WorldWideScience

Sample records for alto lazio-2 reactor

  1. Embarazo de alto riesgo

    OpenAIRE

    Conde Agudelo, Afustín; Fundación Valle de Lili

    2001-01-01

    Factores de riesgo/ Identificación de la embarazada de alto riesgo/ Principales factores de riesgo/ Asociación entre algúnos factores de riesgo y aumento de la morbimortalidad materno-perinatal/ Asesoramiento preconcepcional/ Manejo del embarazo de alto riesgo.

  2. 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.)

  3. 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.)

  4. The radioactive beam facility ALTO

    International Nuclear Information System (INIS)

    Essabaa, Saïd; Barré-Boscher, Nicole; Cheikh Mhamed, Maher; Cottereau, Evelyne; Franchoo, Serge; Ibrahim, Fadi; Lau, Christophe; Roussière, Brigitte; Saïd, Abdelhakim; Tusseau-Nenez, Sandrine; Verney, David

    2013-01-01

    Highlights: • Research at the ALTO TNA-facility. • R and D on radioactive ion sources. • R and D on the lanthanide beam production by fluorination. • Recent developments on uranium carbide targets. -- Abstract: The Transnational Access facility ALTO (TNA07-ENSAR/FP7) has been commissioned and received from the French safety authorities, the operation license. It is allowed to run at nominal intensity to produce 10 11 fissions/s in a thick uranium carbide target by photo-fission using a 10 μA, 50 MeV electron beam. In addition the recent success in operating the selective laser ion source broadens the physics program with neutron-rich nuclear beams possible at this facility installed at IPN Orsay. The facility also aims at being a test bench for the SPIRAL2 project. In that framework an ambitious R and D program on the target ion source system is being developed

  5. 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.)

  6. Reactor

    International Nuclear Information System (INIS)

    Evans, R.M.

    1976-01-01

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

  7. Muffins con aceite de girasol alto estearico

    OpenAIRE

    González Procopio, Gimena

    2015-01-01

    Las enfermedades cardiovasculares constituyen una de las causas más importantes de discapacidad y muerte prematura en nuestro país y en todo el mundo, a su vez la modificación de los factores de riesgo puede reducir los episodios cardiovasculares y la muerte prematura tanto en las personas con enfermedad cardiovascular establecida como en aquellas con alto riesgo cardiovascular debido a uno o más factores de riesgo Objetivo: Identificar la variación en el perfil lipídico de una...

  8. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

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

  9. 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.

  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. 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

  12. PENSIONES DE ALTOS FUNCIONARIOS EN LA JURISPRUDENCIA CONSTITUCIONAL: SOSTENIBILIDAD FINANCIERA

    OpenAIRE

    Carlos Arturo Hernández Díaz; Javier Francisco Franco Mongua

    2014-01-01

    El régimen pensional de los altos funcionarios del Estado, considerado como especial, ha generado insostenibilidad financiera hasta antes del 2013. Tiempo en el que se adopta una visión más garantista de los derechos de igualdad, equidad, solidaridad y equilibrio financiero del sistema general de pensiones, típico de una posición del Análisis Económico del Derecho (AED). Entonces, el estudio de las decisiones jurisprudenciales respecto del sistema especial de pensiones de los altos funcionari...

  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. Open Spaces for Arts Education ‐ The ALTO Ecosystem

    NARCIS (Netherlands)

    Casey, John; Greller, Wolfgang; Davies, Hywel; Follows, Chris; Turner, Nancy; Webb-Ingall, Ed

    2012-01-01

    Casey, J., Greller, W., Davies, H., Follows, C., Turner, N., & Webb-­Ingall, E. (2011, 27-30 September). Open Spaces for Arts Education - The ALTO Ecosystem Model. Paper presentation of "Future Learning Spaces", at the 7th annual Designs on E-learning 2011 (DeoL) conference, Helsinki, Finland.

  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. Criterios para identificar patologías 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 características que determinan su comportamiento como pacientes de alto costo, para definir si dicha patología puede considerarse como Enfermedad de Alto Costo en Colombia.

  17. PENSIONES DE ALTOS FUNCIONARIOS EN LA JURISPRUDENCIA CONSTITUCIONAL: SOSTENIBILIDAD FINANCIERA

    Directory of Open Access Journals (Sweden)

    Carlos Arturo Hernández Díaz

    2014-01-01

    Full Text Available El régimen pensional de los altos funcionarios del Estado, considerado como especial, ha generado insostenibilidad financiera hasta antes del 2013. Tiempo en el que se adopta una visión más garantista de los derechos de igualdad, equidad, solidaridad y equilibrio financiero del sistema general de pensiones, típico de una posición del Análisis Económico del Derecho (AED. Entonces, el estudio de las decisiones jurisprudenciales respecto del sistema especial de pensiones de los altos funcionarios, en el marco de las herramientas económicas, es el claro ejemplo para decisiones posteriores que busquen la eficiencia jurídica y económica de los sistemas normativos.

  18. 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.......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 ... on the 3.5 m telescope at the Calar Alto observatory. The galaxies in DR1 already cover a wide range of properties in color-magnitude space, morphological type, stellar mass, and gas ionization conditions. This offers the potential to tackle a variety of open questions in galaxy evolution using spatially...

  19. 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.

  20. 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

  1. 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.

  2. 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

  3. 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

  4. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-09-01

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

  5. 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.)

  6. Reactor Neutrinos

    OpenAIRE

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

    2013-01-01

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

  7. BOILING REACTORS

    Science.gov (United States)

    Untermyer, S.

    1962-04-10

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

  8. Reactor vessel

    NARCIS (Netherlands)

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

    1999-01-01

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

  9. The Arctic Lower Troposphere Observed Structure (ALTOS) Campaign

    Energy Technology Data Exchange (ETDEWEB)

    Verlinde, J

    2010-10-18

    The ALTOS campaign focuses on operating a tethered observing system for routine in situ sampling of low-level (< 2 km) Arctic clouds. It has been a long-term hope to fly tethered systems at Barrow, Alaska, but it is clear that the Federal Aviation Administration (FAA) will not permit in-cloud tether systems at Barrow, even if unmanned aerial vehicle (UAV) operations are allowed in the future. We have provided the scientific rationale for long-term, routine in situ measurements of cloud and aerosol properties in the Arctic. The existing restricted air space at Oliktok offers an opportunity to do so.

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

    OpenAIRE

    Ainhoa Vásquez Mejías

    2016-01-01

    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-Chil...

  11. 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.)

  12. 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

  13. 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)

  14. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Nagatomi, Shozo.

    1976-01-01

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

  15. 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

  16. 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

  17. 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

  18. Obreras y empresarias en el Periodo Romano Alto Imperial

    Directory of Open Access Journals (Sweden)

    Pilar Fernández Uriel

    2011-01-01

    Full Text Available Análisis de la situación laboral y las diferentes medios y trabajos de las mujeres en el contexto de la Roma alto Imperial, frente a la situación mentalidad tradicional femenina a través de la documentación que proporcionan las fuentes históricas. Se contempla su relación con la sociedad, su ámbito doméstico e incluso la posible repercusión que pudiera existir en la cultura y mentalidad de este momento histórico.Analysis of the labor situation and the different ways and works of women in the context of high Imperial Rome, facing the situation traditionally minded women through the documentation provided by historical sources. It sees its relationship with society, its domestic and even the possible impact that might exist in the culture and mentality of this historical moment.

  19. 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

  20. 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...

  1. 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.

  2. 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)

  3. 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)

  4. 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)

  5. 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.

  6. 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

  7. 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

  8. SLOWPOKE reactor

    International Nuclear Information System (INIS)

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

    1974-01-01

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

  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. Evaluating Sustainability: Limits and Possibilities in Alto Douro Vinhateiro, Portugal

    Directory of Open Access Journals (Sweden)

    José Francisco Ferreira

    2013-12-01

    Full Text Available The Alto Douro Wine Region, located in North of Portugal, is one of the most important portuguese wine regions. In last decades, it has faced serious difficulties, common to many rural areas of the country and around the world. Problems such as aging and population loss, low economic, social and cultural density, low literacy, difficulties in the wine sector, poor associative movement, lack of common strategies among regional municipalities, and institutional difficulties, among others, affect its development and suggest that the region may not be managed in a sustainable way. Facing this scenario, a methodology to assess regional sustainability was developed. 76 indicators were used, grouped into 23 aspects and 5 dimensions. From this evaluation, a regional value was obtained which translates the regional situation relating to sustainable development. In a 0 to 100 scale, the region received a score of 57.14 points, showing that sustainability, if implemented as a regional strategy, could be highly benefic to regional improvement.

  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. Bird diversity and conservation of Alto Balsas (southwestern Puebla), Mexico.

    Science.gov (United States)

    Ramírez-Albores, Jorge E

    2007-03-01

    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.

  13. 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

  14. 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.

  15. 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.

  16. Reactor Neutrinos

    Directory of Open Access Journals (Sweden)

    Soo-Bong Kim

    2013-01-01

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

  17. 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.

  18. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

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

  19. Chemical Reactors.

    Science.gov (United States)

    Kenney, C. N.

    1980-01-01

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

  20. 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.)

  1. Propulsion reactors

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

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

  2. 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

  3. Agricultura familiar e programas de desenvolvimento rural no Alto Jequitinhonha

    Directory of Open Access Journals (Sweden)

    Eduardo Magalhães Ribeiro

    2007-12-01

    Full Text Available Os regimes agrários peculiares e os baixos níveis relativos dos indicadores sócio-econômicos fizeram com que a região do alto Jequitinhonha, nordeste de Minas Gerais, fosse considerada uma das mais complexas do Brasil. Por isso, vários governos orientaram para lá programas de desenvolvimento rural. Mas esses esforços não produziram bons resultados. Este artigo analisa as relações entre programas públicos e agricultura familiar, fazendo um balanço dos métodos e resultados das últimas três décadas. Conclui pela necessidade de incorporar as especificidades de história, ambientes e sociedade aos programas, que deveriam partir das experiências das organizações da região e se ajustar às ações e à cultura desses agricultores.The agrarian conditions and the low relative levels of the socioeconomic indicators cause the area of the "High Jequitinhonha Valley", in the northeast of the State of Minas Gerais, to be considered one of the most complex areas of Brazil. For this reason several governanmental administrations have recommended rural development programs. Most of these efforts, however, have not produced adequate results. This article analyzes the relationships between public programs and family farming, making a survey of the methods and results of the last three decades. It concludes that there is a need to incorporate the specificities of history, environment and culture into the rural programs. It is suggested that the programs take into consideration the experience accumulated by the regional organizations and be adjusted to the interest and culture of the local family producers.

  4. 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.

  5. 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.

  6. UMA NOVA ESPÉCIE DE SPASALUS (COLEOPTERA PASSALIDAE) DO ALTO RIO NEGRO. AMAZONAS, BRASIL.

    OpenAIRE

    Fonseca,Claudio Ruy Vasconcelos da

    1992-01-01

    Spasalus ellanae, uma nova eepécie PASSALIDAE (COLEOPTERA) alto rio Negro, Amazonas, Brasil, é descrita e ilustrada. Spasalus ellanae n. sp. from Negro river, Amazonas, Brazil, is described and illustrated.

  7. 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)

  8. Reactor utilization

    International Nuclear Information System (INIS)

    Zecevic, V.

    1963-01-01

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

  9. 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.

  10. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Araki, Takao; Saito, Yasushi.

    1987-01-01

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

  11. Demanding Change : The Collective Challenges of the Juntas Vecinales of El Alto

    OpenAIRE

    Tarazona Machicao, Mateo

    2010-01-01

    The Juntas Vecinales of El Alto portray a telling picture of the current process of societal change inBolivia. Formed to attend the collective needs of indigenous migrants striving to settle down on theoutskirts of the capital, the Juntas Vecinales have grown as an intrinsic part of El Alto becomingsignificant socio-political actors and part of the indigenous social movements propelling the processof change in Bolivia. Their traditional function of supervising public policy by pressuring serv...

  12. 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)

  13. 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.

  14. 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

  15. CAFE: Calar Alto Fiber-fed Echelle spectrograph

    Science.gov (United States)

    Sánchez, S. F.; Aceituno, J.; Thiele, U.; Grupp, F.; Dreizler, S.; Bean, J.; Benitez, D.

    2011-11-01

    The Calar Alto Fiber-fed Echelle spectrograph (CAFE) is an instrument underconstruction at CAHA to replace FOCES, the high-resolution echellespectrograph at the 2.2 m telescope of the observatory. FOCES is a property ofthe Observatory of the Munich University, and it was recalled it from Calar Altoin 2009. The instrument comprised a substantial fraction of thetelescope time during its operational life-time, and it is due to that it wastaken the decision to build a replacement.CAFE shares its basic characteristics with those of FOCES. However, significantimprovements have been introduced in the original design, the quality of thematerials, and the overall stability of the system. In particular: (i) a newcalibration Iodine cell is foreseen to operate together with the standard ThArlamps; (ii) the optical quality of all the components has been selected to belambda/20, instead of the original lambda/10; (iii) an isolated room hasbeen selected to place the instrument, termalized and stabilized againstvibrations (extensive tests have been performed to grant the stability); (iv)most of the mobile parts in FOCES has been substituted by fixed elements, toincrease the stability of the system; and finally (v) a new more efficientCCD, with a smaller pixel has been acquired. It is expected that the overallefficiency and the quality of the data will be significantly improved withrespect to its precesor. In particular, CAFE is design and built to achieveresolutions of R ˜ 70000, which will be kept in the final acquired data,allowing it to compete with current operational extrasolar planets hunters.After two years of work all the components are in place. The instrument is nowfinally assembled, and we are performing the the first alignment tests. It isexpected that the commissioning on the laboratory will finish at the end of2010, followed by the commissioning on telescope along the first semester of2011. If everything goes well, we will offer the instrument in a shared

  16. 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.

  17. 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)

  18. 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

  19. 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

  20. 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

  1. Neutronic reactor

    International Nuclear Information System (INIS)

    Carleton, J.T.

    1977-01-01

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

  2. 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.)

  3. 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.

  4. 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

  5. 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

  6. Reactor container

    International Nuclear Information System (INIS)

    Otsuka, Hiroaki; Yoshida, Takashi.

    1979-01-01

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

  7. 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.)

  8. 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.)

  9. 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

  10. 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.)

  11. 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.)

  12. 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

  13. 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

  14. Pilates como complemento del entrenamiento en fútbol de alto rendimiento

    OpenAIRE

    Olmo Cárceles, Natalia del

    2015-01-01

    Editar registro: Hoy en día existen muchos métodos distintos de entrenamiento que inciden en todas las cualidades físicas. El método Pilates es uno de ellos, y a pesar de sus múltiples beneficios, es un entrenamiento que no se ha incorporado en los clubes de alto rendimiento como complemento del entrenamiento. En este trabajo realizo una reflexión sobre las características y los beneficios que aporta este método. Su posible aplicación en el entrenamiento de fútbol de alto rendimiento, tanto c...

  15. Compromiso intestinal por quemadura eléctrica de alto voltaje: caso clínico

    OpenAIRE

    C. Arriagada; C. Soto; V. Peña; J. Villegas

    2013-01-01

    Las quemaduras son una de las causas más importantes de discapacidad y mortalidad en todo el mundo. En las producidas por electricidad de alto voltaje, las manifestaciones sistémicas más frecuentes son la insuficiencia renal y las arritmias. La lesión visceral secundaria a una quemadura eléctrica es infrecuente y su tratamiento quirúrgico constituye un desafío. En este artículo presentamos el caso clínico de un paciente con quemadura eléctrica de alto voltaje con compromiso de la pared abdomi...

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

    OpenAIRE

    Antonio Miranda; Sergio Franco; William Uribe; Mauricio Duque; Francisco Femenía; Adrián Baranchuk

    2012-01-01

    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 permea...

  17. Photocatalytic reactor

    Science.gov (United States)

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

    1999-01-01

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

  18. 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

  19. D and DR Reactors

    Data.gov (United States)

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

  20. 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.)

  1. 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.

  2. 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.)

  3. Reactor container

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-09-07

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

  4. 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.)

  5. 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…

  6. Altos ingresos e impuesto de renta en Colombia, 1993-2010

    Directory of Open Access Journals (Sweden)

    Facundo Alvaredo

    2014-12-01

    Full Text Available Este artículo presenta las series de participación del ingreso de los niveles superiores de la distribución en Colombia entre 1993 y 2010, basadas en datos del impuesto de renta personal. Se obtienen cuatro resultados empíricos principales: 1 el ingreso está altamente concentrado: el 1% más alto captó más del 20% de ingreso total en 2010, el mayor nivel de desigualdad en cualquier año reciente de la muestra WTID; 2 los individuos de altos ingresos son, en esencia, rentistas y propietarios de capital; 3 mientras que las encuestas de hogares muestran que la desigualdad ha disminuido desde 2006, los resultados basados en impuestos muestran que la concentración en la parte superior se ha mantenido estable; cuando los coeficientes de Gini de las encuestas se ajustan para tener en cuenta los ingresos más altos reportados en la declaración de impuestos, la desigualdad es más alta y la reducción de la desigualdad es menos pronunciada; 4 el impuesto de renta poco reduce el alto nivel de desigualdad.

  7. 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. 

  8. 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.

  9. 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

  10. CALIFA, the Calar Alto Legacy Integral Field Area survey. III. Second public data release

    NARCIS (Netherlands)

    García-Benito, R.; Zibetti, S.; Sánchez, S. F.; Husemann, B.; de Amorim, A. L.; Castillo-Morales, A.; Cid Fernandes, R.; Ellis, S. C.; Falcón-Barroso, J.; Galbany, L.; Gil de Paz, A.; González Delgado, R. M.; Lacerda, E. A. D.; López-Fernandez, R.; de Lorenzo-Cáceres, A.; Lyubenova, M.; Marino, R. A.; Mast, D.; Mendoza, M. A.; Pérez, E.; Vale Asari, N.; Aguerri, J. A. L.; Ascasibar, Y.; Bekerait*error*ė, S.; Bland-Hawthorn, J.; Barrera-Ballesteros, J. K.; Bomans, D. J.; Cano-Díaz, M.; Catalán-Torrecilla, C.; Cortijo, C.; Delgado-Inglada, G.; Demleitner, M.; Dettmar, R.-J.; Díaz, A. I.; Florido, E.; Gallazzi, A.; García-Lorenzo, B.; Gomes, J. M.; Holmes, L.; Iglesias-Páramo, J.; Jahnke, K.; Kalinova, V.; Kehrig, C.; Kennicutt, R. C.; López-Sánchez, Á. R.; Márquez, I.; Masegosa, J.; Meidt, S. E.; Mendez-Abreu, J.; Mollá, M.; Monreal-Ibero, A.; Morisset, C.; del Olmo, A.; Papaderos, P.; Pérez, I.; Quirrenbach, A.; Rosales-Ortega, F. F.; Roth, M. M.; Ruiz-Lara, T.; Sánchez-Blázquez, P.; Sánchez-Menguiano, L.; Singh, R.; Spekkens, K.; Stanishev, V.; Torres-Papaqui, J. P.; van de Ven, G.; Vilchez, J. M.; Walcher, C. J.; Wild, V.; Wisotzki, L.; Ziegler, B.; Alves, J.; Barrado, D.; Quintana, J. M.; Aceituno, J.

    This paper describes the Second Public Data Release (DR2) of the Calar Alto Legacy Integral Field Area (CALIFA) survey. The data for 200 objects are made public, including the 100 galaxies of the First Public Data Release (DR1). Data were obtained with the integral-field spectrograph PMAS/PPak

  11. CALIFA, the Calar Alto Legacy Integral Field Area survey : II. First public data release

    NARCIS (Netherlands)

    Husemann, B.; Jahnke, K.; Sanchez, S. F.; Barrado, D.; Bekeraite, S.; Bomans, D. J.; Castillo-Morales, A.; Catalan-Torrecilla, C.; Cid Fernandes, R.; Falcon-Barroso, J.; Garcia-Benito, R.; Gonzalez Delgado, R. M.; Iglesias-Paramo, J.; Johnson, B. D.; Kupko, D.; Lopez-Fernandez, R.; Lyubenova, M.; Marino, R. A.; Mast, D.; Miskolczi, A.; Monreal-Ibero, A.; Gil de Paz, A.; Perez, E.; Perez, I.; Rosales-Ortega, F. F.; Ruiz-Lara, T.; Schilling, U.; van de Ven, G.; Walcher, J.; Alves, J.; de Amorim, A. L.; Backsmann, N.; Barrera-Ballesteros, J. K.; Bland-Hawthorn, J.; Cortijo, C.; Dettmar, R. -J.; Demleitner, M.; Diaz, A. I.; Enke, H.; Florido, E.; Flores, H.; Galbany, L.; Gallazzi, A.; Garcia-Lorenzo, B.; Gomes, J. M.; Gruel, N.; Haines, T.; Holmes, L.; Jungwiert, B.; Kalinova, V.; Kehrig, C.; Kennicutt, R. C.; Klar, J.; Lehnert, M. D.; Lopez-Sanchez, A. R.; de Lorenzo-Caceres, A.; Marmol-Queralto, E.; Marquez, I.; Mendez-Abreu, J.; Molla, M.; del Olmo, A.; Meidt, S. E.; Papaderos, P.; Puschnig, J.; Quirrenbach, A.; Roth, M. M.; Sanchez-Blazquez, P.; Spekkens, K.; Singh, R.; Stanishev, V.; Trager, S. C.; Vilchez, J. M.; Wild, V.; Wisotzki, L.; Zibetti, S.; Ziegler, B.

    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

  12. CALIFA, the Calar Alto Legacy Integral Field Area survey. II. First public data release

    NARCIS (Netherlands)

    Husemann, B.; Jahnke, K.; Sánchez, S. F.; Barrado, D.; Bekerait*error*ė, S.; Bomans, D. J.; Castillo-Morales, A.; Catalán-Torrecilla, C.; Cid Fernandes, R.; Falcón-Barroso, J.; García-Benito, R.; González Delgado, R. M.; Iglesias-Páramo, J.; Johnson, B. D.; Kupko, D.; López-Fernandez, R.; Lyubenova, M.; Marino, R. A.; Mast, D.; Miskolczi, A.; Monreal-Ibero, A.; Gil de Paz, A.; Pérez, E.; Pérez, I.; Rosales-Ortega, F. F.; Ruiz-Lara, T.; Schilling, U.; van de Ven, G.; Walcher, J.; Alves, J.; de Amorim, A. L.; Backsmann, N.; Barrera-Ballesteros, J. K.; Bland-Hawthorn, J.; Cortijo, C.; Dettmar, R.-J.; Demleitner, M.; Díaz, A. I.; Enke, H.; Florido, E.; Flores, H.; Galbany, L.; Gallazzi, A.; García-Lorenzo, B.; Gomes, J. M.; Gruel, N.; Haines, T.; Holmes, L.; Jungwiert, B.; Kalinova, V.; Kehrig, C.; Kennicutt, R. C.; Klar, J.; Lehnert, M. D.; López-Sánchez, Á. R.; de Lorenzo-Cáceres, A.; Mármol-Queraltó, E.; Márquez, I.; Mendez-Abreu, J.; Mollá, M.; del Olmo, A.; Meidt, S. E.; Papaderos, P.; Puschnig, J.; Quirrenbach, A.; Roth, M. M.; Sánchez-Blázquez, P.; Spekkens, K.; Singh, R.; Stanishev, V.; Trager, S. C.; Vilchez, J. M.; Wild, V.; Wisotzki, L.; Zibetti, S.; Ziegler, B.

    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

  13. 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

  14. NEUTRONIC REACTOR

    Science.gov (United States)

    McGarry, R.J.

    1958-04-22

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

  15. 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

  16. 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.

  17. PERFIL ACTUAL DEL AGRICULTOR ECOLÓGICO EN LA COMARCA DEL ALTO GUADALENTÍN (MURCIA

    Directory of Open Access Journals (Sweden)

    A.B. Pérez

    2008-01-01

    Full Text Available Dentro de la Comunidad de Murcia, la Comarca del Alto Guadalentín representa el 7,01% del total de la superficie murciana dedicada a agricultura ecológica. En este trabajo se analiza el perfil del agricultor ecológico en la Comarca del Alto Guadalentín para ello se realizaron encuestas al 74,03% de los agricultores de la zona, según los datos obtenidos del Consejo Agricultura Ecológica de la Región de Murcia. Los resultados obtenidos revelan que casi el 50% de los agricultores de la Comarca del Alto Guadalentín se inició como agricultor ecológico mediante un cambio del sistema de agricultura convencional hacia la agricultura ecológica, siendo el factor económico con casi el 57% uno de los principales motivos para pasar de un tipo de agricultura a otro. Por otro lado, el mayor porcentaje de los agricultores ecológicos del Alto Guadalentín (35% se encuentran en un intervalo de edad entre 46 y 55 años. El 28% tienen entre 36 y 45 años y casi el 25% tienen una edad superior a 56 años. Solamente el 12,28% de los agricultores de la Comarca tienen edades inferiores a los 36 años. El 87% de los agricultores del Alto Guadalentín no pertenecen a ningún tipo de asociación.

  18. 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.

  19. 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)

  20. Survey of research reactors

    International Nuclear Information System (INIS)

    Boek, H.; Villa, M.

    2004-06-01

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

  1. 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.)

  2. 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

  3. Determining Reactor Neutrino Flux

    OpenAIRE

    Cao, Jun

    2011-01-01

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

  4. 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.)

  5. 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

  6. Reactor container

    International Nuclear Information System (INIS)

    Kagawa, Tatsuo; Yanai, Ryoichi.

    1976-01-01

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

  7. 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.

  8. 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

  9. Compromiso intestinal por quemadura eléctrica de alto voltaje: caso clínico

    Directory of Open Access Journals (Sweden)

    C. Arriagada

    2013-12-01

    Full Text Available Las quemaduras son una de las causas más importantes de discapacidad y mortalidad en todo el mundo. En las producidas por electricidad de alto voltaje, las manifestaciones sistémicas más frecuentes son la insuficiencia renal y las arritmias. La lesión visceral secundaria a una quemadura eléctrica es infrecuente y su tratamiento quirúrgico constituye un desafío. En este artículo presentamos el caso clínico de un paciente con quemadura eléctrica de alto voltaje con compromiso de la pared abdominal y lesión intestinal secundaria.

  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. 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.

  13. 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.

  14. 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)

  15. Geografia Rural das Novas Colônias do Alto Uruguai

    Directory of Open Access Journals (Sweden)

    Raymond Pébayle

    2014-05-01

    Full Text Available Versa sobre a geografia rural das Novas Colônis do Alto Uruguai. Artigo publicado no Boulletin de L'Association de Géographes Français nº 350-351, janeiro-fevereiro de 1967. Artigo dividido em: Paisagens rurais e sistemas de cultura; Uma sociedade rural em crise; O pêso de um isolamento. Trad.: Gilberto Lazare Rocha

  16. 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

  17. 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)

  18. 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

  19. 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.

  20. 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

  1. Research reactor instrumentation

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2001-02-01

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

  2. 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

  3. 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.

  4. 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.)

  5. 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

  6. Reactor shutdown method

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  7. 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

  8. 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

  9. 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)

  10. 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)

  11. 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.)

  12. 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)

  13. 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.)

  14. 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.)

  15. The Jules Horowitz reactor

    International Nuclear Information System (INIS)

    2003-01-01

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

  16. Thorium fueled reactor

    Science.gov (United States)

    Sipaun, S.

    2017-01-01

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

  17. 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

  18. 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

  19. 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)

  20. 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.

  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. 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

  3. Spinning fluids reactor

    Science.gov (United States)

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

    2012-11-20

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

  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. 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.)

  6. 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.)

  7. 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.

  8. 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.

  9. 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....

  10. Coleoptera Scarabaeidae em corredores ecológicos na eucaliptocultura do Alto Vale do Jequitinhonha

    OpenAIRE

    Ferreira, Caroline Conrado

    2015-01-01

    Foram utilizadas espécies de Coleoptera Scarabaeidae como bioindicadores para avaliar a efetividade de faixas de vegetação em recomposição como corredores ecológicos entremeados a plantios comerciais de eucalipto. O estudo foi desenvolvido em cinco municípios do Alto Vale do Jequitinhonha, Minas Gerais. Comparou-se a estimativa da diversidade de espécies, relacionando os diferentes tipos de isca utilizados e os ecossistemas. A amostragem foi realizada em seis tipologias: regeneração inicial e...

  11. Liderar equipos de alto desempeño: un gran reto para las organizaciones actuales

    OpenAIRE

    Uribe R., Ana Fernanda; Molina L., Juan Máximo; Contreras, Francoise; Barbosa-Ramirez, David-Hernando; Espinosa, Juan C

    2013-01-01

    Los continuos e impredecibles cambios que deben afrontar las organizaciones en la actualidad les exigen asumir retos cada vez más complejos que les garanticen resultados para sobrevivir en un mercado altamente competitivo. Tal condición requiere de directivos que optimicen sus habilidades para liderar equipos, considerando unas características que antes parecían irrelevantes. El propósito de éste estudio es delimitar conceptualmente el liderazgo en relación con los equipos de alto desempeño y...

  12. 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...

  13. Aceite de semilla de girasol con alto contenido en δ-tocoferol

    OpenAIRE

    Velasco Varo, Leonardo; Fernández Martínez, José María

    2006-01-01

    Aceite de semilla de girasol con alto contenido en δ-tocoferol. La presente invención se refiere a un aceite de semillas de girasol modificadas genéticamente a través de dos ciclos de inducción artificial de mutaciones seguidos en cada caso por procesos de identificación de individuos mutantes que poseen el carácter deseado. Dicho aceite se caracteriza por poseer entre el 26% y el 80% de los tocoferoles en forma de delta-tocoferol. Esta elevada producción de delta-tocoferol está determinada p...

  14. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

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

  15. Neutron fluxes in test reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-01-01

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

  16. 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)

  17. Agroclimatic zoning of peanut plants for the Bacia do Alto Paraguai, Mato Grosso State, Brazil

    Directory of Open Access Journals (Sweden)

    João Danilo Barbieri

    2015-06-01

    Full Text Available Agroclimatic zoning of peanut plants for the Bacia do Alto Paraguai, Mato Grosso State, Brazil The success of a technified, productive and sustainable agriculture is achieved through the knowledge on climate and soil of a place, combined with their appropriate management. This study aimed to determine the agroclimatic zoning of peanut plants for the Bacia do Alto Paraguai, Mato Grosso State, Brazil, by identifying the cities with aptitude for exploring this crop and establishing the times for its sowing. Soil and climate conditions were evaluated for the region, respecting the cycle (90-120 days and water demands (400-600 mm of the crop. The water storage capacity (WSC and water requirement satisfaction index (WRSI were determined for the types of soil classified according to the clay content. It was possible to conclude that all cities that cultivate peanut plants have more than 50 % of WSC 75 soil type with more than 35 % of clay (Arenápolis, Barra do Bugres, Indiavaí, Lambarí D’Oeste, Nova Olímpia, Rondonópolis, São José dos Quatro Marcos and Tangará da Serra. Such soil favors a late cultivation, which can be performed up to the 7th ten-days period. For the WSC 30 soil type, with less than 15 % of clay, the cultivation should only start from the 6th ten-days period, due to its low water absorption capacity.

  18. Characterization of tabique walls nails of the Alto Douro Wine Region

    Science.gov (United States)

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

    2016-11-01

    Tabique is one of the main Portuguese traditional building techniques which use raw materials as stone, earth andwood. In general, a tabique building component as a wall consist of a wooden structure made up of vertical boards connected to laths by metal nails and covered on both sides by an earth based material. This traditional building technology as an expressive incidence in the Alto Douro Wine Region located in the interior of Northern Portugal, added to the UNESCO's Word Heritage Sites List in December 2001 as an `evolved continuing cultural landscape'. Furthermore, previous research works have shown that the existing tabique construction, in this region, reveals a certain lack of maintenance partially justified by the knowledge loosed on that technique, consequently this construction technique present an advanced stage of deterioration. This aspect associated to the fact that there is still a lack of scientific studies in this field motivated the writing of this paper, the main objectives are to identify and characterize the nails used in the timber connections. The nails samples were collected from tabique walls included in tabique buildings located in LamegoMunicipality, near Douro River, in the Alto Douro Wine Region. This work also intends to give guidelines to the rehabilitation and preservation of this important legacy.

  19. 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.

  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. Liderar equipos de alto desempeño: un gran reto para las organizaciones actuales.

    Directory of Open Access Journals (Sweden)

    Ana Fernanda Uribe R.

    2013-12-01

    Full Text Available Los continuos e impredecibles cambios que deben afrontar las organizaciones en la actualidad les exigen asumir retos cada vez más complejos que les garanticen resultados para sobrevivir en un mercado altamente competitivo. Tal condición requiere de directivos que optimicen sus habilidades para liderar equipos, considerando unas características que antes parecían irrelevantes. El propósito de éste estudio es delimitar conceptualmente el liderazgo en relación con los equipos de alto desempeño y discutir entorno al rol que este debe tener en su conformación y mantenimiento. Se puntualiza sobre la necesidad de que el líder se convierta en un facilitador para la transformación no solo de las personas que componen los equipos, sino dela organización, a través de desarrollo y crecimiento. Se plantea la necesidad de incluir en los procesos de dirección exitosa de equipos de alto desempeño factores como la estrategia organizacional, la gestión humana y la estructura organizacional, todos ellos permeados necesariamente por los estilos de liderazgo y la actitud del líder hacia el cambio.

  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. 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.

  4. ALTO RIESGO DE CONSUMO DE ALCOHOL EN TRABAJADORES DE ATENCIÓN PRIMARIA DE SALUD, LORETO, PERÚ, 2011

    Directory of Open Access Journals (Sweden)

    Henry Zagaceta Camiñas

    2012-06-01

    Full Text Available El consumo de alcohol de alto riesgo o dependencia puede afectar la salud y el desempeño profesional. Los trabajadores de la atención primaria de salud (TAPS son clave en la referencia, prevención y tratamiento de las consecuencias de este consumo. Sin embargo, existe poca evidencia sobre el nivel de consumo de alcohol en TAPS. La investigación fue de tipo transversal, aleatorizado por conveniencia. 150 TAPS (médicos, enfermeras y obstetras de 3 centros de salud primarios fueron reclutados y se les aplicó el Cuestionario de Identificación de los Trastornos debidos al Consumo de Alcohol (AUDIT. Los TAPS de los tres centros estudiados, presentaron un alto porcentaje de bebedores en alto riesgo (40%-46%, al menos 50% de bebedores de alto riesgo fueron de sexo masculino y en grupos de edad correspondiente al rango de 31 a 40 años (56.3%. El porcentaje de bebedores con dependencia encontrado en este estudio es mayor a lo encontrado en otros estudios nacionales que incluían Loreto. El alto riesgo de consumo de alcohol podría ser un problema laboral aun no evaluado en salud que necesita futura investigación.

  5. 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

  6. Hybrid reactors. [Fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Moir, R.W.

    1980-09-09

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

  7. 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...

  8. 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

  9. 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)

  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. 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

  12. 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.)

  13. 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)

  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 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

  16. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

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

  17. 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)

  18. 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

  19. 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

  20. 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

  1. 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.

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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.)

  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. 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

  9. Primera cita de la especie Goniozus legneri (Hymenoptera: Bethylidae en el Alto Valle de Río Negro, Patagonia Argentina First record of the species Goniozus legneri Gordh in the Alto Valle de Río Negro, Patagonia, Argentina

    Directory of Open Access Journals (Sweden)

    Silvina Garrido

    2005-07-01

    Full Text Available Se reporta por primera vez para la zona del Alto Valle de Río Negro, a Goniozus legneri Gordh, parasitando naturalmente larvas de Cydia pomonella (L, "carpocapsa", en montes comerciales de manzanos y nogales. Se comentan brevemente su hallazgo, características morfológicas, distribución, biología e influencia en las poblaciones de "carpocapsa".First record of Goniozus legneri Gordh, parasitizing larva of Cydia pomonella (L, "codlingh moth", in apple and walnut orchard from the Alto Valle de Río Negro. Discover, morphology, distribution, biology, and influence on the "codling moth" population are briefly commented.

  10. 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

  11. Reactor core monitor for nuclear reactor

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

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

  12. 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

  13. 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

  14. 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.

  15. 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

  16. Implantación de prácticas de recursos humanos en empresas manufactureras de alto rendimiento

    OpenAIRE

    Goñi Villegas, Iñaki

    2010-01-01

    Este proyecto aborda la posible implantación de prácticas de recursos humanos en empresas manufactureras denominadas de alto rendimiento (HPM, High Performance Manufacturing), mediante el estudio empírico de una encuesta realizada a 266 empresas de 9 países del mundo. El trabajo se enmarca en el proyecto “HPM Project-Spain: proyecto para la manufactura de alto rendimiento (High Performance Manufacturing)”, financiado por el Ministerio de Educación y Ciencia del Gobierno de España....

  17. 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...

  18. Procedimiento para obtener un producto prebiótico de alto contenido en fibra soluble, dicho producto y sus aplicaciones

    OpenAIRE

    Rupérez Antón, Pilar; Mateos-Aparicio, Inmaculada

    2008-01-01

    Procedimiento para obtener un producto prebiótico de alto contenido en fibra soluble, dicho producto y sus aplicaciones. La presente invención describe un procedimiento para obtener un producto prebiótico de alto contenido en fibra soluble a partir del uso de fibra insoluble proveniente de residuos vegetales y de la aplicación de altas presiones. Así sus aplicaciones son como suplemento dietético natural rico en fibra en alimentos utilizándose a residuos de soja, subpr...

  19. Comportamientos sexuales de un grupo de hombres de alto riesgo que tienen sexo con hombres en Lima - Perú.

    OpenAIRE

    Díaz Gervasi, Giovani Martín; Programa de Doctorado en Psicología. Facultad de Psicología de la Universidad Peruana Cayetano Heredia.

    2015-01-01

    El presente estudio buscó identificar los comportamientos, las características psicosexuales de riesgo y sociodemográficas en un grupo de hombres de alto riesgo que tuvieron sexo con hombres (HARSH) en Lima. La muestra estuvo conformada por 254 HSH y el muestreo aplicado fue no probabilístico. Se empleó una basede datos secundarios del estudio: “Prevalencia, Incidencia de VIH y prevalencia de infección por VHS-2, en una población de Hombres que tienen sexo con Hombres (HSH) de alto riesgo en ...

  20. Autoestima y refuerzo en estudiantes de 5º básico de una escuela de alto riesgo

    OpenAIRE

    Ramírez Peradotto, Pedro; Duarte Vargas, Juan; Muñoz Valdivia, Roxina

    2005-01-01

    Este artículo describe los resultados de una investigación cuasi experimental, de grupo experimental y control con pretest – postest, que tuvo como propósito probar un tratamiento basado en un programa de refuerzo de intervalo variable, cuya finalidad era modificar la autoestima escolar de niños entre 10 y 11 años, definidos como de “alto riesgo” por presentar altos índices de repetición de cursos, ausentismo y deserción, que son alumnos de la escuela La Bandera, E-97,...

  1. 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.

  2. Integrando capacidades de alto nivel en la toma de decisiones de agentes inteligentes

    OpenAIRE

    Errecalde, Marcelo Luis; Aguirre, Guillermo; Ferretti, Edgardo; Schlesinger, Federico

    2009-01-01

    Este artículo describe, en forma resumida, los trabajos de investigación y desarrollo que se están llevando a cabo en la línea “Agentes y Sistemas Inteligentes” del LIDIC, en el área de agentes cognitivos. A diferencia de otras líneas de investigación del LIDIC, que se centran en problemas de optimización y el uso de enfoques de soft computing, nuestra línea se centra en la formalización, diseño y desarrollo de agentes computacionales con capacidades cognitivas de alto nivel, y en especial en...

  3. 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.

  4. Desarrollo rural y deterioro del bosque. Región interestatal del Alto Lerma

    Directory of Open Access Journals (Sweden)

    María Estela Orozco-Hernández

    2009-01-01

    Full Text Available Esta investigación analiza las condiciones naturales y socioeconómicas de la región interestatal Alto Lerma, mediante una evaluación diagnóstica de las fortalezas, oportunidades, debilidades y amenazas que afectan la utilización de las áreas que corresponden a bosques templados. Se aportan elementos para repensar las formas de intervención y apropiación de los recursos forestales y se proponen estrategias para la atención social y ambiental de las comunidades rurales. Se analizó información cartográfica, estadística y documental, así como la obtenida por medio de entrevistas proporcionadas por funcionarios públicos.

  5. Nutrient content of earthworms consumed by Ye'Kuana Amerindians of the Alto Orinoco of Venezuela.

    Science.gov (United States)

    Paoletti, M G; Buscardo, E; VanderJagt, D J; Pastuszyn, A; Pizzoferrato, L; Huang, Y-S; Chuang, L-T; Millson, M; Cerda, H; Torres, F; Glew, R H

    2003-02-07

    For the Makiritare (Ye'Kuana) native people of the Alto Orinoco (Venezuela), earthworms (Anellida: Glossoscolecidae) are an important component of the diet. Two species in particular are widely consumed: 'kuru' (Andiorrhinus kuru n. sp.) and 'motto' (Andiorrhinus motto). We analysed eviscerated kuru body proper, and whole and smoked preparations of motto for their content of protein and amino acids, fatty acids and 20 minerals and trace elements. The samples contained large amounts of protein (64.5-72.9% of dry weight), essential amino acids, calcium and iron together with notable quantities of other important elements, indicating that these earthworms contain potentially useful quantities of many nutrients that are critical to the health of the humans who consume them.

  6. Structure of the neutron rich Ga and Ge isotopes observed at ALTO

    International Nuclear Information System (INIS)

    Verney, D.; Lebois, M.; Ibrahim, F.

    2009-01-01

    During test runs dedicated to the commissioning of ALTO (Accelerateur Lineaire et Tandem a Orsay), β and β-n decay of the very neutron rich 31 84 Ga 53 could be observed at the tape station installed on-line with the PARRNe mass-separator. γ-lines observed in the resulting spectra and a careful analysis of the balance of their relative intensities point toward the existence of two β-decaying states in 84 Ga. The decay of these long-lived states appear to feed the 2 1 + and 4 1 + excited states of 32 84 Ge 52 and the 1/2 1 + state in 32 83 Ge 51 allowing a significant improvement of the knowledge on nuclear structure in the immediate vicinity of 78 Ni. (author)

  7. Sistema de calefacción solar para reducir el friaje en viviendas alto andinas

    OpenAIRE

    Espinoza Montes, Ciro Abelardo

    2013-01-01

    La investigación que se realizó es tecnológico y nivel aplicado. Se encuentra dentro de la línea investigación de Energía Solar, con él se pretendió determinar la configuración del Sistema de calefacción solar que influye eficientemente en reducir el friaje en viviendas alto andinas. Para lo cual se diseñó, construyó e instaló Sistemas de Calefacción Solar en los distritos ubicados entre 3600 m.s.n.m. y 4000 m.s.n.m. de las provincias de Chupaca y Concepción de la Región Junín, Perú. Se utili...

  8. 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.

  9. Technical specifications, Hanford production reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gilbert, W.D. [comp.

    1962-06-25

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

  10. 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.)

  11. 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

  12. 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)

  13. CAREM 25 nuclear reactor

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  14. 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.)

  15. 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

  16. 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.)

  17. Advanced converter reactors

    International Nuclear Information System (INIS)

    Kasten, P.R.

    1979-01-01

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

  18. 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)

  19. 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.

  20. 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

  1. Nuclear reactor instrumentation method

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  2. 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

  3. 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

  4. Assistência prestada à adolescente no momento do parto em uma maternidade de alto risco

    Directory of Open Access Journals (Sweden)

    Márcia Juliana Mello da Silva

    2015-03-01

    Full Text Available Objetivo: Analisar as práticas obstétricas realizadas em adolescentes parturientes atendidas em uma maternidade de alto risco. Métodos: Estudo observacional, de corte transversal, documental e descritivo, realizado com busca em 157 prontuários de parturientes adolescentes atendidas em maternidade de alto risco em Maceió-AL, no período de janeiro a junho/2013. Avaliaram-se variáveis socioeconômicas, práticas obstétricas e clínica, sendo os resultados apresentados em frequência simples. Resultados: Entre as parturientes, a idade variou de 14 a 19 anos, e 96 (61,1% viviam em união estável. Com relação aos dados obstétricos, 125 (79,6% eram primigestas e 73 realizaram de 4 a 6 consultas de pré-natal. Em 107 (68,1% prontuários o partograma não foi encontrado. Entre os partos realizados, em 75 (47,8% os profissionais não realizaram episiotomia, em 110 (70,1% foram realizadas manobras ativas do 3º estágio e 146 (86,6% adolescentes não tiveram complicações clínicas no parto. Conclusão: Evidenciou-se que algumas práticas obstétricas preconizadas pelo Ministério da Saúde estão sendo realizadas com as parturientes adolescentes, mas não são suficientes para uma assistência de qualidade.

  5. Situación estimada de la zona cohesiva en el horno alto

    Directory of Open Access Journals (Sweden)

    Cores, A.

    2010-08-01

    Full Text Available A series of sinters are manufactured in the pilot plant, using a mineral mixture, like that blast furnace. The sinters are characterised, by chemical and granulometric analysis and by determining the softening and melting temperatures. In the blast furnace temperatures are determined by using a series of probes in the furnace which make it possible to locate the position of the isotherm of higher temperature of 950°C, which correspond to the reserve thermic zone. A model has been developed, proposing and indirect estimation of the shape of the cohesive zone through the determination of the isotherm with the highest temperature in the thermic reserve zone. The values of the softening and melting temperatures of sinters can be used to estimate the isotherms limiting the cohesive zone in the 1300-1400 °C range.

    En planta piloto se fabrica una serie de sinterizados a partir de mezclas minerales como las utilizadas en el horno alto. Se caracterizan los sinterizados mediante análisis químico y granulométrico y determinación de las temperaturas de reblandecimiento y fusión. En el horno alto, mediante una serie de sondas, se determinan las temperaturas en el horno, lo que permite situar la posición de la isoterma de mayor temperatura de 950 °C, que corresponde a la zona de reserva térmica. Se ha desarrollado un modelo que propone una estimación indirecta de la forma de la zona cohesiva a través de la determinación de la isoterma de mayor temperatura de la zona de reserva térmica. Los valores de las temperaturas de reblandecimiento y fusión de los sinterizados permiten estimar las isotermas que limitan la zona cohesiva, en el intervalo de 1.300-1.400 °C.

  6. El desarrollo del turismo en el Parque Natural del Alto Tajo

    Directory of Open Access Journals (Sweden)

    Antonio Mora Sánchez

    2001-01-01

    Full Text Available Este artículo analiza el espacio geográfico delimitado por el Parque Natural del Alto Tajo, buscando métodos y sistemas cuya implantación permitan un desarrollo de la zona desde el punto de vista turístico y que, por otro lado, asegure la compatibilidad de las medidas de desarrollo que se emprendan con las exigencias y ventajas que supone el área geográfica del espacio natural del Alto Tajo. Con objeto de establecer las bases que permitan comprender las posibilidades de desarrollo turístico y las propuestas que para ello se realizan, el estudio aborda un análisis del turismo rural, tendencias actuales, implicaciones, condicionantes y motivaciones. Asimismo, se analizan experiencias de desarrollo turístico en zonas rurales de otras regiones de España, Taramundi y Serranía de Ronda, como experiencias equivalentes de desarrollo turístico rural que muestran la viabilidad de este tipo de actuaciones impulsoras del desarrollo en el ámbito rural. Entre las líneas de acción que se pueden llevar a cabo en el territorio objeto de estudio, desde el punto de vista del desarrollo sostenible, en el corto y en el medio plazo, destacamos algunas consideradas imprescindibles y que hacen referencia a aspectos como el estudio de la capacidad de carga del territorio, la necesidad de un equipamiento fundamental como es un centro de acogida de visitantes, la idoneidad de disponer de un adecuado sistema de Agentes de Desarrollo Local orientado específicamente al sector turístico, así como un plan de comercialización y marketing para los productos turísticos de la zona del Parque Natural.

  7. 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.

  8. Dermatological remedies in the traditional pharmacopoeia of Vulture-Alto Bradano, inland southern Italy

    Directory of Open Access Journals (Sweden)

    Bennett Bradley C

    2008-02-01

    Full Text Available Abstract Background Dermatological remedies make up at least one-third of the traditional pharmacopoeia in southern Italy. The identification of folk remedies for the skin is important both for the preservation of traditional medical knowledge and in the search for novel antimicrobial agents in the treatment of skin and soft tissue infection (SSTI. Our goal is to document traditional remedies from botanical, animal, mineral and industrial sources for the topical treatment of skin ailments. In addition to SSTI remedies for humans, we also discuss certain ethnoveterinary applications. Methods Field research was conducted in ten communities in the Vulture-Alto Bradano area of the Basilicata province, southern Italy. We randomly sampled 112 interviewees, stratified by age and gender. After obtaining prior informed consent, we collected data through semi-structured interviews, participant-observation, and small focus groups techniques. Voucher specimens of all cited botanic species were deposited at FTG and HLUC herbaria located in the US and Italy. Results We report the preparation and topical application of 116 remedies derived from 38 plant species. Remedies are used to treat laceration, burn wound, wart, inflammation, rash, dental abscess, furuncle, dermatitis, and other conditions. The pharmacopoeia also includes 49 animal remedies derived from sources such as pigs, slugs, and humans. Ethnoveterinary medicine, which incorporates both animal and plant derived remedies, is addressed. We also examine the recent decline in knowledge regarding the dermatological pharmacopoeia. Conclusion The traditional dermatological pharmacopoeia of Vulture-Alto Bradano is based on a dynamic folk medical construct of natural and spiritual illness and healing. Remedies are used to treat more than 45 skin and soft tissue conditions of both humans and animals. Of the total 165 remedies reported, 110 have never before been published in the mainland southern Italian

  9. Wine and cultural heritage. The experience of the Alto Douro Wine Region

    Directory of Open Access Journals (Sweden)

    Lina Lourenço-Gomes

    2015-12-01

    Full Text Available The Demarcated Douro Region is one of the oldest demarcated wine regions, and the largest and the most heterogeneous mountainous wine region in the world. Viticulture covers 44,000 ha, and since 2001 an area covering 24,600 ha has been designated as the most representative territory of the Demarcated Douro Region, the Alto Douro Wine Region. This region is included in the list of World Heritage Sites as an evolving and living cultural landscape. The Demarcated Douro Region fits the terroir model, as its economy is based on wine (Porto wine and Douro still wines, supplemented by tourism. During recent decades, both activities have witnessed deep and structural changes, with consequences for the maintenance of the traditional characteristics of the cultural landscape that drove the UNESCO classification. With this issue in mind, the goal of this paper is to describe the recent evolution of the main economic activities of the Demarcated Douro Region. In particular, we aim to deepen the knowledge about the preferences of Portuguese visitors towards the Alto Douro Wine Region and its attributes, thus determining those that deserve preservation and, consequently, public attention. The results of a mixed logit model show that visitors assign highest utility to the preservation of vineyards supported by schist walls, followed by the agglomerations and the characteristic mosaic nature of the landscape. Additionally, respondents who are richer, employed, better educated, better informed regarding the culture of the site and more influenced by the listing are more willing to participate in preserving the cultural heritage of the region.

  10. Interacción dinámica ofensiva en balonmano de alto rendimiento

    Directory of Open Access Journals (Sweden)

    Demetrio Lozano

    2016-09-01

    Full Text Available El objetivo de esta investigación fue analizar las variables que influyen en las fases ofensivas del balonmano de alto rendimiento desde una perspectiva ecológica evaluando los diferentes sistemas tácticos ofensivos en ataque posicional y en contraataque, teniendo en cuenta: el marcador, el tipo de defensa, la simetría numérica, la zona de finalización y el tipo de finalización. Utilizando la metodología observacional y un sistema de observación ad hoc (SOCTO introducido en el software Lince, se registraron un total de 19 partidos de las fases finales masculinas del Campeonato del Mundo 2011, Campeonato de Europa 2012 y Juegos Olímpicos 2012. El análisis descriptivo y de contingencia se complementó con la detección de patrones temporales ­(T-patterns. Los resultados reafirman la autoorganización no lineal de la dinámica de juego ofensivo en el balonmano masculino de alto rendimiento, a partir de la utilización de medios tácticos básicos contra sistemas defensivos abiertos y de medios tácticos complejos contra sistemas defensivos cerrados. Estos medios tácticos complejos ofensivos son los más utilizados en igualdad numérica en la primera secuencia de ataque posicional desde la zona intermedia entre 6 y 9 metros y finalizando en golpe franco a favor del equipo atacante.

  11. 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.

  12. Streamflow forecast in the Alto do Rio Doce watershed in Brazil, using hydrological and atmospheric model

    Science.gov (United States)

    Silva, J. M.; Saad, S. I.; Palma, G.; Rocha, H.; Palmeira, R. M.; Silva, B. L.; Pessoa, A. A.; Ramos, C. G.; Cecchini, M. A.

    2013-05-01

    Electrical energy in Brazil depends essentially on the streamflow, as hydropowers accounts for up to 79% of the total electrical energy installed capacity. Therefore, streamflow forecasts are very important tools to assist in the planning and operation of Brazilian hydroelectric reservoirs. This study evaluated the performance of a distributed hydrological model, Soil and Water Assessment Tool (SWAT) daily streamflow forecasts into four Reservoirs sited in the Alto do Rio Doce Watershed, in Southeast of Brazil. SWAT model was used with precipitation forecast from the regional meteorological model MM5. The calibration and validation processes of SWAT were accomplished using data from four monitoring stations. The model has been run for the 2010-2012 period, and while the apr/2010-set/2011 period has been used for calibration conducted manually, the validation reached the rest of the period. The manual calibration was conducted by the means of sensibility tests of parameters that control surface runoff and groundwater flow, specially the surlag and alpha_bf, respectively the surface runoff lag coefficient and the baseflow recession constant. The daily and monthly Nash-Sutcliffe, R2 and the mean relative error performance indicators were used to assess the relative performance of the model. Results showed that streamflow forecast was very similar toobservations, except in reservoirs with lower drainage areas, where the model did not simulated the beginning of the flood (Dec-Feb). The streamflow forecasts was strongly dependent on the quality of precipitation forecasts used. Given that no correction in the simulated rainfall by the MM5 model in the Alto do Rio Doce watershed has been conducted and no automated calibration method was applied to the parameters of the hydrologic model, we can conclude that the application of the SWAT hydrologic model employing the output data from the MM5 atmospheric model for the streamflow forecast was shown to be a tool of great

  13. 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.

  14. Iris reactor conceptual design

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  15. 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.)

  16. 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

  17. Nuclear reactor design

    CERN Document Server

    2014-01-01

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

  18. Reactor 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.)

  19. 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

  20. 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)

  1. 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.)

  2. 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.)

  3. 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.

  4. Mirror reactor studies

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  5. Multi-purpose reactor

    International Nuclear Information System (INIS)

    1991-05-01

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

  6. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    Hicks, D.

    1970-04-01

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

  7. Reactor scram device for FBR type reactor

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  8. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1993-09-01

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

  9. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    1990-09-01

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

  10. 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.

  11. Community Youth Engagement in East Palo Alto: A Study of the Youth Arts and Music Center Initiative

    Science.gov (United States)

    Henderson, Jamila; Biscocho, Francine; Gerstein, Amy

    2016-01-01

    The Youth Arts and Music Center Initiative is a community-wide effort to design and build an arts center in East Palo Alto. The six-year process, supported by the Goldman Foundation, centered on youth leadership and the arts, and engaged a cross-sector collaborative of partner organizations in an attempt to address the city's shortage of existing…

  12. 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

  13. 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.)

  14. 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.)

  15. 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.)

  16. 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.)

  17. Reactor Safety Research Programs

    Energy Technology Data Exchange (ETDEWEB)

    Edler, S. K.

    1981-07-01

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

  18. 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

  19. Water cooled nuclear reactors

    International Nuclear Information System (INIS)

    Donaldson, A.J.

    1989-01-01

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

  20. Slurry reactor design studies

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-06-01

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

  1. Reactor monitoring device

    International Nuclear Information System (INIS)

    Kono, Shigehiro.

    1996-01-01

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

  2. 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

  3. 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

  4. 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.).

  5. 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.)

  6. 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)

  7. Reactor safety assessment system

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  8. Fast breeder reactors

    International Nuclear Information System (INIS)

    1978-01-01

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

  9. Reactor shutdown device

    International Nuclear Information System (INIS)

    Masuda, Hiroyuki.

    1983-01-01

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

  10. Mirror machine reactors

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  11. Reactor flux calculations

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-02-15

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

  12. Reactor pressure tank

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  13. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-04-01

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

  14. 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

  15. Nuclear reactor theory

    International Nuclear Information System (INIS)

    Sekimoto, Hiroshi

    2007-09-01

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

  16. Power reactor design trends

    International Nuclear Information System (INIS)

    Hogan, W.J.

    1985-01-01

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

  17. Reactor power control system

    International Nuclear Information System (INIS)

    Tomisawa, Teruaki.

    1981-01-01

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

  18. Research reactor support

    International Nuclear Information System (INIS)

    2005-01-01

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

  19. Reactors of the world

    International Nuclear Information System (INIS)

    1971-01-01

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

  20. Elmo Bumpy Torus Reactor

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  1. 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

  2. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2001-01-01

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

  3. First Algerian research reactor

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

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

  4. 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

  5. NUCLEAR REACTOR FUEL SYSTEMS

    Science.gov (United States)

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

    1959-09-15

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

  6. Fast Breeder Reactor studies

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-07-01

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

  7. Fusion reactor radioactive waste management

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  8. 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

  9. Special lecture on nuclear reactor

    International Nuclear Information System (INIS)

    Jo, Nam Jin

    1993-08-01

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

  10. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1975-11-01

    Research activities in fiscal 1974 in Reactor Engineering Division of eight laboratories and computing center are described. Works in the division are closely related with the development of a multi-purpose High-temperature Gas Cooled Reactor, the development of a Liquid Metal Fast Breeder Reactor in Power Reactor and Nuclear Fuel Development Corporation, and engineering of thermonuclear fusion reactors. They cover nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology and aspects of the computing center. (auth.)

  11. Música, rito e cosmologia Desana e Baniwa no Alto Rio Negro, Amazonas, Brasil: uma pesquisa colaborativa

    Directory of Open Access Journals (Sweden)

    Líliam Cristina Barros Cohen

    2015-08-01

    Full Text Available Este artigo discute as conexões entre a mitologia e a música dos grupos indígenas Guahari Diputiro Porã e Hohodene, na região do Alto Rio Negro, Amazonas, Brasil. O sib Desana Guahari Diputiro Porã originalmente habitava o Rio Papuri, um braço do Rio Uaupés, na região do Alto Rio Negro. Atualmente algumas pessoas do sib vivem em Iauaretê. As frátrias Baniwa, denominadas Hohodene eWalipere-dakenai vivem no Rio Içana, um tributário do Rio Aiari. A mitologia e os repertórios musicais são compartilhados pelos grupos da região em diferentes versões. A pesquisa se baseou em diálogos com o bayá, especialista em cantos e mitos, em São Gabriel da Cachoeira e em Iauaretê. A pesquisa também se baseou em uma longa vivência com os pajés (xamãs do rio Aiari. Através de entrevistas, gravações e filmagens das sessões, e com mais de três décadas de aprendizado sobre as tradições Hohodene, são mostradas as conexões fundamentais entre identidade coletiva, os instrumentos sagrados, a origem mitológica dos clãs, o processo de dinâmica da criação e transmissão da identidade através da música por gerações, e o processo de pesquisa etnomusicológica colaborativa estabelecido entre as comunidades indígenas, as instituições de pesquisa e ONGs. Este trabalho também apresenta aspectos da origem humana através da performance musical e do rito. Primeiramente serão apresentados os mitos de criação e das flautas sagradas, seguidos pela descrição dos repertórios musicaisDesana e Baniwa, alguns deles aparecem nas “Casas de Transformação” –portais para as dimensões espirituais da origem.

  12. Textural and microstructural development of the Barro Alto Complex: implications for seismic anisotropy

    Science.gov (United States)

    Silveira, Camila; Lagoeiro, Leonardo; Barbosa, Paola; Cavalcante, Geane Carolina; Ferreira, Filippe; Suita, Marcos; Conte, Thailli

    2017-04-01

    Crustal rheology is associated with the behavior of its constituents in response to stress and strain, while the seismic anisotropy is a property that can correlate these parameters. Seismic properties are strongly related to the microstructures and crystallographic preferred orientation (CPO) of the rocks. In this work, we study CPO-derived seismic anisotropy of metamorphosed gabbro-norites from the Barro Alto (Brazil central) layered complex. The EBSD technique was employed to analyze the crystallographic orientation of the main mineral assembly, diopside and feldspar. The Barro Alto complex belongs to the Tocantins Structural Province, developed between the Amazon and São Francisco cratons, during the Neoproterozoic Brasiliano orogenic cycle. This complex was formed by a mafic-ultramafic layered intrusion mylonitized and metamorphosed under granulite facies conditions. The mylonitic foliation shows compositional segregation into felsic and mafic bands. The samples are composed of porphyroclasts of plagioclase and diopside in a fine matrix of plagioclase, clinopyroxene, orthopyroxene and, less commonly, amphibole and biotite. The plagioclase porphyroclasts exhibit undulose extinction and core-mantle structure. In fine matrix samples the poles to a(100), b(010) and c(001) are randomly distributed in both phases. However, for increasing matrix grain size plagioclase grains shows maxima of a(100) poles sub-parallel to the foliation and b(010) normal to the foliation. The low value of the J index (2.4 for plagioclase and 1.8 for diopside) indicates poorly developed fabric. Misorientation profiles showing high frequency of small angle boundaries are typical of recrystallization by subgrain rotation mechanisms. The microstructural and CPO analyses suggest deformation controlled by diffusive processes. The CPO models were compared to models described in the literature, based on the anorthite + diopside assembly, since these are the major phases, and thus control the

  13. RA Reactor applications, Annex A

    International Nuclear Information System (INIS)

    Cupac, S.; Vukadin, Z.

    2000-01-01

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

  14. RA Reactor applications, Annex A

    International Nuclear Information System (INIS)

    Cupac, S.; Vukadin, Z.

    1998-01-01

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

  15. RA Reactor applications, Annex A

    International Nuclear Information System (INIS)

    Cupac, S.; Vukadin, Z.

    1996-01-01

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

  16. Nuclear reactor container

    International Nuclear Information System (INIS)

    Takahashi, Hiroyuki.

    1987-01-01

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

  17. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1981-01-01

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

  18. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1984-01-01

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

  19. Nuclear reactor (1960)

    International Nuclear Information System (INIS)

    Maillard, M.L.

    1960-01-01

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

  20. Backfitting of research reactors

    International Nuclear Information System (INIS)

    Delrue, R.; Noesen, T.

    1985-01-01

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

  1. Ageing of research reactors

    International Nuclear Information System (INIS)

    Ciocanescu, M.

    2001-01-01

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

  2. Integrated nuclear reactor

    International Nuclear Information System (INIS)

    Pales, I.; Hasko, V.

    1984-01-01

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

  3. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2001-04-01

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

  4. Inertial thermonuclear reactors

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  5. Reactor pressure vessel support

    International Nuclear Information System (INIS)

    Butti, J.P.

    1978-01-01

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

  6. Pressure tube reactor

    International Nuclear Information System (INIS)

    Matsumoto, Tomoyuki; Fujino, Michihira.

    1980-01-01

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

  7. Nuclear reactor core catcher

    International Nuclear Information System (INIS)

    1977-01-01

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

  8. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1985-01-01

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

  9. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2002-01-01

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

  10. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2002-04-01

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

  11. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2002-04-01

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

  12. Reactor vessel sealing plug

    International Nuclear Information System (INIS)

    Dooley, R.A.

    1986-01-01

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

  13. Small reactor operating mode

    International Nuclear Information System (INIS)

    Snell, V.G.

    1997-01-01

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

  14. New reactor type proposed

    CERN Multimedia

    2003-01-01

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

  15. Pulsed fusion reactors

    International Nuclear Information System (INIS)

    1975-01-01

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

  16. Pressurized water reactor systems

    International Nuclear Information System (INIS)

    Meyer, P.J.

    1975-01-01

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

  17. K-Reactor readiness

    International Nuclear Information System (INIS)

    Rice, P.D.

    1991-01-01

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

  18. Polymeric Membrane Reactors

    OpenAIRE

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

    2008-01-01

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

  19. Alternative breeder reactor technologies

    International Nuclear Information System (INIS)

    Spinrad, B.I.

    1978-01-01

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

  20. Reactor Neutron Sources

    International Nuclear Information System (INIS)

    Aksenov, V.L.

    1994-01-01

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

  1. KS-150 reactor control

    International Nuclear Information System (INIS)

    Wagner, K.

    1974-01-01

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

  2. The replacement research reactor

    International Nuclear Information System (INIS)

    Cameron, R.; Horlock, K.

    2001-01-01

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

  3. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Butterfield, C.E.; Waite, E.

    1982-01-01

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

  4. OECD Halden reactor project

    International Nuclear Information System (INIS)

    1978-01-01

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

  5. Generation IV reactors: economics

    International Nuclear Information System (INIS)

    Dupraz, B.; Bertel, E.

    2003-01-01

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

  6. Department of Reactor Technology

    DEFF Research Database (Denmark)

    Risø National Laboratory, Roskilde

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

  7. Regulations for RA reactor operation

    International Nuclear Information System (INIS)

    1980-09-01

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

  8. Reactor of the XXI century

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  9. Licensing of nuclear reactor operators

    International Nuclear Information System (INIS)

    1979-09-01

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

  10. Reactor power measuring device

    International Nuclear Information System (INIS)

    Ichige, Masayuki; Ishige, Takanori.

    1997-01-01

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

  11. Materials for fusion reactors

    International Nuclear Information System (INIS)

    Ehrlich, K.; Kaletta, D.

    1978-03-01

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

  12. Fast breeder reactors

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  13. Nuclear reactors to come

    International Nuclear Information System (INIS)

    Lung, M.

    2002-01-01

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

  14. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1988-01-01

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

  15. Reactor operation method

    International Nuclear Information System (INIS)

    Osumi, Katsumi; Miki, Minoru.

    1979-01-01

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

  16. LMFBR type reactor

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  17. OECD Halden reactor project

    International Nuclear Information System (INIS)

    1979-01-01

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

  18. The reactor antineutrino anomalies

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-07-01

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

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  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. 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)

  7. INSTRUMENTOS DE PROMOCIÓN DE LOS VINOS EN LOS RESTAURANTES DE ALTO NIVEL

    Directory of Open Access Journals (Sweden)

    Gil Saura, I.

    2009-01-01

    Full Text Available En los últimos años, la comercialización de vinos está adquiriendo un peso creciente en los establecimientos de restauración. El aumento en la complejidad de la oferta de vinos determina que la elección del consumidor esté condicionada por la oferta presente en la carta y por la influencia del personal de sala. El objetivo del presente trabajo es identificar y caracterizar los instrumentos relevantes de promoción de los vinos que utilizan los restaurantes, en función de la presencia de personal formado en vinos. Como resultado de un estudio realizado para una muestra de restaurantes de alto nivel, observamos que el contenido y el diseño de la carta de vinos se encuentran en granmedida condicionados por la presencia de sumiller, constituyéndose ambos en instrumentos básicos de promoción de los vinos en el restaurante.

  8. 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.

  9. Estimation of forest attributes by integration of inventory and remotely sensed data in Alto Molise

    Directory of Open Access Journals (Sweden)

    Ugo Chiavetta

    2008-01-01

    Full Text Available Forest ecosystems for their important multifunctional value, need a complex and increasing amount of descriptive information to support their management. Ecological and environmental related attributes have became nowadays important as traditional ones, such as wood growing stock and basal area. The correct application of Sustainable Forest Management criteria is boosted by spatial contiguous knowledge of such attributes. For such a reason in the last years a huge number of scientific experiences in the forest area have been concentrated to study the relationship between data acquired in the field and remotely sensed multispectral images. Models based on such relationships can be used to estimate and map forest attributes acquired in the field on the basis of a statistical sampling design. can be sucould not take in consideration spatially structured data. In last years many researches have focused on possible relationships between field data and remote sensed informations derived from multispectral imagery. Modeling these relationships allows to extend inventory data to not explored surfaces. In this paper were discussed results on spatializing forest biometrical attributes, tree heterogeneity and dimensional heterogeneity assessed during an inventory of Mountain Community “Alto Molise” (IS throw Spot 5 and Lansat TM 7 imagery. For this purpose a multilinear regression and a k-Nearest Neighbor classifier were used.

  10. deportistas de alto nivel en el territorio español

    Directory of Open Access Journals (Sweden)

    Cristina L\\u00F3pez de Subijana

    2014-01-01

    Full Text Available La formación académica y la planificación son fundamentales para una exitosa inserción laboral de los atletas de élite. El objetivo de esteestudio fue detectar el nivel de aplicación de las medidas de formación por los diferentes agentes que participan en el sistema. Al analizar el proceso deinformación se apreciaron ciertas carencias en el mismo. El cambio de fechas de exámenes con motivo de competiciones/concentraciones oficiales fueel aspecto más demandado por los diferentes deportistas. Dado que el periodo de los 20 a los 30 años es crítico para la formación, sería necesario aportarun servicio de cobertura total para la población de deportistas de Alto Nivel, con el fin de dar un asesoramiento permanente y trazar una línea continuadesde la vida deportiva a la vida laboral en los deportistas.

  11. 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.

  12. 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.

  13. Estimación de la exposición a fluoruros en Los Altos de Jalisco, México Estimation of exposure to fluoride in "Los Altos de Jalisco", México

    OpenAIRE

    Roberto Hurtado-Jiménez; Jorge Gardea-Torresdey

    2005-01-01

    OBJETIVO: Estimar la exposición a fluoruros y riesgos potenciales a la salud humana en Los Altos de Jalisco, México. MATERIAL Y MÉTODOS: Se midió electroquímicamente la concentración de fluoruros en 105 pozos y seis tomas de agua potable, en los Altos de Jalisco, de mayo a julio de 2002. Se estimó la dosis de exposición y la ingestión total de fluoruros para: bebés de 10 kg, niños de 20 kg y adultos de 70 kg. RESULTADOS: La concentración de fluoruros en las muestras de agua varió entre 0.1 y ...

  14. The reactor Cabri

    International Nuclear Information System (INIS)

    Ailloud, J.; Millot, J.P.

    1964-01-01

    It has become necessary to construct in France a reactor which would permit the investigation of the conditions of functioning of future installations, the choice, the testing and the development of safety devices to be adopted. A water reactor of a type corresponding to the latest CEA constructions in the field of laboratory or university reactors was decided upon: it appeared important to be able to evaluate the risks entailed and to study the possibilities of increasing the power, always demanded by the users; on the other hand, it is particularly interesting to clarify the phenomena of power oscillation and the risks of burn out. The work programme for CABRI will be associated with the work carried out on the American Sperts of the same type, during its construction, very useful contacts were made with the American specialists who designed the se reactors. A brief description of the reactor is given in the communication as well as the work programme for the first years with respect to the objectives up to now envisaged. Rough description of the reactor. CABRI is an open core swimming-pool reactor without any lateral protection, housed in a reinforced building with controlled leakage, in the Centre d'Etudes Nucleaires de Cadarache. It lies alone in the middle of an area whose radius is 300 meters long. Control and measurements equipment stand out on the edge of that zone. It consumes MTR fuel elements. The control-safety rods are propelled by compressed air. The maximum flow rate of cooling circuit is 1500 m 3 /h. Transient measurements are recorded in a RW330 unit. Aims and work programme. CABRI is meant for: - studies on the safety of water reactors - for the definition of the safety margins under working conditions: research of maximum power at which a swimming-pool reactor may operate with respect to a cooling accident, of local boiling effect on the nuclear behaviour of the reactor, performances of the control and safety instruments under exceptional

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

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  16. Materials for nuclear reactors

    International Nuclear Information System (INIS)

    Banerjee, S.; Kamath, H.S.

    2005-01-01

    The improved performance of present generation nuclear reactors and the realization of advanced reactor concepts, both, require development of better materials. Physical metallurgy/materials science principles which have been exploited in meeting the exacting requirements of nuclear reactor materials (fuels and structural materials), are outlined citing a few specific examples. While the incentive for improvement of traditional fuels (e.g., UO 2 fuel) is primarily for increasing the average core burn up, the development of advanced fuels (e.g., MOX, mixed carbide, nitride, silicide and dispersion fuels) are directed towards better utilization of fissile and fertile inventories through adaptation of innovative fuel cycles. As the burn up of UO 2 fuel reaches higher levels, a more detailed and quantitative understanding of the phenomena such as fission gas release, fuel restructuring induced by radiation and thermal gradients and pellet-clad interaction is being achieved. Development of zirconium based alloys for both cladding and pressure tube applications is discussed with reference to their physical metallurgy, fabrication techniques and in-reactor degradation mechanisms. The issue of radiation embrittlement of reactor pressure vessels (RPVs) is covered drawing a comparison between the western and eastern specifications of RPV steels. The search for new materials which can stand higher rates of atomic displacement due to radiation has led to the development of swelling resistant austenitic and ferritic stainless steels for fast reactor applications as exemplified by the development of the D-9 steel for Indian fast breeder reactor. The presentation will conclude by listing various materials related phenomena, which have a strong bearing on the successful development of future nuclear energy systems. (author)

  17. Method of operating a reactor

    International Nuclear Information System (INIS)

    Oosumi, Katsumi; Yamamoto, Michiyoshi.

    1980-01-01

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

  18. 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)

  19. Sodium-cooled nuclear reactors

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  20. BR2 Reactor: Introduction

    International Nuclear Information System (INIS)

    Moons, F.

    2007-01-01

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

  1. 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.

  2. 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.

  3. Radiation detectors for reactors

    International Nuclear Information System (INIS)

    Balagi, V.

    2005-01-01

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

  4. Reactors PMT backlog

    International Nuclear Information System (INIS)

    Olson, H.P.

    1986-01-01

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

  5. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    Jaouen, C.; Beroux, P.

    2012-01-01

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

  6. Mirror reactor studies

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  7. Reactor core control device

    International Nuclear Information System (INIS)

    Sano, Hiroki

    1998-01-01

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

  8. Reactor physics computations

    International Nuclear Information System (INIS)

    Shapiro, A.

    1977-01-01

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

  9. Nuclear reactor apparatus

    International Nuclear Information System (INIS)

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

    1978-01-01

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

  10. Reactor power control device

    International Nuclear Information System (INIS)

    Nishiyama, Hiroyuki.

    1991-01-01

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

  11. Tandem mirror reactors

    International Nuclear Information System (INIS)

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

    1978-01-01

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

  12. Reactor shutdown device

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  13. FBR type reactors

    International Nuclear Information System (INIS)

    Maemoto, Junko.

    1985-01-01

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

  14. RB research reactor Safety Report

    International Nuclear Information System (INIS)

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

    1979-04-01

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

  15. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    Lu, Hong; Miller, D.W.

    1991-01-01

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

  16. Baseline to Evaluate Off-Site Suspended Sediment-Related Mining Effects in the Alto Tajo Natural Park, Spain

    OpenAIRE

    Zapico, Ignacio; Laronne, J. B.; Martín Moreno, Cristina; Martín Duque, J. F.; Ortega, Ana Isabel; Sánchez Castillo, L.

    2016-01-01

    Mining is a human activity with considerable environmental impact. To evaluate such impacts, international laws require undertaking local studies based on direct sampling to establish baseline conditions of parameters modified by human activities. Mining takes place near the Alto Tajo Natural Park, where a suspended sediment concentration (SSC) baseline is required to determine whether mining affects water quality. To this end, we have monitored the Tajo River and its tributary the Tajuelo fo...

  17. 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.

  18. How uncontrolled urban expansion increases the contamination of the Titicaca Lake Basin (El Alto, La Paz, Bolivia)

    OpenAIRE

    Archundia, D.; Duwig, Céline; Spadini, L.; Uzu, Gaëlle; Guédron, Stéphane; Morel, M. C.; Cortez, R.; Ramos, O. R.; Chincheros, J.; Martins, J. M. F.

    2017-01-01

    Cities in developing countries encounter rapid waves of social transformation and economic development where the environment is mostly a neglected aspect. The Katari watershed encompasses mining areas, El Alto city (one of the fastest growing urban areas in South America and the biggest in the Altiplano) as well as agricultural areas. Its outlet is Cohana Bay, one of the most polluted areas of Lake Titicaca. Here we propose an integrative approach (hydrological, physicochemical, chemical and ...

  19. Impacto estético de edifícios altos percebidos ao nível da rua.

    Directory of Open Access Journals (Sweden)

    Mg. Arq. Debora Gregoletto

    2015-12-01

    Full Text Available O objetivo deste artigo é avaliar o impacto estético de edifícios altos com diferentes alturas, percebidos ao nível de ruas com distintas larguras por três grupos de respondentes com diferentes níveis e tipos de formação acadêmica. Impactos de edifícios altos na estética urbana podem ser percebidos de diferentes formas pelos usuários do espaço urbano conforme a relação entre a altura desses edifícios e a largura das vias, especialmente quando observados ao nível da rua, onde a cidade é vivenciada pelos transeuntes. A coleta de dados foi realizada através de questionários aplicados via internet para usuários do espaço urbano de Porto Alegre, divididos em três grupos de respondentes: 48 arquitetos; 48 não arquitetos com curso universitário completo e 33 pessoas sem curso universitário concluído ou iniciado. A análise de dados foi realizada através de testes estatísticos não-paramétricos. Os resultados indicam que o impacto estético de edifícios mais altos (18 pavimentos tende a ser negativo e que tais impactos são afetados pela relação entre as larguras das ruas e as alturas dos edifícios; em vias com menor largura o impacto negativo dos edifícios mais altos é maior do que em vias com uma maior largura

  20. 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.

  1. Primera cita de la especie Goniozus legneri (Hymenoptera: Bethylidae en el Alto Valle de Río Negro, Patagonia Argentina

    Directory of Open Access Journals (Sweden)

    Silvina GARRIDO

    2005-01-01

    Full Text Available Se reporta por primera vez para la zona del Alto Valle de Río Negro, a Goniozus legneri Gordh, parasitando naturalmente larvas de Cydia pomonella (L, "carpocapsa", en montes comerciales de manzanos y nogales. Se comentan brevemente su hallazgo, características morfológicas, distribución, biología e influencia en las poblaciones de "carpocapsa".

  2. Reactor Structural Materials: Reactor Pressure Vessel Steels

    Energy Technology Data Exchange (ETDEWEB)

    Chaouadi, R

    2000-07-01

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

  3. Reactor Structural Materials: Reactor Pressure Vessel Steels

    International Nuclear Information System (INIS)

    Chaouadi, R.

    2000-01-01

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

  4. 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

  5. USO DO SOLO E COBERTURA VEGETAL NA BACIA DO ALTO CURSO DO RIO UBERABA

    Directory of Open Access Journals (Sweden)

    Vera Lucia Abdala

    2011-04-01

    Full Text Available As informações geradas do meio físico, levando em consideração a declividade, solos e uso das terras, permitem conhecer as características e as condições das áreas, fornecendo subsídios para atividades de análise ambiental e planejamento conservacionista. O presente estudo teve objetivo de delimitar, identificar e avaliar as diferentes categorias de uso do solo e cobertura vegetal na área bacia do alto curso do rio Uberaba, numa área de aproximadamente 528 km2, localizadas entre as coordenadas geográficas 19° 30’ e 19o 45’ sul e 47o 38’ e 48o 00’ oeste de Greenwich. Utilizou-se técnicas de geoprocessamento e sensoriamento remoto para mapeamento da bacia em estudo. A cobertura vegetal natural remanescente é caracterizada pelos seguintes tipos: mata/cerradão (galeria, topo e encostas, cerrado, campo cerrado (sujo que juntos perfazem o equivalente a 30.363,57 hectares (57% da área; A vegetação natural vem sendo substituída em sua maior parte por pastagens e cultura anuais; A área em estudo é caracterizada em sua maior parte pelo seu relevo plano com baixas declividades; Os canais de 1º e 2º ordem dos córregos que nascem nas bordas da chapada é que mantém o volume de água do rio Uberaba no período seco.

  6. 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.

  7. 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)

  8. 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.

  9. 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.

  10. 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.

  11. Reactor safety analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

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

  12. Reactor for exothermic reactions

    Science.gov (United States)

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

    1993-03-02

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

  13. Refueling of nuclear reactors

    International Nuclear Information System (INIS)

    Meuschke, R.E.

    1987-01-01

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

  14. Nuclear reactor safety device

    Science.gov (United States)

    Hutter, Ernest

    1986-01-01

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

  15. The nuclear reactor systems

    International Nuclear Information System (INIS)

    Bacher, P.

    2008-01-01

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

  16. Reactor control device

    International Nuclear Information System (INIS)

    Araki, Takao; Inoue, Toyokazu.

    1981-01-01

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

  17. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-08-01

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

  18. Nuclear reactor risk assessment

    International Nuclear Information System (INIS)

    Higson, D.J.

    1982-01-01

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

  19. Breazeale Reactor Modernization Program

    International Nuclear Information System (INIS)

    Davison, C. C.

    2003-01-01

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

  20. Fusion reactor materials

    International Nuclear Information System (INIS)

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

    1994-02-01

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

  1. MERCHANT MARINE SHIP REACTOR

    Science.gov (United States)

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

    1961-05-01

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

  2. Utilization of research reactors

    International Nuclear Information System (INIS)

    1962-01-01

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

  3. Compact stellarators as reactors

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  4. Reactor container facility

    International Nuclear Information System (INIS)

    Saito, Takashi; Nagasaka, Hideo.

    1990-01-01

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

  5. International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

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

    1989-09-01

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

  6. BWR type reactor system

    International Nuclear Information System (INIS)

    Morooka, Shin-ichi.

    1980-01-01

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

  7. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-08-01

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

  8. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-01-01

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

  9. Licensed operating reactors

    International Nuclear Information System (INIS)

    Hartfield, R.A.

    1990-03-01

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

  10. Nuclear reactor containment device

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu.

    1980-01-01

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

  11. Nuclear Rocket Engine Reactor

    CERN Document Server

    Lanin, Anatoly

    2013-01-01

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

  12. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Hoizumi, Atsushi.

    1986-01-01

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

  13. AREVA's nuclear reactors portfolio

    International Nuclear Information System (INIS)

    Marincic, A.

    2009-01-01

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

  14. Oscillatory flow chemical reactors

    Directory of Open Access Journals (Sweden)

    Slavnić Danijela S.

    2014-01-01

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

  15. Reactor Materials Research

    International Nuclear Information System (INIS)

    Van Walle, E.

    2002-01-01

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

  16. ARIES tokamak reactor study

    International Nuclear Information System (INIS)

    Steiner, D.; Embrechts, M.

    1990-07-01

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

  17. Nuclear reactor core assembly

    International Nuclear Information System (INIS)

    Baxi, C.B.

    1978-01-01

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

  18. Particle bed reactor modeling

    Science.gov (United States)

    Sapyta, Joe; Reid, Hank; Walton, Lew

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

  19. Advanced reactors: A retrospective

    International Nuclear Information System (INIS)

    Starr, C.

    1989-01-01

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

  20. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    Aspden, G.J.

    1980-01-01

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

  1. Reactor pressure vessel materials

    International Nuclear Information System (INIS)

    Suzuki, K.

    1998-01-01

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

  2. Australia's new nuclear reactor

    International Nuclear Information System (INIS)

    Kemeny, L.

    2007-01-01

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

  3. Netherlands Interuniversity Reactor Institut

    International Nuclear Information System (INIS)

    1978-01-01

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

  4. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2002-04-01

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

  5. Perspectives on reactor safety

    International Nuclear Information System (INIS)

    Haskin, F.E.

    1994-03-01

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

  6. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2000-01-01

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

  7. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2000-07-01

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

  8. Perspectives on reactor safety

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-03-01

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

  9. Fast quench reactor method

    Science.gov (United States)

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

    1999-08-10

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

  10. Nuclear reactor pressure vessel

    International Nuclear Information System (INIS)

    McDonald, B.N.

    1976-01-01

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

  11. Computerized reactor monitor and control for research reactors

    International Nuclear Information System (INIS)

    Buerger, L.; Vegh, E.

    1981-09-01

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

  12. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-12-01

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

  13. The market for research reactors

    International Nuclear Information System (INIS)

    Roegler, H.J.

    1986-01-01

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

  14. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

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

    1983-09-01

    Research and development activities in the Department of Reactor Engineering in fiscal 1982 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Since fiscal 1982, Systematic research and development work on safeguards technology has been added to the activities of the Department. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  15. High Flux Isotope Reactor (HFIR)

    Data.gov (United States)

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

  16. Reactor operation safety information document

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

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

  17. Nuclear reactors for the future

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  18. Fusion reactor development: A review

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

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

  19. Inertial confinement fusion reactor systems

    International Nuclear Information System (INIS)

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

    1980-01-01

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

  20. BENITO, NUEVO MUTANTE DE FLOR DE JAMAICA (Hibiscus sabdariffa, L.) DE ALTO POTENCIAL PRODUCTIVO EN CONDICIONES DE BAJOS SUMINISTROS DE AGUA

    OpenAIRE

    María C. González Cepero

    2015-01-01

    En el Instituto Nacional de Ciencias Agrícolasse desarrolló un programa de mejoramiento genético dirigidoa obtener variedades de Flor de Jamaica de alto potencialproductivo, en condiciones de bajos suministros de agua.

  1. REACTOR FUEL ELEMENTS TESTING CONTAINER

    Science.gov (United States)

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

    1963-01-15

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

  2. Engineering reactors for catalytic reactions

    Indian Academy of Sciences (India)

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

  3. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-04-01

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

  4. Fast reactors: potential for power

    International Nuclear Information System (INIS)

    1983-02-01

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

  5. Digital control of research reactors

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  6. Reactor component automatic grapple

    International Nuclear Information System (INIS)

    Greenaway, P.R.

    1982-01-01

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

  7. LMFBR type reactor

    International Nuclear Information System (INIS)

    Kumaoka, Yoshio; Kawamura, Yutaka.

    1990-01-01

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

  8. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    Baddley, A.H.

    1981-01-01

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

  9. The reactor vessel steels

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  10. Thermal Reactor Safety

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

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

  11. Thermal Reactor Safety

    International Nuclear Information System (INIS)

    1980-06-01

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

  12. Hydrodynamic Cavitation Reactors contd…

    Indian Academy of Sciences (India)

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

  13. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Sekimizu, Koichi

    1980-01-01

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

  14. Reactor instrumentation and control

    International Nuclear Information System (INIS)

    Wach, D.; Beraha, D.

    1980-01-01

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

  15. Nuclear Reactor Sharing Program

    International Nuclear Information System (INIS)

    1994-01-01

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

  16. The Chernobyl reactor accident

    International Nuclear Information System (INIS)

    1986-01-01

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

  17. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    Barjon, Robert

    1975-01-01

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

  18. Reactor control system. PWR

    International Nuclear Information System (INIS)

    2009-01-01

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

  19. Reactor vessel stud tensioner

    International Nuclear Information System (INIS)

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

    1982-01-01

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

  20. Fossil fuel furnace reactor

    Science.gov (United States)

    Parkinson, William J.

    1987-01-01

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

  1. Fast reactor programme

    International Nuclear Information System (INIS)

    Plakman, J.C.

    1982-01-01

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

  2. Reactor operational transient analysis

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  3. Fusion reactor materials

    International Nuclear Information System (INIS)

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

    1980-01-01

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

  4. Reactor physics of CANFLEX

    International Nuclear Information System (INIS)

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

    1997-07-01

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

  5. WATER BOILER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1960-11-22

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

  6. Cermet fuel reactors

    International Nuclear Information System (INIS)

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

    1987-09-01

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

  7. Integral Fast Reactor Program

    International Nuclear Information System (INIS)

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

    1993-06-01

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

  8. Nuclear reactor vessels

    International Nuclear Information System (INIS)

    Sato, Yoshimi; Fukuda, Yoshio.

    1987-01-01

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

  9. Studies on reactor physics

    International Nuclear Information System (INIS)

    1960-01-01

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

  10. University Reactor Instrumentation Program

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1992-11-01

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

  11. Fusion reactor materials

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1989-01-01

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

  12. Method of reactor operation

    International Nuclear Information System (INIS)

    Nakajima, Takeshi

    1988-01-01

    Purpose: To minimize the power change due to the increase in xenone and power distribution after reaching the rated power in the case of using fresh fuels no requiring conditioning operation thereby starting the nuclear reactor in a short period of time and stably. Method: When control rods are entirely inserted only with a purpose for the compensation of the reactivity in a xenon-unsaturated state such as upon starting of the nuclear reactor, peaking is generated in the lower portion of the reactor core. Therefore, it is necessary to insert control rods for additionally suppressing the peaking in the lower portion of the reactor core to a relatively shallow level. In view of the above, a plurality of control rods are divided into a first control rod group finally inserted in the rated power state and a second control rod group other than the above. Then, the power is once elevated to the rated power level by means of such an intermediate control rod pattern that the ratio of the total extraction amount between the first control rod group and the second control rod group is made constant. Then, the control rods are extracted stepwise while setting the ratio of the total extraction amount constant in accordance with the change of the accumulating amount of xenone, to thereby obtain the purpose. (kamimura, M.)

  13. Integral Fast Reactor concept

    Energy Technology Data Exchange (ETDEWEB)

    Till, C.E.; Chang, Y.I.

    1986-01-01

    The Integral Fast Reactor (IFR) is an innovative LMR concept, being developed at Argonne National Laboratory, that fully exploits the inherent properties of liquid metal cooling and metallic fuel to achieve breakthroughs in economics and inherent safety. This paper describes key features and potential advantages of the IFR concept, technology development status, fuel cycle economics potential, and future development path.

  14. Integral Fast Reactor concept

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.

    1986-01-01

    The Integral Fast Reactor (IFR) is an innovative LMR concept, being developed at Argonne National Laboratory, that fully exploits the inherent properties of liquid metal cooling and metallic fuel to achieve breakthroughs in economics and inherent safety. This paper describes key features and potential advantages of the IFR concept, technology development status, fuel cycle economics potential, and future development path

  15. Tandem mirror reactor

    International Nuclear Information System (INIS)

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

    1977-01-01

    A parametric analysis and a preliminary conceptual design for a 1000 MWe Tandem Mirror Reactor (TMR) are described. The concept is sufficiently attractive to encourage further work, both for a pure fusion TMR and a low technology TMR Fusion-Fission Hybrid

  16. Nuclear Reactors and Technology

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-01-01

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

  17. Orphee reactor experimental equipment

    International Nuclear Information System (INIS)

    1987-01-01

    Experimental equipment around the ORPHEE reactor is presented. The neutron source; and the spectrometers and sample environment (inelastic and quasi-elastic scattering, elastic scattering, spread scattering, small angle scattering) are described. An experiment proposal and reports guide is supplied [fr

  18. NEUTRONIC REACTOR FUEL PUMP

    Science.gov (United States)

    Cobb, W.G.

    1959-06-01

    A reactor fuel pump is described which offers long life, low susceptibility to radiation damage, and gaseous fission product removal. An inert-gas lubricated bearing supports a journal on one end of the drive shsft. The other end has an impeller and expansion chamber which effect pumping and gas- liquid separation. (T.R.H.)

  19. Mirror reactor blankets

    International Nuclear Information System (INIS)

    Lee, J.D.; Barmore, W.L.; Bender, D.J.; Doggett, J.N.; Galloway, T.R.

    1976-01-01

    The general requirements of a breeding blanket for a mirror reactor are described. The following areas are discussed: (1) facility layout and blanket maintenance, (2) heat transfer and thermal conversion system, (3) materials, (4) tritium containment and removal, and (5) nuclear performance

  20. Low Power Reactor Comparisons

    Energy Technology Data Exchange (ETDEWEB)

    Homeyer, W. G. [General Atomics Site, San Diego, CA (United States)

    1969-02-21

    Studies were made of a number of low power (< 300 kWe) thermionic reactors containing flashlight or unit cell thermionic fuel elements. The objective of these studies was to determine the feasibility of producing a net power of 50 to 100 kWe with a power plant weighing 3000 to 4000 lb (1360 to 1820 kg).