-adjacent corners. This provides mixing, and temperature-averaging, of coolant from twelve columns

  4. 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.)

  5. 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.)

  6. Nuclear reactors

    International Nuclear Information System (INIS)

    Matheson, J.E.

    1983-01-01

    A nuclear reactor has an upper and a lower grid plate. Protrusions project from the upper grid plate. Fuel assemblies having end fittings fit between the grid plates. An arrangement is provided for accepting axial forces generated during the operation of the nuclear reactor by the flow of the cooling medium and thermal expansion and irradiation-induced growth of the fuel assembly, which comprises rods. Each fuel assembly rests on the lower grid plate and its upper end is elastically supported against the upper grid plate by the above-mentioned arrangement. The arrangement comprises four (for example) torsion springs each having a torsion tube and a torsion bar nested within the torsion tube and connected at one end thereto. The other end of the torsion bar is connected to an associated one of four lever arms. The torsion tube is rigidly connected to the other end fitting and the springs are disposed such that the lever arms are biassed against the protrusions. (author)

  7. Adsorción de metales pesados sobre lodos de horno alto

    Directory of Open Access Journals (Sweden)

    López-Delgado, A.

    1998-05-01

    Full Text Available Most of industrial liquid effluents have high contents of heavy metals. The recovery of these metals is environmental and economically interesting. In this work we study the use of sludge, a by-product of the steel industry, as an adsorbent for the removal of heavy metals from liquid effluents. The adsorption of Pb2+, Zn2+, Cd2+, Cu2+ and Cr3+ on the sludge was investigated by determination of adsorption isotherms. The effect of time, equilibrium temperature and concentration of metal solution on sludge adsorption efficiency was evaluated. The adsorption process was analysed using the theories of Freundlich and Langmuir and the thermodynamic values ΔG, ΔH and ΔS corresponding to each adsorption process were calculated. Blast furnace sludge was found to be an effective sorbent for Pb, Zn, Cd, Cu and Cr-ions within the range of ion concentrations employed.

    Los efluentes líquidos de la mayoría de los procesos industriales contienen una carga importante de metales pesados que, por motivos tanto económicos como medioambientales interesa recuperar. En este trabajo, se estudia la utilización de lodos procedentes de la depuración por vía húmeda de los gases de horno alto como soporte para la retención de metales pesados contenidos en efluentes líquidos. La adsorción de Pb2+, Zn2+, Cd2+, Cu2+ y Cr3+ sobre el lodo de horno alto se determina mediante la obtención de las isotermas de adsorción, variando la concentración de las soluciones metálicas y analizando la influencia del tiempo y de la temperatura de equilibrio en la capacidad de adsorción del lodo. Para describir el proceso de adsorción se consideraron las teorías de Freundlich y Langmuir y, posteriormente, se calcularon los valores termodinámicos ΔG, ΔH y ΔS, correspondientes a cada proceso de adsorción. Para todos

  8. 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.)

  9. 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.

  10. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-11-01

    This single page document is the November 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the production reactor.

  11. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-01

    This single page document is the October 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  12. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-15

    This single page document is the October 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  13. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-09-15

    This single page document is the September 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  14. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-15

    This single page document is the December 16, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  15. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-01

    This single page document is the December 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

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

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

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

  17. The CEA research reactors

    International Nuclear Information System (INIS)

    Schwartz, J.P.

    1993-01-01

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

  18. Atomic reactor thermal engineering

    International Nuclear Information System (INIS)

    Kim, Gwang Ryong

    1983-02-01

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

  19. Nuclear reactor types

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

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

  20. The crust role at Paramillos Altos intrusive belt: Sr and Pb isotope evidence

    International Nuclear Information System (INIS)

    Ostera, H.A.; Linares, E; Haller, M.J; Cagnoni, M.C

    2001-01-01

    Paramillos Altos Intrusive Belt (PAIB) (Ostera, 1996) is located in the thick skinned folded-thrust belt of Malargue, southwestern Mendoza, Argentina. Geochemical, geochronologic and isotopic studies were carried out in it (Ostera 1996, 1997, Ostera et al. 1999; Ostera et al. 2000) and these previous papers suggested a minor involvement of the crust in the genesis of the PAIB. According with Ostera et al. (2000) it is composed by stocks, laccoliths, dykes and sills which range in composition from diorites to granodiorites, and from andesites to rhyolites, and divided in five Members, which range in age from Middle Miocene to Early Miocene: a- Calle del Yeso Dyke Complex (CYDC), with sills and dykes of andesitic composition (age: 20±2 Ma). b- Puchenque-Atravesadas Intrusive Complex (PAIC), composed by dykes and stocks ranging from diorites to granodiorites (age: 12.5±1 Ma). c- Arroyo Serrucho Stock (SAS), an epizonal and zoned stock, with four facies, with K/Ar and Ar/Ar dates of 10±1 and 9.5±0.5 Ma. d- Portezuelo de los Cerros Bayos (PCB), that includes porphyritic rocks of rhyolitic composition, of 7.5±0.5 Ma. e- Cerro Bayo Vitrophyres (CBV), with andesitic sills and dykes (age: 4.8±0.2 Ma). We present in this paper new Sr and Pb isotopes data that constrain the evolution of the PAIB (au)

  1. Contribution for geochronological evolution study of the Pianco-Alto Brigida fold belt system

    International Nuclear Information System (INIS)

    Brito Neves, B.B. de; Basei, M.A.S.; Van Schmus, W.R.

    1990-01-01

    The Proterozoic Painco-Alto Fold Belt is situated in the central portion of the Borborema Province and it probably is just a segment of a longer structural development encompassed between the Patos (N) and Pernambuco (S) lineaments. The geochronological study was carried out along a cross section in the central part of the belt (Paraiba State) where biotite-muscovite quartz schists are the predominating rock types, including intercalations of bi-modal volcanics, marbles and quartzites. These rocks were metamorphosed in the amphibolite facies, and they display a complex history of folding. Zircons of the acid volcanics (meta-rhyolytes where analysed through U/Pb method and they plot in a discordia diagram with superior intercept indicating ages around 1100 Ma. Whole rocks Rb/Sr analyses on the same meta-volcanics are indicating isochrons of 950Ma. These data are being respectively interpreted as ages of sedimentation (and volcanism) and regional metamorphism associated to the main (D sub(2)) phase of folding. One of the main purpose of this paper is to stress the importance of the ages around 950Ma, in the central domain of the Borborema Province, as result of regional folding and metamorphism. Some other occurence of ages in the 1000-900Ma range will be discussed as support for this interpretation from now on adopted. (author)

  2. Earth-based construction material field tests characterization in the Alto Douro Wine Region

    Science.gov (United States)

    Cardoso, Rui; Pinto, Jorge; Paiva, Anabela; Lanzinha, João Carlos

    2017-12-01

    The Alto Douro Wine Region, located in the northeast of Portugal, a UNESCO World Heritage Site, presents an abundant vernacular building heritage. This building technology is based on a timber framed structure filled with a composite earth-based material. A lack of scientific studies related to this technology is evident, furthermore, principally in rural areas, this traditional building stock is highly deteriorated and damaged because of the rareness of conservation and strengthening works, which is partly related to the non-engineered character of this technology and to the knowledge loosed on that technique. Those aspects motivated the writing of this paper, whose main purpose is the physical and chemical characterization of the earth-based material applied in the tabique buildings of that region through field tests. Consequently, experimental work was conducted and the results obtained allowed, among others, the proposal of a series of adequate field tests. At our knowledge, this is the first time field tests are undertaken for tabique technology. This information will provide the means to assess the suitability of a given earth-based material with regards to this technology. The knowledge from this study could also be very useful for the development of future normative documents and as a reference for architects and engineers that work with this technology to guide and regulate future conservation, rehabilitation or construction processes helping to preserve this important legacy.

  3. Aristocracias y dependientes en el Alto Ebro (siglos V-VIII

    Directory of Open Access Journals (Sweden)

    Santiago CASTELLANOS

    2009-12-01

    Full Text Available RESUMEN: El estudio de la documentación tardoantigua supone un avance en el conocimiento histórico y el debate historiográfico acerca de los múltiples problemas que presenta la Alta Edad Media en el Norte de la Península Ibérica. El autor profundiza en fuentes sobre la zona del Alto Ebro durante la Antigüedad tardía, al tiempo que proporciona un panorama social de tal ámbito, a fin de entender mejor el posterior mundo altomedieval, lejos de algunos modelos basados exclusivamente en fuentes altomedievales.ABSTRACT: The study of documents from late antiquity has led to progress in the historical knowledge and the historiographical debate surrounding the many problems presented by the Early Middle Ages in the north of the Iberian Peninsula. The author makes an in-depth study of sources from the Upper Ebro area during Late Antiquity, at the same time giving a social panorama of this same area, in order to better understand the subsequent early mediaeval world. This scene has turned out to be very different from models based exclusively on early mediaeval sources.

  4. Tabique walls composite earth-based material characterization in the Alto Douro wine region, Portugal

    Directory of Open Access Journals (Sweden)

    Rui CARDOSO

    2015-12-01

    Full Text Available The Alto Douro Wine Region, located in the northeast of Portugal, a UNESCO World Heritage Site, presents a relevant tabique building stock, a traditional vernacular building technology. A technology based on a timber framed structure filled with a composite earth-based material. Meanwhile, previous research works have revealed that, principally in rural areas, this Portuguese heritage is highly deteriorated and damaged because of the rareness of conservation and strengthening works, which is partly related to the non-engineered character of this technology and to the growing phenomenon of rural to urban migration. Those aspects associated with the lack of scientific studies related to this technology motivated the writing of this paper, whose main purpose is the physical and chemical characterization of the earth-based material applied in the tabique buildings of that region. Consequently, an experimental work was conducted and the results obtained allowed, among others, the proposal of a particle size distribution envelope in respect to this material. This information will provide the means to assess the suitability of a given earth-based material in regard to this technology. The knowledge from this study could be very useful for the development of future normative documents and as a reference for architects and engineers that work with earth to guide and regulate future conservation, rehabilitation or construction processes helping to preserve this fabulous legacy.

  5. Earth-based construction material field tests characterization in the Alto Douro Wine Region

    Directory of Open Access Journals (Sweden)

    Cardoso Rui

    2017-12-01

    Full Text Available The Alto Douro Wine Region, located in the northeast of Portugal, a UNESCO World Heritage Site, presents an abundant vernacular building heritage. This building technology is based on a timber framed structure filled with a composite earth-based material. A lack of scientific studies related to this technology is evident, furthermore, principally in rural areas, this traditional building stock is highly deteriorated and damaged because of the rareness of conservation and strengthening works, which is partly related to the non-engineered character of this technology and to the knowledge loosed on that technique. Those aspects motivated the writing of this paper, whose main purpose is the physical and chemical characterization of the earth-based material applied in the tabique buildings of that region through field tests. Consequently, experimental work was conducted and the results obtained allowed, among others, the proposal of a series of adequate field tests. At our knowledge, this is the first time field tests are undertaken for tabique technology. This information will provide the means to assess the suitability of a given earth-based material with regards to this technology. The knowledge from this study could also be very useful for the development of future normative documents and as a reference for architects and engineers that work with this technology to guide and regulate future conservation, rehabilitation or construction processes helping to preserve this important legacy.

  6. Trends in linguistic, scholastic and educational policies in trentino and Alto Adige (1919-1939

    Directory of Open Access Journals (Sweden)

    Elisa Gori

    2016-01-01

    Full Text Available The text proposes the examination of school and educational policy choices made in the territories of Trentino and Alto Adige, for German and Ladin speaking minorities in the time period between the end of the first major world conflict and the beginning of the second. During the historical period under consideration, the territories of the new provinces were headquarters and object of multiple political, economic and cultural operations, marked by different and opposite strategies: referrals of implicit nationalist trend which attributed extensive legislative powers to central authorities, were replaced by more democratic guidelines, that embraced local autonomies and recognized the rights of the minorities. Search for a political balance between the two instances, which was initially pursued, left the field with the arrival of the first fascist government to a new scenario with the aim of Italianize, even with the use of violence, the kind and organization of the new provinces. The same contradictory scenario will mark the evolution of educational policies in the new territories; the attempt to extend the Italian scholastic regulations to new provinces, first gradually and respectfully on the linguistic minorities, their schools and traditions, with the fascist government will suffer a significant change in behavior and reasoning. The theme of this research, which is little studied and analyzed in detail, assumes its relevance, whether in terms of historical and educational research linked to particular historic moment and geographical context, whether in terms of the consequences that it had in the construction of the Italian Republic.

  7. ALGUNAS HERRAMIENTAS PARA LA TOMA DE DECISIONES DE INVERSIÓN EN PROYECTOS DE ALTO RIESGO

    Directory of Open Access Journals (Sweden)

    Julio Villarreal

    2007-01-01

    Full Text Available En este trabajo se presenta un posible aplicación metodológica para la toma de decisiones de inversión en proyectos de alto riesgo como las que típicamente son apoyados por los llamados fondos de capital de riesgo. El objetivo final es mostrar como es posible a través de esta metodología, reducir las asimetrías de información típicas en la relación entre inversionistas de riesgo (accionistas de capital y gestores de proyectos (accionistas industriales. La metodología propuesta se aplica a un plan de negocios real, pero de igual manera se puede aplicar a otros proyectos riesgosos, y muestra cómo una adecuada estructuración de un proceso de decisión, usando los modelos y herramientas adecuadas puede ser muy útil tanto en decisiones de fondos de inversión como en la estructuración de procesos de evaluación de alternativas de decisión estratégicas en las que el riesgo hace inapropiado el tradicional análisis determinístico.

  8. Las galerías filtrantes del Alto Lerma: usos y manejos sociales

    Directory of Open Access Journals (Sweden)

    Roberto Montes-Hernández

    2011-01-01

    Full Text Available La ubicación y estudio del manejo social del agua de las galerías filtrantes en el Estado de México no se ha realizado porque se ignora la existencia de este sistema hidráulico. En el presente artículo se informa por primera vez la georreferenciación y descripción del uso y manejo social del agua de las galerías filtrantes del Alto Lerma. Con base en trabajo de campo, revisión de archivos y etnografía, se verifica y describe la existencia de dicho sistema en esta región. El desarrollo de este trabajo es parte de una investigación más amplia, denominada "Caracterización del uso y manejo social del agua de las galerías filtrantes en el Estado de México", bajo la supervisión de Tonatiuh Romero.

  9. El poblamiento humano antiguo en el valle alto del Lozoya (Madrid

    Directory of Open Access Journals (Sweden)

    Belén Márquez

    2008-01-01

    Full Text Available La localización en superficie en el término municipal de Lozoya (Madrid de un conjunto de piezas de industria lítica achelense permite retrotraer el primer poblamiento de esta zona al Pleistoceno medio, cuando hasta la fecha las evidencias más antiguas en el valle alto del río Lozoya se remontaban a inicios del Pleistoceno superior. El nuevo hallazgo sitúa al río Lozoya en relación cultural con el poblamiento humano antiguo de los ríos Jarama y Manzanares.The discovery of a surface sample of Acheulean lithic industry at the Lozoya district (Madrid takes back to the Middle Pleistocene the first human peopling of this area. Until now themost ancient evidences at the Upper Lozoya Valley went back to the initial Upper Pleistocene. The new findings place the Lozoya River in cultural relation with the ancient human population of Jarama and Manzanares Rivers.

  10. COMPREENSÃO DA PAISAGEM DO ALTO CAMAQUÃ: debate ambiental sobre o Bioma Pampa

    Directory of Open Access Journals (Sweden)

    Adriano Severo Figueiró

    2011-01-01

    Full Text Available El presente articulo trata de la confi guración del paisaje de la subcuenca del Alto Camaquã/RS, bien como la evolución de determinados elementos naturales y la historia de las culturas que tornaran esta una de las más bellas e intrigantes paisajes que componen el territorio gaucho y el denominado Bioma Pampa. Este recorte de estudio fue determinado en función de su importancia para la conservación y protección de este bioma brasilero amenazado por la introducción de formas de "desarrollo exógeno" actualmente aprobadasy que no están de acuerdo con las particularidades socioeconómicas, culturales y ambientales de la región.En este sentido, el documento analiza las particularidades existentes y condicionamiento que los elementos naturales de este paisaje representan para el proceso de propiedad y planifi cación territorial del Pampa.

  11. Hyphessobrycon ocasoensis sp. n. (Teleostei, Characidae una nueva especie para el Alto Cauca, Colombia

    Directory of Open Access Journals (Sweden)

    García-Alzate, C. A.

    2008-12-01

    Full Text Available Hyphessobrycon ocasoensis n. sp. (Teleostei, Characidae a new species from the Alto Cauca, Colombia Hyphessobrycon ocasoensis n. sp. (Characiformes, Characidae from heterorhabdus group (Gery, 1977 is described from the upper Cauca River in Colombia. The new species is distinguished from all other known species by the following combination of characters: three unbranched and eight branched fins in the dorsal fin; short maxillary bone with one or no teeth; four small foramens in the maxillary bone, and five in the premaxillary; 5-17 scales with pores in the lateral line, six between the lateral line and anal-fin origin, six between the lateral line and pelvic-fin origin, and nine predorsals; depth of the caudal peduncle has a mean of 16.7% in standard length; interorbital width 50.6% in head; a dark spot on caudal peduncle and a dark lateral band that extends vertically from the dorsal–fin origin to the tips of the middle caudal fin rays. Physical and chemical data of their habitat are included.

  12. The staging and performativity of ethnic tourism in Los Altos de Chiapas

    Directory of Open Access Journals (Sweden)

    Eugenia Bayona Escat

    2018-05-01

    Full Text Available This paper reflects on the ethnic tourism and the selective and particular visions that tourists have about the indigenous population, described as different and exotic. The constructive look of the tourist is combined with the need to experiment with the otherness to authenticate the travel. This implies deepening the processes that make up the ethnic imaginary within the global leisure market, but also in analyzing the role that performance activities acquire as a tourist attraction. The work wants to explore the exhibition of the indigenous body in the tourist market from two visions: on the one hand, the interest of the body as cultural heritage; on the other, the moving body on the tourist stage. For the analysis I will use the ethnographic data of the region Altos Tzotzil Tzeltal of Chiapas (Mexico with great influx of ethnic tourists. The purpose is to observe how in these tourist spaces, built as exotic and outside the world economic and cultural system, they become precisely transnational places of exchange of glances, and in places where it is exhibited, observes and commodified a body qualified as ethnic.

  13. Multidrug-resistant pulmonary tuberculosis in Los Altos, Selva and Norte regions, Chiapas, Mexico.

    Science.gov (United States)

    Sánchez-Pérez, H J; Díaz-Vázquez, A; Nájera-Ortiz, J C; Balandrano, S; Martín-Mateo, M

    2010-01-01

    To analyse the proportion of multidrug-resistant tuberculosis (MDR-TB) in cultures performed during the period 2000-2002 in Los Altos, Selva and Norte regions, Chiapas, Mexico, and to analyse MDR-TB in terms of clinical and sociodemographic indicators. Cross-sectional study of patients with pulmonary tuberculosis (PTB) from the above regions. Drug susceptibility testing results from two research projects were analysed, as were those of routine sputum samples sent in by health personnel for processing (n = 114). MDR-TB was analysed in terms of the various variables of interest using bivariate tests of association and logistic regression. The proportion of primary MDR-TB was 4.6% (2 of 43), that of secondary MDR-TB was 29.2% (7/24), while among those whose history of treatment was unknown the proportion was 14.3% (3/21). According to the logistic regression model, the variables most highly associated with MDR-TB were as follows: having received anti-tuberculosis treatment previously, cough of >3 years' duration and not being indigenous. The high proportion of MDR cases found in the regions studied shows that it is necessary to significantly improve the control and surveillance of PTB.

  14. Reporte de cuatro casos clínicos de filariasis en Alto Nanay, Loreto

    Directory of Open Access Journals (Sweden)

    Javier Vargas-Herrera

    Full Text Available El presente estudio describe los hallazgos clínicos, parasitológicos y de laboratorio de cuatro pacientes residentes en el distrito de Alto Nanay, Maynas, Loreto, Perú; infectados con microfilarias de Mansonella ozzardi. La evaluación clínica incluyó las especialidades de oftalmología, cardiología y nefrología. En el caso 1, destaca la presencia de dos tumoraciones subcutáneas, una a nivel dorsal y la otra en el tercio inferior de la pierna izquierda; en el caso 2, la sensación de “hormigueo o frío en las piernas”; en el caso 3 se encontró asociada una infección crónica por hepatitis B y en el caso 4 una tumoración de gran tamaño en región lumbar izquierda. En los cuatro pacientes se encontró Mansonella ozzardi y eosinofilia, tres presentaron valores mayores a 20%. La tumoración en el caso 4 correspondió a una hernia de contenido intestinal. Es necesario ejecutar más estudios clínicos y evaluar su verdadero efecto patógeno, es también pertinente estudiar la diversidad genética de filarias de la Amazonia peruana.

  15. Farmers typology and crops sustainability in Alto Urubamba, La Convencion – Cusco

    Directory of Open Access Journals (Sweden)

    Isaías Merma

    2012-06-01

    Full Text Available The research was conducted in the geographical region of Alto Urubamba, province of La Convencion, Cusco - Peru. The objective was to identify types of farmers and evaluate crops sustainability on farms of high forest. Surveys were applied to a sample of 106 farmers in both biophysical and socio-economic terms in order to identify typology; this information was analyzed through descriptive statistics. Multivariate analysis using preselected variables was performed to identify types of farmers. In addition, sustainability of eight tropical crops was evaluated; for this purpose, three farms for each crop were selected from 24 evaluated farms. Practical indicators of soil quality and crop health with a valuation from 0 to 10 were used; farmers participated during this evaluation. The results show that there are three types of farmers according to their efficiency in resources management and their economic logic. The crops of tea (6.65 and mango (6.50 obtained the highest values of sustainability, followed by coffee (6.25, cocoa (6.25, citrus (5.50, banana (5.45 and coca (5.10. Papaya (4.60 shows a value less than five; therefore, is considered as unsustainable according to local conditions.

  16. Reactor safety

    International Nuclear Information System (INIS)

    Meneley, D.A.

    The people of Ontario have begun to receive the benefits of a low cost, assured supply of electrical energy from CANDU nuclear stations. This indigenous energy source also has excellent safety characteristics. Safety has been one of the central themes of the CANDU development program from its very beginning. A great deal of work has been done to establish that public risks are small. However, safety design criteria are now undergoing extensive review, with a real prospect of more stringent requirements being applied in the future. Considering the newness of the technology it is not surprising that a consensus does not yet exist; this makes it imperative to discuss the issues. It is time to examine the policies and practice of reactor safety management in Canada to decide whether or not further restrictions are justified in the light of current knowledge

  17. 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

  18. 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

  19. Reactor container

    International Nuclear Information System (INIS)

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

    1976-01-01

    Purpose: To provide a container for a reactor provided with a pressure suppressing chamber pool which can prevent bubble vibrating load, particularly negative pressure generated at the time of starting to release exhaust from a main steam escape-safety valve from being transmitted to a lower liner plate of the container. Constitution: This arrangement is characterized in that a safety valve exhaust pool for main steam escape, in which a pressure suppressing chamber pool is separated and intercepted from pool water in the pressure suppressing chamber pool, a safety valve exhaust pipe is open into said safety valve exhaust pool, and an isolator member, which isolates the bottom liner plate in the pressure suppressing chamber pool from the pool water, is disposed on the bottom of the safety valve exhaust pool. (Nakamura, S.)

  20. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    In the system described the fuel elements are arranged vertically in groups and are supported in such a manner as to tend to tilt them towards the center of the respective group, the fuel elements being urged laterally into abutment with one another. The elements have interlocking bearing pads, whereby lateral movement of adjacent elements is resisted; this improves the stability of the reactor core during refuelling operations. Fuel elements may comprise clusters of parallel fuel pins enclosed in a wrapper of hexagonal cross section, with bearing pads in the form of spline-like ribs located on each side of the wrapper and extending parallel to the longitudinal axis of the fuel element, being interlockable with ribs on pads of adjacent fuel elements. The arrangement is applicable to a reactor core in which fuel elements and control rod guide tubes are arranged in modules each of which comprises a cluster of at least three fuel elements, one of which is rigidly supported whilst the others are resiliently tilted towards the center of the cluster so as to lean on the rigidly supported element. It is also applicable to modules comprising a cluster of six fuel elements, each resiliently tilted towards a central void to form a circular arch. The modules may include additional fuel elements located outside the clusters and also resiliently tilted towards the central voids, the latter being used to accommodate control rod guide tubes. The need for separate structural members to act as leaning posts is thus avoided. Such structural members are liable to irradiation embrittlement, that could lead to core failure. (U.K.)

  1. 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.

  2. Energy and quality of life: a case study in HPP Tijuco Alto, Ribeira, SP; Energia e qualidade de vida: estudo de caso da Uhe Tijuco Alto no Municipio de Ribeira, SP

    Energy Technology Data Exchange (ETDEWEB)

    Conceicao, Andre Luiz da [Universidade Estadual de Campinas (FEM/UNICAMP), SP (BRazil). Fac. de Engenharia Mecanica], email: conceicao.andreluiz@yahoo.com.br; Seixas, Sonia Regina da Cal [Universidade Estadual de Campinas (NEPAM/UNICAMP), SP (BRazil). Nucleo de Estudos e Pesquisas Ambientais], email: srcal@unicamp.br

    2010-07-01

    This paper deals with a critical and reflexive that the issue involving the possibility of construction and operation of Hydroelectric Power (HEP) Tijuco Alto, the upper course of the Ribeira Valley between Sao Paulo and Parana, in the Vale do Ribeira. This project will directly affect the towns of Ribeira-SP, Itapirapua Paulista-SP, Cerro Azul-PR, Dr. Ulysses-PR and Adrianopolis-PR. Thus, we defined the main objective of the research examines the quality of life in the city of Ribeira-SP, at the possibility of deployment of the dam. Thus, field research was conducted in the city and interviews with residents, where it was possible to observe, among other things the precarious economic conditions, social, urban and cultural community. Another aspect noted was the fact that most respondents to position themselves for the construction of the HPP Tijuco Alto, citing primarily the need for local development and increased job opportunities. Those opposing the plant, highlighted environmental issues, mainly, reasons related to loss of peace and security site. Regardless of those who are for or against, a technical opinion issued by IBAMA in 2008 points to the likely deployment of the HPP Tijuco Alto. (author)

  3. HTLV-I en población de alto riesgo sexual de Pisco, Ica, Perú.

    Directory of Open Access Journals (Sweden)

    Patricia GARRIDO

    1997-07-01

    Full Text Available Objetivo: Se estudiaron 141 personas con alto riesgo sexual en la ciudad de Pisco para detectar infección por HTLV-I. Material y Métodos: Se encuestaron y se tomaron muestras de sangre a 141 personas que involucró a trabajadoras sexuales (32, varones homosexuales (54, y varones bisexuales(55. Resultados: Tres de treintidós (10.4% trabajadoras sexuales fueron positivas; uno de cincuenticuatro (1.9% de varones homosexuales y ninguno de 55 bisexuales. Hubo una elevada frecuencia de parejas, así como el antecedente de enfermedades de transmisión sexual (ETS en estos grupos con comportamiento de riesgo. Conclusiones: El HTLV-I es una infección frecuente en grupos de alto riesgo sexual de Pisco-Perú. (Rev Med Hered 1997; 8:104-107.

  4. Sobre la determinación de la calidad de las escorias de horno alto y de las puzolanas

    Directory of Open Access Journals (Sweden)

    Wittekindt, W.

    1964-06-01

    Full Text Available Not availableEn la molienda de clínker portland con escoria de horno alto para obtener cemento portland de hierro y cemento de horno alto, uno está más seguro de la calidad del clínker que de la escoria. El análisis del clínker y el cálculo de los minerales de clínker, facilitado por este análisis, nos dice ya, en gran parte, si se puede fabricar con este clínker un cemento portland de mayor o menor resistencia, si pueden esperarse buenas resistencias iniciales o si hay que contar más bien con mayores resistencias finales, cual es la resistencia del cemento a los sulfatos, etc.

  5. Relación entre el estilo de vida de una joven deportista de alto rendimiento y los patrones funcionales de salud de Marjory Gordon

    OpenAIRE

    Fabra Heredia, Juan Manuel; Casadó Marín, Lina

    2014-01-01

    Estudio de caso que busca conocer y comprender la relación que hay entre el estilo de vida de una joven deportista de alto rendimiento y los patrones funcionales de salud, a través de la valoración realizada a una joven deportista de alto rendimiento, desde una perspectiva holística, para adentrarse en las peculiaridades propias de este estilo de vida y crear un punto de partida para los cuidados de enfermería dirigidos a deportistas de alto rendimiento. En este caso, se observaron factores p...

  6. Evaluation of some energy options for the replacement of wood in cooking food in the Region Alto Patia

    International Nuclear Information System (INIS)

    Santacruz, Carlos A; Macia, Andres F

    2006-01-01

    In the present article an environmental evaluation appears financier and social of the different power solutions for the substitution from the wood in the food baking. First begins to describe the region of the Alto Patia, soon the objective population defines, this is village the San Juanito, in addition and they define the evaluation criteria the propose technologies that are: Solar, Electric, coal, gas and finally it is selected most suitable for this region.

  7. Lípidos séricos en escolares y adolescentes sanos chilenos de estrato socioeconómico alto

    Directory of Open Access Journals (Sweden)

    Zacarías S. José, Dr.

    2012-11-01

    Conclusiones: En niños y adolescentes chilenos sanos de estratos socioeconómicos altos, hay una alta proporción con colesterol total y colesterol LDL en zonas de riesgo o aumentadas. Las concentraciones de colesterol de adolescentes mujeres son significativamente mayores que las de varones. No se observó una asociación de lípidos séricos con perímetro abdominal o con IMC.

  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. The prototype fast reactor

    International Nuclear Information System (INIS)

    Broomfield, A.M.

    1985-01-01

    The paper concerns the Prototype Fast Reactor (PFR), which is a liquid metal cooled fast reactor power station, situated at Dounreay, Scotland. The principal design features of a Fast Reactor and the PFR are given, along with key points of operating history, and health and safety features. The role of the PFR in the development programme for commercial reactors is discussed. (U.K.)

  10. 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)

  11. NCSU Reactor Sharing Program

    International Nuclear Information System (INIS)

    Perez, P.B.

    1993-01-01

    The Nuclear Reactor Program at North Carolina State University provides the PULSTAR Research Reactor and associated facilities to eligible institutions with support, in part, from the Department of Energy Reactor Sharing Program. Participation in the NCSU Reactor Sharing Program continues to increase steadily with visitors ranging from advance high school physics and chemistry students to Ph.D. level research from neighboring universities

  12. Reactor safety method

    International Nuclear Information System (INIS)

    Vachon, L.J.

    1980-01-01

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

  13. Sedimentation survey of Lago Loíza, Trujillo Alto, Puerto Rico, July 2009

    Science.gov (United States)

    Soler-López, Luis R.; Licha-Soler, N.A.

    2014-01-01

    Lago Loíza is a reservoir formed at the confluence of Río Gurabo and Río Grande de Loíza in the municipality of Trujillo Alto in central Puerto Rico, about 10 kilometers (km) north of the town of Caguas, about 9 km northwest of Gurabo, and about 3 km south of Trujillo Alto (fig. 1). The Carraizo Dam is owned and operated by the Puerto Rico Aqueduct and Sewer Authority (PRASA), and was constructed in 1953 as a water-supply reservoir for the San Juan Metropolitan area. The dam is a concrete gravity structure that is located in a shallow valley and has a gently sloping left abutment and steep right abutment. Non-overflow sections flank the spillway section. Waterways include an intake structure for the pumping station and power plant, sluiceways, a trash sluice, and a spillway. The reservoir was built to provide a storage capacity of 26.8 million cubic meters (Mm3) of water at the maximum pool elevation of 41.14 meters (m) above mean sea level (msl) for the Sergio Cuevas Filtration Plant that serves the San Juan metropolitan area. The reservoir has a drainage area of 538 square kilometers (km2) and receives an annual mean rainfall that ranges from 1,600 to 5,000 millimeters per year (mm/yr). The principal streams that drain into Lago Loíza are the Río Grande de Loíza, Río Gurabo, and Río Cañas. Two other rivers, the Río Bairoa and Río Cagüitas, discharge into the Río Grande de Loíza just before it enters the reservoir. The combined mean annual runoff of the Río Grande de Loíza and the Río Gurabo for the 1960–2009 period of record is 323 Mm3. Flow from these streams constitutes about 89 percent of the total mean annual inflow of 364 Mm3 to the reservoir (U.S. Geological Survey, 2009). Detailed information about Lago Loíza reservoir structures, historical sediment accumulation, and a dredge conducted in 1999 are available in Soler-López and Gómez-Gómez (2005). During July 8–15, 2009, the U.S. Geological Survey (USGS) Caribbean Water Science

  14. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    Baeten, Peter

    2006-01-01

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

  15. Reactor core and initially loaded reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Koyama, Jun-ichi; Aoyama, Motoo.

    1989-01-01

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

  16. 222 Rn exposure assessment in the caves of Parque Estadual Turistico do Alto Ribeira (PETAR)

    International Nuclear Information System (INIS)

    Alberigi, Simone

    2006-01-01

    In the present work, radon concentrations in six caves of PETAR - Parque Estadual Turistico do Alto Ribeira (High Ribeira River Touristic State Park) were carried out with Makrofol E solid state nuclear track detectors (SSNTD) and used to assess the annual effective dose received by regional tour guides. The park has four visitation centers: Santana, Ouro Grosso, Caboclos e Casa de Pedra and receives nearly 40,000 people annually. The caves evaluated were Couto, Agua Suja, Laje Branca, Morro Preto and Santana, from Santana center and Alambari de Baixo from Ouro Grosso center, for being the most frequently visited caves. The exposure period of the SSNTD was, at least, three months, over a period of 26 months, from October 2003 to November 2005.The 222 Rn concentrations lay in a range from 153 Bq.m -3 to 6607 Bq.m -3 and we observed that, in general, for chilly weather, the radon levels decrease. The annual effective dose, considering the most realistic scenario, with geometric mean concentrations, an equilibrium factor of 0.5 and annual exposure time for each cave, varied from 0.2 mSv.a -1 for the Couto cave, strongly ventilated, to 4.0 mSv.a -1 for the Santana cave, the most frequently visited and no external communication. For the worst scenario, with arithmetic mean concentrations, equilibrium factor 1 and annual exposure time for all caves, the annual effective dose was 16.1 mSv.a -1 . All assessed effective doses received by the tour guides are bellow 20 mSv.a -1 suggested as an annual effective dose limit for occupational exposure by the International Commission of Radiological Protection (ICRP 60, 1990). (author)

  17. Fish mercury concentration in the Alto Pantanal, Brazil: influence of season and water parameters.

    Science.gov (United States)

    Hylander, L D; Pinto, F N; Guimarães, J R; Meili, M; Oliveira, L J; de Castro e Silva, E

    2000-10-16

    The tropical flood plain Pantanal is one of the world's largest wetlands and a wildlife sanctuary. Mercury (Hg) emissions from some upstream gold mining areas and recent findings of high natural Hg levels in tropical oxisols motivated studies on the Hg cycle in the Pantanal. A survey was made on total Hg in the most consumed piscivorous fish species from rivers and floodplain lakes in the north (Cáceres and Barão de Melgaço) and in the south part of Alto Pantanal (around the confluence of the Cuiabá and Paraguai rivers). Samples were collected in both the rainy and dry seasons (March and August 1998) and included piranha (Serrasalmus spp.), and catfish (Pseudoplatystoma coruscans, pintado, and Pseudoplatystoma fasciatum, cachara or surubim). There was only a small spatial variation in Hg concentration of the 185 analyzed fish samples from the 200 x 200 km large investigation area, and 90% contained total Hg concentration below the safety limit for regular fish consumption (500 ng g(-1)). Concentration above this limit was found in both Pseudoplatystoma and Serrasalmus samples from the Baia Siá Mariana, the only acid soft-water lake included in this study, during both the rainy and dry seasons. Concentration above this limit was also found in fish outside Baia Siá Mariana during the dry season, especially in Rio Cuiabá in the region of Barão de Melgaço. The seasonal effect may be connected with decreasing water volumes and changing habitat during the dry season. The results indicate that fertile women should restrict their consumption of piscivorous fishes from the Rio Cuiabá basin during the dry season. Measures should be implanted to avoid a further deterioration of fish Hg levels.

  18. NUEVAS TERAPIAS EN EL MANEJO DE LOS GLIOMAS DE ALTO GRADO

    Directory of Open Access Journals (Sweden)

    Dr. Raúl Valenzuela

    2017-05-01

    Full Text Available El reto de mejorar el tratamiento actual de los gliomas de alto grado ha sido abordado con inmensa creatividad, desarrollándose una gran variedad de estrategias para este fin. El análisis interino de un estudio fase III mostró que el beneficio de la terapia standard mejora al complementarla con terapia de campos eléctricos alternantes (Novo TTF-100 A; dadas las limitaciones de un análisis interino, queda por establecer la real magnitud y relevancia clínica de esta mejoría. El presunto beneficio de usar tratamiento antiviral contra citomegalovirus es muy controvertido y su utilidad no se ha demostrado en forma fehaciente. Las terapias antiangiogénicas han mostrado ser útiles para el manejo de las recurrencias, al menos como tratamiento sintomático, pero no han demostrado mejorar la sobrevida en pacientes de novo. La terapia dirigida contra señales intracelulares de crecimiento, conceptualmente muy atractiva, todavía no ha logrado resultados clínicos exitosos. Hay datos preliminares promisorios respecto al uso clínico de vacunas antitumorales y de inmunomodulación con inhibidores de “checkpoints”; también hay algunos datos preliminares a favor del uso de virus oncolíticos. La terapia genética parece estar en etapas aún muy tempranas de su desarrollo y probablemente demore más tiempo en llegar a demostrar utilidad clínica.

  19. Diversidad de peces en la cuenca del Alto Yuruá (Ucayali, Perú

    Directory of Open Access Journals (Sweden)

    Blanca Rengifo

    2013-05-01

    Full Text Available El presente estudio compara los patrones de diversidad de peces en la Cuenca del Alto Yurúa. El área de estudio comprendió tres sub cuencas: Beu, Breu y Yurúa, todas sin impacto antropogénico. Mediante pesca con redes de arrastre a orilla, se colectaron 10564 individuos y se identificaron 185 especies de peces. En escala regional, el promedio del índice de diversidad Shannon (H’ para Beu fue de 2,02; para Breu 1,84 y para Yuruá 1,75. Según el análisis de rarefacción, Yurúa tuvo la riqueza de especies esperada más alta (91 spp. en comparación con Beu (87 y Breu (68. En la escala local, los ambientes lóticos presentaron mayor riqueza y diversidad que los lénticos. La diversidad promedio (H’ fue mayor en lóticos (Beu 2,04; Breu 1,90; y Yurúa 1,86, comparados con lénticos de los mismos (Beu 1,66; Breu 1,86; y Yurúa 1,82. La mayor diversidad de peces observada en ambiente lóticos podría explicarse por que la mayoría de peces amazónicos tienen el comportamiento de desplazarse por los canales principales de los ríos, mientras que los lagos pueden presentar condiciones de estrés estacional (alta presión de depredación y bajas concentraciones de oxígeno disuelto.

  20. Tratamento do paciente com mielodisplasia de alto risco Treatment of myelodysplastic syndrome in high risk patients

    Directory of Open Access Journals (Sweden)

    Evandro M. Fagundes

    2006-09-01

    Full Text Available O tratamento do paciente com mielodisplasia deve ser feito considerando o risco biológico da doença, a idade e as condições clínicas do paciente. De um modo geral, uma doença de alto risco necessitaria de um tratamento mais agressivo. Porém, devido à elevada idade mediana no diagnóstico, a maioria dos pacientes não tolera tratamentos intensivos. O transplante de células-tronco hematopoiéticas é a única opção para aqueles que objetivam a cura da doença. Para aqueles que não podem se submeter a um transplante, as opções incluem o uso de quimioterapia intensiva, agentes hipometilantes, tratamento suportivo e/ou inclusão em estudos clínicos. A quimioterapia intensiva semelhante à utilizada para leucemia mielóide aguda é uma boa opção para pacientes em boas condições clínicas e com menos de 65 anos de idade.To initiate a treatment for myelodysplastic syndrome, the physician should consider the patient's age, status performance and the risk of transformation to acute myeloid leukemia (AML and death. In theory, a high risk disease should be approached with intense treatment however most patients are not healthy enough to receive aggressive treatment with chemotherapy or stem cell transplantation. For those who are not able to receive a transplantation, the treatment options include AML-like chemotherapy, hypomethylating agents, supportive care alone or participation in a clinical trial. AML-like chemotherapy is still a reasonable choice for those patients who are in good clinical conditions and are younger than 65 years of age.

  1. Occupational safety and health practices among flower greenhouses workers from Alto Tietê region (Brazil)

    International Nuclear Information System (INIS)

    Ribeiro, Marcela G.; Colasso, Camilla G.; Monteiro, Paula P.; Filho, Walter R. Pedreira; Yonamine, Maurício

    2012-01-01

    In this preliminary study the occupational safety and health practices among flower greenhouses workers were evaluated. The study was carried out in the alto Tietê region, located at the Sao Paulo State, Brazil. Inadequate welfare facilities; poor pesticide storage, use and disposal conditions; use of highly toxic pesticides; lack of adequate data regarding pesticide use; and incorrect use and maintenance of PPE were observed in most of the visited greenhouses. These results suggest that, in greenhouses, workers may be at higher risk of pesticide exposure, due to many factors that can intensify the exposure such as the lack of control on reentry intervals after pesticide application. Specific regulations are needed to ensure better OSH practices on pesticide use and to improve working conditions in greenhouses, in order to deal with the peculiarities of greenhouse working environment. Some of the special requirements for greenhouses workers' protection are the establishment of ventilation criteria for restricted entry interval; clear reentry restrictions; and EPI for workers other than applicators that need to enter the greenhouse before expiring REI interval. Another important way to improve OSH practices among workers includes the distribution of simple guidelines on the dos and don'ts regarding OSH practices in greenhouses and extensively training interventions to change the perception of hazards and the behavior towards risk. - Highlights: ► Occupational safety and health practices among flower greenhouses workers were evaluated. ► Lack of clear reentry restrictions can intensify the exposure in greenhouses. ► Specific regulations dealing with the peculiarities of greenhouse working environment are needed. ► Distribution of simple guidelines relying on greenhouse working can improve OSH practices. ► Training interventions are important to change the workers' perception of hazards and behavior towards risk.

  2. Ethnobotanical notes about some uses of medicinal plants in Alto Tirreno Cosentino area (Calabria, Southern Italy

    Directory of Open Access Journals (Sweden)

    Impieri Massimo

    2007-11-01

    Full Text Available Abstract Background The present paper contributes to enrich the ethnobotanical knowledge of Calabria region (Southern Italy. Research was carried out in Alto Tirreno Cosentino, a small area lying between the Tyrrhenian coast and the Pollino National Park. In the area studied medicinal plants still play a small role among farmers, shepherds and other people who live far from villages and built-up areas. Methods Information was collected by interviewing native people, mainly elderly – engaged in farming and stock-raising activities – and housewives. The plants collected, indicated by the locals, have been identified according to "Flora d'Italia". The exsiccata vouchers are preserved in the authors' own herbaria. Results 52 medicinal species belonging to 35 families are listed in this article. The family, botanical and vernacular name, part of the plant used and respective manipulation are reported there and, when present, similar or identical uses in different parts of Calabria or other Italian regions are also indicated. Conclusion Labiatae, Rosaceae and Leguminosae are the families most frequently present, whilst Compositae and Brassicaceae are almost absent. The uses of the recorded species relate to minor ailments, mainly those of the skin (15 species, respiratory apparatus diseases (11, toothache, decay etc. (10 and rheumatic pains (8. The easy availability of these remedies provides a quick way of curing various minor complaints such as tooth-ache, belly and rheumatic pain and headaches and can also serve as first aid as cicatrizing, lenitive, haemostatic agents etc. The role in veterinary medicine is, on the contrary, more important: sores, ulcers, tinea, dermatitis, gangrenous wounds of cattle, and even respiratory ailments are usually cured by resort to plants.

  3. CONSIDERATIONS FOR THE ADJUSTMENT OF SWINE PRODUCTION CONDUCT IN THE ALTO URUGUAI CATARINENSE

    Directory of Open Access Journals (Sweden)

    Cláudio Rocha de Miranda

    2011-07-01

    Full Text Available This paper presents a partial survey of the SPC evaluation, conducted in 2010, with swine signatory to the properties of the SPC in the microregion of Alto Uruguai Catarinense, in order to evaluate the effective implementation of corrective measures established in the Term. The survey was conducted through visits in September 2010 in 58 farmers, selected from representative sampling. For the sampling plan two basic conditions should be followed: 1 in all municipalities nineteen producers should be visited, 2 the type of contractual relationship of the pig farmers should be considered. For the average pig farmer environmental adaptations such expenses are considered significant, given remuneration of the activity is considered small. The SPC was considered of great importance for about 70% of respondents. For some pig farmers, the SPC is serving as a sort of extension of time in which the pig farmers are taking advantage to make the maximum depreciation of facilities. In the farms visited, there was being done isolation of the areas of riparian and annotation of the legal reserve, but it appears that such practice is being conducted in a bureaucratic way. The aging of pig farmers is an indisputable fact, perceiving few properties where there are possible successors. Considering the actions that are being implemented, it appears that term led to the development of numerous environmental improvements on farms. Furthermore, provided the necessary security for the pig farmers continue producing. However, it can be perceived the need for the measures envisaged are associated with effective monitoring and technical education, since some measures are being met, as merely bureaucratic, given that many producers do not understand the environmental importance of compliance with these legal requirements.

  4. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

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

  5. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Yasutomi, Yoshiyuki; Nakagawa, Moroo; Sawai, Yuichi; Chiba, Akio; Suzuki, Yasutaka.

    1997-01-01

    Silicon composited with reinforcing metals is used for a divertor cooling substrate having an effect as a cooling tube to provide a silicon base composite material having increased electric resistance and toughness. The blending ratio of reinforcing materials in the form of granules, whiskers or long fibers is controlled in order to control heat conductivity, electric resistivity and mechanical performances. The divertor cooling substrate comprising the silicon base composite material is integrated with a plasma facing material. The production method therefor includes ordinary metal matrix composite forming methods such as powder metallurgy, melting penetration method, high pressure solidification casting method, centrifugal casting method and vacuum casting method. Since the cooling plate is constituted with the light metal and highly electric resistant metal base composite material, sharing force due to eddy current can be reduced, and radiation exposure can be minimized. Accordingly, a cooling structure for a thermonuclear reactor effective for the improvement of environmental problems caused by waste disposal can be attained. (N.H.)

  6. 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

  7. Nuclear reactors

    International Nuclear Information System (INIS)

    Pearson, K.G.

    1977-01-01

    Reference is made to auxiliary means of cooling the nuclear fuel clusters used in light or heavy water cooled nuclear reactors. One method is to provide one or more spray cooling tubes. From holes in the side walls of those tubes coolant water may be sprayed laterally into the cluster against the rods. The flow of main coolant may thus be supplemented or even replaced by the auxiliary coolant. A difficulty, however, is that only those fuel rods close to a spray cooling tube can readily be reached by the auxiliary coolant. In the arrangement described, where the fuel rods are spaced apart by transverse grids, at least one of the interspaces between the grids is provided with an axially extending auxiliary coolant conduit having lateral holes through which an auxiliary coolant is sprayed into the cluster. A deflector is provided that extends from a transverse grid into a position in front of the holes and deflects auxiliary coolant on to parts of the fuel rods otherwise inaccessible to the auxiliary coolant. The construction of the deflector is described. (U.K.)

  8. 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.)

  9. 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

  10. 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

  11. 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)

  12. 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)

  13. 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

  14. Guide to power reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

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

  15. Reactor core of FBR type reactor

    International Nuclear Information System (INIS)

    Hayashi, Hideyuki; Ichimiya, Masakazu.

    1994-01-01

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

  16. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  17. Pimelodus paranaensis, sp. n., um novo Pimelodidae (Pisces, Siluriformes do Alto Paraná, Brasil

    Directory of Open Access Journals (Sweden)

    Heraldo A. Britski

    1988-01-01

    Full Text Available Descreve-se Pimelodus paranaensis, sp. n., da bacia do Alto Paraná, Brasil, com base em 20 exemplares. A nova espécie pode ser assim diagnosticada: (i dentes presentes e formando duas áreas isoladas no vômer; (ii faixa pré-maxilar de dentes com um ângulo projetado para trás; (iii teto do crânio coberto por pele fina; (iv comprimento da nadadeira adiposa 3,9 a 4,3 vezes no comprimento padrão; (v a maior altura da nadadeira adiposa 3,1 a 4.3 vezes no seu comprimento; (vi região dorsal do corpo de cor castanha com pequenas manchas arredondadas, castanho-escuras. Apesar de possuir dentes vomerianos como em Pimelodus albicans, e como em certos exemplares de P. clarias (sensu Eigenmann & Eigenmann, 1890, achamos que as verdadeiras relações desta nova espécie e sua situação genérica só poderão ser estabelecidas após uma nova boa revisão do grupo.Pimelodus paranaensis, n. sp., from the Upper Paraná basin, is described on the basis of 20 specimens. The new species can be diagnosed as follows: (1 teeth present and forming two isolated on the vomer; (2 premaxillary band of teeth with a backward projecting angle; (3 top of head covered with thin layer of skin; (4 adipose fin basis 3,9 to 4.6 in standard length; (5 greatest depth of adipose fin 3.1 to 4.3 in its length, (6 dark spots along the dorsum. In spite of having teeth on the vomer as Pimelodus albicans, and as some specimens of P. clarias (sensu Eigenmann & Eigenmann, 1890 and in being similar to Bagropsis reinhardti in many respects, we feel that the true relationships and the generic status of the new species can be established only after a thorough revision of the group.

  18. Social perception of the forest landscape in Trentino-Alto Adige (Italy: comparison of case studies

    Directory of Open Access Journals (Sweden)

    Pastorella F

    2016-12-01

    Full Text Available The landscape is the product of human activities and nature as developed during the centuries. However, the landscape has a symbolic value because it can be considered the identity and culture of a territory that includes the values and beliefs of local population. The Alpine landscape is a unicum in the world due to its geomorphologic, climatic and vegetation characteristics and socio-economic conditions of local population. Over the centuries the social perception of Alps has changed: in a first phase the Alps were considered “horrible and scary mountains”, later Alps were perceived as “beautiful and fascinating places”, and currently the Alpine mountains are considered a place of relaxation and recreation. The analysis of landscape perception aimed to investigate the visitors’ opinions about landscape is an important instrument to support the decision concerning the land planning and management. This study focuses on the analysis of the aesthetic perception of visitors on Alpine landscapes following two perspectives: a first overall perspective considering the landscape as a mosaic of different land uses and a second perspective of detail observing the individual components that characterize the forest landscape. The aim of the study is to identify the most appreciated elements of landscape from the aesthetic point of view and the influence of socio-demographic characteristics of respondents on individual perception. In order to investigate the perception about the Alpine landscapes 358 visitors of two sites of Trentino-Alto Adige (Val di Genova and Santa Maria lake were interviewed using a structured questionnaire. The results show that the most appreciated elements of the landscape by the visitors are water (lakes and rivers and forests. These preferences are also conditioned by the site where the interviews were made. In addition, the results show that for the respondents of this survey the forest with the highest attractiveness

  19. Conduta na lesão intraepitelial de alto grau em mulheres adultas

    Directory of Open Access Journals (Sweden)

    Pauliana Sousa Oliveira

    Full Text Available O câncer cervical é a segunda causa mais comum de câncer entre as mulheres no mundo, apesar de apresentar grande potencial de prevenção e cura quando diagnosticado e tratado precocemente, o que pode reduzir a taxa de mortalidade entre as acometidas. Como não há consenso entre as medidas terapêuticas nas lesões intraepiteliais escamosas cervicais de alto grau (HSIL, buscamos discutir a conduta frente às mulheres adultas que apresentam HSIL e o seguimento após o procedimento adotado. Foi realizada pesquisa eletrônica no Medline (através do PubMed, National Guidelines Clearinghouse, Google Acadêmico e Lilacs. Os consensos identificados foram avaliados segundo sua validade e recomendações. Em relação ao acompanhamento após o tratamento, o Europeu acompanha por citologia de 6/6 meses; o Australiano, citologia e colposcopia de 6/6 meses; o Americano preconiza a realização da captura híbrida em seis a 12 meses ou citologia em seis meses. Já o Projeto Diretrizes do Brasil recomenda que reavaliações clínicas e colpocitológicas devam ser realizadas a cada três ou quatro meses nos primeiros dois anos de seguimento. Estudos comparando o método "Ver e Tratar" com os três passos (histologia, colposcopia, biópsia concluíram que este último é indicado em mulheres LSIL/ASCUS antes de se submeterem à exérese da zona de transformação (EZT, enquanto que o "Ver e Tratar" é indicado em mulheres com HSIL comprovada na citologia e sugestiva na colposcopia, pois apresenta como vantagens, o baixo custo e a resolução imediata. Todos os consensos são unânimes ao afirmar que frente à HSIL comprovada, retira-se a lesão por meio de ablação ou conização ou EZT.

  20. Alto Patache fog oasis in the Atacama Desert: Geographical basis for a sustainable development program

    Science.gov (United States)

    Calderón, M.; Cereceda, P.; Larrain, H.; Osses, P.; Pérez, L.; Ibáñez, M.

    2010-07-01

    Alto Patache coastal fog oasis is a protected area located south of Iquique, Northern Chile, being presently in charge of the Atacama Desert Center (ADC) research group of the Pontificia Universidad Católica de Chile, since 1997. On 2007, the Chilean Government bestowed a piece of land stretch covering 1,114 hectares to ADC scientific group for scientific research, ecosystem protection and environmental education. This oasis has been recently studied from different points of view: climate, biogeography, fog collection, geomorphology, soil survey and land use planning, plant distribution, conservation and archaeology. During 2009, a study of the geographical basis to elaborate a general management plan was undertaken to collect information to fulfill our planned out objectives. Through this study, georreferenciated strategic information was compiled to evaluate future actions conducting to a sustainable development within the protected area. This information was translated into thematic maps showing the spatial distribution of variables like: climate, geology, geomorphology, soils, vegetation, fauna, archaeological sites and management zones. The methodology used is the analysis of satellite imagery, using GPS by creating a cartographic Data Base incorporated in GIS. Results show that the area starts at the littoral plain, ranging from 500 m to 2.000 m, being continued in parts by a piedmont intercepted by a very abrupt mega-cliff, or hectares of climbing sand dunes leading to a short high plateau limited by a soft hilly area to the East. Two soil types are characteristic: Entisols (Torriorthent) covering the coastal beach sediments, and Aridisols along the cliff and adjacent hills. Vegetation consists not only of a very rich lichen cover, but also of endangered vascular species associations constituting a very fragile sub-tropical coastal desert community, such as Eulychnia, Cumulopuntia, Eriosyce cacti, and Lycium - Nolana- Ephedra communities. Fog oasis

  1. Metal and trace element sediment assessment from Guarapiranga reservoir, Alto Tiete Basin, Sao Paulo, SP, Brazil

    International Nuclear Information System (INIS)

    Guimaraes, Guilherme Moura

    2011-01-01

    The Guarapiranga Reservoir, located in Sao Paulo metropolitan region, Brazil, is responsible for supplying about 20% of the entire population's water needs of this region or approximately 3.7 million people. However, this system has shown significant degradation in water quality, due to untreated domestic sewage and industrial effluents. In this study sediment samples were collected at five points along the reservoir and total concentration of some major (Fe, K and Na), trace (As, Ba, Br, Co, Cr, Cs, Hf, Hg, Rb, Sb, Sc, Ta, Tb, Th, U, V and Zn) and rare earth (Ce, Eu, La, Lu, Nd, Sm, Tb and Yb) elements were determined by instrumental neutron activation analysis (INAA). By inductively coupled plasma optical emission spectrometry (ICP OES) the concentrations of Al, Ba, Be, Ca, Co, Cr, Cu, Fe, K, Li, Mg, Mn, Na, Ni, Pb, Ti, V e Zn were determined after digestion procedure following US EPA 3051 methodology. The concentrations of metals Cd and Pb were determined by graphite furnace atomic absorption spectrometry (GFAAS) and total Hg by cold vapor atomic absorption spectrometry (CVAAS). Methodology validation according to precision and accuracy was performed by reference materials analyses for the three different analytical techniques used. Multielemental results obtained by INAA were compared to NASC (North American Shale Composite), Upper Continental Crust (UCC) and soil from Guarapiranga park values. The Enrichment Factor (EF) and Geo accumulation Index (Igeo) were also evaluated for these data. Metal concentration results by ICP OES and AAS in the samples were compared to the TEL and PEL oriented values established by the Canadian Council of Ministers of the Environment and also adopted by CETESB (Environmental Protection Agency of the Sao Paulo State). The results were also compared to regional reference values (VRR) of limnic sediments from the Alto Tiete Basin. From these data an assessment of metal and trace element accumulated in the sediments from the

  2. FORMAS DE LEITO E TRANSPORTE DE CARGA DE FUNDO DO ALTO RIO PARANÁ

    Directory of Open Access Journals (Sweden)

    Débora Pinto Martins

    2005-12-01

    Full Text Available O presente trabalho estima o transporte de carga de fundo no alto rio Paraná em Porto São José, PR (22º45’52”S e 53°10’34”W, num trecho de aproximadamente 2 km a jusante da Usina Hidrelétrica Engenheiro Sérgio Motta (Porto Primavera, onde o rio Paraná apresenta canal único com largura média de 1.200m e vazão média anual é de 8.912 m³/s. O cálculo da carga de fundo do canal foi baseado na determinação do tamanho das formas de leito e de sua velocidade de deslocamento linear, obtidos a partir de sucessivos levantamentos batimétricos. Foram realizadas três campanhas de levantamentos ecobatimétricos em diferentes momentos do ciclo hidrológico do rio, sendo cada campanha constituída por dois levantamentos separados em intervalos de 16 a 20 dias. O cálculo da carga de fundo baseou-se equação: Cf = (1-pH k Ud onde p é a porosidade (adimensional, H a altura média das formas de leito (m, k o coeficiente morfométrico das formas de leito (adimensional e Ud a velocidade de deslocamento das formas de leito (m/dia. As dunas são as formas de leito predominantes neste trecho do rio Paraná, com comprimento entre 50 e 100 m (média de 70,68 m e altura de 0,80 a 2,20 m (média de 1,30 m. A velocidade média de deslocamento linear das formas de fundo foi de 56,8 m/mês, para o período de maior vazão; e 45,0 m/mês para o período de menor vazão. O transporte médio de carga e fundo no rio Paraná foi estimado em 2.820,6 ton/dia, o que corresponde a 1.029.300 ton/ano. Comparando com dados anteriores, os autores sugerem que o transporte hidrossedimentar de fundo no trecho de canal estudado está sofrendo interferência da barragem de Porto Primavera.

  3. Guanaco traces and hunting strategies at Alto Patache North Chilean fog oasis

    Science.gov (United States)

    Larrain, H.; Cereceda, P.; Pérez, L.

    2010-07-01

    1. In foregoing Fog Conferences, some of us have made explicit the rich botanic and faunistic inventory to be found at this Chilean Fog site. This was specially apparent under strong ENSO conditions, as it happened in 1997/98 in the area. Among the mammal biggest species represented, the guanaco (Lama guanicoe Müller) merits special mention. Clear traces of their presence and eventual hunting and slaughtering by primitive populations have survived until present times. Among them, the myriads of guanaco trails still covering practically all the slopes along the foggy area, close to the sea, and their wollowing and defecating places are found. Also, although less studied, plant eating traces left behind by roaming camelids can be seen. 2. Guanaco hunting traces still visible at Alto Patache can be portrayed differently through : A) Analysis of lithic artifacts used as arms in hunting operations; B) Botanic response to animal attack; C) Examination of topographic traits used by primitive man in guanaco hunting strategies. A. Hundreds of lithic instruments made of stone, were abandoned by hunters in situ, some of them were intact, some fragmented, which would demonstrate a direct relationship with hunting and slaughtering, and also their elaboration in workshops at place. Lithic points, scrapers and knives were found at places specially apt for hunting or slaughtering activities. Total isolation of the mountain fog site previous to our arrival in 1996, favoured their conservation at place. B. Careful observation of some local plants showed clear traces of guanaco feeding habits. As a proof thereof, old cactus of the species Eulychnia iquiquensis show in their basal portions clear signals in the forms of scars, caused by the eating by guanacos. Guanaco faeces were found at the foot of Ephedra plants. Many dead Stipa ichu plants (Gramineae), in different areas of the oasis provide evidence of cutting close to their basis, caused by sharp guanaco tooth under severe food

  4. Arsenic in drinking water in the Los Altos de Jalisco region of Mexico.

    Science.gov (United States)

    Hurtado-Jiménez, Roberto; Gardea-Torresdey, Jorge L

    2006-10-01

    To establish the degree of contamination by arsenic in drinking water in the Los Altos de Jalisco (LAJ) region of west-central Mexico, and to estimate the levels of exposure that residents of the area face. Total arsenic concentration (the sum of all arsenic forms, organic and inorganic) was determined for 129 public water wells in 17 municipal capitals (cabeceras municipales) of the LAJ region, using inductively coupled plasma-optical emission spectroscopy. For most of the wells, water samples were taken in both November 2002 and October 2003. The levels of exposure to arsenic were estimated for babies (10 kg), children (20 kg), and adults (70 kg). Mean concentrations of arsenic higher than the Mexican national guideline value of 25 micro g/L were found in 44 (34%) of the 129 wells. The mean concentration of total arsenic for the 129 wells ranged from 14.7 micro g/L to 101.9 micro g/L. The highest concentrations were found in well water samples collected in the cities of Mexticacán (262.9 micro g/L), Teocaltiche (157.7 micro g/L), and San Juan de los Lagos (113.8 micro g/L). Considering the global mean concentration for all the wells in each of the 17 cities, the mean concentration of arsenic exceeded the Mexican guideline value in 7 of the cities. However, the global mean concentration in all 17 cities was higher than the World Health Organization guideline value of 10 micro g/L for arsenic. The range of the estimated exposure doses to arsenic in drinking water was 1.1-7.6 micro g/kg/d for babies, 0.7-5.1 micro g/kg/d for children, and 0.4-2.7 micro g/kg/d for adults. At the exposure doses estimated in the LAJ region, the potential health effects from chronic arsenic ingestion include skin diseases, gastrointestinal effects, neurological damage, cardiovascular problems, and hematological effects. While all the residents may not be affected, an important fraction of the total population of the LAJ region is under potential health risk due to the ingestion of high

  5. Fiscalidad tributaria y post-tributaria en el Alto Imperio Romano

    Directory of Open Access Journals (Sweden)

    José Carlos Jordán Reyes

    2010-01-01

    Full Text Available Con el tránsito de la República al Imperio, el sistema impositivo romano experimenta una profunda transformación. La fiscalidad cívica, regulada minuciosamente en el tributum, tiene su continuidad en las reformas fiscales emprendidas por Augusto, principalmente en el nuevo impuesto de sucesiones, la vicesima hereditatum y en la capitatio terrena. Se trata de un modelo tributario basado en la tradición republicana y con un fuerte sentido legal. A este modelo tributario se superpuso, como consecuencia de las necesidades de un Imperio en expansión, una fiscalidad ecléctica, con aportaciones de tributos de origen oriental, ajenas por completo al universo jurídico romano. Destinados en un principio a las provincias, fueron contaminando el sistema tributario romano en su conjunto. Estos tributos foráneos fueron a su vez contaminados por normas de Derecho romano, que les aportaron una naturaleza jurídica de la que solían carecer. En resumen, a lo largo del alto Imperio se va configurando un sistema tributario híbrido, complejo, de raíces romanas y orientales, con rasgos de fuerte juridicidad y al mismo tiempo con anomalías en su naturaleza jurídica y procedimental.The shift from the Roman Republic to the Roman Empire brought about a profound transformation of the Roman tax system. The tax reforms set forth by Augustus, most particularly, the new heritage tax, the vicesima hereditatum, and the capitatio terrena, did not mean a complete break from the civic fiscality which the tributum carefully regulated. Augustus’s system of taxation was based on the republican tradition and it had a strong sense of legality. Because of the needs of an expanding Empire, they added to this system of taxation an eclectic fiscality which included oriental taxes which had nothing to do with the Roman legal tradition. Originally designed for the provinces, these oriental taxes pervaded and corrupted the entire Roman system of taxation. In the same way, they

  6. Sustentabilidad: Liderar Organizaciones Migrantes en el Uruguay- Aspectos Asociados al Alto Desempeño Empresarial

    Directory of Open Access Journals (Sweden)

    Alberto González

    2016-04-01

    Full Text Available Las empresas son organizaciones cuya actividad principal son los negocios y se suele confundir ambos aspectos: el negocio y la organi-zación. La experiencia muestra que las empresas que permaecen en el tiempo se caracterizan por gestionar y evolucionar la relación organización-negocio en principalmente tres modalidades: mejorando su modelo de negocio, integrando nuevos negocios y migrando a otros negocios. Es cada vez más necesario para la supervivencia de una organización, el fortalecer dicha competencia específica de “migrar”: capacidad de desvin-cularse de un (modelo de negocio y asumir otro (modelo de negocio. Esta realidad impacta diferente a cada stakeholder. Los propietarios pueden migrar con mayor facilidad si deciden retirar su capital, vender el negocio, etc. El costo para los trabajadores es superior, afecta su fuente de trabajo y las condiciones de vida familiar, hasta su inclusión o exclusión social. Para la comunidad, la caída o reconversión de una organización puede implicar un costo colectivo enorme. El pensamiento económico y administrativo ha tendido a focalizar el problema en la sustentabilidad del negocio, pero desde la mirada ética y pasando por la Doctrina Social de la Iglesia, la sustentabilidad de la organización resulta más importante que la sustentabilidad del negocio. Se entrevistaron 55 empresas uruguayas que han perdurado más de 30 años, soportando radicales cambios del entorno, manteniendo posiciones de primera línea en sus áreas de acción. Un análisis cuantitativo de sus respuestas ilustra los factores de alto desempeño de su gestión, y un análisis cuali-tativo identifica características asociadas a su sustentabilidad organizacional, las cuales se presentan mediante el concepto de organizaciones migrantes. Los resultados muestran que además de las competencias de gestión, importan los valores y las actitudes de la dirección, confirmando la relevancia que tiene para las escuelas de

  7. Tokamak reactor studies

    International Nuclear Information System (INIS)

    Baker, C.C.

    1981-01-01

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

  8. 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

  9. 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.

  10. 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

  11. 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

  12. 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

  13. 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

  14. Control for nuclear reactor

    International Nuclear Information System (INIS)

    Ash, E.B.; Bernath, L.; Facha, J.V.

    1980-01-01

    A nuclear reactor is provided with several hydraulically-supported spherical bodies having a high neutron absorption cross section, which fall by gravity into the core region of the reactor when the flow of supporting fluid is shut off. (auth)

  15. 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.

  16. 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.)

  17. Guidebook to nuclear reactors

    International Nuclear Information System (INIS)

    Nero, A.V. Jr.

    1976-05-01

    A general introduction to reactor physics and theory is followed by descriptions of commercial nuclear reactor types. Future directions for nuclear power are also discussed. The technical level of the material is suitable for laymen

  18. continuous stirred tank reactor (CSTR)

    African Journals Online (AJOL)

    AFRICAN JOURNALS ONLINE (AJOL) · Journals · Advanced Search ... stirred tank reactor (CSTR) and the small and large intestines as plug flow reactor (PFR) ... from the two equations are used for the reactor sizing of the modeled reactors.

  19. Variación antropométrica y nutricional en Susques y Alto Comedero entre 2002-2007

    Directory of Open Access Journals (Sweden)

    Bejarano, Ignacio

    2007-01-01

    Full Text Available Las poblaciones humanas experimentan variaciones de los parámetros antropométricos como expresión de los cambios socioambientales. El objetivo de este trabajo fue analizar la variación temporal de talla, peso y estado nutricional en dos poblaciones jujeñas situadas a distintos niveles altitudinales. Los datos procedieron de mediciones realizadas en 2002 y 2007 en poblaciones de 6 a 17 años de Susques (3500 m y Alto Comedero (1200 m. Se calcularon las categorías nutricionales de Waterlow y las diferencias entre talla y peso y categorías nutricionales se establecieron con ANOVA y prueba de comparación de proporciones (χ2 respectivamente. Para ambas poblaciones se observaron diferencias interanuales estadísticamente significativas de los promedios de talla y peso, siendo menores en Susques en el 2007, lo contrario sucede en Alto Comedero. Las diferencias interanuales de la categorías nutricionales no fueron estadísticamente significativas en Alto Comedero, pero si en Susques para normonutridos y obesos que disminuyeron y aumentaron respectivamente entre 2002 y 2007. En el contexto de las modificaciones socioeconómicas experimentadas por la población susqueña en los últimos años, debido a su mayor conexión e integración con poblaciones vecinas por la apertura del Paso de Jama, los resultados indicarían un empeoramiento de las condiciones nutricionales de su población infanto juvenil.

  20. Reactor physics aspects of CANDU reactors

    International Nuclear Information System (INIS)

    Critoph, E.

    1980-01-01

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

  1. Estructura temporal, interacción táctica y eficacia en asaltos de esgrima de alto nivel

    OpenAIRE

    Tarragó Garcia, Rafael

    2017-01-01

    [spa] El objetivo general de esta tesis doctoral fue caracterizar las acciones técnico-tácticas en los asaltos de esgrima de competición de alto nivel en sus seis modalidades. Para ello se determinó la estructura temporal de los asaltos, analizando la eficacia de las acciones y la efectividad bilateral de las frases de armas en función del periodo del asalto, de la zona de la pista en que se realizaron y del tiempo que restaba de asalto, y efectuando un análisis del diálogo táctico. Se estru...

  2. HTLV-I en población de alto riesgo sexual de Pisco, Ica, Perú.

    OpenAIRE

    GARRIDO, Patricia; ANICAMA, Rolando; GOTUZZO, Eduardo; CHAUCA, Gloria; WATTS, Douglas

    2013-01-01

    Objetivo: Se estudiaron 141 personas con alto riesgo sexual en la ciudad de Pisco para detectar infección por HTLV-I. Material y Métodos: Se encuestaron y se tomaron muestras de sangre a 141 personas que involucró a trabajadoras sexuales (32), varones homosexuales (54), y varones bisexuales(55). Resultados: Tres de treintidós (10.4%) trabajadoras sexuales fueron positivas; uno de cincuenticuatro (1.9%) de varones homosexuales y ninguno de 55 bisexuales. Hubo una elevada frecuencia de parejas,...

  3. Operações motivadoras condicionadas transitivas em atletas de alto rendimento : da replicação ao conceito

    OpenAIRE

    Figueiredo, Luiz Eduardo de

    2013-01-01

    O presente estudo investigou o efeito das operações motivadoras condicionadas transitivas sobre a primeira resposta de uma cadeia comportamental de dois elos em uma tarefa de computador com participantes atletas de alto rendimento. Na cadeia comportamental, o comportamento de pressionar a tecla vermelha sob um esquema de razão variável 14, produzia a apresentação de 5 segundos do reforçador condicionado maçã, na presença do qual, pressionar a tecla azul resultava em 1 ponto verde trocável pel...

  4. Agroindustria y extractivismo en el Alto Cauca. Impactos sobre los sistemas de subsistencia Afrocampesinos y resistencias (1950-2011)

    OpenAIRE

    Irene Vélez Torres; Daniel Varela; Sandra Rátiva; Andrés Salcedo

    2013-01-01

    La agroindustria y el extractivismo han generado un profundo cambio en las prácticaseconómicas tradicionales del Alto Cauca en Colombia en detrimento de los sistemas socio-económicos de subsistencia de la población local Afro-campesina. El intenso conflictoarmado y la migración forzada han acompañado la instauración de estos modelos de acumulaciónpor despojo. Utilizando una metodología de investigación participativa, este artículoanaliza críticamente la disputa por el acceso y la propiedad so...

  5. Carga viral de seis tipos de Virus del Papiloma Humano de alto riesgo y su asociacion con lesiones cervicales

    OpenAIRE

    Del Río Ospina, Luisa Fernanda

    2015-01-01

    Introducción: La infección por un tipo de Virus del Papiloma Humano de alto riesgo (VPH-AR), es el factor principal en el desarrollo de Cáncer de Cérvix (CC). La carga viral puede modular esta asociación, por lo que resulta importante su cuantificación y el establecimiento de su relación con lesiones precursoras de CC. Metodología: 60 mujeres con lesiones escamosas intraepiteliales (LEI) y 120 mujeres sin LEI, confirmadas por colposcopia, fueron incluidas en el estudio. Se determinó la car...

  6. Análisis económico y ambiental de la agricultura alternativa. Caso: Alto Ricaurte - Boyacá

    OpenAIRE

    González A., Carolina; Gutiérrez B., Patricia

    1992-01-01

    El trabajo: Análisis económico y ambiental de la agricultura alternativa, caso: Alto Ricaurte Boyacá, aborda un tema de trascendencia como es la propuesta de un modelo de agricultura alternativa como base para un desarrollo sustentable, lo cual es, precisamente una de las principales preocupaciones de la comunidad internacional que motivó la convocatoria de la llamada Cumbre de la tierra que por estos días se reúne en Río de Janeiro.

  7. Inteligencia fluida y cristalizada en el autismo de alto funcionamiento y el síndrome de Asperger

    OpenAIRE

    Pérez, P.F.

    2016-01-01

    La inteligencia en los trastornos del espectro autista, especialmente en el autismo de alto funcionamiento y el síndrome de Asperger, ha sido tema de numerosas investigaciones que pretenden establecer la capacidad intelectual que se observa en estos sujetos. Algunos de los resultados más sobresalientes señalan que la inteligencia fluida es uno de los aspectos de desempeño superior en esta población, en comparación con el desempeño en las pruebas que miden inteligencia cristalizada como la esc...

  8. Prescrição de terapias baseadas em evidências para pacientes de alto risco cardiovascular: estudo REACT

    Directory of Open Access Journals (Sweden)

    Otávio Berwanger

    2013-03-01

    Full Text Available FUNDAMENTO: Dados de atendimento ambulatorial ao paciente de alto risco cardiovascular no Brasil são insuficientes. OBJETIVO: Descrever o perfil e documentar a prática clínica do atendimento ambulatorial de pacientes de alto risco cardiovascular no Brasil, no que diz respeito à prescrição de terapias baseadas em evidências. MÉTODOS: Registro prospectivo que documentou a prática clínica ambulatorial de indivíduos de alto risco cardiovascular, que foi definido como a presença de um dos seguintes fatores: doença arterial coronariana, cerebrovascular e vascular periférica; diabetes; ou aqueles com pelo menos três dos seguintes fatores: hipertensão arterial, tabagismo, dislipidemia, maiores 70 anos, histórico familiar de doença arterial coronariana, nefropatia crônica ou doença carotídea assintomática. Foram avaliadas características basais e a taxa de prescrição das intervenções medicamentosas e não medicamentosas. RESULTADOS: Foram incluídos 2.364 pacientes consecutivos, sendo 52,2% do gênero masculino, idade média de 66,0 anos (± 10,1. Dentre os pacientes incluídos, 78,3% utilizavam antiplaquetários, 77,0% estatinas e, dos pacientes com história de infarto do miocárdio, 58,0% receberam betabloqueadores. O uso concomitante destas três classes foi de 34%. Não atingiram as metas preconizadas pelas diretrizes 50,9% dos hipertensos, 67% dos diabéticos e 25,7% dos dislipidêmicos. Os principais preditores de prescrição de terapias com benefício comprovado foram centro com cardiologista e histórico de doença arterial coronariana. CONCLUSÃO: Este registro nacional e representativo identificou hiatos importantes na incorporação de terapias com benefício comprovado, oferecendo um panorama real dos pacientes de alto risco cardiovascular.

  9. Molten salt breeder reactor

    International Nuclear Information System (INIS)

    1977-01-01

    MSBR Study Group formed in October 1974 has studied molten salt breeder reactor and its various aspects. Usage of a molten salt fuel, extremely interesting as reactor chemistry, is a great feature to MSBR; there is no need for separate fuel making, reprocessing, waste storage facilities. The group studied the following, and these results are presented: molten salt technology, molten salt fuel chemistry and reprocessing, reactor characteristics, economy, reactor structural materials, etc. (Mori, K.)

  10. Zero energy reactor 'RB'

    Energy Technology Data Exchange (ETDEWEB)

    Popovic, D; Takac, S; Markovic, H; Raisic, N; Zdravkovic, Z; Radanovic, Lj [Boris Kidric Institute of Nuclear Sciences, Vinca, Beograd (Yugoslavia)

    1959-03-15

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

  11. Reactor utilization, Annex A

    International Nuclear Information System (INIS)

    Martinc, R.; Stanic, A.

    1984-01-01

    Reactor was operated until August 1984 due to prohibition issued by the Ministry since the reactor does not have the emergency cooling system nor special filters in the ventilation system yet. This means that the operation plan was fulfilled by 69%. This annex includes detailed tables containing data about utilization of reactor experimental channels, irradiated samples, as well as interruptions of operation. Detailed data about reactor power during this period are shown as well

  12. 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)

  13. 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)

  14. The fast reactor

    International Nuclear Information System (INIS)

    1980-02-01

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

  15. Mirror fusion reactor design

    International Nuclear Information System (INIS)

    Neef, W.S. Jr.; Carlson, G.A.

    1979-01-01

    Recent conceptual reactor designs based on mirror confinement are described. Four components of mirror reactors for which materials considerations and structural mechanics analysis must play an important role in successful design are discussed. The reactor components are: (a) first-wall and thermal conversion blanket, (b) superconducting magnets and their force restraining structure, (c) neutral beam injectors, and (d) plasma direct energy converters

  16. 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.)

  17. Rotating reactors : a review

    NARCIS (Netherlands)

    Visscher, F.; Schaaf, van der J.; Nijhuis, T.A.; Schouten, J.C.

    2013-01-01

    This review-perspective paper describes the current state-of-the-art in the field of rotating reactors. The paper has a focus on rotating reactor technology with applications at lab scale, pilot scale and industrial scale. Rotating reactors are classified and discussed according to their geometry:

  18. 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.)

  19. 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.)

  20. 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)

  1. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Sherwood, D.G.; Wilson, J.F.; Salton, R.B.; Fensterer, H.F.

    1981-01-01

    A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus includes drivemechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displayer rods through the reactor vessel

  2. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Sherwood, D.G.; Wilson, J.F.; Salton, R.B.; Fensterer, H.F.

    1982-01-01

    A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus includes drive mechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displacer rods through the reactor vessel. (author)

  3. Otium, materialidade e paisagem nas villae do Alto Alentejo português em época romana = Otium, Materiality and Landscape in the Roman Villae of Alto Alentejo (Portugal

    Directory of Open Access Journals (Sweden)

    André Carneiro

    2015-03-01

    Full Text Available A arquitectura das villae foi cuidadosamente pensada para permitir o máximo desfrute de uma vivência de gosto urbano e cosmopolita. A atenção dada à inserção da construção na paisagem, as soluções para harmonizar o espaço exterior criando atmosferas favoráveis, a contemplação para o exterior e a criação de espaços e ambientes construídos que permitissem potenciar o otium e o convivium são discutidos neste trabalho, com exemplos de sítios no Alto Alentejo.Roman villae were carefully designed to fulfil the urban and cosmopolitan way of living. Considering some archaeological sites in Alto Alentejo (Portugal, one intends to discuss the adjustment of the built structure to the landscape, the creation of chosen atmospheres by modelling the outer space, the countryside contemplation and the creation of spaces and indoor environments that would promote otium and convivium.

  4. Liquefaction Hazard Maps for Three Earthquake Scenarios for the Communities of San Jose, Campbell, Cupertino, Los Altos, Los Gatos, Milpitas, Mountain View, Palo Alto, Santa Clara, Saratoga, and Sunnyvale, Northern Santa Clara County, California

    Science.gov (United States)

    Holzer, Thomas L.; Noce, Thomas E.; Bennett, Michael J.

    2008-01-01

    Maps showing the probability of surface manifestations of liquefaction in the northern Santa Clara Valley were prepared with liquefaction probability curves. The area includes the communities of San Jose, Campbell, Cupertino, Los Altos, Los Gatos Milpitas, Mountain View, Palo Alto, Santa Clara, Saratoga, and Sunnyvale. The probability curves were based on complementary cumulative frequency distributions of the liquefaction potential index (LPI) for surficial geologic units in the study area. LPI values were computed with extensive cone penetration test soundings. Maps were developed for three earthquake scenarios, an M7.8 on the San Andreas Fault comparable to the 1906 event, an M6.7 on the Hayward Fault comparable to the 1868 event, and an M6.9 on the Calaveras Fault. Ground motions were estimated with the Boore and Atkinson (2008) attenuation relation. Liquefaction is predicted for all three events in young Holocene levee deposits along the major creeks. Liquefaction probabilities are highest for the M7.8 earthquake, ranging from 0.33 to 0.37 if a 1.5-m deep water table is assumed, and 0.10 to 0.14 if a 5-m deep water table is assumed. Liquefaction probabilities of the other surficial geologic units are less than 0.05. Probabilities for the scenario earthquakes are generally consistent with observations during historical earthquakes.

  5. Empresas electrónicas de alto potencial de crecimiento: Posicionamiento financiero ante retos de futuro

    Directory of Open Access Journals (Sweden)

    Nuria Arimany-Serrat

    2016-02-01

    Full Text Available Objetivo: La investigación posiciona les empresas electrónicas españolas a nivel financiero en el período 2011-2013 en el marco del espacio europeo; ya que el futuro mundo empresarial pasa por el progreso tecnológico y el impacto de las empresas electrónicas es decisivo y por tanto conocer su posición a nivel español y su situación económica financiera en los últimos años nos ayuda a delimitar como podrán afrontar los retos de futuro. Diseño/metodología/enfoque: Los datos que hemos utilizado para esta investigación, recogen los datos económicos financieros de una muestra de empresas electrónicas españolas consideradas de alto crecimiento ya que tienen un crecimiento del ROA mínimo del 3% y un crecimiento de los ingresos de explotación en el período analizado mínimo del 6%. Sobre estas compañías se lleva a cabo un análisis económico financiero y un estudio estadístico descriptivo con modelos de regresión para determinar resultados y conclusiones al respecto. Resultados: El estudio nos permite determinar la salud económica financiera de las empresas electrónicas que concentran un 97% de las ventas en España y determina variables financieras, de género y de innovación que inciden en los resultados de este sector empresarial, para determinar su sintonía en perspectiva europea. Limitaciones: Sería conveniente ampliar la muestra a otras empresas tecnológicas, a parte de la electrónicas, y ampliar el período temporal utilizado hasta el ejercicio 2014, aunque los datos no están disponibles en la base de datos SABI utilizada. Implicaciones prácticas: El trabajo permite valorar la proyección a nivel económico financiero de las empresas electrónicas en estos últimos años en España en relación con la situación europea, para poder valorar si podrán afrontar los retos de futuro inminentes. Implicaciones sociales: Los resultados permiten valorar los cambios a nivel económico financiero de estas empresas para

  6. Estudio geoeléctrico en el valle alto del Rio Patía

    Directory of Open Access Journals (Sweden)

    Pérez Cerón Rosalbina

    1995-10-01

    Full Text Available

    The resistivity survey carried out at the upper valley of the Patía River, provided good information to define the sedimentary sequence of the area. A general sequence from top to base is described as follows: recent deposits with resistivity values between 20 and 400 Ohrn-m, fine to medium grain, sandstones with resistivity values between 20 and 70 Ohrn-m, fine grain sandstones and silstones with resistivity values between 8 and 20 Ohrn-rn, and clayli basement, with resistivity less than 20 Ohm-m. There are two kinds of aquifers; free, related to sands and gravels from alluvial fans and terraces (resistivity values between 70 and 400 Ohrn-m and thickness between 25 and 75, semi-confined related to tertiary sandstones (resistivities values between 20 and 30 Ohm-m, thickness between 35 and 150 m. The water quality of the upper aquifers is good enough with small amounts of salt content. Saline water is found at the lower aquifer.

    The resistivity method was useful to locate geological discontinuities; some of them found with surface expression associated with lineaments and faults. Some of these geological features have been mapped in previous geological works on the area. In general the interpretation based on the resistivity results shows a block tectonics environment affecting cretaceous and tertiary rocks and probably the quaternary deposit.

    La prospección eléctrica en el valle alto del Rio Patía, permitió definir una secuencia típica constituida de techo a base por

  7. The academic training of the professional Agricultural engineer in Public University of El Alto (UPEA

    Directory of Open Access Journals (Sweden)

    Mayta-Mamani Adelio

    2015-11-01

    Full Text Available La agronomía ha significado para el ser humano desde sus orígenes una de las actividades más importantes y vitales, porque tienen relación con el sustento alimenticio en las sociedades. En la actualidad el agrónomo está frente a un importante reto, quizás el más importante desde la revolución industrial. Este reto se relaciona con los alimentos transgénicos, para lograr nuevas variedades de los cultivos y con nuevas propiedades. La carrera de Ingeniería Agronómica de la Universidad Pública de El Alto, cubre el espectro de formación universitaria vinculada a las características productivas y sociales de la economía del país. Por otra parte, el desarrollo de Ingeniería Agronómica tiene vínculos con el Instituto de Investigación y Extensión Agrícola de la Carrera y las instituciones públicas y privadas. Objeto de la profesión. La carrera de Ingeniería Agronómica, pretende contribuir a mejorar el nivel de producción y productividad de alimentos, generando ciencia y tecnología, y transfiriendo oportunamente a las unidades productivas para su implementación. Uno de los principios de la carrera de Ingeniería Agronómica es la recuperación y valoración de los conocimientos locales y ancestrales, la investigación participativa, armonizar esta situación, con el conocimiento convencional. Misión. Formar profesionales con alta capacidad técnica y científica, consciente del poder de conocimiento y comprometidos con el desarrollo rural sostenible, con libertad de pensamiento, dignidad, solidaridad, reciprocidad, respeto a la naturaleza y al prójimo, para responder con convicción frente a los grandes desafíos y oportunidades del mundo globalizado. Visión. Constituirse en una unidad académica de excelencia, referente a nivel nacional e internacional, que forma jóvenes profesionales del país, para desempañar trabajos; en producción agrícola, pecuaria y silvicultura, en diferentes pisos ecológicos para satisfacer

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

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

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

  9. Reactor as furnace and reactor as lamp

    International Nuclear Information System (INIS)

    Goldanskii, V.I.

    1992-01-01

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

  10. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

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

  11. 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

  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. Avances en la regulación y control del estado térmico del horno alto

    Directory of Open Access Journals (Sweden)

    Babich, A.

    1997-04-01

    Full Text Available An automated system of direction (SAD for the control of the thermal state of the hearth of the blast furnace is used, taking into account the interrelation existing between the pig iron temperature and its silicon content. By the magnitude of the thermal exergy of the process, which determines the heat work capacity the variations in the heating of the hearth can be valued and carried out the necessary control and regulation actions, such as the variations in the pulverized coal injection and in the sinter/coke relation in the melting bed of the blast furnace.

    Se utiliza un sistema automatizado de dirección (SAD para el control del estado térmico del crisol del horno alto, teniendo en cuenta la relación que existe entre la temperatura del arrabio y su contenido de silicio. Por la magnitud de la exergía térmica del proceso, que determina la capacidad de trabajo del calor, se pueden valorar las variaciones de calentamiento del crisol y realizar las acciones necesarias de control y regulación, como son las variaciones en la inyección de carbón pulverizado y en la relación sinterizado/coque en el lecho de fusión del horno alto.

  14. Análisis de la matutinidad-vespertinidad en jóvenes atletas de alto rendimiento

    Directory of Open Access Journals (Sweden)

    Alejo Sebastián García-Naveira Vaamonde

    2015-01-01

    Full Text Available El objetivo de este trabajo fue estudiar la relación entre la matutinidad-vespertinidad, la edad, el sexo, la ansiedad rasgo y la modalidad deportiva en depor- tistas adolescentes. La muestra estaba formada por 102 jóvenes atletas españoles de alto rendimiento (54 mujeres y 48 hombres con una edad entre los 14 y 17 años. Se midió la matutinidad-vespertinidad mediante la Escala Compuesta de Matutinidad-Vespertinidad (CS y la ansiedad rasgo mediante el Inventario de Ansie- dad Estado-Rasgo (STAI. Los resultados indican que no existe relación entre el cronotipo, la edad, el sexo y la ansiedad de los deportistas, mientras que estos son más matutinos que la población general de adolescentes y los velocistas/vallistas son más vespertinos que el resto de modalidades. Se concluye que la práctica deportiva de alto rendimiento puede que sea un Zeitzbergs ex- terno que modifica aspectos psicológicos, fisiológicos y bioquímicos de los jóvenes.

  15. Estudio farmacoepidemiológico de uso de antiinflamatorios no esteroideos en pacientes de alto riesgo cardiovascular

    Directory of Open Access Journals (Sweden)

    Jorge Enrique Machado-Alba

    Full Text Available Con el objetivo de determinar la frecuencia de uso prolongado de antiinflamatorios no esteroideos (AINES en pacientes colombianos de alto riesgo cardiovascular (ARC se desarrolló un estudio retrospectivo en el cual se identificaron pacientes de ARC que usaron AINES por más de cinco meses continuos entre enero de 2011 y marzo de 2013. Se identificó a los pacientes que recibían crónicamente nitratos, digitálicos, y clopidogrel y ácido acetil salicílico (ASA, quienes fueron identificados como de ARC. Se realizó un análisis de frecuencias de uso según la comedicación recibida. Se encontró uso concomitante de AINES en el 0,35% de los consumidores de nitratos (tiempo promedio: 9,5 ± 4,4 meses, en el 0,36% de los consumidores de clopidogrel y ASA (tiempo promedio: 9,3 ± 3,4 meses, y en el 0,4% de los consumidores de digitálicos (10,2 ± 4,6 meses. Se concluye que existe una baja proporción de uso de AINES de manera crónica en pacientes de alto riesgo cardiovascular.

  16. Caracterización de carbones para la inyección por toberas en el horno alto

    Directory of Open Access Journals (Sweden)

    Babich, A.

    1998-05-01

    Full Text Available The efficiency of blast furnace operation with pulverized coal injection (PCI by tuyeres is determined by the composition and properties of the used coals and by the quality of the ferrous burden and coke. A study in thermobalance of coals to be injected by tuyeres is carried out, and the softening and melting temperatures of coals ash are determined. The coal performance and its influence in the blast furnace operation is estimated.

    La eficacia de la operación del horno alto con inyección de carbón pulverizado (ICP por toberas, está determinada por la composición y propiedades de los carbones utilizados y por la calidad de la carga férrea y del coque. Se realiza el estudio en termobalanza de carbones destinados a la inyección por toberas y se determinan las temperaturas de reblandecimiento y fusión de la ceniza de estos carbones. Se estima el comportamiento de los carbones y su influencia en la operación del horno alto.

  17. Floristic Diversity of Two Zones of Humid Tropical Forest at Alto Baudó, Chocó, Colombia

    Directory of Open Access Journals (Sweden)

    Luis Javier Mosquera Ramos

    2007-08-01

    Full Text Available Between June and August of 2005 the floristic composition ≥1 cm of DAP was determined in an area of ? 0.2 ha of humid tropical forest at the localities of Pie de >Pató (05º 30' 56" N and 76º 58' 26" W and Nauca (5º 41' 6" N and 77º 00' 36" W, Alto Baudó, Chocó Colombia . En each locality an area of 0.1 ha was sampled which was divided into smaller areas of 2 x 50 cm each. A total of 1618 inidivduals were recorded represented by 257 species, 156 genres and 56 botanical families from which 842 individuals, 161 species, 108 genres and 46 families where found at Pie de Pató, and 776 individuals, 161 species, 98 genres and 45 families at Nauca. At Pie de Pató the families best represented in terms of genres were Rubiaceae (12 genres and 27 species, Arecaceae (eight genres and eight species and Bombacaceae (seven genres and ten species. At Nauca they were Rubiaceae (eleven genres and 25 species, Moraceae (eight genera and 13 species and Arecaceae (eigth genres and eight species. The richness index was of 23,75 and 24,05 for Pie de Pató and Nauca respectively. Diversity change was stimated as 4,43 for both localities. These results indicate high diversity of these forests at Alto Baudó.

  18. Sílica gel obtida de escória de alto forno: Marabá, Pará

    Directory of Open Access Journals (Sweden)

    M. M. Rebelo

    2015-09-01

    Full Text Available ResumoSílica gel com propriedades similares à sílica comercial foi obtida a partir de escória de alto forno (EAF, utilizando digestão com ácido clorídrico. A EAF-sílica obtida foi caracterizada por diferentes técnicas, mostrando-se amorfa, com pureza 99,7% e área específica 282 m2/g. Apresentou caráter hidrofílico alto (12,27%, com água de constituição de ~ 6,18%, o que foi confirmado pela perda de massa durante a análise termogravimétrica. As partículas de EAF-sílica apresentaram tamanhos micrométricos (< 1 µm em forma de agregados, distribuição granulométrica unimodal e D50 7,0 µm.

  19. O suicídio Tikúna no Alto Solimões: uma expressão de conflitos

    Directory of Open Access Journals (Sweden)

    Regina M. de Carvalho Erthal

    Full Text Available O objetivo deste trabalho é buscar um entendimento a respeito da ocorrência de suicídios entre os índios Tikúna do Alto Solimões (Amazonas, um objeto de difícil aproximação e que aponta para a necessidade de abordagem interdisciplinar. A etnografia realizada preocupou-se em captar a vinculação entre os eventos de suicídio da última década com a exacerbação dos confrontos entre diferentes grupos faccionais que atualizam, em outro contexto histórico, os mecanismos de resolução de conflitos próprios das antigas malocas. Na base desses confrontos está o abandono a que tal população tem sido submetida pelos órgãos responsáveis pela definição e implementação das políticas públicas para as populações indígenas, com especial destaque para a falência do modelo de assistência proposto para a área do Alto Solimões.

  20. 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

  1. The fast breeder reactor

    International Nuclear Information System (INIS)

    Davis, D.A.; Baker, M.A.W.; Hall, R.S.

    1990-01-01

    Following submission of written evidence, the Energy Committee members asked questions of three witnesses from the Central Electricity Generating Board and Nuclear Electric (which will be the government owned company running nuclear power stations after privatisation). Both questions and answers are reported verbatim. The points raised include where the responsibility for the future fast reactor programme should lie, with government only or with private enterprise or both and the viability of fast breeder reactors in the future. The case for the fast reactor was stated as essentially strategic not economic. This raised the issue of nuclear cost which has both a construction and a decommissioning element. There was considerable discussion as to the cost of building a European Fast reactor and the cost of the electricity it would generate compared with PWR type reactors. The likely demand for fast reactors will not arrive for 20-30 years and the need to build a fast reactor now is questioned. (UK)

  2. 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.)

  3. 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.)

  4. 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.)

  5. The Maple reactor project

    International Nuclear Information System (INIS)

    Malkoske, G.R.; Labrie, J.-P.

    2003-01-01

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

  6. Fission reactors and materials

    International Nuclear Information System (INIS)

    Frost, B.R.T.

    1981-12-01

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

  7. Angioplastia del tronco de la arteria coronaria izquierda no protegido en pacientes con alto riesgo quirúrgico

    Directory of Open Access Journals (Sweden)

    Victor Mauro

    2008-01-01

    Full Text Available IntroducciónEl tratamiento de elección de la enfermedad del tronco de la coronaria izquierda (TCI es la cirugía de revascularización miocárdica (CRM. Un número creciente de pacientes presenta comorbilidades y/o inestabilidad clínica que condicionan un alto riesgo quirúrgico.ObjetivosEvaluar los resultados de la angioplastia (ATC del TCI no protegido en pacientes con alto riesgo para CRM (EUROSCORE = 6.Material y métodosDe 59 pacientes con ATC de TCI no protegido se excluyeron 8 con infarto agudo de miocardio (IAM en shock cardiogénico y 12 sin características de alto riesgo; de los restantes pacientes de alto riesgo fueron objeto de este estudio los 32 tratados con stents convencionales.Se comparó la mortalidad hospitalaria predicha por EUROSCORE logístico con la observada, así como la incidencia de complicaciones mayores y su evolución alejada.ResultadosLa mediana de edad fue de 76,5 años, el 41% tenía 80 años o más, el 22% eran mujeres, el 28% diabéticos, el 56% tenía disfunción ventricular moderada a grave, el 31% insuficiencia renal crónica, el 50% vasculopatía periférica, el 53% angina refractaria, el 22% IAM reciente, el 28% procedimientos de emergencia y la mediana de EUROSCORE fue de 10,5 puntos.El 41% de los pacientes presentaban compromiso del TCI distal. El éxito angiográfico fue del 94%. Se utilizaron inhibidores IIb/IIIa en el 47%, cutting balloon en el 28%, Rotablator® en el 3% y balón de contrapulsación en el 31%. En todos se implantó un stent y en el 50% se trataron otras obstrucciones.La mortalidad hospitalaria fue del 3,1% (intervalo de confianza del 95% 0,2%-14,5%, p = 0,003, en tanto que la predicha era del 23,8%. Ningún paciente presentó déficit neurológico, IAM transmural ni requirió diálisis. Un paciente debió ser sometido a CRM electiva por fracaso del procedimiento.La mediana de seguimiento fue de 15,5 meses, período en el que se registraron 6 muertes (2 cardiovasculares y 4

  8. Caracterização morfológica do poliestireno de alto impacto (HIPS Morphological characterization of high impact psolystyrene (HIPS

    Directory of Open Access Journals (Sweden)

    Juliana Rovere

    2008-03-01

    Full Text Available Poliestireno de alto impacto (HIPS é uma blenda polimérica clássica de reator produzida por polimerização in-situ de estireno em solução com borracha butadiênica. Na literatura, está bem estabelecida a importância do tamanho de partícula e da densidade da ligação cruzada da borracha na capacidade de cavitação e no controle dos mecanismos de tenacificação na matriz estirênica. No presente trabalho as técnicas de microscopia eletrônica de transmissão (MET e espalhamento de luz laser de baixo ângulo (LALLS foram empregadas para observar a distribuição do tamanho de partícula, e a análise digital de imagem foi aplicada para quantificar os parâmetros morfológicos nas micrografias. Medidas do tamanho de partícula e da fração aparente volumétrica de partícula foram feitas para diferentes espessuras na MET e comparadas com o parâmetro estatístico D[4,3] obtido na LALLS.High impact polystyrene (HIPS is a classical reactor polymer blend produced by in-situ polymerization of styrene in solution with polybutadiene rubber. It is well established in the literature the importance of particle size and rubber crosslink density on the particle cavitation capability and on the controlling of toughening mechanisms in the styrene matrix. In the present work transmission electron microscopy (TEM and low-angle laser light scattering (LALLS were employed for investigating particle size distribution, with digital imaging being applied in the quantitative analysis of the micrographs. Measurements of apparent volume fraction and average particle size were carried out for different slice thicknesses in TEM and compared with the statistical parameter D[4,3] obtained by LALLS.

  9. Reactor Vessel Surveillance Program for Advanced Reactor

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-10-15

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

  10. Ecoturismo en Ecuador: El caso del Oglán alto

    Directory of Open Access Journals (Sweden)

    Pedro Hernández Pardo

    2011-12-01

    Full Text Available Ecuador es un país con unos grandes recursos naturales que han sido explotados a lo largo de su historia, posee una gran biodiversidad, Amazonia, Sierra y Costa, y una gran  riqueza  cultural.  Una  forma  de  aprovechar  esos recursos  de  una  forma  sostenible  y  permitiendo  el desarrollo  económico  es  el  eco  turismo,  en  todas  sus tipologías. Para que el turismo sea sostenible hay que entender las necesidades, los activos potenciales y los valores culturales del área donde se va desarrollar. La creación de empleo estable y de calidad, debe ser parte de esa sostenibilidad, porque es fundamental para que la población  pueda  percibir  los  beneficios  del  turismo. Para conseguirlo   es   necesario   la   existencia   de emprendedores   capaces   de   formar   microempresas, pequeñas  y medianas  empresas,  que  sean  rentables  y generadoras de empleo. La cultura indígena amazónica es básicamente  comunitaria  y  agrícola  por  lo  que  es difícil la creación de actividades empresariales por esas comunidades.   Pero   desde   hace   ya   años,   estas comunidades indígenas,  están perdiendo su cultura, su lengua,  y  su  propia  vida  natural,  adquiriendo  valores occidentales que nada tienen que ver con los suyos. El eco turismo es una buena forma de recuperar sus valores, su cultura y sus tradiciones, y a la vez, una forma de asegurar su progreso economico respetando su hábitat natural   y   sus   recursos   de   una   forma   sostenible, permitiendo   que   actividades   destructivas   como   la madera y el petróleo, sean abandonadas. Un ejemplo lo tenemos en el Oglán Alto, donde la comunidad quechua “Pablo  López”  ha  decidido  proteger  su  patrimonio ancestral   mediante   la   creación   de   una   Estación Científica,  gracias  a  un  acuerdo  con  la  Universidad Central

  11. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Carlos Ruben Calabrese

    1999-01-01

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

  12. Siting of research reactors

    International Nuclear Information System (INIS)

    1987-01-01

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

  13. Reactor core for FBR type reactor

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  14. 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)

  15. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

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

  16. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    Kouts, H.

    1986-01-01

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

  17. Avaliação da conduta conservadora na lesão intraepitelial cervical de alto grau

    Directory of Open Access Journals (Sweden)

    Nelson Shozo Uchimura

    2012-06-01

    Full Text Available OBJETIVO: Analisar a associação entre a conduta conservadora em lesão intraepitelial cervical de alto grau com o índice de recidiva da neoplasia e faixa etária. MÉTODOS: Estudo transversal e retrospectivo realizado com 509 mulheres (15-76 anos atendidas no período de 1996 a 2006, com colpocitologia oncótica alterada, em um serviço público de referência em Maringá, PR. Os dados foram coletados dos prontuários médicos e estudadas as variáveis diagnóstico definitivo, tipos de tratamento, ocorrência da lesão e recidivas, analisados por meio de testes de associação de qui-quadrado de Pearson e teste exato de Fisher. RESULTADOS: A lesão intraepitelial cervical de alto grau ocorreu em 168 casos; destes, 31 mulheres foram submetidas à amputação cônica, 104 a cirurgias de alta frequência, nove histerectomizadas e 24 receberam conduta conservadora. Dentre as mulheres com lesão de alto grau e tratadas de forma conservadora, oito (33,3% recidivaram, enquanto dentre as submetidas à conduta não conservadora dez (6,9% recidivaram, sendo essa diferença estatisticamente significante (p = 0,0009, RP = 4,8 (IC95% 2,11;10,93. Para aquelas que fizeram o seguimento clínico-citológico, três (30,0% e, dentre as cauterizadas, cinco (35,7% recidivaram no prazo de três anos, sem diferença significante (p = 0,5611. A recidiva abaixo e acima de 30 anos ocorreu, respectivamente, em sete (13,8% e 11 (12,2% mulheres (p = 0,9955. CONCLUSÕES: A idade da mulher não influencia o prognóstico de recidiva. O tratamento conservador deve ser indicado como conduta de exceção, dada a alta taxa de recidiva, e o seguimento deve ser rigoroso, com acompanhamento citológico e colposcópico de até três anos, período em que ocorre a maioria das recidivas.

  18. CRECIMIENTO DEL MAÍZ EN VERTISOLES CON ALTO ALUMINIO EN LA BAIXADA MARANHENSE PRE-AMAZONIA, BRASIL

    Directory of Open Access Journals (Sweden)

    Alessandro Costa da Silva

    2014-01-01

    Full Text Available Crecimiento del maíz en vertisoles con alto aluminio en la Baixada Maranhense pre-Amazonia, Brasil. El objetivo de este trabajo fue evaluar el crecimiento del maíz en suelos con alto contenido de aluminio. Se midió el efecto del Al3+ en raíces y la cantidad de materia seca (raíz, hoja y tallo de maíz. Se efectuó la caracterización físico-química de cuatro muestras de suelo con alto aluminio colectadas del horizonte Ap, en tres municipios de la región conocida como Baixada Maranhense (Pre-Amazonia, Brasil: Santa Rita (SR, Arari (AR y Vitoria do Mearim (VM y un testigo colectado en el municipio de São Luís, Área del Núcleo de Tecnología Rural (T. El estudio, ejecutado en 2009, se llevó a cabo en invernadero y se utilizó 2 dm3 de suelo por maceta. Asimismo las muestras fueron divididas en muestras con y sin fertilización. La variación en la longitud de la raíz y de materia seca de las hojas difirió significativamente entre tratados con y sin fertilizante, excepto en la muestra de la localidad T. La producción de materia seca de raíz, tallo y hoja fue mayor en todos los suelos cuando se fertilizó. El suelo testigo también superó a todos los demás en cuanto a producción de materia seca en la raíz, posiblemente como resultado de una menor cantidad de Al3+ (1,2 cmolc/dm3 en comparación con los suelos SR, AR y VM (6,8; 8,0 y 7,0 cmolc/dm3 respectivamente. Se concluye la fertilización reduce el efecto detrimental del aluminio en la producción de maíz en la Baixada Maranhense.

  19. ¿El buen entrenador nace o lo hace el deportista? El camino hacia el alto nivel en triatlón

    Directory of Open Access Journals (Sweden)

    Germ\\u00E1n Ruiz Tendero

    2014-01-01

    Full Text Available La figura del entrenador adquiere un peso importante en el sistema deportivo y por tanto en el éxito de sus deportistas. Las claves de su éxito han sido estudiadas desde diferentes perspectivas. El estudio en retrospectiva del recorrido por el cual se llega al alto nivel es una de ellas. El propósito de este estudio fue determinar el camino de los entrenadores de triatlón previo a su llegada al alto nivel, así como las circunstancias en las que se produjo el paso hacia el alto rendimiento. Para ello se entrevistó a una muestra de 14 entrenadores españoles de alto nivel en triatlón. Los resultados muestran un recorrido prevalente en el que el entrenador fue anteriormente deportista y entrenador en alguna/s de las disciplinas fundamentales (DF de las que se compone el triatlón (natación, ciclismo, atletismo, llegando al alto nivel de triatlón con una edad aproximada de 30 años. Los años de experiencia previa varían en función del pasado del entrenador, no llegándose a alcanzar los 10 años de media en ningún caso, hasta el inicio en la etapa de alto nivel. Sería recomendable, por tanto, contextualizar los años de experiencia previos, para optimizar la selección de muestras de entrenadores expertos.

  20. 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

  1. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

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

  2. 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...

  3. Upgradation of Apsara reactor

    International Nuclear Information System (INIS)

    Mammen, S.; Mukherjee, P.; Bhatnagar, A.; Sasidharan, K.; Raina, V.K.

    2009-01-01

    Apsara is a 1 MW swimming pool type research reactor using high enriched uranium as fuel with light water as coolant and moderator. The reactor is in operation for more than five decades and has been extensively used for basic research, radioisotope production, neutron radiography, detector testing, shielding experiments etc. In view of its long service period, it is planned to carry out refurbishment of the reactor to extend its useful life. During refurbishment, it is also planned to upgrade the reactor to a 2 MW reactor to improve its utilization and to upgrade the structure, system and components in line with the current safety standards. This paper gives a brief account of the design features and safety aspects of the upgraded Apsara reactor. (author)

  4. Organización socioeconómica y territorial en la región del Alto Lerma, Estado de México

    Directory of Open Access Journals (Sweden)

    Estela Orozco Hernández

    2012-02-01

    Full Text Available Este trabajo muestra que la región del Alto Lerma es un espacio de organización compleja, donde se entrelazan procesos sociales y territoriales diversos, representados por la existencia de estructuras agrarias, urbanas e industriales. Cada una de estas estructuras tiene necesidades e intereses que definen las formas de apropiación, control y producción del espacio regional y, por lo tanto, constituyen factores determinantes de la configuración socioterritorial del Alto Lerma. Se analiza la información estadística oficial, así como los trabajos disponibles, desde una perspectiva hipotético-deductiva.

  5. IRMANDADE DO ROSÁRIO DOS PRETOS DE SANTA EFIGÊNIA DO ALTO DA CRUZ: PROPOSTA DE GESTÃO DE UM ARQUIVO EM OURO PRETO (MG).

    OpenAIRE

    Silva, Laurimar Gomes da

    2009-01-01

    A proposta deste projeto visa atender a uma demanda da Irmandade do Rosário dos Pretos de Santa Efigênia do Alto da Cruz na cidade de Ouro Preto (MG), a fim de consolidar parcerias no sentido de preservar e gerir o arquivo. Fundada em 1719, compondo uma das vinte irmandades encontradas na cidade, a Irmandade do Rosário dos Pretos de Santa Efigênia do Alto da Cruz se particulariza por ser a responsável pela administração da igreja barroca de Santa Efigênia, que no imaginário ...

  6. Tolerancia a la violencia de pareja en tres historias de vida de mujeres de estrato económico alto de Lima

    OpenAIRE

    Mujica, Jaris; Bedoya, Silvana

    2017-01-01

    Objetivo: esta investigación analiza la presencia de violencia física y psicológica ejercidas por la pareja (varón) a una víctima (mujer) en el estrato económico alto de Lima. Método: se recolectaron los datos a través de la técnica “historia de vida” en un registro profundo de los discursos de tres mujeres adultas del estrato económico alto. Resultados: los resultados ratifican resultados de la literatura precedente (concentrada en sectores de medios y bajos recursos económicos) en las forma...

  7. Prática pedagógica aos educandos com deficiência intelectual numa escola de ensino fundamental com alto IDEB

    OpenAIRE

    Wilma Carin Silva Porta

    2015-01-01

    No atual contexto da inclusão escolar, em que os educandos com deficiência intelectual constituem a maioria dentre os demais deficientes, indagações sobre a atuação dos professores da sala comum das escolas com alto Índice de Desenvolvimento da Educação Básica (Ideb) com esta população, tornam-se sobremaneira importantes. O presente estudo teve como objeto de análise a prática pedagógica na perspectiva inclusiva, de professores do ciclo I do ensino fundamental, numa escola com alto índice do ...

  8. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1980-09-01

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

  9. 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

  10. 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)

  11. 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)

  12. 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)

  13. Fast reactors worldwide

    International Nuclear Information System (INIS)

    Hall, R.S.; Vignon, D.

    1985-01-01

    The paper concerns the evolution of fast reactors over the past 30 years, and their present status. Fast reactor development in different countries is described, and the present position, with emphasis on cost reduction and collaboration, is examined. The French development of the fast breeder type reactor is reviewed, and includes: the acquisition of technical skills, the search for competitive costs and the spx2 project, and more advanced designs. Future prospects are also discussed. (U.K.)

  14. 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)

  15. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

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

  16. 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.)

  17. 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.

  18. The Dragon reactor experiment

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The concept on which the Dragon Reactor Experiment was based was evolved at the Atomic Energy Research Establishment at Harwell in 1956, and in February of that year a High Temperature Gas- cooled Reactor Project Group was set up to study the feasibility of a helium-cooled reactor with a graphite or beryllium moderator, and with the emphasis on the thorium fuel cycle [af

  19. 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

  20. 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)

  1. Integral fast reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1989-01-01

    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

  2. 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

  3. 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

  4. 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

  5. HOMOGENEOUS NUCLEAR POWER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1959-09-01

    A homogeneous nuclear power reactor utilizing forced circulation of the liquid fuel is described. The reactor does not require fuel handling outside of the reactor vessel during any normal operation including complete shutdown to room temperature, the reactor being selfregulating under extreme operating conditions and controlled by the thermal expansion of the liquid fuel. The liquid fuel utilized is a uranium, phosphoric acid, and water solution which requires no gus exhaust system or independent gas recombining system, thereby eliminating the handling of radioiytic gas.

  6. Australian research reactor studies

    International Nuclear Information System (INIS)

    McCulloch, D.B.

    1978-01-01

    The Australian AEC has two research reactors at the Lucas Heights Research Establishment, a 10 HW DIDO class materials testing reactor, HIFAR, and a smaller 100kW reactor MOATA, which was recently upgraded from 10kW power level. Because of the HIFAR being some 20 years old, major renewal and repair programmes are necessary to keep it operational. To enable meeting projected increases in demand for radioisotopes, plans for a new reactor to replace the HIFAR have been made and the design criteria are described in the paper. (author)

  7. 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

  8. Reactor feedwater system

    International Nuclear Information System (INIS)

    Hikabe, Katsumi.

    1978-01-01

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

  9. 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.

  10. 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

  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. 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

  13. Advanced CANDU reactors

    International Nuclear Information System (INIS)

    Dunn, J.T.; Finlay, R.B.; Olmstead, R.A.

    1988-12-01

    AECL has undertaken the design and development of a series of advanced CANDU reactors in the 700-1150 MW(e) size range. These advanced reactor designs are the product of ongoing generic research and development programs on CANDU technology and design studies for advanced CANDU reactors. The prime objective is to create a series of advanced CANDU reactors which are cost competitive with coal-fired plants in the market for large electricity generating stations. Specific plant designs in the advanced CANDU series will be ready for project commitment in the early 1990s and will be capable of further development to remain competitive well into the next century

  14. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Doshi, P.K.; George, R.A.; Dollard, W.J.

    1982-01-01

    A mechanical spectral shift arrangement for controlling a nuclear reactor includes a plurality of reactor coolant displacer members which are inserted into a reactor core at the beginning of the core life to reduce the volume of reactor coolant-moderator in the core at start-up. However, as the reactivity of the core declines with fuel depletion, selected displacer members are withdrawn from the core at selected time intervals to increase core moderation at a time when fuel reactivity is declining. (author)

  15. 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.)

  16. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-02-15

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation. [Serbo-Croat] Pored osnovnih karakeristika reaktora RA, organizacije rada i finansijskih pokazatelja, razmatra se stanje opreme reaktora nakon 18 godina rada, pitanja dozvole za rad sa 80% obogacenim gorivom, problem skladistenja isluzenog goriva u bazenu zgrade reaktora i potreba za obnavljanjem komponenti opreme, pre svega elektronske.

  17. 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

  18. 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

  19. FBR type reactors

    International Nuclear Information System (INIS)

    Suzuoki, Akira; Yamakawa, Masanori.

    1985-01-01

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

  20. FBR type reactor

    International Nuclear Information System (INIS)

    Hayase, Tamotsu.

    1991-01-01

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

  1. Farewell to a reactor

    International Nuclear Information System (INIS)

    Skanborg, P.

    1976-01-01

    Denmark's second reactor, DR 2, whose first criticality took place the night of 18/19 December 1958 was shut down for the last time on 31 October 1975. It was a light-water moderrated and cooled reactor of swimming-pool type with a thermal power of 5 MW, using 90% enriched uranium. The operation is described. The reactor and auxiliary equipment are now being put 'in store' - all fuel elements sent for reprocessing, the reactor tank and cooling circuits emptied, and a lead shielding placed over the tank opening. The rest of the equipment will remain in place. (B.P.)

  2. Indian advanced nuclear reactors

    International Nuclear Information System (INIS)

    Saha, D.; Sinha, R.K.

    2005-01-01

    For sustainable development of nuclear energy, a number of important issues like safety, waste management, economics etc. are to be addressed. To do this, a number of advanced reactor designs as well as fuel cycle technologies are being pursued worldwide. The advanced reactors being developed in India are the AHWR and the CHTR. Both the reactors use thorium based fuel and have many passive features. This paper describes the Indian advanced reactors and gives a brief account of the international initiatives for the sustainable development of nuclear energy. (author)

  3. Patrimonio Gastronómico e Turismo Como Estrategia de Desarrollo Local en El Alto Lerma, Toluca - México

    Directory of Open Access Journals (Sweden)

    Alejandro Tonatiuh Romero Contreras

    2012-11-01

    Full Text Available Este artigo tem como objetivos descrever e caracterizar a formação da cozinha tradicional da região de Alto Lerma, a fim de reconhecer o patrimônio culinário existente, iniciando pela parte mais básica da gastronomia desta região, no Valle de Toluca, México. Assim como o potencial para o desenvolvimento local das comunidades detentoras de tal saber. A fim de alcançar tais objetivos, utilizou-se a informação geográfica, arqueológica e etnográfica de projetos publicados, bem como teses profissionais e pesquisas de campo, identificando aquelas características ou sabores que conferem o caráter regional através do tempo.

  4. Projeto Sabura: dez anos a ultrapassar barreiras e a quebrar estigmas no Bairro do Alto da Cova da Moura (BACM)

    OpenAIRE

    Marco Pais Neves dos Santos

    2017-01-01

    O Sabura é um projeto pioneiro no panorama do turismo étnico português que funciona no Bairro do Alto da Cova da Moura (BACM) e que recentemente comemorou uma década de existência (2004/2014). Neste trabalho fazemos a primeira apresentação pública dos resultados deste projeto. Começamos com uma introdução e seguidamente apresentamos um enquadramento histórico-geográfico do BACM, um breve historial da Associação Cultural Moinho da Juventude (ACMJ) e uma descrição da origem e evolução do Sabura...

  5. IMPACTOS DA ATIVIDADE TURÍSTICA À ECONOMIA MUNICIPAL DE ALTO PARAÍSO DE GOIÁS, BRASIL

    Directory of Open Access Journals (Sweden)

    Tathiana Rodrigues Salgado

    2014-01-01

    Full Text Available El turismo en Alto Paraíso de Goiás tiene un papel importante en la economía de la ciudad, ya sea moviendo las tiendas locales o mediante la generación de puestos de trabajo directos y de temporada. Sin embargo, una vertiente poco explorada por los administradores municipales son los ingresos fiscales relacionados con este segmento económico, como se ve en la investigación. El flujo de turistas, contribuye poco a la formación de las finanzas municipales, principalmente debido a la falta de una legislación específica para mejorar el uso de las actividades turísticas.

  6. Avaliação do património vegetal natural do Alto Douro Vinhateiro 2001 -2012

    Directory of Open Access Journals (Sweden)

    Paulo Farinha-Marques

    2014-06-01

    Full Text Available O Alto Douro Vinhateiro é uma paisagem cultural evolutiva viva, património mundial desde 2001. Dez anos após a distinção foi feito um estudo multidisciplinar sobre o seu estado de conservação. No trabalho que aqui se apresenta avalia-se a evolução, entre 2001 e 2012, das classes de uso do solo que codificam o património natural do ADV: Matos e Matas, Pinhais e Galerias Ripícolas. A avaliação foi feita com base em quatro locais de amostragem associados a paisagens de referência. Discute-se a incidência das transformações detetadas e as suas implicações na manutenção do caráter de mosaico da paisagem e na diversidade sensorial e ecológica.

  7. RELATION OF IDENTITY- POLITICAL CULTURE IN THE INDIGENOUS AUTONOMY FORMATION. CASE STUDY IN “LOS ALTOS CHIAPAS” COMMUNITY

    Directory of Open Access Journals (Sweden)

    Víctor Manuel Santos Chávez

    2006-04-01

    Full Text Available SUMMARY The assumption of new studies about the indigenous movement in Mexico involves the need for articulating political and cultural dimensions of some social groups, as well as the reformulation of how that kind of studies should be done: In this study the need for combining the political dimensions (local power structure and cultural dimensions (ethnic identity redefinitions is established in order to examine the implications that such relationship has in the uprising of new indigenous movements and the emergence of de facto indigenous autonomies: To carry out this study, we had to think about the researching questions from a given referent , in this case it was a community from Los Altos the Chiapas. This community gave us the actual elements for the discussion of concrete research, the new indigenous movement in Chiapas and the indigenous autonomy.

  8. REPERCUSIONES TERRITORIALES DE LA POLÍTICA AGRARIA COMUNITARIA SOBRE LAS ESTRUCTURAS AGRARIAS DEL ALTO Y MEDIO VINALOPÓ (ALICANTE

    Directory of Open Access Journals (Sweden)

    Antonio M. Rico Amorós

    1995-01-01

    Full Text Available a política de estructuras agrarias de la Unión Europea, sometida ahora a un hondo proceso de reflexión y reforma, ha propiciado en el Alto y Medio Vinalo- pó una serie de repercusiones estructurales, productivas, y espaciales. Las pri- mas que regulan el arranque definitivo de superficies de viñedo, con más de 7.000 Has arrancadas hasta la actualidad constituyen su más relevante exponen- te, aunque no es el único ni mucho menos. Este trabajo persigue la identificación y evaluación de las líneas de ayuda comunitarias, estatales, y autonómicas, de efectos espaciales más relevantes, sometiendo los mismos a reflexión.

  9. CARACTERIZACIÓN Y EVALUACIÓN DE LA SUSTENTABILIDAD DE FINCAS EN ALTO URUBAMBA, CUSCO, PERÚ*

    OpenAIRE

    Merma, Isaías; Universidad Nacional San Antonio Abad del Cusco (Perú).; Julca, Alberto; Universidad Nacional Agraria La Molina (Perú).

    2012-01-01

    El estudio se llevó a cabo en la provincia de La Convención, Cusco – Perú, en la región geográfica de selva alta conocida como Alto Urubamba. Tiene como objetivo evaluar las características prediales y medir la sustentabilidad de fincas a través de indicadores adaptados al lugar. Se recogió información de campo tanto en términos biofísicos y socio-económicos y se analizó en variables seleccionadas, a partir de una base de datos aplicando programas como SPSS, MINITAB y Análisis Cluster. Los re...

  10. A biocultural perspective on fictive kinship in the Andes: social support and women's immune function in El Alto, Bolivia.

    Science.gov (United States)

    Hicks, Kathryn

    2014-09-01

    This article examines the influence of emotional and instrumental support on women's immune function, a biomarker of stress, in the city of El Alto, Bolivia. It tests the prediction that instrumental support is protective of immune function for women living in this marginal environment. Qualitative and quantitative ethnographic methods were employed to assess perceived emotional and instrumental support and common sources of support; multiple linear regression analysis was used to model the relationship between social support and antibodies to the Epstein-Barr virus. These analyses provided no evidence that instrumental social support is related to women's health, but there is some evidence that emotional support from compadres helps protect immune function. © 2014 by the American Anthropological Association.

  11. Agroindustria y extractivismo en el Alto Cauca. Impactos sobre los sistemas de subsistencia Afrocampesinos y resistencias (1950-2011

    Directory of Open Access Journals (Sweden)

    Irene Vélez Torres

    2013-12-01

    Full Text Available La agroindustria y el extractivismo han generado un profundo cambio en las prácticaseconómicas tradicionales del Alto Cauca en Colombia en detrimento de los sistemas socio-económicos de subsistencia de la población local Afro-campesina. El intenso conflictoarmado y la migración forzada han acompañado la instauración de estos modelos de acumulaciónpor despojo. Utilizando una metodología de investigación participativa, este artículoanaliza críticamente la disputa por el acceso y la propiedad sobre la tierra y los bienesambientales del territorio, rescatando el punto de vista de comunidades Afrodescendientesy organizaciones sociales que han resistido desde la colonia y hasta nuestros días para defendersus pueblos y territorios.

  12. Estudio florístico y aportaciones a la conservación del alto Cabriel (Cuenca)

    OpenAIRE

    Mayoral García-Berlanga, Olga

    2011-01-01

    El alto Cabriel es un área montañosa inmersa en plena Serranía de Cuenca (Sistema Ibérico meridional), con altitudes entre los 910 y los 1.840 m. La zona de estudio com-prende 93.311 hectáreas -repartidas en 20 cuadrículas UTM de 10 km de lado- y 16 muni-cipios. Casi la mitad de la longitud del río Cabriel, afluente izquierdo del Júcar, discurre por la zona de estudio. Dominan las litologías calcáreas, destacando dos afloramientos de areniscas del Bundsandstein. Desde un punto de vista bio...

  13. Género, leña y sostenibilidad: el caso de una comunidad de los Altos de Chiapas

    Directory of Open Access Journals (Sweden)

    Denise Soares

    2006-01-01

    Full Text Available In this paper we analyse the strategies of use and management of firewood by the families in Pozuelos, a community of the municipality of Chamula, located in the Altos de Chiapas. We also explain the factors that promote or hinder the acceptance of alternative technologies that aim to reduce the consumption of firewood among rural families and thus decrease the female workload and increase the conservation of the woods. The analysis is focussed on the times and workloads of bio-fuel supply as well as on the complementarity of functions in the domestic nucleus for the collection of the resource and on the factors that interfere with technology appropriation, in this case wood-saving stoves. This work identifies the role of the women as administrators of the forestal resources for energy purposes and points out the factors that restrict the acceptance of technological changes as sociocultural, economical, climatic and technical.

  14. Inteligencia fluida y cristalizada en el autismo de alto funcionamiento y el síndrome de Asperger

    OpenAIRE

    Pérez Rivero, Paula Fernanda; Martínez Garrido, Lía Margarita

    2015-01-01

    La inteligencia en los trastornos del espectro autista, especialmente en el autismo de alto funcionamiento y el síndrome de Asperger, ha sido tema de numerosas investigaciones que pretenden establecer la capacidad intelectual que se observa en estos sujetos. Algunos de los resultados más sobresalientes señalan que la inteligencia fluida es uno de los aspectos de desempeño superior en esta población, en comparación con el desempeño en las pruebas que miden inteligencia cristalizada como la esc...

  15. Economic Valuation of Cultural Heritage: Application to a museum located in the Alto Douro Wine Region– World Heritage Site

    Directory of Open Access Journals (Sweden)

    Susana Fonseca

    2010-04-01

    Full Text Available Cultural assets are increasingly being considered in the policies of social and economic development of territories due to spillover effects. However, since cultural assets are not transacted in the market, their use value should be calculated using indirect methods of evaluation or non market techniques. In this paper, the travel cost method was chosen to estimate the curve of demand in the Museum of Lamego which constitutes an important cultural item of the Alto Douro Wine Region, classified by UNESCO in 2001, as a world heritage site – a living and evolving cultural landscape. The results of the application of the Poisson model confirm the expected, that is, the probability of visiting the museum is positively influenced by the educational level, female gender and negatively by the travel cost.

  16. PERCEPCIONES DE LOS SISTEMAS DE TRABAJO DE ALTO RENDIMIENTO E INTENCIÓN DE MARCHA. UN ANÁLISIS MULTINIVEL

    Directory of Open Access Journals (Sweden)

    García Chas, Romina

    2012-09-01

    Full Text Available La investigación sobre los sistemas de trabajo de alto rendimiento (STAR se ha centrado principalmente en el efecto sobre el rendimiento organizativo desde una perspectiva directiva. Este estudio diferencia entre la perspectiva de los empleados y los directivos sobre los STAR y examina la relación entre ambas perspectivas y la intención de marcha en una muestra conformada por ingenieros, utilizando la metodología multinivel. Los resultados indican que existen importantes diferencias entre la percepción de los empleados del STAR y la percepción de los directivos y que el STAR intentado afecta solo indirectamente (a través del STAR experimentado a la intención de marcha de los ingenieros.

  17. Tendencias en la síntesis de alcohol polivinílico de alto peso molecular

    Directory of Open Access Journals (Sweden)

    José Ernesto Perilla

    1998-09-01

    Full Text Available En el presente artículo se comentan los resultados de algunas publicaciones realizadas acerca de la producción de alcohol polivinílico, PVOH, de alto peso molecular. Los estudios sobre la producción de un polímero de estas características toman dos vertientes principales. La primera consiste en la polimerización del acetato de vinilo, VAM, a temperaturas bajas, donde las reacciones de transferencia de actividad de cadena a polímero se vean reducidas, y la segunda la producción de PVOH por la hidrólisis de polivinil ésteres, obtenidos por polimerización de monémeros diferentes del VAM.

  18. Determination of uranium in Toxodon Platensis' teeth from Alto Ribeira region in Sao Paulo State for isotope dating

    International Nuclear Information System (INIS)

    Figueiredo, Ana M.G.; Saiki, Mitiko; Sarkis, Jorge E.S.; Kakazu, Mauricio H.; Karmann, Ivo

    2000-01-01

    In the present work, the concentration of uranium in dentine and dental enamel of a pre-molar of Toxodon platensis (kind of herbivorous) from South America Quaternary, present in the region of Alto Ribeira, Sao Paulo, was determined, in order to date this fossil by using the ESR method (Electron Spin Resonance). The analytical techniques Epithermal Neutron Activation Analysis and High Resolution Inductively Coupled Plasma Mass Spectrometry were employed. The results obtained by using the two cited analytical techniques were in good agreement. These results, together with the data of total dose of deposed ionizing radiation and of the rate dose, allowed to find a ESR age of (6,7 +/- 1,3) Ka for the dentine, and of (5,0 +/- 1,6 Ka) for the dental enamel. Considering an average age of 6 Ka, this date corresponds to the Low to Medium Holocene, which is an unprecedented datum for this species in the southeastern region of Brazil. (author)

  19. CARACTERIZAÇÃO MORFOESTRUTURAL DO ALTO CURSO DA BACIA HIDROGRÁFICA DO RIO JAGUARIBE, CEARÁ-BRASIL

    OpenAIRE

    Mickaelle Braga da Silva; Rubson Pinheiro Maia

    2017-01-01

    O presente trabalho propõe uma análise morfoestrutural do alto curso da bacia hidrográfica do rio Jaguaribe, Ceará-Brasil, através da relação litologia/drenagem/relevo. A análise baseou-se em levantamentos bibliográficos e cartográficos; na aplicação de técnicas de geoprocessamento e tabulação e análise dos dados. Dentre os produtos de sensoriamento remoto disponíveis para a área, destacam-se os dados Shuttle Radar Topography Mission-SRTM, com resolução espacial de 30 metros. Este produto com...

  20. Gentrificación de La Candelaria: reconfiguraciones de lugar de residencia y consumo de grupos de altos ingresos

    Directory of Open Access Journals (Sweden)

    Adrian Smith Manrique Gómez

    2013-01-01

    Full Text Available El sector de La Candelaria (Bogotá D. C., Colombia ha vuelto a ser un lugar de consumo y residencia de grupos de personas de altos ingresos económicos, luego de su abandono a mediados del siglo XX por efecto de múltiples problemáticas urbanas. Esta dinámica de relocalización es conocida por la geografía urbana como gentrificación; tendencia previamente registrada en otras urbes e integrante del proceso global de construcción urbana. El artículo ofrece una lectura de dicha dinámica urbana bogotana a partir del análisis de sus causas, el seguimiento a su funcionamiento y sus consecuencias.

  1. Tipología de productores y sostenibilidad de cultivos en Alto Urubamba, La Convención – Cusco

    Directory of Open Access Journals (Sweden)

    Isaías Merma

    2012-01-01

    Full Text Available La investigación se llevó a cabo en la región geográfica del Alto Urubamba, provincia de La Convención, Cusco – Perú. El objetivo fue identificar tipos de productores y evaluar la sostenibilidad de cultivos en fincas agrícolas de selva alta. Para la tipología se aplicó encuestas a una muestra de 106 productores tanto en términos biofísicos como socio-económicos analizándose la información mediante la estadística descriptiva. Luego se identificó los tipos de productores mediante el análisis multivariado utilizando variables previamente seleccionadas. Asimismo se evaluó la sostenibilidad de ocho cultivos tropicales; para esto, se seleccionó tres fincas por cultivo de un total de 24 fincas evaluadas. Se utilizó índices prácticos de calidad del suelo y salud del cultivo con una valoración de 0 a 10 y se calificó con la participación de los productores. Los resultados muestran que en la zona existen tres tipos de productores según su eficiencia en el manejo de recursos y su lógica económica. Los cultivos de té (6.65 y mango (6.50 obtienen los valores más altos de sostenibilidad, seguidos del café (6.25, cacao (6.25, cítricos (5.50, plátano (5.45 y coca (5.10. La papaya (4.60 muestra un valor menor a cinco, lo que califica a este cultivo como no sustentable para las condiciones en estudio.

  2. TENDÊNCIAS HIDROLÓGICAS NO ALTO CURSO DA BACIA HIDROGRÁFICA DO RIO UBERABA, EM MINAS GERAIS

    Directory of Open Access Journals (Sweden)

    Vítor de Oliveira Santos

    2016-06-01

    Full Text Available O aumento da demanda hídrica por parte das médias e grandes cidades brasileiras tem gerado preocupações no poder público quanto ao abastecimento urbano. Na contramão do aumento da demanda por água, os sistemas hídricos parecem não mais suprir as necessidades impostas pela sociedade, sobretudo nos períodos de estiagem. A bacia hidrográfica do rio Uberaba ilustra esse cenário pois vem sofrendo escassez hídrica desde o início dos anos 2000. Desde então percebe-se a realização de medidas urgentes como a transposição das águas do rio Claro para suprir a demanda hídrica da cidade de Uberaba, além da criação da Área de Proteção Ambiental – APA rio Uberaba. Este trabalho tem como objetivo central analisar estatisticamente, através de testes de tendência, séries históricas de vazão no âmbito do alto curso do rio Uberaba. Justifica-se a escolha do alto curso do referido rio como objeto de estudo o fato de o abastecimento público do município de Uberaba ser realizado dentro de seus limites. Como método utilizou-se os testes de regressão linear, Mann-Kendall, Mann-Kendall Sazonal, Curvatura de Sen e o teste de homogeneidade de Pettitt. Os resultados indicam paulatina redução das vazões de estiagem e ligeiro aumento das vazões máximas.

  3. Vidrios de silicato a partir de residuos galvánicos con alto contenido en Cr y Ni

    Directory of Open Access Journals (Sweden)

    Mello-Castanho, S. R. H.

    2006-02-01

    Full Text Available The environmental and human health related with harmful industrial waste is nowadays an issue of worldwide great concern. Particularly the case of galvanic solid waste, because of its high content in heavy metals, it is highly harmful from both environmental and human health point of view. In this study, glasses containing up to 40 wt% of galvanic waste with a high content of chromium and nickel were obtained. The chemical stability of these glasses was studied by hydrolytic, alkaline and acid attack. Finally the different glasses were studied by X-ray diffraction, X-ray fluorescence and infrared spectroscopy techniques in order to rationalize and to understand its observed chemical stability.

    La eliminación de los residuos industriales tóxicos, es en la actualidad un objetivo prioritario a nivel mundial. Para el caso particular de los residuos sólidos galvánicos, su alto contenido en metales pesados resulta perjudicial tanto para la salud como para el medio ambiente. En este trabajo se han obtenido vídrios con un 40% en peso de residuos galvánicos de alto contenido en cromo y níquel. La estabilidad química de los vídrios obtenidos fue comprobada mediante ensayos de resistencia al ataque hidrolítico, ácido y alcalino. Finalmente, los diferentes vídrios fueron caracterizados por diferentes técnicas difración de rayos-X, fluorescencia de rayos-X, espectrometría infrarroja.

  4. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  5. 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

  6. FFTF reactor assembly system technology

    International Nuclear Information System (INIS)

    Mangelsdorf, T.A.

    1975-01-01

    An overview is presented of the FFTF reactor and plant together with descriptions of core components, core internals, core system, primary and secondary control rod system, reactor instrumentation, reactor vessel and closure head, and supporting test programs

  7. 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

  8. Revitalization of reactor usage through reactor sharing

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1986-01-01

    The purpose of this work was to renew interest in using the University Florida Training Reactor (UFTR) for educational and training purposes outside the Nuclear Engineering Sciences (NES) and Environmental Engineering Sciences (EES) Departments at the University of Florida and for research by others outside the NES Department. The availability of the UFTR made possible through a US Department of Energy (DOE) Reactor Sharing Grant provided the mechanism to pursue generation of renewed interest at all levels both within the University of Florida and from other educational and corporate institutions

  9. 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

  10. 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.)

  11. 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.)

  12. The heavy water reactors

    International Nuclear Information System (INIS)

    Brudermueller, G.

    1976-01-01

    This is a survey of the development so far of this reactor line which is in operation all over the world in various types (e.g. BHWR, PHWR). MZFR and the CANDU-type reactors are discussed in more detail. (UA) [de

  13. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1983-01-01

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

  14. Osiris reactor descriptive report

    International Nuclear Information System (INIS)

    1976-03-01

    OSIRIS is a swimming pool reactor of 70 MW thermal power. Its main purpose is the irradiation of reactor materials in high neutron flux. A description is given of the air conditioning, ventilation, and radioactive gas removal system. (R.L.)

  15. FBR type reactor core

    International Nuclear Information System (INIS)

    Tamiya, Tadashi; Kawashima, Katsuyuki; Fujimura, Koji; Murakami, Tomoko.

    1995-01-01

    Neutron reflectors are disposed at the periphery of a reactor core fuel region and a blanket region, and a neutron shielding region is disposed at the periphery of them. The neutron reflector has a hollow duct structure having a sealed upper portion, a lower portion opened to cooling water, in which a gas and coolants separately sealed in the inside thereof. A driving pressure of a primary recycling pump is lowered upon reduction of coolant flow rate, then the liquid level of coolants in the neutron reflector is lowered due to imbalance between the driving pressure and a gas pressure, so that coolants having an effect as a reflector are eliminated from the outer circumference of the reactor core. Therefore, the amount of neutrons leaking from the reactor core is increased, and negative reactivity is charged to the reactor core. The negative reactivity of the neutron reflector is made greater than a power compensation reactivity. Since this enables reactor scram by using an inherent performance of the reactor core, the reactor core safety of an LMFBR-type reactor can be improved. (I.N.)

  16. Mirror hybrid reactor studies

    International Nuclear Information System (INIS)

    Bender, D.J.

    1978-01-01

    The hybrid reactor studies are reviewed. The optimization of the point design and work on a reference design are described. The status of the nuclear analysis of fast spectrum blankets, systems studies for fissile fuel producing hybrid reactor, and the mechanical design of the machine are reviewed

  17. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    2000-01-01

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

  18. 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

  19. Gas-cooled reactors

    International Nuclear Information System (INIS)

    Vakilian, M.

    1977-05-01

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

  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. 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

  2. Thermal reactor strategy

    International Nuclear Information System (INIS)

    1981-01-01

    This statement sets down briefly the CEGB's views on the requirement for nuclear power and outlines current progress in the implementation of the CEGB's thermal reactor strategy. The programme is traced historically, together with statements of Government policy. The place of Magnox, AGR, SGHWR, PWR and fast breeder reactors is discussed. Advantages and problems associated with the various types are outlined. (U.K.)

  3. Supercritical Water Reactors

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  4. 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)

  5. Fusion reactors - types - problems

    International Nuclear Information System (INIS)

    Schmitter, K.H.

    1979-07-01

    A short account is given of the principles of fusion reactions and of the expected advantages of fusion reactors. Descriptions are presented of various Tokamak experimental devices being developed in a number of countries and of some mirror machines. The technical obstacles to be overcome before a fusion reactor could be self-supporting are discussed. (U.K.)

  6. 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

  7. Tank type reactor

    International Nuclear Information System (INIS)

    Otsuka, Fumio.

    1989-01-01

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

  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. Reactor dynamics calculations

    International Nuclear Information System (INIS)

    Devooght, J.; Lefvert, T.; Stankiewiez, J.

    1981-01-01

    This chapter deals with the work done in reactor dynamics within the Coordinated Research Program on Transport Theory and Advanced Reactor Calculations by three groups in Belgium, Poland, Sweden and Italy. Discretization methods in diffusion theory, collision probability methods in time-dependent neutron transport and singular perturbation method are represented in this paper

  11. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-08-01

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

  12. Compact torsatron reactors

    International Nuclear Information System (INIS)

    Lyon, J.F.; Carreras, B.A.; Lynch, V.E.; Tolliver, J.S.; Sviatoslavsky, I.N.

    1988-05-01

    Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R 0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R 0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

  13. Iris reactor conceptual design

    International Nuclear Information System (INIS)

    Carelli, M.D.; Conway, L.E.; Petrovic, B.; Paramonov, D.V.; Galvin, M.; Todreas, N.E.; Lombardi, C.V.; Maldari, F.; Ricotti, M.E.; Cinotti, L.

    2001-01-01

    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)

  14. The secure heating reactor

    International Nuclear Information System (INIS)

    Pind, C.

    1987-01-01

    The SECURE heating reactor was designed by ASEA-ATOM as a realistic alternative for district heating in urban areas and for supplying heat to process industries. SECURE has unique safety characteristics, that are based on fundamental laws of physics. The safety does not depend on active components or operator intervention for shutdown and cooling of the reactor. The inherent safety characteristics of the plant cannot be affected by operator errors. Due to its very low environment impact, it can be sited close to heat consumers. The SECURE heating reactor has been shown to be competitive in comparison with other alternatives for heating Helsinki and Seoul. The SECURE heating reactor forms a basis for the power-producing SECURE-P reactor known as PIUS (Process Inherent Ultimate Safety), which is based on the same inherent safety principles. The thermohydraulic function and transient response have been demonstrated in a large electrically heated loop at the ASEA-ATOM laboratories

  15. 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.

  16. 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.

  17. 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.)

  18. Reactor feedwater device

    International Nuclear Information System (INIS)

    Igarashi, Noboru.

    1986-01-01

    Purpose: To suppress soluble radioactive corrosion products in a feedwater device. Method: In a light water cooled nuclear reactor, an iron injection system is connected to feedwater pipeways and the iron concentration in the feedwater or reactor coolant is adjusted between twice and ten times of the nickel concentration. When the nickel/iron ratio in the reactor coolant or feedwater goes nearer to 1/2, iron ions are injected together with iron particles to the reactor coolant to suppress the leaching of stainless steels, decrease the nickel in water and increase the iron concentration. As a result, it is possible to suppress the intrusion of nickel as one of parent nuclide of radioactive nuclides. Further, since the iron particles intruded into the reactor constitute nuclei for capturing the radioactive nuclides to reduce the soluble radioactive corrosion products, the radioactive nuclides deposited uniformly to the inside of the pipeways in each of the coolant circuits can be reduced. (Kawakami, Y.)

  19. Research reactor DHRUVA

    International Nuclear Information System (INIS)

    Veeraraghaven, N.

    1990-01-01

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

  20. 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.)

  1. Fusion reactor pumped laser

    International Nuclear Information System (INIS)

    Jassby, D.L.

    1988-01-01

    A nuclear pumped laser is described comprising: a toroidal fusion reactor, the reactor generating energetic neutrons; an annular gas cell disposed around the outer periphery of the reactor, the cell including an annular reflecting mirror disposed at the bottom of the cell and an annular output window disposed at the top of the cell; a gas lasing medium disposed within the annular cell for generating output laser radiation; neutron reflector material means disposed around the annular cell for reflecting neutrons incident thereon back into the gas cell; neutron moderator material means disposed between the reactor and the gas cell and between the gas cell and the neutron reflector material for moderating the energy of energetic neutrons from the reactor; converting means for converting energy from the moderated neutrons to energy pumping means for pumping the gas lasing medium; and beam compactor means for receiving output laser radiation from the annular output window and generating a single output laser beam therefrom

  2. Reactor core cooling device

    International Nuclear Information System (INIS)

    Kobayashi, Masahiro.

    1986-01-01

    Purpose: To safely and effectively cool down the reactor core after it has been shut down but is still hot due to after-heat. Constitution: Since the coolant extraction nozzle is situated at a location higher than the coolant injection nozzle, the coolant sprayed from the nozzle, is free from sucking immediately from the extraction nozzle and is therefore used effectively to cool the reactor core. As all the portions from the top to the bottom of the reactor are cooled simultaneously, the efficiency of the reactor cooling process is increased. Since the coolant extraction nozzle can be installed at a point considerably higher than the coolant injection nozzle, the distance from the coolant surface to the point of the coolant extraction nozzle can be made large, preventing cavitation near the coolant extraction nozzle. Therefore, without increasing the capacity of the heat exchanger, the reactor can be cooled down after a shutdown safely and efficiently. (Kawakami, Y.)

  3. 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

  4. 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

  5. Índice hiperbárico en la prevención primaria de las complicaciones hipertensivas del embarazo de alto riesgo

    Directory of Open Access Journals (Sweden)

    Alfonso Otero González

    2015-11-01

    Resultados: En las gestantes remitidas a consulta de Nefrología (38,2%, diagnosticadas de alto riesgo de PE y tratadas con AAS 100 mg nocturno (desde la semana 17 se redujo la incidencia de episodios de PE un 96,94%.

  6. Quasi una mostra. Giulio Carlo Argan, Wart Arslan e l'allestimento del Museo dell'Alto Adige tra propaganda e museografia, 1933-1939

    Directory of Open Access Journals (Sweden)

    Angelini, Gianpaolo

    2015-10-01

    Full Text Available L’articolo prende in esame la riorganizzazione del Museo dell’Alto Adige a cura di Wart Arslan negli anni 1933-1938 in relazione alle scelte dell’allestimento, alla propaganda di regime, agli studi sulla pittura barocca nel primo Novecento, sulla scorta dell’epistolario di Arslan e degli articoli apparsi sulla stampa specialistica.

  7. The CAREM reactor and present currents in reactor design

    International Nuclear Information System (INIS)

    Ordonez, J.P.

    1990-01-01

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

  8. 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.)

  9. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1978-10-01

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

  10. 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.)

  11. 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)

  12. Parasitosis intestinal, su relación con factores ambientales en niños del sector "Altos de Milagro", Maracaibo Intestinal parasitosis, its relation to environmental factors in children from the "Altos de Milagro", Maracaibo

    Directory of Open Access Journals (Sweden)

    Madeline Espinosa Morales

    2011-09-01

    Full Text Available INTRODUCCIÓN: El parasitismo intestinal de conjunto con otras enfermedades infecciosas trasmisibles, constituye el motivo por el cual un gran número de pacientes acude a los consultorios populares en la República Bolivariana de Venezuela; dentro de ellos predominan los niños y adolescentes, debido a la pobre condición higiénico- sanitaria de las barriadas. OBJETIVO: Determinar la presencia de algunos factores ambientales condicionantes en niños parasitados, del sector "Altos de Milagro"Norte, Maracaibo estado Zulia, entre diciembre de 2008 y diciembre de 2009. MÉTODOS: Se realizó un estudio descriptivo, retrospectivo para determinar el comportamiento de la parasitosis intestinal en los niños del sector y su relación con algunos factores ambientales, para lo cual se utilizó una encuesta realizada por la autora, con la finalidad de obtener la información relacionada con las diferentes variables a estudiar. RESULTADOS: Fueron atendidos 56 pacientes, 51,7 % representó al sexo masculino, este último fue el más parasitado con un 42,7 %, predominaron las edades comprendidas entre 1-4 años con 39,2 %, la disposición inadecuada de excretas estuvo presente en un 86,6 %, así como la presencia de vectores en un 94,6 %, y 26 pacientes consumían agua no tratada (57,8 %. CONCLUSIONES: Existió una elevada presencia de la enfermedad, el sexo masculino fue el más afectado; sin embargo no mostró diferencias significativas con el otro sexo. Predominó el grupo etario de 1-4 años. El alto porcentaje obtenido en los factores ambientales estudiados, mostró que fueron importantes en el comienzo, transmisión y propagación de la parasitosis. Se recomendó efectuar programas de intervención comunitaria que impidan o limiten la aparición de estas enfermedades.INTRODUCTION: The intestinal parasitism together with other transmissible and infectious disease is the reason by which many patients come to popular consulting rooms in the Bolivarian

  13. 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

  14. 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)

  15. Prevalencia de genotipos del virus del papiloma humano de alto riesgo no vacunables dentro del programa de Detección Precoz de Cáncer de Cérvix en Cantabria

    Directory of Open Access Journals (Sweden)

    María Paz-Zulueta

    2016-06-01

    Conclusiones: Atendiendo al alto porcentaje de VPH de alto riesgo oncogénico no vacunable, habría que replantear la estrategia de prevención en la población, que podría tener una falsa sensación de protección.

  16. Evaluación de la exposición a selenio en Los Altos de Jalisco, México Evaluation of the exposure to selenium in Los Altos de Jalisco, México

    Directory of Open Access Journals (Sweden)

    Roberto Hurtado-Jiménez

    2007-08-01

    Full Text Available OBJETIVO: Evaluar la exposición a selenio (Se vía agua potable en los habitantes de Los Altos de Jalisco. MATERIAL Y MÉTODOS: Se determinó la concentración de Se en 125 pozos y se estimaron los niveles de exposición a Se en bebés, niños y adultos. RESULTADOS: La dosis de exposición y la ingestión de Se vía agua potable variaron en los siguientes rangos: a bebés: 1.3-6.7 µg/kg/d y 12.6-67.2 µg/d; b niños: 0.8-4.5 µg/kg/d y 16.8-89.6 µg/d; c adultos: 0.6-3.0 µg/kg/d y 33.6-179.2 µg/d. CONCLUSIONES: En este caso, la exposición a Se representa un riesgo potencial para la salud de la población, ya que en la mayoría de los casos es mayor que la recomendada por organismos internacionales de salud. Sin embargo, no es tan alta como para esperar la ocurrencia de selenosis.OBJECTIVE: To evaluate the exposure to selenium in drinking water in Los Altos de Jalisco (Jalisco State Heights. MATERIALS AND METHODS: The concentration of selenium was determined in 125 water wells, and the exposure doses to selenium were estimated for babies, children and adults. RESULTS: The estimated values of the exposure doses to selenium and total intake of selenium were in the following ranges, respectively: (a babies: 1.3-6.7 µg/kg/d and 12.6-67.2 µg/d; (b children: 0.8-4.5 µg/kg/d and 16.8-89.6 µg/d, (c adults: 0.6-3.0 µg/kg/d and 33.6-179.2 µg/d. CONCLUSIONS: The estimated exposure levels to selenium were higher than those recommended as optimum by international health organizations, representing a potential health risk. Nevertheless, estimated values are not high enough to produce selenosis.

  17. Tobacco planters and collectors in the Alto Paraná colonization of Misiones (1930-1946 Tabacaleros y acopiadores en la colonización del Alto Paraná Misionero (1930-1946

    Directory of Open Access Journals (Sweden)

    María Cecilia Gallero

    2011-01-01

    Full Text Available During the settler expansion between the decades 1920-1930 in the Alto Paraná of Misiones, the tobacco was for German-Brazilian settlers a product to obtain monetary incomes and for their own consum. The aim of this paper is to analyze the link between producers and collectors of tobacco, trying to identify the conflicting elements of this relationship (disputes over the classification and the product price. The heuristic work focused on Johann Company, the company's largest collectors of Puerto Rico Colony and the only one that keeps the records since its beginings (1929. The product their collected the most time was tobacco (1929-1985, and in descending order of importance their also collected tung, cassava starch and lard. Throughout the book collection of tobacco sales it is showed both sides of the production of tobacco: tobacco producers and collectors. This information has been enriched by interviews with key informants.Durante la expansión colonizadora de las décadas de 1920-1930 en el Alto Paraná Misionero, el tabaco fue para los colonos alemanes-brasileños un cultivo destinado a la obtención de ingresos monetarios y bienes de consumo. El objetivo de este trabajo es analizar el vínculo entre productores y acopiadores de tabaco, tratando de identificar los elementos conflictivos de esta relación (disputas por la clasificación y el precio del producto. El trabajo heurístico se focalizó en la Compañía Johann, la empresa acopiadora más grande de la colonia Puerto Rico y la única que mantiene los registros desde su creación (1929. El producto que acopió por más tiempo fue el tabaco (1929-1985, y en orden de importancia decreciente también acopiaron tung, almidón de mandioca y grasa de cerdo. A través de los libros de acopio y de venta de tabaco enfardelado se da vida a las dos caras de la producción del tabaco: los productores tabacaleros y los acopiadores. Dicha información ha sido enriquecida con entrevistas a

  18. 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.

  19. 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.)

  20. Fourth Generation Reactor Concepts

    International Nuclear Information System (INIS)

    Furtek, A.

    2008-01-01

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

  1. 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)

  2. 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)

  3. 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.)

  4. 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.)

  5. Method of reactor operation

    International Nuclear Information System (INIS)

    Maeda, Katsuji.

    1982-01-01

    Purpose: To prevent stress corrosion cracks in stainless steels caused from hydrogen peroxide in reactor operation in which the density of hydrogen peroxide in the reactor water is controlled upon reactor start-up. Method: A heat exchanger equipped with a heat source for applying external heat is disposed into the recycling system for reactor coolants. Upon reactor start-up, the coolants are heated by the heat exchanger till arriving at a temperature at which the dissolving rate is faster than the forming rate of hydrogen peroxide in the coolants, and nuclear heating is started after reaching the above temperature. The temperature of the reactor water is increased in such a manner and, when it arrives at 140 0 C, extraction of control elements is started and the heat source for the heat exchanger is interrupted simultaneously. In this way spikes in the density of hydrogen peroxide are suppressed upon reactor start-up to thereby decrease the stress corrosion cracks in stainless steels. (Horiuchi, T.)

  6. 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

  7. 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

  8. 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

  9. 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.)

  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 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.).

  12. Reactor feedwater system

    International Nuclear Information System (INIS)

    Kagaya, Hiroyuki; Tominaga, Kenji.

    1993-01-01

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

  13. Reactor feedwater control device

    International Nuclear Information System (INIS)

    Koshi, Yuji.

    1993-01-01

    In the device of the present invention, an excess response is not caused in a reactor feed water system even when voids are fluctuated by using an actual water level signal as a reactor water level signal. That is, a standard water level signal and a reactor water level signal are inputted to a comparator. An adder adds water level difference signal outputted from the comparator and mismatch flow rate signal prepared by multiplying the difference between a main steam flow rate signal and a feed water flow rate signal by a mismatch gain. A feed water controller integrates the added signal and outputs flow rate demand signal. A feed water system receives the flow rate demand signal as input. A water level calculation means is disposed to such a device for calculating an actual water level based on the change of coolant possessing amount of the reactor, and the output thereof is defined as a reactor water level signal. With such procedures, excessive elevation of water level of the reactor can be prevented even upon occurrence of void fluctuation phenomenon or the like in the reactor such as upon sole scram operation. Accordingly, plant shut down caused thereby can be avoided safely. (I.S.)

  14. 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.)

  15. Evidencias paleoclimáticas en asentamientos del Alto Piura durante del período Intermedio Temprano

    Directory of Open Access Journals (Sweden)

    1993-01-01

    Full Text Available EVIDENCES PALEOCLIMATIQUES SUR DES SITES DU HAUT PIURA AU COURS DE LA PREMIERE PERIODE INTERMEDIAIRE. Ce travail présente les évidences géomorphologiques observées dans les fouilles archéologiques de Vicús, Haut Piura (1987-1990. Il s’agit, en général, d’altérations causées probablement par des pluies d’intensités diverses qui font penser que l’humidité était plus importante qu’aujourd’hui. Trois événements d’importance sont à détacher : le plus ancien, probablement du 4ème siècle ap. J.C., provoque des dommages importants dans l’architecture et anticipe des changements culturels significatifs qui débouchent sur l’introduction de l’architecture en briques et les éléments de style mochica 2 le suivant a des effets similaires, et même plus percutants et précède une diminution notable des évidences dans l’occupation de la zone. Ensuite, il n’y a pas d’évidences claires de présence mochica. Certains indices permettent de le situer au 6ème siècle ap. J.C. 3 Le troisième est plus récent et précède une occupation Chimú-Inca. Se presenta las evidencias geomorfológicas observadas en las excavaciones arqueológicas llevadas a cabo en Vicús, Alto Piura (1987-1990. En su mayoría se trata de alteraciones probablemente causadas por precipitaciones de diferentes intensidades que hacen pensar en una humedad probablemente algo mayor que en la actualidad. Destacan tres eventos de mayor impacto: 1 El más temprano, probablemente del cuarto siglo d.C., causa daños importantes en la arquitectura y antecede a cambios culturales significativos que llevan a la introducción de la arquitectura de adobes y elementos del estilo Mochica 2 el siguiente tiene efectos similares o aún más impactantes y antecede a una disminución notable de evidencias de ocupación de la zona después de este evento ya no hay evidencias claras de presencia mochica hay algunos indicios que permiten ubicarlo en el sexto siglo d.C. 3 El

  16. Simwe model application on susceptibility analysis to linear erosion: a case study in Alto Douro wine region.

    Science.gov (United States)

    Fernandes, Joana; Bateira, Carlos; Soares, Laura; Faria, Ana; Moura, Rui; Gonçalves, José

    2016-04-01

    The wine production in Alto Douro Wine Region - one of the world's oldest regulated and demarcated wine region - is based on a slope system organized in agricultural terraces once supported exclusively by dry stone walls. It has been undergoing the necessary changes for the introduction of technological innovations partially associated to the mechanization of vineyards work. In this sense, different forms of terrain framing have been implemented, namely the substitution of stone walls by earth embankments. This evolution raises a group of problems related to the hydric soil erosion and landscape preservation, since Alto Douro Wine Region is classified as UNESCO World Heritage Site since 2001. The study area is mostly occupied by vineyards planted in the agriculture terraces without continuous vegetation, the flow proceeds superficially influenced by the weak infiltration capacity and hydraulic conductivity. So, because of this conditioning factor the erosive features present non-significant depth, and the length thereof is limited essentially by the slope of the land, where was registered 64 gullies and 78 rills This paper focuses on the evaluation of susceptibility to linear erosion, through the application of SIMWE (SIMulated Water Erosion), (Mitas and Mitasova, 1998), using a digital elevation model, with pixel of one square meter of spatial resolution, created through detail aerial photographs, (side pixel of 50 cm), submitted to automatic stereo-correlation procedures in Agisoft PhotoScan software. The results provided by the model are compared with hydrological characteristics of the soil, (infiltration capacity, and hydraulic conductivity), soil texture, and soil structure parameters (identified by electrical resistivity measurement) where obtained from field monitoring. This approach demonstrates an association between the spatial distribution of erosive features with high values of soil saturation, and reduced water discharge (10-110 cm3/s), that are

  17. Heterogeneous gas core reactor

    International Nuclear Information System (INIS)

    Han, K.I.

    1977-01-01

    Preliminary investigations of a heterogeneous gas core reactor (HGCR) concept suggest that this potential power reactor offers distinct advantages over other existing or conceptual reactor power plants. One of the most favorable features of the HGCR is the flexibility of the power producing system which allows it to be efficiently designed to conform to a desired optimum condition without major conceptual changes. The arrangement of bundles of moderator/coolant channels in a fissionable gas or mixture of gases makes a truly heterogeneous nuclear reactor core. It is this full heterogeneity for a gas-fueled reactor core which accounts for the novelty of the heterogeneous gas core reactor concept and leads to noted significant advantages over previous gas core systems with respect to neutron and fuel economy, power density, and heat transfer characteristics. The purpose of this work is to provide an insight into the design, operating characteristics, and safety of a heterogeneous gas core reactor system. The studies consist mainly of neutronic, energetic and kinetic analyses of the power producing and conversion systems as a preliminary assessment of the heterogeneous gas core reactor concept and basic design. The results of the conducted research indicate a high potential for the heterogeneous gas core reactor system as an electrical power generating unit (either large or small), with an overall efficiency as high as 40 to 45%. The HGCR system is found to be stable and safe, under the conditions imposed upon the analyses conducted in this work, due to the inherent safety of ann expanding gaseous fuel and the intrinsic feedback effects of the gas and water coolant

  18. Reactor Sharing Program

    International Nuclear Information System (INIS)

    Tehan, Terry

    2002-01-01

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

  19. Necessity of research reactors

    International Nuclear Information System (INIS)

    Ito, Tetsuo

    2016-01-01

    Currently, only three educational research reactors at two universities exist in Japan: KUR, KUCA of Kyoto University and UTR-KINKI of Kinki University. UTR-KINKI is a light-water moderated, graphite reflected, heterogeneous enriched uranium thermal reactor, which began operation as a private university No. 1 reactor in 1961. It is a low power nuclear reactor for education and research with a maximum heat output of 1 W. Using this nuclear reactor, researches, practical training, experiments for training nuclear human resources, and nuclear knowledge dissemination activities are carried out. As of October 2016, research and practical training accompanied by operation are not carried out because it is stopped. The following five items can be cited as challenges faced by research reactors: (1) response to new regulatory standards and stagnation of research and education, (2) strengthening of nuclear material protection and nuclear fuel concentration reduction, (3) countermeasures against aging and next research reactor, (4) outflow and shortage of nuclear human resources, and (5) expansion of research reactor maintenance cost. This paper would like to make the following recommendations so that we can make contribution to the world in the field of nuclear power. (1) Communication between regulatory authorities and business operators regarding new regulatory standards compliance. (2) Response to various problems including spent fuel measures for long-term stable utilization of research reactors. (3) Personal exchanges among nuclear experts. (4) Expansion of nuclear related departments at universities to train nuclear human resources. (5) Training of world-class nuclear human resources, and succession and development of research and technologies. (A.O.)

  20. Development of Reactor Console Simulator for PUSPATI TRIGA Reactor

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  1. Chemical and mineralogical characterization of elbaites from the Alto Quixaba pegmatite, Seridó province, NE Brazil

    Directory of Open Access Journals (Sweden)

    Ana C.M. Ferreira

    2005-12-01

    Full Text Available The Alto Quixaba pegmatite, Seridó region, northeastern Brazil, is a 60º/80ºSW-trending subvertical dike discordantly intruded into biotite schists of the Upper Neoproterozoic Seridó Formation. It has three distinct mineralogical and textural zones, besides a replacement body that cuts the pegmatite at its central portion and in which occur, among other gem minerals, colored elbaites. Elbaites usually occur as prismatic crystals, elongate according to the c-axis, with rounded faces and striations parallel to this axis. Optically, crystals are uniaxial negative with strong pleochroism; refractive index extraordinary axis = 1.619-1.622 and ordinary axis = 1.639-1.643, birefringence between 0.019 and 0.021, average relative density of 3.07, and the following unit cell parameters: ao = 15.845 Å, co = 7.085 Å and V = 1540.476 Å. There is alkali deficiency in the X site of 12-17%. The elbaites are relatively enriched in MnO (1.69 to 2.87% and ZnO (up to 2.98%.O pegmatito Alto Quixaba na região do Seridó, nordeste do Brasil, é um corpo subvertical de direção 60°/80°SW intrudindo discordante biotita xistos da Formação Seridó. Apresenta três zonas distintas em termos de mineralogia e textura, al��m de uma zona de alteração em forma de dique na qual ocorre, entre outros minerais-gema, elbaítas coloridas. As elbaítas ocorrem como cristais prismáticos alongados de acordo com o eixo C, com faces arredondadas e estrias paralelas a esse eixo. Os cristais são uniaxiais negativos e apresentam forte pleocroísmo; índices de refração nE = 1,619-1,622 e nO = 1.639-1.643, birrefrigência entre 0,019 e 0,021, densidade relativa de 3,07, e os parâmetros seguintes da célula unitária: ao = 15,845 Å, co = 7,085 Å e V = 1540,476 Å. O sítio X apresenta deficiência em álcalis entre 12 e 17%. As elbaítas são relativamente ricas em MnO (1,69 a 2,87% e ZnO (até 2,98%.

  2. Reactividad y propiedades mecánicas de escoria de alto horno activada por álcalis

    Directory of Open Access Journals (Sweden)

    Escalante-García, J. I.

    2002-10-01

    Full Text Available Investigations were carried out to characterize the reactivity and mechanical properties in blast furnace slag pastes activated by 5 alkali systems such as NaOH, waterglass and combinations of Na2CO3, Na2SO4 y Ca(OH2 in concentrations of 5%. Cubes of 5cm were prepared and cured under water for up to 120 days at 20 and 60°C. The highest compressive strengths were noted for the waterglass activation, followed by one of the combination of 3 compounds, while NaOH activation resulted in the lowest strengths. Increased temperatures favored the strength for the waterglass activation, outperforming those of the Portland cement paste used as control at all times, whereas it had a negative effect for all other activations. The reactivity of the systems, as obtained by measurements of non evaporable water and selective chemical dissolution, indicated that the slag is more reactive under the NaOH activation. Scanning electron microscopy by means of backscattered electrons confirmed the different reactivities and the mechanical properties observed.

    Se realizaron estudios de caracterización de reactividad y propiedades mecánicas en pastas de escoria de alto horno activada por 5 sistemas alcalinos como NaOH, vidrio soluble y combinaciones de Na2CO3, Na2SO4 y Ca(OH2 en concentraciones de 5%. Se prepararon cubos de 5cm por lado y se curaron durante 120 días a 20 y 60°C bajo agua. Los valores mas altos de resistencia mecánica fueron registrados por el sistema de escoria activada con vidrio soluble, seguido por una de las combinaciones de 3 reactivos químicos, mientras que el desarrollo de propiedades mecánicas fue más pobre con la activación por NaOH. El aumento en la temperatura de curado favoreció la resistencia a la compresión de escoria con vidrio soluble, superando a la del cemento Portland a todos los tiempos de curado; para los otros sistemas el incremento de la temperatura de curado resultó perjudicial. En contraste con las

  3. Nuevo modelo matemático para la distribución de carga en el horno alto

    Directory of Open Access Journals (Sweden)

    Jiménez, J.

    1998-05-01

    Full Text Available A mathematical model for burden distribution in the blast furnace, has been developed. A set of operational variables related with the charging system (Paul Wurth plus other parameters related with the burden itself, such as ore and coke repose angles, weights discharged and the effect of the uprising gas, have been taken into account. These data are processed by modern computer tools. As a result, the burden distribution inside the blast furnace is obtained. Every time that a charge is added to the blast furnace, the model updates the burden distribution. The approach employed is based on considering each burden layer described by a set of interrelated polynomials. It has been tested comparing its results with burden layers obtained in a physical model of the blast furnace (scale 1/10. After installation in Aceralia blast furnace B control computers, the model is currently being employed as a tool for process control.

    El modelo matemático desarrollado describe la distribución de carga en el tragante de un horno alto. Se ha empleado un conjunto de variables operacionales relacionadas con el sistema de carga (Paul Wurth, junto con otras obtenidas de la carga, tales como el peso descargado, los ángulos de reposo de los materiales y el efecto del gas al atravesar el horno. Estos datos se procesan mediante herramientas informáticas. Como resultado, se obtiene la distribución de carga en el horno. Cada vez que se introduce una carga, el modelo actualiza la distribución. La aproximación empleada considera el perfil de cada capa de carga, el cual está descrito por un conjunto de polinomios interrelacionados. Los resultados se comparan con la distribución obtenida en un modelo físico del horno (escala 1/10. Tras su instalación en los ordenadores de proceso del horno alto B de Aceralia, el modelo se emplea actualmente para el control del mismo.

  4. Linguagem de programação JULIA: uma alternativa open source e de alto desempenho ao MATLAB

    Directory of Open Access Journals (Sweden)

    João Marcello Pereira

    2017-06-01

    Full Text Available O MATLAB® é um dos principais softwares utilizados nos cursos de ciências exatas e de engenharia para o ensino de programação numérica e pesquisa científica, em função de sua sintaxe de alto nível e dos diversos toolboxes do seu amigável ambiente de programação. Apesar das muitas vantagens, é um software proprietário que apresenta um alto custo de aquisição para as instituições de ensino e uso individual. Além disso, possui código fonte fechado e os programas nativos “.m” não são plenamente compatíveis em outros ambientes de programação com suporte a esse formato de arquivo. Embora existam softwares livres e open source com relativa semelhança de IDE (Integrated Development Environment ou Ambiente de Desenvolvimento Integrado e sintaxe de código, muitos desses softwares apresentam baixo desempenho computacional em relação ao MATLAB®. Dessa forma, o objetivo no presente trabalho é apresentar a linguagem de programação Julia, como alternativa ao MATLAB®, no ensino de programação numérica e simbólica, bem como de pesquisa científica. Neste trabalho são comparadas as características das duas linguagens de programação, sendo apresentado um benchmark entre as linguagens em que se avaliam o tempo de execução e os resultados dos cálculos. Para isso, foram implementados em JULIA e em MATLAB® os algoritmos Série de Fibonacci Recursiva e Gráfico 2D dos polinômios de Berstein e, ainda, utilizadas as funções nativas de cálculo simbólico, algébrico e equação diferencial numérica Runge-Kutta 45.

  5. Crecimiento del maíz en vertisoles con alto aluminio en la Baixada Maranhense pre-Amazonia, Brasil.

    Directory of Open Access Journals (Sweden)

    Alessandro Costa-da Silva

    2014-07-01

    Full Text Available El objetivo de este trabajo fue evaluar el crecimiento del maíz en suelos con alto contenido de aluminio. Se midió el efecto del Al3+ en raíces y la cantidad de materia seca (raíz, hoja y tallo de maíz. Se efectuó la caracterización físico-química de cuatro muestras de suelo con alto aluminio colectadas del horizonte Ap, en tres municipios de la región conocida como Baixada Maranhense (Pre-Amazonia, Brasil: Santa Rita (SR, Arari (AR y Vitoria do Mearim (VM y un testigo colectado en el municipio de São Luís, Área del Núcleo de Tecnología Rural (T. El estudio, ejecutado en 2009, se llevó a cabo en invernadero y se utilizó 2 dm3 de suelo por maceta. Asimismo las muestras fueron divididas en muestras con y sin fertilización. La variación en la longitud de la raíz y de materia seca de las hojas difirió significativamente entre tratados con y sin fertilizante, excepto en la muestra de la localidad T. La producción de materia seca de raíz, tallo y hoja fue mayor en todos los suelos cuando se fertilizó. El suelo testigo también superó a todos los demás en cuanto a producción de materia seca en la raíz, posiblemente como resultado de una menor cantidad de Al3+ (1,2 cmolc/dm3 en comparación con los suelos SR, AR y VM (6,8; 8,0 y 7,0 cmolc/dm3 respectivamente. Se concluye la fertilización reduce el efecto detrimental del aluminio en la producción de maíz en la Baixada Maranhense.

  6. Efecto de un programa de estiramientos activos en jugadoras de fútbol sala de alto rendimiento

    Directory of Open Access Journals (Sweden)

    Francisco Ayala

    2010-01-01

    Full Text Available El propósito de este estudio fue determinar la progresión de la flexibilidad isquiosural a través del rango de movimiento (ROM de la flexión de cadera antes (línea base de la flexión de cadera, duración 6 semanas, durante (efecto de un programa de estiramientos, duración 8 semanas y después (mantenimiento de la flexibilidad, duración 4 semanas de un programa de estiramientos activos de 8 semanas en jugadoras de alto rendimiento de fútbol sala. Material y método: 10 jugadoras de fútbol sala de alto rendimiento adultas jóvenes completaron este estudio. Un diseño longitudinal, temporal, ininterrumpido de medidas repetidas fue utilizado. Todas las jugadoras llevaron a cabo un programa de estiramientos de 8 semanas. El test unilateral de elevación de la pierna recta fue empleado para evaluar el ROM de la flexión de cadera a las 0, 2, 4 y 6 semanas antes del programa de estiramientos, durante el programa de estiramientos, semanas 2, 4, 6 y 8; y a las 2 y 4 semanas después del cese del programa de estiramientos. Resultados y conclusiones: el análisis de la fase inicial reveló que la línea base del ROM de la flexión de cadera tenía una tendencia irregular, con valores máximos de la flexibilidad isquiosural tanto positivos como negativos. El programa de estiramientos activos de 8 semanas aumentó el ROM de la flexión de cadera un 25,96±8,76%. Cuatro semanas después del cese del programa de estiramientos, el ROM de la flexión de cadera mostró un descenso significativo del 7,9%.

  7. Centro astronómico de Calar-Alto Almería – España

    Directory of Open Access Journals (Sweden)

    Margarit, Salvador

    1980-08-01

    Full Text Available The Basic Agreement of Cooperation in Scientific Research and Technological development signed by the Spanish and West German governments in 1970, served as a framework for the agreement signed in 1972 by the National Astronomical Commission and the Max-Planck Society, for the setting up of the «Spanish-German Astronomical Centre». Construction work was started in 1973 on the Calar-Alto (2,168 m, the highest point in the Sierra de los Filabres in the province of Almería. At present the last of the domed buildings, which is intented to accommodate a 3.5 m diameter Telescope and should go into operation in 1983, is at the completion stage. By this date all work will have been completed, with four domed buildings for telescopes of different sizes and the buildings for laboratory, living quarters, services and workshops needed for the use of the scientific instruments. The 1.52 m diameter National Astronomical Observatory telescope has been installed in a separate building beside the infrastructure of the Spanish-German Astronomical Centre.

    El Convenio Básico de Cooperación en la Investigación Científica y en el Desarrollo tecnológico suscrito entre los gobiernos de España y de la República Federal de Alemania en 1970, sirvió de marco para el acuerdo firmado en 1972 entre la Comisión Nacional de Astronomía y la Sociedad Max-Planck, para el establecimiento del «Centro Astronómico» Hispano-Alemán. En 1973 se iniciaron los trabajos de Obras en Calar-Alto (2.168 m cota máxima de la Sierra de los Filabres en la provincia de Almena. Actualmente se halla en fase de terminación el último de los edificios de Cúpula destinado a albergar un Telescopio de 3,5 m de diámetro y cuya puesta en servicio se prevé en 1983. Para entonces quedará culminada la realización completa con cuatro edificios de Cúpula para telescopios de diferentes tamaños y las edificaciones destinadas a laboratorio, residencia, viviendas, servicios y

  8. Aplicabilidade do Brums: estados de humor em atletas de voleibol e tênis no alto rendimento

    Directory of Open Access Journals (Sweden)

    Tatiana Marcela Rotta

    2014-12-01

    Full Text Available Introdução: Os estados de humor são indicadores que auxiliam sobremaneira o rendimento e a prevenção da saúde do atleta. Objetivo: Analisar a aplicabilidade do instrumento BRUMS na avaliação do perfil de estados de humor em atletas de alto rendimento do sexo masculino, de voleibol n=59 e tênis n=69. Métodos: comparar as variáveis independentes: modalidade esportiva (voleibol e tênis; tempo de prática no alto rendimento (até 2 anos; mais de 2 anos e categorias de idade (jovens e adultos com as variáveis dependente do perfil de humor (tensão, depressão, raiva, vigor, fadiga e confusão mental. O estudo causal-comparativo, utilizou, para coleta de dados, o instrumento BRUMS, validado no Brasil, com participação das autoras desse estudo. Resultados: Ao executar a MANOVA, foram verificadas diferenças entre as modalidades (F=4,289/ p=0,001; Hotellings's Trace = 0,216 e tempo de prática (F=5,845/ p<0,001; Hotelling's Trace = 0,295 no vigor. A modalidade versus tempo de prática apresentou significância na interação das duas variáveis (p=0,003, em torno de 7% da variância. Também na variável tensão p=0,05 (voleibol vs. tempo de prática, na variável raiva p=0,001 (voleibol vs. categoria de idade. No tênis, a depressão p=0,001, raiva p=0,04 e confusão mental p< 0,02 com médias maiores em adultos e mais experientes. Conclusão: A modalidade foi responsável por 11% da alteração no perfil de humor (p=0,001.

  9. Armonización entre proceso de aprendizaje y práctica deportiva en universitarios deportistas de alto nivel

    Directory of Open Access Journals (Sweden)

    Pedro R. Álvarez Pérez

    2012-01-01

    Full Text Available Este trabajo se ha centrado en el análisis de las dificultadesque los estudiantes universitarios deportistas de alto nivel encuentran para conciliar su proceso formativo con la práctica deportiva de alta competición. Sin una ayuda adecuada para gestionar la alternancia de esta doble actividad, muchos de estos estudiantes pueden verse abocados a situaciones de estrés, fracaso oabandono de los estudios o del deporte. Por eso, el objetivo de la investigación se orientó al diagnóstico de lascondiciones bajo las cuales se lleva a cabo el proceso de aprendizaje de estos estudiantes deportistas y la evaluación de las necesidades que tienen para compaginar el proceso formativo con la práctica deportiva. Se siguió un método descriptivo y exploratorio, empleándose diferentes estrategias de corte cualitativo: una entrevista en profundidad con los 16 estudiantes deportistas de alto nivel reconocidos por el Consejo Superior de Deportes y matriculados en diversas titulaciones de la Universidad de La Laguna durante el curso 2009-2010 y un grupo de discusión con 8 informantes críticos cuya actividad profesional estaba vinculada a la formación y la práctica deportiva. Después del proceso de análisis de contenido,esencialización y categorización de las proposiciones de respuesta ofrecidas por los participantes, los resultados pusieron de manifiesto que son diversas las variables que condicionan el desarrollo paralelo de estas dos actividades (tiempo, motivación, exigencias formativas, etc.. Del estudio se deriva la necesidad de tener en cuenta la realidad personal de estos estudiantes, introduciendo medidas de apoyo y adaptando la enseñanza a su situación y a sus necesidades específicas para el desarrollo en paralelo de la actividad deportiva y académica.

  10. Demographic, health services and socio-economic factors associated with pulmonary tuberculosis mortality in Los Altos Region of Chiapas, Mexico.

    Science.gov (United States)

    Nájera-Ortiz, J C; Sánchez-Pérez, H J; Ochoa-Díaz, H; Arana-Cedeño, M; Lezama, Ma Salazar; Mateo, M Martín

    2008-08-01

    Chiapas is one of the Mexican states having the highest rates of Pulmonary Tuberculosis (PTB), due to the numerous factors impeding its management and control (poverty, poor housing and nutrition, shortage of health resources, among others). To analyse the PTB mortality of a cohort of patients in Los Altos Region of Chiapas, who had been diagnosed with PTB from January 1, 1998 to December 31, 2002; and, to identify demographic, socioeconomic and health services utilization factors, associated with death from PTB. Analysis of a cohort of patients aged over 14 years diagnosed with PTB in the above mentioned period (n = 431) in Los Altos region of Chiapas. The records of the Tuberculosis Programme were reviewed, and patients were located through a search attempting to locate them in their homes. Those found alive were interviewed and asked to provide sputum samples. In the case of deceased patients, a verbal autopsy was obtained from a member of their family. The records of the PTB Programme in the area were incomplete and erroneous in many cases. The results of the home follow-up visits were: 208 (48%) patients located alive, five of whom were still PTB positive (three with multi-drug resistance); 145 (34%) could not be located and 78 (18%) had already died. Apparently, in at least 40 cases, the deaths were associated with PTB. Of these forty, 33 (83%) died without having received any medical care. The factors associated with dying from PTB were: 45 and over years of age (OR = 1.3; 95% CI = 0.98-1.3), 0-3 schooling years (OR = 3.3; 95% CI = 1.1-9.6), engaged in agriculture (OR = 2.2; 95% CI = 1.1-4.4), not living in main villages of their municipality (OR = 1.2; 95% CI = 1.0-1.3), living in a rural community (OR = 2.7; 95% CI = 1.1-6.8), not having been treated in DOTS (OR = 1.2; 95% CI = 1.0-1.3) and having defaulted from treatment (OR = 11.5; 95% CI = 5.3-24.8). The high rate of mortality due to PTB observed constitutes a serious public health problem deserving

  11. OBTENÇÃO DE BARRAS DE CEREAIS DE CAJU AMEIXA COM ALTO TEOR DE FIBRAS

    Directory of Open Access Journals (Sweden)

    LUíSA HELENA ELLERY MOUR�O

    2010-03-01

    Full Text Available

    As barras de cereais vêm apresentando crescimento constante junto ao público consumidor. Considerando o crescimento do segmento de barras de cereais no setor de alimentos este trabalho teve como objetivos desenvolver barras de cereais de caju ameixa com alto teor de fi bras utilizando ingredientes funcionais e matéria-prima regional; inovar no uso de ingredientes não utilizados nas formulações convencionais; realizar análises físicas, físicoquímicas e químicas e avaliar as propriedades nutricionais. Formulou-se dois tipos de barras, (F1 e (F2 a partir de uma formulação básica (FB. A FB foi processada utilizando-se aveia, fl ocos de arroz, leite em pó desnatado, açúcar mascavo, glucose de milho, gordura vegetal hidrogenada, canela, lecitina de soja e fl ocos de milho. As formulações F1 e F2 diferiram da FB nas concentrações dos ingredientes, na adição de linhaça, de caju ameixa, de castanha de caju, na substituição da gordura vegetal hidrogenada por óleo de canola e na retirada dos fl ocos de milho. A FB resultou 94,39 kcal e F1 e F2 em 95,69 kcal e 101,06 kcal respectivamente em 25g utilizando os coefi cientes de ATWATER. A modifi - cação dos ingredientes provocou aumento signifi cativo no teor de fi bra alimentar tornando as barras F1 e F2 produtos com alto teor de fi bra alimentar (10,58g e 12,69g/100g, respectivamente. Conclui-se que as barras de cereais F1 e F2 podem ser indicadas para indivíduos com constipação intestinal, dislipidemias e sobrepeso. Além disso, ambas poderiam ser enquadradas no conceito de alimento funcional, devido ao fato de conterem um maior teor de fi bras dietéticas que contribuem para a manutenção da boa saúde.

  12. Relación entre factores micro- estructurales e impacto repetido en aleaciones de alto cromo para bolas de molino.

    Directory of Open Access Journals (Sweden)

    E. Albertin

    2008-01-01

    Full Text Available Las aleaciones de alto cromo son empleadas para la fabricación de bolas de molino en industrias de procesamiento de minerales. Los usuarios y fabricantes requieren lograr mejores resultados técnicos-económicos en sus aplicaciones, por lo que necesitan aumentar los conocimientos relacionados con los aspectos estructurales de estos materiales. En este trabajo se realiza una investigación con vistas a establecer relaciones entre la estructura de las aleaciones y su comportamiento ante el impacto repetido que es un fenómeno característico en estos procesos. Se funden bolas con varias aleaciones hipo eutécticas, eutécticas, e hipereutécticas; se prueban en un equipo que simula el impacto repetido. Los resultados permiten comprobar los buenos resultados de aleaciones hipo eutécticas con relaciones de Cr/C altas y a su vez altos contenidos de Cr y de aleaciones eutécticas para menores relaciones de Cr/C y menores contenidos de Cr, en ambos casos los carburos eutécticos son de forma simétrica, regulares y no forman redes continuas de carburos asimétricos bordeando los granos, que presentan peores comportamiento en el impacto repetido y que son el caso de las hipoeutécticas con bajas relaciones Cr/C y las hipereutécticas donde aparecen también grandes carburos primarios.High Chromium alloys are used to manufacture grinding balls for the Industry of Construction Materials. Customers and users need to improve their knowledge about the relationships between microstructure and the parts damage in these alloys to obtain better technical-economics results. In this paper the results of a research to obtain different microstructures of eutectics, hipoeutectics and hipereutectics alloys are presented, searching for the lesser damage in these alloys. These alloys are tested in a repeated impact testing machine that simulate its mechanical behaviour .The results show a good behaviour for hipoeutectic alloys with high relations of Cr/C and high

  13. The geomechanical characterization of the rocky mass foundation of the Tijuco Alto hydroelectric power plant, Ribeira River, Sao Paulo/Parana States, Brazil; Caracterizacao geomecanica do Macico de Fundacao da UHE Tijuco Alto (Rio Ribeira - SP/PR)

    Energy Technology Data Exchange (ETDEWEB)

    Figueiredo, Amarilis Lucia Casteli de

    1996-07-01

    This work has as its main objective the geomechanical characterization on the future rocky mass foundation of the Tijuco Alto dam, sited at the Ribeira river, in the cities of Ribeirao, Sao Paulo state and Adrianopolis, Parana state, Brazil, owned by the Companhia Brasileira de Aluminio (Brazilian company of Aluminium). To reach that target, field studies were made to qualify the geotechnical parameters of the rocky mass, in the axis area open galleries. It was also used in situ deformability and stress test results performed in those galleries, that were reinterpreted for a better adaptation of the mass values. The knowledge of the mass inherent characteristics together with the laboratories test results, allowed for the geomechanical classification applications in several different gallery sectors. The geomechanical data obtained allowed through mathematical expressions, to reach the rocky mass values correlations of interest to the work (deformability and strength), that could be compared to the in situ test results. That analysis permitted, besides the classification critical system evaluation, the geomechanical characterization of the rocky mass, focusing its ability to the dam arch construction. (author)

  14. Selection of sweet potato clones for the region Alto Vale do Jequitinhonha Seleção de clones de batata-doce para a região do Alto Vale do Jequitinhonha

    Directory of Open Access Journals (Sweden)

    Valter C de Andrade Júnior

    2009-09-01

    Full Text Available An experiment was carried out from December 2005 to July 2006, in the Universidade Federal dos Vales do Jequitinhonha e Mucuri (UFVJM, in Diamantina, Minas Gerais State, Brazil, aiming at selecting sweet potato clones for the Alto Vale do Jequitinhonha. We evaluated nine clones from the UFVJM germplasm bank, using cultivars Brazlândia Branca, Brazlândia Roxa, and Princesa as controls. The experimental design was blocks at random, with four replications. Plants were harvested seven months after transplanting. We assessed the fresh mass yield of vines and roots, as well as root shape and resistance to soil insects. Genotypes did not differ from each other for the fresh mass yield of vines (ranging from 3.81 to 11.76 t ha-1. The total yield of roots ranged from 22.0 to 45.4 t ha-1 and clones BD-06, BD-113-TO, BD-15, BD-38, BD-25, BD-61, and cultivar Princesa had statistically the highest figures. However, only clone BD-06 significantly overcame the control cultivars Brazlândia Branca and Brazlândia Roxa. Clone BD-06 had also the highest commercial yield of roots (38.58 t ha-1, statically similar to most of the other clones and cultivar Princesa (25.87 t ha-1, but superior to cultivars Brazlândia Branca and Brazlândia Roxa. Most of the clones tested, including clone BD-06, produced good shaped roots and were resistant to soil insects. Considering our results, clone BD-06 stood out as a good option for growing sweet potato in the Upper Valley of Jequitinhonha.Com o objetivo de selecionar clones de batata-doce para a região do alto Vale do Jequitinhonha, conduziu-se um experimento de dezembro de 2005 a julho de 2006, no CampusJK da Universidade Federal dos Vales do Jequitinhonha e Mucuri, UFVJM, município de Diamantina-MG. Foram avaliados nove clones de batata-doce pertencentes ao banco de germoplasma da UFVJM, juntamente com as cultivares Brazlândia Branca, Brazlândia Roxa e Princesa, utilizadas como testemunhas. O delineamento experimental

  15. 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

  16. Fast breeder reactor

    International Nuclear Information System (INIS)

    Ito, Shin-ichi; Maki, Koichi.

    1975-01-01

    Object: To conserve loaded fuel, aquire controllable surplus reaction degree, increase the breeding index, flatten output and improve sealing of neutrons by inserting a decelerating substance in a blanket section. Structure: A decelerating substance such as beryllium or beryllium oxide is inserted in a blanket section between an outer reactor core and reflector. With this arrangement, neutrons are decelerated to increase the low energy components, which are partly subjected to reflection by the outer reactor core to thereby reduce leakage of neutrons from the reactor core. (Kamimura, M.)

  17. 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

  18. 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)

  19. Reactor utilization, Part 1

    International Nuclear Information System (INIS)

    Martinc, R.; Stanic, A.

    1981-01-01

    The reactor operating plan for 1981 was subject to the needs of testing operation with the 80% enriched fuel and was fulfilled on the whole. This annex includes data about reactor operation, review of shorter interruptions due to demands of the experiments, data about safety shutdowns caused by power cuts. Period of operation at low power levels was used mostly for activation analyses, and the operation at higher power levels were used for testing and regular isotope production. Detailed data about samples activation are included as well as utilization of the reactor as neutron source and the operating plan for 1982 [sr

  20. 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