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  1. Desarrollo de proveedores para la industria nuclear argentina Visión desde las Centrales Nucleares

    Directory of Open Access Journals (Sweden)

    DOMINGO QUILICI

    2013-06-01

    Full Text Available Frente al inicio de una nueva etapa en la instalación de capacidad núcleo eléctrica en el país, se recorrerá la historia del desarrollo de la industria nuclear nacional (1964-1986 en búsqueda de antecedentes útiles para esta nueva realidad. Partiendo de la intención de dar repuesta a las preguntas: ¿Por qué se decidió tan tempranamente construir una central nuclear (en adelante CN; ¿por qué se decidió comprarla con una modalidad particular de los contratos “llave en mano”, en vez del desarrollo de una versión “criolla”? Y cuál fue el significado de la apertura del “paquete tecnológico” en aquel momento; se indagará sobre los antecedentes del desarrollo de proveedores para la industria nuclear en la Argentina. Se describirán las acciones que llevaron a la compra de las centrales de Atucha I, Embalse y Atucha II y como a partir de esas decisiones se implementaron políticas para maximizar la participación nacional en la construcción de las mismas y para la transferencia de tecnología del exterior hacia la industria local. Se analizará el Plan Nuclear puesto en vigencia a fines de los años setenta, desde el punto de vista de su influencia sobre el desarrollo tecnológico endógeno. Abstract The history of the development of national nuclear industry (1964-1986 will be reviewed in the search of useful patterns for the present new phase in the installation of nucleo-electric capacity in the country Precedents of development of suppliers for the argentinean nuclear industry will be considered, taking as starting point the following questions: Why the early decision of constructing a Nuclear Power Plant was taken? Why was it decided to buy it under a peculiar version of a turnkey contract instead of developing a “native” design? What were the implications of opening “technological packages” at that time? Actions leading to the construction of Atucha I, Embalse and Atucha II stations will be described, as well

  2. Desarrollo e implantación en un APS de una metodologia para identificar los fallos de inicio de vida en una Central Nuclear

    OpenAIRE

    González Celades, María

    2015-01-01

    El proyecto Desarrollo e implantación en un Análisis Probabilista de Seguridad de una metodología para identificar los fallos de inicio de vida en una central nuclear tiene como objetivo el desarrollo de una herramienta para identificar qué fallos de componente forman parte del período de inicio de infancia, de una central nuclear. Estos fallos deberían ser eliminados de la Base de Datos del Análisis Probabilista de Seguridad (BD APS) ya que no son representativos de la operación real de la c...

  3. Design optimization of the Laguna Verde nuclear power station fuel recharge; Optimacion del diseno de recargas de combustible para la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Cortes Campos, Carlos Cristobal [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico)

    1991-12-31

    It is described, in general terms, the procedure that is followed to accomplish the optimization of the recharge design, and an example is shown where this procedure was applied for the analysis of the type BWR reactor of Unit No. 1 of the Laguna Verde Nuclear Power Station. [Espanol] Se describe en terminos generales el procedimiento que se sigue para realizar la optimacion del diseno de recargas, y se muestra un ejemplo en el que se utilizo dicho procedimiento para el analisis del reactor tipo BWR de la unidad 1, de la Central Laguna Verde (CLV).

  4. Modular plant of electro chlorination of seawater for nuclear power plants; Planta modular de electrocloracion de agua de mar para centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Dumas, H.; Sesma, J. L.

    2015-07-01

    Iberdola Engineering and Construction has supplied the seawater electro chlorination plant for the EPR of Flamanville 3. The plant produces sodium hypochlorite from the electrolysis of the seawater and injects it continuously to protect the cooling circuits against the marine flora and fauna. As a consequence of the problems faced during the erection of the plant, Iberdola Engineering and construction develops an innovation project to design a modular electro chlorination system for Nuclear Power Plants. The result is a competitive product that reduces significantly the installation costs and the delivery data. (Author)

  5. Nuclear Energy in Central Europe 98, Proceedings

    International Nuclear Information System (INIS)

    Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 63 articles from Slovenia, sorounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Nuclear Methods, Reactor Physics, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation and Nuclear Waste disposal

  6. Demand of natural uranium to satisfy the requirements of nuclear fuel of new nuclear power plants in Mexico; Demanda de uranio natural para satisfacer los requerimientos de combustible nuclear de nuevas centrales nucleares en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J. R.; Rios, M. del C.; Alonso, G.; Palacios H, J. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: jrrs@nuclear.inin.mx

    2008-07-01

    Due to the expectation of that in Mexico new plants of nuclear energy could be installed, turns out from the interest to evaluate the uranium requirements to operate those plants and to also evaluate if the existing reserves in the country could be sufficient to satisfy that demand. Three different scenes from nuclear power plant expansion for the country are postulated here that are desirable for the diversification of generation technologies. The first scene considers a growth in the generation by nuclear means of two reactors of type ABWR that could enter operation by years 2015 and 2020, in the second considers the installation of four reactors but as of 2015 and new every 5 years, in the scene of high growth considers the installation of 6 reactors of the same type that in the other scenes, settling one every three years as of 2015. The results indicate that the uranium reserves could be sufficient to only maintain in operation to one of the reactors proposed by the time of their useful life. (Author)

  7. Notions and methodologies for uncertainty analysis in simulations of transitory events of a nuclear central; Nociones y metodologias para analisis de incertidumbre en simulaciones de eventos transitorios de una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alva N, J. [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Ingenieria Nuclear, Avenida IPN S/N Colonia Lindavista, 07738 Mexico D.F. (Mexico); Ortiz V, J.; Amador G, R.; Delfin L, A. [ININ, Carretera Mexico-Toluca SN La Marquesa, 52750 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: neriaesfm@gmail.com

    2007-07-01

    The present work has as objective to gather the basic notions related with the uncertainty analysis and some of the methodologies to be applied in the studies of transitory events analysis of a nuclear power station, in particular of those thermal hydraulics phenomena. The concepts and methodologies mentioned in this work are the result of an exhaustive bibliographical investigation of the topic in the nuclear area. The methodologies of uncertainties analysis have been developed by diverse institutions and they are broadly used at world level for their application in the results of the computer codes of the class of better estimation in the thermal hydraulics analysis and safety of plants and nuclear reactors. The main sources of uncertainty, types of uncertainty and aspects related with the models of better estimation and better estimation method are also presented. (Author)

  8. Nuclear insurance in Central and Eastern Europe

    International Nuclear Information System (INIS)

    In the world outside the former Soviet Union, insurance industries in their respective domestic markets have pooled their resources so as to provide a secure and cost-effective conduit for the transaction of insurance business on behalf of the nuclear industry. These are the so-called nuclear pools. This paper explains the four main principles behind nuclear liability insurance and discusses their application to Central Europe and in particular to the problems facing the nuclear industry in Eastern Europe. (author)

  9. Development of database for spent fuel and special waste from the Spanish nuclear power plants; Desarrollo de la base de datos para el combustible gastado y residuos especiales de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Gandal, R.; Rodriguez Gomez, M. A.; Serrano, G.; Lopez Alvarez, G.

    2013-07-01

    GNF Engineering is developing together with ENRESA and with the UNESA participation, the spent fuel and high activity radioactive waste data base of Spanish nuclear power plants. In the article is detailed how this strategic project essential to carry out the CTS (centralized temporary storage) future management and other project which could be emerged is being dealing with, This data base will serve as mechanics of relationship between ENRESA and Spanish NPPS, covering the expected necessary information to deal with mentioned future management of spent fuel and high activity radioactive waste. (Author)

  10. Central Institute for Nuclear Research (1956 - 1979)

    International Nuclear Information System (INIS)

    The Central Institute for Nuclear Research (ZfK) of the Academy of Sciences of the GDR is presented. This first overall survey covers the development of the ZfK since 1956, the main research activities and results, a description of the departments responsible for the complex implementation of nuclear research, the social services for staff and the activities of different organizations in the largest central institute of the Academy of Sciences of the GDR. (author)

  11. Monitoring systems online of oil for transformers of nuclear power plants; Sistemas de monitorizacion online del aceite para transformadores de potencia de Centrales

    Energy Technology Data Exchange (ETDEWEB)

    Sarandeses, S.

    2014-07-01

    The nuclear power plants are showing their concern due to the existence of recent failures related to the bulky transformers of power. These transformers are not security, but are important for the production of power as its failure can cause transient on the floor, reactor scram or shooting, that can cause interruptions in the production of energy or might force us to reduce the power of production The analysis of gases dissolved in transformer oil is recognized as a trial key to identify a submerged transformer failure in oil. With this analysis it is not possible to ensure that there is no damage in the transformer, but the probability of risk of this type of failure can be reduced. The industry recommended to equip the new large power transformers with oil online monitoring systems and in some cases also be It recommended its use in existing transformers. (Author)

  12. Central Bureau for Nuclear Measurements

    International Nuclear Information System (INIS)

    The main task of CBNM is defined as the specific programme Nuclear Measurements and Reference Materials. In the field of neutron data for standards, for fission and for fusion application, the nuclear charge distribution and odd-even effects for mass, charge and neutron number in the cold spontaneous fission of 252Cf were determined. X- and γ-ray emission probabilities were evaluated in the frame of an IAEA coordinated Research Project. The subthermal fission cross section measurements of 235U, 233U and 239Pu, were finalised. The dependence of the experimental weighting function of C6D6 detectors on thickness of several 56Fe samples was determined. Fusion data studies involved the development of a light-ion telescope with improved time - and energy resolution. Double differential cross-sections of 9Be were analysed. Radionuclide metrology dealt with the response of silicon detectors, as well as with the standardization of 192Ir sources. Project Reference Materials reports the EC Certification of nuclear reference materials 210 (PuO2), 523 (Al), 525 (Nb) and 526 (Nb). Progress was achieved in the preparation of dried solid spikes of uranium and plutonium for undiluted reprocessing input solution analysis. 10B and 6Li deposits were prepared for a redetermination of the neutron lifetime. Preliminary studies on speciation of trace metals in biological fluids were successful. Radioactive waste barrels were analysed by γ-scanning and blood samples were irradiated with 0.6 MeV neutrons. Exploratory research resulted in first measurements of transition radiation properties

  13. Nuclear energy options for Central Asia

    International Nuclear Information System (INIS)

    Full text: The five countries of Central Asia have a strong basis for the development of commercial nuclear energy. Several test reactors have operated within the region, including the Ak tau BN350 - a very advanced fast breeder reactor combined with a large water desalination plant. The Central Asian countries have a large cadre of well-trained nuclear scientists and engineers who could operate and maintain nuclear power plants and expanded nuclear fuel infrastructure as they evolve. The Central Asia region experiences significant demand for base-load energy in major population centers and industrial development areas. A well-developed electricity transmission grid could transmit nuclear-generated electricity from the power stations to the load centers. Finally, given the large land area and the relatively small population (in relation to the size of the region) there exist many remote and stable sites where nuclear generation centers can be sited and connected to the transmission grid. A good example is the Semipalatinsk Nuclear Test Site (STS) whose vast area could easily contain several nuclear power plants, which would be cooled by the water flow of the Irtish River. The Kazakhstan authorities have already identified several potential nuclear power plant sites within the national transmission system, the STS being one such prospective site. The large-scale availability of uranium in the region affords the uranium exporting countries - particularly Kazakhstan and Uzbekistan - significant leverage with international nuclear reactor vendors in establishing the terms for nuclear plant imports into the region. Such leverage could further be increased if multiple reactor orders are submitted, for instance by two or more countries ordering similar types of plants to be installed at various sites in their territories. The added value of the uranium exports from Central Asia does not have to be measured only in terms of supporting the development of fuel cycle

  14. Central depression of nuclear charge density distribution

    International Nuclear Information System (INIS)

    The center-depressed nuclear charge distributions are investigated with the parametrized distribution and the relativistic mean-field theory, and their corresponding charge form factors are worked out with the phase shift analysis method. The central depression of nuclear charge distribution of 46Ar and 44S is supported by the relativistic mean-field calculation. According to the calculation, the valence protons in 46Ar and 44S prefer to occupy the 1d3/2 state rather than the 2s1/2 state, which is different from that in the less neutron-rich argon and sulfur isotopes. As a result, the central proton densities of 46Ar and 44S are highly depressed, and so are their central charge densities. The charge form factors of some argon and sulfur isotopes are presented, and the minima of the charge form factors shift upward and inward when the central nuclear charge distributions are more depressed. Besides, the effect of the central depression on the charge form factors is studied with a parametrized distribution, when the root-mean-square charge radii remain constant.

  15. Nuclear Safety in Central and Eastern Europe

    International Nuclear Information System (INIS)

    Nuclear safety is one of the critical issues with respect to the enlargement of the European Union towards the countries of Central and Eastern Europe. In the context of the enlargement process, the European Commission overall strategy on nuclear safety matters has been to bring the general standard of nuclear safety in the pre-accession countries up to a level that would be comparable to the safety levels in the countries of the European Union. In this context, the primary objective of the project was to develop a common format and general guidance for the evaluation of the current nuclear safety status in countries that operate commercial nuclear power plants. Therefore, one of the project team first undertakings was to develop an approach that would allow for a consistent and comprehensive overview of the nuclear safety status in the CEEC, enabling an equal treatment of the countries to be evaluated. Such an approach, which did not exist, should also ensure identification of the most important safety issues of the individual nuclear power plants. The efforts resulted in the development of the ''Performance Evaluation Guide'', which focuses on important nuclear safety issues such as plant design and operation, the practice of performing safety assessments, and nuclear legislation and regulation, in particular the role of the national regulatory body. Another important aspect of the project was the validation of the Performance Evaluation Guide (PEG) by performing a preliminary evaluation of nuclear safety in the CEEC, namely in Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, and Slovenia. The nuclear safety evaluation of each country was performed as a desktop exercise, using solely available documents that had been prepared by various Western institutions and the countries themselves. Therefore, the evaluation is only of a preliminary nature. The project did not intend to re-assess nuclear safety, but to focus on a comprehensive summary

  16. UPVAPOR: computer application for the analysis of the results of Cofrentes Nuclear Power Plant production; UPVAPOR: Aplicacion informatica para el analisis de resultados de produccion en Central Nuclear Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, M. J.; Baraza Peregrin, A.; Bucho Piqueras, L.; Vaquer Perez, J. I.; Lopez Lopez, B.

    2010-07-01

    UPVapor is a software developed for the Cofrentes Nuclear Power Plant Group of Results. This application presents a graphical environment for analysis in which the user has available many variables registered to configure the graphics. This application saves a lot of time at work because it allows other users to do their own analysis without resorting to analysts.

  17. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico. Part 2; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico. Parte 2

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. de L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    At the present time the operation licenses in force for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) will expire in the year 2020 and 2025 for the Unit-1 and Unit-2, respectively, for which the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has begun its preparation to assist a solicitude of the licensee to continue the operation of the NPP-L V. The present work has the purpose of defining the steps to continue and to generate the documents that would help in this process, as the normative, guides, procedures, regulations, controls, etc. so that the evaluation process will be effective and efficient, as much for the regulator organ as for the licensee. The advance carried out in the continuation of the conformation of an evaluation process of license renovation solicitude is also exposed, taking like base the requirements established by the CNSNS, the regulator organ of the United States (US NRC), and the IAEA for license renovation solicitude of this type. A summary of the licenses granted from the beginning of commercial operation of the NPP-L V is included, both units and the amendments to these licenses, explaining the reason of the amendment shortly and in the dates they were granted. A brief exposition of the nuclear power plants to world level that have received extension of its operation is included. The normative that can be applied in a life extension evaluation is presented, the evaluation process to continue with the guides of the US NRC, the reach of the evaluation and the minimum information required to the licensee that should accompany to their solicitude. (author)

  18. Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M. L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    So that the construction stages, of operation, closing, dismantlement and the radioactive waste disposal of a nuclear power plant (NPP) are carried out in Mexico, is necessary that the operator has a license, permission or authorization for each stage. In Mexico, these licenses, permissions or authorizations are granted by the Energy Secretariat with base in the verdict of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). The operation licenses ar the moment effective for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) they will expire respectively in the year 2020 and 2025 for the Unit 1 and Unit 2, for what the CNSNS has begun its preparation before a potential solicitude of the licensee to continue the operation of the NPP-L V. Defining the process to continue and to generate the documents that would help in this phase as normalization, guides, procedures, regulations, controls, etc., is the task that intends to be carried out the regulator body so that the evaluation process is effective and efficient, so much for the same regulator body as for the licensee. This work exposes the advance that the CNSNS has in this aspect and is centered specifically in the conformation of an evaluation process of license renovation solicitude, taking as base what the regulator body of the United States of North America (US NRC) established and following to the IAEA. Also, this work includes statistical of electric power production in Mexico, licensing antecedents for the NPP-L V, a world perspective of the license renovations and the regulation of the US NRC related to the license renovation of a NPP. (Author)

  19. Regulator process for the authorization of an amendment to the operation license of a nuclear power plant in Mexico; Proceso regulador para la autorizacion de una enmienda a la licencia de operacion de una central nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Perez, R.; Espinosa V, J.M.; Salgado, J.R.; Mamani, Y.R. [CNSNS, Dr. Barragan 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)

    2005-07-01

    The regulator process by which an authorization is granted from an amendment to the License of Operation of a nuclear power station in Mexico is described. It makes an appointment the effective legal mark, the technical characteristics of the modification, the evaluation process and deposition upon oath of tests and finally the elaboration of the Safety report and the Technical Verdict that is a correspondent for the regulator organism to the Secretary of Energy, the one that in turn is the responsible of granting the amendment the License just as it establishes it the Law. (Author)

  20. The Influence of Soft Contact Lens Materials on the Central, Para-Central and Peripheral Corneal Endothelium

    OpenAIRE

    Lloyd McKernan, Aoife; Simo Mannion, Luisa; O'Dwyer, Veronica

    2015-01-01

    Title: The influence of soft contact lens materials on the central, para-central and peripheral corneal endothelium prior to and following two weeks cessation of soft contact lens wear. Purpose: To examine the influence of a variety of soft contact lens (SCL) materials on the central, para-central and peripheral corneal endothelium measurements, prior to and following two weeks cessation of SCL wear. Methods: Endothelial measurements were taken using the CEM-530 (Nidek, Japan) specular ...

  1. Towards Quantum Transport for Central Nuclear Reactions

    CERN Document Server

    Danielewicz, Pawel; Barker, Brent

    2016-01-01

    Nonequilibrium Green's functions represent a promising tool for describing central nuclear reactions. Even at the single-particle level, though, the Green's functions contain more information that computers may handle in the foreseeable future. In this study, we explore slab collisions in one dimension, first in the mean field approximation and demonstrate that only function elements close to the diagonal in arguments are relevant, in practice, for the reaction calculations. This bodes well for the application of the Green's functions to the reactions. Moreover we demonstrate that an initial state for a reaction calculation may be generated through adiabatic transformation of interactions. Finally, we report on our progress in incorporating correlations into the dynamic calculations.

  2. Central depression of the nuclear charge distribution

    International Nuclear Information System (INIS)

    As a systematic feature of all measured charge distributions we find a shift in the form-factor zeroes as compared to a simple folding model. To first order, this shift can be interpreted as resulting from the central depression w, caused by the Coulomb repulsion. Accounting for it leads to an increase in the surface width of nuclear charge distributions by 0.105 fm. This interpretation of the experimental findings is compared with the droplet model, which relates w with the compression modulus K and the asymmetry energy J. Accounting for w leads to an increase in the extrapolated nuclear matter density by 7.5%. However, this macroscopic model is not able to describe the experimental results in detail since w is also influenced by shell effects. HF+BCS calculations with effective Skyrme-type interactions reproduce part of the data, revealing the influence of shells on w. Here, too, there remain discrepancies in details. A level of accuracy is reached at which most probably also the skewness of the charge distribution must be taken into account. (orig.)

  3. Fourth Regional Meeting: Nuclear Energy in Central Europe, Proceedings

    International Nuclear Information System (INIS)

    Fourth Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 89 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accidents, Ageing and Integrity, Thermal Hydraulics, NPP Operation Experiance, Radioactive Waste Management, Environment and Other Aspects, Public and Nuclear Energy, SG Replacement and Plant Uprating.

  4. The French national system for centralized accounting of nuclear materials

    International Nuclear Information System (INIS)

    The French national system for centralized accounting of nuclear materials located on French soil is described. Texts of accountancy regulations and operator's obligations, which determine the technical conditions for nuclear material management are presented. The NUclear Material Operation Declaration Form used for declaring changes in inventory is considered. The hardware configuration of the automated accounting system for nuclear materials consists of multiprocessor mini-computer, SUN computers, a SYBASE relational database manager and optical fiber network

  5. Central Institute of Nuclear Research Rossendorf 25 years old

    International Nuclear Information System (INIS)

    A colloquium dedicated the 25th anniversary of the foundation of the Central Institute for Nuclear Research of the GDR Academy of Sciences was held on January, 21st, '81. 13 papers were given which dealt with aspects of the institute's history as well as with modern trends in nuclear and solid state physics, nuclear energy and chemistry, radioisotope production, radiation protection and nuclear information. (author)

  6. Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

    International Nuclear Information System (INIS)

    Third Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 71 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accident management, Thermal Hydraulics, NPP Operation, Radioactive Waste Management, Main Components Integrity, Environment and Other Aspects and Public Information

  7. Technical economic feasibility study for the implementation of a nuclear power plant for the production of electricity in Colombia; Estudio de factibilidad tecnico economica para la implementacion de una central de energia nuclear para la produccion de energia electrica en Colombia

    Energy Technology Data Exchange (ETDEWEB)

    Gonzales, David E.; Bolanos, Hernan G.; Mayorga, Manuel A.; Rodriguez, Edwin A., E-mail: david_egO@yahoo.es, E-mail: hernanbolaos@yahoo.com.ar, E-mail: alejo_mayorga@yahoo.com, E-mail: edwin.rodriguez@distoyota.com.co [Escuela Colombiana de Carreras Industriales (ECCI), Bogota (Colombia). Grupo de Investigacion GIATME

    2013-07-01

    A study on the technical and economic feasibility will be used to implement a nuclear power in Colombia to generate electricity. To this will be searched if there are previous studies on this topic and what they concluded. The manner in which power is supplied will be discussed in a national level nowadays, its strengths and weaknesses. It will be investigated the legal norms that exists in the country on nuclear power and renewable energy sources, the standards established at world level, the nuclear accidents and the great examples. Providers will be sought on the world market nuclear equipment which serve to this purpose and the technical characteristics of these equipment will be discussed. The type of fuel used in nuclear reactors, its origin, method of production, specifications, availability and long-term and safe handling and final disposal are considered. safe handling of this technology and policy or international rules that will studied.

  8. Critérios de estabilidade atmosférica para a região da Central Nuclear Almirante Álvaro Alberto, Angra dos Reis - RJ Criteria of atmospheric stability for the region around the nuclear power plant Almirante Álvaro Alberto, Angra dos Reis - RJ

    Directory of Open Access Journals (Sweden)

    José Francisco De Oliveira Júnior

    2010-06-01

    Full Text Available Realizaram-se avaliações climatológicas, sazonais e diárias, da estabilidade atmosférica na região da Central Nuclear Almirante Álvaro Alberto (CNAAA, Angra dos Reis - RJ. A climatológica foi baseada no critério de Pasquill-Gifford (P-G para um período de 26 anos (1980-2006 e a sazonal-diária pelos números de Richardson Global (RiB e de Froude (Fr - estudo de caso (2002-05. O Fr foi usado na caracterização do escoamento da região. O critério de P-G mostrou que as classes predominantes foram D, E e F (no período noturno e diurno. Avaliaram-se as classes predominantes com a direção e velocidade do vento, os setores mais freqüentes foram S, SSW, SSE no período diurno e N, NNE, NNW e E no noturno. Quanto à velocidade verificou-se que a classe D foi mais veloz, e as classes E e F menos velozes, em qualquer período. As maiores velocidades foram coincidentes com a brisa marítima. Baseado no RiB, a condição estaticamente estável prevaleceu em comparação às demais, sendo de 79%, seguida da instável (17% e neutra (4%. O Fr indicou que o escoamento na CNAAA foi caracterizado por regime de vento fraco, com forte estabilidade e ar estagnado. A maior parte das ocorrências (63% foi para Fr inferior a 0,1, seguida de poucas ocorrências nas categorias Fr igual a 1,0 (8% e superior a 1,7 (12%. Os critérios utilizados na caracterização da estabilidade na região e na análise do regime de escoamento indicaram a baixa capacidade da atmosfera para a dispersão de poluentes, devido à predominância da condição estável e do regime de bloqueio.The atmospheric stability over the nuclear power plant Almirante Álvaro Alberto (CNAAA, Angra dos Reis - RJ, Brazil, was analyzed at climatological, seasonal, and daily scales. The climatologic analysis was based on the Pasquill-Gifford (P-G for a long-term series of 26 years (1980 - 2006, while the seasonal/daily was performed using the Global Richardson number, RiB, and the Froude number

  9. Nuclear Science Curriculum and Curriculum para la Ciencia Nuclear.

    Science.gov (United States)

    American Nuclear Society, La Grange Park, IL.

    This document presents a course in the science of nuclear energy, units of which may be included in high school physics, chemistry, and biology classes. It is intended for the use of teachers whose students have already completed algebra and chemistry or physics. Included in this paper are the objectives of this course, a course outline, a…

  10. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1995-07-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  11. Energia nuclear: Uma solução para Portugal?

    OpenAIRE

    Pedro Cosme Costa Vieira

    2006-01-01

    As pessoas receiam a energia nuclear por diversas razões. Foi desenvolvida no contexto de uma guerra mundial, é a base da “destruição mútua garantida”, houve o acidente de Chernobyl e é necessário guardar o combustível utilizado durante vários séculos. Mas Portugal não tem recursos energéticos e precisa de energia para se desenvolver sem aumentar a emissão para a atmosfera de dióxido de carbono. No sentido de informar sobre a solução nuclear, neste trabalho explico a tecnologia e apresento um...

  12. Nuclear Power in South-Central Brazil

    International Nuclear Information System (INIS)

    The region of South-Central Brazil includes the states of Sao Paulo, Rio de Janeiro, Guanabara and Minas Gerais. The most recent power study was made by Canambra Engineering Consultants Limited. This group reported that the public-grid electricity output for the area in 1962 was 2.16 GW (average generation), with an installed capacity of 3.41 GW and annual mean load factor of 63.4; an increase in power requirements for 1970 was forecast, corresponding to an average output of 5.37 GW and an installed capacity of 8.3 GW. This forecast was based on an annual growth rate of 11.9% in generation. ''The energy requirements have grown at an average annual rate of 10.9% since 1955; however, the present forecast is based on the assumption of power being available as required, and hence includes the suppressed demand resulting from existing restrictions in generating and distribution capacity''

  13. 30 years of Central Institute for Nuclear Research at Rossendorf

    International Nuclear Information System (INIS)

    A celebration and a scientific colloquium dedicated the 30th anniversary of the foundation of the Central Institute for Nuclear Research (CINR) of the GDR Academy of Sciences were held on January, 23rd and 24th, '86 at Rossendorf. The speaches and lectures given by the president of the GDR Academy of Sciences and by scientists of the CINR dealt with problems of policy of science, history of the CINR, nuclear methods, microelectronics, nuclear energy research, development and production of radioisotopes and scientific instruments. (author)

  14. U. S. Central Station Nuclear Power Plants: operating history

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission.

  15. U.S. Central Station Nuclear Power Plants: operating history

    International Nuclear Information System (INIS)

    The information assembled in this booklet highlights the operating history of U. S. Central Station nuclear power plants through December 31, 1976. The information presented is based on data furnished by the operating electric utilities. The information is presented in the form of statistical tables and computer printouts of major shutdown periods for each nuclear unit. The capacity factor data for each unit is presented both on the basis of its net design electrical rating and its net maximum dependable capacity, as reported by the operating utility to the Nuclear Regulatory Commission

  16. Centrales nucleares en España : el parón nuclear

    OpenAIRE

    Sanz Díaz, Benito (1949-)

    1984-01-01

    Este libro constituye una oportuna y valiosa contribución a ese necesario debate nacional sobre la energía nuclear. Tiene como objetivo la central nuclear de Cofrentes, una de las postreras y más singulares —tanto por su modelo como por su emplazamiento e historia de construcción— de las centrales nucleares que entrarán en funcionamiento en nuestro país. El libro, sin embargo, aporta información sobre la totalidad del programa nuclear español y su permanente visión económica garantiza la vía ...

  17. Internal event analysis for Laguna Verde Unit 1 Nuclear Power Plant. Accident sequence quantification and results; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Cuantificacion de secuencias de accidente y resultados

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1994-07-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant, CNSNS-TR 004, in five volumes. The reports are organized as follows: CNSNS-TR 004 Volume 1: Introduction and Methodology. CNSNS-TR4 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR 004 Volume 3: System Analysis. CNSNS-TR 004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR 005 Volume 5: Appendices A, B and C. This volume presents the development of the dependent failure analysis, the treatment of the support system dependencies, the identification of the shared-components dependencies, and the treatment of the common cause failure. It is also presented the identification of the main human actions considered along with the possible recovery actions included. The development of the data base and the assumptions and limitations in the data base are also described in this volume. The accident sequences quantification process and the resolution of the core vulnerable sequences are presented. In this volume, the source and treatment of uncertainties associated with failure rates, component unavailabilities, initiating event frequencies, and human error probabilities are also presented. Finally, the main results and conclusions for the Internal Event Analysis for Laguna Verde Nuclear Power Plant are presented. The total core damage frequency calculated is 9.03x 10-5 per year for internal events. The most dominant accident sequences found are the transients involving the loss of offsite power, the station blackout accidents, and the anticipated transients without SCRAM (ATWS). (Author)

  18. Internal event analysis of Laguna Verde Unit 1 Nuclear Power Plant. System Analysis; Analisis de Eventos Internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Analisis de sistemas

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis of Laguna Verde Unit 1 Nuclear Power Plant{sup ,} CNSNS-TR-004, in five volumes. The reports are organized as follows: CNSNS-TR-004 Volume 1: Introduction and Methodology. CNSNS-TR-004 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR-004 Volume 3: System Analysis. CNSNS-TR-004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR-004 Volume 5: Appendices A, B and C. This volume presents the results of the system analysis for the Laguna Verde Unit 1 Nuclear Power Plant. The system analysis involved the development of logical models for all the systems included in the accident sequence event tree headings, and for all the support systems required to operate the front line systems. For the Internal Event analysis for Laguna Verde, 16 front line systems and 5 support systems were included. Detailed fault trees were developed for most of the important systems. Simplified fault trees focusing on major faults were constructed for those systems that can be adequately represent,ed using this kind of modeling. For those systems where fault tree models were not constructed, actual data were used to represent the dominant failures of the systems. The main failures included in the fault trees are hardware failures, test and maintenance unavailabilities, common cause failures, and human errors. The SETS and TEMAC codes were used to perform the qualitative and quantitative fault tree analyses. (Author)

  19. The nuclear sector in Russia and Central Europe

    International Nuclear Information System (INIS)

    This document is a compilation of texts presented during a workshop at the French National Assembly (Paris, December 2, 1993). Participants are political, economical, technical or military specialists of the nuclear question in Eastern countries and Russia and comes from various French, European or international organisations involved in nuclear industry. The aim of the workshop is to debate about the economical and safety aspects of nuclear installations in Eastern and Central Europe countries, and about the financial and human means that occidental countries can provide for the improvement of installations safety. Also political and military aspects of the international control of nuclear trade, nuclear weapons and fissile materials management in the Independent States Community is discussed. (J.S.). 4 figs., 13 tabs

  20. Nuclear Research and Development Institutes in Central and Eastern Europe

    International Nuclear Information System (INIS)

    The science and technology (S and T) sector is faced today with complex and diverse challenges. National science budgets are under pressure, and many countries are changing how research and development (R and D) is funded, reducing direct subsidies and introducing competition for both governmental and alternative sources of revenue. On the other hand, the transition toward knowledge-based economies is creating new opportunities in the S and T sector as governments look to it to foster economic growth through innovation. A number of countries in Central and Eastern Europe have recently joined the European Union (EU) which has defined the Lisbon Strategy to create a 'knowledge triangle' of research, education and innovation to underpin the European economic and social model, and economic growth. This strategy seeks to increase investment in science and technology across the EU to a target of 3% of GDP by 2010, with two-thirds of funds coming from the private sector. By comparison, funding for R and D in most Central and Eastern European countries is only around 1% GDP, of which about 90% is provided by the governments. R and D has become more international, reflecting a more interdependent and globalized world. R and D progress is not only of interest to individual countries but also tries to respond to the needs of a broader society. Governments still maintain national networks, but increasingly emphasize international cooperation, both to avoid duplication of expensive infrastructure, and because scientific excellence requires an exchange of ideas and cooperation that crosses borders. These challenges and opportunities directly impact the research and development institutes (RDIs), including the nuclear RDIs. It is important for the nuclear RDIs to take account of these trends in the broader S and T sector in their vision and strategy. Several nuclear RDIs have become very successful, but others are struggling to adapt. The challenges have been particularly severe

  1. Analysis of internal events for the Unit 1 of the Laguna Verde nuclear power station; Analisis de eventos internos para la Unidad 1 de la Central Nucleolelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    This volume presents the results of the starter event analysis and the event tree analysis for the Unit 1 of the Laguna Verde nuclear power station. The starter event analysis includes the identification of all those internal events which cause a disturbance to the normal operation of the power station and require mitigation. Those called external events stay beyond the reach of this study. For the analysis of the Laguna Verde power station eight transient categories were identified, three categories of loss of coolant accidents (LOCA) inside the container, a LOCA out of the primary container, as well as the vessel break. The event trees analysis involves the development of the possible accident sequences for each category of starter events. Events trees by systems for the different types of LOCA and for all the transients were constructed. It was constructed the event tree for the total loss of alternating current, which represents an extension of the event tree for the loss of external power transient. Also the event tree by systems for the anticipated transients without scram was developed (ATWS). The events trees for the accident sequences includes the sequences evaluation with vulnerable nucleus, that is to say those sequences in which it is had an adequate cooling of nucleus but the remoting systems of residual heat had failed. In order to model adequately the previous, headings were added to the event tree for developing the sequences until the point where be solved the nucleus state. This process includes: the determination of the failure pressure of the primary container, the evaluation of the environment generated in the reactor building as result of the container failure or cracked of itself, the determination of the localization of the components in the reactor building and the construction of boolean expressions to estimate the failure of the subordinated components to an severe environment. (Author)

  2. Nuclear Research Center Karlsruhe, Central Safety Department. Annual report 1992

    International Nuclear Information System (INIS)

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, biophysics of multicellular systems, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1992 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.)

  3. Proceedings of the Second Regional Meeting on Nuclear Energy in Central Europe

    International Nuclear Information System (INIS)

    Second Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contains 75 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region

  4. Oficinas centrales para Burlington Corporate - Greensboro (EE. UU.

    Directory of Open Access Journals (Sweden)

    Odell, Associates Inc. Arquitectos

    1972-05-01

    Full Text Available Built with the fundamental idea of putting into effect the character and requirements of the privately-owned company, while at the same time satisfying its commercial necessities, these central offices present us with an expressive example of the combination of two important building materials, glass and steel. The criteria adopted as guide-lines allowed significant advantages to be obtained in those aspects which are most influential when deciding the kind of building to be erected —all by means of well-studied coordination.Realizadas con la idea fundamental de materializar el carácter y exigencias de la empresa propietaria, a la vez que satisfacer sus necesidades de índole comercial, nos ofrecen estas oficinas centrales un expresivo ejemplo de combinación de dos importantes materiales constructivos: vidrio y acero. Los criterios adoptados como directrices permitieron conseguir unas significativas ventajas en aquellos aspectos más Influyentes a la hora de decidir el tipo de construcción. Todo ello mediante una coordinación muy estudiada.

  5. AP1000, a nuclear central of advanced design; AP1000, una central nuclear de diseno avanzado

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, N.; Viais J, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: nhm@nuclear.inin.mx

    2005-07-01

    The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

  6. Annual progress report on nuclear data 1983 of the Central Bureau for Nuclear Measurements, Geel (Belgium)

    International Nuclear Information System (INIS)

    In this progress report of the Central Bureau for Nuclear Measurements at Geel (Belgium) researches related to neutron data and to non-neutron nuclear data are gathered. Neutron data are essentially related to cross-section measurements: for instance, concerning actinides, structural materials as Cr and Fe, fission products. Some studies are classified as concerning standard neutron data. Underlying physics is no forgotten neither than equipment (linear accelerator). Non-neutron nuclear data is concerned essentially with decay studies. Some compilations and evaluations are also given. Improvement of measurement and source preparation techniques is a part of this section

  7. Karlsruhe Nuclear Research Center, Central Safety Department. Annual report 1993

    International Nuclear Information System (INIS)

    The Central Safety Department is responsible for handling all tasks of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: behavior of trace elements in the environment and decontamination of soil, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurements and personnel dosimetry. This report gives details of the different duties, indicates the results of 1993 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.)

  8. Nuclear legislation in Central and Eastern Europe and the NIS

    CERN Document Server

    2000-01-01

    This publication examines the legislation and regulations governing the peaceful uses of nuclear energy in eastern European countries. It covers 11 countries from Central and Eastern Europe and 11 countries from the New Independent States. The chapters follow a systematic format making it easier for the reader to carry out research and compare information. This study will be updated regularly. Albania Kazakhstan Armenia Latvia Belarus Lithuania Bosnia and Herzegovina Poland Bulgaria Republic of Moldova Croatia Romania Czech Republic Russian Federation Estonia Slovak Republic Former Yugoslav Re

  9. Búsqueda y análisis de nuevos métodos de seguimiento del funcionamiento de centrales nucleares PWR

    OpenAIRE

    Roca-Cusachs Maennicke, Beatriz

    2006-01-01

    El siguiente proyecto ha sido realizado en el departamento STEP (Simulation and information technologies for power generation systems) de la división R&D (investigación y desarrollo) en la empresa EDF (Electricité de France). Este proyecto estudia nuevas metodologías de seguimiento del funcionamiento de una central nuclear mediante el programa CEF (Contrôle Economique du Fonctionnement), utilizado por las centrales para controlar el funcionamiento termodinámico del circuito secundario. El obj...

  10. Instrumentos de gestión de riesgos para centrales eólicas.

    OpenAIRE

    Sánchez de la Nieta López, Agustín Alejandro

    2013-01-01

    La tesis titulada "Instrumentos de gestion de riesgos para centrales eolicas" tiene por objeto desarrollar una estrategia de gestion de riesgos de un productor eolico en el mercado electrico español. Para implementar la estrategia de gestion de riesgos se realizaran modelos de prediccion de precios y vientos, modelos de optimizacion media-varianza y otros modelos, como el Valor en Riesto, Value at Risk (VaR) y el Valor Condicional del Riesgo, Conditional Value at Risk (CVaR). Los riesgos ...

  11. Piping information centralized management system for nuclear plant, PIMAS

    International Nuclear Information System (INIS)

    Piping works frequently cause many troubles in the progress of construction works, because piping is the final procedure in design and construction and is forced to suffer the problems in earlier stages. The enormous amount of data on quality control and management leads to the employment of many unskilled designers of low technical ability, and it causes confusion in installation and inspection works. In order to improve the situation, the ''piping information management system for nuclear plants (PIMAS)'' has been introduced attempting labor-saving and speed-up. Its main purposes are the mechanization of drafting works, the centralization of piping informations, labor-saving and speed-up in preparing production control data and material management. The features of the system are as follows: anyone can use the same informations whenever he requires them because the informations handled in design works are contained in a large computer; the system can be operated on-line, and the terminals are provided in the sections which require informations; and the sub-systems are completed for preparing a variety of drawings and data. Through the system, material control has become possible by using the material data in each plant, stock material data and the information on the revision of drawings in the design department. Efficiency improvement and information centralization in the manufacturing department have also been achieved because the computer has prepared many kinds of slips based on unified drawings and accurate informations. (Wakatsuki, Y.)

  12. Nuclear power in eastern and central Europe. Background paper

    International Nuclear Information System (INIS)

    The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab

  13. International Conference Nuclear Energy in Central Europe 99, V. 1. Proceedings

    International Nuclear Information System (INIS)

    International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 101 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Reactor Physics, Research Reactors, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation, Nuclear Energy and Public, Radioactive Waste, Radiological Protection and Environmental Issues, Nuclear Methods and Monte Carlo and Deterministic Transport Calculations

  14. Logistics of nuclear fuel production for nuclear submarines; Logistica de producao de combustiveis para submarinos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Leonam dos Santos [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil). E-mail: leosg@uol.com.br

    2000-07-01

    The future acquisition of nuclear attack submarines by Brazilian Navy along next century will imply new requirements on Naval Logistic Support System. These needs will impact all the six logistic functions. Among them, fuel supply could be considered as the one which requires the most important capacitating effort, including not only technological development of processes but also the development of a national industrial basis for effective production of nuclear fuel. This paper presents the technical aspects of the processes involved and an annual production dimensioning for an squadron composed by four units. (author)

  15. BORILAIN. Mobile device for automatic continuous supply of liquid injection system backup of a nuclear plant in emergency; BORILAIN. Dispositivo movil para el abastecimiento automatico en continuo del sistema de inyeccion del liquido de reserva de una central nuclear en situacion de emergencia

    Energy Technology Data Exchange (ETDEWEB)

    Lacalle, J.; Traino, J.; Troeung, J.; Arnaldos, A.; Alcaraz, D. A.; Lopez, B.; Ponce, A. T.

    2014-07-01

    This paper presents the design and development of the first automatic mobile device for the preparation of a neutron absorbing solution, and providing continuous, 30 days, of the injection system liquid reserve of a nuclear emergency. The work has been developed by GD Energy Services (GDES) for Electricite de France (EDF). (Author)

  16. Diseño del campo de heliostatos para torres solares de receptor central

    OpenAIRE

    Gómez Cristóbal, Alfonso

    2011-01-01

    En el presente proyecto se va a presentar una modelización matemática, en la aplicación Matlab, para realizar el diseño preliminar de un campo solar de heliostatos de una central termoeléctrica, basada en la tecnología de concentración solar con receptor central de torre. Primero, se estudiará el principal recurso energético con el que cuenta la humanidad, el Sol, sus características, cómo llega su energía a la Tierra en forma de radiación, y los distintos procesos que determinan la distribuc...

  17. Proceedings of the International Conference Nuclear Energy in Central Europe 2001

    International Nuclear Information System (INIS)

    International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 98 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: reactor physics, thermal hydraulics, probabilistic safety assessment (PSA) and severe accidents, nuclear materials, NPP and research reactor operation, environmental issues and radiation measurement, fusion, radioactive waste and regulatory issues and public relations

  18. Polarographic determination of Iodide and Iodate, in Solutions Coming from Aerosols in Fission Products Containment Studies in Nuclear Power Stations; Determinacion Polarografica de Especies de Iodo (Ioduro y Iodato) en Soluciones Procedentes de Aerosoles, para Estudios de Contencion de Productos de Fision en Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, M.; Ballesteros, O.; Fernandez, M.; Clavero, M.; Gonzalez, A. M. [Ciemat, Madrid (Spain)

    2000-07-01

    A polarographic method is described for the iodine species determination, iodide and iodate in water solutions. the iodate can be determined by differential pulse polarography. Calibration curves and the detection and determination limits have been obtained. Iodides is oxidized to iodate with sodium hypochlorite and the excess of oxidizing agent is destroyed with sodium sulphide. The concentration of iodide is calculated as the difference between the concentration of iodate in the sample before and after the oxidation. As an application, species of iodine in samples coming from the experimental plants GIRS (Gaseous Iodine Removal by Sprays) of Nuclear Fission Department of the CIEMAT, dedicated to fission products containment studies in nuclear power station, were determined. (Author) 10 refs.

  19. Visual interface for the automation of the instrumented pendulum of Charpy tests used in the surveillance program of reactors vessel of nuclear power plants; Interfase visual para la automatizacion del pendulo instrumentado de pruebas Charpy utilizado en el programa de vigilancia de la vasija de reactores de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Rojas S, A.S.; Sainz M, E.; Ruiz E, J.A. [ININ, Carretera Mexico-Toluca Km.36.5, Mpio. de Ocoyoacac, Estado de Mexico (Mexico)]. E-mail: asrs@nuclear.inin.mx; esm@nuclear.inin.mx; jare@nuclear.inin.mx

    2004-07-01

    Inside the Programs of Surveillance of the nuclear power stations periodic information is required on the state that keep the materials with those that builds the vessel of the reactor. This information is obtained through some samples or test tubes that are introduced inside the core of the reactor and it is observed if its physical characteristics remain after having been subjected to the radiation changes and temperature. The rehearsal with the instrumented Charpy pendulum offers information on the behavior of fracture dynamics of a material. In the National Institute of Nuclear Research (ININ) it has an instrumented Charpy pendulum. The operation of this instrument is manual, having inconveniences to carry out rehearsals with radioactive material, handling of high and low temperatures, to fulfill the normative ones for the realization of the rehearsals, etc. In this work the development of a computational program is presented (virtual instrument), for the automation of the instrumented pendulum. The system has modules like: Card of data acquisition, signal processing, positioning system, tempered system, pneumatic system, compute programs like it is the visual interface for the operation of the instrumented Charpy pendulum and the acquisition of impact signals. This system shows that given the characteristics of the nuclear industry with radioactive environments, the virtual instrumentation and the automation of processes can contribute to diminish the risks to the personnel occupationally exposed. (Author)

  20. Perfeccionamiento del modelo de vasija del reactor de la central de Ascó para el código de cálculo Relap5

    OpenAIRE

    Berggren Durall, Alberto

    2012-01-01

    El objetivo principal del proyecto realizado es el de perfeccionar el modelo de vasija de la central nuclear de Ascó utilizando el código de cálculo RELAP5/mod3.3. Con este fin se proponen y estudian tres variaciones en la modelación de la vasija perteneciente al modelo general de planta y se escogen dos escenarios relevantes para analizar y comparar los comportamientos. En primer lugar, a partir de un cambio real efectuado en la CNA se desarrolla una nueva nodalización de l...

  1. Ultrasonic meters in the feedwater flow to recover thermal power in the reactor of nuclear power plant of Laguna Verde U1 and U2; Medidores ultrasonicos en el flujo de agua de alimentacion para recuperar potencia termica en el reactor de la Central Nuclear Laguna Verde U1 and U2

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F. [CFE, Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)]. e-mail: francisco.tijerina@cfe.gob.mx

    2008-07-01

    The engineers in nuclear power plants BWRs and PWRs based on the development of the ultrasonic technology for the measurement of the mass, volumetric flow, density and temperature in fluids, have applied this technology in two primary targets approved by the NRC: the use for the recovery of thermal power in the reactor and/or to be able to realize an increase of thermal power licensed in a 2% (MUR) by 1OCFR50 Appendix K. The present article mentions the current problem in the measurement of the feedwater flow with Venturi meters, which affects that the thermal balance of reactor BWRs or PWRs this underestimated. One in broad strokes describes the application of the ultrasonic technology for the ultrasonic measurement in the flow of the feedwater system of the reactor and power to recover thermal power of the reactor. One is to the methodology developed in CFE for a calibration of the temperature transmitters of RTD's and the methodology for a calibration of the venturi flow transmitters using ultrasonic measurement. Are show the measurements in the feedwater of reactor of the temperature with RTD's and ultrasonic measurement, as well as the flow with the venturi and the ultrasonic measurement operating the reactor to the 100% of nominal thermal power, before and after the calibration of the temperature transmitters and flow. Finally, is a plan to be able to realize a recovery of thermal power of the reactor, showing as carrying out their estimations. As a result of the application of ultrasonic technology in the feedwater of reactor BWR-5 in Laguna Verde, in the Unit 1 cycle 13 it was recover an equivalent energy to a thermal power of 25 MWt in the reactor and an exit electrical power of 6 M We in the turbogenerator. Also in the Unit 2 cycle 10 it was recover an equivalent energy to a thermal power of 40 MWt in the reactor and an exit electrical power of 16 M We in the turbogenerator. (Author)

  2. Aceitabilidade de um futuro banco de objetos simuladores para controle de qualidade em medicina nuclear

    OpenAIRE

    Fernanda Carla Lima Ferreira; Divanizia do Nascimento Souza

    2011-01-01

    OBJETIVO: O objetivo deste trabalho foi verificar a aceitabilidade para a implantação no Brasil de um banco de objetos simuladores nacional, ou bancos regionais, para uso compartilhado desses objetos em atividades de controle de qualidade nos serviços de medicina nuclear. MATERIAIS E MÉTODOS: Foram analisadas as respostas dadas em um questionário que foi enviado a supervisores de radioproteção e físicos médicos de serviços de medicina nuclear do Brasil. Inicialmente, o questionário foi valida...

  3. US central station nuclear electric generating units: significant milestones

    International Nuclear Information System (INIS)

    Listings of US nuclear power plants include significant dates, reactor type, owners, and net generating capacity. Listings are made by state, region, and utility. Tabulations of status, schedules, and orders are also presented

  4. Collective phenomena in non-central nuclear collisions

    Energy Technology Data Exchange (ETDEWEB)

    Voloshin, Sergei A.; Poskanzer, Arthur M.; Snellings, Raimond

    2008-10-20

    Recent developments in the field of anisotropic flow in nuclear collision are reviewed. The results from the top AGS energy to the top RHIC energy are discussed with emphasis on techniques, interpretation, and uncertainties in the measurements.

  5. Ortho-para mixing hyperfine interaction in the H2O+ ion and nuclear spin equilibration.

    Science.gov (United States)

    Tanaka, Keiichi; Harada, Kensuke; Oka, Takeshi

    2013-10-01

    The ortho to para conversion of water ion, H2O(+), due to the interaction between the magnetic moments of the unpaired electron and protons has been theoretically studied to calculate the spontaneous emission lifetime between the ortho- and para-levels. The electron spin-nuclear spin interaction term, Tab(SaΔIb + SbΔIa) mixes ortho (I = 1) and para (I = 0) levels to cause the "forbidden" ortho to para |ΔI| = 1 transition. The mixing term with Tab = 72.0 MHz is 4 orders of magnitude higher for H2O(+) than for its neutral counterpart H2O where the magnetic field interacting with proton spins is by molecular rotation rather than the free electron. The resultant 10(8) increase of ortho to para conversion rate possibly makes the effect of conversion in H2O(+) measurable in laboratories and possibly explains the anomalous ortho to para ratio recently reported by Herschel heterodyne instrument for the far-infrared (HIFI) observation. Results of our calculations show that the ortho ↔ para mixings involving near-degenerate ortho and para levels are high (∼10(-3)), but they tend to occur at high energy levels, ∼300 K. Because of the rapid spontaneous emission, such high levels are not populated in diffuse clouds unless the radiative temperature of the environment is very high. The low-lying 101 (para) and 111 (ortho) levels of H2O(+) are mixed by ∼10(-4) making the spontaneous emission lifetime for the para 101 → ortho 000 transition 520 years and 5200 years depending on the F value of the hyperfine structure. Thus the ortho ↔ para conversion due to the unpaired electron is not likely to seriously affect thermalization of interstellar H2O(+) unless either the radiative temperature is very high or number density of the cloud is very low. PMID:23530629

  6. Nuclear magnetic resonance imaging of the central nervous system

    International Nuclear Information System (INIS)

    In this article a review is given of the use of magnetic resonance imaging for the central nervous system. An example of the screening of the population for multiple scelerosis is given. A good preliminary examination and the supply of relevant information to the person which performs the imaging is necessary. (R.B.). 9 figs.; 4 tabs

  7. The Staffing of Central Electricity Generating Board Nuclear Power Stations

    International Nuclear Information System (INIS)

    An account is given of the staffing requirements and organization at a CEBG nuclear power station. The training of staff and licensing requirements for reactoroperating staff are discussed. Experience gained to data of the outcome of pre-operating training and detailed planning in the operational sphere is given. (author)

  8. Harmonisation of Nuclear Emergency Preparedness in Central and Eastern Europe

    International Nuclear Information System (INIS)

    Under its Technical Co-operation programme the International Atomic Energy Agency has implementing a Regional Project RER/9/050:- Harmonisation of Regional Nuclear Emergency Preparedness for its Member States in the Europe region since 1997. The background of the project together with its achievements and future plans are presented in this paper. (author)

  9. Swedish support programme on nuclear non-proliferation in Central and Eastern Europe and Central Asia

    International Nuclear Information System (INIS)

    At the request of the Swedish Government, the Swedish Nuclear Power Inspectorate has established a support and co-operation programme in the area of nuclear non-proliferation with Russia and several of the republics of the former Soviet Union. The Programme was initiated in 1991 and an overall goal is to accomplish national means and measures for control and protection of nuclear material and facilities, in order to minimise the risk of proliferation of nuclear weapons and illicit trafficking of nuclear material and equipment. The objective of the Swedish Support Programme is to help each, so called, recipient State to be able to, independently and without help from outside, take the full responsibility for operating a national non-proliferation system and thereby fulfil the requirements imposed through the international legal instruments. This would include both the development and implementation of a modern nuclear legislation system, and the establishment of the components making up a national system for combating illicit trafficking. The support and co-operation projects are organised in five Project Groups (i.e. nuclear legislation, nuclear material control, physical protection, export/import control, and combating of illicit trafficking), which together cover the entire non-proliferation area. Up till June 2000, support and co-operation projects, completed and on-going, have been carried out in ten States, namely Armenia, Azerbaijan, Belarus, Georgia, Kazakstan, Latvia, Lithuania, Moldova, Russia and Ukraine. Furthermore, programmes have been initiated during the first part of 2000 with Estonia, Uzbekistan, Kyrgyzstan and Tajikistan. In addition, assistance has been given to Poland on a specific nuclear material accountancy topic. All projects are done on request by and in co-operation with these States. The total number of projects initiated during the period 1991 to June 2000 is 109, thereof 77 have been completed and 32 are currently on-going. It is the

  10. AP1000, a nuclear central of advanced design

    International Nuclear Information System (INIS)

    The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

  11. Nuclear power plant insurance in Central and Eastern Europe

    International Nuclear Information System (INIS)

    It was only after the decay of the Warsaw Pact, accompanied by emerging democratic structures and abolishment of the state monopolies, that an insurance market with private insurance companies had a chance to develop in these countries. West European insurance companies and their associations assisted and participated in this development by sending representatives and establishing branch offices. The paper reviews the current insurance regime for nuclear power plants of the Russian design types from the angle of international insurers as well as German insurance companies, referring to achievements so far and the foreseeable development. (orig./CB)

  12. Fuel operation of EDF nuclear fleet presentation of the centralized organization for operational engineering at the nuclear generation division

    International Nuclear Information System (INIS)

    The main feature of EDF Nuclear Fleet is the standardization, with 'series' of homogeneous plants (same equipment, fuel and operation technical documents). For fuel operation, this standardization is related to the concept of 'fuel management scheme' (typical fuel reloads with fixed number and enrichment of fresh assemblies) for a whole series of plants. The context of the Nuclear Fleet lead to the choice of a centralized organization for fuel engineering at the Nuclear Generation Division (DPN), located at UNIPE (National Department for Fleet Operation Engineering) in Lyon. The main features of this organization are the following: - Centralization of the engineering activities for fuel operation support in the Fuel Branch of UNIPE, - Strong real-time link with the nuclear sites, - Relations with various EDF Departments in charge of design, nuclear fuel supply and electricity production optimization. The purposes of the organization are: - Standardization of operational engineering services and products, - Autonomy with independent methods and computing tools, - Reactivity with a technical assistance for sites (24 hours 'hot line'), - Identification of different levels (on site and off site) to solve core operation problems, - Collection, analysis and valorization of operation feedback, - Contribution to fuel competence global management inside EDF. This paper briefly describes the organization. The main figures of annual engineering production are provided. A selection of examples illustrates the contribution to the Nuclear Fleet performance. (authors)

  13. Methodology for carrying out energy diagnosis in auxiliaries systems in thermal electrical central stations; Metodologia para realizar un diagnostico energetico en sistemas auxiliares de centrales termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Nebradt Garcia, Jesus [Comision Federal de Electricidad (CFE), Mexico, D. F. (Mexico); Rojas Hidalgo, Ismael; Huante Perez, Liborio [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1998-12-31

    One of the potential areas for energy saving in Central Electric Power Plants are the auxiliaries system, so as to based in a preliminary energy diagnosis and considering that energy saving measures would be taken, going from the instrumentation, operational changes in equipment, as well as in using velocity variators in motors, it turns out to be that the energy consumption of auxiliaries at 75% load in a 150 MW thermal power plant varies from 3% to 4% and for the case of a 350 MW power plant the energy consumption of the auxiliaries represents 2 to 3.5%. Nowadays this consumption are above 6%. Considering that the country has 40 units with capacities varying from 150 to 350 MW, the economical and the fuel saving would be substantial. This paper will present a summary of the methodology to be used to carry out this type of projects. [Espanol] Una de las areas potenciales de ahorro de energia en centrales termoelectricas son los sistemas auxiliares, de tal manera que basados en un diagnostico energetico preliminar y considerando que se aplicarian las medidas de ahorro de energia que van desde la instrumentacion, cambios operativos en equipos, asi como el uso de variadores de velocidad en motores, se tienen que los consumos de auxiliares para un 75% de carga en una central termoelectrica de 150 MW varian desde un 3% hasta un 4% y para el caso de una central termoelectrica de 350 MW, el consumo de auxiliares representa del 2 al 3.5%. Hoy en dia dichos consumos estan por encima del 6%. Si consideramos que el pais cuenta con 40 unidades que varian desde 150 MW hasta 350 MW, entonces los ahorros economicos y de combustible serian impactantes. La presente ponencia mostrara un resumen de la metodologia a emplear para la realizacion de este tipo de proyectos.

  14. The central dose register for the nuclear industry in Sweden

    International Nuclear Information System (INIS)

    A central dose register which is operated by decentral terminals has many great advantages. The register is as fast as possible updated. Data from the register can be obtained within seconds. Special hot jobs can be supervised easily and without time delay for dose information. It is very easy to handle a large number of personnel travelling around the country for maintenance. The computer in the system is a CDC Cyber 172 placed at Studsvik and the terminals are connected via telephone lines. Most dose information is automatically transferred to the dose register from automatic TLD readers of the Studsvik type. The dose register system also supervises the condition of the TLD readers and their calibration by the use of dosimeters which have been given a reference dose. The information from the system can be obtained on many different listings for year, quarter, month, department, personal history, job number, etc

  15. Colour of the nucleus as a marker of nuclear hardness, diameter and central thickness

    OpenAIRE

    Gullapalli Vamsi; Murthy Praveen; Murthy K

    1995-01-01

    Hundred and thirty patients, aged above 40 years, with senile cataract were examined. Age and colour were selected as the probable preoperative indicators of nuclear hardness. The lens material collected after manual extracapsular extraction was washed and the nucleus isolated. The diameter and central thickness of the nucleus were measured; the mean diameter and mean central thickness were 7.13 mm ± 0.76 and 3.05 mm ± 0.48, respectively. The hardness of the nucleus was measured...

  16. Safety doctrine for nuclear submarines in Brazil; Doutrina de seguranca para submarinos nucleares no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Leonam dos Santos

    2012-07-15

    The recognition of nuclear ship as a single system, incorporating the safety problems and the techniques of both naval and nuclear industry, constitutes a pressing need in order to make nuclear energy as a means of propulsion. Recognize the nuclear ship as the results of two major branches of engineering implies the need for a safety doctrine that deals with the ship and the nuclear facility as a system combining and synthesizing all aspects relevant to military ships as to the commercial nuclear power plants. The non-recognition of nuclear ship as a specific system results in the application of safety rules and regulations set for conventional ships, overlapping (and possibly conflicting) rules and regulations developed to nuclear power plants. This approach does not lead to an optimization of design and operation of the ship, neither from the safety nor from the functional point of view. The paper presents the aspects of naval, nuclear and nuclear ships safety, the application of the doctrine, the control methods and conclusions. (author)

  17. Annual report 89. Central Bureau for nuclear measurements

    International Nuclear Information System (INIS)

    This report covers CBNM's activities during the second year of the multiannual programme 1988-91. Its contents and form reflect the change in the role and in the working conditions of the Joint Research Center of which CBNM is an institute. The main task of CBNM as covered by the European Communities Framework Programme is defined as the specific programme Nuclear Measurements and Reference Materials. The activities of the CBNM - like for the other institutes of the JRC - are only in part funded as Specific Programme. A small proportion of the specific programme budget is allotted to Exploratory Research, in preparation of possible extensions of existing competences or of potential new activities. Parts of the funding are coming from Support to Other Commission Services and from Work for Third Parties on the basis of contracts. 36 contributions have been presented during a series of international conferences; 24 articles have been submitted for publication in scientific/technical journals

  18. NATO nuclear reductions and the assurance of Central and Eastern European Allies

    OpenAIRE

    Guthe, Kurt

    2013-01-01

    Recent years have seen a debate within NATO over the issue of whether U.S. nonstrategic nuclear weapons in Europe should be retained in their current status, reduced in number, or withdrawn from the Continent. Some countries, including Germany, the Netherlands, and Belgium have advocated removal of the weapons. Others, notably member states in Central and Eastern Europe (CEE) are wary of changes in the nuclear posture of the alliance. The position of the United States and NATO as a whole i...

  19. Nuclear safety in the newly independent states in central and eastern Europe

    International Nuclear Information System (INIS)

    The Chernobyl nuclear reactor accident in 1986 has led to a reassessment of safety issues in the nuclear industry's of the Commonwealth of Independent States (CIS) and in central and eastern Europe. Three aspects of the problem are explained and addressed here, design inadequacies in the RBMK and other reactor types, less than adequate operational safety procedures and lack of independent government regulation of state utilities, allowing economic targets to overcome safe operation of plants. (UK)

  20. Disponibilidade de biomassa florestal residual para combustão na central termoeléctrica de Sines

    OpenAIRE

    Simas, Filipa Camacho da Silva Pinto e

    2013-01-01

    A presente dissertação consistiu na avaliação da disponibilidade de biomassa florestal residual para utilização como combustível na central termoeléctrica de Sines, para produção de electricidade. Por se tratar de uma central termoeléctrica com elevadas emissões de CO2 e pelas condições favoráveis de localização face à obtenção de biomassa, pretendeu-se quantificar e avaliar o potencial energético da biomassa florestal residual disponível de forma a substituir futuramente, parte do combust...

  1. Effect of nuclear spin symmetry in cold and ultracold reactions: D + para/ortho-H$_2$

    OpenAIRE

    Simbotin, I.; Côté, R

    2015-01-01

    We report results for reaction and vibrational quenching of the collision D with para-H$_2$($v,j=0$) and ortho-H$_2$($v,j=1$) at cold and ultracold temperatures. We investigate the effect of nuclear spin symmetry for barrier dominated processes ($0\\le v\\le 4$) and for one barrierless case ($v=5$). We find resonant structures for energies in the range corresponding to 0.01--10 K, which depend on the nuclear spin of H$_2$, arising from contributions of specific partial waves. We discuss the imp...

  2. Effect of nuclear spin symmetry in cold and ultracold reactions: D + para/ortho-H$_2$

    CERN Document Server

    Simbotin, I

    2015-01-01

    We report results for reaction and vibrational quenching of the collision D with para-H$_2$($v,j=0$) and ortho-H$_2$($v,j=1$) at cold and ultracold temperatures. We investigate the effect of nuclear spin symmetry for barrier dominated processes ($0\\le v\\le 4$) and for one barrierless case ($v=5$). We find resonant structures for energies in the range corresponding to 0.01--10 K, which depend on the nuclear spin of H$_2$, arising from contributions of specific partial waves. We discuss the implications on the results in this benchmark system for ultracold chemistry.

  3. Overview of nuclear legislation in Central and Eastern Europe and the NIS

    International Nuclear Information System (INIS)

    This study provides an overview of current legislation governing the peaceful uses of nuclear energy in Central and Eastern European countries and the New Independent States. Revised to include information obtained since its original publication in October 1995, the current issue focuses on the institutional and legal frameworks which have been established in the countries under consideration. The competent nuclear authorities, the legislation in force, draft legislation and regulations, international conventions and membership in nuclear organisations of each country in the region are presented. (K.A.)

  4. Nuclear energy for environmental protection; A energia nuclear para protecao do meio ambiente

    Energy Technology Data Exchange (ETDEWEB)

    Souza, Jair Albo Marques de

    1992-12-31

    In 1990 nuclear energy supplied about 17% of the total electric power produced in the world, what makes it the third most used power source after coal and hydropower. In this paper the advantages of using nuclear power for generating large quantities of electric power are presented 18 figs., 23 tabs.

  5. Estudo da viabilidade do preparo direto para descanso de cíngulo em incisivo central superior

    Directory of Open Access Journals (Sweden)

    ALENCAR José Freire de

    2000-01-01

    Full Text Available Esta pesquisa teve como finalidade estudar a viabilidade do preparo direto para descanso em cíngulo de incisivo central superior, por intermédio de processamento de imagem. Foram reproduzidos dez dentes íntegros, montados em um suporte de alumínio com resina acrílica e distribuídos entre cinco especialistas, que executaram os preparos para descanso. Em seguida, os corpos-de-prova foram cortados ao longo de suas coroas, tendo como guia um corte inicial, feito no centro da borda incisal de cada dente. O preparo foi então dimensionado, estabelecendo-se medidas lineares e angulares que permitissem uma análise comparativa entre o perfil original do dente e aquele após o preparo, enquanto se determinava a perfuração ou não da camada de esmalte. Todas as observações foram feitas, digitalizando-se os perfis e processando as imagens num programa específico. Dos cinqüenta modelos preparados, seguindo critérios estabelecidos, trinta e três perfuraram a camada de esmalte. Sendo assim, o incisivo central superior não está indicado para receber preparo direto para descanso de cíngulo.

  6. Energy and Centrality Dependences of Charged Multiplicity Density in Relativistic Nuclear Collisions

    Institute of Scientific and Technical Information of China (English)

    SA; Ben-hao; Bonasera; A; TAI; An

    2002-01-01

    Using a hadron and string cascade model, JPCIAE, the energy and centrality dependences of chargedparticle pseudo rapidity density in relativistic nuclear collisions were studied. Within the framework ofthis model, both the relativistic p + p experimental data and the PHOBOS and PHENIX Au + Au data at

  7. Teaching simulator for divulgation of the nuclear energy; Simulador docente para divulgacion de la energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ortega B, M.G.; Gutierrez F, R. [FI-UNAM, DEPFI Campus Morelos (Mexico)] e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    To solicitude of the authorities of the 'Universum' sciences museum of the UNAM, it develops a highly interactive computational system, to provide of information to the population in general about basic principles, uses and benefits of the nuclear energy. The objective is to achieve a better understanding and acceptance of the nuclear technology in our country. The system allows the visualization and simulation of nuclear processes as well as of its applications. The system is divided in three levels: basic, intermediate and simulation. In the basic level multimedia information is included on diverse basic concepts of the nuclear energy. The intermediate level includes the description and operation of some systems of the Laguna Verde nuclear power plant (CNLV). Finally the simulation level contains representative scenarios that the user can control by means of virtual control panels of the main systems of the CNLV. Inside the system a part of interactive games is included with the purpose that the user remembers with more easiness all the concepts and advantages of the nuclear energy mentioned during the previous levels. The system contributes, by means of the development of multimedia computational tools and of simulation, to the popularization of the use and applications of the nuclear energy in Mexico. (Author)

  8. Nuclear power in Central and Eastern Europe at the turn of Millennium

    International Nuclear Information System (INIS)

    In Central and Eastern European countries the use of nuclear energy for electricity generation begun in late 1950's and reached a stage of industrial maturity since 1970. In mid - 1998 there were 65 nuclear units connected to the grid, with the total installed capacity of 44.3 GWe and a nuclear electricity generation exceeding 249 TWh, supplying almost 22% of the total electricity produced in this region. Other 14 nuclear units with a total generating capacity of over 11.5 GWe were under construction in five countries: 4 in Ukraine and Russia, 3 in Slovakia, 2 in the Czech Republic and 1 in Romania. Although nuclear power has become an important energy source in many Central and Eastern European countries, especially in those countries with poor fossil energy resources (Lithuania - 82%, Bulgaria - 45.4%, Slovakia - 44%, Hungary - 40.8%), it still relies heavily on ex-Soviet and Russian - design technology (WWER and RBMK - type reactors). This implies large-scale implementation of upgrading and modernization programs for safe and reliable operation, in order to achieve levels of safety comparable with Western European standards, along with the eventual decommissioning of first generation nuclear units having serious functioning failures (e.g. Chernobyl 1, Ignalina 1 and 2, Kozloduy 1 and 2). In some countries, following the implementation of short and long term investment schemes for further improvement of the reliability and safety of operating NPP's performances, the capacity factor has reached the highest figures: Krsko NPP (Slovenia) - 88.3%, Paks NPP (Hungary) - 86.6% and Dukovany NPP (Czech Rep.) - 81%. In Romania the first CANDU - 6 unit in Europe, operable at Cernavoda since December 1996, had very satisfactory results, generating 9.7% of the country's electricity production, with a good overall load factor - 87.27%. The Chernobyl nuclear accident had immediate consequences upon the operation of NPPs and a number of restrictions were imposed. But, actually

  9. Verification and software validation for nuclear instrumentation; Verificacion y validacion de software para instrumentacion nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gaytan G, E. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Salgado G, J. R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico); De Andrade O, E. [Universidad Federal de Rio de Janeiro, Caixa Postal 68509, 21945-970 Rio de Janeiro (Brazil); Ramirez G, A., E-mail: elvira.gaytan@inin.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Alto Lucero, Veracruz (Mexico)

    2014-10-15

    In this work is presented a Verification Methodology and Software Validation, to be applied in instruments of nuclear use with associate software. This methodology was developed under the auspices of IAEA, through the regional projects RLA4022 (ARCAL XCIX) and RLA1011 (RLA CXXIII), led by Mexico. In the first project three plans and three procedures were elaborated taking into consideration IEEE standards, and in the second project these documents were updated considering ISO and IEC standards. The developed methodology has been distributed to the participant countries of Latin America in the ARCAL projects and two related courses have been imparted with the participation of several countries, and participating institutions of Mexico like Instituto Nacional de Investigaciones Nucleares (ININ), Comision Federal de Electricidad (CFE) and Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). In the ININ due to the necessity to work with Software Quality Guarantee in systems for the nuclear power plant of the CFE, a Software Quality Guarantee Plan and five procedures were developed in the year 2004, obtaining the qualification of the ININ for software development for the nuclear power plant of CFE. These first documents were developed taking like reference IEEE standards and regulator guides of NRC, being the first step for the development of the methodology. (Author)

  10. Nuclear desalination for the northwest of Mexico; Desalacion nuclear para el noroeste de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Ortega C, R. F. [Instituto de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)

    2008-07-01

    The IMPULSA project of the Engineering Institute of UNAM, it has dedicated from the year 2005 to the study and development of new desalination technologies of seawater with renewable energies. The objective is to form a group of expert engineers and investigators in the desalination topics able to transform their scientific knowledge in engineering solutions, with a high grade of knowledge of the environment and the renewable energies. In the middle of 2007 was took the initiative in the IMPULSA project to study the nuclear desalination topic. It is evident that before the high cost of the hydrocarbons and its high environmental impact, the nuclear generation alternative of energy becomes extremely attractive, mainly for desalination projects of seawater of great size. The Northwest of Mexico is particularly attractive as the appropriate site for one nuclear desalination plant of great size given its shortage of drink water and the quick growth of its population; as well as its level of tourist, agricultural and industrial activity. In this study was revised the state of the art of the nuclear desalination on the world and it is simulated some couplings and operation forms of nuclear reactors and desalination units, from the thermodynamic and economic viewpoint with the purpose of identifying the main peculiarities of this technology. The objective of the study was to characterize several types and sizes of nuclear reactors of the last generation that could be couple to a desalination technology as multi-stage distillation, type flash distillation or inverse osmosis. It is used for this effect the DEEP 3.1 program of the IAEA to simulate the coupling and to carry out an economic preliminary evaluation. Was found cost very competitive of 0.038-0.044 US$/kWh for the electric power production and 0.60 to 0.77 US$/m{sup 3} for the drink water produced, without including the water transport cost or the use of carbon certificates. (Author)

  11. Renewable energies. A challenge and an opportunity for Central America; Energias renovables. Un reto y una oportunidad para America Central

    Energy Technology Data Exchange (ETDEWEB)

    Guevara, Leo; Castro S, Rene [Instituto Centroamericano de Administracion de Empresas (INCAE) (Costa Rica)

    2007-07-15

    There are analyzed in this working paper the following aspects: the Central America countries and their relations with the regional energy potencies -Mexico and Venezuela- and the impact they have in the energy supply. There are also explore the following aspects: the San Jose Agreement linked to the fossil fuels supply, the emerging scope boosted by Brazil and Colombia regarding to the alternative fuels. [Spanish] Este trabajo analiza los paises centroamericanos y sus relaciones con las potencias energeticas regionales como Mexico y Venezuela, y como estas impactan el suministro de energia en la region. Tambien se exploran mecanismos como el Pacto de San Jose, ligado al suministro de combustibles fosiles y las oportunidades emergentes impulsadas por Brasil y Colombia con combustibles alternativos.

  12. Nuclear Data for Safe Operation and Waste Transmutation: ANDES (Accurate Nuclear Data for nuclear Energy Sustainability); Datos nucleares para la operacion segura y la transmutacion de residuos: Andes (Datos Nucleares Precisos para la Sostenibilidad de la Energia Nuclear)

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, E. M.

    2014-07-01

    Nuclear research within the 7th Framework Program (FP7 and FP7+2) of EURATOM has devoted a significant fraction of its efforts to the development of advanced nuclear fuel cycles and reactor concepts, mainly fast reactors, aiming to improve the long term sustainability by reduction of the final wastes, optimal use of natural resources and improvement of safety in the present and future nuclear installations. The new design need more accurate basic nuclear data for isotopes, like minor actinides, potentially playing an important role in the operation, fuel concept, safety or final wastes of those reactors and fuel cycles. Four projects, ANDES, ERINDA, EUFRAT and CHANDA, supported by EURATOM within the FP7 and FP7+2, have put together most of the European Nuclear Data community to respond efficiently and in a coordinated way to those needs. This paper summarizes the objectives, and main achievements of ANDES, the project responsible for most of the measurements and technical achievements that was coordinated by CIEMAT. Indeed, CIEMAT has coordinated the nuclear data R and D projects within EURATOM during the last 7 years (NUDATRA domain of EUROTRANS, and ANDES) and will continue this coordination in the CHANDA project till 2017. (Author)

  13. Ground acceleration in a nuclear power plant; Aceleracion del suelo en una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pena G, P.; Balcazar, M.; Vega R, E., E-mail: pablo.pena@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    A methodology that adopts the recommendations of international organizations for determining the ground acceleration at a nuclear power plant is outlined. Systematic presented here emphasizes the type of geological, geophysical and geotechnical studies in different areas of influence, culminating in assessments of Design Basis earthquake and the earthquake Operating Base. The methodology indicates that in regional areas where the site of the nuclear power plant is located, failures are identified in geological structures, and seismic histories of the region are documented. In the area of detail geophysical tools to generate effects to determine subsurface propagation velocities and spectra of the induced seismic waves are used. The mechanical analysis of drill cores allows estimating the efforts that generate and earthquake postulate. Studies show that the magnitude of the Fukushima earthquake, did not affect the integrity of nuclear power plants due to the rocky settlement found. (Author)

  14. Research study on operability in large-scale centralized control room. Regarding nuclear technology

    International Nuclear Information System (INIS)

    This study was performed to establish man-machine technology for panel-less instrumentation applicable to large-scale centralized control rooms of nuclear power plants. Work-load analysis of the operator in a large-scale centralized control room was performed and the basic constitution of an operator control station examined. Operability of panel-less instrumentation on based on a CRT touch-screen was examined with a mock-up operator control station manufactured according to the result of work-load analysis. The results of this study culminated in a design guideline for panel-less instrumentation. (author)

  15. Design and axial optimization of nuclear fuel for BWR reactors; Diseno y optimizacion axial de combustible nuclear para reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Garcia V, M.A

    2006-07-01

    In the present thesis, the modifications made to the axial optimization system based on Tabu Search (BT) for the axial design of BWR fuel type are presented, developed previously in the Nuclear Engineering Group of the UNAM Engineering Faculty. With the modifications what is mainly looked is to consider the particular characteristics of the mechanical design of the GE12 fuel type, used at the moment in the Laguna Verde Nucleo electric Central (CNLV) and that it considers the fuel bars of partial longitude. The information obtained in this thesis will allow to plan nuclear fuel reloads with the best conditions to operate in a certain cycle guaranteeing a better yield and use in the fuel burnt, additionally people in charge in the reload planning will be favored with the changes carried out to the system for the design and axial optimization of nuclear fuel, which facilitate their handling and it reduces their execution time. This thesis this developed in five chapters that are understood in the following way in general: Chapter 1: It approaches the basic concepts of the nuclear energy, it describes the physical and chemical composition of the atoms as well as that of the uranium isotopes, the handling of the uranium isotope by means of the nuclear fission until arriving to the operation of the nuclear reactors. Chapter 2: The nuclear fuel cycle is described, the methods for its extraction, its conversion and its enrichment to arrive to the stages of the nuclear fuel management used in the reactors are described. Beginning by the radial design, the axial design and the core design of the nuclear reactor related with the fuel assemblies design. Chapter 3: the optimization methods of nuclear fuel previously used are exposed among those that are: the genetic algorithms method, the search methods based on heuristic rules and the application of the tabu search method, which was used for the development of this thesis. Chapter 4: In this part the used methodology to the

  16. Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007

    International Nuclear Information System (INIS)

    This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

  17. The AP1000 registered philosophy fits nuclear new build in Central Europe

    International Nuclear Information System (INIS)

    The World Nuclear Association estimates a steady growth in the number of reactors to be built in the next 20 years. The number of reactors in operation worldwide today is about 440 and will rise within the next couple of decades. It is speculated that Western Europe (including Germany) will have more reactors coming offline than online in the future due to limited lifetime versus plans for new build. In contrast, Eastern Europe (including Russia) is forecasting an increase in their nuclear generating capacity. This includes new market entrants such as Poland as well as expansion projects in the Czech Republic and Hungary; Germany's eastern neighbors. Unfortunately, as Germany and Switzerland phase out nuclear the net capacity in Western Europe is expected to drop even more. In addition to the phase out of nuclear, the federal German government decided to increase the power generation of renewables, focusing on wind and solar. The consequence of simultaneously implementing these new requirements is the creation of high frequency load changes from wind fluctuations or solar peaks without having the nuclear base load to maintain a constant capacity. These decisions on Germany's energy polices has extenuating circumstances which create challenges for local transmission system operators, as well as for neighboring countries' transmission system operators due to the synchronous grid of Continental Europe. This challenge will force the countries connected to Germany by the synchronous grid to place even more importance on their nuclear new build programs in the years to come. Though Germany is phasing out nuclear all together, its neighboring countries in Central and Eastern Europe are continuing with nuclear new build efforts. Therefore, it is still important for the German public to understand the options the nuclear industry have when selecting nuclear reactor vendors. The designs of today are more technically advanced, however the AP1000 registered plant stands out

  18. Sites for locations of nuclear reactors; Sitios para emplazamientos de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Balcazar, M.; Huerta, M.; Lopez, A., E-mail: miguel.balcazar@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    A restriction on sites of nuclear energy is the history of seismic activity, in its magnitude (Richter) and intensity (Mercalli). This article delimits the areas of greatest magnitude and national seismic intensity, with restrictions of ground acceleration; the supplement areas with a low magnitude of seismic activity are shown. Potential sites for the location of these sites are introduced into a geographic information system. The set of geo-referenced data contains the location of the active volcanic manifestations; the historical record of earthquake epicenters, magnitudes and intensities; major geological faults; surface hydrology and water bodies; location of population density; protected areas; contour lines; the rock type or geology. The geographic information system allows entering normative criteria and environmental restrictions that correlate with geo-referenced data described above, forms both probable and exclusion areas for the installation of nuclear sites. (Author)

  19. Uso do ultra-som para punção venosa central em paciente obeso com adenomegalia cervical

    Directory of Open Access Journals (Sweden)

    Jaderson Wollmeister

    2008-08-01

    Full Text Available JUSTIFICATICA E OBJETIVOS: As técnicas clássicas para punção venosa central são realizadas com base em referências anatômicas de superfície e conhecimento da anatomia vascular da região em que se realizará a punção. O uso do ultra-som permite a realização da punção sob visão direta das estruturas vasculares, peri-vasculares e da agulha de punção. O objetivo deste relato foi descrever o uso do ultra-som no auxílio de acesso venoso central em paciente obeso e com adenomegalias. RELATO DO CASO: Paciente do sexo masculino, branco, 28 anos, 1,70 m, 120 kg, com diagnóstico de linfoma de Hodgkin esclerose nodular. Solicitado ao Serviço de Anestesiologia do Hospital Governador Celso Ramos, punção de veia jugular interna direita guiada por ultra-som devido à presença de gânglio supraclavicular que prejudicava a referência anatômica de punção e à obesidade do paciente. Após a obtenção da melhor imagem a veia jugular interna esquerda foi puncionada e colocado um cateter venoso de triplo lúmen. A punção foi única, com progressão fácil do cateter e realizada sem complicações. CONCLUSÕES: O uso da ultra-sonografia para punção venosa central pode evitar complicações tornando o procedimento mais seguro para o paciente.

  20. Central Asian Nuclear-Weapon-Free-Zone and the Collective Security Treaty

    International Nuclear Information System (INIS)

    In February 1997 Kazakhstan, Kyrgyzstan, Tajikistan, Turkmenistan, and Uzbekistan decided to establish Central Asian Nuclear-Weapon-Free-Zone (CANWFZ). As a matter of fact, negotiations on establishing that zone started in 1998 when Kyrgyzstan proposed draft basic element of a treaty on CANWFZ. After almost two years rather successful work on drafting the treaty, since April 2000 no meetings take place between diplomats of the five Central Asian states. It is recognized by many experts that it is the Tashkent 1992 Collective Security Treaty (CST) which caused a deadlock. Usually CST is interpreted as allowing the deployment of Russian nuclear weapons on the territory of the CST member states, for example, of Kazakhstan. However, more detailed analysis shows, that CST cannot a serious obstacle for creating CANWFZ

  1. Strategies for a competitive nuclear fuel; Estrategias para un combustible nuclear competitivo

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez, J. M.; Rebollo, L.

    2001-07-01

    In the new framework of electricity generation, Nuclear Power Plants are operated by the electric utilities based on the competition required by an increasingly deregulated and liberalized market so that there is frequently a competition between the strategies of innovation and standardisation. On one had, innovation promotes the use of new technologies, products and/or processes locking for a reduction of costs based on the increase of the operating margins, while, on the other hand, standardisation promotes the use of well known and consolidated technologies, products and/or processes looking for getting the maximum benefit from the accumulated previous operating experience. In order to evaluate the standardisation versus the innovation an analysis of risks and opportunities of each of these strategies applied to the industry of the nuclear fuel has been suggested. As a results of it, a combined strategy innovation + standardisation based on the integration of both basic strategies in a complementary mode, has been suggested, the disadvantages of each of these strategies being compensated with the advantages of the other one. in this way, the total risk is minimized, the global opportunities are maximized and the main overall objective of getting the maximum benefit of the combination of both strategies looking for a competitive nuclear fuel is guaranteed. (Author)

  2. IAEA activities to improve occupational radiation protection in nuclear power plants in Central and Eastern Europe

    International Nuclear Information System (INIS)

    The following aspects are highlighted: developing standards, ISOE (Information System on Occupational Exposure), providing assistance, and intercomparisons. By means of these coordinated efforts, the IAEA aims at improving occupational radiation protection in nuclear power plants in Central and Eastern Europe. The objective is not only transfer of knowledge and technology but also encouraging cooperation between health physicists in those countries as well as with health physicists in Western countries. (P.A.)

  3. Modern techniques for the emissions control in thermal electric stations; Tecnicas modernas para el control de emisiones en centrales termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Romo Millares, C. A. [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1995-12-31

    This paper presents the techniques and the control equipment for emissions in thermal stations that have the highest possibilities of being considered in the immediate future in the national energy panorama and the established frame for the environmental normativity. The pollutant compounds subject to revision are the nitrogen and sulfur oxides and unburned particles. [Espanol] Se presentan las tecnicas y equipos de control de emisiones para centrales termoelectricas que tienen mayores posibilidades de ser consideradas en el futuro inmediato dentro del panorama energetico nacional y el marco establecido por la normatividad ambiental. Los compuestos contaminantes sujetos a revision son los oxidos de nitrogeno y azufre y las particulas inquemadas.

  4. Diseño de la Oficina de Proyectos (PMO) para Oleoducto Central S. A.

    OpenAIRE

    Amaya Vanegas, Efraín

    2014-01-01

    En el estado actual de la economía y de la industria colombiana se hace evidente que los proyectos juegan un papel importante en el cumplimento de los objetivos estratégicos de las organizaciones del sector minero-energético -- Para garantizar el éxito de los proyectos, la entidad debe asegurar que las competencias organizacionales sean las apropiadas para el tamaño y complejidad de sus proyectos -- La unidad organizacional con dicha responsabilidad es la Oficina de Proyectos la cual se crea ...

  5. Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

    Science.gov (United States)

    Yussup, F.; Ibrahim, M. M.; Haris, M. F.; Soh, S. C.; Hasim, H.; Azman, A.; Razalim, F. A. A.; Yapp, R.; Ramli, A. A. M.

    2016-01-01

    With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering.

  6. Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering

  7. Regional Strategies Concerning Nuclear Fuel Cycle and HLRW in Central and Eastern European Countries

    International Nuclear Information System (INIS)

    In March 2009 a regional meeting on national strategies concerning nuclear fuel cycle and high level radioactive waste (HLRW) was held in Budapest with the participation of Central and Eastern European countries, Russia and France. Following the meeting a Task Force was set-up with fuel cycle experts from different countries in order to analyse the possible fuel cycle strategies in the region. The Task Force produced an Opinion Paper in spring 2010 on the Regional Strategies Concerning Nuclear Fuel Cycle and HLRW in Central and Eastern European Countries with several recommendations. The Opinion Paper emphasizes that the countries in the Central and Eastern European region are small, and they have modest NPP capacities compared to large nuclear countries. Spent fuel reprocessing facilities are not available in the region, but Russia and France offer such services for these countries. Deep geological repositories are not in operation in any of these countries, and in some of the countries the geological conditions do not allow to design such facilities. For these reasons the countries of the region may need special services and a regional approach could produce common benefit for waste management. (author)

  8. Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

    Energy Technology Data Exchange (ETDEWEB)

    Yussup, F., E-mail: nolida@nm.gov.my; Ibrahim, M. M., E-mail: maslina-i@nm.gov.my; Soh, S. C.; Hasim, H. [Instrumentation and Automation Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Haris, M. F. [Information Technology Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Azman, A. [Prototype and Development Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Razalim, F. A. A.; Yapp, R. [Health Physics Group, Radiation Safety and Health Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Ramli, A. A. M. [Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia)

    2016-01-22

    With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering.

  9. Transparência do banco central: uma análise para o caso brasileiro

    Directory of Open Access Journals (Sweden)

    Helder Ferreira de Mendonça

    2010-03-01

    Full Text Available Central Bank transparency: an analysis of the Brazilian case. Nowadays there is a tendency among central banks of increasing transparency in the conduction of the monetary policy. After the adoption of inflation targeting in Brazil there was an increase in the communication of the Central Bank of Brazil with the public. This paper makes a brief review of the recent theoretical and empirical literature concerning this subject. Furthermore, an analysis due to the transparency in the conduction of Brazilian monetary policy on important macroeconomic variables is made. The findings denote that an increase in transparency improves the behavior of several macroeconomic variables.

  10. Nuclear power plants making a comeback in Japan; El retorno de la centrales nucleares en Japon

    Energy Technology Data Exchange (ETDEWEB)

    Torralbo, J. R.

    2016-08-01

    We reproduce in this magazine the interesting article published by the president of the SNE in issue 46 of Cuadernos de Energia in October 2015, which describes the events that have taken place since the March 11, 2011 earthquake in Japan, the largest in its history, and the subsequent tsunami, which affected the Fukushima power plant, as well as the measures implemented since then and how some of this country nuclear power plants are being started up again. (Author)

  11. Annual progress report on nuclear data 1989. Central Bureau for nuclear measurements

    International Nuclear Information System (INIS)

    In 1989 the efforts for the improvement of the set of standard neutron cross sections and other quantities selected within the INDC/NEANDC Standards File continued. In particular a detailed study of the nuclear mass and charge distribution of the cold and near cold fission of 252Cf yielded understanding of cold mass rearrangements in nuclei. Accuracy of alpha-particle emission probabilities for major transitions in the decay of 236Pu, 239Pu and 243Am was improved to better than 0.5%. In the field of nuclear data for fission technology work was concentrated on European requests in the NEA High Priority Request List. The number of neutrons emitted per neutron absorbed, was obtained for 235U between 2 and 100 meV neutron energy. Using the weighting function determined at CBNM for neutron capture detectors, a new value was obtained for the neutron width of the 1.15 keV resonance in 56FeΓn = (62.9 ± 2.1) meV. In the field of nuclear data for fusion technology, measurements continued aiming at an improvement of relevant data for neutron transport calculations in the blanket and for prediction of gas production. The radionuclide metrology subproject follows three lines: determination of decay-scheme data, preparation of special standards and the improvement of measurement techniques including international comparisons

  12. Shipping of spent nuclear fuel to Central and Eastern Europe, and other nuclear waste deals

    International Nuclear Information System (INIS)

    In its reply to a written question in Parliament, the German federal government puts emphasis on the fact that all agreements concerning industrial or economic cooperation in the nuclear sector, concluded between the GDR and the Soviet Union, have been declared to be terminated in 1991. Hence the government declares that there are no international treaties any more that might serve as a vehicle for performing spent fuel shipments to Russia or any other state of the CIS. The German federal government further states to be prepared to contribute its share to the multinational assistance programme adopted in 1992 at the World Economic Summit Conference for the purpose of enhancing the safety of Soviet-design nuclear power plant. A number of projects, the government states, are in preparation with the competent institutions in the CIS, as e.g. projects for reactor safety analysis, improvement of reactor operating safety, safer nuclear fuel supply and waste management, and installation of a system for environmental radioactivity monitoring. (orig./HSCH)

  13. Creation of zone free nuclear weapon (ZFNW) in the Central Asia

    International Nuclear Information System (INIS)

    Issues on non-proliferation of mass demolition weapons are of special importance for people of Kazakhstan. The whole damage brought to nature and people's health by nuclear tests at the Semipalatinsk test site (STS) is not revealed yet. Kazakhstan contributed much to the matter of nuclear disarmament. More than six years ago for the first time in the world by RK President's resolution an operating nuclear test site closed. Kazakhstan was the first to fulfill obligations in accordance with Lisbon protocol. Kazakhstan liquidated the fourth nuclear potential in the world. It's time to undertake further steps in the field of non-proliferation. One of such steps is the creation of a ZFNW in the central Asia. The idea of ZFNW creation is being acknowledged more and more during last 30 years. All the four present zones include more than 100 countries. If the Antarctic Region is taken into account the zones cover more than 50% of dry land. Regional ZFNWs attract attention as a means of reflecting and rewarding general valuers in the sphere of nuclear disarmament and armament control. Such zones help tj narrow geographical sphere of military nuclear activity and to strengthen non-proliferation regime. The importance of ZFNW in the process of strengthening global and regional peace and safety is confirmed by the documents of Conference for countries joined the agreement on non-proliferation (AN) of 1995 and the first meeting of the Organizing Committee for Conference of 2000

  14. Methodology for transient simulation of a small heliothermic central station; Metodologia para simulacao transiente de uma pequena central heliotermica

    Energy Technology Data Exchange (ETDEWEB)

    Wendel, Marcelo

    2010-08-15

    The final steps of generating electricity from concentrated solar power technologies are similar to conventional thermal processes, since steam or gas is also employed for moving turbines or pistons. The fundamental difference lies on the fact that steam or hot gas is generated by solar radiation instead of fossil fuels or nuclear heat. The cheapest electricity generated from solar energy has been achieved with large-scale power stations based on this concept. Computer simulations represent a low-cost option for the design of thermal systems. The present study aims to develop a methodology for the transient simulation of a micro-scale solar-thermal power plant (120 kWe) which should be appropriate in terms of accuracy and computational effort. The facility considered can optionally operate as a cogeneration plant producing electric power as well as chilled water. Solar radiation is collected by parabolic troughs, electricity is generated by an organic Rankine cycle and chilled water is produced by an absorption cooling cycle. The organic Rankine cycle is of interest because it allows for a plant with relatively simple structure and automated operation. The simulation methodology proposed in this study is implemented in TRNSYS with new components (TYPEs) developed for the solar field and thermal cycles. The parabolic trough field component is based on an experimental efficiency curve of the solar collector. In the case of the Rankine and absorption cycles, the components are based on performance polynomials generated with EES from detailed thermodynamic models, which are calibrated with performance data from manufacturers. Distinct plant configurations are considered. An optimization algorithm is used for searching the best operating point in each case. Results are presented for the following Brazilian sites: Fortaleza, Petrolina and Bom Jesus da Lapa. The latter offers the highest global plant performance. An analysis about the influence of the thermal storage on

  15. Security central processing unit applications in the protection of nuclear facilities

    International Nuclear Information System (INIS)

    New or upgraded electronic security systems protecting nuclear facilities or complexes will be heavily computer dependent. Proper planning for new systems and the employment of new state-of-the-art 32 bit processors in the processing of subsystem reports are key elements in effective security systems. The processing of subsystem reports represents only a small segment of system overhead. In selecting a security system to meet the current and future needs for nuclear security applications the central processing unit (CPU) applied in the system architecture is the critical element in system performance. New 32 bit technology eliminates the need for program overlays while providing system programmers with well documented program tools to develop effective systems to operate in all phases of nuclear security applications

  16. Scenarios simulation of severe accident type small loss of coolant (Loca), with the code MELCOR version 2.1 for the nuclear power plant of Laguna Verde; Simulacion de escenarios de accidente severo tipo perdida de refrigerante (Loca) pequeno, con el codigo MELCOR version 2.1 para la central nucleo-electrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Cardenas V, J.; Mugica R, C. A.; Godinez S, V., E-mail: Jaime.cardenas@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    In this work was carried out the analysis of two scenarios of the accident type with loss of coolant in a recirculation loop for a break with smaller ares to 0.1 ft{sup 2} (4.6 cm{sup 2}), which is classified according to their size like small Loca. The first simulated scenario was a small Loca without action of the emergency coolant injection systems, and the second was a small Loca with only the available system LPCS. This design base accident was taken into account for its relevance with regard to the damage to the core and the hydrogen generation. Was also observed and analyzed the response of the action of the ECCS that depend of the loss of coolant reason and this in turn depends of the size and type of the pipe break. The specified scenarios were simulated by means of the use of MELCOR model for the nuclear power plant of Laguna Verde that has the Comision Nacional de Seguridad Nuclear y Salvaguardias. (Author)

  17. Knowledge management in nuclear power plants; Gestion del conocimiento en las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Cal, C. de la; Barasoain, F.; Buedo, J. L.

    2013-03-01

    This article aims to show the importance of knowledge management from different perspectives. In this first part part of the article, the overall approach that performs CNAT of knowledge management is described. In the second part, a specific aspect of knowledge management in ANAV, tacit knowledge transfer is showed. finally, the third part discusses the strategies and actions that are followed in CNCO for knowledge management. All this aims to show an overview of knowledge management held in the Spanish Nuclear Power Plants. (Author)

  18. New zirconium alloys for nuclear application; Novas ligas de zirconio para aplicacao nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lobo, R.M.; Andrade, A.H.P., E-mail: rmlobo@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2010-07-01

    Zirconium alloys are widely used in the nuclear industry, mainly in fuel cladding tubes and structural components for PWR plants. The service life of these components, which operate under high temperatures conditions ({approx} 300 deg C), has led to developing new alloys with the aim to improve the mechanical properties, corrosion resistance and irradiation damage. The variation in the composition of the alloy produces second phase particles which alter the materials properties according to their size and distribution, is essential therefore, knowledge their characteristics. Analysis of second phase particles in zirconium alloys are carried out by scanning electron microscopy, transmission electron microscopy and image analysis. This study used the zircaloy-4 to illustrate the characterization of these alloys through the study of second phase particles. (author)

  19. Proposal of the visual inspection of the integrity of the storage cells of spent fuel from the nuclear power plant of Laguna Verde; Propuesta para la inspeccion visual de la integridad de las celdas de almacenamiento de combustible gastado de la Central Laguna Verde (CLV)

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez M, J. L.; Rivero G, T.; Merino C, F. J. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Santander C, L. E., E-mail: francisco.merino@inin.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Veracruz-Medellin Km 7.5, Col. Dos Bocas, 94271 Medellin, Veracruz (Mexico)

    2015-09-15

    As part of the evaluation of the structural integrity of the components of nuclear plants, particularly those applying for life extension is necessary to carry out inspections and nondestructive testing to determine the state meet. In many cases these activities are carried out in areas with high levels of radiation and contamination difficult to access, so that are required to use equipment or robotic systems operated remotely. Among others, the frames and cells of the storage pools for spent fuel are structures subject to a program of tests and inspections, and become relevant because the nuclear power plant of Laguna Verde (NPP-LV) is processing the license to extend the operational life of its reactors. Of non-destructive testing can be used to verify the physical condition of the frames and storage cells, is the remote visual inspection which is a test that allows determine the physical integrity of the components by one or more video cameras designed to applications in underwater environments with radiation, and are used to identify and locate adverse conditions such as ampoules, protuberances, pitting, cracks, stains or buckling, which could affect the three main functions for which the store components are designed: to maintain the physical integrity of spent fuels, store them properly guaranteeing their free insertion and removal, and ensure that the store as a whole meets the criticality criteria that k{sub eff} is less than 0.95 throughout the life of the plant. This paper describes a proposal to carry out the visual inspection of the storage cells of spent fuel from the NPP-LV using a probe including one or more video cameras along with your recorder, and its corresponding control program. It is noted that due to the obtained results, the nuclear power plant personnel can make decisions regarding remedial actions or applying complementary methods to verify that the cells and frames have not lost their physical integrity, or in particular that the cover

  20. Scope for nuclear weapon-free zone in central and eastern Europe

    International Nuclear Information System (INIS)

    The idea of a Central Europe free of nuclear weapons has its roots, of course, in the end of the cold war and the break-up of the former Union. These historical developments created the necessary conditions for the Lisbon Protocol, the successful withdrawal of all nuclear weapons from Belarus, Ukraine, and Kazakhstan as well as these countries' accession to the Non-Proliferation Treaty. It is admitted that even before these steps had been achieved, Belarus had put forward the nuclear-free zone initiative at the United Nations General Assembly in 1991. Like all the other nuclear weapon-free zones, existing or potential, a proposal for such a zone entails that it be analysed in the context of its political environment, regional specificity as well as the role, and implications of the relevant outside powers. These include Warsaw Pact dissolution and its impact on control of tactical nuclear weapons as well as the North Atlantic Treaty Organisation (NATO's) expansion eastwards. It is equally important to look at the issue in the context of its history, or, in other words, the past attempts

  1. Nuclear hydrogen - possibilities for Brazil; Hidrogenio nuclear - possibilidades para o Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Saliba-Silva, Adonis Marcelo; Linardi, Marcelo [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Centro de Celulas a Combustivel e Hidrogenio]. E-mail: saliba@ipen.br

    2008-07-01

    The energy vector hydrogen represents a good possibility to replace fossil fuels. One of the main renewable sources of interest for hydrogen is water, which is abundant and can be decomposed directly into pure H{sub 2} and O{sub 2}. This water splitting can be performed by the following methods: electrolysis, thermal decomposition, and thermochemical cycles. The thermochemical cycles and high temperature electrolysis (HTE) are often thought to be feasible methods to be associated with a High Temperature Gas cooled Reactor (HTGR). Both routines have high efficiency at temperature range of 700-950 deg C. In this work, is presented an attainable proposal for Brazilian production of hydrogen based on a HTGR followed by HTE system. A research group at Fuel Cell and Hydrogen Center - CCCH at IPEN/CNEN-SP has elaborated a working plan for 10 years, where it is proposed a R and D line for hydrogen production based on nuclear energy supplied by HTGR. So, in this work, a Brazilian program for researching in this area is proposed inviting potential cooperation. (author)

  2. Effectiveness of a large mimic panel in an existing nuclear power plant central control board

    International Nuclear Information System (INIS)

    We conducted the analysis of the nuclear power plant (NPP) operators' behaviors under emergency conditions by using training simulators as a joint research project by Japanese BWR groups for twelve years. In the phase-IV of this project we executed two kinds of experiments to evaluate the effectiveness of the interfaces. One was for evaluations of the interfaces such as CRTs with touch screen, a large mimic panel, and a hierarchical annunciator system introduced in the newly developed ABWR type central control board. The other was that we analyzed the operators' behaviors in emergency conditions by using the first generation BWR type central control board which was added new interfaces such as a large display screen and demarcation on the board to help operators to understand the plant. The demarcation is one of the visual interface improvements and its technique is that a line enclosing several components causes them to be perceived as a group.The result showed that both the large display panel Introduced in ABWR central control board and the large display screen in the existing BWR type central control board improved the performance of the NPP operators in the experiments. It was expected that introduction of the large mimic panel into the existing BWR type central control boards would improve operators' performance. However, in the case of actual installation of the large display board into the existing central control boards, there are spatial and hardware constraints. Therefore the size of lamps, lines connecting from symbols of the pumps or valves to the others' will have to be modified under these constraints. It is important to evaluate the displayed information on the large display board before actual installation. We made experiments to solve these problems by using TEPCO's research simulator which is added a large mimic panel. (author)

  3. Outline and operation results of centralized radwaste treatment facility in Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    In the Fukushima Nuclear Power Station I (Daiichi), Unit 1 started operation in 1971 and Unit 6 in 1979; the six power plants are now in steady operation. The Centralized Radwaste Treatment Facility, whose construction was started in 1980 and completed in 1984, is located south of Unit 4. Its total floor space is 36,000 m2, the main building being of the size of a 1,100 MW reactor building. The following equipments in Centralized Radwaste Treatment Facility are described, including features and operation results: radioactive liquid volume reduction treatment facility, laundary-center waste water concentration treatment facility, machinery drain water treatment facility, combustible solids incineration facility. (Mori, K.)

  4. Microsurgical approach of arteriovenous malformations in the central lobule Abordagem microciúrgica para malformações arteriovenosas no lóbulo central

    Directory of Open Access Journals (Sweden)

    Feres Chaddad-Neto

    2008-12-01

    Full Text Available Arteriovenous malformations (AVM are neurovascular disorders that occur mainly in young adults. Their clinical presentation is variable and depends on its location, size and occurrence of bleeding. They can represent incidental findings in neuro radiological exams. The treatment of these lesions when located in eloquent areas, namely around the central sulcus, is controversial, with different therapeutical approaches presented in the literature. We consider that surgical extirpation of many of these lesions is feasible in selected cases , when supported by profound anatomical knowledge and refined microsurgical technique, achieving cure with minimal aditional deficit. In the present article, we elaborate a surgical technique for the approach of AVMs located in the central sulcus, specially in finding the topographic lesion location and craniotomy.Malformações arteriovenosas (MAV são uma entidade patológica que ocorre mais frequentemente em adultos jovens. Sua manifestação clínica é variável e depende de sua localização, tamanho e ocorrência ou não de sangramento. Podem também ser diagnoticadas como achados incidentais em investigações neurorradiólogicas . O tratamento destas lesões, quando localizadas em áreas eloqüentes, em particular aquelas lesões localizadas próximas ao sulco central do cérebro, é controverso e diferentes abordagens terapêuticas são relatadas. Consideramos que a ressecção cirúrgica destas lesões é viável em casos selecionados, quando realizada sob profundo conhecimento anatômico e técnica microcirúrgica refinada, pois deste modo, as lesões podem ser curadas sem agregar morbidade ao paciente. No presente artigo, discutimos a técnica cirúrgica para MAVs localizadas nas adjacências do sulco central do cérebro, especialmente a localização topográfica da lesão e craniotomia.

  5. Respuesta hidrológica del Pirineo central al cambio ambiental proyectado para el siglo XXI

    OpenAIRE

    López-Moreno, J. I.; Vicente-Serrano, S. M.; Zabalza, J.; J. Revuelto; Gilaberte, M.; C. Azorín-Molina; Morán-Tejeda, E.; García-Ruiz, J.M.; Tague, C.

    2014-01-01

    Streamflows in five Mediterranean mountain headwaters in the central Spanish Pyrenees were projected under various climate and land use change scenarios. Streamflows were simulated using the Regional Hydro-Ecologic Simulation System (RHESSys). The results show that changes in precipitation and temperature could cause a decline of annual streamflow between 13% and 23%, depending on the considered catchment. When the effect of increased forest cover in the basins is added to climate change effe...

  6. Evaluation of cable ageing in Nuclear Power Plants; Evaluacion del envejecimiento de cables en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lopez Vergara, T. [Empresarios Agrupados, A. I. E. Madrid (Spain); Alonso Chicote, J. [TECNATOM, S. A. (Spain); Burnay, S. [AEA Technology (UK)

    2000-07-01

    The majority of power, control and instrumentation cables in nuclear power plants use polymers as their basic material for insulation and jacket. In many cases, these cables form part of safety-related circuits and should therefore be capable of operating correctly under both normal and accident conditions. Since polymeric materials are degraded by the long term action of the radiation and thermal environments found in the plant, it is important to be able to establish the cable condition during the plant lifetime. Nowadays there are a number of different methods to evaluate the remaining lifetime of cables. In the case of new plants, or new cables in old plants, accelerated ageing tests and predictive models can be used to establish the behaviour of the cable materials under operating conditions. There are verified techniques and considerable experience in the definition of predictive models. This type of approach is best carried out during the commissioning stage or in the early stages of operation. In older plants, particularly where there is a wide range of cable types in use, it is more appropriate to use condition monitoring methods to establish the state of degradation of cables in-plant. Over the last 10 years there have been considerable developments in methods for condition monitoring of cables and a tool-box of practical techniques are now available. There is no single technique which is suitable for all cable materials but the range of methods covers nearly all of the types currently in use, at present, the most established methods are the indented, thermal analysis (OIT, OITP and TGA) and dielectric loss measurements, All of these are either non-destructive methods or require only micro-samples of material. (Author) 15 refs.

  7. Five years of partnership between nuclear power stations in Germany and the CIS and Central European states

    International Nuclear Information System (INIS)

    For five years, partnerships have existed between German nuclear power stations and nuclear power stations in the CIS and central European states with the object of increasing the nuclear safety and reliability of nuclear power stations through the interchange of experience by experts at all operational organisational levels. In this period, about 200 reciprocal meetings, exchanges of groups of experts, secondments into the partners' plants and seminars, of which about two-thirds have been in German nuclear power stations, have taken place. Improvements and a change in safety-responsibility awareness are clearly established. In this area, the partnerships have made an important contribution. (orig.)

  8. A position paper for a central procurement organization for the nuclear power industry

    International Nuclear Information System (INIS)

    This paper integrates the results of numerous nuclear utility industry meetings with commercial business practices. The Central Procurement Organization (CPO) is designed to achieve an immediate 30%--50% reduction in total procurement, engineering qualification, warehousing, and distribution cost. Three (3) areas define a CPO success criteria: (1) Lean, credible, and cost-effective issues discussed include facility cost, operational cost, staff expertise, product priorities, warehousing, and distribution, (2) Common technical, commercial, and quality requirement issues discussed include current industry practices and proposed future methodologies, and (3) Financial survivability issues which are the most critical since the CPO must exist during changing internal and external utility environments

  9. Permission of change of limits in the vapor generators of the Atucha I Nuclear Central

    International Nuclear Information System (INIS)

    In the mark of the modification of the Atucha-I Nuclear Central Installation (CNA-I) as consequence of the Introduction of the System 'Second Drain of Heat' (SSC), the Entity Responsible for the CNA-I (NASA) requested authorization to the Nuclear Regulatory Authority (ARN) to modify the value of the minimum level of water in the secondary side in the Steam generators (GVs) to activate the signal 'shoot of the Cut of the Reactor' (RESA-LLV). As the level in the GVs is one of those parameters that are used to shoot the Emergency Feeding System (RX), component of the SSC System, also was analyzed the change in the activation of the shoot signal of the 'Second Drain of Heat' (2SSC-LLV). The ARN uses for the study of the nuclear safety of nuclear power plants, the series of prediction programs RELAP5/MOD3.X. It participates of the evaluation and maintenance activities of these codes through specific agreements with the U.S. Nuclear Regulatory Commission (US-NRC). It is necessary to account with programs of this type since the ARN it licenses the construction and operation of Nuclear Power Plants (NPPs) and other outstanding facilities and it inquires its operation according to its own standards. With these tools its are auditing the calculations that the Responsible Entities of the operation make to guarantee the operability of the NPPs assisting the mentioned standards. The analysis with computational codes is used as a tool to achieve the best understanding in the behavior of the plant in union with the engineering approach, the manual calculations, the data analysis and the experience in the operation of the machine. (Author)

  10. Center for Nuclear Safety in Central and Eastern Europe: a platform for co-operation

    International Nuclear Information System (INIS)

    The paper presents a summary of the current status and the activities of the Centre of Nuclear Safety in Central and Eastern Europe (CENS). The CENS is a non-profit and independent association supported by the Swiss and Slovak Governments. The main mission of the CENS is to provide an independent platform for technical co-operation between the regulatory authorities of the Western and Eastern countries. The key partners of the CENS are the Swiss Federal Nuclear Safety Inspectorate (HSK), the International Atomic Energy Agency (IAEA), the US Department of Energy (US DOE), the Nuclear Regulatory Authority of the Slovak Republic (UJD), the Gesellschaft fuer Anlagen-und Reaktorsicherheit mbH (GRS), Germany and the Institute of Radiation Protection and Nuclear Safety (IRSN), France. The CENS programs for 2003-2004 are presented. It can be considered as a complement to the IAEA activities in the area of short-term and event urgent planning. CENS projects as an example are presented. CENS proposals for co-operation with the Bulgarian institutions are made in connection with the topics of the forum round table discussions

  11. Introgression evidence and phylogenetic relationships among three (ParaMisgurnus species as revealed by mitochondrial and nuclear DNA markers

    Directory of Open Access Journals (Sweden)

    Jakovlić I.

    2013-01-01

    Full Text Available The taxonomy of (ParaMisgurnus genera is still debated. We therefore used mitochondrial and nuclear DNA markers to analyze the phylogenetic relationships among Misgurnus anguillicaudatus, Paramisgurnus dabryanus and Misgurnus fossilis. Differing phylogenetic signals from mitochondrial and nuclear marker data suggest an introgression event in the history of M. anguillicaudatus and M. mohoity. No substantial genetic evidence was found that Paramisgurnus dabryanus should be classified as a separate genus.

  12. ¿La intervención del Banco Central afecta el momentum de la tasa de cambio?: evidencia empírica para Colombia / does Central Bank intervention affect the momentum of the exchange rate? empirical evidence for Colombia

    OpenAIRE

    Reyes Roa, María Fernanda

    2011-01-01

    Este documento estudia la incidencia de la intervención cambiaria del banco central en la inercia de corto plazo de la tasa de cambio de Colombia usando un enfoque probabilístico. Para esto, se estima un modelo de respuesta binaria que usa información diaria de la tasa de cambio peso/dólar que se controla por variables relevantes para explicar el comportamiento de la tasa de cambio en el corto plazo y por los montos diarios de intervención del banco central en el mercado cambiario. Se encuent...

  13. Respuesta hidrológica del Pirineo central al cambio ambiental proyectado para el siglo XXI

    OpenAIRE

    López-Moreno, Juan I.; Vicente Serrano, Sergio M.; Zabalza, Javier; Revuelto, Jesús; Gilaberte-Búrdalo, M.; Azorín-Molina, César; Morán-Tejeda, Enrique; García-Ruiz, José María; Tague, C.

    2014-01-01

    [ES] Se han simulado los caudales de cinco cabeceras de ríos en los Pirineos centrales españoles, considerando diferentes escenarios de cambio climático y de uso del suelo. Los caudales fueron simulados utilizando el modelo hidro-ecológico RHESSys (Regional Hydro-Ecologic Simulation System). Los resultados muestran que los cambios proyectados por un conjunto de modelos climáticos regionales en precipitaciones y temperaturas en el siglo XXI podrían causar una disminución del caudal anual entre...

  14. Negative sequence relay applied to generator 1 of the Laguna Verde nuclear power plant; Aplicacion de un relevador de secuencia negativa en el generador 1 de la central de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Diaz de la Serna P, Enrique [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1988-12-31

    The rotor of a synchronous generator can be dangerously heated in a short time by stator current unbalance, therefore it must be protected with a specific relay. This article discusses the protection and the adjustments selected for Unit 1 of the Comision Federal de Electricidad Laguna Verde Nuclear Nuclear Power Station. [Espanol] El rotor de un generador sincrono puede calentarse peligrosamente en un tiempo corto debido a desbalance de corrientes en el estator, por lo que debe protegerse con un relevador especifico. En este articulo se describen la proteccion y los ajustes seleccionados para la unidad 1, de la central nucleoelectrica Laguna Verde de la Comision Federal de Electricidad.

  15. Colour of the nucleus as a marker of nuclear hardness, diameter and central thickness.

    Science.gov (United States)

    Gullapalli, V K; Murthy, P R; Murthy, K R

    1995-12-01

    Hundred and thirty patients, aged above 40 years, with senile cataract were examined. Age and colour were selected as the probable preoperative indicators of nuclear hardness. The lens material collected after manual extracapsular extraction was washed and the nucleus isolated. The diameter and central thickness of the nucleus were measured; the mean diameter and mean central thickness were 7.13 mm +/- 0.76 and 3.05 mm +/- 0.48, respectively. The hardness of the nucleus was measured with a lens guillotine designed by us. Regression analysis was applied to the parameters measured and these were compared with the colour and age. The parameters measured had the following relationship: Colour vs hardness (r value = 0.7569) (p 0.05) Age vs diameter (r value = 0.0987) (p > 0.05) Age vs central thickness (r value = 0.1700) (p > 0.05) The values showed that colour had a statistically significant relationship with all the 3 parameters (p cataractous lens nucleus, the preoperative knowledge of which would help the surgeon in planning small-incision surgery including phacoemulsification. PMID:8655196

  16. 30 years in the Veracruz state coast landscape: Laguna Verde nuclear power station. 1. ed.; 30 anos de paisaje costero veracruzano: Central Nucleoelectrica Laguan Verde

    Energy Technology Data Exchange (ETDEWEB)

    Guevara, S; Moreno Casasola, P; Castillo Campos, G; Dorantes, C; Gonzalez Garcia, F; Halffter, G; Isunza, E; Lot H, A; Mendoza, R; Paradowska, K; Priego, A; Sanchez Vigil, C; Vazquez, G [Comision Federal de Electricidad and Instituto Nacional de Ecologia A.C. (Mexico)

    2008-07-01

    results of the environmental measurements also demonstrate that the nuclear option of electrical energy generation, when it is operated with safety and efficiency, is one of the friendlier forms with the environment of power generation. [Spanish] Hace 36 anos nacio uno de los proyectos energeticos mas importantes de Mexico; el diseno y construccion de la Central Nuclear Laguna Verde. Este proyecto se volvio realidad gracias al compromiso de un grupo de profesionistas mexicanos que dieron lo mejor de ellos para su realizacion. En Mexico no existia en ese momento una legislacion que contemplara la proteccion del medio ambiente; sin embargo, la Constitucion preve que cuando en el pais no exista legislacion para el desarrollo de un proyecto. Este debe adoptar la legislacion del pais que lo esta vendiendo. En el caso especifico de Laguna Verde, se adopto la legislacion de los Estados Unidos de America y en la parte ambiental se tuvo que realizar el primer Manifiesto de Impacto Ambiental, que se titulo Informe ambiental para la construccion de la Central Nuclear Laguna Verde en el Estado de Veracruz. Este estudio lo realizaron varias instituciones tanto nacionales como extranjeras. Entre las mas sobresalientes se cuenta con: la Universidad Nacional autonoma de Mexico, el Instituto Politecnico Nacional, la Universidad Veracruzana, el Instituto Nacional para la Investigacion de los Recursos Biologicos, el Instituto de Ecologia, A.C. Con este informe, los ingenieros se dieron a la tarea de disenar y construir, los biologos y ecologos a realizar los estudios para mitigar los efectos causados al medio ambiente durante la construccion y, posteriormente, durante la operacion de la Central Nuclear. Despues de 18 anos de operacion comercial de la central se concluye el presente libro, en el cual se comparan los resultados obtenidos en 1972, cuando se iniciaron los estudios para el informe ambiental, contra los obtenidos a lo largo de este periodo. Es importante ver en los resultados de

  17. Respuesta hidrológica del Pirineo central al cambio ambiental proyectado para el siglo XXI

    Directory of Open Access Journals (Sweden)

    López-Moreno, J. I.

    2014-12-01

    Full Text Available Streamflows in five Mediterranean mountain headwaters in the central Spanish Pyrenees were projected under various climate and land use change scenarios. Streamflows were simulated using the Regional Hydro-Ecologic Simulation System (RHESSys. The results show that changes in precipitation and temperature could cause a decline of annual streamflow between 13% and 23%, depending on the considered catchment. When the effect of increased forest cover in the basins is added to climate change effects, the decrease in annual streamflow is enhanced up to 19% and 32%. The largest hydrological changes resulting from environmental change are projected mainly in early spring, summer and autumn, when the decline may exceed 40%. Winter is the least affected season by environmental change because of increased runoff as a consequence of reduced storage of water in the snowpack and an earlier onset of the snowmelt, and the lower consumption of water by vegetation during the cold season. The magnitude of hydrological change as a result of the assumed environmental change scenarios may lead to serious impacts on water management and ecology of the studied region, as well as the water availability in the Ebro basin.Se han simulado los caudales de cinco cabeceras de ríos en los Pirineos centrales españoles, considerando diferentes escenarios de cambio climático y de uso del suelo. Los caudales fueron simulados utilizando el modelo hidroecológico RHESSys (Regional Hydro-Ecologic Simulation System. Los resultados muestran que los cambios proyectados por un conjunto de modelos climáticos regionales en precipitaciones y temperaturas en el siglo XXI podrían causar una disminución del caudal anual entre el 13% y el 23%, dependiendo de la cuenca considerada. Cuando se añade a los efectos del cambio climático el efecto del aumento de la cubierta forestal en las cuencas, la disminución de los caudales anuales oscila entre el 19% y el 32%, dependiendo de la cuenca

  18. Colour of the nucleus as a marker of nuclear hardness, diameter and central thickness

    Directory of Open Access Journals (Sweden)

    Gullapalli Vamsi

    1995-01-01

    Full Text Available Hundred and thirty patients, aged above 40 years, with senile cataract were examined. Age and colour were selected as the probable preoperative indicators of nuclear hardness. The lens material collected after manual extracapsular extraction was washed and the nucleus isolated. The diameter and central thickness of the nucleus were measured; the mean diameter and mean central thickness were 7.13 mm ± 0.76 and 3.05 mm ± 0.48, respectively. The hardness of the nucleus was measured with a lens guillotine designed by us. Regression analysis was applied to the parameters measured and these were compared with the colour and age. The parameters measured had the following relationship: Colour vs hardness (r value = 0.7569 (p < 0.001 Colour vs diameter (r value = 0.3962 (p < 0.001 Colour vs central thickness (r value = 0.4785 (p < 0.001 Age vs hardness (r value = -0.0499 (p > 0.05 Age vs diameter (r value = 0.0987 (p > 0.05 Age vs central thickness (r value = 0.1700 (p > 0.05 The values showed that colour had a statistically significant relationship with all the 3 parameters (p < 0.001, while age had no significant relationship with the same parameters. The results indicated that colour can be used more reliably to predict physical characteristics of the cataractous lens nucleus, the preoperative knowledge of which would help the surgeon in planning small-incision surgery including phacoemulsification.

  19. Experience from the operation of the Swedish Central Interim Storage Facility for Spent Nuclear Fuel, CLAB

    International Nuclear Information System (INIS)

    Currently, about 50% of the electric power in Sweden is generated by means of nuclear power. The Swedish nuclear programme comprises 12 plants. According to political decisions, no more nuclear power plants will be built and the existing plants will not be operated beyond the year 2010. The programme will give rise to not more than 7800 t U of spent fuel, which will be directly disposed of in the crystalline bedrock without reprocessing. A keystone in the spent fuel management strategy is the Central Interim Storage Facility for Spent Nuclear Fuel, CLAB. After intensive pre-project work, the licensing of CLAB according to the Building, Environment Protection and Atomic Energy Acts took place in 1978-1979. After a total licensing time of about 20 months, the last permit was obtained in August 1979. By August 1994, CLAB had received and unloaded some 720 fuel transport casks, corresponding to about 2000 t U, and 60 casks containing highly active core components. The performance of the plant has been very satisfactory and with increasing experience it has been possible to reduce the operating and maintenance costs. The extensive efforts during the design phase have resulted in a collective dose of 25-30% of the dose calculated in the final safety report. Owing to a low activity release from the fuel and optimized management of the used water filtering agents, the number of waste packages emanating from CLAB has been less than 10% of what was originally expected. The activity release to air and water from the facility during the first five years of operation has been around 0.01% of the permissible release. In order to postpone the building of additional storage pools, new storage canisters have been developed which has increased the storage capacity from 3000 to 5000 t U. (author). 1 fig

  20. Treatment of operational experience of nuclear power plants in WANO; Tratamiento de la experiencia operativa de las centrales nucleares en WANO

    Energy Technology Data Exchange (ETDEWEB)

    Ibanez, M.

    2013-09-01

    The article describes the activities associated to the Operating Experience Programme of the World Association of Nuclear Operators. The programme manages the event reports submitted by the nuclear power plants to the WANO database for the preparation by the Operating Experience Central Team of some documents like the significant Operating Experience Reports and Significant Event Reports that help the stations to avoid similar events. (Author)

  1. Energy and centrality dependences of charged multiplicity pseudorapidity density in relativistic nuclear collisions

    CERN Document Server

    Zhou Dai Mei; Sá Ben-Hao; Li Zhong Dao

    2002-01-01

    Using a hadron and string cascade model, JPCIAE, and the corresponding Monte Carlo events generator, the energy and centrality dependences of charged particle pseudorapidity density in relativistic nuclear collisions were studied. Within the framework of this model, both the relativistic p anti p experimental data and the PHOBOS and PHENIX Au + Au data could be reproduced fairly well without retuning the model parameters. The author shows that since is not a well defined physical variable both experimentally and theoretically, the charged particle pseudorapidity density per participant pair can increase and also can decrease with increasing of , so it may be hard to use charged particle pseudorapidity density per participant pair as a function of to distinguish various theoretical models for particle production

  2. Energy and centrality dependences of charged multiplicity pseudorapidity density in relativistic nuclear collisions

    International Nuclear Information System (INIS)

    Using a hadron and string cascade model, JPCIAE, and the corresponding Monte Carlo events generator, the energy and centrality dependences of charged particle pseudorapidity density in relativistic nuclear collisions were studied. Within the framework of this model, both the relativistic p anti p experimental data and the PHOBOS and PHENIX Au + Au data could be reproduced fairly well without retuning the model parameters. The author shows that since part> is not a well defined physical variable both experimentally and theoretically, the charged particle pseudorapidity density per participant pair can increase and also can decrease with increasing of part>, so it may be hard to use charged particle pseudorapidity density per participant pair as a function of part> to distinguish various theoretical models for particle production

  3. Nuclear policies in Central Europe. Environmental policy and enlargement of the European Union: Austria's policies towards Nuclear Reactors in neighboring countries

    International Nuclear Information System (INIS)

    Austria's anti-nuclear policies are rooted in the successful anti-nuclear referendum on the Zwentendorf nuclear power plant (Lower Austria) in 1978 and the great impact of the Chernobyl catastrophe on Austria in 1986. Since about 1990, official Austria has pursued anti-nuclear policies not only at home but also abroad. In particular, reactors in Central and Eastern European Countries (CEEC) are the focal points of Austria's foreign anti-nuclear policies. Strategies include increasing nuclear safety, promoting energy efficiency and sustainable energy sources (such as renewable resources), and extending international legal frameworks to account for nuclear safety. Involvement in domestic energy issues in other countries is not an easy task, and while Austrian policy makers have had some success in increasing awareness of nuclear safety in Europe, they have also made a number of strategic mistakes. Notwithstanding real and substantiated concerns regarding nuclear safety, Austrian policies have lost credibility during recent years. This book explores the history and the development of Austrian anti-nuclear policies, and discusses the political economy of such policies. Particular emphasis is laid on the 2002 referendum against the Temelin reactor in the neighboring Czech Republic. (orig.)

  4. Rapid prototyping of the Central Safety System for Nuclear Risk in ITER

    International Nuclear Information System (INIS)

    The Central Safety System for Nuclear Risk (CSS-N) coordinates the safety control systems to ensure nuclear safety for the ITER complex. Since the CSS-N is a safety critical system, its validation and commissioning play a very important role; in particular the required level of reliability must be demonstrated. In such a scenario, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the control system requirements. Furthermore the models can than be used for the rapid prototyping of the safety system. Hardware-in-the-loop simulations can also be performed in order to assess the performance of the control hardware against a plant simulator. The proposed approach relies on the availability of a plant simulator to develop the prototype of the control system. This paper introduces the methodology used to design and develop both the CSS-N Oriented Plant Simulator and the CSS-N Prototype.

  5. Rapid Prototyping of the Central Safety System for Nuclear Risk in ITER

    International Nuclear Information System (INIS)

    Full text of publication follows: In the current ITER Baseline design, the Central Safety System for Nuclear Risk (CSS-N) is the safety control system in charge to assure nuclear safety for the plant, personnel and environment. In particular it is envisaged that the CSS shall interface to the plant safety systems for nuclear risk and shall coordinate the individual protection provided by the intervention of these systems by the activation, where required, of additional protections. The design of such a system, together with its implementation, strongly depends on the requirements, particularly in terms of reliability. The CSS-N is a safety critical system, thus its validation and commissioning play a very important role, since the required level of reliability must be demonstrated. In such a scenario, where a new and non-conventional system has to be deployed, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the system requirements, and they will be used to test and validate the control logic. Furthermore these tools can be used to rapid design the safety system and to carry out hardware-in-the-loop (HIL) simulations, which permit to assess the performance of the control hardware against a plant simulator. Both a control system prototype and a safety system oriented plant simulator have been developed to assess first the requirements and then the performance of the CSS-N. In particular the presented SW/HW framework permits to design and verify the CSS protection logics and to test and validate these logics by means of HIL simulations. This work introduces both the prototype and plant simulator architectures, together with the methodology adopted to design and implement these validation tools. (authors)

  6. Skills for development of nuclear professional for field observations; Competencias para el desarrollo de profesionales nucleares para las observaciones en el campo

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez Gutierrez, N.; Buedo, J. L.

    2012-07-01

    The presence of commanders in the field is a growing need in the nuclear sector. The education, training and monitoring of the leaders involved in monitoring programs, allow have a group of nuclear professionals that offer specific and useful feedback and helps improve plant safety.

  7. Storage facilities of spent nuclear fuel in dry for Mexican nuclear facilities; Instalaciones de almacenamiento de combustible nuclear gastado en seco para instalaciones nucleares mexicanas

    Energy Technology Data Exchange (ETDEWEB)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Sanchez J, J., E-mail: juan.salmeron@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    In this article the relevant aspects of the spent fuel storage and the questions that should be taken in consideration for the possible future facilities of this type in the country are approached. A brief description is proposed about the characteristics of the storage systems in dry, the incorporate regulations to the present Nuclear Regulator Standard, the planning process of an installation, besides the approaches considered once resolved the use of these systems; as the modifications to the system, the authorization periods for the storage, the type of materials to store and the consequent environmental impact to their installation. At the present time the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) considers the possible generation of two authorization types for these facilities: Specific, directed to establish a new nuclear installation with the authorization of receiving, to transfer and to possess spent fuel and other materials for their storage; and General, focused to those holders that have an operation license of a reactor that allows them the storage of the nuclear fuel and other materials that they possess. Both authorizations should be valued according to the necessities that are presented. In general, this installation type represents a viable solution for the administration of the spent fuel and other materials that require of a temporary solution previous to its final disposal. Its use in the nuclear industry has been increased in the last years demonstrating to be appropriate and feasible without having a significant impact to the health, public safety and the environment. Mexico has two main nuclear facilities, the nuclear power plant of Laguna Verde of the Comision Federal de Electricidad (CFE) and the facilities of the TRIGA Reactor of the Instituto Nacional de Investigaciones Nucleares (ININ) that will require in a future to use this type of disposition installation of the spent fuel and generated wastes. (Author)

  8. Seleção de clones de batata para microclimas de altitude no Planalto Central Selection of potato cultivars for high altitude microclimates in Central Brazil

    Directory of Open Access Journals (Sweden)

    Nei Peixoto

    2002-09-01

    Full Text Available Iniciou-se em 1986, em Anápolis, um programa de desenvolvimento de cultivares de batata adaptadas ao clima de altitude do Brasil Central, partindo-se de 15.000 genótipos, resultantes de 200 famílias obtidas pela Embrapa Hortaliças em 1985 e 1986. No primeiro ciclo, em 1986, foram selecionados 5.000 genótipos, considerando-se aspectos fenológicos, incidência de doenças, qualidade dos tubérculos e potencial de produção. Esses mesmos critérios foram adotados nas gerações posteriores, selecionando-se, anualmente, 15-20% de genótipos superiores. Em 1990 avaliaram-se 52 destes clones, tendo como testemunhas as cultivares Achat e Bintje; Destes foram selecionados 28 clones promissores que foram submetidos à cultura de ápices caulinares e à indexação para os vírus PLRV, PVY e PVX na Embrapa Hortaliças. No período de 1995 a 1997 foram avaliados em Goiás, nos municípios de Anápolis, Morrinhos, Pirenópolis e Urutaí, e em Jaboticabal. Os dados foram submetidos à análise de variância, e aqueles referentes a 14 genótipos em 7 ambientes, à regressão pelo método de Eberhart & Russell. Os clones BAT 2, BAT 3, BAT 4, BAT 19, BAT 27 e BAT 28 destacaram-se entre os mais produtivos, considerando-se, também, as características de tubérculos para o consumo. Os genótipos responderam proporcionalmente à melhoria do ambiente. O clone BAT 19 foi o mais estável.A potato selection program was done in Anapolis, State of Goias, Brazil, beginning in 1986 with 15,000 genotypes, resulting from 200 crosses obtained by Embrapa Hortaliças in 1985 and 1986. In the first selection cycle, in 1986, 5,000 genotypes were selected, considering plant growth and development, disease incidence, tuber quality and yield potential. These criteria were also adopted in further generations, when 15 to 20% of the best genotypes were yearly selected. In 1990 52 of the selected genotypes were evaluated in comparison with the cultivars Achat and Bintje. The

  9. Tamanho e Número Ideal de Amostras para Coleta de Gafanhotos na Região Depressão Central do Rio Grande do Sul

    OpenAIRE

    Nathália Carvalho; Ervandil Costa; Danilo Souza; Juliana Garlet

    2013-01-01

    Objetivando observar a viabilidade de um novo método para amostragem de acridóideos (conhecidos vulgarmente por gafanhotos), bem como a distancia percorrida e número ideal de amostras para amostragem foi proposto o estudo. Os levantamentos foram conduzidos em duas áreas de campo nativo no município de São Sepé, localizado na região Depressão Central no RS. As coletas foram realizadas durante o verão de 2009 com o auxilio de uma rede de coleta adaptada. As distâncias avaliadas foram de 5, 10, ...

  10. A utilização da lavadora de louça industrial: uma alternativa para a central de material e esterilização

    Directory of Open Access Journals (Sweden)

    Yukie Yokoyama

    1994-03-01

    Full Text Available Neste estudo as autoras relatam a experiência desenvolvida na Central de Material e Esterilização de um hospital de grande porte da cidade de São Paulo, na utilização de uma máquina lavadora de louça de uso industrial, readaptada com temperatura ideal para o processo de lavagem de instrumental. O estudo apresenta uma forma alternativa de trabalho com diminuição do tempo para operacionalização do serviço e menor exposição do pessoal aos resíduos orgânicos.

  11. Blogs para la enseñanza de literatura infantil y juvenil en español: espacio central de la LIJ 2.0

    OpenAIRE

    Rovira Collado, José; Llorens García, Ramón Francisco

    2012-01-01

    Para analizar la recepción de las obras de literatura infantil y juvenil en internet, los blogs continúan siendo un espacio fundamental para la opinión crítica, la reflexión académica y la práctica docente configurándose como eje central del concepto LIJ 2.0. Después de analizar dicho concepto, se presentarán en primer lugar los principales blogs de la LIJ en castellano, donde encontramos espacios de escritores e ilustradores, propuestas de animación a la lectura, repositorios de obras y crít...

  12. Use of nuclear fusion systems for spent nuclear fuel degradation;Utilizacion de sistemas de fusion nuclear para degradacion de combustible nuclear gastado

    Energy Technology Data Exchange (ETDEWEB)

    Nieto, M.; Ramos, G. [IPN, Centro de Investigacion en Ciencia Aplicada y Tecnologia Avanzada, Unidad Queretaro, Cerro Blanco 141, Colinas del Cimatario, 76090 Queretaro (Mexico); Herrera V, J. J. E., E-mail: mnieto@ipn.m [UNAM, Instituto de Ciencias Nucleares, Circuito Exterior, Ciudad Universitaria, 04510 Mexico, D. F. (Mexico)

    2009-10-15

    One of the severe problems of the nuclear industry that should be resolved to facilitate its acceptance like viable energy alternative is of the wastes. In spite of having alternative of fuel reprocessing, many of them have been abandoned by economic or security reasons. In the present work, the alternative is described for using reactors of nuclear fusion as sources of fast neutrons with two important applications in mind: the plutonium burning and the transmutation of the elements that contribute in way more important to their radioactivity, mainly the smaller actinides and the fission products of long half life. (Author)

  13. A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Central Asia

    International Nuclear Information System (INIS)

    The goal of this research work is to promote the cooperation in the field of nuclear related works with Kazakhstan and Uzbekistan which are main countries in the central Asia. To make a basis on exchanging researchers, a staff in KAERI had visited INP NNC RK, touring research reactors, and make a discussion with the staffs in INP. With this, there is a efforts to make an arrangement between KAERI and NNC RK, signing will be made in near futures. To understand the level of nuclear technology in Uzbekistan, Dr. Rho had made a trip to INP. He visited the Gamma-radiation facility, a research reactor. In Nov. 2005, the chairman of Science Academy visited Korea to discuss the future cooperation in the field of peaceful use of the nuclear energy. By doing so, Korea will make an effort to cooperate with countries in the Central Asia

  14. A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Central Asia

    Energy Technology Data Exchange (ETDEWEB)

    Rho, Si Pyo; Kim, Cheol Jung; Yoo, Bung Duk; Kim, Jae Woo; Lee, Myung Ho; Kim, Kyung Pyo

    2006-02-15

    The goal of this research work is to promote the cooperation in the field of nuclear related works with Kazakhstan and Uzbekistan which are main countries in the central Asia. To make a basis on exchanging researchers, a staff in KAERI had visited INP NNC RK, touring research reactors, and make a discussion with the staffs in INP. With this, there is a efforts to make an arrangement between KAERI and NNC RK, signing will be made in near futures. To understand the level of nuclear technology in Uzbekistan, Dr. Rho had made a trip to INP. He visited the Gamma-radiation facility, a research reactor. In Nov. 2005, the chairman of Science Academy visited Korea to discuss the future cooperation in the field of peaceful use of the nuclear energy. By doing so, Korea will make an effort to cooperate with countries in the Central Asia.

  15. Determination of activity by gamma spectrometry of radionuclides present in drums of residues generated in nuclear centrals; Determinacion de actividad por espectrometria gamma de radionucleidos presentes en tambores de residuos generados en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, J.C.; Fernandez, J. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250, Ciudad Autonoma de Buenos Aires (Argentina)]. e-mail: jaguiar@cae.arn.gov.ar

    2006-07-01

    The generation of radioactive residuals in nuclear centrals as CNA I (Atucha I Nuclear Central) and CNE (Embalse Nuclear Central) makes that the measurement of those radionuclides has been a previous stage to the waste management. A method used in those nuclear centrals it is the gamma spectrometry with HPGe detectors, previous to the immobilization of the residual in a cemented matrix, with this the contact with the external agents and its possible dispersion to the atmosphere in the short term is avoided. The ARN (Nuclear Regulatory Authority) of Argentina it carries out periodically intercomparisons and evaluations of the measurement and procedures systems used in the nuclear power stations for the correct measurement and determination of activity of radioactive residuals by gamma spectrometry. In this work an independent method of measurement is exposed to the nuclear power stations. To determine the activity of the residuals by gamma spectrometry deposited in drums, it is required of the precise knowledge of the efficiency curve for such geometry and matrix. Due to the RNA doesn't have a pattern of these characteristics, a mathematical model has been used to obtain this efficiency curve. For it, it is necessary to determine previously: 1) the geometric efficiency or solid angle sustained by the source-detector system (drum-detector) applying a mathematical model described in this work. 2) To estimate the auto-attenuation factor that present the photons in the cemented matrix, these calculations are carried out with a simple equation and its are verified with the Micro Shield 6.10 program. The container commonly used by these nuclear power stations its are drums for 220 liters constructed with SAE 1010 steel and with a thickness of 0.127 cm, with an approximate weight 7.73 Kg., internal diameter of 57.1 cm, and height: 87 cm. The results obtained until the moment register a discrepancy from 5 to 10% with relationship to the measurements carried out by the

  16. International Conference Nuclear Energy in Central Europe 99, V. 2. Proceedings. Embedded Meeting Neutron Imaging Methods to Detect Defects in Materials

    International Nuclear Information System (INIS)

    International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The second book of proceedings contain 14 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics cover Neutron Imaging Methods

  17. Science and technology as strategic way for nuclear activities; A C e T como fator estrategico para as atividades nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Paiano, Silvestre

    2000-07-01

    The article brings few instructive examples on the interaction between nuclear energy and other areas of science and technology, Microelectronics, computer technology, and new materials are among the many technologies which are crucial for developing nuclear energy technology. On the other way round, nuclear energy presents also a wide range of new demands and opportunities for several areas of science and technology. The problem is that such a relationship is not well understood by the society, and to a large extent it brings about the very process of legitimating the use of nuclear energy (author)

  18. Report on the Fourth Reactor Refueling. Laguna Verde Nuclear Central. Unit 1. April-May 1995

    International Nuclear Information System (INIS)

    The fourth refueling of the Unit 1 of Laguna Verde Nuclear Central was executed in the period of April 17 to May 31 of 1995 with the participation of a task group of 358 persons, included technicians and radiation protection officials and auxiliaries.The radiation monitoring and radiological surveillance to the workers was present length ways the refueling process and always attached to the ALARA criteria. The check points for radiation levels were set at: primary container or dry well, reloading floor, decontamination room (level 10.5), turbine building and radioactive waste building. To take advantage of the refueling process, rooms 203 and 213 of the turbine buildings were subject to inspection and maintenance work in valves, heaters and drains of heaters. Management aspects as personnel selection and training, costs, and countable are also presented in this report. Owing to the high cost of man-hour of the members of the ININ staff, its participation in the refueling process was in smaller number than years before. (Author)

  19. Role of nuclear factor kappa B in central nervous system regeneration

    Institute of Scientific and Technical Information of China (English)

    Christian Engelmann; Falk Weih; Ronny Haenold

    2014-01-01

    Activation of nuclear factor kappa B (NF-κB) is a hallmark of various central nervous system (CNS) pathologies. Neuron-speciifc inhibition of its transcriptional activator subunit RelA, also referred to as p65, promotes neuronal survival under a range of conditions, i.e., for ischemic or excitotoxic insults. In macro-and microglial cells, post-lesional activation of NF-κB triggers a growth-permissive program which contributes to neural tissue inlfammation, scar formation, and the expression of axonal growth inhibitors. Intriguingly, inhibition of such inducible NF-κB in the neuro-glial compartment, i.e., by genetic ablation of RelA or overexpression of a trans-dominant negative mutant of its upstream regulator IκBα, significantly enhances functional recovery and promotes axonal regeneration in the mature CNS. By contrast, depletion of the NF-κB subunit p50, which lacks transcriptional activator function and acts as a transcriptional repressor on its own, causes precocious neuronal loss and exacerbates axonal degeneration in the lesioned brain. Collectively, the data imply that NF-κB orchestrates a multicellular pro-gram in whichκB-dependent gene expression establishes a growth-repulsive terrain within the post-lesioned brain that limits structural regeneration of neuronal circuits. Considering these subunit-speciifc functions, interference with the NF-κB pathway might hold clinical potentials to improve functional restoration following traumatic CNS injury.

  20. Masses and Scaling Relations for Nuclear Star Clusters, and their Coexistence with Central Black Holes

    CERN Document Server

    Georgiev, Iskren Y; Leigh, Natan; Lützgendorf, Nora; Neumayer, Nadine

    2016-01-01

    Galactic nuclei typically host either a Nuclear Star Cluster (NSC, prevalent in galaxies with masses $\\lesssim 10^{10}M_\\odot$) or a Massive Black Hole (MBH, common in galaxies with masses $\\gtrsim 10^{12}M_\\odot$). In the intermediate mass range, some nuclei host both a NSC and a MBH. In this paper, we explore scaling relations between NSC mass (${\\cal M}_{\\rm NSC}$) and host galaxy total stellar mass (${\\cal M}_{\\star,\\rm gal}$) using a large sample of NSCs in late- and early-type galaxies, including a number of NSCs harboring a MBH. Such scaling relations reflect the underlying physical mechanisms driving the formation and (co)evolution of these central massive objects. We find $\\sim\\!1.5\\sigma$ significant differences between NSCs in late- and early-type galaxies in the slopes and offsets of the relations $r_{\\rm eff,NSC}$--${\\cal M}_{\\rm NSC}$, $r_{\\rm eff, NSC}$--${\\cal M}_{\\star,\\rm gal}$ and ${\\cal M}_{\\rm NSC}$--${\\cal M}_{\\star,\\rm gal}$, in the sense that $i)$ NSCs in late-types are more compact at...

  1. Elaboration of database to support the selection of sites for nuclear installations; Elaboracao de banco de dados para suporte a escolha de locais para instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Dayana Braga Cordeiro; Martins, Vivian Borges, E-mail: braga1dayana@gmail.com, E-mail: vbmartins@gmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The main objective of this study is to collect data to develop a geocoded geographic database, contributing to the monitoring of nuclear activities situated in the Sao Francisco Basin, and also treat, adapt, display, and organize these data in the form of a single database so that they can be used in the decision-making process.

  2. Mortality pattern of the surrounding population of the Central Nuclear Almirante Alvaro Alberto / 1986 to 2007; Padrao da mortalidade da populacao circunvizinha a Central Nuclear Almirante Alvaro Alberto / 1986 a 2007

    Energy Technology Data Exchange (ETDEWEB)

    Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos [Fundacao Eletronuclear de Assistencia Medica (CIRA/FEAM), Angra dos Reis, RJ (Brazil). Centro de Informacoes sobre Radioepidemiologia; Xavier, Diego Ricardo [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil). lnst. de Comunicacao e Informacao Cientifica e Tecnologica; Silva, Roseli Monteiro da [Fundacao Inst. Oswaldo Cruz (FIOCRUZ), Rio de Janeiro, RJ (Brazil)

    2011-05-15

    This paper aims to update two earlier epidemiological studies on the mortality profile of the resident population in the influence area of the Central Nuclear Almirante Alvaro Alberto. The main objective is analyze and compare the profile of mortality among the population classified in areas with the distance from source of exposure in three strata. Municipalities contained within a radius of 30 km of the nuclear power, neighboring municipalities, contained within a radius of 30 to 50 km, municipalities contained within 50 to 100 km, beyond Cabo Frio, which presents similar characteristics to the municipality of Angra dos Reis

  3. Determination of activity by gamma spectrometry of radionuclides present in drums of residues generated in nuclear centrals

    International Nuclear Information System (INIS)

    The generation of radioactive residuals in nuclear centrals as CNA I (Atucha I Nuclear Central) and CNE (Embalse Nuclear Central) makes that the measurement of those radionuclides has been a previous stage to the waste management. A method used in those nuclear centrals it is the gamma spectrometry with HPGe detectors, previous to the immobilization of the residual in a cemented matrix, with this the contact with the external agents and its possible dispersion to the atmosphere in the short term is avoided. The ARN (Nuclear Regulatory Authority) of Argentina it carries out periodically intercomparisons and evaluations of the measurement and procedures systems used in the nuclear power stations for the correct measurement and determination of activity of radioactive residuals by gamma spectrometry. In this work an independent method of measurement is exposed to the nuclear power stations. To determine the activity of the residuals by gamma spectrometry deposited in drums, it is required of the precise knowledge of the efficiency curve for such geometry and matrix. Due to the RNA doesn't have a pattern of these characteristics, a mathematical model has been used to obtain this efficiency curve. For it, it is necessary to determine previously: 1) the geometric efficiency or solid angle sustained by the source-detector system (drum-detector) applying a mathematical model described in this work. 2) To estimate the auto-attenuation factor that present the photons in the cemented matrix, these calculations are carried out with a simple equation and its are verified with the Micro Shield 6.10 program. The container commonly used by these nuclear power stations its are drums for 220 liters constructed with SAE 1010 steel and with a thickness of 0.127 cm, with an approximate weight 7.73 Kg., internal diameter of 57.1 cm, and height: 87 cm. The results obtained until the moment register a discrepancy from 5 to 10% with relationship to the measurements carried out by the

  4. The stress tests performed by the Spanish nuclear power plants.; Las pruebas de resistencia realizadas a las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, J. R.

    2011-07-01

    In the wake of the accident that occurred at Fukushima nuclear power plant in Japan, the European Union decided to subject the European plants to a reassessment of their safety margins, in accordance with the lessons learned from that accident. On December 31st last, following a process of exhaustive analysis, the Nuclear Safety Council submitted the final reports corresponding to the evaluations performed by the Spanish nuclear power plants, with the results obtained and conclusions drawn. Also detailed are the actions proposed to improve the nuclear safety of these facilities in response to extreme situations. (Author)

  5. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2007 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2007/01/01; Worldwide status of nuclear power plants (12/31/2007); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2007; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2007; Performance indicator of French PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2007; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2007; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2007; Long term shutdown units at 12/31/2007; COL (combined licences) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary.

  6. Conventional and intelligent generalized supervisory control for combined cycle generating power stations.; Control supervisiorio generalizado convencional e inteligente para centrales de generacion de ciclo combinado

    Energy Technology Data Exchange (ETDEWEB)

    Martinez M, Miguel A; Sanchez P, Marino [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico); Gonzalez Rubio S, Jose L [Cento Nacional de Investigacion y Desarrollo Tecnologico (Cenidet), Cuernavaca, Morelos (Mexico)

    2005-07-01

    Under the expectations of expansion of electric power generation in Mexico, this work exposes the development of a conventional and intelligent generalized supervisory control (CSG) for a combined cycle generation power plant. This one allows to obtain the optimal operation of the power plant through the automatic starting of the generating units and to obtain the maximum possible amount of electrical power in automatic and safe form. For the development of the CSG a control loop by temperature was implemented for the gas turbine system and a control loop by strangled pressure for the gas turbine and a control loop by strangled pressure for the steam turbine. The design of these supervisory systems was made with base in the critical limits on the involved variables of the process: blading average temperature, for the gas turbine (GT) and strangled pressure for the steam turbine (ST) [Spanish] Bajo estas expectativas de expansion de generacion de energia en Mexico, este trabajo expone el desarrollo de un control supervisorio generalizado (CSG) para una central generacion de ciclo combinado. Este permite lograr la operacion optima de la planta a traves del arranque automatico de las unidades generadoras y obtener la maxima cantidad posible de potencia electrica en forma automatica y segura. Para el desarrollo del CSG se implanto un lazo de control por temperatura para el sistema de turbina de gas y un lazo de control por presion estrangulada para la turbina de gas y un lazo de control por presion estrangulada para la turbina de vapor. El diseno de estos sistemas supervisorio se realizo con base en los limites criticos de las variables del proceso involucradas: temperatura promedio de empaletado para la turbina de gas (TG) y presion estrangulada para la turbina de vapor (TV)

  7. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

  8. Feasibility of the operation CFE`s conventional power plants for industrial cogeneration; Factibilidad de operar las centrales termoelectricas convencionales de la CFE para cogeneracion industrial

    Energy Technology Data Exchange (ETDEWEB)

    Buendia Dominguez, Eduardo H.; Acosta Torres, Rosa Aracely [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1997-12-31

    An analysis is made on how cogeneration could help to maximize the power plant performance since thanks to cogeneration this type of power plants could utilize a part of the waste energy to be supplied to other processes. Also mention is made of the utilization of computer programs to help the design and the realization of functioning tests of this type of power plants. An economic evaluation is presented on the feasibility of operating this type of power plants as cogeneration units and it is concluded that the operation of fossil power plants in the cogeneration mode is not affected by the site where the power plant is located [Espanol] Se analiza como la cogeneracion podria ayudar a maximizar el rendimiento de las centrales termoelectricas ya que gracias a la cogeneracion este tipo de centrales podrian utilizar una parte de la energia desechada para suministrarla a otros procesos. Tambien se menciona la utilizacion de programas de computo para auxiliar en el diseno o realizacion de pruebas de funcionamiento sobre este tipo de plantas. Se presenta una evaluacion economica sobre la factibilidad de operar este tipo de plantas como unidades de cogeneracion y se concluye en que la operacion de centrales termoelectricas en modo de cogeneracion no se ve afectado por el sitio donde se encuentra la central

  9. ORBITALES. A program for the calculation of wave functions with an analytical central potential; ORBITALES. Programa de calculo de Funciones de Onda para una Potencial Central Analitico

    Energy Technology Data Exchange (ETDEWEB)

    Yunta Carretero; Rodriguez Mayquez, E.

    1974-07-01

    In this paper is described the objective, basis, carrying out in FORTRAN language and use of the program ORBITALES. This program calculate atomic wave function in the case of ths analytical central potential (Author) 8 refs.

  10. Early alert system for oscillations detection applied to the Central of Laguna Verde; Sistema de alerta temprana para deteccion de oscilaciones aplicada a la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Calleros M, G.; Zapata Y, M.; Avila N, A.; Herrera H, S. F., E-mail: gcm9acpp@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Veder, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

    2011-11-15

    The code Early Alert System developed by Engineering of the Reactor of the nuclear power plant of Laguna Verde is presented, showing its reliability like preventive and corrective instrument to external interferences to the reactor core, due to equipment malfunction associated to the typical systems of a nuclear power plant, as those that control the reactor pressure, those that feed water to the reactor, those that control the valves of the main turbine. With this purpose, real cases of application of the System are shown where the results are compared with the independent evaluations carried out by the supplier, observing compatibility in both results. The benefits of the logarithm are discussed in the nuclear industry as soon as in non nuclear ambits. (Author)

  11. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1997 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1997; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; forecasts; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

  12. Allocation of responsibilities between central and local authorities concerning nuclear power plant licensing

    International Nuclear Information System (INIS)

    This paper examines Belgian regulations on licences to construct and operate nuclear power plants in the context of implementation of the 1980 Act concerning regionalisation. It also reviews the relevant nuclear legislation in certain other countries. (NEA)

  13. 75 FR 9576 - Civil Nuclear Policy Mission to Central and Eastern Europe

    Science.gov (United States)

    2010-03-03

    ... and support an indigenous civil nuclear industry--the first of many milestones laid out by the... Slovakia is still a year or more away from releasing a nuclear tender, language included in the...

  14. Neutron-skin effect and centrality dependence of high-$p_{\\mathrm{T}}$ observables in nuclear collisions

    CERN Document Server

    Helenius, Ilkka; Eskola, Kari J

    2016-01-01

    We report on our studies of the neutron-skin effects in high-$p_{\\mathrm{T}}$ observables at the LHC. We study the impact of the neutron-skin effect on the centrality dependence of inclusive direct photon, high-$p_{\\mathrm{T}}$ hadron and $W^{\\pm}$ production in nuclear collisions at the LHC. The neutron-skin effect refers to the observation that in spherical heavy nuclei, the tail of the neutron distribution extends farther than the distribution of protons, which can affect observables sensitive to electroweak phenomena in very peripheral collisions. We quantify this effect for direct photons, charged hadrons and W bosons as a function of the collision centrality. In the case of direct photons we find that it will be difficult to resolve the neutron-skin effect, given the uncertainties in the nuclear PDFs and their spatial dependence. With charged hadrons and W's, however, up to 20~\\% unambiguous effects are expected for most peripheral collisions.

  15. US central station nuclear electric generating units: significant milestones (status as of April 1, 1982)

    International Nuclear Information System (INIS)

    Milestone dates are presented concerning the licensing and operating activities of US nuclear power plants. Listings of US nuclear power plants are also presented in alphabetical arrangement by state and alphabetical arrangement by electric utility. Projected US nuclear power plant growth is presented through the year 1990

  16. Central nuclear almirante Alvaro Alberto: study on the phytoplanktonic variation in the region of unity 1 - Angra dos Reis - RJ

    International Nuclear Information System (INIS)

    By according of ''staff'' which has elaborated the first works in phitoplankton, in initial phasis (before operation) of Central Nuclear Almirante Alvaro Alberto - CNAAA Unidade 1, Angra dos Reis, Rio de Janeiro, Brazil we carry out a search about physic - chemicals parameters at same area, during the times of 11 months, too. The efluent region presents a phytoplanktonic comunity of reasonable environmental conditions. The evaluation of biological parameters, or in the words, a natural environment in equilibrium. (author)

  17. Mejoras en el sistema MOIRA para su aplicación a los emplazamientos nucleares fluviales españoles

    OpenAIRE

    Gallego Díaz, Eduardo F.; Iglesias Ferrer, Rafael; Dvorzhak, Alla; Hofman, Dmitry

    2011-01-01

    Entre las posibles secuelas de un accidente nuclear hay que contar con la contaminación radiactiva a medio y largo plazo de los sistemas acuáticos de agua dulce. Frente a ese problema, es fundamental disponer de una evaluación realista del impacto radiológico, ecológico, social y económico de las posibles estrategias de gestión, para poder adoptar las decisiones más convenientes de forma racional. MOIRA es un sistema de ayuda a la decisión desarrollado en el curso de los Programas Marco Europ...

  18. Turbine model for the Laguna Verde nucleo electric central based in the RELAP code; Modelo de turbina para la Central nucleoelectrica de Laguna Verde basado en el codigo RELAP

    Energy Technology Data Exchange (ETDEWEB)

    Cortes M, F.S.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [Facultad de Ingenieria, Division de Estudios de Posgrado, Grupo de Ingenieria Nuclear, UNAM (Mexico)]. e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    The Nuclear Power stations as Laguna Verde occupy at the present time a place every time but important as non pollutant alternative, economic and trusty to generate electricity. It is for it that the Group of Nuclear Engineering of the Engineering Faculty (GrlNFI) of the National Autonomous University of Mexico (UNAM) it develops investigation projects applied to Nuclear Centrals. One of the projects in process is the development of a Classroom simulator, which it can configures to consent to diverse models of nuclear systems with training purposes in normal operation, or, to consent to specialized nuclear codes for the analysis of transitory events and have a severe accident. This work describes the development, implementation and it proves of a simplified model of the Main turbine to be integrated to the group of models of the Classroom simulator. It is part of the current effort of GrlNFI guided to obtain a representation of all the dynamic models necessary to simulate the Plant Balance of the Laguna Verde Central. It is included the development of the unfolding graphic which represent the modeling of the Main turbine, and of the control interface that allows the user to manipulate in simple way, direct and interactive this device during the training or the analysis. With this work it is wanted to contribute to the training of new technicians and to support the operation personnel of the Centrals. Also, the developed infrastructure is guided to contribute in the design and analysis of new Nuclear Power stations with the contribution of new computational tools for the visualization, simulation and process control. (Author)

  19. Nuclear emergency buildings of Asco and Vandellos II nuclear power plants; Centros alternativos de emergencias de las centrales nucleares de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Massuet, J.; Sabater, J.; Mirallas Esteban, S.

    2016-08-01

    The Nuclear Emergency Buildings sited at Asco and Vandellos II Nuclear Power Plants (NPP) are designed to safety manage emergencies in extreme situations, beyond the design basis of the Nuclear Power Plants. Designed in accordance with the requirements of the Spanish Nuclear Regulator (Consejo de Seguridad Nuclear-CSN) these buildings are ready to operate over a period of 72 hours without external assistance and ensure habitability for crews of 120 and 70 people respectively. This article describes the architectural conception, features and major systems of the Nuclear Emergency Buildings sited at Asco and Vandellos II. (Author)

  20. Development of 3D models of buildings for containment of the nuclear power plant of Almaraz and of the Trillo Nuclear with the GOTHIC 8.0 code; Desarrollo de modelos 3D de los edificios de conten cion de la Central Nuclear de Almaraz y de la Central Nuclear de Trillo con el codigo GOTHIC 8.0

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, G.; Bocanegra Melian, R.; Fernandez Cosils, K.; Barreira Pereira, P.; Rey Peinado, L.; Posada Barral, J. M.

    2014-07-01

    The objective of the first phase of the research of CNAT and the UPM project is the construction of several three-dimensional models detailed GOTHIC 8.0 code of containment of a buildings plant type PWR-W and KWU, corresponding to the Central Nuclear de Almaraz (CNA) and Trillo (CNT) respectively. (Author)

  1. Anàlisis de contenció en un accident termohidràulic d'una central nuclear

    OpenAIRE

    Zamora Povea, Imanol

    2013-01-01

    Aquest projecte és el resultat de la cooperació entre el món universitari i l’empresa privada, doncs ha requerit de la cooperació de la Secció d'Enginyeria Nuclear de la Universitat Politècnica de Catalunya i l’àrea Nuclear Services de l’enginyeria IDOM S.A. El treball desenvolupat ha tingut dues vessants diferenciades. La primera línia de treball ha sigut l’elaboració d’un model de la contenció de la central nuclear Vandellòs II mitjançant el codi GOTHIC v7.2a. Així mateix, s’ha tractat d...

  2. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities

    International Nuclear Information System (INIS)

    This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic

  3. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project

    Energy Technology Data Exchange (ETDEWEB)

    Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia (Tish) P. Tuttle

    2012-01-31

    This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic

  4. ¿Es cierto que una central térmica de carbón da lugar a más emisiones radiactivas que una central nuclear?

    OpenAIRE

    J.A. Menéndez

    2009-01-01

    Se ha dicho que, por unidad de energía producida, una central térmica de carbón emite, principalmente en las cenizas volantes, una cantidad de radiactividad 100 veces superior a la que emite una central nuclear de fisión. ¿Es esto cierto?

  5. ¿Es cierto que una central térmica de carbón da lugar a más emisiones radiactivas que una central nuclear?

    Directory of Open Access Journals (Sweden)

    J.A. Menéndez

    2009-08-01

    Full Text Available Se ha dicho que, por unidad de energía producida, una central térmica de carbón emite, principalmente en las cenizas volantes, una cantidad de radiactividad 100 veces superior a la que emite una central nuclear de fisión. ¿Es esto cierto?

  6. Propuesta preliminar de sistema experto para determinar el método de ensayo no destructivo aplicado a una central hidroeléctrica

    OpenAIRE

    Javier H. Lafont; Marisa D. Panizzi; Sattolo, Iris; Desimone, Carlos; Ziobrowsky, Claudio; García, Alejandro; Obrutsky, Alba; Méndez, Jorge; Acosta, Daniel

    2013-01-01

    El propósito de esta línea de investigación consiste en la conceptualización de un Sistema Experto que permite determinar que método de Ensayo No Destructivo es el indicado para ser aplicado en una Central Hidroeléctrica. Se empleará para ello la metodología I.D.E.A.L., de la Ingeniería del Conocimiento. En este estadio del trabajo de investigación se realizó la definición del dominio, el cálculo de viabilidad de la propuesta y la adquisición del conocimiento de los expertos. Luego se avanzar...

  7. Diseño de un calentador de agua de alimentación para una central térmica

    OpenAIRE

    González Díaz, Damián

    2010-01-01

    El presente proyecto consistente en el diseño de un calentador de agua de alimentación para una Central Térmica para producción de electricidad, ha sido realizado en colaboración con la empresa Foster Wheeler Energía S.L.U, con el apoyo técnico de sus programas informáticos y bibliografía. Foster Wheeler Energía S.L.U pertenece a Foster Wheeler Global Power Group, que es una de las dos unidades de negocio del grupo Foster Wheeler Limited, cuya sede reside en New Jersey, (E.E.U.U.). Foster Whe...

  8. A high resolution record of chlorine-36 nuclear-weapons-tests fallout from Central Asia

    Energy Technology Data Exchange (ETDEWEB)

    Green, J.R. E-mail: jaromy.green@gcccks.edu; Cecil, L.D.; Synal, H.-A.; Santos, J.; Kreutz, K.J.; Wake, C.P

    2004-08-01

    The Inilchek Glacier, located in the Tien Shan Mountains, central Asia, is unique among mid-latitude glaciers because of its relatively large average annual accumulation. In July 2000, two ice cores of 162 and 167 meters (m) in length were collected from the Inilchek Glacier for (chlorine-36) {sup 36}Cl analysis a part of a collaborative international effort to study the environmental changes archived in mid-latitude glaciers worldwide. The average annual precipitation at the collection site was calculated to be 1.6 m. In contrast, the reported average annual accumulations at the high-latitude Dye-3 glacial site, Greenland, the mid-latitude Guliya Ice Cap, China, and the mid-latitude Upper Fremont Glacier, Wyoming, USA, were 0.52, 0.16 and 0.76 m, respectively. The resolution of the {sup 36}Cl record in one of the Inilchek ice cores was from 2 to 10 times higher than the resolution of the records at these other sites and could provide an opportunity for detailed study of environmental changes that have occurred over the past 150 years. Despite the differences in accumulation among these various glacial sites, the {sup 36}Cl profile and peak concentrations for the Inilchek ice core were remarkably similar in shape and magnitude to those for ice cores from these other sites. The {sup 36}Cl peak concentration from 1958, the year during the mid-1900s nuclear-weapons-tests period when {sup 36}Cl fallout was largest, was preserved in the Inilchek core at a depth of 90.56 m below the surface of the glacier (74.14-m-depth water equivalent) at a concentration of 7.7 x 10{sup 5} atoms of {sup 36}Cl/gram (g) of ice. Peak {sup 36}Cl concentrations from Dye-3, Guliya and the Upper Fremont glacial sites were 7.1 x 10{sup 5}, 5.4 x 10{sup 5} and 0.7 x 10{sup 5} atoms of {sup 36}Cl/g of ice, respectively. Measurements of {sup 36}Cl preserved in ice cores improve estimates of historical worldwide atmospheric deposition of this isotope and allow the sources of {sup 36}Cl in ground

  9. Albicampo, variedad de frijol de temporal para Valles Altos de la Mesa Central Albicampo, rainfed bean variety for the High Valleys of the Central Mexican Plateau

    OpenAIRE

    Dagoberto Garza-García; Ramón Garza-García; Carmen Jacinto-Hernández

    2010-01-01

    Albicampo (Phaseolus vulgaris L.) es una variedad de grano negro opaco pequeño, tipo Jamapa, liberada en 2010 por el programa de frijol del Campo Experimental Valle de México (CEVAMEX) del Instituto Nacional de Investigaciones Forestales, Agrícolas y Pecuarias (INIFAP). Se obtuvo mediante una cruza simple, utilizando selección masal hasta la generación F4. En la F5 se realizó selección individual para resistencia a enfermedades, calidad de grano y características agronómicas. Esta variedad se...

  10. Environmental management systems implemented in the Spanish nuclear power plants; Sistemas de gestion ambiental implantados en las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Redondo, R.; Fernandez Guisado, M. B.; Hortiguela, R.; Bustamante, L. F.; Esparza, J. L.; Villareal, M.; Yague, F.

    2013-09-01

    The companies that own the Spanish Nuclear Power Plants, aware of social concern and in the context of a growing demanding environmental legislation, have a permanent commitment to the electricity production based on the principles of a maximum respect for the environment, safety, quality, professionalism and continuous improvement. In order to minimize the environmental impact of their plants they have implemented and Environmental Management System based on the ISO 14001 Standard. They minimize the environmental impact by identifying the significant environmental aspects and defining the corresponding objectives. This article describes the referred environmental management systems and their environmental objectives, as applied and defined by the Spanish Nuclear Power Plants. (Author)

  11. Accelerating the global nuclear renaissance: the central challenge of sustainable development

    International Nuclear Information System (INIS)

    The rebirth of nuclear energy has become an unmistakable reality that is gathering speed and momentum on the full world stage. All around the world, old-school anti-nuclear environmentalism is being eclipsed by a new realism that recognises nuclear energy's essential virtue: its capacity to deliver cleanly generated power safely, reliably, and on a massive scale. For serious environmentalists, the real challenge is that nuclear energy is not yet growing fast enough to play its needed role in the clean-energy revolution our world so desperately needs. A fair assessment shows that not one of the commonly cited ''public concerns'' poses a reasonable obstacle to a global expansion of nuclear power: Proliferation, Operational Safety, Cost Reduction, Waste Management. In three areas, governments must take decisive action to grow the nuclear industry: (1) Construct a comprehensive global regime to curtail greenhouse emissions; (2) Elevate nuclear investment to a national and international policy priority; and (3) Support educational development of the nuclear profession for an expanded global role. The global nuclear industry will be indispensable if humanity is to preserve the environment that enabled civilisation to evolve. Governments must emerge from postures of timidity and equivocation to act decisively in support of that industry. Our world is in dire peril, and we have no time to lose

  12. Modularization in construction processes New Nuclear Power Plants; Modularizacion en procesos de construccion de Nuevas Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Martinez, I.; Cobos, A.; Herrera Ropero, D.

    2012-07-01

    The aim of this work is that it has the capacity and expertise to analyze the suitability of modular technology design and construction compared to conventional nuclear plants. It will define the criteria for selecting the areas of modularity and the impact on design and its interfaces with engineering, supply, including logistics and construction.

  13. Apoyo para políticas y estrategias de manejo integrado de recursos hídricos en América Central

    OpenAIRE

    Enrique Aguilar; Fernando López; Nelson Flores; Luis Morgan

    1999-01-01

    El presente informe presenta los resultados de la cooperación técnica no reembolsable BID-CRRH N° ATN/SF-5758-RG. "Apoyo para políticas y estrategias de manejo integrado de recursos hídricos en América Central". El trabajo se sustenta en una serie de entrevistas realizadas en Costa Rica, El Salvador, Guatemala, Honduras, Nicaragua y Panamá. El diálogo establecido por los consultores con los niveles técnicos y políticos, así como con representantes de distintos grupos sociales o sectores inter...

  14. Utilización del diseño central compuesto para evaluar la robustez de un método de CLAR

    OpenAIRE

    Soares, Luiz Alberto Lira; Pereira de Souza, Tatiane; González Ortega, George; Petrovick, Pedro Ros

    2007-01-01

    El objetivo del presente trabajo fue evaluar la robustez del método CLAR-fase invertida, previamente validado, para separación y cuantificación de catequina y epicatequina. La robustez fue investigada por medio de un diseño central compuesto, las variables independientes fueron concentración de ácido acético y proporciones iniciales de acetonitrila y las variables dependientes fueran el tiempo de retención, el factor de capacidad y la resolución de ambos picos. El ensayo fue realizado u...

  15. Una perspectiva geoarqueológica para comprender la ocupación humana en la costa central de la provincia de Buenos Aires

    OpenAIRE

    Verónica Aldazabal; Nilda E. Weiler; Emilio Eugenio

    2004-01-01

    El trabajo plantea los condicionamientos ambientales que sustentan un modelo de colonización humana en la región costera central de la provincia de Buenos Aires a partir del Holoceno medio. Desde el punto de vista geomorfológico, estratigráfico y cronológico se determinó la presencia de líneas de costa con edades entre los 5200 y 2200 AP. Por otro lado, se aportan datos acerca de las características de los suelos, de la vegetación y de posibles recursos para la subsistencia humana a partir de...

  16. Microsurgical approach of arteriovenous malformations in the central lobule Abordagem microciúrgica para malformações arteriovenosas no lóbulo central

    OpenAIRE

    Feres Chaddad-Neto; Andrei Fernandes Joaquim; Marcos Juliano dos Santos; Paulo Wagner Linhares; Evandro de Oliveira

    2008-01-01

    Arteriovenous malformations (AVM) are neurovascular disorders that occur mainly in young adults. Their clinical presentation is variable and depends on its location, size and occurrence of bleeding. They can represent incidental findings in neuro radiological exams. The treatment of these lesions when located in eloquent areas, namely around the central sulcus, is controversial, with different therapeutical approaches presented in the literature. We consider that surgical extirpation of many ...

  17. Utilização da técnica do varal para angioplastia de estenose de veia central com stent-graft Utilization of the through-and-through technique for central vein angioplasty using stent-graft

    Directory of Open Access Journals (Sweden)

    Ricardo Wagner da Costa Moreira

    2012-09-01

    Full Text Available A estenose de veia central é uma das situações mais frequentes em pacientes com insuficiência renal crônica em hemodiálise. A angioplastia com o uso de stent-graft tem obtido bons resultados nestes casos. O sistema de liberação dos stents é de calibre maior, podendo dificultar sua navegabilidade em áreas de estenose ou tortuosidade acentuadas. A técnica do varal é comumente utilizada para o tratamento endovascular do aneurisma de aorta, permitindo atingir bom mecanismo de estiramento e facilitando a navegação do sistema de entrega da endoprótese. Descrevemos o caso de uma angioplastia de veia central com stent-graft na qual foi utilizada a técnica do varal para permitir a transposição da área de estenose.The central vein stenosis is one of the most common conditions in patients with chronic kidney failure in a hemodialysis program. In these cases, angioplasty using stent-grafts has obtained good results. The stent-graft delivery system is generally of large diameter what can hinder its navigability in very severe stenosis or tortuosities. The through-and-through technique is commonly used for endovascular treatment of aortic aneurysms, making possible to achieve a good mechanism of stretch and easy navigation of the endograft delivery system. We report a case of a central venous stenosis in wich a stent-graft was inserted using the through-and-through technique in order to cross the lesion.

  18. Biópsia estereotáxica para linfomas primários do sistema nervoso central

    OpenAIRE

    MURILO S. MENESES; Brian P. O'Neill; Kelly, Patrick J.

    1992-01-01

    Os linfomas primários do SNC são raros, mas sua incidência tem aumentado nos últimos anos, Estes tumores frequentemente se localizam nos gânglios da base e tálamo ou se apresentam de forma multifocal. O tratamento atual para eles é a radioterapia, associada ou não a quimioterapia. Devido à sua extremamente baixa morbidade, a biópsia estereo-táxica é o método ideal para determinar o diagnóstico histológico em pacientes com suspeita de linfomas do SNC. Os autores apresentam estudo de 49 casos d...

  19. TCF/Lef regulates the Gsx ParaHox gene in central nervous system development in chordates

    OpenAIRE

    Garstang, Myles Grant; Osborne, Peter; Ferrier, David Ellard Keith

    2016-01-01

    Background The ParaHox genes play an integral role in the anterior-posterior (A-P) patterning of the nervous system and gut of most animals. The ParaHox cluster is an ideal system in which to study the evolution and regulation of developmental genes and gene clusters, as it displays similar regulatory phenomena to its sister cluster, the Hox cluster, but offers a much simpler system with only three genes. Results Using Ciona intestinalis transgenics, we isolated a regulatory element upstream ...

  20. Molecular species identification of Central European ground beetles (Coleoptera: Carabidae using nuclear rDNA expansion segments and DNA barcodes

    Directory of Open Access Journals (Sweden)

    Raupach Michael J

    2010-09-01

    Full Text Available Abstract Background The identification of vast numbers of unknown organisms using DNA sequences becomes more and more important in ecological and biodiversity studies. In this context, a fragment of the mitochondrial cytochrome c oxidase I (COI gene has been proposed as standard DNA barcoding marker for the identification of organisms. Limitations of the COI barcoding approach can arise from its single-locus identification system, the effect of introgression events, incomplete lineage sorting, numts, heteroplasmy and maternal inheritance of intracellular endosymbionts. Consequently, the analysis of a supplementary nuclear marker system could be advantageous. Results We tested the effectiveness of the COI barcoding region and of three nuclear ribosomal expansion segments in discriminating ground beetles of Central Europe, a diverse and well-studied invertebrate taxon. As nuclear markers we determined the 18S rDNA: V4, 18S rDNA: V7 and 28S rDNA: D3 expansion segments for 344 specimens of 75 species. Seventy-three species (97% of the analysed species could be accurately identified using COI, while the combined approach of all three nuclear markers provided resolution among 71 (95% of the studied Carabidae. Conclusion Our results confirm that the analysed nuclear ribosomal expansion segments in combination constitute a valuable and efficient supplement for classical DNA barcoding to avoid potential pitfalls when only mitochondrial data are being used. We also demonstrate the high potential of COI barcodes for the identification of even closely related carabid species.

  1. US central station nuclear electric generating units: significant milestones (status as of July 1, 1980)

    International Nuclear Information System (INIS)

    The status of 189 US nuclear power plants is reported in a table which gives the name, owner, capacity, type, NSSS architect and contractor and data of public announcement, NSSS order, licensing, and initial operation. The plants are also indexed according to state, region, utility, and alphabetical name. The utility nuclear steam supply system orders are also listed

  2. Elecnuc. Nuclear power plants in the world; Elecnuc. Les centrales nucleaires dans le monde

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1999 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1999; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; grid connection forecasts; world electric power market; electronuclear owners and share holders in EU, capacity and load factor; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; 1999 gross load factor by operator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

  3. Technological tendencies for the improvement of the performance of combined cycle power stations; Tendencias tecnologicas para el mejoramiento del desempeno de centrales de cilco combinado

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez P, Marino; Garduno R, Raul; Chavez T, Rafael [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2001-07-01

    In this article are dealt some the aspects that have turned the combined cycle generating power stations (CCGPS) into the dominant way for the electrical generation in the world. In the first part it is presented the plan of expansion of the national electrical generation and similar information that the U.S.A. has for the CCGPS, which will give an idea of the importance and the impact that has this technology at the moment. The basic characteristics that are necessary to specify in order to satisfy the environmental and operation requirements, and the available technologies to increase the global efficiency of the CCGPS are also exposed. Finally it describes the evolution of the technology of control for CCGPS developed in the Gerencia de Control e Instrumentacion (GCI), as well as the capacities available to support the electrical sector in this technological discipline. [Spanish] En este articulo se tratan algunos de los aspectos que han convertido a las centrales de generacion de ciclo combinado (CGCC) en el modo dominante para la generacion electrica en el mundo. En la primera parte se presenta el plan de expansion de la generacion electrica nacional e informacion similar que los EE.UU. tienen para las CGCC, lo que dara una idea de la importancia y del impacto que tiene actualmente esta tecnologia. Se exponen tambien las caracteristicas principales que es necesario especificar a fin de satisfacer los requerimientos ambientales y de operacion, y las tecnologias disponibles para incrementar la eficiencia global de las CGCC. Finalmente se describe la evolucion de la tecnologia de control para CGCC desarrollada en la Gerencia de Control e Instrumentacion (GCI), asi como las capacidades disponibles para apoyar al sector electrico en esta disciplina tecnologica.

  4. Methodology for the integral comparison of nuclear reactors: selecting a reactor for Mexico; Metodologia para la comparacion integral de reactores nucleares: seleccion de un reactor para Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Reyes R, R.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)]. e-mail: ricarera@yahoo.com.mx

    2006-07-01

    In this work it was built a methodology to compare nuclear reactors of third generation that can be contemplated for future electric planning in Mexico. This methodology understands the selection of the reactors to evaluate eliminating the reactors that still are not sufficiently mature at this time of the study. A general description of each reactor together with their main ones characteristic is made. It was carried out a study for to select the group of parameters that can serve as evaluation indicators, which are the characteristics of the reactors with specific values for each considered technology, and it was elaborated an evaluation matrix indicators including the reactors in the columns and those indicators in the lines. Since that none reactor is the best in all the indicators were necessary to use a methodology for multi criteria taking decisions that we are presented. It was used the 'Fuzzy Logic' technique, the which is based in those denominated diffuse groups and in a system of diffuse inference based on heuristic rules in the way 'If Then consequence> ', where the linguistic values of the condition and of the consequence is defined by diffuse groups, it is as well as the rules always they transform a diffuse group into another. Later on they combine all the diffuse outputs to create a single output and an inverse transformation is made that it transfers the output from the diffuse domain to the real one. They were carried out two studies one with the entirety of the indicators and another in which the indicators were classified in three approaches: the first one refers to indicators related with the planning of the plants inside the context of the general electric sector, the second approach includes indicators related with the characteristics of the fuel and the third it considers indicators related with the acting of the plant in safety and environmental impact. This second study allowed us to know the qualities of

  5. Datos para la historia de una iniciativa fallida: la escuela central de gimnástica Data for the history of a unsuccessful enterprise: the Central School of Gimnastics

    Directory of Open Access Journals (Sweden)

    Anastasio MARTÍNEZ NAVARRO

    2013-09-01

    Full Text Available El objetivo de este artículo es plantear algunos fenómenos de fondo que explican la historia de la Escuela Central de Gimnástica de Madrid (1883-1892, primer centro oficial establecido en España para la formación de los profesores de educación física, cuya corta vida en realidad sólo se extiende de 1887 a 1892. En el momento de su clausura, todos los documentos fueron almacenados en los archivos de la Universidad Central (hoy Universidad Complutense de Madrid. La revisión de esta documentación fundamenta este trabajo que esperamos ofrezca nuevas informaciones sobre las condiciones de la Escuela, funcionamiento y razones explicativas de su efímera vida.The aim of this article has been to put forward some badknown facts dealing with the history of the Central School of Gymnastics of Madrid (1883-1892, the former physical education teachers' training Centre stablished in Spain, which short life only spread realy from 1887 to 1892. At the time of its closing, all its documents were stored in the archives of Central University (Complutense University of Madrid, at present; the review of these papers is the documentary basis underlaying this work which offers, we hope, some new information about the School conditions and operation and about the reasons explaining its ephemeral life.

  6. Analysis of pumping systems to large flows of cooling water in power plants; Analisis de sistemas de bombeo para grandes flujos de agua de enfriamiento en centrales termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Sanchez, Ramon; Herrera Velarde, Jose Ramon; Gonzalez Sanchez, Angel [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)]. E-mail: rsanchez@iie.org.mx; jrhv@iie.org.mx; ags@iie.org.mx

    2010-11-15

    Accurate measurement of large water flows remains being a challenge in the problems of implementation of circulating water systems of power plants and other applications. This paper, presents a methodology for the analysis in pumping systems with high rates of water in power plants, as well as their practical application and results in pipelines water flow of a thermoelectrical power plant of 350 MW. In this power plant, the water flow per pipeline for a half of condenser oscillates around 7 m{sup 3}/s (14 m{sup 3}/s per power generating unit). In this analysis, we present the techniques used to measure large flows of water with high accurately, as well as the computational model for water circulating system using PIPE FLO and the results of practical application techniques. [Spanish] La medicion precisa de grandes flujos de agua, sigue siendo un reto en los problemas de aplicacion de sistemas de agua de circulacion de centrales termoelectricas, entre otras aplicaciones. En este articulo, se presenta una metodologia para el analisis de sistemas de bombeo con grandes flujos de agua en centrales termoelectricas, asi como, su aplicacion practica y los resultados obtenidos en los ductos de agua de circulacion de una central generadora con unidades de 350 MW. En esta central, los flujos por caja de agua oscilan alrededor de los 7 m{sup 3}/s (14 m{sup 3}/s por unidad generadora). En el analisis, se presentan las tecnicas utilizadas para medir con precision grandes flujos de agua (tubo de Pitot), asi como, el modelado del sistema de agua de circulacion por medio de un paquete computacional (PIPE FLO) y resultados obtenidos de la aplicacion de dichas tecnicas.

  7. Whole study of nuclear matter collective motion in central collisions of heavy ions of the FOPI detector

    International Nuclear Information System (INIS)

    In this work we study the collective phenomena in the central collisions of heavy ions for the Au + Au, Xe + CsI and Ni + Ni systems at incident energies from 150 to 400 MeV/nucleon with the data of the FOPI detector. In order to describe completely the flow of the nuclear matter, we fit the double differential momentum distributions with two-dimensional Gaussian. We study the characteristic parameters of the collective flow (flow range, aspect ratios, flow parameter) versus the charge and the mass of the fragments as well as the incident energy and the centrality of the collisions. The transverse energy is used for selecting the central collisions. The method of the Gaussian fits requires also to reconstruct the reaction plane of the event. Then we correct the parameters for the finite number of particles effects and account for the influence of the acceptance of the detector. We confirm the importance of the thermal motion for the light charge or mass fragments and, conversely, the predominance of the collective motion for the heavy fragments. A common flow angle for all the types of particles is highlighted for the first time, demonstrating the power of the method of the Gaussian fits; The evolution of the other parameters confirms the observations done with other methods of flow analysis. These results should contribute to put constraints on the collision models and to enlarge our knowledge of the properties of the nuclear matter. (author)

  8. um san joanense na organizaçao europeia para a investigaçao nuclear

    CERN Multimedia

    Gomes Costa, Joana

    2006-01-01

    Pedro Martel is a Sanjoanense, aged 39 years, who is involved in the most recent project of the European Organisation for Nuclear Research (CERN) in Geneva, Switzerland: this project will recreate the conditions of the "Big Bang" (1 page)

  9. Superiority of centralized procurement and its technical and economic analysis for nuclear power intensification construction

    International Nuclear Information System (INIS)

    The intensified management is the basic orientation for modernized enterprise group to improve efficiency and benefit. For most industrial enterprises, in the implementation of intensification management process, the centralized procurement is one of most efficient paths. At present most of the international's and domestic outstanding enterprises are studying and positively using this approach. This article indicated that the centralized procurement mode is inevitable during intensification construction process based on the theoretical analysis of the advantage of centralized procurement and the economic analysis of typical cases. (author)

  10. Internalization of externalities in the generation costs of electric power centrals of carbon, combined cycle and nuclear; Internalizacion de externalidades en los costos de generacion de centrales electricas de carbon, ciclo combinado y nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gomez R, M.C. [Universidad Anahuac del Norte (Mexico); Palacios H, J.; Ramirez S, R.; Alonso V, G. [ININ, Carretera Mexico-Toluca Km. 36.5 Ocoyoacac 52750 Edo. de Mexico (Mexico)]. e-mail: fgrivera@avantel.net

    2007-07-01

    The technologies of electric power generation that use fossil fuels, they incorporate in the Even Total Cost of Generation (CTNG) only the direct costs of generation (investment, fuel costs, operation costs and maintenance). nevertheless, the nuclear energy incorporates besides the direct costs, the externalities that causes to the human health and the environment. In this work the CTNG is calculated that incorporates the externalities, of a thermoelectric power station of coal, a plant of combined cycle and of four reactors of Generation III (ABWR, ACR, AP1000 and EPR). The obtained results show that the nuclear power station has smaller CTNG that the technologies that use fossil fuels. It is important to stand out that they are only considering the externalities of the stage of electricity generation, for what the mining phase and transport of the fuel toward the central are not considered in the present document. (Author)

  11. A prototype system dynamic model of nuclear and radiological export controls in Central Asia and the Caucasus; enhancing the effectiveness of preventing illicit nuclear material trafficking

    International Nuclear Information System (INIS)

    An urgent need calls out for improved border security and export control systems in the Central Asian and Caucasus regions to prevent illicit nuclear and radioactive materials trafficking. Effective nuclear and radiological exports controls are essential because these regions contain numerous nuclear facilities and radioactive materials as well as lie at the crossroads between seekers and suppliers of technologies that could be employed in nuclear and radiological weapons. Porous and unprotected borders compound these concerns. Moreover, the states within these regions are struggling with forming new regulations and laws, obtaining sufficient portal monitoring equipment, training customs and border security personnel, and coordinating these activities with neighboring states. Building this infrastructure all at once can severely task any government. Thus, unsurprisingly, most of these states have inadequate export control and border security systems. To enable each state in these regions determine how to better prevent illicit nuclear and radiological materials trafficking, the authors have developed a prototype system dynamics model focused on evaluating and improving of effectiveness of export controls. System dynamics modeling, a management tool that grew out of the field of system engineering and nonlinear dynamics, uses two structures: causal loop diagrams and stock and flow diagrams. The former shows how endogenous systematic factors interact with each other to produce feedback mechanisms that results in either balancing or reinforcing loops. A classic example is a arms race, modeled as a vicious cycle or reinforcing loop. In addition to interacting with each other, causal loops influence the flow of stock, which is material concern. In the export control system dynamics model, the stock represents nuclear and radioactive materials. System dynamics modelling is an iterative process that is continually modified by user input. Therefore, export control

  12. The reactor ALLEGRO and the sustainable nuclear energy in Central Europe

    OpenAIRE

    Gadó János

    2014-01-01

    The Visegrád-4 countries (CZ, HU, PL and SK) would like to use nuclear energy on the long run. The construction of new Generation 3+ nuclear units probably belong in each country to this realm. These reactors will provide safe and cheap electric energy approximately until the end of the 21st century. In order to use nuclear energy in the 22nd century, sustainability of fuel supply shall be achieved by applying Generation 4 breeder reactors with fast spectrum. The corresponding research and de...

  13. Dispositivo de posicionamiento de muestras biológicas para su irradiación en un canal radial de un reactor nuclear

    OpenAIRE

    Maritza Rodríguez - Gual; Felix Mas – Milián; Airton Deppman; Paulo Rogerio Pinto - Coelho

    2011-01-01

    Por la demanda de un dispositivo experimental para el posicionamiento de las muestras biológicas para su irradiación en un canal radial de un reactor nuclear de investigaciones en funcionamiento, se construyó y se puso en marcha un dispositivo para la colocación y retirada de las muestras en la posición de irradiación de dicho canal. Se efectuaron las valoraciones económicas comparando con otro tipo de dispositivo con las mismas funciones. Este trabajo formó parte de un proyecto internacional...

  14. Recommendations for the nuclear fuel management in Mexico; Recomendaciones para la gestion del combustible nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Ortega C, R.F. [FI-UNAM, Paseo Cuauhnahuac 8532, Jiutepec, Morelos (Mexico)

    2003-07-01

    In this work some observations about the economic and strategic importance of the nuclear fuel management of a nucleo electric power station are presented, especially of the fuel management outside of the reactor core or supply function. We know that the economic competitiveness of the nucleo electric generation in fact resides in its low cost of fuel, in comparison with other alternative energy generation sources. Notwithstanding, frequently it is not given to this function the importance that should to have. The objective of this work is to focus again the mission of this activity, at view of the evolution and the peculiarities of the international markets of the nuclear fuel cycle. Equally a brief exhibition of the markets is made, from the uranium supply until the post- irradiation phase. In the case of the pre-irradiation phase we are in front of a market that the buyers dominate and that seemingly it will not present bigger problems in the next years, however situations exist like the decrease of the existent uranium inventories and the lack opening of new mines that can change the panorama. In relation with the post-irradiation phase, is necessary to study the strategies followed by other countries as the one uranium and plutonium recycled. As I have observed that the reality of that this passing in these markets and the practice of the fuel management, sometimes do not go of the hand, I have looked for to contribute some ideas and suggestions, on as going adapting this important function. (Author)

  15. A proactive method for safety management in nuclear facilities; Um metodo proativo para gerenciamento da seguranca em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Grecco, Claudio Henrique dos Santos; Carvalho, Paulo Victor Rodrigues de; Santos, Isaac Antonio Luquetti dos, E-mail: grecco@ien.gov.br, E-mail: paulov@ien.gov.br, E-mail: luquetti@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN/RJ), Rio de Janeiro, RJ (Brazil). Div. de Instrumentacao e Confiabilidade Humana

    2014-07-01

    Due to the modern approach to address the safety of nuclear facilities which highlights that these organizations must be able to assess and proactively manage their activities becomes increasingly important the need for instruments to evaluate working conditions. In this context, this work presents a proactive method of managing organizational safety, which has three innovative features: 1) the use of predictive indicators that provide current information on the performance of activities, allowing preventive actions and not just reactive in safety management, different from safety indicators traditionally used (reactive indicators) that are obtained after the occurrence of undesired events; 2) the adoption of resilience engineering approach in the development of indicators - indicators are based on six principles of resilience engineering: top management commitment, learning, flexibility, awareness, culture of justice and preparation for the problems; 3) the adoption of the concepts and properties of fuzzy set theory to deal with subjectivity and consistency of human trials in the evaluation of the indicators. The fuzzy theory is used primarily to map qualitative models of decision-making, and inaccurate representation methods. The results of this study aim an improvement in performance and safety in organizations. The method was applied in a radiopharmaceutical shipping sector of a nuclear facility. The results showed that the method is a good monitoring tool objectively and proactively of the working conditions of an organizational domain.

  16. The reactor ALLEGRO and the sustainable nuclear energy in Central Europe

    Directory of Open Access Journals (Sweden)

    Gadó János

    2014-01-01

    Full Text Available The Visegrád-4 countries (CZ, HU, PL and SK would like to use nuclear energy on the long run. The construction of new Generation 3+ nuclear units probably belong in each country to this realm. These reactors will provide safe and cheap electric energy approximately until the end of the 21st century. In order to use nuclear energy in the 22nd century, sustainability of fuel supply shall be achieved by applying Generation 4 breeder reactors with fast spectrum. The corresponding research and development is organized now in the framework of the V4G4 Centre of Excellence establshed by the nuclear research institutes of the region with a strong technical support from the French CEA. The most important milestone of these efforts is the start-up of the ALLEGRO reactor that shall demonstrate the viability of the gas cooled fast reactor technology.

  17. The reactor ALLEGRO and the sustainable nuclear energy in Central Europe

    Science.gov (United States)

    Gadó, János

    2014-09-01

    The Visegrád-4 countries (CZ, HU, PL and SK) would like to use nuclear energy on the long run. The construction of new Generation 3+ nuclear units probably belong in each country to this realm. These reactors will provide safe and cheap electric energy approximately until the end of the 21st century. In order to use nuclear energy in the 22nd century, sustainability of fuel supply shall be achieved by applying Generation 4 breeder reactors with fast spectrum. The corresponding research and development is organized now in the framework of the V4G4 Centre of Excellence establshed by the nuclear research institutes of the region with a strong technical support from the French CEA. The most important milestone of these efforts is the start-up of the ALLEGRO reactor that shall demonstrate the viability of the gas cooled fast reactor technology.

  18. 1989 annual report of the Rossendorf Central Institute of Nuclear Research

    International Nuclear Information System (INIS)

    The research and development results are classified by research lines. Each section starts with an introduction summing up the developments of the particular field of work, followed by progress reports on specific projects, contributions on partial results not published so far, and summaries of 1989 publications. Research priorities are, among others, the fields of nuclear spectroscopy; ion-beam solid state physics; positron emission tomography; nuclear trace technology; neutron doping, and accelerator development. (DG)

  19. Radioisotope production using U-120 cyclotron, Central Institute for Nuclear Research, Rossendorf (DDR)

    International Nuclear Information System (INIS)

    The method of radionuclide production at the Rossendorf U-120 cyclotron and chemical reprocessing of the products produced into radiopharmaceuticals, aimed at application in nuclear medice, are described. The radionuclides are produced by target irradiation at nuclear reactions (4He, 2n), (d, 2n), (d, n), (d, α) and others. 67Ga, 81Rb-21mKr, 211At, 111In, 123I, 18F radionuclide production are considered in detail. The Rossendorf U-120 cyclotron beam parameters are also presented

  20. AZTLAN platform: Mexican platform for analysis and design of nuclear reactors; AZTLAN platform: plataforma mexicana para el analisis y diseno de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A. M.; Puente E, F. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Edif. 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Francois L, J. L.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: armando.gomez@inin.gob.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco No. 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)

    2014-10-15

    The Aztlan platform Project is a national initiative led by the Instituto Nacional de Investigaciones Nucleares (ININ) which brings together the main public houses of higher studies in Mexico, such as: Instituto Politecnico Nacional, Universidad Nacional Autonoma de Mexico and Universidad Autonoma Metropolitana in an effort to take a significant step toward the calculation autonomy and analysis that seeks to place Mexico in the medium term in a competitive international level on software issues for analysis of nuclear reactors. This project aims to modernize, improve and integrate the neutron, thermal-hydraulic and thermo-mechanical codes, developed in Mexican institutions, within an integrated platform, developed and maintained by Mexican experts to benefit from the same institutions. This project is financed by the mixed fund SENER-CONACYT of Energy Sustain ability, and aims to strengthen substantially to research institutions, such as educational institutions contributing to the formation of highly qualified human resources in the area of analysis and design of nuclear reactors. As innovative part the project includes the creation of a user group, made up of members of the project institutions as well as the Comision Nacional de Seguridad Nuclear y Salvaguardias, Central Nucleoelectrica de Laguna Verde (CNLV), Secretaria de Energia (Mexico) and Karlsruhe Institute of Technology (Germany) among others. This user group will be responsible for using the software and provide feedback to the development equipment in order that progress meets the needs of the regulator and industry; in this case the CNLV. Finally, in order to bridge the gap between similar developments globally, they will make use of the latest super computing technology to speed up calculation times. This work intends to present to national nuclear community the project, so a description of the proposed methodology is given, as well as the goals and objectives to be pursued for the development of the

  1. International assistance to upgrade the safety of Soviet-designed nuclear power plants. Selected activities in Eastern and Central Europe and the countries of the former Soviet Union

    International Nuclear Information System (INIS)

    The overview is merely a snapshot of nuclear safety activities to assist the countries of Eastern and Central Europe and the former Soviet Union. While many other activities are planned or ongoing, this publication is meant to provide a general overview of the world community's commitment to improving the safety of Soviet-designed nuclear reactors

  2. A cosmic-ray nuclear event with an anomalously strong concentration of energy and particles in the central region

    International Nuclear Information System (INIS)

    A cosmic-ray-induced nuclear event detected in an emulsion chamber is described. The event consist of 217 shower cores with ΣEγ=1.275 TeV. In a logarithmic scale, energy and particles are emitted most densely at the small lateral distance corresponding to 0.5 mm; 77% of the total energy and 61% of the total multiplicity are inside a radius of 0.65 cm. The shower cores in the central region show exponential-type energy distribution and nonisotropic azimuthal distribution

  3. The service lifetime of Spain's nuclear plants; La vida util de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez-Bolanos, M.

    2008-07-01

    In recent years consideration has been given to the long-term operation of nuclear reactors, beyond their originally foreseen design lifetime. This article analyses the legal and safety requirements that this implies, in the wake of the document dealing with this issue that was approved by the Plenary of the CSN in April 2005. The article is completed with an interview with Dale Klein, president of the United States regulatory body, in which he describes the experience accumulated in his country, where lifetime extensions have already been approved for 50 plants. (Author)

  4. Decree no 77-623 of 6 June 1977 amending Decree no 73-278 of 13 March 1973 setting up a Superior Council for Nuclear Safety and a Central Service for the Safety of Nuclear Installations

    International Nuclear Information System (INIS)

    Under this Decree, the Central Service for the Safety of Nuclear Installations is placed from now onwards within the Directorate of Mines which comes under the Ministry of Industry, Trade and Crafts. The Head of the Central Service for the Safety of Nuclear Installations and his deputy are appointed by Order of the Minister of Industry, Trade and Crafts, on the proposal of the Director of Mines. (NEA)

  5. Business plan of the Nuclear Information Center, Central Research Institute of Electric Power Industry

    International Nuclear Information System (INIS)

    The Nuclear Information Center was born on June 15, 1983, in the Research and Development Headquarters. The purpose of its establishment is to analyze and deliver synthetically the information on nuclear power generation as electric power industry by collecting all information, and to contribute to the safe operation and the improvement of reliability of nuclear power generation. The necessity of positively utilizing the information on the experience of nuclear power generation was recognized particularly owing to the TMI accident. The organization of the Center is composed of the divisions of statistical analysis, information analysis, technical development, information management and general affairs. The ''Committee of raising grade of nuclear power station information'', the ''Expert committee on information analysis and evaluation'' and so on are organized. The number of personnel of the Center is 21, and 12 of them are temporarily transferred from electric power companies. The business of the Center is as shown by the organization of the Center, and it is briefly explained. As the effective means to obtain the information from foreign countries, the Center has utilized the NOTEPAD system managed by the INPO of USA. Its information can be read through the communication networks of KDD and USA. (Kako, I.)

  6. Central depression in nuclear density and its consequences for the shell structure of superheavy nuclei

    International Nuclear Information System (INIS)

    The influence of the central depression in the density distribution of spherical superheavy nuclei on the shell structure is studied within the relativistic mean-field theory. A large depression leads to the shell gaps at the proton Z=120 and neutron N=172 numbers, whereas a flatter density distribution favors N=184 and leads to the appearance of a Z=126 shell gap and to the decrease of the size of the Z=120 shell gap. The correlations between the magic shell gaps and the magnitude of the central depression are discussed for relativistic and nonrelativistic mean field theories

  7. Central depression in nuclear density and its consequences for the shell structure of superheavy nuclei

    CERN Document Server

    Afanasjev, A V

    2005-01-01

    The influence of the central depression in the density distribution of spherical superheavy nuclei on the shell structure is studied within the relativistic mean field theory. Large depression leads to the shell gaps at the proton Z=120 and neutron N=172 numbers, while flatter density distribution favors N=184 for neutrons and leads to the appearance of a Z=126 shell gap and to the decrease of the size of the Z=120 shell gap. The correlations between the magic shell gaps and the magnitude of central depression are discussed for relativistic and non-relativistic mean field theories.

  8. Cost comparison of central electric power generation using coal and nuclear fuels

    International Nuclear Information System (INIS)

    This paper addresses the current and expected future costs of generating electricity with the two available practical modes of power generation, coal and nuclear. It describes the procedures and inputs used to arrive at the conclusion that generation with nuclear fuels will be about 16% more economical than generation with the best coal alternative. Recognizing the uncertainty in long range estimates of this type, various sensitivity checks are developed to determine how much the capital, fuel, and operating costs would have to change to force a change in the ranking of the alternatives. The results are current estimates of the costs of generating electricity in the future in the middle western area of the United States with large nuclear units, and with comparably sized and comparably loaded coal units firing high and low sulfur coals

  9. Industrial risks - Traceability and the centralization of responsibilities are essential for nuclear safety

    International Nuclear Information System (INIS)

    A new regulation has been implemented in France concerning the safety and the transparency of nuclear activities. The main changes are the centralisation of the responsibilities through first, a clear reaffirmation that the operator of the facility is the only responsible for the facility operations and secondly the limitation of sub-contracting to the level 3 for instance a society chosen by EDF to provide services can sub-contract some of these services but the sub-contractor himself is not allowed to sub-contract. The transparency of nuclear activities is improved through making it compulsory to have a written record of any decision taken in a nuclear facility. (A.C.)

  10. Automatic system of welding for nuclear fuel rods; Sistema automatico de soldadura para barras de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Romero G, M; Romero C, J. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1998-07-01

    The welding process of nuclear fuel must be realized in an inert gas environment (He) and constant flow of this. In order to reach these conditions it is necessary to do vacuum at the chamber and after it is pressurized with the noble gas (purge) twice in the welding chamber. The purge eliminates impurities that can provoke oxidation in the weld. Once the conditions for initiating the welding are gotten, it is necessary to draw a graph of the flow parameters, pressure, voltage and arc current and to analyse those conditions in which have been carried out the weld. The rod weld must be free of possible pores or cracks which could provoke rod leaks, so reducing the probability of these failures should intervene mechanical and metallurgical factors. Automatizing the process it allows to do reliable welding assuring that conditions have been performed, reaching a high quality welding. Visually it can be observed the welding process by means of a mimic which represents the welding system. There are the parameters acquired such as voltage, current, pressure and flow during the welding arc to be analysed later. (Author)

  11. Albicampo, variedad de frijol de temporal para Valles Altos de la Mesa Central Albicampo, rainfed bean variety for the High Valleys of the Central Mexican Plateau

    Directory of Open Access Journals (Sweden)

    Dagoberto Garza-García

    2010-12-01

    Full Text Available Albicampo (Phaseolus vulgaris L. es una variedad de grano negro opaco pequeño, tipo Jamapa, liberada en 2010 por el programa de frijol del Campo Experimental Valle de México (CEVAMEX del Instituto Nacional de Investigaciones Forestales, Agrícolas y Pecuarias (INIFAP. Se obtuvo mediante una cruza simple, utilizando selección masal hasta la generación F4. En la F5 se realizó selección individual para resistencia a enfermedades, calidad de grano y características agronómicas. Esta variedad se distingue de otras del mismo tipo comercial, por su alto rendimiento, excelente calidad culinaria y alto contenido de proteína, así plasticidad fenológica que le permite adaptarse a zonas, tanto de crítico como de buen temporal de lluvia. Es resistente a antracnosis (Colletotrichum lindemuthianum Sacc & Magn. Briosi & Cav., tizón común (Xanthomonas campestris pv phaseoli (Smith Dye y pudrición de raíz (Pythium y Rhizoctonia, y tolerante a roya (Uromyces appendiculatus (Pers.:Pers. Unger. Es de ciclo intermedio (105 a 115 días a madurez, su hábito de crecimiento es tipo III (indeterminado, con guía corta y flores moradas. Albicampo expresa su máximo potencial en áreas desde 2000 hasta 2400 msnm, suelo profundo y un mínimo de 350 mm de precipitación pluvial.Albicampo (Phaseolus vulgaris L., a small opaque dry bean seed variety from the Jamapa class, was released in 2010 by the bean program of the INIFAP's Campo Experimental Valle de Mexico. It was obtained through a simple cross, using bulk selection to the F4 followed by individual selection in F5 for disease, quality and agronomic traits. It distinguishes from other varieties of the same commercial class because of its high yield (>2 t ha-1, excellent cooking quality and high protein content, as well as phenological plasticity which enables it to adapt itself from critical to good rain season. It is resistant to anthracnose (Colletotrichum lindemuthianum Sacc & Magn. Briosi & Cav

  12. International conference on a nuclear-weapon-free zone in central Asia, 15-16 September 1997 Tashkent, Uzbekistan. Building an integral part of the global nuclear security system

    International Nuclear Information System (INIS)

    This Conference is the first fruit of the joint effort by the Central Asian States to counter external threats and challenges. The decision to declare Central Asia a nuclear-weapon-free zone is a further manifestation of the Central Asian States' shared interest in ensuring security, stability and peace for all the inhabitants of the region and in creating the necessary -indeed, the essential- conditions for its sustainable development and prosperity

  13. Phylogeny and biogeography of Poecilia (Cyprinodontiformes: Poeciliinae) across Central and South America based on mitochondrial and nuclear DNA markers.

    Science.gov (United States)

    Ho, Adeljean L F C; Pruett, Christin L; Lin, Junda

    2016-08-01

    Poeciliids are a diverse group of small Neotropical fishes, and despite considerable research attention as models in ecology and evolutionary biology, our understanding of their biogeographic and phylogenetic relationships is still limited. We investigated the phylogenetic relationships of South and Central American Poecilia, by examining 2395 base pairs of mitochondrial DNA (ATPase 8/6, COI) and nuclear DNA (S7) for 18 species across six subgenera. Fifty-eight novel sequences were acquired from newly collected specimens and 20 sequences were obtained from previously published material. Analyses of concatenated and partitioned mitochondrial DNA and nuclear DNA sets resulted in a well-supported phylogeny that resolved several monophyletic groups corresponding to previously hypothesized subgenera and species complexes. A divergence-dating analysis supported the hypothesis of the genus Poecilia dispersing into Central America in the early Pliocene (ancestors of Psychropoecilia+Allopoecilia+Mollienesia: 7.3-2.0Mya) from predominantly South America. Subsequently, one lineage (subgenus Allopoecilia: 5.1-1.3Mya) expanded deeper into South America from Lower-Central America, and one lineage expanded from Nuclear-Central America into South America (subgenus Mollienesia: 0.71-0.14Mya). The subgenus Mollienesia diverged into three monophyletic groups that can be identified by nuptial male dorsal fin morphology and inner jaw dentition. A subclade of the unicuspid short-fins (subgenus Mollienesia) was the lineage that expanded into South America during the middle Pleistocene. Species in this subclade are now distributed across northern South America, where they are partially sympatric with Allopoecilia. However the P. (A.) caucana complex was not monophyletic, with P. (A.) wandae clustering in the Mollienesia subclade that expanded into South America. It is apparent that characters (body size, scale count, pigmentation, and gonopodium morphology) used to define the P. (A

  14. Nuclear fuel cycle facilities in the world (excluding the centrally planned economies)

    International Nuclear Information System (INIS)

    Information on the existing, under construction and planned fuel cycle facilities in the various countries is presented. Some thirty countries have activities related to different nuclear fuel cycle steps and the information covers the capacity, status, location, and the names of owners of the facilities

  15. Development of renal simulators for use in nuclear medicine; Desenvolvimento de simuladores renais para uso em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Dullius, Marcos Alexandre

    2014-09-01

    Quality control programs in nuclear medicine include verifying the efficiency of all equipment used for diagnosis and therapy, including scintillation cameras. To that end, we have developed and evaluated the performance of four phantom kidneys - two static anthropomorphic, one semi-dynamic, and one dynamic - to acquire static and dynamic renal scintigraphic images. The static anthropomorphic phantoms were used to characterize and evaluate the response of the processing system for different concentrations of radionuclides through static renal scintigraphy images ({sup 99m}Tc-DMSA), obtained with posterior, right posterior oblique, left posterior oblique, and anterior incidences. The static phantoms were made in two ways; one was made of acrylic from a mold of a pair of human kidneys preserved in formalin, and the second was built with acrylonitrile butadiene styrene (ABS), in a 3D printer using the Slicer program, based on a computed tomography (CT) of the thorax, using the Slicer program. The semi-dynamic and dynamic phantoms were constructed to characterize and evaluate images of dynamic renal scintigraphy. In the semi-dynamic phantom, the injection of radiotracer was performed manually, whereas in the dynamic phantom, the radiotracer was automatically injected through an injector system. With the semi-dynamic phantom, it was possible to analyze the formation of a renogram with normal renal scintigraphic appearance using an imaging system. The simulations obtained from the dynamic phantom simulator enabled studies of normal renal scintigraphy and four other forms of renograms. The static anthropomorphic phantom kidneys proved to be efficient for use in evaluations of varying concentrations of radionuclides. The dynamic phantom kidney was useful for analysis of scintigraphic images and obtaining different pathways for elimination of the radioisotope, allowing for analysis of different renograms. Therefore, the new kidney phantoms would be useful for quality

  16. Statistical analysis about corrosion in nuclear power plants; Analisis estadistico de la corrosion en centrales nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Naquid G, C.; Medina F, A.; Zamora R, L. [Instituto Nacional de Investigaciones Nucleares, Gerencia de Ciencia de Materiales, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    Nowadays, it has been carried out the investigations related with the structure degradation mechanisms, systems or and components in the nuclear power plants, since a lot of the involved processes are the responsible of the reliability of these ones, of the integrity of their components, of the safety aspects and others. This work presents the statistics of the studies related with materials corrosion in its wide variety and specific mechanisms. These exist at world level in the PWR, BWR, and WWER reactors, analysing the AIRS (Advanced Incident Reporting System) during the period between 1993-1998 in the two first plants in during the period between 1982-1995 for the WWER. The factors identification allows characterize them as those which apply, they are what have happen by the presence of some corrosion mechanism. Those which not apply, these are due to incidental by natural factors, mechanical failures and human errors. Finally, the total number of cases analysed, they correspond to the total cases which apply and not apply. (Author)

  17. The Fossil Nuclear Outflow in the Central 30 pc of the Galactic Center

    CERN Document Server

    Hsieh, Pei-Ying; Hwang, Chorng-Yuan; Shimajiri, Yoshito; Matsushita, Satoki; Koch, Patrick M; Iono, Daisuke

    2016-01-01

    We report a new 1-pc (30") resolution CS($J=2-1$) line map of the central 30 pc of the Galactic Center (GC), made with the Nobeyama 45m telescope. We revisit our previous study of the extraplanar feature called polar arc (PA), which is a molecular cloud located above SgrA* with a velocity gradient perpendicular to the Galactic plane. We find that the PA can be traced back to the Galactic disk. This provides clues of the launching point of the PA , roughly $6\\times10^{6}$ years ago. Implications of the dynamical time scale of the PA might be related to the Galactic Center Lobe (GCL) at parsec scale. Our results suggest that in the central 30 pc of the GC, the feedback from past explosions could alter the orbital path of the molecular gas down to the central tenth of parsec. In the follow-up work of our new CS($J=2-1$) map, we also find that near the systemic velocity, the molecular gas shows an extraplanar hourglass-shaped feature (HG-feature) with a size of $\\sim$13 pc. The latitude-velocity diagrams show tha...

  18. Modernization of the subsystem man-machine interface for operation of the combined cycle central of Gomez Palacio; Modernizacion del subsistema de interfaz hombre-maquina para operacion de la central de ciclo combinado de Gomez Palacio

    Energy Technology Data Exchange (ETDEWEB)

    Rivas S, Alfonso; Uribe B, Carlos E; Alvarez C, Victor [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2002-07-01

    In order to take care of the modernization of the Combined Cycle Central of Gomez Palacio (CCCGP) of the Comision Federal de Electricidad (CFE), the Instituto de Investigaciones Electricas (IIE), through the Management of Supervision of Processes (GSP) developed the subsystem of Interface Man-Machine (IMM), to replace the workstations that are deteriorated and obsolete by personal computers, maintaining the same functions of the IMM of the present system, including the management and processing functions that at the present time another system makes. Also, to replace the equipment of the concentrators of communications by a PC with greater capacity, than allows improving in general the flexibility and robustness of the system. Among the main functions integrated in the IMM subsystem there are: the communications master with the controllers (equipment SAC), redundancy of servers, database, historical registry storage, alarm management, tabulations, tendency graphs in real time and historical, process diagrams and Control Panels. [Spanish] Con el objeto de atender las necesidades de modernizacion de la Central de Ciclo Combinado Gomez Palacio (CCCGP) de la Comision Federal de Electricidad (CFE), el Instituto de Investigaciones Electricas (IIE), a traves de la Gerencia de Supervision de Procesos (GSP) desarrollo el subsistema de Interfaz Hmbre-Maquina (IHM), para reemplazar las estaciones de trabajo que se encuentran deterioradas y obsoletas por computadoras personales, manteniendo las mismas funciones de la IHM del sistema actual, incluyendo las funciones de administracion y procesamiento que en la actualidad realiza otro sistema. Asimismo, para reemplazar los equipos de los concentradores de comunicaciones por PC con mayor capacidad, que permitan mejorar la flexibilidad y robustez del sistema en general. Entre las principales funciones integradas en el subsistema de IHM se encuentran: el Maestro de comunicaciones con los controladores (equipo SAC), redundancia de

  19. Central nervous system assessment in nuclear medicine. Clinical aspects: tracers and indications

    International Nuclear Information System (INIS)

    Nuclear neuroimaging techniques allow the study of functional and neurochemical aspects of the human brain in vivo. SPECT (Single Photon Emission Computed Tomography) as well as PET (Positron Emission Tomography) are non-invasive techniques which present two modalities: functional and biochemical. The functional one provides information about neuronal activity measured through metabolism (PET) or regional brain perfusion (SPECT, RMN f). Biochemical neuroimaging provides information on the chemical substrates involved in neurotransmission (receptors, transporters and enzymes) and allows the study of the synaptic activity through imaging of the different brain regions. This information about neurochemical aspects of neurotransmission is an exclusive field of nuclear neuroimaging techniques SPECT and PET. In this paper we discuss the tracers used for each modality of brain SPECT as well as their main clinical uses. (author)

  20. NucleoRed - Computerized system for increasing the effectiveness of the technical administrative conduct of the Laguna Verde Central; NucleoRed - Sistema computarizado para incrementar la efectividad de la gestion tecnico-administrativa de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Luna D, J. [Central Nucleoelectrica Laguna Verde, Carretera cardel-Nautla Km. 42.5 Veracruz (Mexico)]. e-mail: jluna@cfe.gob.mx

    2003-07-01

    The on-line systems for the management of the Laguna Verde Central (CLV) have had the challenge to evolve from the PC's of first generation until emigrate to the new Internet technologies, so that they allow to the diverse work groups to have the computer tool that allows them to gather the necessary data and to carry out efficiently the analysis of their results. To confront the previous challenge, in the CLV it has been developed and implemented the Nucleo Red that is an on-line system with the objective of providing in it lines strategic information for the Technician-administrative management of the plant in the nuclear context. The Nucleo Red is the computational tool that reflects the technical administrative processes implemented by personnel of the different Operative departments, it seeks to cooperate to the reliable and efficient operation of the first nucleo electric central of Mexico, with technology and Mexican personnel the one which already it had received international recognitions. The perspective of this computer system is to continue inside the process of continuous improvement and that although it was designed for a nucleo electric plant it can also be taken to the conventional plants of generation of electric power, so that this technology can be taken advantage of in other non nuclear facilities. The objective of the present work, is to show the new modules that have been developed in the Nucleo Red, its operation in general, and the benefits that it presents its use. (Author)

  1. Política, burocracia e redes sociais: as nomeações para o alto escalão do Banco Central do Brasil

    OpenAIRE

    Cecília Olivieri

    2007-01-01

    O estudo das nomeações para os cargos de direção do Banco Central do Brasil, pela análise de redes sociais, permite compreender aspectos fundamentais do sistema político-administrativo brasileiro. A escolha dos dirigentes públicos afeta a governabilidade e a governança do país. A troca entre cargos e o apoio parlamentar podem garantir a estabilidade do governo, mas também podem reduzir o controle do Presidente da República sobre a burocracia e sobre a direção das políticas públicas. A análise...

  2. Propuesta para la recuperación de los machetes Zuazaga de los centrales azucareros con electrodos de acero al cromo.

    OpenAIRE

    R. Collazo Carceller; H. López Salinas; A. Días Romero

    2009-01-01

    El trabajo resume el estudio y análisis desarrollado, para la presentación de una propuesta tecnológica de recuperación de los machetes Zuazaga, en nuestros centrales azucareros. Se determinó la influencia de los parámetros, energía introducida (Hi), número de capas (Nc) y ancho del depósito (Ad), en la morfología y el incremento de la resistencia al desgaste abrasivo, utilizando el electrodo de acero al cromo DUR 600. Se realizó una valoración económica de la propuesta tecnológicaThis work, ...

  3. Hinkley point C: A new chance for nuclear power plant construction in central Europe?

    International Nuclear Information System (INIS)

    This text focuses on the decision of the European Commission on the admissibility of state support for the expansion of Hinkley Point C, a British nuclear power plant. The European Commission not only influenced the development of energy sector in the UK with its decision, but also sent a strong signal that it is possible to use state aid for new nuclear power plants in the EU. The example of the Czech Republic shows the way this signal may be perceived by governments and energy stakeholders and how it can influence the national debates about the construction of new nuclear power plants, even before the detailed information about the whole case of state aid for Hinkley Point C has been published. -- Highlights: •Text deals with the EU's decision on the state support for the NPP Hinkley Point C. •This decision sends a strong signal about possible state aid for new NPPs in the EU. •Other member states are possible to consider similar pattern of financing. •The case of the Czech Republic is used to demonstrate the situation

  4. Desarrollo de nuevos aceros ferríticos ODS para aplicaciones nucleares

    OpenAIRE

    García Rodríguez, Nerea

    2014-01-01

    Mención Internacional en el título de doctor El daño por irradiación que experimentan los metales utilizados en aplicaciones nucleares se traduce en modificaciones microestructurales que implican cambios drásticos en sus propiedades fruto de las colisiones entre partículas. La fragilización, el hinchamiento y la activación radioactiva son las consecuencias principales del bombardeo de neutrones. Los neutrones y los núcleos de los átomos de la red interaccionan provocando des...

  5. National phantoms bank for the service of nuclear medicine in Cuba. Utility for the quality control of the instrumentation; Banco de fantomas nacional para los servicios de medicina nuclear en Cuba. Utilidad para el control de calidad de la instrumentacion

    Energy Technology Data Exchange (ETDEWEB)

    Varela C, C.; Diaz B, M. [CCEEM, Calle 4 No. 455 (altos) e/19 y 21, Vedado, Ciudad Habana (Cuba); Lopez B, G.M. [CPHR, Calle 20 No. 4113 e/41 y 47, Playa Ciudad Habana (Cuba)]. e-mail: consuelo.varela@infomed.sld.cu

    2006-07-01

    Although, most of the applications in Nuclear Medicine have diagnostic ends, its going enlarging considerably the therapeutic applications. So that the diagnostic accuracy or the therapy effectiveness have not been affected, it becomes indispensable the quality control of the instrumentation, independently of its technological complexity and/or its exploitation period. Before the real lack of phantoms in the institutions, it was created a bank that puts to disposition of all the institutions, the existent phantoms in the country, and those that are going acquired, centralized by the State Control of Medical Equipment Center (CCEEM) and with Web access in its place www.eqmed.sld.cu. Having like base the elaboration of the National Protocol for the Quality Control of the Instrumentation in Nuclear Medicine that keeps in mind the international normative and the own existent conditions, were dictated and established two national regulations and its are being carried out the first audits to the instrumentation quality. These have evidenced the partial realization of the established quality controls in the services, the necessity to make aware as for the fulfillment of the criteria and quality concepts for the instrumentation, as well as the necessity to increase the phantoms number to the bank to guarantee the fulfillment of the Quality Control Programs. (Author)

  6. SIMPRO, a practical tool for training the staff of Laguna Verde nuclear power plant; El SIMPRO, una herramienta practica para la capacitacion y entrenamiento del personal de la CNLV

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez Valdez, Guillermo Omar; Gomez Camargo, Octavio; Castelo Cuevas, Luis; Vazquez Bustos, Jesus [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2012-06-22

    Laguna Verde Nuclear Power Plant (LVNPP) has implemented a real physical model, which represents several parts of a simplified version of its process. This development has proved to be very useful to improve the compliance with training programs and staff training maintenance in the different disciplines of engineering. Such programs are required by regulations and standards applicable for Nuclear Power Plants (NPP), so that the personnel working in these facilities can be able to respond on time to any contingency that might arise. This paper outlines the creation of the real physical model, how it is integrated and some of the practices that can be performed on this model. [Spanish] La Central Nucleoelectrica de Laguna Verde ha implementado un modelo fisico real que representa varias partes de una version simplificada de su proceso. Este desarrollo ha demostrado ser muy util para mejorar el cumplimiento de programas de adiestramiento, incluidos los del personal de mantenimiento, en diferentes disciplinas de ingenieria. Dichos programas son requeridos por las regulaciones y normas aplicables a las centrales nucleoelectricas, de manera que el personal que trabaja en estas instalaciones pueda ser capaz de responder oportunamente a cualquier contingencia que pudiera surgir. Este articulo describe la creacion del modelo fisico real, como se integra y algunas de las practicas que pueden llevarse a cabo con el.

  7. Organización de la explotación en maquinas de pivote central eléctricas para el riego del cultivo de la papa

    Directory of Open Access Journals (Sweden)

    Lorenzo E. Camejo B.

    2009-01-01

    Full Text Available Se realizó el trabajo para la organización de la explotación de las máquinas de riego de pivote central Western5 en el cultivo de la papa (solanum tuberosum en la provincia Ciego de Ávila, teniéndose en consideración el tipo de suelo, sus propiedades hidrofísicas, fases de desarrollo del cultivo, exigencias hídricas y regulaciones de la máquina, lo que conlleva a obtener las normas de riego, intervalos de riego y regulaciones para cada fase de desarrollo del cultivo; aplicándose en todas las máquinas de riego de papas en la provincia, capacitando además a todos los operadores y técnicos en la explotación y regulación de la máquina por fases de desarrollo del cultivo. Los resultados obtenidos muestran un considerable ahorro de agua y energía en la campaña de riego, obteniéndose rendimientos entre 28-32 t/ha.

  8. Model of automatic fuel management for the Atucha II nuclear central with the PUMA IV code

    International Nuclear Information System (INIS)

    The Atucha II central is a heavy water power station and natural uranium. For this reason and due to the first floor reactivity excess that have this type of reactors, it is necessary to carry out a continuous fuel management and with the central in power (for the case of Atucha II every 0.7 days approximately). To maintain in operation these centrals and to achieve a good fuels economy, different types of negotiate of fuels that include areas and roads where the fuels displace inside the core are proved; it is necessary to prove the great majority of these managements in long periods in order to corroborate the behavior of the power station and the burnt of extraction of the fuel elements. To carry out this work it is of great help that a program implements the approaches to continue in each replacement, using the roads and areas of each administration type to prove, and this way to obtain as results the one regulations execution in the time and the average burnt of extraction of the fuel elements, being fundamental this last data for the operator company of the power station. To carry out the previous work it is necessary that a physicist with experience in fuel management proves each one of the possible managements, even those that quickly can be discarded if its don't fulfill with the regulatory standards or its possess an average extraction burnt too much low. For this it is of fundamental help that with an automatic model the different administrations are proven and lastly the physicist analyzes the more important cases. The pattern in question not only allows to program different types of roads and areas of fuel management, but rather it also foresees the possibility to disable some of the approaches. (Author)

  9. Central depression in nuclear density and its consequences for the shell structure of superheavy nuclei

    OpenAIRE

    Afanasjev, A. V.; Frauendorf, S.

    2006-01-01

    The influence of the central depression in the density distribution of spherical superheavy nuclei on the shell structure is studied within the relativistic mean field theory. Large depression leads to the shell gaps at the proton Z=120 and neutron N=172 numbers, while flatter density distribution favors N=184 for neutrons and leads to the appearance of a Z=126 shell gap and to the decrease of the size of the Z=120 shell gap. The correlations between the magic shell gaps and the magnitude of ...

  10. Nuclear starburst-driven evolution of the central region in NGC 6764

    CERN Document Server

    Leon, S; Laine, S; Kotilainen, J K; Schinnerer, E; Lee, S -W; Krips, M; Reunanen, J; Scharwächter, J

    2007-01-01

    We study the CO and the radiocontinuum emission in an active galaxy to analyze the interplay between the central activity and the molecular gas. We present new high-resolution observations of the CO(1-0) and CO(2-1) emission lines, and 3.5 cm and 20 cm radio continuum emission in the central region of the LINER/starburst galaxy NGC 6764. The galaxy has an outflow morphology in radio continuum, spatially coincident with the CO and H$\\alpha$ emission, and centered slightly off the radio continuum peak at the LINER nucleus. The total molecular gas mass in the center is about 7x10^8 \\msun, using a CO luminosity to total molecular gas conversion factor that is three times lower than the standard one. CO(1-0) emission is found near the boundaries of the radio continuum emission cone. The outflow has a projected expansion velocity of 25 km/s relative to the systemic velocity of NGC6764. About 4x 10^6 \\msun of molecular gas is detected in the outflow. The approximate location (~1 kpc) of the dynamical inner Lindblad ...

  11. Una perspectiva geoarqueológica para comprender la ocupación humana en la costa central de la provincia de Buenos Aires

    Directory of Open Access Journals (Sweden)

    Verónica Aldazabal

    2004-12-01

    Full Text Available El trabajo plantea los condicionamientos ambientales que sustentan un modelo de colonización humana en la región costera central de la provincia de Buenos Aires a partir del Holoceno medio. Desde el punto de vista geomorfológico, estratigráfico y cronológico se determinó la presencia de líneas de costa con edades entre los 5200 y 2200 AP. Por otro lado, se aportan datos acerca de las características de los suelos, de la vegetación y de posibles recursos para la subsistencia humana a partir de los 5000 AP en la zona comprendida a partir de la cota de 5 m hasta el alcance del nivel marino actual.We outline the environmental conditioning that supports a model of human colonization in the central coastal region of Buenos Aires Province beginning in the middle Holocene. Palaeoshore lines were determined with ages between 5200 and 2200 BP from a geomorphological, stratigraphical and chronological perspective. In addition, data were provided on soil characteristics, vegetation, and possible resources for human subsistence in the area during the past 5000 years, from a height above sea level of 5 m up to the current sea level.

  12. Inspection experience with RA-3 spent nuclear fuel assemblies at CNEA's central storage facility

    International Nuclear Information System (INIS)

    Aluminum-based spent nuclear fuel from Argentina's RA-3 research reactor is to be shipped to the Savannah River Site near Aiken, South Carolina, USA. The spent nuclear fuel contains highly enriched uranium of U.S. origin and is being returned under the US Department of Energy's Foreign Research Reactor/Domestic Research Reactor (FRR/DRR) Receipt Program. An intensive inspection of 207 stored fuel assemblies was conducted to assess shipping cask containment limitations and assembly handling considerations. The inspection was performed with video equipment designed for remote operation, high portability, easy setup and usage. Fuel assemblies were raised from their vertical storage tubes, inspected by remote video, and then returned to their original storage tube or transferred to an alternate location. The inspections were made with three simultaneous video systems, each with dedicated viewing, digital recording, and tele-operated control from a shielded location. All 207 fuel assemblies were safely and successfully inspected in fifteen working days. Total dose to personnel was about one-half of anticipated dose. (author)

  13. Toward fostering the scientific and technological literacy establishment of the 'Central Scientific and Technological Museum-Institute' and nuclear development

    International Nuclear Information System (INIS)

    The public in general does not necessarily have enough knowledge for the reasonable decision making in the application of scientific and technological development even in the ear of the Information Society. However strongly the necessity of the consensus in the scientific policy like nuclear R and D is required, it is impossible to attain the goal, unless the scientific literacy of the general public is. In order to improve it the role of the scientific museum as a social educational facility is very important. In this respect, there still remains vast room to improve in the Japanese museum system and its activities. The concept of the 'Central Scientific and Technological Museum-Institute', which also operates very small-sized reactor for the educational use, is developed in this paper. (author)

  14. Generalized conventional and intelligent supervisory control system for combined cycle generation power plants; Sistema de control supervisorio generalizado convencional e inteligente para centrales de generacion de ciclo combinado

    Energy Technology Data Exchange (ETDEWEB)

    Martinez Morales, Miguel Angel

    2004-12-15

    (conventional or intelligent) is possible to get more power generation than if we use the automatic methods based on feedback MW control. Consequently, the financial benefit due to the MW generated along a period of 2 months, is equivalent to return the investment required if the CCPP would had been repowered. Test also showed that with the fuzzy based SGC is possible to get a 'little more' power generation than if we use the PID based SGC. The development and implementation of the SGC was made in three phases: First Phase: Upgrading of the simulation dynamic mathematical model and implementation in a new software platform based on LabWindows/CVI. Second Phase: Design, implementation and testing of the PID based SGC. Third Phase: Design and implementation and testing of the Intelligent SGC, based in fuzzy logic. [Spanish] El programa de obras de generacion de la Comision Federal de Electricidad (CFE) del ano 2004 al ano 2008 esta caracterizado por el dominio del proceso de ciclo combinado para la expansion de generacion de energia en Mexico [CFE, 2000]. De acuerdo con los datos presentados por esta fuente, el incremento estimado en la capacidad de generacion de potencia electrica es de 12876 MW, de los cuales las centrales de ciclo combinado aportaran 10655 MW, lo que representa el 82.75%. Bajo estas expectativas de expansion de generacion de energia en Mexico, en este trabajo de tesis se desarrollo un sistema de control supervisorio generalizado (CSG) convencional (PID) e inteligente (logica difusa) para una central de generacion de ciclo combinado, el cual permite lograr la operacion optima de la planta a traves del arranque automatico de las unidades generadoras y obtener la maxima cantidad posible de potencia electrica en forma automatica y segura. Para el desarrollo del CSG se implanto un lazo de control por temperatura para el sistema de turbina de gas (TG) y un lazo de control por presion estrangulada para la turbina de vapor (TV). El diseno de estos sistemas

  15. Theoretical study of the central depression of nuclear charge density distribution by electron scattering

    International Nuclear Information System (INIS)

    The charge form factors of elastic electron scattering for isotones with N=20 and N=28 are calculated using the phase-shift analysis method, with corresponding charge density distributions from relativistic mean-field theory. The results show that there are sharp variations at the inner parts of charge distributions with the proton number decreasing. The corresponding charge form factors are divided into two groups because of the unique properties of the s-states wave functions, though the proton numbers change uniformly in two isotonic chains. Meanwhile, the shift regularities of the minima are also discussed, and we give a clear relation between the minima of the charge form factors and the corresponding charge radii. This relation is caused by the diffraction effect of the electron. Under this conclusion, we calculate the charge density distributions and the charge form factors of the A=44 nuclei chain. The results are also useful for studying the central depression in light exotic nuclei. (authors)

  16. The peaceful uses of nuclear energy and national borders in Central Europe

    International Nuclear Information System (INIS)

    The German National Group of AIDN/INLA also invited to its Regensburg meeting representatives from neighbouring states. The main theme of the meeting was the legal problems resulting from transfrontier impacts of the peaceful uses of nuclear energy, and the Chernobyl accident just added topical importance to this subject that already before had been a problem of burning interest. The papers and discussions encompass the whole range of principle legal problems as well as the differing approaches adopted by the various national legal systems and the resulting problems encountered in practice. Solutions already existing - as e.g. on the basis of multi- or bilateral agreements - were summarised, and outline solutions and lines of orientation for future practice were discussed. (orig.)

  17. Key locations for soybean genotype assessment in Central Brazil Locais-chave para avaliação de genótipos de soja na Região Central do Brasil

    Directory of Open Access Journals (Sweden)

    Roberto Miranda Pacheco

    2009-05-01

    Full Text Available The objective of this work was to identify key locations for the establishment of soybean (Glycine max genetic breeding programs, in the Central Region of Brazil. Grain yield data of three maturity groups of soybean genotypes, from regional trials conducted over three years, at 18 locations in Brazilian Cerrado were used. A key location for the early phases of the breeding program was defined as the site that best classifies the winning genotypes in the region. Key locations for the final phases were defined as those sites that best represent each environmental stratum, in relation to the adaptability of the respective winning genotype. This adaptability was estimated by additive main effects and multiplicative interaction (AMMI model analysis, using the distance between the score of each location in a stratum and the score of the winning genotype, which characterizes such stratum in an AMMI biplot. The locations that best classified the winning genotypes over space and time were Mineiros, Placas and Rio Verde. For the final phases of genotype selection, with data from the three maturity group, the recommended locations were: Buritis, Chapadão do Céu, Iraí, Pamplona, Placas, Planaltina, Rio Verde, Sacramento, Senador Canedo, Uberaba, and Uberlândia.O objetivo deste trabalho foi identificar locais-chave para o estabelecimento de programas de melhoramento genético de soja (Glycine max, na Região Central do Brasil. Foram utilizados dados de produtividade de grãos de genótipos de soja, de três ciclos de maturação, obtidos de ensaios regionais conduzidos por três anos em 18 localidades da região. O local-chave para a condução das fases preliminares do programa foi definido como a localidade que melhor classifica os genótipos vencedores na região. Os locais-chave para as fases finais foram definidos como os que melhor representam cada estrato ambiental identificado, em termos da adaptabilidade do respectivo genótipo vencedor. Essa

  18. Volcanic and seismic hazards at a proposed nuclear power site in central Java

    Science.gov (United States)

    McBirney, Alexander R.; Serva, Leonello; Guerra, M.; Connor, Charles B.

    2003-08-01

    A nuclear power plant site has been proposed near the base of Mount Muria, a long-dormant volcano in Indonesia. Over a period of eight years the volcanic and seismic hazards were investigated, first by the contractor and later by a joint team of Indonesian geologists and consultants to the International Atomic Energy Agency. In order to assess the risk posed by a large volcano for which there is no record of historical eruptions, it was necessary to determine the age of the last activity by geological and geochronological means and to deduce from this whether the volcano posed a credible risk. Similarly, because there was no adequate record of seismic activity, the seismic hazards were investigated mainly by geological, geomorphological, and geophysical methods that identified and characterized potential seismogenic sources related to the volcano or tectonic movements (i.e. active/capable faults). Muria Volcano has not erupted since about two thousand years ago, but the last activity was sufficiently recent to rule out any assumption that the volcano is extinct. Detailed studies indicated that the proposed site may be vulnerable to the effects of air-borne tephra, pyroclastic flows and surges, debris flows, lahars, and opening of new vents. A more serious factor, however, was the poor geotechnical properties of the foundation material that required a careful analysis of the seismic hazards. Although the project was suspended, the study proved useful, because it provided an opportunity to develop procedures and techniques that could be applied in similar studies elsewhere.

  19. Evaluación de la peligrosidad sísmica en España para aplicaciones relacionadas con la seguridad nuclear. Resultados preliminares.

    OpenAIRE

    Benito Oterino, Belen; Gaspar Escribano, Jorge M.; Rivas Medina, Alicia; Martínez Díaz, José Jesús; Rodriguez, O.; M.S. Ramírez

    2011-01-01

    En este trabajo se presentan los avances realizados en el marco del proyecto “Evaluación de la Peligrosidad Sísmica en España para aplicaciones relacionadas con la seguridad nuclear” financiado por el Consejo de Seguridad Nuclear. La finalidad última del proyecto es ahondar en el conocimiento de la peligrosidad sísmica y de su incertidumbre en los emplazamientos de instalaciones críticas como instalaciones nucleares y almacenamientos de residuos radiactivos en nuestro país. Con ese prop...

  20. Development of the process of energy transfer from a nuclear Power Plant to an intermediate temperature electrolyse; Desarrollo del proceso de transferencia de energia desde una central nuclear a un electrolizador de temperatura intermedia

    Energy Technology Data Exchange (ETDEWEB)

    Munoz Cervantes, A.; Cuadrado Garcia, P.; Soraino Garcia, J.

    2013-07-01

    Fifty million tons of hydrogen are consumed annually in the world in various industrial processes. Among them, the ammonia production, oil refining and the production of methanol. One of the methods to produce it is the electrolysis of water, oxygen and hydrogen. This process needs electricity and steam which a central nuclear It can be your source; Hence the importance of developing the transfer process energy between the two. The objective of the study is to characterize the process of thermal energy transfer from a nuclear power plant to an electrolyzer of intermediate temperature (ITSE) already defined. The study is limited to the intermediate engineering process, from the central to the cell.

  1. Nuclear fragmentation in central collisions: Ni + Au from 32 to 90 A*MeV

    International Nuclear Information System (INIS)

    Heavy ion collisions are one of tools for studying nuclear system far away from its equilibrium state. This work concerns the most violent collisions in the Ni + Au system for incident energies ranging from 32 up to 90 AMeV. These events were detected with the multidetector INDRA and selected by the Principal Component Analysis (multidimensional analysis). This method classifies the events according their detection features and their degree of dissipation. We observed two deexcitation mechanisms: a fusion/fission - evaporation process and a multifragmentation process. Those two coexist from 32 to 52 AMeV whereas only one subsists at 90 AMeV. For those two mechanisms, an component was observed which seems to be linked to the initial phase of the reaction. The energy fluctuations of this component leads to variations in the energy deposit which determines the deexcitation of the system. The experimental multifragmentation data of the Ni + Au system (52 and 90 AMeV) were compared to the predictions of a statistical model and to the experimental data of the system Xe + Sn at 50 AMeV (also detected with INDRA). These comparisons show the lack of collective radial energy for fragments (Z≥10) in the Ni + Au system, and show that the degree of multifragmentation depends of the thermal excitation energy. Mean kinetic energies of particles and lights fragments (Z≥10) are larger in the Ni + Au system than the Xe + Sn system. This observation shows that these particles are more sensitive to the entrance channel for an asymmetric system than for a symmetric system (for the same number of nucleons). (author)

  2. Genkai Nuclear Power Station Units 1 and 2. Upgrading of central instrumentation equipment

    International Nuclear Information System (INIS)

    Genkai Unit No.1 started commercial operation in October 19754 and Genkai Unit No.2 in March 1981. They are two-loop PWR plants with the electrical power output of 559 MW each. Units No.1 and 2 have been successfully operation and accumulated good results to data. Meanwhile, striving to maintain and enhance reliability, Kyushu Electric Power Company has been systematically implementing upgrade and repair works by reflecting knowledge acquired from nuclear power plant operating experience in Japan and overseas and the outcome of technological developments. The main control boards had been modified several times, as had other equipment before this upgrading project started. Although there was no significant problem in the safe and stable plant operation using the boards as they were, the scalability and maintainability became worse. This would become a problem in future in view of the continuation of safe and stable plant operation for a long time. We thought to enhance the reliability, operability and monitorability further and decided to replace the main control boards with new ones equipped with more CRTs that are the same type as those used in the latest Genkai Units No.3 and 4 located in the same site. And, the related systems, including the primary and secondary system control systems, plant computers, and alarm and monitor cabinets, were replaced with the units featuring the latest technology. Hereafter, this project may be called as CBR in short. The replacement work was implemented by coinciding with the 20th refueling outage (March 6 to August 18, 2001) for Unit No.1 and with the 16th refueling outage (March 16 to September 20, 2001) for Unit No.2. (author)

  3. El pronóstico de la evaporación, para el manejo sostenible de la llanura central de Matanzas

    Directory of Open Access Journals (Sweden)

    Milagros Alfonso Cabrera

    2010-10-01

    Full Text Available El manejo sostenible de los recursos naturales, con participación de las comunidades en la protección del entorno, y en la toma de decisiones en el ámbito local, teniendo en cuenta la necesidad de practicar una economía ecológica para dar solución a los problemas de la alimentación de la población, han sido objetivos centrales de nuestro trabajo, que, como resultado de la investigación proveniente del Proyecto: Agroclimatología de la Radiación solar en la llanura central de Matanzas viene desarrollándose desde enero del 2001; se ha trabajado en el monitoreo de la Radiación Solar, la Precipitación y la Evaporación en toda la zona correspondiente a la llanura, donde luego del análisis estadístico se observó una correlación positiva entre la Radiación solar y el resto de la variables, se define que la regresión asume la mayor variabilidad de la ecuación , y la correlación múltiple de los cuadrados (R2 es elevada, concluyendo que la probabilidad de error del valor del pronóstico es prácticamente nula, todo ello resumido en que es el primer intento en nuestra provincia (no hay antecedentes de ello, de trabajar en el pronóstico de la Revista Avanzada Científica Vol. 9 No. 2 Año 2006 Evaporación mensual, a partir de una ecuación de regresión que permita predecir dicha Evaporación, considerando la Radiación Solar y la Precipitación, para brindarle a los agricultores una sólida herramienta que les permita elevar la eficiencia en el manejo del agua de riego y otras labores agrícolas a partir de los niveles de transpiración de los cultivos y aporte además definiciones precisas sobre la factibilidad de la siembra de cultivos en secano.

  4. Simplified system for the pressure control of a Nucleo electric central of the BWR type; Sistema simplificado para el control de presion de una central Nucleoelectrica del tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez J, J. [FI-UNAM, DEPFI Campus Morelos, Jiutepec, Morelos (Mexico)

    2003-07-01

    One of the main preoccupations of the electric power generator stations is the appropriate operation of the same ones. The operators must be qualified to respond in an adequate way and to be able to take to these power stations to an optimal, sure and stable operation condition under any circumstance. The Laboratory of Analysis in Nuclear Reactors Engineering (LAIRN) of the Engineering Faculty of UNAM (Fl) in collaboration with the International Atomic Energy Agency (IAEA), it develops an interactive classroom simulator in which simulations of the phenomena which take place in a nuclear power station are executed. The classroom simulator bases its operation on specialized nuclear codes feeding interactive graphic unfolding with those that it is possible to make a monitoring, supervision and control of the behavior of the power station under any operation regime, either in normal operation, transitory events or postulated accident sequence. The development of this classroom simulator includes a modular and re configurable structure. Due to it is indispensable to count with a higher inter activity with the system it is included the simulation of the control system of the plant and inside the same, one of those more important it is the reactor pressure control system. The present work describes the conceptual design and the used methodology for the development and implementation in the simulator of a simplified model of the pressure control system for a BWR generic central. The reach of the development will allow to accomplish the necessary tests to demonstrate that this has an adequate performance according to the carried out simplifications. (Author)

  5. Risk factors for central venous catheter-related infections in pediatric intensive care Fatores de risco para as infecções relacionadas ao caracter venoso central em terapia intensiva pediátrica

    Directory of Open Access Journals (Sweden)

    Ricardo Vilela

    2007-01-01

    Full Text Available OBJECTIVES: To identify risk factors for short-term percutaneously inserted central venous catheter-related infections in children and to evaluate the accuracy of a mortality score in predicting the risk of infection. METHOD: After reviewing the charts of patients who developed catheter-related infection in a university hospital's pediatric intensive care unit, we conducted a case-controlled study with 51 pairs. Variables related to patients and to catheter insertion and use were analyzed. Risk factors were defined by logistic regression analysis. The accuracy of the Pediatric Risk of Mortality score to discriminate the risk for infection was tested using the Receiver Operating Characteristic curve. RESULTS: Infection was associated with respiratory failure, patient's length of stay, duration of tracheal intubation, insertion of catheter in the intensive care unit and parenteral nutrition. Insertion site (femoral or internal jugular was unimportant. Multivariate logistic regression analysis identified the following variables. Risk factors included more than one catheter placement (p=0.014 and duration of catheter use (p=0.0013, and protective factors included concomitant antibiotic use (p=0.0005 and an intermittent infusion regimen followed by heparin filling compared to continuous infusion without heparin (p=0.0002. Pediatric Risk of Mortality did not discriminate the risk of infection. CONCLUSIONS: Central parenteral nutrition and central venous catheters should be withdrawn as soon as possible. Femoral vein catheterization carries a risk of infection similar to internal jugular catheterization. The Pediatric Risk of Mortality score should not be used to predict the risk of central catheter-related infections.OBJETIVOS: Identificar fatores de risco para as infecções relacionadas a cateter venoso central de curta permanência, inserido por punção, em crianças e avaliar a eficiência de um escore de mortalidade pediátrica em prever o risco

  6. Política, burocracia e redes sociais: as nomeações para o alto escalão do Banco Central do Brasil

    Directory of Open Access Journals (Sweden)

    Cecília Olivieri

    2007-11-01

    Full Text Available O estudo das nomeações para os cargos de direção do Banco Central do Brasil, pela análise de redes sociais, permite compreender aspectos fundamentais do sistema político-administrativo brasileiro. A escolha dos dirigentes públicos afeta a governabilidade e a governança do país. A troca entre cargos e o apoio parlamentar podem garantir a estabilidade do governo, mas também podem reduzir o controle do Presidente da República sobre a burocracia e sobre a direção das políticas públicas. A análise de redes sociais permite a construção dos critérios de escolha dos dirigentes públicos, revela novos padrões de interface entre Estado e sociedade e ilumina o estudo da accountability entre dirigentes públicos e a burocracia e entre governo e sociedade.

  7. Plan y proyecto territorial en las Comarcas Centrales de Cataluña: Herramientas de ordenación para una nueva escala de ciudad

    Directory of Open Access Journals (Sweden)

    Pablo Elinbaum

    2014-09-01

    Full Text Available La ordenación del territorio catalán se regula mediante un marco legal que disocia el planeamiento urbanístico del regional. No obstante, los responsables del Programa de Planeamiento Territorial de la Generalitat (2003-2010 reformulan la interrelación instrumental entre ambos sistemas legales, apoyándose en un nuevo modelo de referencia para las múltiples escalas territoriales. Mediante el análisis de cuatro planes concurrentes en un mismo territorio (la subregión de las Comarcas Centrales de Cataluña, pretendemos definir la complementariedad proyectual entre los elementos de ordenación de dos niveles de planeamiento. El resultado se sintetiza en dieciocho variables temáticas y de ordenación que determinan la especificidad del proyecto territorial. La articulación proyectual entre ambos niveles de planeamiento permite considerar el territorio regional como una ciudad, al menos como un espacio integrado, aunque con diferentes intensidades de urbanidad.

  8. Propuesta para la recuperación de los machetes Zuazaga de los centrales azucareros con electrodos de acero al cromo.

    Directory of Open Access Journals (Sweden)

    R. Collazo Carceller

    2009-09-01

    Full Text Available El trabajo resume el estudio y análisis desarrollado, para la presentación de una propuesta tecnológica de recuperación de los machetes Zuazaga, en nuestros centrales azucareros. Se determinó la influencia de los parámetros, energía introducida (Hi, número de capas (Nc y ancho del depósito (Ad, en la morfología y el incremento de la resistencia al desgaste abrasivo, utilizando el electrodo de acero al cromo DUR 600. Se realizó una valoración económica de la propuesta tecnológicaThis work, sumarises the study and the analisys developed, to prupose the Zuazaga cut cane thecnology recuperation, in aur sugar mills. The parameters influency was determinated, Heat input (Hi, Number of layers (Nc and the Cord whith (Ad, in the mofology and the abrasive wear resistance increase, using the cromiun steel UTP DUR - 600. The economical calculation of the thecnology was done.

  9. Establishment of the nuclear regulatory framework for the process of decommissioning of nuclear installations in Mexico; Establecimiento del marco regulador nuclear para el proceso de cierre de instalaciones nucleares en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A., E-mail: juan.salmeron@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2015-09-15

    Today has not managed any process of decommissioning of nuclear installations in the country; however because of the importance of the subject and the actions to be taken to long term, the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico, accordance with its objectives is developing a National Nuclear Regulatory Framework and defined requirements to ensure the implementation of appropriate safety standards when such activities are performed. In this regard, the national nuclear regulatory framework for nuclear installations and the particular case of nuclear power reactors is presented, as well as a proposed licensing process for the nuclear power plant of Laguna Verde based on international regulations and origin country regulations of the existing reactors in nuclear facilities in accordance with the license conditions of operation to allow to define and incorporate such regulation. (Author)

  10. Radiation exposure and central nervous system cancers: A case-control study among workers at two nuclear facilities

    International Nuclear Information System (INIS)

    A nested case-control study was conducted among workers employed between 1943 and 1977 at two nuclear facilities to investigate the possible association of primary malignant neoplasms of the central nervous system (CNS) with occupational exposure to ionizing radiation from external and internal sources. Eighty-nine white male and female workers, who according to the information on death certificates dies of primary CNS cancers, were identified as cases. Four matched controls were selected for each case. External radiation exposure data were available from film badge readings for individual workers, whereas radiation dose to lung from internally deposited radionuclides, mainly uranium, was estimated from area and personnel monitoring data and was used in analyses in lieu of the dose to the brain. Matched sets were included in the analyses only if information was available for the case and at least one of the corresponding controls. Thus, the analyses of external radiation included 27 cases and 90 matched controls, and 47 cases and 120 matched controls were analyzed for the effects of radiation from internally deposited uranium. No association was observed between deaths fron CNS cancers and occupational exposure to ionizing radiation from external or internal sources. However, due to the small number of monitored subjects and low doses, a weak association could not be ruled out. 43 refs., 1 fig., 15 tabs

  11. Statistical analysis of the wind around a nuclear power plant; Analisis estadistico del viento alrededor de una central nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Tejeda, A; Alvarez, Oscar; Contreras, A. D.; Jauregui, E. [Universidad Veracruzana, (Mexico)

    1996-12-31

    In order to show an appropriate methodology for the climatic analysis of the wind, some of the recent results in the investigation of the field flow around the Laguna Verde Nuclear Power Station, at Veracruz State (Mexico,) through the angular correlation coefficients and contingency tables among the registered wind directions by a meteorological tower at the levels of 10 and 60 meters high are presented. Finally, by applying an objective analysis of the data some conclusions are obtained in connection with the local winds with the mesoscale systems. [Espanol] Con el objeto de mostrar una metodologia apropiada en el analisis climatico del viento, se presentan algunos resultados recientes en la investigacion del campo de flujo en los alrededores de la central nucleoelectrica de Laguna Verde, Veracruz (Mexico), a traves de los coeficientes de correlacion angulares y de tablas de contingencia entre las direcciones del viento registradas por una torre meteorologica en los niveles de 10 y 60 metros de altura. Finalmente, aplicando analisis objetivo de los datos, se obtienen algunas conclusiones sobre la conexion de los vientos locales con los sistemas de mesoescala.

  12. Metodologías para la localización óptima de centrales de biomasa y minihidráulica como recursos energéticos renovables en la comarca de El Bierzo

    OpenAIRE

    de la Paz Blanco, Carlos

    2012-01-01

    El propósito principal de este trabajo es la localización de zonas óptimas para la instalación de centrales de Biomasa Forestal y Minihidraúlica que puedan generar energía eléctrica y estén conectadas a la red. Para ello se han concebido distintas metodologías basadas fundamentalmente en técnicas de Evaluación Multicriterio (EMC), donde a partir de diferentes datos se obtienen factores y restricciones que afectan a cada una de las Energías Renovables objeto de estudio.

  13. Nuclear security in major public events: the XV Pan American Games and the III Para-Pan American Games in Brazil

    International Nuclear Information System (INIS)

    The organization of a major public event involving large numbers of spectators and participants, presents important security challenges. Taking this into consideration, the Brazilian Nuclear Energy Commission (CNEN) has been requested, by the National Secretary of Public Security/ Ministry of Justice (SENASP/MJ), by the end of 2006, to participate on the security actions to be implemented in both the XV Pan American Games and III Para Pan American Games. The XV Pan American Games 2007 and the III Para Pan American Games were held in Rio de Janeiro, Brazil from 13 to 29 July 2007 and from 12 to 19 August 2007, respectively. Those events had 8700 participants between athletes, coaches and referees from 42 countries. More than 300 competition events were held at 17 different venues and were covered by 4910 professionals from TV, radio and written press. Around 2 million tickets have been sold or distributed and 18,000 volunteers participated on the organization. The participation of CNEN was concentrated on the implementation of specific nuclear and radiological security measures to be applied at those events. This was part of a multi-institutional plan for the security of the Games, coordinated by the National Secretary of Public Security of the Ministry of Justice (SENASP/MJ). The support provided by IAEA under a Cooperation Arrangement with the Brazilian authorities was a key factor for the success of the whole operation. The actions taken and the lessons identified by the Brazilian Nuclear Energy Commission related to nuclear and radiological security for the Pan American Games and for the Para Pan American Games are presented. (author)

  14. Nuclear security in major public events: The XV Pan-American games and the III Para Pan American games in Brazil

    International Nuclear Information System (INIS)

    The organization of a major public event involving large numbers of spectators and participants, presents important security challenges. Taking this into consideration, the Brazilian Nuclear Energy Commission (CNEN) has been requested, by the National Secretary of Public Security/ Ministry of Justice (SENASP/MJ), by the end of 2006, to participate on the security actions to be implemented in both the XV Pan-American Games and III Para Pan American Games. The XV Pan American Games 2007 and the III Para Pan American Games were held in Rio de Janeiro, Brazil from 13 to 29 July 2007 and from 12 to 19 August 2007, respectively. Those events had 8700 participants between athletes, coaches and referees from 42 countries. More than 300 competition events were held at 17 different venues and were covered by 4910 professionals from TV, radio and Mitten press. Around 2 million tickets have been sold or distributed and 18,000 volunteers participated on the organization. The participation of CNEN was concentrated on the implementation of specific nuclear and radiological security measures to be applied at those events. This was part of a multi institutional plan for the security of the Games, coordinated by the National Secretary of Public Security of the Ministry of Justice (SENASP/MJ). The support provided by IAEA under a Cooperation Arrangement with the Brazilian authorities was a key factor for the success of the whole operation. The actions taken and the lessons identified by the Brazilian Nuclear Energy Commission related to nuclear and radiological security for the Pan American Games and for the Para Pan American Games are presented. (author)

  15. Nuclear security in major public events: the XV Pan American Games and the III Para-Pan American Games in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Mello, Luiz A. de; Monteiro Filho, Joselio S.; Belem, Lilia M.J.; Torres, Luiz F.B. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioprotecao e Segurania Nuclear. Coordenacao de Salvaguardas e Protecao Fisica], e-mail: gpf@cnen.gov.br

    2009-07-01

    The organization of a major public event involving large numbers of spectators and participants, presents important security challenges. Taking this into consideration, the Brazilian Nuclear Energy Commission (CNEN) has been requested, by the National Secretary of Public Security/ Ministry of Justice (SENASP/MJ), by the end of 2006, to participate on the security actions to be implemented in both the XV Pan American Games and III Para Pan American Games. The XV Pan American Games 2007 and the III Para Pan American Games were held in Rio de Janeiro, Brazil from 13 to 29 July 2007 and from 12 to 19 August 2007, respectively. Those events had 8700 participants between athletes, coaches and referees from 42 countries. More than 300 competition events were held at 17 different venues and were covered by 4910 professionals from TV, radio and written press. Around 2 million tickets have been sold or distributed and 18,000 volunteers participated on the organization. The participation of CNEN was concentrated on the implementation of specific nuclear and radiological security measures to be applied at those events. This was part of a multi-institutional plan for the security of the Games, coordinated by the National Secretary of Public Security of the Ministry of Justice (SENASP/MJ). The support provided by IAEA under a Cooperation Arrangement with the Brazilian authorities was a key factor for the success of the whole operation. The actions taken and the lessons identified by the Brazilian Nuclear Energy Commission related to nuclear and radiological security for the Pan American Games and for the Para Pan American Games are presented. (author)

  16. Teste de proficiência para medições de radioatividade na medicina nuclear Proficiency test for radioactivity measurements in nuclear medicine

    Directory of Open Access Journals (Sweden)

    Akira Iwahara

    2009-08-01

    Full Text Available OBJETIVO: Avaliar o desempenho dos calibradores de radionuclídeos de 55 serviços de medicina nuclear brasileiros em medição de atividade de radiofármaco contendo 99Tc m. Testes de proficiência foram aplicados em 63 resultados originados do programa de comparação promovido pelo Laboratório Nacional de Metrologia das Radiações Ionizantes do Instituto de Radioproteção e Dosimetria. MATERIAIS E MÉTODOS: O desempenho foi avaliado em relação ao critério de aceitação de ±10% de exatidão exigido pela norma brasileira e também aos critérios estabelecidos pela ISO/IEC Guide 43-1, e classificado como "aceitável" ou "não aceitável". Amostras de 99Tc m usadas nas comparações foram fornecidas por alguns dos participantes e calibradas no Laboratório Nacional de Metrologia das Radiações Ionizantes para determinar o valor de referência da atividade. RESULTADOS: Esta comparação com o 99Tc m mostrou que o desempenho aceitável atendendo à exigência da norma regulatória foi de 82,5%, enquanto pelos critérios estabelecidos pela norma ISO/IEC 43-1 foi de 81,0%. Por outro lado, calibradores de radionuclídeos com detector Geiger-Müller apresentaram desempenho inferior quando comparados com os dotados com câmara de ionização. CONCLU-SÃO: Nesta comparação, a avaliação do desempenho baseada nos critérios da ISO/IEC 43-1, os quais são aplicados a laboratórios analíticos, apesar de serem mais restritivas, foi bastante consistente com o critério de exatidão exigido pela norma nacional.OBJECTIVE: To assess the performance of radionuclide calibrators in 55 Brazilian nuclear medicine services in the measurement of 99Tc m radiopharmaceutical activity. Proficiency tests were applied to data sets with 63 results originated from the comparison program developed by Laboratório Nacional de Metrologia das Radiações Ionizantes of Instituto de Radioproteção e Dosimetria. MATERIALS AND METHODS: The calibrators' performance was

  17. Automatic system of tests for control equipment in combined cycle power stations; Sistema automatico de pruebas para equipos de control en centrales de ciclo combinado

    Energy Technology Data Exchange (ETDEWEB)

    Martinez M, Miguel A; Flores L, Zenon; Delgadillo V, Miguel A; Gutierrez A, Ruben [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2001-07-01

    This article deals on the Automatic System of Tests, denominated PROBADOR, used by the Gerencia de Control e Instrumentation (GCI) of the Instituto de Investigaciones Electricas (IIE)for the accomplishment of dynamic tests in laboratory, to the systems of acquisition and control developed with the electronic line SAC-IIE that are installed in the Thermoelectric Power station of Combined Cycle (CTCC) of Dos Bocas, Veracruz and Gomez Palacio, Durango, Mexico. Also the architecture, the functions that are carried out in the equipment of the System of Acquisition and control (SAC) and in the personal computer (PC) that conforms it are described, as well as the methodology used for the development of the tests. The PC constitutes Interface Man-Machine (IMM) and in the SAC equipment the simulation of the processes is made (by means of the execution of algebraic-differential equations) in the compressor, combustion chamber, gas turbine, heat recuperators, steam turbines and condenser equipment that integrate a CTCC. The equations that are used are based in the thermodynamics, flow dynamics and heat transfer; they become attached to the real process with a margin of error that is estimated in 10%. Finally, the tendencies of the PROBADOR and the technical and economic advantages are described that it has provided for the improvement in the performance of the control systems, before different situations, with no need to have the real process. [Spanish] Este articulo versa sobre el Sistema Automatico de Pruebas, denominado PROBADOR, utilizado por la Gerencia de Control e Instrumentacion (GCI) del Instituto de Investigaciones Electricas para la realizacion de pruebas dinamicas en laboratorio, a los sistemas de adquisicion y control desarrollado con la linea electronica SAC-IIE que estan instalados en las Centrales Termoelectricas de Ciclo Combinado (CTCC) de Dos Bocas, Veracruz y Gomez Palacio, Durango, Mexico. Tambien se describen la arquitectura, las funciones que se llevan

  18. Conflictos socioambientales en torno a la energía nuclear. Perspectivas desde la Investigación para la Paz

    Directory of Open Access Journals (Sweden)

    Luis Sánchez Vázquez

    2011-06-01

    Full Text Available En los últimos años se ha reactivado el debate sobre la energía nuclear. Esta opción hareemergido amparada en la etiqueta de «energía limpia», por la no emisión de gases deefecto invernadero en su proceso productivo. Sin embargo, la incertidumbre sobre lasfases de tratamiento necesarias para administrar con seguridad los residuos, incluyendo,en su caso, el reprocesado del combustible; los problemas ambientales derivados de laminería del uranio; e incluso los riesgos laborales derivados del trabajo con materialfisionables, componen un panorama de situaciones conflictivas de carácter complejoque continúa siendo el principal caballo de batalla de la oposición antinuclear y ecologista.En este artículo se pretenden identificar los distintos conflictos socioambientalesaparejados a la energía nuclear teniendo en cuenta su ciclo de vida completo, con elobjetivo aportar soluciones al debate sobre la problemática ambiental en torno a laenergía nuclear desde la perspectiva de la Investigación para la Paz.

  19. Nuclear magnetic resonance imaging of the central nervous system; A good use of the possibilities. Kernspinresonantie-tomografie van het centrale zenuwstelsel; Een goed gebruik van de mogelijkheden

    Energy Technology Data Exchange (ETDEWEB)

    Knaap, M.S. van der (Rijksuniversiteit Utrecht (Netherlands). Academisch Ziekenhuis); Valk, J. (Vrije Universiteit, Amsterdam (Netherlands). Afdeling Radiodiagnostiek en Neuroradiologie)

    1989-12-09

    In this article a review is given of the use of magnetic resonance imaging for the central nervous system. An example of the screening of the population for multiple scelerosis is given. A good preliminary examination and the supply of relevant information to the person which performs the imaging is necessary. (R.B.). 9 figs.; 4 tabs.

  20. Technological tendencies for the development and implementation of fault tolerant active controls in combined cycle power plants; Tendencias tecnologicas para el desarrollo e implantacion de controles activos tolerantes a fallas en centrales de ciclo combinado

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez P, Marino; Verde R, Cristina [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2006-07-01

    This document proposes a methodology that reunites support tools for the operator of a Combined Cycle Generating Power Station allowing him to identify and to classify gas turbine faults, it also reunites some tools for the generation of action advices in the decision making on the operation maneuvers necessary to counteract the effects caused by faults. We are talking about a system implemented in a power station with the reconfiguration of processes and fault arrangement capacities. For this purpose, the line of exhibition delimits first the existing knowledge on automatic control and operations supervision systems in a CCPP and immediately emphasizes the cracks of the system to let pass to the fault tolerant active control system that will detect faults of the gas and steam turbo-generators of a Combined Cycle Generating Power Plant. [Spanish] El presente documento propone una metodologia que reuna herramientas de ayuda al operador de una Central Generadora de Electricidad de Ciclo Combinado para permitirle la identificacion y clasificacion de fallas en las turbinas de gas, asi como herramientas para la generacion de consejos de accion en la toma de decisiones sobre las maniobras de operacion necesarias para contrarrestar los efectos provocados por fallas. Se trata principalmente de un sistema implantado en una central con las capacidades de re-configuracion de procesos y acomodo de fallas. Para esto, la linea de exposicion delimita primero el conocimiento existente sobre sistemas automaticos de control y supervision de operacion en una CGCC y resalta enseguida las grietas del sistema para darle paso al sistema de control activo tolerante a fallas que detectara fallas de los turbogeneradores de gas y vapor de una Central Generadora de Electricidad de Ciclo Combinado.

  1. Investigation on the environmental radioactivity of the proposed location for Nuclear Power Plant Station in Ujung Watu area, Central Java

    International Nuclear Information System (INIS)

    During the period of November 1981 and March 1983, preliminary investigation of the environmental radioactivity at the proposed location of nuclear power station in Ujung Watu area in Central Java has been carried out. The investigated area covers an area within a radius of 5 km of the proposed location. During this period a total of about 319 environmental samples which consist of soils, grasses, drinking and surface waters, several food-item of agricultural and sea product have been collected. Measurement of exposure and absorbed dose level were also carried out at 52 and 27 locations within the investigated area. Measurement of exposure dose was carried out using scintillation probe detector coupled to rate meter and absorbed dose level was measured using TL-dosemeter. The samples were analysed for the gross - α and β radioactivity, the content of H-3, Cs-137 and Sr-90. Results showed that the radiation level of the area has a range of 4 ± 18 mR/h with an average of about 4.6 x 1.4 mR/h. Absorbed dose showed a value within the range of 4.5 - 6.9 x 10-7 Gy/day with an average value of 6.2 ± 1.2 x 10-7 Gy/day. The value area is within the normal range of natural level. Measurement of fall-out indicated that the integral impact of Cs-137 and Sr-90 from fall-out to this area were about 2.6 MBq/km2 and 1.5 MBg/km2 respectively. However, no Cs-137 and Sr-90 were detected in the samples collected during this study. (author). 9 refs

  2. Masses and scaling relations for nuclear star clusters, and their co-existence with central black holes

    Science.gov (United States)

    Georgiev, Iskren Y.; Böker, Torsten; Leigh, Nathan; Lützgendorf, Nora; Neumayer, Nadine

    2016-04-01

    Galactic nuclei typically host either a nuclear star cluster (NSC, prevalent in galaxies with masses ≲1010 M⊙) or a massive black hole (MBH, common in galaxies with masses ≳1012 M⊙). In the intermediate-mass range, some nuclei host both an NSC and an MBH. In this paper, we explore scaling relations between NSC mass (M_NSC) and host-galaxy total stellar mass (M_{star ,gal}) using a large sample of NSCs in late- and early-type galaxies, including a number of NSCs harbouring an MBH. Such scaling relations reflect the underlying physical mechanisms driving the formation and (co)evolution of these central massive objects. We find ˜1.5σ significant differences between NSCs in late- and early-type galaxies in the slopes and offsets of the relations reff,NSC-M_NSC, reff,NSC-M_{star ,gal} and M_NSC-M_{star ,gal}, in the sense that (i) NSCs in late types are more compact at fixed M_NSC and M_{star ,gal}; and (ii) the M_NSC-M_{star ,gal} relation is shallower for NSCs in late types than in early types, similar to the M_BH-M_{star ,bulge} relation. We discuss these results in the context of the (possibly ongoing) evolution of NSCs, depending on host-galaxy type. For NSCs with an MBH, we illustrate the possible influence of an MBH on its host NSC, by considering the ratio between the radius of the MBH sphere of influence and reff,NSC. NSCs harbouring a sufficiently massive black hole are likely to exhibit surface brightness profile deviating from a typical King profile.

  3. Evaluación de la efectividad y satisfacción del apósito con Gluconato de Clorhexidina 3M™ Tegaderm™ en el cuidado del catéter central tunelizado para hemodiálisis

    Directory of Open Access Journals (Sweden)

    Antonio López González

    2016-03-01

    Full Text Available Introducción: Son múltiples los métodos y materiales utilizados para el manejo del orificio de inserción del catéter venoso central tunelizado para hemodiálisis con el fin de prevenir infecciones asociadas a su uso. El objetivo de este estudio es analizar el uso del Apósito con Gluconato de Clorhexidina 3M™ Tegaderm™ con respeto al Apósito formado por gasa y esparadrapo en la cura del orificio de inserción del catéter tunelizado para hemodiálisis. Material y método: Se ha llevado a cabo un estudio prospectivo durante 32 semanas en el que se han incluido 9 pacientes portadores de catéter venoso central tunelizado. Se han recogido datos referentes al estado del orificio de inserción del catéter, del túnel, de la zonza colindante, aplicabilidad del material, satisfacción del paciente, percepción del profesional y costes. Resultados: No se ha evidenciado diferencias en la eficacia para la prevención de infecciones entre ambos apósitos. En el análisis de satisfacción, se constata una mayor percepción de seguridad con el uso del apósito con clorhexidina además de una reducción de coste de la técnica. Discusión: Basándonos en los costes, satisfacción del paciente y en la percepción del personal de enfermería responsable de la técnica, el Apósito con Gluconato de Clorhexidina es una buena alternativa para el cuidado del orificio de inserción del catéter tunelizado para hemodiálisis.

  4. Optimization of the availability and safety relationship of nuclear propulsion installations for military vessels; Otimizacao do conjugado disponibilidade versus seguranca das instalacoes propulsoras nucleares para navios militares

    Energy Technology Data Exchange (ETDEWEB)

    Santos Guimaraes, Leonam dos [Centro Tecnologico da Marinha (CTMSP), Sao Paulo, SP (Brazil)

    1997-12-01

    The relationship between energy generation availability and the safety of the nuclear installation which produces this energy assumes a very especial characteristic when we are dealing with naval propulsion plants. This relationship has no parallel with commercial nuclear power plants. A ship at sea is safety only if he could dispose quickly of the energy produced by his nuclear propulsion plant. This paper presents briefly the main aspects of that relation. 14 refs., 3 figs., 1 tab.

  5. Conflictos socioambientales en torno a la energía nuclear. Perspectivas desde la Investigación para la Paz

    OpenAIRE

    Luis Sánchez Vázquez

    2011-01-01

    En los últimos años se ha reactivado el debate sobre la energía nuclear. Esta opción hareemergido amparada en la etiqueta de «energía limpia», por la no emisión de gases deefecto invernadero en su proceso productivo. Sin embargo, la incertidumbre sobre lasfases de tratamiento necesarias para administrar con seguridad los residuos, incluyendo,en su caso, el reprocesado del combustible; los problemas ambientales derivados de laminería del uranio; e incluso los riesgos laborales derivados del tr...

  6. Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal

    OpenAIRE

    Pedro, Miguel António de Morais

    2012-01-01

    O presente trabalho tem como objectivo avaliar economicamente e determinar a viabilidade da implementação de um reactor nuclear para produção de energia eléctrica. Faz-se uma abordagem a aspectos da energia nuclear no mundo e em particular a energia nuclear na união europeia, faz-se uma análise sobre a estrutura do sector nuclear em Espanha e o futuro da energia no mundo. É realizada uma análise sobre a energia nuclear em Portugal, são abordados aspectos como o planeamento energético, a local...

  7. Central-to-peripheral nuclear modification factors in Pb-Pb collisions at $\\sqrt{s_{NN}}$= 17.3 GeV

    CERN Document Server

    Antinori, F; Badalà, A; Barbera, R; Belogianni, A; Bhasin, A; Bloodworth, Ian J; Bombara, M; Bruno, G; Bull, S A; Caliandro, R; Campbell, M; Carena, W; Carrer, N; Clarke, R F; Dainese, A; De Haas, A P; De Rijke, P C; Di Bari, D; Di Liberto, S; Divià, R; Elia, D; Evans, D; Feofilov, G A; Fini, R A; Ganoti, P; Ghidini, B; Grella, G; Helstrup, H; Hetland, K F; Holme, A K; Jacholkowski, A; Jones, G T; Jovanovic, P; Jusko, A; Kamermans, R; Kinson, J B; Knudson, K; Kolojvari, A A; Kondratiev, V; Králik, I; Kravcakova, A; Kuijer, P; Lenti, V; Lietava, R; Løvhøiden, G; Manzari, V; Martinská, G; Mazzoni, M A; Meddi, F; Michalon, A; Morando, M; Nappi, E; Navach, F; Norman, P I; Palmeri, A; Pappalardo, G S; Pastircák, B; Pisút, J; Pisútová, N; Platt, R J; Posa, F; Quercigh, Emanuele; Riggi, F; Röhrich, D; Romano, G; Safarík, K; Sándor, L; Schillings, E; Segato, G F; Sené, M; Sené, R; Snoeys, W; Soramel, F; Spyropoulou-Stassinaki, M; Staroba, P; Toulina, T A; Turrisi, R; Tveter, T S; Urbán, J; Valiev, F F; Van den Brink, A; Van de Ven, P; Van den Vyvre, P; van Eijndhoven, N; Van Hunen, J J; Vascotto, Alessandro; Vik, T; Villalobos Baillie, O; Vinogradov, L I; Virgili, T; Votruba, M F; Vrláková, J; Závada, P

    2005-01-01

    We present central-to-peripheral nuclear modification factors, R_CP, for the p_T distributions of K^0_S, Lambda, Anti-Lambda, and negatively charged particles, measured at central rapidity in Pb-Pb collisions at top SPS energy. The data cover the 55% most central fraction of the inelastic cross section. The K^0_S and Lambda R_CP(p_T) are similar in shape to those measured at sqrt{s_NN} = 200 GeV at RHIC, though they are larger in absolute value. We have compared our K^0_S R_CP data to a theoretical calculation. The prediction overestimates the data at p_T \\approx 3-4 GeV/c, unless sizeable parton energy loss is included in the calculation.

  8. Simulation technology for training in the management of severe accidents in nuclear power; Tecnologia de simulacion para entrenamiento en gestion de accidentes severos en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gil Moya, E.; Ruiz Martin, J. A.

    2012-07-01

    The objective of the project consists of the development of a module of severe accident based on the code Thermo-hydraulic MAAP and their integration in a Spanish CN training Simulator. Currently, stimulated the tools designed by Tecnatom aimed at training and assistance in the management of emergencies, complemented by the development of a dynamic interactive guides of severe accidents, thus constituting a set of aid for the operation.

  9. Fuel cycle management by the electric enterprises and spanish nuclear Power plants; Gestion del ciclo de combustible por las empresas electricas y centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Celma, E. M.; Gonzalez, C.; Lopez, J. V.; Melara, J.; Lopez, L.; Martinez, J. C.; Culbras, F.; Blanco, J.; Francia, L.

    2015-07-01

    The Nuclear Fuel Group reports to the Technology Committee of the UNESA Nuclear Energy Committee, and is constituted by representatives of both the Spanish Utilities and the Nuclear Power Plants. The Group addresses the nuclear plant common issues in relation to the operation and management of the nuclear fuel in their different stages of the Fuel Cycle. The article reviews the activities developed by the Group in the Front-End, mainly in the monitoring of international programs that define criteria to improve the Fuel Reliability and in the establishment of common bases for the implementation of changes in the regulation applying the nuclear fuel. Concerning the Back-End the Group focuses on those activities of coordination with third parties related to the management of used fuel. (Author)

  10. Engineering and maintenance applied to safety-related valves in nuclear power plants; Ingenieria y mantenimiento aplicado a valvulas relacionadas con la seguridad en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Verdu, M. F.; Perez-Aranda, J.

    2014-04-01

    Nuclear Division in Iberdrola engineering and Construction has a team with extensive experience on engineering and services works related to valves. Also, this team is linked to UNESA as Technical support and Reference Center. Iberdrola engineering and construction experience in nuclear power plants valves, gives effective response to engineering and maintenance works that can be demanded in a nuclear power plant and it requires a high degree of qualification and knowledge both in Operation and Outages. (Author)

  11. El pretensado y su vigilancia en las centrales nucleares españolas : Descripción y análisis histórico de los resultados

    OpenAIRE

    Codinach Fitó, Marc

    2008-01-01

    La utilización del pretensado en las centrales nucleares es un tema singular que difiere de la utilización que se le suele dar a un sistema de armadura activa convencional. En esta tesina se hace un estado del conocimiento de esta tecnología situándolo en el contexto de las centrales nucleares españolas. Además se analizan los datos obtenidos de las vigilancias realizadas hasta hoy en los diferentes edificios de contención de las centrales nucleares españolas y se extraen la...

  12. Computerized system for the support of the predictive maintenance in thermoelectric power stations of Comision Federal de Electricidad; Sistema computarizado para el apoyo del mantenimiento predictivo en centrales termoelectricas de la Comision Federal de Electricidad

    Energy Technology Data Exchange (ETDEWEB)

    Aranda A, Segio; Garcia M, Raul; Poujol G, Francisco; Chairez C, Carlos; Dominguez M, Nely [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2002-07-01

    This paper describes the functionality of the Integral System of Information for the Diagnosis of Predictive Maintenance (SIIDMP) in the thermoelectric centrals, whose primary target is to give support to the personnel related with the maintenance and operation of the thermoelectric central to optimize the application of the inspection, maintenance and its associated costs. It is important to comment that in the generating power stations of Comision Federal de Electricidad (CFE) techniques and methodologies for the preventive and corrective maintenance are applied, in addition of which they count on electronic equipment of operation dedicated to the inspection and control of vibratory equipment. The architecture of the SIIDMP is of the client-server type and for its design and implantation Windows NT 4.0 was used as operating system, SQL Server 7.0 as server and manager of the database, Visual C++ for the programs of data mining, Vision Basic 6.0 for the codification of the application programs and Interface Man-Machine (IMM), the communication mechanism Open Data Base Connectivity (ODBC) to establish the connection with the different data sources, as well as libraries of symbols and graphs that were included in the interface of the user. The main objective of the SIIDMP is to take care of the own necessities on optimization, improvements and savings in the operation of the power stations. With systems like the SIIDMP, a reduction of the costs due to shutdowns by accidental failures of the main equipment is looked for, limiting the deterioration of the equipment, as well as to provide knowledge and aid to all the personnel who take part in the management of the operation and conservation of the facilities of the power station. [Spanish] Se describe la funcionalidad del Sistema Integral de Informacion para el Diagnostico de Mantenimiento Predictivo en las centrales termoelectricas (SIIDMP), cuyo objetivo principal es apoyar al personal relacionado con el

  13. Analysis of the evolution of the collective dose in nuclear power plants in Spain; Analisis de la evolucion de la dosis colectiva en las centrales nucleares de Espana

    Energy Technology Data Exchange (ETDEWEB)

    Ponjuan Reyes, G.; Ruibia Rodiz, M. A. de la; Rosales Calvo, M.; Labarta Mancho, T.; Calavia Gimenez, I.

    2011-07-01

    This article presents an analysis of the evolution of occupational collective dose of the Spanish nuclear power plants during the period 2000 - 2008 within the international context, by the Nuclear Safety Council (CSN) in order to have information contrasted to assessing the extent of application of the ALARA criteria in the Spanish plants and identify areas of priority attention.

  14. The Nuclear Safety Council's Instruction IS-30 on program requirements of fire protection at nuclear power plants; La instruccion IS-30 del consejo de Seguridad Nuclear sobre requisitos del programa de proteccion contraincendios en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Peco, J.

    2015-07-01

    The Nuclear Safety Councils Instrumentation IS-30 is the standard that establishes the fire protection program requirements for the Spanish nuclear power plants with operating license in order to satisfy the two fire protection objectives, which are the adoption of the defense-in-depth principle for fire protection and, by fire area confinement, to ensure that one train of components needed to achieve and maintain the safe shutdown conditions is free of fire damage, and that radioactive liberation is minimized. (Author)

  15. Determination of leveled costs of electric generation for gas plants, coal and nuclear; Determinacion de costos nivelados de generacion electrica para plantas de gas, carbon y nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G.; Palacios H, J.C.; Ramirez S, J.R.; Gomez, A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: galonso@nuclear.inin.mx

    2005-07-01

    The present work analyzes the leveled costs of electric generation for different types of nuclear reactors known as Generation III, these costs are compared with the leveled costs of electric generation of plants with the help of natural gas and coal. In the study several discount rates were used to determine their impact in the initial investment. The obtained results are comparable with similar studies and they show that it has more than enough the base of the leveled cost the nuclear option it is quite competitive in Mexico. Also in this study it is also thinks about the economic viability of a new nuclear power station in Mexico. (Author)

  16. Nuclear parameters determination of the {sup 127}Te {beta} {sup -} decay: a proposal for teaching nuclear physics; Determinacao de parametros nucleares do nucleo de {sup 127}Te: uma proposta para o ensino de fisica nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Batista, Wagner Fonseca

    2011-07-01

    A study of the {sup 127}Te {beta}{sup -} decay was carried out by means of gamma spectroscopy measurements using high resolution HPGe detector, in the region from 30 keV to 1.0 MeV, aiming to get a better understanding of the {sup 127}Te nuclear structure. The radioactive sources of {sup 12}7Te were obtained from the {sup 126}Te(n,{gamma}){sup 1}'2{sup 7}Te nuclear reaction produced in the IEA- R1 nuclear reactor at IPEN/CNEN-SP. Five gamma {sup t}ransitions previously attributed to this decay were confirmed with a better precision than previously. The half-life of {sup 127}Te was also studied resulting in data with lower uncertainty. Using a set of data selected from gamma spectroscopy measurements was developed and applied a didactic proposal for high school students using the Excel software. (author)

  17. Training simulators for power plant operation based in multimedia, intelligent tutorials and virtual reality; Simuladores para entrenamiento en la operacion de centrales basados en multimedia, tutores inteligentes y realidad virtual

    Energy Technology Data Exchange (ETDEWEB)

    Rossano Roman, Miguel; Tavira Mondragon, Jose A.; Romero Jimenez, Guillermo; Buenabad Arias, Maria de los Angeles [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1997-12-31

    The possibility of utilizing simulators to support the fossil fuel power plants operation personnel training, is analyzed. These simulators can be based in multimedia, intelligent tutorials and virtual reality. The software and hardware advances of these technologies are analyzed and it is concluded that the simulators development for operators training supported in the fore mentioned technologies represents a new alternative for the instruction of personnel of this type of power stations that has to be analyzed and evaluated, since one of the disadvantages of this type of technologies is the equipment and software investment cost [Espanol] Se analiza la posibilidad de utilizar simuladores para ayudar al entrenamiento del personal en la operacion de centrales termoelectricas, dichos simuladores pueden estar basados en multimedia, tutores inteligentes y realidad virtual. Se describen los avances en software y hardware de estas tecnologias y se concluye en que el desarrollo de simuladores para el entrenamiento de operadores apoyados con las tecnologias antes mencionadas representa una nueva alternativa para la instruccion del personal de este tipo de centrales, que hay que analizar y evaluar, ya que una de las desventajas de este tipo de tecnologias es el costo de inversion en equipo y software

  18. Evaluation of fatigue damage in nuclear power plants: evolution and new tools of analysis; Evaluacion del dano a fatiga en centrales nucleares: evolucion y nuevas herramientas de analisis

    Energy Technology Data Exchange (ETDEWEB)

    Cicero, R.; Corchon, F.

    2011-07-01

    This paper presents new fatigue mechanisms requiring analysis, tools developed for evaluation and the latest trends and studies that are currently working in the nuclear field, and allow proper management referring facilities the said degradation mechanism.

  19. Law no. 111/1996 on the safe deployment of nuclear activities - A law central to the Romanian nuclear law system

    International Nuclear Information System (INIS)

    Law no. 111/1996 on the safe deployment of nuclear activities was published in its original form in the Official Gazette of Romania, Part no. 267 of 29th October 1996. The complexity of this law prevents from performing a comprehensive analysis of the legal provisions thereof for which reason the author shall review only those aspects he consider to be relevant to the issues dealt with by this law. Furthermore, as the author intends his undertaking to be a comparative analysis of Law no. 111/1996 in its successive stages - from its issue till the present - he uses mostly the present tense even though the law has been amended and in some respects the changes are quite significant. The presentation contains the following three sections: 1. Passing of Law no. 111/1996 on the safe deployment of nuclear activities - a turning point in the development of the Romanian nuclear law; 2. The successive modifications of Law no. 111/1996 on safe deployment of nuclear activities; 3. Law no. 193/2003 for the modification and completion of Law no. 111/1996 on the safe deployment of nuclear activities - a key moment in the modernization of Romanian nuclear law and harmonization with the relevant international requirement. In conclusion, the issue of Law no. 111/1996 on safe deployment of nuclear activities represents a turning point in the development of Romanian nuclear law. From this moment on one may regard it as a modern area of the Romanian law, European in spirit. The pre-existent legal framework - namely the Law no. 61/1974 on the deployment of activities in the Romanian nuclear field - was no longer up to the existing standards and its replacement by a new, modern law, fully harmonized with the European and NATO accession requirements was a must. Such a new, European law was to fully guarantee the safe deployment of nuclear activities for exclusively peaceful purposes, so that the requirements regarding the nuclear safety, protection of professionally exposed personnel

  20. Aplicativo para dosimetria interna usando a distribuição biocinética de fótons baseada em imagens de medicina nuclear

    Directory of Open Access Journals (Sweden)

    Viriato Leal Neto

    2014-10-01

    Full Text Available Objetivo: Este artigo apresenta uma forma de se obterem estimativas de dose em pacientes submetidos a tratamentos radioterápicos a partir da análise das regiões de interesse em imagens de medicina nuclear. Materiais e Métodos: Foi desenvolvido o software denominado DoRadIo (Dosimetria das Radiações Ionizantes, que recebe as informações sobre os órgãos fontes e o órgão alvo e retorna resultados gráficos e numéricos. As imagens de medicina nuclear utilizadas foram obtidas de catálogos disponibilizados por físicos médicos. Nas simulações utilizaram-se modelos computacionais de exposição constituídos por fantomas de voxels acoplados ao código Monte Carlo EGSnrc. O software foi desenvolvido no Microsoft Visual Studio 2010 com o modelo de projeto Windows Presentation Foundation e a linguagem de programação C#. Resultados: Da aplicação das ferramentas foram obtidos: o arquivo para otimização das simulações Monte Carlo utilizando o EGSnrc, a organização e compactação dos resultados dosimétricos com todas as fontes, a seleção das regiões de interesse, a contagem da intensidade dos tons de cinza nas regiões de interesse, o arquivo das fontes ponderadas e, finalmente, todos os resultados gráficos e numéricos. Conclusão: A interface de usuários pode ser adaptada para uso em clínicas de medicina nuclear como ferramenta computacional auxiliar na estimativa da atividade administrada.

  1. Fifth research coordination meeting on the measurement and evaluation of transactinium isotope nuclear data. Central Bureau for Nuclear Measurements, Geel, Belgium, 1-3 September 1982

    International Nuclear Information System (INIS)

    Proceedings of the fifth meeting of the participants in the IAEA Coordinated Research Programme to measure and evaluate the required nuclear decay data of heavy element radionuclides, convened by the IAEA Nuclear Data Section on 1-3 September 1982 at CBNM, Geel, Belgium. The meeting participants reviewed the data requirements, updated and extended the recommended list of half-lives, and continued to review the status of alpha and gamma radiation spectra emitted in the decay of transactinium isotopes. (author)

  2. IGALL, key factor in long-term operation of nuclear power plants; IGALL, factor clae en la operacion a largo plazo de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Calatayud, M. A.; Sainero, J.

    2014-10-01

    The ageing management is a key factor during the Long Term Operation of Nuclear Power Plants and also during the licensed period; IGALL is an international accepted reference guide that shows how the manage it. The knowledge of the reasons to develop this project, how the results have been reached and the public access to them for future use of the Nuclear Power Plants, are the purpose of this article. (Author)

  3. Experience with a mobile data storage device for transfer of studies from the critical care unit to a central nuclear medicine computer

    International Nuclear Information System (INIS)

    The introduction of mobile scintillation cameras has enabled the more immediate provision of nuclear medicine services in areas remote from the central nuclear medicine laboratory. Since a large number of such studies involve the use of a computer for data analysis, the concurrent problem of how to transmit those data to the computer becomes critical. A device is described using hard magnetic discs as the recording media and which can be wheeled from the patient's bedside to the central computer for playback. Some initial design problems, primarily associated with the critical timing which is necessary for the collection of gated studies, were overcome and the unit has been in service for the past two years. The major limitations are the relatively small capacity of the discs and the fact that the data are recorded in list mode. These constraints result in studies having poor statistical validity. The slow turn-around time, which results from the necessity to transport the system to the department and replay the study into the computer before analysis can begin, is also of particular concern. The use of this unit has clearly demonstrated the very important role that nuclear medicine can play in the care of the critically ill patient. The introduction of a complete acquisition and analysis unit is planned so that prompt diagnostic decisions can be made available within the intensive care unit. (author)

  4. Final results of the cadmium and spectral ratios obtained inside of the fuel rod positioned in the central position of the IPEN/MB-01 nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bitelli, Ulysses d' Utra; Mura, Luiz Ernesto C.; Santos, Diogo Feliciano dos, E-mail: ubitelli@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Lambiasi, Beatriz G.N. [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)

    2015-07-01

    The spectral ratios are very important to determine some nuclear reactors parameters such as reaction rates, fuel lifetime, etc and some safety operational conditions. This study aims to determine the spectral ratios in 2 (two) spatial positions located inside the core of the Nuclear Reactor IPEN/MB-01. These places are at the central position of the nuclear reactor core in an asymptotic neutron flux region. The experiment consists in inserting different activation foil detectors inside an experimental fuel rod. The experimental rod is assembled at the central position of the reactor core. Activation neutron foil detectors of different elements such as {sup 197}Au, {sup 238}U, {sup 45}Sc, {sup 58}Ni, {sup 24}Mg, {sup 47}Ti and {sup 115m}In were used to cover a large range of neutron spectrum. Saturation activity per target nucleus was obtained by gamma spectrometry using a HPGe system. The experimental cadmium ratios compared with values computed by MCNP-4C code show good agreement. (author)

  5. Germany: of the nuclear energy expansion to the structure for their gradual abandonment; Alemania: de la expansion de la energia nuclear a la estructura para su abandono gradual

    Energy Technology Data Exchange (ETDEWEB)

    Mez, L. [Frei Universitat Berlin, Environmental Policy Research Centre, Thielallee 47, 14195 Berlin (Germany)

    2009-07-01

    This work exposes a panorama of the German nuclear industry, where the investment in this sector began around the fifty, having great peak during the period 1968 at 1989. Causes like a poor electricity demand, the over capacity and a persistent controversy among the public opinion for the nuclear energy use, stop the expansion from this industry to the little time of established. In contrast with the legal situation in most of the countries, in Germany the operation licences were granted without it limits of time. Nevertheless, the operation expectation was estimated inside a range of 20 to 40 years, depending in particular on the service life of the renovation parts. Taking into account these data, seven nuclear power plants of those that have already operated for 20 years or more, are about to confront expensive reconstructions or the closing in the following five years; while other seven will be closed in the subsequent 10 or 15 years. While the federal politicians and their directive went favorable until recent time in general to the extended use of nuclear energy, some authorities of the states became more restrictive when interpreting the allowed forecasts, what has generated continuous differences and regulatory uncertainty. In consequence, the facilities in operation gradually have shown interest in reaching agreements with the government about the nuclear politics, by means of the regulations reestablishment and one calculus linked at the costs. In spite of the many and constant judgments of the public opinion, the federal nuclear politics was up to 1998 on the side of the alliance pro nuclear and back to the industry by means of multiple fiscal and regulatory privileges. This official position was reverted by first time after the federal elections of that year, when a new red-green federal government announcement the gradual retirement of the nuclear energy of Germany. That coalition pact among the Democratic Social parties (red) and green

  6. Cardiac tamponade in an infant during contrast infusion through central venous catheter for chest computed tomography; Tamponamento cardiaco durante infusao de contraste em acesso venoso central para realizacao de tomografia computadorizada do torax em lactente

    Energy Technology Data Exchange (ETDEWEB)

    Daud, Danilo Felix; Campos, Marcos Menezes Freitas de; Fleury Neto, Augusto de Padua [Hospital Geral de Palmas, TO (Brazil)

    2013-11-15

    Complications from central venous catheterization include infectious conditions, pneumothorax, hemothorax and venous thrombosis. Pericardial effusion with cardiac tamponade hardly occurs, and in infants is generally caused by umbilical catheterization. The authors describe the case of cardiac tamponade occurred in an infant during chest computed tomography with contrast infusion through a central venous catheter inserted into the right internal jugular vein. (author)

  7. Sobrevivência e crescimento inicial em campo de espécies florestais nativas do Brasil Central indicadas para sistemas silvipastoris Survival and initial growing of native tree seedlings in pastures of Central Brazil

    Directory of Open Access Journals (Sweden)

    Alex Melotto

    2009-06-01

    Full Text Available Objetivou-se, neste estudo, avaliar o índice de sobrevivência e o crescimento inicial de 11 espécies arbóreas nativas do Brasil central, plantadas diretamente em pastagem de Brachiaria brizantha cv. Marandu, em Campo Grande, MS. O solo foi classificado como Latossolo Vermelho, argiloso e distrófico, onde foi implantado um arboreto com 16 parcelas compostas, cada uma, por um indivíduo das 11 espécies selecionadas, em blocos casualizados (DBC com quatro repetições. Os espaçamentos em campo foram de 10,0 x 4,0 m. Houve diferenças (P=0,05 entre as médias de sobrevivência das espécies estudadas, indicando influência do estágio sucessional da espécie. Os maiores índices foram de ocorrência nas seguintes espécies: ipê (Tabebuia impetiginosa, caroba (Jacaranda decurrens e da aroeira (Myracrodruon urundeuva. As mais altas taxas de crescimento relativo nos 12 meses avaliados foram alcançadas por chico-magro (Guazuma ulmifolia, caroba (J. cuspidifolia e canafístula (Peltophorum dubium. Houve diferença estatística (P=0,05 entre o crescimento das espécies de estágios sucessionais iniciais (pioneiras e as de estádios tardios, e tais diferenças acentuaram-se com a idade e com a estação chuvosa. Três espécies que obtiveram as melhores combinações dos acréscimos em altura, diâmetro do colo e sobrevivência foram aptas para o cultivo em pastagens na região dos Cerrados: chico-magro (G. ulmifolia, caroba (J. cuspidifolias e canafístula (P. dubium, sendo todas três de estágios sucessionais iniciais.This work aimed to evaluate the rate of survival and the initial development of eleven native tree species established in existing pastures of Brachiaria brizantha at the Beef Cattle Center (Campo Grande, MS. The soil is a dystrophic clay Dark- Red Latosoil. The seedlings were planted in 16 rows, with 10 m between rows and 4 m between plants in a row. It was used a completely randomized design with four replicates. Each row

  8. Nuclear

    International Nuclear Information System (INIS)

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  9. Safety doctrine synthesis for nuclear submarines construction and operation; Sintese de doutrina de seguranca para projeto e operacao de submarinos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Leonam dos Santos; Veiga, Jorge Pinheiro da Costa [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil). E-mail: leosg@uol.com.br; Brinati, Hernani Luiz [Sao Paulo Univ., SP (Brazil). Escola Politecnica. Dept. de Engenharia Naval

    2000-07-01

    The paper consists in an abstract of the thesis with the same title. This thesis intended to organize and to systematize a Global Safety Doctrine applicable to future national Nuclear Attack Submarines (SSN) considering both nuclear and naval aspects. This doctrine has the form of a set of basic principles, general criteria, specific requirements, design verification process procedures for construction and operation inspection, aiming the assurance of a high level of safety pattern to these warships. Consequently the doctrine would form a consistent and coherent basis for Nuclear Safety Authority (NSA) evaluate the social acceptability of SSN life cycle risks, considering the proposed Safety Objectives, in order to contribute to its competent decisions on submarine licensing. (author)

  10. Genetic algorithm with fuzzy clustering for optimization of nuclear reactor problems; Um algoritmo genetico com clusterizacao nebulosa para a otimizacao de problemas de reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Machado, Marcelo Dornellas; Sacco, Wagner Figueiredo; Schirru, Roberto [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear

    2000-07-01

    Genetic Algorithms (GAs) are biologically motivated adaptive systems which have been used, with good results, in function optimization. However, traditional GAs rapidly push an artificial population toward convergence. That is, all individuals in the population soon become nearly identical. Niching Methods allow genetic algorithms to maintain a population of diverse individuals. GAs that incorporate these methods are capable of locating multiple, optimal solutions within a single population. The purpose of this study is to introduce a new niching technique based on the fuzzy clustering method FCM, bearing in mind its eventual application in nuclear reactor related problems, specially the nuclear reactor core reload one, which has multiple solutions. tests are performed using widely known test functions and their results show that the new method is quite promising, specially to a future application in real world problems like the nuclear reactor core reload. (author)

  11. Physical start up of the Dalat nuclear research reactor with the core configuration having a central neutron trap

    International Nuclear Information System (INIS)

    After the reactor has reached physical criticality with the core configuration exempt from central neutron trap on 1 November 1983, the core configuration with a central neutron trap has been arranged in the reactor and the reactor has reached physical criticality with this core configuration at 17h48 on 18 December 1983. The integral worths of different control rods are determined with accuracy. 2 refs., 24 figs., 18 tabs

  12. Actinides inventory of the nuclear power plant of Laguna Verde Unit 1; Inventario de actinidos de la Central Nuclear Laguna Verde Unidad 1

    Energy Technology Data Exchange (ETDEWEB)

    Martinez C, E.; Ramirez S, J. R. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Alonso V, G., E-mail: eduardo.martinez@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U. P. Adolfo Lopez Mateos, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico)

    2013-10-15

    At the present time 435 nuclear power reactors exist for the electricity generation operating in the world and 63 in construction. Mexico has two reactors type BWR in the nuclear power plant of Laguna Verde. The nuclear fuel that is used in the nuclear reactors is retired of the reactor core when the energy that this contained has been extracted. This used fuel is known as spent nuclear fuel, the problem with this fuel is that was irradiated inside the reactor and continuous emitting a high radiation, as well as a significant heat quantity when being extracted, for what is necessary to maintain it in cooling and with some shielding to be protected of the radiation that emits. This objective is achieved confining the fuel in the spent nuclear fuel pool, where it is cooled and the same pool provides the necessary shielding to maintain the surroundings in safety radiation levels for the personnel that work in the power plant. An inconvenience of the pools is its limited storage capacity and that after certain time is necessary to remove the fuel, according to the established regulation to continue operating. To correct this inconvenience, two alternatives of spent fuel disposition exist, 1) the final disposition in deep geologic repositories and 2) the reprocessing and recycled of spent fuel. Each alternative presents its particularities and specific problems; however taking many years to be able to implement anyone of them. To carry out the second option, is indispensable to estimate the total mass of actinides generated in the spent nuclear fuel, that which represents to develop a methodology for it, this action is the main purpose of the present work. Inside our calculation method was necessary to appeal to diverse computation tools as the codes Origin-S and Keno V.a. Later on the obtained were compared with a problem type Benchmark, being obtained a smaller absolute error to 1.0%. (Author)

  13. Evaluación de la validez del modelo constitutivo Drucker Prager Extendido para la simulación de la respuesta mecánica de un Vertisol de la región central de Cuba

    OpenAIRE

    Alain Ariel de la Rosa Andino; Miguel Herrera Suárez; Omar González Cueto; Lázaro Ventura Benítez Leyva; Inhaudis Calzada Pompa; Laura García Pedraza

    2013-01-01

    El presente trabajo se efectúa con el objetivo de evaluar el modelo constitutivo Drucker Prager Extendido para la simulación de la respuesta mecánica de un Vertisol de la región central de Cuba a través del método de elementos finitos. Para la simulación de la respuesta mecánica del suelo en estudio se emplea el software ABAQUS/CAE 6.8.1 como herramienta computacional. La simulación comprendió: la descripción del problema a simular, definición del modelo virtual, definición de las propiedades...

  14. On line chemical analyzers for high purity steam and water, applied to steam power plants; Analizadores quimicos en linea para agua y vapor de alta pureza, aplicados a centrales termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Diaz Perez, Ruth [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1989-12-31

    This article presents a general overview of the advances in the subject of on line analyzers of chemical parameters for high purity water and steam and specifies which ones are commercially available. Also are mentioned besides, the criteria nowadays applied for the selection of the sites for sample grabbing and the analysis that is necessary to perform in each point, depending on the power plant type and the treatment administered (phosphates-Ph coordinated or AVT treatment). [Espanol] El articulo presenta un panorama general de los avances que en materia de analizadores de parametros quimicos en linea para agua y vapor de alta pureza, y especifica cuales estan disponibles en forma comercial. Se citan, ademas los criterios que se aplican actualmente para seleccionar los puntos de toma de muestra y los analisis que es necesario efectuar en cada punto, dependiendo del tipo de central y del tratamiento que se le administre (fosfatos-pH coordinado o tratamiento AVT).

  15. A Validation Process for the Groundwater Flow and Transport Model of the Faultless Nuclear Test at Central Nevada Test Area

    Energy Technology Data Exchange (ETDEWEB)

    Ahmed Hassan

    2003-01-01

    Many sites of groundwater contamination rely heavily on complex numerical models of flow and transport to develop closure plans. This has created a need for tools and approaches that can be used to build confidence in model predictions and make it apparent to regulators, policy makers, and the public that these models are sufficient for decision making. This confidence building is a long-term iterative process and it is this process that should be termed ''model validation.'' Model validation is a process not an end result. That is, the process of model validation cannot always assure acceptable prediction or quality of the model. Rather, it provides safeguard against faulty models or inadequately developed and tested models. Therefore, development of a systematic approach for evaluating and validating subsurface predictive models and guiding field activities for data collection and long-term monitoring is strongly needed. This report presents a review of model validation studies that pertain to groundwater flow and transport modeling. Definitions, literature debates, previously proposed validation strategies, and conferences and symposia that focused on subsurface model validation are reviewed and discussed. The review is general in nature, but the focus of the discussion is on site-specific, predictive groundwater models that are used for making decisions regarding remediation activities and site closure. An attempt is made to compile most of the published studies on groundwater model validation and assemble what has been proposed or used for validating subsurface models. The aim is to provide a reasonable starting point to aid the development of the validation plan for the groundwater flow and transport model of the Faultless nuclear test conducted at the Central Nevada Test Area (CNTA). The review of previous studies on model validation shows that there does not exist a set of specific procedures and tests that can be easily adapted and

  16. Serpent: an alternative for the nuclear fuel cells analysis of a BWR; SERPENT: una alternativa para el analisis de celdas de combustible nuclear de un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Silva A, L.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U.P. Adolfo Lopez Mateos, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Gomez T, A. M., E-mail: lidi.s.albarran@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    In the last ten years the diverse research groups in nuclear engineering of the Universidad Nacional Autonoma de Mexico and Instituto Politecnico Nacional (UNAM, IPN), as of research (Instituto Nacional de Investigaciones Nucleares, ININ) as well as the personnel of the Nuclear Plant Management of the Comision Federal de Electricidad have been using the codes Helios and /or CASMO-4 in the generation of cross sections (X S) of nuclear fuel cells of the cores corresponding to the Units 1 and 2 of the nuclear power plant of Laguna Verde. Both codes belong to the Studsvik-Scandpower Company who receives the payment for the use and their respective maintenance. In recent years, the code Serpent appears among the nuclear community distributed by the OECD/Nea which does not has cost neither in its use neither in its maintenance. The code is based on the Monte Carlo method and makes use of the processing in parallel. In the Escuela Superior de Fisica y Matematicas of the IPN, the personnel has accumulated certain experience in the use of Serpent under the direction of personal of the ININ; of this experience have been obtained for diverse fuel burned, the infinite multiplication factor for three cells of nuclear fuel, without control bar and with control bar for a known thermodynamic state fixed by: a) the fuel temperature (T{sub f}), b) the moderator temperature (T{sub m}) and c) the vacuums fraction (α). Although was not realized any comparison with the X S that the codes Helios and CASMO-4 generate, the results obtained for the infinite multiplication factor show the prospective tendencies with regard to the fuel burned so much in the case in that is not present the control bar like when it is. The results are encouraging and motivate to the study group to continue with the X S generation of a core in order to build the respective library of nuclear data as a following step and this can be used for the codes PARCS, of USA NRC, DYN3D of HZDR, or others developed locally

  17. Production logistic for an attack nuclear submarine squadron fuel; Logistica de producao de combustivel para um esquadrao de submarinos nucleares de ataque

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Leonam dos Santos [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)

    1999-08-01

    The future acquisition of nuclear attack submarines by Brazilian Navy along next century will imply new requirements on Naval Logistic Support System. These needs will impact all the six logistic functions. Among them, fuel supply could be considered as the one which requires the most important capacitating effort, including not only technological development of processes but also the development of a national industrial basis for effective production of nuclear fuel. This paper presents the technical aspects of the processes involved and an annual production dimensioning for an squadron composed by four units. (author)

  18. Europa central

    Directory of Open Access Journals (Sweden)

    Karel BARTOSEK

    2010-02-01

    Full Text Available La investigación francesa continúa interesándose por Europa Central. Desde luego, hay límites a este interés en el ambiente general de mi nueva patria: en la ignorancia, producto del largo desinterés de Francia por este espacio después de la Segunda Guerra Mundial, y en el comportamiento y la reflexión de la clase política y de los medios de comunicación (una anécdota para ilustrar este ambiente: durante la preparación de nuestro coloquio «Refugiados e inmigrantes de Europa Central en el movimiento antifascista y la Resistencia en Francia, 1933-1945», celebrado en París en octubre de 1986, el problema de la definición fue planteado concreta y «prácticamente». ¡Y hubo entonces un historiador eminente, para quién Alemania no formaría parte de Europa Central!.

  19. First Central and Eastern European Workshop on Quality control, patient dosimetry and radiation protection in diagnostic and interventional radiology and nuclear medicine

    International Nuclear Information System (INIS)

    First Central and Eastern European Workshop on Quality Control, Patient Dosimetry and Radiation Protection in Diagnostic and Interventional Radiology and Nuclear Medicine, scientifically supported and accredited as a CPD event for medical physicists by EFOMP, National 'Frederic Joliot-Curie' Research Institute for Radiobiology and Radiohygiene (NRIRR), Budapest, Hungary, April 25-28, 2007. Topics of the meeting included all areas of medical radiation physics except radiation therapy. A unique possibility was realized by inviting four European manufacturers of quality control instrumentation, not only for exhibiting but they also had 45 minutes individual presentations about each manufacturer's product scale and conception. Further sessions dealt with dosimetry, optimization, quality control and testing, radiation protection and standardization, computed tomography and nuclear medicine, in 29 oral presentations and 1 poster of the participants. (S.I.)

  20. Training-related activities for nuclear power plant personnel in the countries of Central and Eastern Europe and the former Soviet Union. Working material

    International Nuclear Information System (INIS)

    A Technical Cooperation Meeting on Training-Related Activities for NPP Personnel in the Countries of Central and Eastern Europe and the Former Soviet Union was held at the IAEA, Vienna. The main objective of the meeting was to identify, through information exchange and discussion, possible TC projects and assistance related to nuclear power plant (NPP) personnel training, which would meet overall coherent national goals and would demonstrate and important impact and relevance for national policy priorities. An array of such projects were identified for each participating country of the CEEC and FSU as were a number of regional cooperation projects. Refs, figs and tabs

  1. A digital method for period measurements in a nuclear reactor; Um metodo digital para medidas de periodo em um reator nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Mundim, Sergio Gorretta

    1971-02-15

    The present paper begins by giving a theoretical treatment for the nuclear reactor period. The conventional method of measuring the period is analysed and some previously developed digital methods are described. The paper criticises the latter, pointing out some deficiencies which the proposed process is able to eliminate. All errors connected with this process are also analysed. The paper presents suitable solutions to reduce them to a minimum. The total error is found to he less than the error presented by the other methods described. A digital period meter is designed with memory resources and an automatic scaler changer. Integrated circuits specifications are used in it. Real time experiments with nuclear reactors were made in order to check te validity of the method. The data acquired were applied to a simulated digital period meter implemented in a general purpose computer. The nuclear part of the work was developed at the 'Comissao Nacional de Energia Nuclear' and the simulation work was dane at the 'Departamento de Calculo Cientifico' of COPPE, which also advised the author in the completion of this thesis. (author)

  2. Rewriting the history: a new future for the nuclear energy in United Kingdom?; Reescribiendo la historia: un nuevo futuro para la energia nuclear en Reino Unido?

    Energy Technology Data Exchange (ETDEWEB)

    Woodman, B. [University of Warwick, Coventry CV4 8UW (United Kingdom)

    2009-07-01

    From ends of the ninety, the new nuclear energy has been rejected three times like an option of viable energy generation for United Kingdom: once during the privatization of the electric supply industry and twice during the subsequent revisions to the energy politicians carried out in 2003. Nevertheless, three years more late, a new debate around the energy politics gave an unusual turning in the industry destination, characterized by the firm consideration in the political calendar about the new reactors development, as well as of governmental politicians guided to impel it. This recent interest arises of restlessness regarding the future security of the supply and to the necessity of reducing the carbon dioxide emissions of United Kingdom. With the purpose of obtaining the sufficient support of civil politicians and investors for the new construction project, the industry will have to devise convincing arguments to prove that it has already solved those problems that it suffered in the past and, also that deserves to receive a special treatment in the liberated market of the electricity. This document synthesizes the structure of the nuclear industry in United Kingdom, some recent historical data and the reasons for those that the new nuclear reactors were not very received in the past. It also indicates the measures that have taken in recent times to modify that perspective. Finally, it analyzes the possible future of the nuclear energy at long term in United Kingdom. (Author)

  3. Permission of change of limits in the vapor generators of the Atucha I Nuclear Central; Permiso de cambio de limites en los GVs de la CNA-I

    Energy Technology Data Exchange (ETDEWEB)

    Ventura, M. [Autoridad Regulatoria Nuclear, Av. Libertador 8250 (1429), Capital Federal (Argentina)]. e-mail: mventura@sede.arn.gov.ar

    2006-07-01

    In the mark of the modification of the Atucha-I Nuclear Central Installation (CNA-I) as consequence of the Introduction of the System 'Second Drain of Heat' (SSC), the Entity Responsible for the CNA-I (NASA) requested authorization to the Nuclear Regulatory Authority (ARN) to modify the value of the minimum level of water in the secondary side in the Steam generators (GVs) to activate the signal 'shoot of the Cut of the Reactor' (RESA-LLV). As the level in the GVs is one of those parameters that are used to shoot the Emergency Feeding System (RX), component of the SSC System, also was analyzed the change in the activation of the shoot signal of the 'Second Drain of Heat' (2SSC-LLV). The ARN uses for the study of the nuclear safety of nuclear power plants, the series of prediction programs RELAP5/MOD3.X. It participates of the evaluation and maintenance activities of these codes through specific agreements with the U.S. Nuclear Regulatory Commission (US-NRC). It is necessary to account with programs of this type since the ARN it licenses the construction and operation of Nuclear Power Plants (NPPs) and other outstanding facilities and it inquires its operation according to its own standards. With these tools its are auditing the calculations that the Responsible Entities of the operation make to guarantee the operability of the NPPs assisting the mentioned standards. The analysis with computational codes is used as a tool to achieve the best understanding in the behavior of the plant in union with the engineering approach, the manual calculations, the data analysis and the experience in the operation of the machine. (Author)

  4. Regulatory activities related with the modification of the frequency of the programmed stoppings of the Argentine nuclear centrals; Actividades regulatorias relacionadas con la modficacion de la frecuencia de las paradas programadas de las centrales nucleares argentinas

    Energy Technology Data Exchange (ETDEWEB)

    Marino, E.; Calvo, J.; Waldman, R.; Navarro, R

    2006-07-01

    The mandatory character documentation of the Argentinean nuclear power stations in Embalse and Atucha I, required the realization of a programmed stoppings every twelve months to execute that settled down in the maintenance and surveillance programs for each installation. Nucleoelectrica Argentina S.A., in it character of Responsible Entity of the operation of these power stations, requested to the Argentinean Nuclear Regulatory Authority, in 2003 and 2005 respectively, the authorization to change the period of the repetitive tests and of the preventive maintenance of the systems related with the safety, to extend them from twelve to eighteen months. The mentioned applications were founded in economic aspects and in inclining to a decrease in the doses of the workers that perform in the activities that are carried out in the programmed stops. The adopted position by the Nuclear Regulatory Authority to decide on these applications was based on the result of diverse evaluations that included the use of the Probabilistic Analysis of Safety specific of each power station, the operative experience resultant of the execution of the preventive maintenance program, and of the results of the repetitive tests and of the inspections in service. The regulatory decisions were different in each case. Indeed, the Embalse nuclear power station was authorized by the Regulatory Authority to modify from twelve to eighteen months the period among the realization of the repetitive tests and of the preventive maintenance, conditioned to the execution of some specific regulatory requirements. On the other hand, the Atucha I nuclear power station was not authorized to modify this period. In this presentation that is detailed the acted by the Nuclear Regulatory Authority in both cases, the used analysis tools, and the foundation of the adopted decisions. (Author)

  5. Adaptabilidade e estabilidade de cultivares registradas de feijão em diferentes épocas de semeadura para a depressão central do Rio Grande do Sul

    OpenAIRE

    Ribeiro Nerinéia Dalfollo; Jost Evandro; Possebon Sandro Borba; Cargnelutti Filho Alberto

    2004-01-01

    O objetivo deste trabalho foi identificar cultivares de feijão com adaptação geral ou específica ao cultivo em diferentes épocas de semeadura e com estabilidade de produção na região da depressão central do Rio Grande do Sul, principalmente, para fins de melhoramento. Os experimentos foram conduzidos no Campus da Universidade Federal de Santa Maria, durante os anos agrícolas 2000/01, 2001/02 e 2002/03, nos cultivos de safra (ambientes favoráveis) e de safrinha (ambientes desfavoráveis). O del...

  6. Seleção de marcas para o varejo de supermercados de pequeno e médio porte em cidades da região central do Paraná

    OpenAIRE

    Syritiuk, Paulo Sergio

    2013-01-01

    Resumo: Nesta tese os estudos foram desenvolvidos considerando a atuação do varejo de supermercados localizados em uma região especifica do Estado do Paraná, denominada geograficamente de região central. Procurou-se analisar os supermercados a partir do porte ou tamanho classificando-os em pequenos, médios e grandes. A partir disso procurou-se estudar a maneira como os responsáveis por compras do mix de produtos selecionam o composto produto/marca que serão disponibilizados para os clientes f...

  7. Avaliação microbiológica e físico-químicas da qualidade da água para o consumo humano na província do planalto central - Huambo - Angola

    OpenAIRE

    Fernandes, Lafayete de Assunção

    2014-01-01

    A água é um dos recursos mais abundante no planeta e essencial a vida, pelo que é imprescindível a sua gestão e qualidade. No entanto a sua utilidade deve ser salvaguardada quer nos aspectos ambientais quer sanitários. O presente estudo teve como objetivo analisar amostras de água para o consumo humano provenientes da cidade do Planalto Central - Huambo, Angola, e associar a qualidade com o meio envolvente. Assim colheram-se duas amostras de água da torneira e do poço e avaliou-se a qualid...

  8. Propuesta para la recuperación de los machetes Zuazaga de los centrales azucareros con electrodos de acero al cromo. // Proposal for Recuperation of Sugar Mill Cut Cane by Using Chromium Steel Electrodes.

    OpenAIRE

    R. Collazo-Carceller; H López-Salinas; A. Días-Romero.

    2009-01-01

    El trabajo resume el estudio y análisis desarrollado, para la presentación de una propuestatecnológica de recuperación de los machetes Zuazaga, en nuestros centrales azucareros. Sedeterminó la influencia de los parámetros, energía introducida (Hi), número de capas (Nc) y anchodel depósito (Ad), en la morfología y el incremento de la resistencia al desgaste abrasivo, utilizandoel electrodo de acero al cromo DUR 600. Se realizó una valoración económica de la propuestatecnológica.Palabras claves...

  9. Avaliação do tipo de curativo utilizado em cateter venoso central para hemodiálise Evaluación del tipo de curativo utilizado en cateter venoso central para hemodiálisis Evaluation of tow types of dressings used on central venous catheters for hemodialysis

    OpenAIRE

    Luciene Fátima Neves Monteiro Barros; Valquíria Grego Arênas; Ana Rita de Cássia Bettencourt; Solange Diccini; Dayana Souza Fram; Angélica Gonçalves Silva Belasco; Dulce Aparecida Barbosa

    2009-01-01

    OBJETIVOS: Avaliar a efetividade de dois tipos de curativos utilizados em cateter venoso central (CVC) em pacientes submetidos à hemodiálise; identificar a taxa de infecção no local de saída e de bacteremia comparando o curativo com gaze e micropore em relação ao filme transparente. MÉTODOS: Foi realizado um ensaio clínico randomizado controlado abrangendo 66 pacientes, sendo 33 nos grupos 1 e 2, respectivamente. No Grupo 1 o curativo utilizado foi gaze e micropore e no Grupo 2 filme transpar...

  10. Ansatz para el estado fundamental de la ecuación de Schröedinger con un campo de fuerzas centrales

    OpenAIRE

    Flego, Silvana; Torroba, Patricia Laura

    2013-01-01

    Recientemente fue propuesto un procedimiento, basado en la conexión existente entre la ecuación de Schrödinger (SE) y la Medida de Información de Fisher (FIM), que permite obtener un ansatz para las autofunciones del estado fundamental de una SE unidimensional, no relativística, cuyo potencial es convexo. La técnica fue utilizada con éxito para tratar modelos que incorporan potenciales convexos simétricos. En esta comunicación exploramos la potencia predictiva de ese formalismo en una situaci...

  11. Perspectives of the central Laguna Verde after Fukushima for the period 2012 at the 2015 in operation and maintenance; Perspectivas de la central Laguna Verde despues de Fukushima para el periodo 2012 al 2015 en operacion y mantenimiento

    Energy Technology Data Exchange (ETDEWEB)

    Rivera C, A., E-mail: arr99999@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Veracruz (Mexico)

    2012-10-15

    The Nuclear Power Plants Management of the Federal Commission of Electricity in Mexico by means an internal analysis confronts the threat to the nuclear industry of the event of Fukushima that affected the public opinion, and the emission of new regulations. This situation demands to improve the results of the operation and maintenance of the nuclear power plant of Laguna Verde, to contribute value with their excellence in the acting to the nuclear option in Mexico. The internal analysis defined with clarity the perspectives based on weaknesses and strengths of the operation (monitoring and control of on-line parameters), and in the maintenance (sustained by the planning), enriched with the external experiences emitted by the institutes INPO and WANO for the nuclear industry, with all this strategic objectives 2012 to 2015 were presented and the initiatives as the extension of the useful life to 20 years more, as well as the focused actions to diminish the threat that the event of Fukushima influenced negatively in the public opinion, by means the diffusion of the good results that can be obtained in the nuclear power plant of Laguna Verde between 2012 and 2015, taking advantage of its modernized power of 810 MW-hour for each generating unit, doing visible that the Project of Extended Power Increase is a generation reality of 120% of the original value, to be able to enter at the excellence levels of the nuclear world. (Author)

  12. Estudio conceptual para la implementación de diverters automáticos en una central a gas de ciclo combinado.

    OpenAIRE

    Hincapié Gómez, Esteban; Sierra Restrepo, Horacio

    2011-01-01

    Se presenta un estudio básico sobre dampers diverters mecánicos y automáticos como punto de apoyo a la posible implementación de dispositivos automáticos en la central Termoeléctrica La Sierra de las Empresas Publicas de Medellín E.S.P. Se describe brevemente el funcionamiento y los componentes de una central a gas de ciclo combinado. Se identifica diferentes tipos de dampers y su papel en las centrales termoeléctricas. Se recopila información sobre diferentes aspectos tanto de los dispositi...

  13. Modernization of the turbo in the Laguna Verde Nuclear Power Plant; Modernizacion del turbogrupo en la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Liebana, B.; Merino, A.; Cobos, A.; Gonzalez, J. J.

    2010-07-01

    The power increase of the Laguna Verde Nuclear Power Plant is a project for the rehabilitation and modernization of the turbo and associated equipment to get an increase of its power and of its service life. The project scope includes the design, the engineering, the equipment supply, the installation, the testing and the commissioning. This paper describes the first phase of the project.

  14. Fukushima, two years later, modification requirements in nuclear power plants; Fukushima, dos anos despues, requerimientos de modificacion en centrales nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez J, J.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Salmeron V, J. A., E-mail: jerson.sanchez@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    The occurred events in the nuclear power plant of Fukushima Daiichi as consequence of the strong earthquake of 9 grades in the Richter scale and the later tsunami with waves estimated in more than 14 meters high began a series of important questions about the safety of the nuclear power plants in operation and of the new designs. Firstly, have allowed to be questioned on the magnitudes and consequences of the extreme external natural events; that can put in risk the integrity of the safety barriers of a nuclear power plant when being presented in a multiple way. As consequence of the events of the Fukushima Daiichi NPP, the countries with NPPs in operation and /or construction carried out evaluations about their safety operation. They have also realized evaluations about accidents and their impact in the safety, analysis and studies too that have forced to the regulatory bodies to continue a systematic and methodical revision of their procedures and regulations, to identify the possible improvements to the safety in response to the events happened in Japan; everything has taken it to determine the necessity to incorporate additional requirements to the nuclear power plants to mitigate events Beyond the Design Base. Due to Mexico has the nuclear power plant of Laguna Verde, with two units of BWR-5 type with contention Mark III, some the modifications can be applicable to these units to administrate and/or to mitigate the consequences of the possible occurrence of an accident Beyond the Design Base and that could generate a severe accident. In this work an exposition is presented on the modification requirements to confront external natural events Beyond the Design Base, and its application in our country. (Author)

  15. The resurgence of nuclear energy. An option for the climatic change and for the emergent countries?; El resurgimiento de la energia nuclear. Una opcion para el cambio climatico y para los paises emergentes?

    Energy Technology Data Exchange (ETDEWEB)

    Campos A, L. [UNAM, Instituto de Investigaciones Economicas, Circuito Mario de la Cueva, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Nieva G, R.; Mulas, P. [Instituto de Investigaciones Electricas, Av. Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico); Velez, C. [Electricite de France, Comite Cientifico Asesor, 22-30 avenue de Wagram, 75382 Paris (France); Ortiz M, J. R. [ININ, Carretera Mexico-Toluca s/n, 52759 Ocoyoacac, Estado de Mexico (Mexico); Thomas, S. [University of Greenwich, 30 Park Row, London SE10 9LS (United Kingdom); Finon, D. [Centre International de Recherche sur l' Environment et le Developpement, CNRS, Campus du Jardin Tropical 45 bis, avenue de la Belle Gabrielle 94736, Nogent-sur-Marne Cedex (France); Woodman, B. [University of Warwick, Coventry CV4 8UW (United Kingdom); Mez, L. [Freie Universitat Berlin, Environmental Policy Research Centre, Thielallee 47, 14195 Berlin (Germany)

    2009-07-01

    The modern society is organized in mistaken form. A tremendous inability of the juridical, political, social and cultural system exists to interrelate the ecosystem (the resources that allow the life and the human activity) with the economic way of production, that is to say with the manner like the human beings appropriate of the nature and they transform it to satisfy the reproduction necessities of the capital and the population. Today we are already paying the consequences of this error. Of continuing with this tendency the next six years, a global increase of five centigrade grades is expected in the temperature, with effects like the increase of the sea level, floods, droughts, among other global problems, for what the gases of greenhouse effect are and they will continue being the main environmental challenge of the X XI century because they not represent alone a threat for the development but also for the humanity survival. The world conscience has wakened up, and in most of the countries where is stopped the construction of new nuclear power plants the plans are reconsidered to return the use of this source, being the two main reasons for reconsideration: the concern for the climatic change and the new world perception about the limits of fossil fuel reserves. The world return of the interest for the nuclear energy, it force to take in consideration the energy politics of Mexico whose structure is too much dependent of hydrocarbons and the import of liquefied natural gas and other energies, subject to the prices volatility and in a frame that lacks long term vision. Here the whole problem of the nuclear industry is exposed, the experiences, the risks, the costs, the future of the energy production for the populations that every time has a bigger consumption, the reader will have, this way, a wide panorama of diverse topics and interests that affect to generation of nuclear energy. (Author)

  16. Analysis of the distribution of radiopharmaceuticals for nuclear medicine in Brazil; Analise da distribuicao de Radiofarmacos para servicos de Medicina Nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Kuahara, Lilian T.; Correa, Eduardo L.; Potiens, Maria P.A., E-mail: lilian547@hotmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    The objective of this study was to analyze the distribution of radiopharmaceuticals produced by Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN), as part of a project to develop a methodology for control and calibration of activimeters used by these Nuclear Medicine Services. This survey was conducted using registry data of registered customers and, with bases in such information, we analyzed the number of clinics all over the country. Considering the distribution of radiopharmaceuticals and what the most used in 2011, there was a total of 365 clinics, and this distribution as follows: Southeast with 56%, South 18%, Northeast 15%, North 4%, and Midwest with 7%. Among the various radioisotopes provided 26 were sold and most in demand are the {sup 67}Ga, {sup 131}I and IPEN-tec (technetium generator)

  17. A hybrid approach to solving the problem of design of nuclear fuel cells; Un enfoque hibrido para la solucion del problema del diseno de celdas de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Montes T, J. L.; Perusquia del C, R.; Ortiz S, J. J.; Castillo, A., E-mail: joseluis.montes@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    An approach to solving the problem of fuel cell design for BWR power reactor is presented. For this purpose the hybridization of a method based in heuristic knowledge rules called S15 and the advantages of a meta-heuristic method is proposed. The synergy of potentialities of both techniques allows finding solutions of more quality. The quality of each solution is obtained through a multi-objective function formed from the main cell parameters that are provided or obtained during the simulation with the CASMO-4 code. To evaluate this alternative of solution nuclear fuel cells of reference of nuclear power plant of Laguna Verde were used. The results show that in a systematic way the results improve when both methods are coupled. As a result of the hybridization process of the mentioned techniques an improvement is achieved in a range of 2% with regard to the achieved results in an independent way by the S15 method. (Author)

  18. Spectrographic determination of metallic impurities in organic coolants for nuclear reactors; Determinacion espectrografica de impurezas metalicas en refrigerantes organicos para reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Martin Munoz, M.; Alvarez Gonzalez, F.

    1969-07-01

    A spectrochemical method for determining metallic impurities in organic coolants for nuclear reactors is given. The organic matter in solid samples is eliminated by controlled distillation and dry ashing in the presence of magnesium oxide as carrier. Liquid, samples are vacuum distillated. The residue is analyzed by carrier distillation and by total burning techniques. The analytical results are discussed and compared with those obtained destroying the organic matter without carrier and using the copper spark technique. (Author) 12 refs.

  19. Regulatory activities related with the modification of the frequency of the programmed stoppings of the Argentine nuclear centrals

    International Nuclear Information System (INIS)

    The mandatory character documentation of the Argentinean nuclear power stations in Embalse and Atucha I, required the realization of a programmed stoppings every twelve months to execute that settled down in the maintenance and surveillance programs for each installation. Nucleoelectrica Argentina S.A., in it character of Responsible Entity of the operation of these power stations, requested to the Argentinean Nuclear Regulatory Authority, in 2003 and 2005 respectively, the authorization to change the period of the repetitive tests and of the preventive maintenance of the systems related with the safety, to extend them from twelve to eighteen months. The mentioned applications were founded in economic aspects and in inclining to a decrease in the doses of the workers that perform in the activities that are carried out in the programmed stops. The adopted position by the Nuclear Regulatory Authority to decide on these applications was based on the result of diverse evaluations that included the use of the Probabilistic Analysis of Safety specific of each power station, the operative experience resultant of the execution of the preventive maintenance program, and of the results of the repetitive tests and of the inspections in service. The regulatory decisions were different in each case. Indeed, the Embalse nuclear power station was authorized by the Regulatory Authority to modify from twelve to eighteen months the period among the realization of the repetitive tests and of the preventive maintenance, conditioned to the execution of some specific regulatory requirements. On the other hand, the Atucha I nuclear power station was not authorized to modify this period. In this presentation that is detailed the acted by the Nuclear Regulatory Authority in both cases, the used analysis tools, and the foundation of the adopted decisions. (Author)

  20. Prevalence of congenital malformations in the vicinity of nuclear plants: data from the Central-East France registry

    International Nuclear Information System (INIS)

    To study the prevalence of malformations around the nuclear power plants in the Rhone-Alps region and compare it with their distribution in other parts of the region monitored by the registry. Methods: Municipalities with fewer than 50,000 inhabitants surrounding the 5 nuclear plants in operation from 1979 through 2002 were studied. Every municipality situated near a nuclear site (n=121) was assigned an exposure index, which we estimated from the distance between the municipality and the plant. A Poisson model and a reference population, defined as the 2154 municipalities in the region situated farther than 10 km from a nuclear plant were used to calculate relative risks for congenital malformations, after adjustment for year of birth, maternal age, district of birth, population density, average family income, and presence of chemical plants subject to E U Seveso regulations. Results: Significant differences were not observed for either gene/chromosome anomalies (p=0.50) or minor malformations (p=0.14). Risks for overall malformations and those defined as major non-syndromic appear to be reduced in areas less than 5 km from nuclear plants (RR=0.75 and RR=0.71, respectively). The only comparison showing a higher rate of malformations in populations living near nuclear sites involved rural communities situated 5 to 10 km from a plant (RR=1.41 for the major non-syndromic malformations and 1.31 for all malformations). Conclusion: These results may be random or may be explained by exposure to the plants, but a more likely explanation is the existence of confounding factors for which we could not adjust, such as road traffic for urban communities and pesticides in rural ones. (author)

  1. Development of a prototype of a Master Central Unit (MCU) for the automation of Distribution Control Centers; Desarrollo de un prototipo de Unidad Central Maestra (UCM) para la automatizacion de Centros de Control de Distribucion

    Energy Technology Data Exchange (ETDEWEB)

    Uribe Blanco, Carlos Eduardo; Mata Almanza, Rafael; Picasso Blanquel, Cuitlahuac [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2011-07-01

    For the purpose of contributing to the strategic plan and to the improvement of productivity and competitiveness levels, the Federal Electric Commission (CFE, Spanish acronym) is making a significant investment in human resources and materials to modernize electric energy supply systems, including monitoring, protection and automatic control for operating all the elements of the electrical process, from generating plants to transmission lines, distribution systems and commercial applications. With this modernization, the CFE is also creating the infrastructure for the interoperability and interconnectivity of the above systems, in such a way to enable it to broaden, continue and complement the functional integration of the linked institutional systems of the latest generation. The total integration of the systems will allow the CFE to move toward Intelligent Electric Networks. Therefore, the CFE requested help from the Electric Research Institute (IIE, Spanish acronym) to develop part of the infrastructure to modernize the automation of distribution. This consists of the development of a prototype of the supervision and control system, using interoperable open technology owned by the CFE which enables using the functions of a SCADA system (Supervisory Control And Data Acquisition) to supervise and control electric distribution networks. [Spanish] Con el proposito de contribuir al plan estrategico y mejoramiento de los niveles de productividad y competitividad, la Comision Federal de Electricidad (CFE) esta invirtiendo fuertemente en recursos humanos y materiales para la modernizacion de los sistemas de suministro de energia electrica, incluyendo el monitoreo, proteccion y control automatico para la operacion de todos los elementos del proceso electrico, desde los centros de generacion hasta las lineas de transmision, los sistemas de distribucion y las aplicaciones de comercializacion. Con dicha modernizacion, la CFE tambien esta generando la infraestructura para la

  2. Rol del fallo mecánico en la optimización del mantenimiento en una central nuclear//Role of the mechanical failure during the maintenance optimization in the nuclear power plant

    OpenAIRE

    Antonio Torres - Valle

    2012-01-01

    Entre las más recientes aplicaciones del Análisis Probabilista de Seguridad (1997 – 2003) de la Central Nuclear Embalse en Argentina, está el Programa de Mantenimiento Orientado a la Seguridad (2006– 2009) el cual se ha desarrollado con el empleo de la metodología de Mantenimiento Centrado en la Confiabilidad (RCM en inglés). El objetivo general del artículo es demostrar la alta contribución de los fallos mecánicos en el diseño de las políticas de mantenimiento de varios sistemas de la instal...

  3. Advances in seismic safety of operating nuclear power plants: IAEA Project Results Seismic-EBP; Avances en la seguridad sismica de centrales nucleares en operacion: Resultados del proyecto OIEA Seismic-EBP

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez juan, A.; Sanchez Cabanero, J. G.; Moreno gonzalez, A.

    2010-07-01

    Records of strong earthquakes occurred in the proximity of facilities in operation have shown that there may be greater than the expected acceleration, the seismic danger that the light of the actual experience can exceed the design basis, and that the aging installations and modifications over its operating life significantly influence seismic response capacity. All this confirms that the earthquake is the external event with the greatest impact on the safety of nuclear installations and the largest contributor (even more than 70%) to the core damage frequency of central probabilistic safety analyzes.

  4. Nuclear and mitochondrial DNA markers in traceability of retail beef samples Marcadores de DNA nuclear e mitocondrial para rastreabilidade da carne bovina comercializada

    Directory of Open Access Journals (Sweden)

    Aline S.M. Cesar

    2010-09-01

    ém de dados da cadeia produtiva. Em geral, a empresa certificadora dispõe das informações do animal que está sendo abatido, porém não tem condições de garantir se houve erro entre abate, desossa, processamento e a distribuição dos produtos. Existe diferenciação no custo e na qualidade dos produtos cárneos, especialmente no mercado internacional, em virtude do sexo e composição racial dos animais. Os marcadores genéticos permitem identificar as características que são controladas num programa de rastreabilidade bovina tais como sexo e composição racial, permitindo identificar e avaliar corretamente para o consumidor, o produto final. A hipótese deste estudo foi que a maioria das amostras de carne bovina vendida no mercado local seria proveniente de fêmeas e com grande participação de raças Zebu. O objetivo deste trabalho foi caracterizar amostras de carne bovina com marcadores de DNA para identificar o sexo e a composição racial. Em dez pontos comerciais da cidade de Pirasssununga, SP, Brasil, foram coletadas 61 amostras e todas foram genotipadas como possuindo DNA mitocondrial Bos taurus e 18 foram positivos para amplificação do cromossomo Y (macho. Para o marcador sat1711b-Msp I a frequência alélica do A foi 0.278 e para o marcador Lhr-Hha I a frequência alélica do T foi 0.417. Os resultados das frequências alélicas do sat1711b-Msp I e Lhr-Hha I apresentaram menor proporção do genoma Bos indicus em relação ao Bos taurus quando comparado ao rebanho Nelore. Com a metodologia descrita neste trabalho foi possível avaliar o sexo e as características de subespécie das amostras de carne bovina, tendo uma importante aplicação para a certificação de produtos cárneos especialmente, em programas de rastreabilidade animal.

  5. Advance: research project on aging electrical wiring in nuclear power plants; Advance: proyecto de investigacion de envejecimiento en cableado electrico en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Cano, J. C.; Ruiz, S.

    2013-07-01

    As Nuclear Power Plants get older it is more important to know the real condition of low voltage, instrumentation, power and control cables. Additionally, as new plants are being built, the election of cables and the use of in-situ monitoring techniques to get reliable aging indicators, can be very useful during the plant life. The goal of this Project is to adapt, optimize and asses Condition Monitoring techniques for Nuclear Power Plants cables. These techniques, together with the appropriate acceptance criteria, would allow specialists to know the state of the cable over its entire length and estimate its residual life. In the Project, accelerated ageing is used in cables installed in European NPPs in order to evaluate different techniques to detect local and global ageing. Results are compared with accepted tests to validate its use for the estimation of cables residual life. This paper describes the main stages of the Project and some results. (Author)

  6. Implementation of the monitoring Plan of the State and behavior of the systems in the Central Nuclear Almaraz; Implantacion del Plan de Seguimiento del Estado y Comportamiento de Sistemas en la Central Nuclear Almaraz

    Energy Technology Data Exchange (ETDEWEB)

    Montero Puertas, I.; Gonzalez Redondo, R.; Lopez Pozo, A.

    2013-07-01

    This work aims to present the implementation process of the Monitoring of the State and behavior of the systems in the Nuclear plan Almaraz. Will define the scope, process, frequencies and criteria of evaluation of the State and behavior of the systems included in the Plan of reliability, as well as the documentary requirements of this evaluation. Cases will also be collected practical real phenomena detected during monitoring degradation made and will explain the actions taken prior to the failure.

  7. Establishment and evolution of Radiological Environmental Monitoring Programmes in nuclear power plants; Establecimiento y evolucion de los programas de vigilancia radiologica ambiental en las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Marugan, I.; Luque, S.; Martin, J. L.; Rey, C.; Salas, R.; Sterling, A.; Ramos, L. M.

    2013-09-01

    This article presents a brief overview of how the Radiological Environmental Monitoring Programmes carried out around nuclear power plants have evolved associated to different reasons as the legal framework, operational phases of the facilities, development on the detection and measurement of low levels of radiation due to the state of art and best available technologies, changes within sites as well as in their surroundings and accident taken place inside and outside of our borders. (Author)

  8. Cleaning chemical and mechanical of heat exchangers in french nuclear plants; Limpieza mecanica y quimica de intercambiadores de calor en centrales nucleares francesas

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz, J. t.; Guerra, P.; Carreres, C.

    2013-03-01

    This project was carried out under the frame of the approval of LAINSA as a supplier of EDF in France. The inspection performed on systems called the moisture separator reheaters (GSS) of CPO series reactor of EDF nuclear power plants has shown evidence of significant clogging due to deposits of magnetite inside the tubes of tube bundle. The pressure drop between inlet and outlet of the heating was close to maximum design criterion. This effect could result in equipment damage and loss of plant productivity. The aim of the work was the design, development, approval and implementation of a procedure for un blocking the tubes of the GSS respecting the integrity of materials and ensuring the harmlessness of cleaning procedures. The procedure used was to completely remove magnetite deposits in order to recover a passage diameter and a surface finish equivalent to the origin, thus avoiding the replacement of the GSS and obtaining a considerable reduction of costs. The achieve these objectives we have developed a procedure that is basically a mechanical pre-cleaning of all tubes of the GSS in order to unblock tem, followed by a chemical cleaning where magnetite is dissolved and crawled out of the tube bundle. The main results were: -Corrosion less than 10 microns. 100-110 Kg of magnetite removed by heat exchanger. -Final pressure drop similar to that of new equipment. -Waste water: 70 m{sup 3} per exchanger, which were managed by an authorized waste management company. This procedure has been applied successfully in 14 GSS type heat exchangers in Fessenheim and Bugey nuclear power plants in France between 2009 and 2011. This project demonstrates that the long experience of LAINSA in the Spanish nuclear industry along with the knowledge and experience in chemical cleaning of SOLARCA, have served to successfully work demanding and mature markets such as the French nuclear market, solving the problem of deposits of magnetite with an effective and safe method for the treated

  9. Public debate about the EPR nuclear power plant at Flamanville; Debat public sur la centrale nucleaire EPR a Flamanville

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The project of building of he EPR reactor at Flamanville (Manche, France) has been submitted to the public debate. This document includes a presentation of the project and of the rules of the public debate, a synthesis of the file made by the prime contractor (EDF), a synthesis of the collective book of national actors concerned by the project (a group of associations for environment protection, Areva company, the ministries of economy and ecology, Global Chance, association of pro-nuclear ecologists (AEPN), 'Sortir du Nucleaire' (out-of nuclear) network, group of scientists for the information about nuclear (GSIEN), association for the promotion of the Flamanville site (Proflam), French nuclear energy society (SFEN) in association with 'Sauvons le Climat' (let's save climate), regional collective association 'EPR non merci, ni ailleurs, ni ici' (EPR, no thanks, neither elsewhere, nor here), NegaWatt), and 5 detailed books of actors: ACRO (association for the control of radioactivity in Western France), CFDT and CGT syndicates, the economic and social council of Basse Normandie region, and Proflam. (J.S.)

  10. Management of fatigue in the Central Nuclear of Cofrentes - implementation of program for calculation of fatigue based on stress

    International Nuclear Information System (INIS)

    This article describes the main features that should have monitoring systems of fatigue to give solid response to requirements associated with long-term operation. The specific examples given throughout the article are drawn from the lessons learned during the implementation of Fat one system Cofrentes Nuclear Power. (Author)

  11. Integrated plant safety assessment: systematic evaluation program. Oyster Creek nuclear generating station. GPU Nuclear Corporation and Jersey Central Power and Light Company. Docket No. 50-219

    International Nuclear Information System (INIS)

    The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Oyster Creek Nuclear Generating Station (located in Ocean County, New Jersey), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  12. Temporary storage in dry of the spent nuclear fuel in the Nuclear Power Plant of Laguna Verde; Almacenamiento temporal en seco del combustible nuclear gastado en la Central Nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, N.; Vargas A, A., E-mail: natividad.hernandez@cfe.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Carretera Veracruz-Medellin Km. 7.5, 94270 Dos Bocas, Veracruz (Mexico)

    2013-10-15

    To guarantee the continuity in the operation of the two nuclear reactors of the nuclear power plant of Laguna Verde (NPP-L V) is an activity of high priority of the Comision Federal de Electricidad (CFE) in Mexico. At the present time, the CFE is working in the storage project in dry of the spent fuel with the purpose of to liberate space of the pools and to have the enlarged capacity of storage of the spent fuel that is discharged of the reactors. This work presents the storage option in dry of the spent fuel, considering that the original capacity of the spent fuel pools of the NPP-L V was of 1242 spaces each one and that in 1991, through a modification of the original design, the storage capacity was increased to 3177 spaces by pool. At present, the cells occupied by unit are of 2165 (68%) for the Unit-I and 1839 (58%) for the Unit-2, however, in 2017 and 2022 the capacity to discharge the complete core will be limited by what is required of a retirement option of spent fuel assemblies to liberate spaces. (author)

  13. Desarrollo de métodos de propagador para el estudio de procesos de ionización molecular empleando la metodología del orbital nuclear molecular y su implementación en el paquete computacional LOWDIN

    OpenAIRE

    Romero Fontalvo, Jhonathan

    2013-01-01

    En este trabajo se propone la teoría de propagadores empleando el método del orbital nuclear molecular para cualquier tipo de partícula (APMO/PT). Esta metodología es una extensión de la teoría del propagador electrónico para estudiar sistemas con más de un tipo de especie cuántica, desarrollada e implementada en su versión diagonal en el programa de química cuántica LOWDIN. La metodología fue aplicada para estudiar efectos cuánticos nucleares en potenciales de ionización electrónicos y energ...

  14. Modelización y validación experimental del transporte de tritio en metal líquido y otros materiales para reactores de fusión nuclear magnética e inercial

    OpenAIRE

    Moral Fernández, Nuria

    2015-01-01

    La presente tesis se centra en el estudio de los fenómenos de transporte de los isótopos de hidrógeno, y más concretamente del tritio, en materiales de interés para los reactores de fusión nuclear. Los futuros reactores de fusión nuclear necesitarán una Planta de Tritio, con una envoltura regeneradora (breeding blanket) y unos sistemas auxiliares claves para su diseño. Por lo tanto su desarrollo y cualificación son cruciales para demostrar que los reactores de fusión son una opción viable com...

  15. Acordos de paz para a América Central nos anos 1980: a busca pela solução negociada 10.5102/uri.v13i1.3088

    Directory of Open Access Journals (Sweden)

    Vanessa Braga Matijascic

    2015-07-01

    Full Text Available As negociações de paz na América Central nos anos 1980 envolveram uma série de iniciativas diplomáticas que contemplaram o Grupo de Contadora e o Grupo de Apoio a Contadora, o grupo de países de Tegucigalpa e, por fim, o desfecho proposto pelas cúpulas centro-americanas. No contexto da política externa de Ronald Reagan foi de extrema importância a iniciativa dos países de Contadora para evitar a primazia da solução proposta pelos Estados Unidos, que era o desfecho da vitória militar perante as guerrilhas nicaraguenses e salvadorenhas. O objetivo deste estudo é possibilitar a compreensão sobre como as iniciativas de Contadora ofereceram outro caminho que, quando acrescidas do escândalo Irã-contras, possibilitou o encaminhamento das cúpulas centro-americanas para o desfecho negociado e pacífico. Para a realização do estudo foi feita revisão bibliográfica e uso de fontes primárias resultantes dos diversos encontros diplomáticos.

  16. Standard model for the safety analysis report of nuclear fuel reprocessing plants; Modelo padrao para relatorio de analise de seguranca de usinas de reprocessamento de combustiveis nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-02-15

    This norm establishes the Standard Model for the Safety Analysis Report of Nuclear Fuel Reprocessing Plants, comprehending the presentation format, the detailing level of the minimum information required by the CNEN for evaluation the requests of Construction License or Operation Authorization, in accordance with the legislation in force. This regulation applies to the following basic reports: Preliminary Safety Analysis Report - PSAR, integrating part of the requirement of Construction License; and Final Safety Analysis Report (FSAR) which is the integrating part of the requirement for Operation Authorization.

  17. Iodine prophylaxis following nuclear accidents - a concept how to distribute potassium-iodide tablets out of the central stocks in the event of an accident

    International Nuclear Information System (INIS)

    With its recommendation ''Iodine prophylaxis following nuclear accidents'' (1996) and its reports of 1997 and 2001 the German Commission on Radiological Protection (SSK) followed the recommendations of the WHO ''Guidelines for iodine prophylaxis following nuclear accidents'' of 1989. The intervention levels were lowered (50 mSv for children/adolescents (up to the age of 18 years) and pregnant women, 250 mSv for adults), the iodine prophylaxis was restricted to persons up to the age of 45 years and the recommended dosage of stable iodine was changed. Due to the lowered reference levels the radius of 25 km around a nuclear power plant that had been the planning radius for the distribution of iodine tablets so far was extended to 100 km. Based on these recommendations the German authorities began to set up new strategies for the provision and distribution of potassium-iodide tablets (iodine tablets). Since 2004, within the radius of 25 km the iodine tablets are pre-distributed to households and/or stored at several points in the municipality for persons up to the age of 45 years. For the new planning radius of 25-100 km iodine tablets are stored in 8 central stocks in Germany for children/adolescents (up to the age of 18 years) and pregnant women. A working group with representatives from federal and Laender authorities has developed a distribution strategy for the distribution out of these central stocks in the event of an accident. It describes a possibility of organising and implementing the distribution of the iodine tablets within the radius of 25-100 km in a nationwide standardised way. (orig.)

  18. Apuntes para la historia de las malformaciones congénitas en terneros de la región central de Cuba - Notes for the history of congenital malformations in calves of the central region of Cuba

    Directory of Open Access Journals (Sweden)

    Rojas Lleonart, Isaías

    2011-01-01

    Full Text Available ResumenSe realizó un estudio retrospectivo sobre los hallazgos de malformaciones congénitas en terneros en la región central de Cuba a partir de los primeros años de la década del 70 hasta nuestros días.SummaryIt was carried out a retrospective study on the discoveries of congenital malformations in calves in the central region of Cuba starting from the first years of the decade of the 70’s until our days.

  19. DTN and international cooperation of the Spanish Nuclear Sector in nuclear technology development processes

    International Nuclear Information System (INIS)

    The Spanish electrical utilities with interests in the Nuclear Sector-IBERDROLA, ENDESA,FUERZAS ELECTRICAS DE CATALU=A5A (FECSA), UNION ELECTRICA FENOSA S.A., COMPA=A5IA SEVILLANA DE ELECTRICIDAD S.A., AND HIDROELECTRICA DEL CANTABRICO S.A.-created on September 26, 1994 the ''Agrupacion Electrica para el Desarrollo Tecnologico Nuclear, A.I.E. (DTN)'' (Electrical Society for Nuclear technology Development A.I.E.) for the purpose of promoting and managing Nuclear Nechnology Development, and integrating and coordinating the efforts of the Nuclear Electrical Sector with industrial companies and other related institutions in spain and abroad. This mission is primarily accomplished by establinhing a common strategy for the Nuclear Electrical Sector in the different areas of responsibility of DTN, centralizing actions by implementing a clear and coherent policy, and ensuring the presence of the entire Electrical Sector in all those fora deemed to be strategic to the Nuclear Sector

  20. A simplified study of public perception in the nuclear field: suggestions for educational campaign for different segments of society; Um estudo simplificado sobre a percepcao publica na area nuclear: sugestoes para campanhas educativas para os diferentes segmentos da sociedade

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Renata Araujo de

    2011-07-01

    During the last years the need for the increase in the electricity energy production as much as in Brazil as in the rest of the world, has raised the tone o the debate about the environmental impacts as a result of these debates, the government and the Non-Governmental Organizations (NGO's) have requested several opinion researches aiming at measuring and evaluating the knowledge and perception of the public in relation to the best non-polluting energy sources. Prior to 2001 these researches would not make any sense in Brazil as the majority of its power grid is made of hydroelectric plants, a renewable energy source. However, when in that year it occurred a drought, the competent authorities have faced the necessity of developing a plan, the National Energy Plan (PNE2030) which recommends, among other objectives, finalizing the construction of the Angra 3 plant and the implementation Df new nuclear plants in places still to be determined. Even considering the complexity of the subject, this paper presents a field research realized from September 28th, 2010 to October 28th, 2010 of the current level of perception of the Brazilian population, specifically the residents of three cities of Rio de Janeiro, about the nuclear area. As a result of this work, it is suggested how the competent authorities should proceed to reach in an efficient manner, by means of communication campaigns both informative and educational, a greater understanding of the population about the proposed subject. (author)

  1. Virtual control desk for operators training: a case study for a nuclear power plant simulator; Mesa de controle virtual para treinamento de operadores: um estudo de caso para um simulador de usina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Aghina, Mauricio Alves da Cunha e

    2009-03-15

    Nuclear Power Plant (NPP) is a facility for electrical energy generation. Because of its high degree of complexity and very rigid norms of security it is extremely necessary that operators are very well trained for the NPP operation. A mistaken operation by a human operator may cause a shutdown of the NPP, incurring in a huge economical damage for the owner and for the population in the case of a electric net black out. To reduce the possibility of a mistaken operation, the NPP usually have a full scope simulator of the plant's control room, which is the physical copy of the original control room. The control of this simulator is a computer program that can generate the equal functioning of the normal one or some scenarios of accidents to train the operators in many abnormal conditions of the plant. A physical copy of the control room has a high cost for its construction, not only of its facilities but also for its physical components. The proposal of this work is to present a project of a virtual simulator with the modeling in 3D stereo of a control room of a given nuclear plant with the same operation functions of the original simulator. This virtual simulator will have a lower cost and serves for pretraining of operators with the intention of making them familiar to the original control room. (author)

  2. Methodology for maintenance analysis based on hydroelectric power stations reliability; Metodologia para realizar analisis de mantenimiento basado en confiabilidad en centrales hidroelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Rea Soto, Rogelio; Calixto Rodriguez, Roberto; Sandoval Valenzuela, Salvador; Velasco Flores, Rocio; Garcia Lizarraga, Maria del Carmen [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2012-07-01

    A methodology to carry out Reliability Centered Maintenance (RCM) studies for hydroelectric power plants is presented. The methodology is an implantation/extension of the guidelines proposed by the Engineering Society for Advanced Mobility Land, Sea and Space in the SAE-JA1012 standard. With the purpose of answering the first five questions, that are set out in that standard, the use of standard ISO14224 is strongly recommended. This approach standardizes failure mechanisms and homogenizes RCM studies with the process of collecting failure and maintenance data. The use of risk matrixes to rank the importance of each failure based on a risk criteria is also proposed. [Spanish] Se presenta una metodologia para realizar estudios de mantenimiento Basado en Confiabilidad (RCM) aplicados a la industria hidroelectrica. La metodologia es una implantacion/ extension realizada por los autores de este trabajo, de los lineamientos propuestos por la Engineering Society for Advanced Mobility Land, Sea and Space en el estandar SAE-JA1012. Para contestar las primeras cinco preguntas del estandar se propone tomar como base los modos y mecanismos de fallas de componentes documentados en la guia para recopilar datos de falla en el estandar ISO-14224. Este enfoque permite estandarizar la descripcion de mecanismos de fallas de los equipos, tanto en el estudio RCM como en el proceso de recopilacion de datos de falla y de mantenimiento, lo que permite retroalimentar el ciclo de mejora continua de los procesos RCM. Tambien se propone el uso de matrices de riesgo para jerarquizar la importancia de los mecanismos de falla con base en el nivel de riesgo.

  3. Quality control in nuclear fuel fabrication on the inspection basis; Control de calidad para fabricacion de combustible nuclear en base a inspecciones

    Energy Technology Data Exchange (ETDEWEB)

    Fuentes S, A. [Instituto Tecnologico de Toluca, Toluca (Mexico)

    1997-12-31

    Every plant productive of electric power requires the use of energetics for the transformation to electricity. In the nucleo electric plant the energetic is the uranium, in which it makes ensembles and is used as fuel in the reactor. To assure that the fuel ensembles fulfill the specifications and requirements of design stipulated in the nucleo electric plant is that under a quality control through inspections during the fabrication process. The purpose of this work is to study and verify that the lineaments of the standard 10 CFR 50 appendix B `Quality assurement for nuclear plants` specially in the criteria `Inspections` that is used to guarantee the quality of the ensembles. This standard is the one that rules every activity and operation inside the pilot plant and its established in the quality program in the production of nuclear fuel for the Laguna Verde plant. The quality of the assemble is verified through each one of the tests or inspections due to the importance of it in the fabrication of fuel. (Author)

  4. An image analyzer system for the analysis of nuclear traces; Un sistema analizador de imagenes para el analisis de trazas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Cuapio O, A

    1990-10-15

    Inside the project of nuclear traces and its application techniques to be applied in the detection of nuclear reactions of low section (non detectable by conventional methods), in the study of accidental and personal neutron dosemeters, and other but, are developed. All these studies are based on the fact that the charged particles leave latent traces of dielectric that if its are engraved with appropriate chemical solutions its are revealed until becoming visible to the optical microscope. From the analysis of the different trace forms, it is possible to obtain information of the characteristic parameters of the incident particles (charge, mass and energy). Of the density of traces it is possible to obtain information of the flow of the incident radiation and consequently of the received dose. For carry out this analysis has been designed and coupled different systems, that it has allowed the solution of diverse outlined problems. Notwithstanding it has been detected that to make but versatile this activity is necessary to have an Image Analyzer System that allow us to digitize, to process and to display the images with more rapidity. The present document, presents the proposal to carry out the acquisition of the necessary components for to assembling an Image Analyzing System, like support to the mentioned project. (Author)

  5. ECED 2013: Eastern and Central Europe Decommissioning. International Conference on Decommissioning of Nuclear Facilities. Conference Guide and Book of Abstracts

    International Nuclear Information System (INIS)

    The Conference included the following sessions: (I) Opening session (2 contributions); (II) Managerial and Funding Aspects of Decommissioning (5 contributions); (III) Technical Aspects of Decommissioning I (6 contributions); (IV) Experience with Present Decommissioning Projects (4 contributions); (V) Poster Session (14 contributions); (VI) Eastern and Central Europe Decommissioning - Panel Discussion; (VII) Release of Materials, Waste Management and Spent Fuel Management (6 contributions); (VIII) Technical Aspects of Decommissioning II (5 contributions).

  6. Complementary assessment of the safety of French nuclear power plants; Evaluations complementaires de surete des centrales nucleaires francaises

    Energy Technology Data Exchange (ETDEWEB)

    Camarcat, N.; Pouget-Abadie, X. [EDF - (France)

    2011-07-15

    As an immediate consequence of the Fukushima accident the French nuclear safety Authority (ASN) asked EDF to perform a complementary safety assessment for each nuclear power plant dealing with 3 points: 1) the consequences of exceptional natural disasters, 2) the consequences of total loss of electrical power, and 3) the management of emergency situations. The safety margin has to be assessed considering 3 main points: first a review of the conformity to the initial safety requirements, secondly the resistance to events overdoing what the facility was designed to stand for, and the feasibility of any modification susceptible to improve the safety of the facility. This article details the specifications of such assessment, the methodology followed by EDF, the task organization and the time schedule. (A.C.)

  7. What they have in common the engineering from the Spanish nuclear power plants?; Que tienen en comun las ingenierias de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Mendez, M.

    2012-11-01

    In recent years, Spain Nuclear Power Plant Engineering have switched their project/task management method to Critical Chain multi-project management, developed by Dr. Goldratt, achieving outstanding results in improving quality and productivity. Multitasking reduction, task and resource synchronizing without the need of exact schedules, implementing a real-time priority information system, relying on the software Concerto, and daily decision making are the basis for the management change that has generated productivity increases of between 20% to 50%, opening new horizons for improvement in other scenarios such as optimizing refueling shutdowns. (Author)

  8. Modernization of electric power systems of the Laguna Verde Nuclear Power Plant; Modernizacion de los sistemas electricos de potencia de la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Gabaldon, M. A.; Gonzalez, J. J.; Prieto, I.

    2011-07-01

    The Power Increase Project of Laguna Verde Nuclear Plant has entailed the replacement, in one unique outage, of the main power electrical systems of the Plant (Isolated Phase Bars, Generator Circuit Breaker and Main Transformer) as well as the replacement of the Turbo-group. The simultaneous substitution of these entire system has never been done by any other Plant in the world, representing an engineering challenge that embraced the design of the new equipment up to the planning, coordination and management of the construction and commissioning works, which were successfully carried out by Iberdrola within the established outage period /47 days) for both units. (Author)

  9. Prevalencia de microsporidios en orinas de pacientes referidos para urocultivo en la Región Pacífico Central

    Directory of Open Access Journals (Sweden)

    Idalia Valerio-Campos

    2002-03-01

    Full Text Available Justificación: La mayoría de las infecciones por microsporidios en el ser humano se han reportado en el tracto gastrointestinal, sin embargo, es posible hallarlos parasitando otros sitios anatómicos como el tracto genitourinario, en donde las patologías pueden variar desde uretritis hasta falla renal. Tradicionalmente esas infecciones se deben al género Encephalitozoon, parásito contra el cual el Albendazol ha demostrado ser un medicamento efectivo. Objetivo: Determinar la prevalencia de microsporidios en personas que son referidas al laboratorio para urocultivo, dados los antecedentes clínicos que presentan. Métodos: El procesamiento de las muestras incluyó su toma con técnica aséptica, su cultivo en los medios de Agar Sangre, MacConkey y Manitol - sal para su estudio por presencia de bacterias y/u hongos y la realización del antibiograma, según los parámetros establecidos por la CCSS para los urocultivos. Adicional a esto se centrifugó una alícuota de 9 ml separando 50 microlitos del sedimento urinario, al cual se le añadió igual volumen de KOH al 5%. Se hicieron frotis los cuales se fijaron con alcohol metílico una vez secos, y se tiñeron con la técnica trierómica de Weber, obviando el paso de la decoloración y la deshidratación. Resultados: Se encontró un 25% de orinas positivas por microsporidios. Los pacientes con edades entre 26 y 55 años presentaron mayor positividad. Conclusiones: El porcentaje de prevalencia encontrado (25% y el hecho de que estas infecciones pueden llegar a causar severos daños al ser humano, hacen imperativa la necesidad de realizar diagnósticos más certeros de esta parasitosis, para lo cual proponemos la tinción de Weber con la modificación presentada en este trabajo para el diagnóstico de las infecciones por microsporidios en el tracto urinario.

  10. Retention capacity of samarium (III) in zircon for it possible use in retaining walls for confinement of nuclear residues; Capacidad de retencion de samario (III) en circon para su posible uso en barreras de contencion para confinamiento de residuos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Garcia G, N

    2006-07-01

    Mexico, as country that produces part of its electric power by nuclear means, should put special emphasis in the development of technologies guided to the sure and long term confinement of the high level nuclear residuals. This work studies the capacity that has the natural zircon to retain to the samarium (III) in solution, by what due, firstly, to characterize the zircon for technical instrumental to determine the purity and characteristic of the mineral in study. The instrumental techniques that were used to carry out the physicochemical characterization were the neutron activation analysis (NAA), the infrared spectroscopy (IS), the thermal gravimetric analysis (TGA), scanning electron microscopy (SEM), transmission electron microscopy (TEM), semiquantitative analysis, dispersive energy spectroscopy (EDS), X-ray diffraction (XRD) and luminescence technique. The characterization of the surface properties carries out by means of the determination of the surface area using the BET multipoint technique, acidity constants, hydration time, the determination of the point of null charge (pH{sub PCN}) and density of surface sites (D{sub s}). The luminescence techniques were useful to determine the optimal point hydration of the zircon and for the quantification of the samarium, for that here intends the development of both analysis techniques. With the adjustment of the titration curves in the FITEQL 4 package the constants of surface acidity in the solid/liquid interface were determined. To the finish of this study it was corroborated that the zircon is a mineral that presents appropriate characteristics to be proposed as a contention barrier for the deep geologic confinement. With regard to the study of adsorption that one carries out the samarium retention it is superior to 90% under the described conditions. This investigation could also be applicable in the confinement of dangerous industrial residuals. (Author)

  11. Strategies for the formation of human resources in the mexican nuclear field; Estrategias para la formacion de recursos humanos en el campo nuclear mexicano

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A.M. [ININ, Carretera Mexico-Toluca s/n, 52750 La Marquesa, Ocoyoacac, Estado de Mexico (Mexico); Valle G, E. del [ESFM, IPN, Unidad Profesional ' Adolfo LopezMateos' , Av. Politecnico Nacional, 07738 Mexico D.F. (Mexico); Francois L, J.L. [Facultad de Ingenieria, UNAM, Paseo Cuauhnahuac 8532, Jiutepec, 62550 Morelos (Mexico); Espinosa P, G. [Universidad Autonoma Metropolitana Iztapalapa, Av. San Rafael Atlixco 186 Col. Vicentina, 09340 Mexico D.F. (Mexico); Mireles G, F. [Universidad Autonoma de Zacatecas, CREN, Av. Ramon Lopez Velarde 801, 98000 Zacatecas (Mexico); Croche B, R. [Universidad Veracruzana, FIME-Xalapa Lomas de Estadio s/n, Xalapa, 91090 Veracruz (Mexico); Lartigue G, J. [Facultad de Quimica-D-UNAM Ciudad Universitaria, 04510 Mexico D.F. (Mexico)]. e-mail: amgt@nuclear.inin.mx

    2007-07-01

    This work looks for to put in the discussion table the topic of the formation of human resources highly qualified that doubtless will need the country in the short term, same that will have to begin to be formed from now on to be able to satisfy the demand in the next future. They take like base several studies carried out by the NEA/OECD and the recommendations that have emanated of the same ones for later to make an approach of the current Mexican situation and to conclude with a series of recommendations that have been identified. The recommendations here exposed, they are only the thought of the authors and in no way they are based on an already carried out study. However it will be important to open the debate on the real strategies to have a national nuclear politics based on solid resultant foundations of the production and training of brilliant human resources. (Author)

  12. Development of parallel GPU based algorithms for problems in nuclear area; Desenvolvimento de algoritmos paralelos baseados em GPU para solucao de problemas na area nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Adino Americo Heimlich

    2009-07-01

    Graphics Processing Units (GPU) are high performance co-processors intended, originally, to improve the use and quality of computer graphics applications. Since researchers and practitioners realized the potential of using GPU for general purpose, their application has been extended to other fields out of computer graphics scope. The main objective of this work is to evaluate the impact of using GPU in two typical problems of Nuclear area. The neutron transport simulation using Monte Carlo method and solve heat equation in a bi-dimensional domain by finite differences method. To achieve this, we develop parallel algorithms for GPU and CPU in the two problems described above. The comparison showed that the GPU-based approach is faster than the CPU in a computer with two quad core processors, without precision loss. (author)

  13. Avaliação do tipo de curativo utilizado em cateter venoso central para hemodiálise Evaluación del tipo de curativo utilizado en cateter venoso central para hemodiálisis Evaluation of tow types of dressings used on central venous catheters for hemodialysis

    Directory of Open Access Journals (Sweden)

    Luciene de Fátima Neves Monteiro de Barros

    2009-01-01

    Full Text Available OBJETIVOS: Avaliar a efetividade de dois tipos de curativos utilizados em cateter venoso central (CVC em pacientes submetidos à hemodiálise; identificar a taxa de infecção no local de saída e de bacteremia comparando o curativo com gaze e micropore em relação ao filme transparente. MÉTODOS: Foi realizado um ensaio clínico randomizado controlado abrangendo 66 pacientes, sendo 33 nos grupos 1 e 2, respectivamente. No Grupo 1 o curativo utilizado foi gaze e micropore e no Grupo 2 filme transparente. Foram coletados os dados sócio demográficos, clínicos e os relacionados às infecções. Os 66 pacientes permaneceram no estudo até a indicação de retirada do cateter que ocorreu nos episódios de infecção quando foram realizadas culturas de óstio e da ponta do CVC e hemocultura quando indicado. RESULTADOS: Não houve diferença estatística significante quanto ao tipo de curativo e as variáveis estudadas. Os CVC posicionados a 90º em relação a pele apresentaram maior taxa de infecção por S. aureus. CONCLUSÃO: O uso do filme transparente não proporcionou redução de infecção, porém a análise qualitativa deste tipo de curativo teve melhor aceitação pelos pacientes e profissionais da Unidade de Diálise de um Hospital Universitário.OBJETIVOS: Evaluar la efectividad de dos tipos de curativos utilizados en cateter venoso central (CVC en pacientes submetidos al hemodiálisis; identificar el índice de infección en el local de salida y de bacteremia comparando el curativo con gaza y micropore el con al filme transparente. MÉTODOS: Fue realizado un ensayo clínico randomizado controlado. En el Grupo 1 el curativo utilizado fue gaza y micropore y en el Grupo 2 filme transparente. Fueron colectados los datos sócio demográficos, clínicos y los relacionados a las infecciones. Los 66 pacientes permanecieron en el estudio hasta la indicación de retirada del cateter que ocurrió en los episodios de infección cuando fueron

  14. Experience in training of health personnel for response to radiological and nuclear accidents; Experiencia na capacitacao de profissionais de saude para a resposta a acidentes radiologicos e nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Maurmo, Alexandre M., E-mail: ammaurmo@gmail.com [Fundacao Eletronuclear de Assistencia Medica (CMRI/CTNV/FEAM), Praia Brava, RJ (Brazil). Centro de Medicina das Radiacoes Ionizantes. Centro de Treinamento Prof. Nelson Valverde; Leite, Teresa C.S.B., E-mail: feam@feam-etn.org.br [Fundacao Eletronuclear de Assistencia Medica (CIRA/FEAM), Praia Brava, RJ (Brazil). Centro de Informacoes em Radioepidemiologia

    2013-07-01

    Eletronuclear Healthcare Foundation is the Institution responsible for the actions of health response involving ionizing radiation in the area of Nuclear Power Plant Almirante Alvaro Alberto in Angra dos Reis. Because of their specific assignments and references for being in training health manpower in the field of ionizing radiation developed a range of Training Courses for Professionals Area Health to prepare them for Response to Radiological and Nuclear Accidents. Modules are proposed specifically for the professional response of the Technical Level and Higher Level, the level Pre-hospital and hospital. These modules are further divided into specific levels or modules, Basic or Introductory, Intermediate and Advanced. Are applied pretests and post tests to monitor the content of fixing, maintaining a historical series of reviews. Your content is theoretical and practical applications developed in 30 to 48 hours, with simulations (drills) and distribution of educational materials. We already have more than 80 applications training, focusing on internal staff and external to the institution, developing interesting partner with the Armed Forces and Civil Defense. It still maintained a link on the institution seeking access and download over 400 titles on the subject and exchange of information and experiences. For improving the teaching material, the authors launched in 2011 the first manual in Portuguese on the subject with new revised edition in 2013: 'Manual of Medical Actions In Radiological Emergencies'. The results indicate increased knowledge and appropriateness of the themes and the strategy proposed for this activity, demonstrating yet passed that information can be multiplied and meets the growing demand of the country that has hosted and will host international events relevant at QBNRE risk. (author)

  15. Systematic approach for assessment of accident risks in chemical and nuclear processing; Abordagem sistematica para avaliacao de riscos de acidentes em instalacoes de processamento quimico e nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Senne Junior, Murillo

    2003-07-15

    The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of

  16. Transference patron for the calibration of activemeters for use in nuclear medicine; Patron de transferencia para la calibracion de activimetros de uso en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Cortes P, A.; Garcia D, O.C.; Ortiz P, I.; Becerril V, A. [Instituto nacional de Investigaciones Nucleares, Laboratorio de Patrones Radiactivos, Departamento de Metrologia, A.P. 18-1027. C.P. 11801 Mexico D.F. (Mexico)

    2000-07-01

    With the object to improve the calibration service of the activemetersof the users (nuclear medicine centres) so internal as external users at ININ and initiating the establishment of the traceability of the activity measures that carry out in the country, with respect to the National Patron of Nuclear Activity No. ININ-PNM-2, it is initiated the characterization and the performance control of the activemeter make Capintec, model CRC-7BT of the laboratory of Radioactive Patrons (LPR) of the Department of Metrology for to convert it in a transference patron. This characterization and control are based in the sustained review of the activemeter calibration for the I-131, Mo-99 and Sm-153 radioisotopes with activities from 100 mCi until some {mu} Ci and the Tc-99m, In-111, Tl-201, Ga-67, Cs-137, Co-60, and Ba-133 with activities of the range of some {mu} Ci. To verify the good performance of the instrument it was revised the linearity of its scale, the stability of readings, the variation of readings respect of the source position inside the activemeter well and it was determined the calibration factors for each one of the radiosotopes mentionated. The radioactive sources of mid-short life that are used which consist in radioactive solutions of 10 cm{sup 3} contained in polyethylene small bottles of 25 cm{sup 3} elaborated in the LPR and whose activity is measured with respect to the National Patron ININ-PNM-2. The sources of mid-large life are ampoules with 5 cm{sup 3} of radioactive solution, calibrated in activity by the primary laboratory, LNHB (formerly LMRI) of France. (Author)

  17. Self-Reliance and Sustainability of Nuclear Analytical Laboratories in Small States of Central Europe: The Slovenian Case

    International Nuclear Information System (INIS)

    The Jožef Stefan Institute is the largest research institution in Slovenia devoted to research in many fields of science and technology. Within the Institute several nuclear analytical laboratories operate, making it the largest nuclear research institution in Slovenia. The Laboratory for Radiation Measuring Systems and Radioactivity Measurements belongs to the Department for Medium and Low Energy Physics, which is engaged mainly in nuclear physics, interactions of radiation with matter and its applications, and in providing a service in radiation measurements and dosimetry. The laboratory was founded almost thirty years ago, when the three accelerators, which formed the basis of the research infrastructure of the department, came to the end of their working lives. The personnel took the opportunity to participate in the programme of radioactivity monitoring of the Krško Nuclear Power Plant, which at that time went into operation. The equipment, i.e., the detectors, electronics and computers, was available, but the expertise was limited to the techniques of measurement and analysis in gamma-ray spectrometry. The absence of the expertise in radiochemistry was a serious drawback, therefore new methods in detector calibration had to be developed. In the following years the laboratory participated not only in the monitoring programme of the nuclear power plant but also in other radioactivity monitoring programmes in Slovenia. Since its foundation the laboratory did not receive any financial support either from the state or from the department. Support in equipment and expertise was received from the International Atomic Energy Agency, the Government of the United States and the United Nations Development Programme. The laboratory is engaged mainly in gamma-ray spectrometric measurements of samples from the natural, living and working environments. The main customers are the Krško Nuclear Power Plant and governmental organizations and agencies. The work for these

  18. Cooperação e poder: a Organização de Cooperação de Shangai como expressão da política externa chinesa para a Ásia Central

    Directory of Open Access Journals (Sweden)

    Andréa Freire Lucena

    2011-01-01

    Full Text Available At the beginning of the twenty-first century, Kazakhstan, China, Kyrgyzstan, Russia, Tajikistan and Uzbekistan established the Shanghai Cooperation Organization. This international organization represents the first Chinese initiative in building an international security organization. This article aims to study the Chinese Foreign Policy for Central Asia from the perspective of the Shanghai Cooperation Organization. We seek to answer how this international organization enables the Chinese state to achieve its interests in Central Asia. / No início do século XXI, Cazaquistão, China, Quirguistão, Rússia, Tajiquistão e Uzbequistão criaram a Organização de Cooperação de Shangai. A proeminência dessa organização internacional está no fato de ela representar a primeira iniciativa chinesa na construção de um organismo internacional de segurança. O presente artigo tem por objetivo estudar a Política Externa Chinesa para a Ásia Central sob a ótica da Organização de Cooperação de Shangai. Como problemática, busca- se responder de que maneira essa organização internacional possibilita ao Estado chinês atingir seus interesses na região centro asiática.

  19. Diseño y montaje de un condensador de vapor down flow para una central térmica de ciclo combinado

    OpenAIRE

    Turiel Casado, Vanesa

    2011-01-01

    El condensador, es un intercambiador de calor situado tras la turbina que condensa el vapor de salida de la misma. En este PFC se abordara la fabricación de un condensador incluyendo: - Descripción del equipo y de los diferentes sistemas auxiliares encargados del mantenimiento y seguridad del equipo. Dichos sistemas aseguran para el mismo un comportamiento correcto y efectivo durante el tiempo de vida del equipo. - Diseño térmico, mecánico y dimensionamiento. - Correctas selecciones ...

  20. Eficiencia de la política monetaria y la estabilidad de las preferencias del Banco Central. Evidencia empírica para el Perú

    OpenAIRE

    Rodríguez, Gabriel

    2008-01-01

    Siguiendo el trabajo de Favero y Rovelli (2003), estimamos un sistema de 3 ecuaciones para diferentes muestras de la economía Peruana con el objetivo de analizar la evolución de los parámetros asociados a las preferencias de la autoridad monetaria y a la estructura de la economía. Los resultados indican que las preferencias de la autoridad monetaria han cambiado entre los diferentes regímenes. En particular, el estimado de la meta implícita de inflación se ha reducido de forma significativa e...

  1. SISTEMA DE CENTRALIZACIÓN DE ALARMAS PARA LA DETECCIÓN DE FALLAS EN LAS CENTRALES TELEFÓNICAS ANALÓGICAS.

    OpenAIRE

    Ing. Leon Febres Andara Laclé

    2002-01-01

    Este estudio destaca la propuesta de aplicación de una plataforma tecnológica que a grandes rasgos cumpla con lo que hoy en día esta implantándose en países desarrollados en Telecomunicaciones como lo es la Televisión Digital, el cual se describe como una proyecto donde estaciones televisivas deben desarrollar una red digital para integrar los servicios que benefician a toda la comunidad. Es importante destacar que, la transmisión de este tipo de señal viene determinada a través de frecuencia...

  2. Regulatory challenges in the management of aging of structural materials in nuclear power plants; Retos reguladores en la gestion del envejecimiento de los materiales estructurales de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Castelo, C.; Mendoza, C.; Mas, E.; Conde, J. M.

    2013-07-01

    The article discusses two major pathways by which a regulatory body, and in particular the CSN, may participate in the acquisition of the necessary knowledge on mechanisms of aging of nuclear structural materials: to participate in forums to share operational experience and R and R project, both nationally and internationally. It notes the importance of this participation to carry out its regulatory function based on the knowledge acquired and the unique challenge of transferring that knowledge to rules and guidelines for their application. The article discusses various R and D projects in which the CSN participates directly. It calls for the presence of regulatory bodies in R and D project funded by the EU and the transfer of the results of such projects to codes, standards or guidelines for feasible implementation. (Author)

  3. Desenvolvimento de software e hardware para irrigação de precisão usando pivô central Development of software and hardware for precision irrigation using the center pivot

    Directory of Open Access Journals (Sweden)

    Tadeu M. de Queiroz

    2008-03-01

    Full Text Available O presente trabalho teve por objetivo desenvolver softwares e hardwares para aplicação ao monitoramento e controle automático para a irrigação de precisão usando sistemas do tipo pivô central. O trabalho foi desenvolvido no Departamento de Engenharia Rural - LER, da Escola Superior de Agricultura "Luiz de Queiroz" - ESALQ, da Universidade de São Paulo - USP, em Piracicaba - SP. Foram utilizados componentes eletrônicos discretos, circuitos integrados diversos, módulos de radiofreqüência, microcontroladores da família Basic Step e um microcomputador. Foram utilizadas as linguagens Delphi e TBasic. O hardware é constituído de dois circuitos eletrônicos, sendo um deles para "interface" com o computador e o outro para monitoramento e transmissão da leitura de tensiômetros para o computador via radiofreqüência. Foram feitas avaliações do alcance e da eficiência na transmissão de dados dos módulos de radiofreqüência e do desempenho do software e do hardware. Os resultados mostraram que tanto os circuitos quanto os aplicativos desenvolvidos apresentaram funcionamento satisfatório. Os testes de comunicação dos rádios indicaram que esses possuem alcance máximo de 50 m. Concluiu-se que o sistema desenvolvido tem grande potencial para utilização em sistemas de irrigação de precisão usando pivô central, bastando para isso que o alcance dos rádios seja aumentado.The objective of this work was to develop softwares and hardwares applied to the management and automatic control for precision irrigation using center pivot systems. They were developed in the Rural Engineering Department - LER, at the "Luiz de Queiroz" College of Agriculture - ESALQ, of São Paulo University - USP, in Piracicaba, SP-Brazil. It was used discrete electronic components, several integrated circuits, radio frequency modules, microcontrollers from the Basic Step family and a microcomputer. The computer software was developed in Delphi language, and

  4. Contribuição da medicina nuclear para a avaliação dos linfomas

    Directory of Open Access Journals (Sweden)

    Sapienza Marcelo T.

    2001-01-01

    Full Text Available A medicina nuclear permite a caracterização funcional de tecidos, acrescentando dados à avaliação anatômica realizada por outros métodos de imagem, como a tomografia computadorizada, ressonância magnética ou ultra-som. Além do diagnóstico e estadiamento, as informações funcionais fornecidas pela medicina nuclear são particularmente úteis no seguimento e avaliação de resposta terapêutica dos pacientes com linfoma. A presença de massa residual após quimioterapia ou a infiltração de linfonodos de pequenas dimensões são exemplos de situações nas quais a avaliação isolada de características anatômicas é insuficiente. Os principais métodos utilizados são a cintilografia com gálio-67, traçador com alta afinidade por transferrina e receptores de ferro, e os estudos com flúor-deoxiglicose, emissor de pósitron que permite a caracterização do metabolismo de glicose nos tecidos. Outros traçadores, como o tálio-201, sestamibi-Tc99m e octreotide-In111, também são utilizados em menor escala na avaliação dos pacientes com linfoma. Os mecanismos de captação, principais indicações dos estudos, limitações e resultados de literatura serão revistos.

  5. New recommendations from the IAEA for medical exposures: impact on nuclear medicine in Brazil; Novas recomendacoes da IAEA para exposicoes medicas: impacto em medicina nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Sa, Lidia Vasconcellos de; Kodlulovich, Simone, E-mail: lidia@ird.gov.br, E-mail: simone@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2013-10-01

    An assessment of the current national standards was performed in order to verify compliance with the new recommendations, taking into account the number of available facilities and medical physicists to meet the requirements. It was found that compliance with the requirements of protocol optimization and individualization of doses, as well as the assignment of responsibility shared by all professionals involved were not disclosed. In Brazil, there is no reference levels established as also there is not a government program to obtain them. The functions and responsibilities of the medical physicist in conducting dosimetry individual patient, quality control and acceptance tests of equipment and also the calibration is not defined in the standard. Currently in Brazil there are 31 certified Medical Physicists in Medicine Nuclear power to meet approximately 390 facilities, representing only 8% required. As a member state of the IAEA, the Brazilian rules governed by CNEN is based on BSS-115, must come to terms with the GSR. The concern is now meeting the requirements, especially those relating to patients, since we have established benchmarks and individualized dosimetry. Beyond addition, the number of medical physicists are not enough to show the country's demand. (author)

  6. Genetic structure based on nuclear and chloroplast microsatellite loci of Solanum lycocarpum A. St. Hil. (Solanaceae) in Central Brazil.

    Science.gov (United States)

    Martins, K; Chaves, L J; Vencovsky, R; Kageyama, P Y

    2011-01-01

    Solanum lycocarpum (Solanaceae) is a woody species found in the Brazilian Cerrado. The flowers are pollinated by Xylocopa spp bees, and seeds are dispersed by mammals with distinct home range sizes. As a consequence, relative contributions of pollen and seeds to overall gene flow can vary according to different spatial scales. We studied the genetic structure of four natural populations of S. lycocarpum separated by 19 to 128 km, including individuals located along dirt roads that interlink three of the populations. A total of 294 individuals were genotyped with five nuclear and six chloroplast microsatellite markers. Significant spatial genetic structure was found in the total set of individuals; the Sp statistic was 0.0086. Population differentiation based on the six chloroplast microsatellite markers (θ(pC) = 0.042) was small and similar to that based on the five nuclear microsatellite markers (θ(p) = 0.054). For this set of populations, pollen and seed flow did not differ significantly from one another (pollen-to-seed flow ratio = 1.22). Capability for long distance seed dispersion and colonization of anthropogenic sites contributes to the ability of S. lycocarpum to maintain genetic diversity. Seed dispersion along dirt roads may be critical in preserving S. lycocarpum genetic diversity in fragmented landscapes. PMID:21523656

  7. Prevalencia de microsporidios en orinas de pacientes referidos para urocultivo en la Región Pacífico Central

    Directory of Open Access Journals (Sweden)

    Idalia Valerio-Campos

    2002-03-01

    Full Text Available Justificación: La mayoría de las infecciones por microsporidios en el ser humano se han reportado en el tracto gastrointestinal, sin embargo, es posible hallarlos parasitando otros sitios anatómicos como el tracto genitourinario, en donde las patologías pueden variar desde uretritis hasta falla renal. Tradicionalmente esas infecciones se deben al género Encephalitozoon, parásito contra el cual el Albendazol ha demostrado ser un medicamento efectivo. Objetivo: Determinar la prevalencia de microsporidios en personas que son referidas al laboratorio para urocultivo, dados los antecedentes clínicos que presentan. Métodos: El procesamiento de las muestras incluyó su toma con técnica aséptica, su cultivo en los medios de Agar Sangre, MacConkey y Manitol - sal para su estudio por presencia de bacterias y/u hongos y la realización del antibiograma, según los parámetros establecidos por la CCSS para los urocultivos. Adicional a esto se centrifugó una alícuota de 9 ml separando 50 microlitos del sedimento urinario, al cual se le añadió igual volumen de KOH al 5%. Se hicieron frotis los cuales se fijaron con alcohol metílico una vez secos, y se tiñeron con la técnica trierómica de Weber, obviando el paso de la decoloración y la deshidratación. Resultados: Se encontró un 25% de orinas positivas por microsporidios. Los pacientes con edades entre 26 y 55 años presentaron mayor positividad. Conclusiones: El porcentaje de prevalencia encontrado (25% y el hecho de que estas infecciones pueden llegar a causar severos daños al ser humano, hacen imperativa la necesidad de realizar diagnósticos más certeros de esta parasitosis, para lo cual proponemos la tinción de Weber con la modificación presentada en este trabajo para el diagnóstico de las infecciones por microsporidios en el tracto urinario.Urine samples from patients with clinical antecedents of suspicion genitourinary pathology were studied for bacteria, fungi and for the

  8. Gestão estratégica de pessoas para a inovação: o caso da Frimesa Cooperativa Central INNOVATION-ORIENTED STRATEGIC MANAGEMENT OF PEOPLE: FRIMESA COOPERATIVA CENTRAL CASE

    Directory of Open Access Journals (Sweden)

    Sonia Regina Hierro Parolin

    2011-05-01

    Full Text Available

    Visando contribuir com a integração das estratégias de gestão de pessoas com inovação, a pesquisa visou identificar relações entre as características organizacionais e o espaço para a criatividade, em uma organização inovativa. As variáveis de características organizacionais abrangeram: estrutura organizacional, filosofia e valores, políticas e sistemas de recursos humanos; as de espaço para a criatividade: encorajamento à criatividade, ambiente da tarefa, recursos e impedimentos organizacionais. O estudo qualitativo exploratóriodescritivo foi realizado em grande empresa inovadora do segmento de laticínios. Foram realizadas entrevistas com gestores de recursos humanos e de tecnologia e aplicação de questionários a 68 funcionários técnicos e administrativos. Os principais resultados demonstram a integração de estratégias de gestão de pessoas e inovação e apontam que o espaço para a criatividade é permeado por práticas de valorização das pessoas e de seus resultados na organização. As práticas de gestão de pessoas mais evidenciadas relacionam-se aos feedbacks construtivos na avaliação de desempenho.

    Aiming at contributing to the integration of the strategies for management of people with innovation, the research focused on identifying relationship between organizational characteristics and space for creativity in an innovative organization. The variables of the organizational characteristics have involved: organizational structure, philosophy and values, and policies and human resources systems; the variables of space for creativity have involved: encouragement for creativity, assignment environment, organizational resources and impediments. Interviews with HR and technology managers have been held, as well as the application of a questionnaire to 68 technical and administrative collaborators. The main results demonstrates the policies and

  9. Spag16, an axonemal central apparatus gene, encodes a male germ cell nuclear speckle protein that regulates SPAG16 mRNA expression.

    Directory of Open Access Journals (Sweden)

    David R Nagarkatti-Gude

    Full Text Available Spag16 is the murine orthologue of Chlamydomonas reinhardtii PF20, a protein known to be essential to the structure and function of the "9+2" axoneme. In Chlamydomonas, the PF20 gene encodes a single protein present in the central pair of the axoneme. Loss of PF20 prevents central pair assembly/integrity and results in flagellar paralysis. Here we demonstrate that the murine Spag16 gene encodes two proteins: 71 kDa SPAG16L, which is found in all murine cells with motile cilia or flagella, and 35 kDa SPAG16S, representing the C terminus of SPAG16L, which is expressed only in male germ cells, and is predominantly found in specific regions within the nucleus that also contain SC35, a known marker of nuclear speckles enriched in pre-mRNA splicing factors. SPAG16S expression precedes expression of SPAG16L. Mice homozygous for a knockout of SPAG16L alone are infertile, but show no abnormalities in spermatogenesis. Mice chimeric for a mutation deleting the transcripts for both SPAG16L and SPAG16S have a profound defect in spermatogenesis. We show here that transduction of SPAG16S into cultured dispersed mouse male germ cells and BEAS-2B human bronchial epithelial cells increases SPAG16L expression, but has no effect on the expression of several other axoneme components. We also demonstrate that the Spag16L promoter shows increased activity in the presence of SPAG16S. The distinct nuclear localization of SPAG16S and its ability to modulate Spag16L mRNA expression suggest that SPAG16S plays an important role in the gene expression machinery of male germ cells. This is a unique example of a highly conserved axonemal protein gene that encodes two protein products with different functions.

  10. La ciudad central de la Ciudad de México: ¿espacio de oportunidad laboral para la metrópoli?

    Directory of Open Access Journals (Sweden)

    Clara Eugenia Salazar

    2010-01-01

    Full Text Available Las áreas centrales de las grandes metrópolis han perdido población y transformado sus actividades económicas como respuesta a la redistribución intrametropolitana de la población y los cambios en la demanda ocupacional. ¿Significa que los centros de las ciudades han perdido su centralidad? El concepto de centralidad puede ser abordado desde diferentes perspectivas, pero todas ellas enfatizan la concentración espacial de funciones urbanas y actividades económicas. En este documento se analiza la evolución de la demanda ocupacional en la Zona Metropolitana de la Ciudad de México entre 1980 y 2003, y en particular en su ciudad central. El periodo de estudio se inscribe en un contexto nacional y local de reestructuración económica, e interesa conocer el papel de la ciudad central en el crecimiento económico y en la generación de empleo metropolitano, así como en su transformación económica y ocupacional.

  11. POBLACIÓN Y FERTILIZACIÓN NITROGENADA EN UN HÍBRIDO DE MAÍZ PARA ENSILAJE EN EL VALLE CENTRAL REGADO Planting density and nitrogen fertilization of hybrid corn for silage in the irrigated central valley

    OpenAIRE

    Patricio Soto O.; Ernesto Jahn B; Susana Arredondo S

    2002-01-01

    Se evaluó el efecto de tres dosis de nitrógeno y cuatro densidades de plantas sobre el rendimiento de forraje y proteína en un híbrido tardío de maíz (Zea mays L.) para ensilaje. Las densidades fueron: 70.000, 90.000, 100.000 y 130.000 plantas ha-1; y los niveles de N fueron 150, 300 y 450 kg de N ha-1, dando origen a 12 tratamientos, los que fueron establecidos en parcelas de 22,4 m². Ambos factores fueron evaluados en un diseño de bloques completos al azar con 4 repeticiones, con arreglo fa...

  12. Microstructure of red clay from the central Pacific deep-sea basin: Significance to subseabed nuclear waste disposal

    International Nuclear Information System (INIS)

    The microstructure of deep-sea illitic red clay from the central Pacific Basin was investigated using transmission and scanning electron microscopy techniques. Gravity core samples (''undisturbed'') and sediments from dredge hauls (''disturbed'') were used in the investigations and analysis. Dredged samples were remolded and reconsolidated to equivalent in situ porosities by geotechnical engineers. To a first approximation, no significant difference in the fabric was observed between the undisturbed and remolded illitic sediment. Samples adjacent to the heater probe were subjected to temperatures slightly below 3000C. Slight preferential clay particle alignment probably resulting from shearing stresses developed in the sediment during probe insertion. Heating of the sediment did not appear to have a significant effect on the fabric, with the exception of localized ''quasi-expansion'' and flow features observed in the microfabric in the near field. 34 refs., 28 figs

  13. Data acquisition and management system for a nuclear processes simulator; Sistema de adquisicion y manejo de datos para un simulador de procesos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez M, J.A.; Santiago C, J. [Facultad de Ingenieria, UNAM, Campus Morelos (Mexico)]. e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    In the development of this work (Data acquisition and management system for a simulator of nuclear processes (SAMAD)), is important to mention the main modules that involve the operation of the same one. At the beginning it was necessary to contemplate the possible programming languages, as well as the compatibility and handling easiness among them. The used languages to be able to land the contemplated ideas are: C{sup ++}, PHP, HTML, as well as the My SQL database manager. After this it was designed the database (DB), which contains the tables of each one of the components, this according to the enter file type of the RELAP5 code that will be use for each simulation, as well as, tables that will allow us to relate and to maintain the control of the information supplied to the DB. Once created the database is interacting with it through an application program based on PHP (Preprocessor). The application basically consists, in extracting the data from each one of the components to work in that moment, that is to say, to obtain the data of the enter file, as well as, to depurate the data, excluding comments. The preprocessor gives bigger easiness to place the data in the DB. Also, it was developed an graphic interface that allows to register variables to the DB, depending from the unfolding to visualize. Another application that has been implemented is the Data Collector that has as function, to obtain in a direct way the data of the display variables of the RELAP5 code, with the purpose of storing them in the DB, this will be carry out in real time and it was updated in a very small time period. (Author)

  14. Communication dated 11 September 2006 from the Permanent Mission of the Republic of Kazakhstan regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia signed on 8 September 2006

    International Nuclear Information System (INIS)

    The Secretariat has received a Note Verbale, dated 11 September 2006, from the Permanent Mission of the Republic of Kazakhstan to the IAEA regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia signed on 8 September 2006 in Semipalatinsk by the leaders of Kazakhstan, Kyrgyzstan, Tajikistan, Turkmenistan and Uzbekistan. The Note Verbale and, as requested therein, the enclosed information regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia, is reproduced herewith for the information of Member States

  15. Central Indicent Reporting and Evaluation Office of VGB evaluation of special incidents in nuclear power plants; Auswertung besonderer Vorkommnisse in Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Buettner, J.; Grundhoefer, M.; Vallana, G. [VGB Technische Vereinigung der Grosskraftwerksbetreiber e.V., Essen (Germany)

    2000-07-01

    The Central Incident Reporting and Evaluation Office (ZMA) has been founded upon recommendation of the plant managers of German nuclear power plants in 1984 to serve as a central point of information flows at VGB. Since then all incidents have been reported to ZMA that are safety-relevant, have an important bearing on the availability or are of public interest. These incidents are stored in a data base and made available to all member companies for their exchange of experience. Measures taken lead to continual improvements of the plant safety and availability. (orig.) [German] Die 'Zentrale Melde- und Auswertestelle' (ZMA) wurde auf Empfehlung der Betriebsleiter der deutschen Kernrkaftwerke im Jahre 1984 als Drehscheibe der Informationsfluesse bei der VGB eingerichtet. Seitdem werden von den Mitgliedsunternehmen alle Vorkommnisse an die ZMA gemeldet, die sicherheitstechnisch relevant, fuer die Verfuegbarkeit wesentlich oder von oeffentlichem Interesse sind. Diese Vorkommnismeldungen werden in einer Datenbank gespeichert und allen Mitgliedsunternehmen zwecks Erfahrungsaustausch zur Verfuegung gestellt. Die durchgefuehrten Massnahmen fuehren zu kontinuierlichen Verbesserungen der Anlagensicherheit und Verfuegbarkeit. (orig.)

  16. Nuclear power plant of Fessenheim: evaluation of the seismic risk; Centrale Nucleaire de Fessenheim: appreciation du risque sismique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The seismic risk taken into account during the sizing of the nuclear power plant of Fessenheim seems to have been under evaluated at this time. The revaluation of the seismic risk, as proposed, until this day by EDF in order to the third ten-year visit of the power plant, planned for 2009, leads to a significant under evaluation of the risk and then is not acceptable. The present expertise details point by point the weaknesses of these revaluation. The power plant has been sized in an elastic manner that is generally strongly for the safety side. It is imperative to proceed the most quickly as possible to a deep control of the seismic resistance of the power plant of Fessenheim and then after having proceeded to a revision of the seismic risk in taking into account the actual knowledge in this field. (N.C.)

  17. Improvements related with the safety required by the Argentine Regulatory Authority to the Atucha I Nuclear Central

    International Nuclear Information System (INIS)

    The Argentinean Nuclear Regulation Authority (ARN) verified the existence of changes in the state of some internal components of the reactor of the Atucha I Nuclear Power station that, of continuing in the time, it could take to an inconvenient degradation for the safety operation of the installation. In consequence, to the effects of preventing that reach this situation, at the end of 1999, the ARN required to the Responsible Entity for the operation of this power station the implementation of an important improvements program in the internal components of the reactor. Additionally, and based on the results of the Probabilistic Safety analysis, it was added the one mentioned improvements program the implementation of an alternative cooling system of the reactor core denominated Second Drain of Heat, due to it was determined that, for some accidental sequences, their performance would reduce considerably the probability of damage to the core. The concretion of the improvements program implied to the Responsible Entity the realization of an important quantity of engineering studies, tests and specific inspections that allowed to carry out changes on the control bars of the reactor and its guide tubes; the coolant channels; the sensors of neutron flow; and diverse components of the primary and moderator systems. On the other hand also it was implemented the system Second Drain of Heat, what represents a considerable effort to make compatible the instrumentation and control of last generation, with the instrumentation and existent control systems in the power station. Also, it was requested to be carried out an integrity of the pressure recipient for to demonstrate the existence of an acceptable margin for the difference among the acceptable limit temperatures and of ductile/fragile transition of the material for all the possible accidental scenarios during the useful life of the reactor. (Author)

  18. Two new species of the bee genus Peponapis, with a key to the North and Central American species (Hymenoptera: Apidae: Eucerini Dos especies nuevas de abejas del género Peponapis, con una clave para las especies de América del Norte y Central (Hymenoptera: Apidae: Eucerini

    Directory of Open Access Journals (Sweden)

    Ricardo Ayala

    2012-06-01

    Full Text Available Two new species of squash bees, Peponapis pacifica Ayala and Griswold sp. n. and P. parkeri Griswold and Ayala sp. n., are described and illustrated. Peponapis pacifica is oligolectic on flowers of Schizocarpum longisepalum (Cucurbitaceae endemic to Mexico, where it is found in the tropical dry forest along the Pacific Coast, between Sonora and Chiapas and in the Balsas River basin; and P. parkeri is known only from the Pacific slope of Costa Rica. A key for the North and Central American species of Peponapis is provided.Se describen e ilustran 2 especies nuevas de abejas, Peponapis pacifica Ayala and Griswold sp. n. y P. parkeri Griswold and Ayala sp. n. De éstas, P. pacifica es oligoléctica sobre flores de Schizocarpum longisepalum (Cucurbitaceae, endémica de México, con distribución asociada al bosque tropical caducifolio a lo largo de la vertiente del Pacífico entre Sonora y Chiapas y en la Cuenca del río Balsas; P. parkeri es conocida sólo para la vertiente del Pacífico de Costa Rica. Se incluye una clave para las especies de América del norte y central.

  19. Direct observation of 134Cs and 137Cs in surface seawater in the western and central North Pacific after the Fukushima Dai-ichi nuclear power plant accident

    Directory of Open Access Journals (Sweden)

    H. Kaeriyama

    2013-06-01

    Full Text Available The horizontal distribution of radioactive cesium (Cs derived from the Fukushima Dai-ichi nuclear power plant (FNPP in the North Pacific is still unclear due to the limitation of direct measurement of the seawater in the open ocean. We present the result of direct observation of radioactive Cs in surface seawater collected from a broad area in the western and central North Pacific in July 2011, October 2011 and July 2012. We also conducted a simple particle tracking experiment to estimate the qualitative spatial distribution of radioactive Cs in the North Pacific. 134Cs was detected at 94 stations out of 123 stations, and 137Cs was detected at all stations. High 134Cs and 137Cs concentrations more than 10 m Bq kg−1 were observed in the area of the northern part of Kuroshio Extension at 144° E and 155° E in July 2011, in the area 147–175° E around 40° N in October 2011, and the northern part of Kuroshio Extension at 155° E and 175°30´ E in July 2012. Combining the result of direct observations and particle tracking experiment, the radioactive Cs derived from the FNPP had been dispersed eastward to the central North Pacific during 2011. It was considered from the horizontal distribution that radioactive Cs was dispersed not only eastward but also north- and southward in the central North Pacific. Pronounced dilution process of radioactive Cs from the FNPP during study period is suggested from temporal change in the activity ratio of 134Cs / 137Cs, which was decay-corrected on 6 April 2011, and relationships between radioactive Cs and temperature.

  20. Aplicación del formato Dublin Core para la descripción de los recursos en la biblioteca virtual del CDICT- Universidad Central de Las Villas (Cuba

    Directory of Open Access Journals (Sweden)

    Lic. Ramón A. Manso Rodríguez

    2002-01-01

    Full Text Available Tomando en consideración el aumento de literatura en soporte electrónico y como parte del desarrollo de sus sistemas automatizados de gestión bibliotecaria, el Centro de Documentación e Información Científico – Técnica de la Universidad Central de Las Villas, Santa Clara, Cuba, construyó su biblioteca virtual utilizando los campos especificados en el formato Dublin Core, para la descripción de los recursos que se le incorporarían al sistema. En este trabajo damos una breve panorámica de la utilización del mismo, además de un análisis conceptual sobre el termino biblioteca virtual

  1. Acordos de paz para a América Central nos anos 1980: a busca pela solução negociada 10.5102/uri.v13i1.3088

    OpenAIRE

    Vanessa Braga Matijascic

    2015-01-01

    As negociações de paz na América Central nos anos 1980 envolveram uma série de iniciativas diplomáticas que contemplaram o Grupo de Contadora e o Grupo de Apoio a Contadora, o grupo de países de Tegucigalpa e, por fim, o desfecho proposto pelas cúpulas centro-americanas. No contexto da política externa de Ronald Reagan foi de extrema importância a iniciativa dos países de Contadora para evitar a primazia da solução proposta pelos Estados Unidos, que era o desfecho da vitória militar perante ...

  2. Análise de viabilidade econômica financeira para a implantação de uma central de massa em uma indústria cerâmica de Itaboraí, RJ

    OpenAIRE

    Da Silva, A.C.; A. J. C. Pithon; Fernandes, J. L.; L. M. dos Santos

    2014-01-01

    Este trabalho apresenta um estudo de viabilidade econômico financeira para a implantação de uma central de massa, com o objetivo de preparar a argila antes do processo produtivo, utilizando-se de técnicas adequadas e apropriadas, que proporcionam economia de matéria-prima, redução do consumo de energia elétrica, redução do consumo de energia térmica, aumento da produtividade, entre outros benefícios. Foram realizadas simulações em três tipos de cenários: pessimista, mais provável e otimista. ...

  3. SISTEMA DE CENTRALIZACIÓN DE ALARMAS PARA LA DETECCIÓN DE FALLAS EN LAS CENTRALES TELEFÓNICAS ANALÓGICAS.

    Directory of Open Access Journals (Sweden)

    Ing. Leon Febres Andara Laclé

    2002-01-01

    Full Text Available Este estudio destaca la propuesta de aplicación de una plataforma tecnológica que a grandes rasgos cumpla con lo que hoy en día esta implantándose en países desarrollados en Telecomunicaciones como lo es la Televisión Digital, el cual se describe como una proyecto donde estaciones televisivas deben desarrollar una red digital para integrar los servicios que benefician a toda la comunidad. Es importante destacar que, la transmisión de este tipo de señal viene determinada a través de frecuencias satelitales las cuales producen la ganancia máxima de este tipo de proyecto, puesto que permite la transmisión de paquetes de videos o datos, lo cual es lo viable en este proyecto.

  4. Gaussian plume model for the SO{sub 2} in a thermoelectric power plant; Modelo de pluma gaussiano para el SO{sub 2} en una central termoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Reyes L, C.; Munoz Ledo, C. R. [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1992-12-31

    The Gaussian Plume Model is an analytical extension to simulate the dispersion of the SO{sub 2} concentration at ground level as a function of the emission changes in the spot sources, as well as the pollutant dispersion in the Wind Rose, when the necessary parameters are fed. The model was elaborated in a personal computer and the results produced are generated in text form. [Espanol] El modelo de pluma gaussiano es una extension analitica para simular la dispersion de las concentraciones de SO{sub 2} a nivel del piso en funcion de los cambios de las emisiones en las fuentes puntuales, asi como, la dispersion del contaminante en la rosa de los vientos cuando se le alimentan los parametros necesarios. El modelo fue elaborado en una computadora personal y los resultados que proporciona los genera en modo texto.

  5. Application of six sigma to reloads design of the Laguna Verde Central with length until 17 days; Aplicacion de seis sigma para disenar recargas de la Central Laguna Verde con duracion hasta de 17 dias

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa G, J.M. [Comision Federal de Electricidad, Central Laguna Verde, Subgerencia General de Operacion, Planeacion, Veracruz (Mexico)]. e-mail: mespinos@cfe.gob.mx

    2007-07-01

    The more important value in the Laguna Verde Central it is the safety. The international experience it confirms us that the more safe plants its are those more productive, this conclusion and reasoning indicate to the power station that we are in the correct road, improving the acting we will obtain that greater interest for us in the Laguna Verde Central (to increase the safety) and as added value to be able to be one of the best business for the Federal Commission of Electricity. With a future vision and commitment of high acting was integrated in an external place to all the area headquarters: (Maintenance, Planning, Operation, Parts of Reserve, Finances, Contracts, Supplies, Warehouse, design Engineering, place Engineering, engineering of systems, radiological Protection, etc.) to carry out a combined work with the unique challenge of drifting with the biggest level detail the program of a recharge and certainly to get ready to achieve their execution (all this without omitting any consideration for smaller or simpler than it seemed), looking for high quality in the works, with and bigger level of safety, with the minimum possible dose, the more reasonable cost and considering a new concept of human character, to achieve the above-mentioned without the participant personnel's stress, with the premise that a good plan and commitment of all the only one that it can bring us as result it is the success of the whole organization. (Author)

  6. Soropositividade para Mycoplasma hyopneumoniae em suínos abatidos em frigoríficos da região central do estado de São Paulo

    Directory of Open Access Journals (Sweden)

    A.F. Vicente

    2013-12-01

    Full Text Available Mycoplasma hyopneumoniae is the etiologic agent of enzootic pneumonia in pigs and causes large economic losses in the swine industry. There is little data on the positivity of this disease in Brazil. The objective of this study was to evaluate the seropositivity for this agent in 200 serum samples collected from pigs in a slaughterhouse located in the central region of São Paulo. A high percentage (52% of positivity was found indicating the presence of the agent and the need to implement control measures.

  7. La restricción intertemporal del presupuesto. Una evaluación empírica para el Gobierno Nacional Central de Colombia, 1950-2010

    Directory of Open Access Journals (Sweden)

    Hernando Chaves Álvaro

    2003-12-01

    Full Text Available En este documento se analiza la sostenibilidad fiscal del Gobierno Nacional Central en Colombia utilizando el enfoque de la Restricción Intertemporal de Presupuesto. Los resultados empíricos revelan que la estrategia fiscal actual es sostenible. No obstante, se vislumbran problemas de insolvencia en el largo plazo, lo que implica generar un mayor superávit primario en comparación con el actualmente programado. Lo anterior, se sustenta en los valores estimados de los indicadores de sostenibilidad fiscal.

  8. Water Deuteration and Ortho-to-Para Nuclear Spin Ratio of H2 in Molecular Clouds Formed via Accumulation of HI Gas

    CERN Document Server

    Furuya, K; Hincelin, U; Hassel, G E; Bergin, E A; Vasyunin, A I; Herbst, Eric

    2015-01-01

    We investigate the water deuteration ratio and ortho-to-para nuclear spin ratio of H2 (OPR(H2)) during the formation and early evolution of a molecular cloud, following the scenario that accretion flows sweep and accumulate HI gas to form molecular clouds. We follow the physical evolution of post-shock materials using a one-dimensional shock model, with post-processing gas-ice chemistry simulations. This approach allows us to study the evolution of the OPR(H2) and water deuteration ratio without an arbitrary assumption concerning the initial molecular abundances, including the initial OPR(H2). When the conversion of hydrogen into H2 is almost complete, the OPR(H2) is already much smaller than the statistical value of three due to the spin conversion in the gas phase. As the gas accumulates, the OPR(H2) decreases in a non-equilibrium manner. We find that water ice can be deuterium-poor at the end of its main formation stage in the cloud, compared to water vapor observed in the vicinity of low-mass protostars w...

  9. Development of a methodology for the economical analysis of fuel cycles, application to the Laguna Verde central; Desarrollo de una metodologia para el analisis economico de ciclos de combustible, aplicacion a la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Malfavon, S.M.; Trejo, M.G.; Hernandez, H. [FI-UNAM, 04500 Mexico D.F. (Mexico); Francois, J.L.; Ortega, R.F. [FI-UNAM, Paseo Cuauhnahuac 8532, Jiutepec, Morelos (Mexico)

    2003-07-01

    In this work a methodology developed to carry out the economical analysis of the fuel cycle of a nuclear reactor is presented. The methodology was applied to the Laguna Verde Nuclear Power Station (CNLV). The design of the reload scenarios of the CNLV are made with the Core Master Presto code (CM-Presto), three-dimensional simulator of the reactor core, the launched data by this, as well as the information of the Energy use plan (PUE), it allowed us to obtain reliable results through the fitness of an algorithm of economic calculation that considers all the components of the fuel cycle to present worth. With the application of the methodology it was obtained the generated energy, as well as their respective cost of each sub lot type of assemblies by operation cycle, from the start-up of the CNLV until September 13, 2002. Using the present worth method its were moved all the values at November 5, 1988, date of operation beginning. To the final of the analysis an even cost of 6.188 mills/kWh was obtained for those first 9 cycles of the Unit 1 of the CNLV, being observed that the costs of those first 3 operation cycles are the more elevated. Considering only the values starting from the cycle 4, the levelled cost turns out to be of 5.96 mills/kWh. It was also obtained the cost by fuel lot to evaluate the performance of assemble with the same physical composition. (Author)

  10. Environmental Decrease of 137Cs-Activity Concentration in Milk in Central Europe After a Nuclear Fallout - A Comparison

    International Nuclear Information System (INIS)

    Full text: After a major contamination of a territory due to fallout from a reactor accident, a reprocessing plant accident or a weapon's detonation, one of the important questions to be addressed is the period required for the countermeasures to be applied. This is particularly important for countermeasures with high costs and consequences to the involved population such as relocation or a prohibition to consume local foodstuff. In that respect, the time required for a contamination with long-lived fission products to decrease below established intervention levels by natural processes of decay and removal from the soil layer is relevant. Therefore, the decrease in activity concentration in milk and other foodstuffs is investigated in several central-European countries and compared to each other. The decrease of activity concentration in the most important foodstuff is very similar in all these countries indicating that this decrease by natural effects is a universal effect typical for agricultural soils. Typically, in the first three years an effective half-life for 137Cs of 1 y, in the following years one of 5 y is observed. Including the first-to-second year decrease this results in a rapid decrease by about three orders of magnitude within a decade after fallout. Implications to long-term counter measures are discussed. (author)

  11. Confronting fluctuations of conserved charges in central nuclear collisions at the LHC with predictions from Lattice QCD

    CERN Document Server

    Braun-Munzinger, P; Redlich, K; Stachel, J

    2016-01-01

    We construct net baryon number and strangeness susceptibilities as well as correlations between electric charge, strangeness and baryon number from experimental data on the particle production yields at midrapidity of the ALICE Collaboration at CERN. The data were taken in central Pb-Pb collisions at $\\sqrt{s_{\\rm NN}}$~=~2.76~TeV and cover one unit of rapidity. We show that the resulting fluctuations and correlations are consistent with Lattice QCD results at the chiral crossover pseudocritical temperature $T_{c} \\simeq$ 155 MeV. This agreement lends strong support to the assumption that the fireball created in these collisions is of thermal origin and exhibits characteristic properties expected in QCD at the transition from the quark gluon plasma to the hadronic phase. Since Lattice QCD calculations are performed at a baryochemical potential of $\\mu_{B}$ = 0, the comparisons with LHC data are the most direct due to the vanishing baryon transport to midrapidity at these high energies.

  12. Multielemental analysis of soil samples from the Assin District of Central Region in Ghana using nuclear and related techniques

    International Nuclear Information System (INIS)

    Macronutrients, micronutrients, pH, salinity and moisture content were determined in soil samples from six farms in two farming towns in Assin North District in the Central Region of Ghana namely Assin Akonfudi and Assin Bereku. Soil samples were taken from cocoa farms, orange farms and palm oil plantations at three different depths. The nutrients determined were Primary macronutrients that was K, Secondary macronutrients that were Ca, Mg and Micronutrients that were, Cl, Co, Cu, Fe, Mn, Mo, Zn, Na and Se and Neutron Activation method and Atomic Absorption Spectrometry were used for the elemental analysis. The pHs were within the acidic range, ranging from 4.50-6.44. The top soil (0-5cm) had the higher pH followed by soil at the depth of 5-30cm and then soil at the depth of 30-40cm that is the pH decreased with depth. The salinity rather increased with depth ranging from 0.3l-2.98dS/m and the moisture content also ranged from 0.5-2.04%. For the soil samples taken from the cocoa farms, K recorded the highest concentration and Mo recorded the lowest concentration in the soil. For soil samples taken from orange farms, Ca recorded the highest concentration and Se recorded the lowest concentration in the soil and for soil samples taken from the palm oil plantations, Fe recorded the highest concentration and Mo recorded the lowest concentration in soil. The macronutrients ranged from 28591.19-6.49 mg/kg and the micronutrients ranged from <0.0004-20344.50 mg/kg. Soils in the cocoa farms were found to be more rich in nutrients and the soils in the palm oil plantations were found to be least rich in nutrients

  13. Actions for the environmental adequateness and emissions control at the Martin del Corral power plant-Termozipa; Obras de adecuacion ambiental y control de emisiones para la central termoelectrica Martin del Corral - Termozipa

    Energy Technology Data Exchange (ETDEWEB)

    Arevalo Osorio, Luis [Empresa de Energia de Bogota, Bogota (Colombia)

    1996-12-31

    In this paper the general data on the Martin del Corral-Termozipa, of Colombia, fossil fueled power plant are exposed. The results of a study to determine the environmental impact originated in the influence zone of this Power Plant are presented, particularly on the Bogota River. The study was framed into the environmental policy driven by the Colombian sector. Different solutions addressed to the optimization of the handling, capacity and control of the emissions and counteract the pollution possibilities of the Bogota River are described [Espanol] En esta ponencia se exponen datos generales de la central termoelectrica Martin del Corral - Termozipa-, de Colombia. Se presentan los resultados de un estudio para determinar el impacto ambiental ocasionado en la zona de influencia de esta central, y en particular sobre el rio Bogota. El estudio se enmarco dentro de la politica ambiental impulsada por el sector colombiano. Se describen diversas soluciones encaminadas a optimizar el manejo, capacidad y control de las emisiones y contrarrestar las posibilidades de contaminacion del rio Bogota

  14. Improvements to the wastewater treatment from the beginning of the operation of Nuclear Asco; Mejoras en la depuracion de aguas residuales desde el inicio de la explotacion de la Central Nuclear de Asco

    Energy Technology Data Exchange (ETDEWEB)

    Esparza Martin, J. L.; Boronat Medico, M.

    2014-07-01

    Sanitary sewage in the Central Nuclear de Asco (CNA), are subject to a series of physico-chemical and biological processes in the wastewater waste (WWTP) before being discharged to the River Ebro. Since the beginning of the exploitation of CNA, the number of workers and administrative restrictions have evolved so that they have forced the execution of modifications of lowest and highest wingspan to comply with applicable legal requirements in the field of discharges. The overall objective of this work is to present the different stages of evolution of the WWTP of CNA from the start of operation of the plant up to the present day. The specific objective is to show the latest enhancements implanted in the sewage treatment plant and the benefits obtained. With technical improvements carried out in the WWTP of CNA, fixed the problem of disposal coming from the central nitrogen, one of the key problems and reason of failure to comply with the parameters imposed by the administration. (Author)

  15. Características de uso de plaguicidas químicos y riesgos para la salud en agricultores de la sierra central del Perú

    OpenAIRE

    Ymelda Montoro; Rocío Moreno; Luis Gomero; Maria Reyes

    2009-01-01

    Con el objetivo de conocer las características sobre el uso e impactos en la salud de los plaguicidas químicos de uso agrícola en las provincias de Chupaca y Concepción en los andes centrales del Perú, se desarrolló un estudio descriptivo transversal entre abril y junio del año 2005, por medio de un cuestionario aplicado a 435 agricultores. Asimismo, se exploró la ubicación de los centros de expendio y la frecuencia de ventas de productos, además, se evaluó los casos de intoxicación reportado...

  16. Hidrocarburos en Kazajastán: nuevas realidades y enfoques para el estudio de las relaciones energéticas de Asia Central

    OpenAIRE

    Aurèlia Mañé Estrada

    2011-01-01

    Desde 1994 se ha hablado mucho acerca del potencial de las antiguas repúblicas soviéticas de Asia Central, como exportadoras de hidrocarburos. Sin embargo, como se argumentará en el artículo, la mayoría de los análisis se basan en dos premisas obsoletas: a) que las relaciones energéticas son como las que el paradigma energético dicotómico (PED) describe - Los países productores frente a países consumidores-, y b) que la función y los objetivos de los países productores en la economía mundial ...

  17. Communication dated 30 May 2014 received from the Permanent Mission of Uzbekistan to the Agency regarding the implementation of the initiative of the President of Uzbekistan on Establishing a Nuclear-Weapon-Free Zone in Central Asia

    International Nuclear Information System (INIS)

    The Director General has received a note verbale dated 30 May 2014 from the Permanent Mission of Uzbekistan to the Agency regarding the implementation of the initiative of the President of Uzbekistan, HE Mr Islam Karimov, on Establishing a Nuclear-Weapon-Free Zone in Central Asia. The note verbale and its attachment are circulated herewith for information, as requested by the Permanent Mission

  18. Centrality dependence of the nuclear modification factor of charged pions, kaons, and protons in Pb-Pb collisions at root s(NN)=2.76 TeV

    Czech Academy of Sciences Publication Activity Database

    Adam, J.; Adamová, Dagmar; Bielčík, J.; Bielčíková, Jana; Brož, M.; Čepila, J.; Contreras, J. G.; Eyyubova, G.; Ferencei, Jozef; Křelina, M.; Křížek, Filip; Kučera, Vít; Kushpil, Svetlana; Mareš, Jiří A.; Petráček, V.; Pospíšil, Jan; Schulc, M.; Špaček, M.; Šumbera, Michal; Vajzer, Michal; Vaňát, Tomáš; Závada, Petr

    2016-01-01

    Roč. 93, č. 3 (2016), s. 034913. ISSN 0556-2813 R&D Projects: GA MŠk(CZ) LG13031 Institutional support: RVO:68378271 ; RVO:61389005 Keywords : ALICE collaboration * heavy ion collisions * centrality dependece Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders; BF - Elementary Particles and High Energy Physics (FZU-D) Impact factor: 3.733, year: 2014

  19. POBLACIÓN Y FERTILIZACIÓN NITROGENADA EN UN HÍBRIDO DE MAÍZ PARA ENSILAJE EN EL VALLE CENTRAL REGADO Planting density and nitrogen fertilization of hybrid corn for silage in the irrigated central valley

    Directory of Open Access Journals (Sweden)

    Patricio Soto O.

    2002-04-01

    Full Text Available Se evaluó el efecto de tres dosis de nitrógeno y cuatro densidades de plantas sobre el rendimiento de forraje y proteína en un híbrido tardío de maíz (Zea mays L. para ensilaje. Las densidades fueron: 70.000, 90.000, 100.000 y 130.000 plantas ha-1; y los niveles de N fueron 150, 300 y 450 kg de N ha-1, dando origen a 12 tratamientos, los que fueron establecidos en parcelas de 22,4 m². Ambos factores fueron evaluados en un diseño de bloques completos al azar con 4 repeticiones, con arreglo factorial 2 x 4. La evaluación se realizó entre los meses de octubre y marzo. Se realizó análisis de varianza y en la comparación de medias se usó la prueba de Duncan y curvas de regresión. Los resultados muestran que al aumentar la cantidad de N aplicado al maíz, se incrementa el rendimiento de forraje y de proteína por hectárea. Este incremento fue de 3,8 t MS ha-1 al pasar de 150 a 300 kg de N ha-1 aplicado y 2,0 t MS ha-1 al aumentar de 300 a 450 kg de N ha-1. El incremento de la densidad de plantas produce un aumento en la producción de forraje por hectárea, mientras que la producción de proteína no sufre variación. El aumento de la fertilización nitrogenada incrementa el contenido de proteína del forraje. Los niveles más altos de aplicación de N presentaron una menor eficiencia (74% en el uso de este elemento comparado con 94% con una aplicación de 150 kg N ha-1 , mientras que las pérdidas de N presentaron el efecto contrario. El aumento en los niveles de fertilización nitrogenada provocaron la disminución del porcentaje de hojas secas en las plantas variando entre 44 y 28 % para una fertilización de 150 y 450 kg N ha-1 , respectivamente.The effect of three nitrogen fertilization rates and four planting densities on dry matter and protein yield of silage corn (Zea mays L. was evaluated. The densities were as follows: 70,000, 90,000, 110,000 and 130,000 plants ha-1, and the nitrogen rates: 150, 300 and 450 kg N ha-1, giving

  20. Diseño de un sistema de gestión de calidad para la división de microscopía electrónica del servicio central de ciencia y tecnología de la Universidad de Cádiz

    OpenAIRE

    2005-01-01

    El objetivo de este proyecto ha sido elaborar un Sistema de Gestión de Calidad para la División de Microscopía Electrónica (DME) del Servicio Central de Ciencia y Tecnología (SCCYT) de la Universidad de Cádiz (UCA).

  1. Valoración de la aptitud física en niños y adolescentes: construcción de cartas percentílicas para la región central del Perú Evaluation of physical fitness levels in children and adolescents: establishing percentile charts for the central region of Peru

    Directory of Open Access Journals (Sweden)

    Alcibíades Bustamante

    2012-06-01

    Full Text Available Objetivos. Establecer cartas percentílicas y valores de referencia estratificada por edad y sexo de los niveles de aptitud física (AF en niños y adolescentes de la región central del Perú. Materiales y métodos. El tamaño de la muestra comprendió a 7843 escolares (4155 mujeres y 3688 varones entre los seis y los diecisiete años de edad. Los niveles de aptitud física fueron evaluados mediante el uso de seis pruebas motoras provenientes de las baterías EUROFIT, FITNESSGRAM y AAPHERD. Las cartas percentílicas fueron construidas por separado para cada sexo, utilizando el método matemático LMS implementado en el programa LMSchartmaker. Resultados. Se verifica valores superiores de AF en los varones, a excepción de la prueba de flexibilidad; la AF incrementa con la edad. Conclusiones. Existe variabilidad interindividual en ambos sexos. Los valores de referencia específicos por edad y sexo pueden utilizarse para la evaluación e interpretación de los niveles de AF de niños y adolescentes de la región central del Perú. Estos hallazgos pueden ayudar en la evaluación de programas de educación física en las escuelas.Objectives. Construct percentile charts and physical fitness (PF reference values stratified by age and sex of children and adolescents from Peru’s central region. Materials and methods. The sample was comprised of 7,843 subjects (4,155 females and 3,688 males between the ages of 6 to 17 years old. Physical fitness was assessed using six tests developed by EUROFIT, FITNESSGRAM and AAPHERD. Percentile charts were developed separately for males and females using the LMS method calculated with LMSchartmaker software. Results. Males showed higher PF values with the exception of flexibility; a clear increase in PF with increasing age was verified. Conclusions. Inter-individual variability in both sexes is substantial. Charts and specific reference values by age and sex may be used for the assessment and interpretation of

  2. Designing and Implementing an OVERFLOW Reader for ParaView and Comparing Performance Between Central Processing Units and Graphical Processing Units

    Science.gov (United States)

    Chawner, David M.; Gomez, Ray J.

    2010-01-01

    In the Applied Aerosciences and CFD branch at Johnson Space Center, computational simulations are run that face many challenges. Two of which are the ability to customize software for specialized needs and the need to run simulations as fast as possible. There are many different tools that are used for running these simulations and each one has its own pros and cons. Once these simulations are run, there needs to be software capable of visualizing the results in an appealing manner. Some of this software is called open source, meaning that anyone can edit the source code to make modifications and distribute it to all other users in a future release. This is very useful, especially in this branch where many different tools are being used. File readers can be written to load any file format into a program, to ease the bridging from one tool to another. Programming such a reader requires knowledge of the file format that is being read as well as the equations necessary to obtain the derived values after loading. When running these CFD simulations, extremely large files are being loaded and having values being calculated. These simulations usually take a few hours to complete, even on the fastest machines. Graphics processing units (GPUs) are usually used to load the graphics for computers; however, in recent years, GPUs are being used for more generic applications because of the speed of these processors. Applications run on GPUs have been known to run up to forty times faster than they would on normal central processing units (CPUs). If these CFD programs are extended to run on GPUs, the amount of time they would require to complete would be much less. This would allow more simulations to be run in the same amount of time and possibly perform more complex computations.

  3. Regionalização das temperaturas mínimas do ar prejudiciais à fecundação das flores de arroz para a região climática da depressão central, RS Minimum air temperatures probabilities harmful to the fecundation of rice flowers in the central region of Rio Grande do Sul, Brazil

    OpenAIRE

    Galileo Adeli Buriol; Valduíno Estefanel; Sílvio Steinmetz; Jacques Leandro Schvambach; Marino Antônio Didone

    2000-01-01

    Foram mapeadas as probabilidades de ocorrência de temperaturas mínimas do ar prejudiciais à fecundação das flores de arroz na Região Climática da Depressão Central do Estado do Rio Grande do Sul. Utilizaram-se os valores de probabilidade de ocorrência de temperaturas mínimas do ar iguais ou inferiores a 13, 15 e 17°C em um ou mais dias, cinco ou mais dias e dei ou mais dias para os meses de dezembro, janeiro, fevereiro e março. As isolinhas de probabilidade foram traçadas em um mapa ipsom...

  4. Development of a methodology for nuclear data uncertainty propagation on isotopic evolution calculations for advanced nuclear systems

    OpenAIRE

    Diez de la Obra, Carlos Javier

    2014-01-01

    Una apropiada evaluación de los márgenes de seguridad de una instalación nuclear, por ejemplo, una central nuclear, tiene en cuenta todas las incertidumbres que afectan a los cálculos de diseño, funcionanmiento y respuesta ante accidentes de dicha instalación. Una fuente de incertidumbre son los datos nucleares, que afectan a los cálculos neutrónicos, de quemado de combustible o activación de materiales. Estos cálculos permiten la evaluación de las funciones respuesta esenciales para el funci...

  5. Water dynamics on ice and hydrate lattices studied by second-order central-line stimulated-echo oxygen-17 nuclear magnetic resonance

    International Nuclear Information System (INIS)

    Oxygen-17 stimulated-echo spectroscopy is a novel nuclear magnetic resonance (NMR) technique that allows one to investigate the time scale and geometry of ultraslow molecular motions in materials containing oxygen. The method is based on detecting orientationally encoded frequency changes within oxygen’s central-transition NMR line that are caused by second-order quadrupolar interactions. In addition to the latter, the present theoretical analysis of various two-pulse echo and stimulated-echo pulse sequences takes also heteronuclear dipolar interactions into account. As an experimental example, the ultraslow water motion in polycrystals of tetrahydrofuran clathrate hydrate is studied via two-time oxygen-17 stimulated-echo correlation functions. The resulting correlation times and those of hexagonal ice are similar to those from previous deuteron NMR measurements. Calculations of the echo functions’ final-state correlations for various motional models are compared with the experimental data of the clathrate hydrate. It is found that a six-site model including the oxygen-proton dipolar interaction describes the present results

  6. Water dynamics on ice and hydrate lattices studied by second-order central-line stimulated-echo oxygen-17 nuclear magnetic resonance

    Science.gov (United States)

    Adjei-Acheamfour, Mischa; Tilly, Julius F.; Beerwerth, Joachim; Böhmer, Roland

    2015-12-01

    Oxygen-17 stimulated-echo spectroscopy is a novel nuclear magnetic resonance (NMR) technique that allows one to investigate the time scale and geometry of ultraslow molecular motions in materials containing oxygen. The method is based on detecting orientationally encoded frequency changes within oxygen's central-transition NMR line that are caused by second-order quadrupolar interactions. In addition to the latter, the present theoretical analysis of various two-pulse echo and stimulated-echo pulse sequences takes also heteronuclear dipolar interactions into account. As an experimental example, the ultraslow water motion in polycrystals of tetrahydrofuran clathrate hydrate is studied via two-time oxygen-17 stimulated-echo correlation functions. The resulting correlation times and those of hexagonal ice are similar to those from previous deuteron NMR measurements. Calculations of the echo functions' final-state correlations for various motional models are compared with the experimental data of the clathrate hydrate. It is found that a six-site model including the oxygen-proton dipolar interaction describes the present results.

  7. Water dynamics on ice and hydrate lattices studied by second-order central-line stimulated-echo oxygen-17 nuclear magnetic resonance

    Energy Technology Data Exchange (ETDEWEB)

    Adjei-Acheamfour, Mischa; Tilly, Julius F.; Beerwerth, Joachim; Böhmer, Roland [Fakultät Physik, Technische Universität Dortmund, 44221 Dortmund (Germany)

    2015-12-07

    Oxygen-17 stimulated-echo spectroscopy is a novel nuclear magnetic resonance (NMR) technique that allows one to investigate the time scale and geometry of ultraslow molecular motions in materials containing oxygen. The method is based on detecting orientationally encoded frequency changes within oxygen’s central-transition NMR line that are caused by second-order quadrupolar interactions. In addition to the latter, the present theoretical analysis of various two-pulse echo and stimulated-echo pulse sequences takes also heteronuclear dipolar interactions into account. As an experimental example, the ultraslow water motion in polycrystals of tetrahydrofuran clathrate hydrate is studied via two-time oxygen-17 stimulated-echo correlation functions. The resulting correlation times and those of hexagonal ice are similar to those from previous deuteron NMR measurements. Calculations of the echo functions’ final-state correlations for various motional models are compared with the experimental data of the clathrate hydrate. It is found that a six-site model including the oxygen-proton dipolar interaction describes the present results.

  8. "CEZAC 06": nueva variedad de ajo tipo Jaspeado para la región norte centro de México "CEZAC 06": new Jaspeado garlic cultivar for the northem-central region of Mexico

    Directory of Open Access Journals (Sweden)

    Manuel Reveles-Hernández

    2011-08-01

    Full Text Available Alrededor de 5 200 hectáreas de ajo son cultivadas en México donde la región norte centro, es una de las principales áreas productoras de esta hortaliza. La falta de variedades de ajo localmente adaptadas es una seria desventaja para los productores de ajo. En este reporte se mencionan las principales características agronómicas de "CEZAC 06", una nueva variedad de ajo disponible para los productores de los estados de Zacatecas, Aguascalientes, Durango, Chihuahua y Coahuila. Las principales ventajas de esta variedad son rendimientos más altos, bulbos consistentemente redondos, menor número de dientes por bulbo y maduración homogénea. En parcelas comerciales el rendimiento se ha mejorado en 9-17% y se han alcanzado rendimientos de hasta 30 t ha-1 con el uso de "CEZAC 06".About 5 200 hectares of garlic are cultivated in Mexico; the north-central region is one of the main producing areas of this vegetable. The lack of locally adapted varieties of garlic is a serious disadvantage for garlic producers. In this paper are mentioned the main agronomic characteristics of "CEZAC 06", a new garlic variety available for producers of Zacatecas, Aguascalientes, Durango, Chihuahua and Coahuila. The main advantages of this variety are higher yield, consistently round bulbs, fewer numbers of cloves per bulb and homogeneous maturation. In commercial plots, yield has improved in 9-17% and there have been achieved yields of up to 30 t ha-1 using "CEZAC 06".

  9. Possibilities and limitations of analogue methods for studying the dynamics of nuclear power stations; Possibilites et limitations du calcul analogique pour les etudes dynamiques de centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Caillet, C.; Deat, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    1. Introduction: the present paper is devoted to analog simulation of problems related to nuclear reactors other than the simulation of the kinetic equations which is well known. 2. Thermodynamic problems: various problems relative to temperature evolution in a reactor, in a pipe, in an exchanger, in a turbine, are studied, and simulation techniques used by earlier authors are critically reviewed. 3. Pipe simulators: it is shown that this problem can be solved by the use of specialized simulators which will be described and analysed. 4. Rotating machine simulators: the particular aspect of rotating machine calculations introducing frequent use of diagrams is emphasized. A simulator requiring both digital and analogue methods is described. 5. The study of a nuclear power station: as an example it is proposed to discuss problems a rising in connection with the preceding elements (a, b, c, d) when simulating the behaviour of large nuclear plants. The part played by ordinary computing elements for the simulation of the different servomechanism transfer functions is considered and process of regulation is outlined. 6. Conclusion: the necessity of the use of high quality simulators and computers is underlined and the accuracy of the solutions is discussed. (author)Fren. [French] 1. Cinetique des reacteurs: la simulation des equations cinetiques d'un reacteur nucleaire ne pose desormais plus de probleme. II est donc possible de faire le point des differentes applications de la technique analogique dans ce domaine. 2. Les problemes thermodynamiques: on discute les differents problemes poses par l'evolution des temperatures dans un reacteur, dans une tuyauterie, dans un echangeur, dans une turbine, et on passe en revue les techniques de simulation proposees jusqu'a ce jour. 3s simulateurs de tuyauteries: on montre comment les differents problemes poses ci-dessus peuvent etre resolus, pour une classe tres vaste de reacteurs par l'emploi de simulateurs

  10. La vertebración territorial en regiones de alta especialización: Valle Central de Chile. Alcances para el desarrollo de zonas rezagadas en torno a los recursos naturales

    Directory of Open Access Journals (Sweden)

    ALBERTO GARCÍA-HUIDOBRO

    2010-04-01

    Full Text Available Los procesos de reestructuración económica y la apertura de los mercados han generado múltiples y variadas consecuencias sobre nuestros territorios. Quizás para Chile, como para otros países latinoamericanos, uno de los más importantes procesos a nivel regional es el desarrollo de espacios altamente especializados o regiones-commodities. Distintos trabajos académicos señalan que interiormente, en conjunto con áreas de gran competitividad, se están generando áreas rezagadas o alejadas de los dinamismos económicos. Por lo tanto: ¿ En qué ha derivado su modelo de vertebración territorial y su sistema de centros poblados ? ¿Cuáles son las características de estas áreas rezagadas ? Y por ende, ¿cuáles son los desafíos a los cuales se enfrentan? El Valle Central de Chile es una de estas áreas donde se evidencia dicha especialización. Por tanto, analizaremos la estructura física territorial en las que han derivado estas regiones y el papel que cumplen sus centros poblados en los nuevos escenarios. A partir de la caracterización de su vertebración territorial avanzaremos hacia la definición de sus zonas menos favorecidas, e intentaremos generar algunas hipótesis que respondan a sus desafíos y requerimientos futuros.Economic restructuring processes and market opening have generated multiple and varied consequences in our territories. Perhaps for Chile, as with other Latin American countries, one of the most important processes at the regional level is the development of highly specialized spaces or commodity-regions. Different academic work indicates that within these spaces, as well as areas of high competitiveness, there are also backward areas with limited economic dynamism. Consequently: What has happened to the model of a territorial spine and system of population center? What are the characteristics of these backward areas? In addition, what are the challenges to be faced? Chile's Central Valley is one of the areas

  11. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states

    International Nuclear Information System (INIS)

    This report deals with two different aspects of the safety and security of nuclear facilities. The first aspect concerns the reconversion of weapon grade plutonium stocks: the plutonium in excess, plutonium hazards and nuclear fuel potentialities, the US program, the Russian program, the actions of European countries (France, Germany), the intervention of other countries, the unanswered questions (political aspects, uncertainties), the solutions of the future (improvement of reactors, the helium-cooled high temperature reactor technology (gas-turbine modular helium reactor: GT-MHR), the Carlo Rubbia's project). The second aspect concerns the actions carried out by the European Union in favor of the civil nuclear facilities of central and eastern Europe: the European Union competencies through the Euratom treaty, the conclusions of the European audit office about the PHARE and TACIS nuclear programs, the status of committed actions, the coming planned actions, and the critical analysis of the policy adopted so far. (J.S.)

  12. Acciones educativas dirigidas al personal médico y de enfermería para disminuir las infecciones del tracto sanguíneo relacionadas a catéteres venosos centrales

    Directory of Open Access Journals (Sweden)

    Milena Villegas Sánchez

    2014-10-01

    Full Text Available Introducción. La bacteriemia relacionada a Catéter Venoso  Central  es una de las principales complicaciones en los pacientes a quienes se les instala un catéter intravascular. Las acciones educativas han mostrado disminución en la tasa de estas infecciones en diferentes estudios.  El objetivo fue determinar la tasa de Infecciones del tracto sanguíneo relacionadas al catéter venoso central (ITS/CVC, en el Servicio de Cuidado Intensivo Neonatal, implementar las acciones preventivas y cuantificar el impacto.Metodología. Es un estudio descriptivo en donde se compara la tasa de ITS/CVC, antes y después de una intervención educativa, en  los pacientes ingresados a SECIN.  La tasa de ITS/CVC  se obtuvo dividiendo el número de éstas entre el número de días-catéter y se multiplicó por 1 000.Resultado. Un resultado relevante es que en el periodo  pre intervención se observa una  tasa  de 32,84 infecciones por 1 000 días (cuarto trimestre del 2012 y primer trimestre del 2013  y en el periodo post intervención la tasa fue de 8,28 infecciones por 1 000 días. (Tercer trimestre y cuarto trimestre del 2013.Conclusión. Se concluye que las acciones educativas para disminuir la tasa de ITS/CVC fueron efectivas.

  13. Equações de volume para Eucalyptus dunnii Maiden, determinadas para a depressão central do Estado do Rio Grande do Sul Equations for Eucalyptus dunnii maiden volume determination on the central depression of State Rio Grande do Sul

    Directory of Open Access Journals (Sweden)

    Paulo Renato Schneider

    1997-08-01

    Full Text Available O estudo foi realizado para definir equações de volume total com casca e comercial sem casca para Eucalyptus dunnii Maiden, na idade de 6,5 anos, implantado em espaçamento 3 x 2m. Foram cubadas, pelo método de Smaliam, 80 árvores distribuídas em classe diamétrica e de forma proporcional em quatro hortos florestais. As equações de volume total com casca e comercial sem casca foram determinadas através do procedimento "stepwise" de regressão, de forma independente, para cada local e, posteriormente, foi estudada a possibilidade de agrupamento destas equações em um modelo único. A análise de covariância aplicada aos dados indicou a possibilidade do emprego de uma única equação para estimar o volume da espécie em toda a região. Selecionou-se pelo alto coeficiente de determinação e baixo erro padrão da estimativa a equação log v = - 9,06566 + 0,93016 . log(d² h para o volume total com casca e log v = -14,14078 + 1,39608 . log(d² h para o volume comercial sem casca. Além disso, não observou-se diferenças na forma do tronco e por conseqüência no volume das árvores nos quatro locais estudados.This study has been carried out to define total bulk volume equations for Eucalyptus dunni Maiden, 6.5 years old, lined up along a 3 by 2 meter-spaced planted setting. These equations were supposed to both trees with and without bark. Eighty trees were cubed by Smalian's method distributed according to diameter classes and following a proportional way, over four forest sites. Equations were determinated through stepwise regression procedure, following an independent process for each site. A second step was evaluate the possiblility of these equations to be reduced into a single one. The covariance analysis applied to data showed the possibility of using an unique one equation to estimate the tree bulk volume to the region. Two equations were selected: one to calculate the total volume of trees with bark and another to determine the

  14. Propuesta para la recuperación de los machetes Zuazaga de los centrales azucareros con electrodos de acero al cromo. // Proposal for Recuperation of Sugar Mill Cut Cane by Using Chromium Steel Electrodes.

    Directory of Open Access Journals (Sweden)

    R. Collazo-Carceller

    2009-09-01

    Full Text Available El trabajo resume el estudio y análisis desarrollado, para la presentación de una propuestatecnológica de recuperación de los machetes Zuazaga, en nuestros centrales azucareros. Sedeterminó la influencia de los parámetros, energía introducida (Hi, número de capas (Nc y anchodel depósito (Ad, en la morfología y el incremento de la resistencia al desgaste abrasivo, utilizandoel electrodo de acero al cromo DUR 600. Se realizó una valoración económica de la propuestatecnológica.Palabras claves: morfología, desgaste abrasivo, parámetro de soldadura, dendrites._____________________________________________________________________________AbstractThis work, sumarises the study and the analisys developed, to prupose the Zuazaga cut canethecnology recuperation, in aur sugar mills. The parameters influency was determinated, Heatinput (Hi, Number of layers (Nc and the Cord whith (Ad, in the mofology and the abrasive wearresistance increase, using the cromiun steel UTP DUR - 600. The economical calculation of thethecnology was done.Key words: morphology abrasive wear, welding parameters. dendrites, modeling

  15. Nuclear Factor kappa B is central to Marek’s Disease herpesvirus induced neoplastic transformation of CD30 expressing lymphocytes in-vivo

    Directory of Open Access Journals (Sweden)

    Kumar Shyamesh

    2012-09-01

    Full Text Available Abstract Background Marek’s Disease (MD is a hyperproliferative, lymphomatous, neoplastic disease of chickens caused by the oncogenic Gallid herpesvirus type 2 (GaHV-2; MDV. Like several human lymphomas the neoplastic MD lymphoma cells overexpress the CD30 antigen (CD30hi and are in minority, while the non-neoplastic cells (CD30lo form the majority of population. MD is a unique natural in-vivo model of human CD30hi lymphomas with both natural CD30hi lymphomagenesis and spontaneous regression. The exact mechanism of neoplastic transformation from CD30lo expressing phenotype to CD30hi expressing neoplastic phenotype is unknown. Here, using microarray, proteomics and Systems Biology modeling; we compare the global gene expression of CD30lo and CD30hi cells to identify key pathways of neoplastic transformation. We propose and test a specific mechanism of neoplastic transformation, and genetic resistance, involving the MDV oncogene Meq, host gene products of the Nuclear Factor Kappa B (NF-κB family and CD30; we also identify a novel Meq protein interactome. Results Our results show that a CD30lo lymphocytes are pre-neoplastic precursors and not merely reactive lymphocytes; b multiple transformation mechanisms exist and are potentially controlled by Meq; c Meq can drive a feed-forward cycle that induces CD30 transcription, increases CD30 signaling which activates NF-κB, and, in turn, increases Meq transcription; d Meq transcriptional repression or activation of the CD30 promoter generally correlates with polymorphisms in the CD30 promoter distinguishing MD-lymphoma resistant and susceptible chicken genotypes e MDV oncoprotein Meq interacts with proteins involved in physiological processes central to lymphomagenesis. Conclusions In the context of the MD lymphoma microenvironment (and potentially in other CD30hi lymphomas as well, our results show that the neoplastic transformation is a continuum and the non-neoplastic cells are actually pre

  16. El efecto zoom para relacionar los desechos líticos de un sitio y los paisajes arqueológicos de cazadores recolectores del Holoceno en la meseta central de Santa Cruz

    Directory of Open Access Journals (Sweden)

    Darío Hermo

    2003-12-01

    Full Text Available El debate acerca de la presencia de instrumentos bifaciales en contextos arqueológicos del Holoceno medio en la Meseta Central santacruceña tiene ya más de medio siglo. En el presente trabajo pretendemos realizar un aporte a esta discusión, basándonos en el análisis tecno-morfológico de desechos de talla provenientes del Componente Superior del sitio arqueológico AEP-1, de la localidad Piedra Museo. La muestra consiste en la totalidad de los desechos resultantes del trabajo sobre el sílex denominado variedad MV, cuyo afloramiento primario es la Laguna D, ubicada a 7 km de distancia en línea recta de AEP-1, otro de los sitios analizados. La metodología utilizada incluye algunos conceptos de la Arqueología del Paisaje, que nos permitieron relacionar información tan disímil como la proveniente de un sitio en estratigrafía y otro en superficie, para articular la información y someter a prueba las hipótesis generadas por otros autores para las coordenadas espaciotemporales en cuestión. Por otro lado, nos referimos a los procedimientos que permitieron el análisis de la tecnología lítica. A partir de nuevas hipótesis se realiza un «efecto zoom» para relacionarlas en los niveles local y regional con los resultados ya formulados por otros investigadores, integrando la información producida a la discusión en cuanto a la tecnología y la apropiación de materias primas líticas durante el Holoceno medio, contrastando las hipótesis planteadas en tales escalas.Discussion of the presence of bifacial tools in the archaeological contexts of the Middle Holocene from Central Plateau, Santa Cruz province, is already more than half a century old. In this paper, we intend to contribute to this discussion through the techno morphological analysis of the lithic debris from the upper component of AEP-1 site, Piedra Museo. The sample contains the total debitage from work using the silex called variety MV, whose primary source is Laguna D, 7 km

  17. Estudios de apoyo a la preparación de procedimientos de ejecución de cálculos de seguridad y operación de una central nuclear con modelos integrales de planta

    OpenAIRE

    Rodríguez Moya, Rafael

    2007-01-01

    La Sección de Ingeniería Nuclear de la Universidad Politécnica de Cataluña, ha colaborado desde 1991 con las plantas nucleares de Ascó y Vandellós con el objetivo, entre otros, de conseguir un modelo validado y documentado de estas centrales. Es por ello que se tiene como objetivo continuo y principal, la mejora y validación de estos modelos, aumentando así la calidad de los datos obtenidos. Siendo la finalidad de esta mejora obtener una óptima y más segura explotación de las p...

  18. Cesium-134 and 137 activities in the central North Pacific Ocean after the Fukushima Dai-ichi nuclear power plant accident

    Directory of Open Access Journals (Sweden)

    J. Kameník

    2013-03-01

    Full Text Available Surface seawater 134Cs and 137Cs samples were collected in the central and western North Pacific Ocean during the 1.5 yr after the Fukushima Dai-ichi nuclear power plant accident to monitor dispersion patterns of these radioisotopes towards the Hawaiian Islands. In the absence of other recent sources and due to its short half-life only those parts of the Pacific Ocean would have detectable 134Cs that were impacted by Fukushima releases. Between March and May 2011, 134Cs was not detected around the Hawaiian Islands and Guam. Here, most 137Cs activities (1.2–1.5 Bq m−3 were in the range of expected preexisting levels. Some samples north of the Hawaiian Islands (1.6–1.8 Bq m−3 were elevated above the 18-month baseline established in surface seawater in Hawaii indicating that those might carry atmospheric fallout. The 18-month time-series analysis of surface seawater from Hawaii did not reveal any seasonal variability or trends, with an average activity of 1.46 ± 0.06 Bq m−3 (Station Aloha, 17 values. In contrast, samples collected between Japan and Hawaii contained 134Cs activities in the range of 1–4 Bq m−3 and 137Cs levels were about 2–3 times above the preexisting activities. We found that the southern boundary of the Kuroshio and Kuroshio extension currents represented a boundary for radiation dispersion with higher activities detected within and north of the major currents. The radiation plume has not been detected over the past 1.5 yr at the main Hawaiian Islands due to the transport patterns across the Kuroshio and Kuroshio extension currents.

  19. Cesium-134 and 137 activities in the central North Pacific Ocean after the Fukushima Dai-ichi Nuclear Power Plant accident

    Directory of Open Access Journals (Sweden)

    J. Kameník

    2013-09-01

    Full Text Available Surface seawater 134Cs and 137Cs samples were collected in the central and western North Pacific Ocean during the 2 yr after the Fukushima Dai-ichi Nuclear Power Plant accident to monitor dispersion patterns of these radioisotopes towards the Hawaiian Islands. In the absence of other recent sources and due to its short half-life, only those parts of the Pacific Ocean would have detectable 134Cs values that were impacted by Fukushima releases. Between March and May 2011, 134Cs was not detected around the Hawaiian Islands and Guam. Here, most 137Cs activities (1.2–1.5 Bq m–3 were in the range of expected preexisting levels. Some samples north of the Hawaiian Islands (1.6–1.8 Bq m–3 were elevated above the 23-month baseline established in surface seawater in Hawaii indicating that those might carry atmospheric fallout. The 23-month time-series analysis of surface seawater from Hawaii did not reveal any seasonal variability or trends, with an average activity of 1.46 ± 0.06 Bq m–3 (Station Aloha, 18 values. In contrast, samples collected between Japan and Hawaii contained 134Cs activities in the range of 1–4 Bq m–3, and 137Cs levels were about 2–3 times above the preexisting activities. We found that the southern boundary of the Kuroshio and Kuroshio extension currents represented a boundary for radiation dispersion with higher activities detected within and north of the major currents. The radiation plume has not been detected over the past 2 yr at the main Hawaiian Islands due to the transport patterns across the Kuroshio and Kuroshio extension currents.

  20. Construção de uma coleção nuclear de arroz para o Brasil Constructing a rice core collection for Brazil

    Directory of Open Access Journals (Sweden)

    Tabare Abadie

    2005-02-01

    Full Text Available A coleção de germoplasma de arroz da Embrapa consiste aproximadamente de 10.000 acessos. O objetivo desse trabalho foi estabelecer a Coleção Nuclear (CN dessa coleção utilizando as informações e dados disponíveis sobre seus acessos. A estratégia CN foi introduzida no manejo de recursos genéticos vegetais com o principal objetivo de ampliar e sistematizar o uso desses recursos. Uma CN deve ser selecionada procurando reter a variabilidade genética existente na coleção inteira (CI com um mínimo de redundância. Os acessos da coleção de arroz foram classificados em três estratos: a variedades tradicionais do Brasil (VT; b linhagens/cultivares melhoradas do Brasil (LCM; e c linhagens/cultivares introduzidas (LCI. As variedades tradicionais foram ainda classificadas segundo o sistema de cultivo (terras altas, várzeas e facultativo. Os três estratos foram representados na Coleção Nuclear, mas ênfase maior foi dada às variedades tradicionais, que constituíram 308 acessos. Os acessos foram alocados para cada sistema de cultivo, proporcionalmente ao produto do logarítmo do número de variedades tradicionais pelo índice de Shannon (medida de diversidade de cada um deles. A seleção dos acessos foi feita com o auxilio do Sistema de Informação Geográfica (SIG. A CN brasileira de arroz está formada por 550 acessos.The Rice Germplasm Collection of Embrapa consists of approximately 10,000 accessions. This study aimed to establish a core collection using the currently available information data for those accessions. The strategy Core Collection (CN was introduced in the management of plant genetic resources with the main purpose of improving the use of these resources. CN should be selected in order to preserve the genetic variability of the whole collection (CI, with minimum redundancy. The accessions within the rice collection were classified into three strata: a landraces from Brazil (VT; b breeding materials from Brazil (LCM

  1. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Kee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    International cooperation in nuclear industries requires nuclear control as prerequisites. The concept of nuclear control is based on the Treaty on the Non-proliferation of Nuclear Weapon (NPT). The International Atomic Energy Agency (IAEA) plays central role in implementing nuclear control. Nuclear control consists of nuclear safeguards, physical protection, and export/import control. Each member state of NPT is subject to the IAEA`s safeguards by concluding safeguards agreements with the IAEA. IAEA recommends member states to implement physical protection on nuclear materials by `The Physical Protection of Nuclear Material` and `The Convention on the Physical Protection of Nuclear Material` of IAEA. Export/Import Control is to deter development of nuclear weapons by controlling international trade on nuclear materials, nuclear equipments and technology. Current status of domestic and foreign nuclear control implementation including recent induction of national inspection system in Korea is described and functions of recently set-up Technology Center for Nuclear Control (TCNC) under the Korea Atomic Energy Research Institute (KAERI) are also explained. 6 tabs., 11 refs. (Author).

  2. Desarrollo teórico e implementación computacional de una metodología no Born-Oppenheimer de teoría de funcionales de la densidad basada en el método del orbital molecular nuclear con escalamiento cúbico para el estudio de efectos cuánticos nucleares

    OpenAIRE

    Moncada Arias, Félix Santiago

    2013-01-01

    En este trabajo se presentan algunos desarrollos teóricos del método del orbital molecular para cualquier partícular (APMO) para reducir su costo computacional y para incluir correlación entre partículas de especies diferentes. Estas metodologías fueron implementadas en el código LOWDIN. También se presentan aplicaciones del método APMO al estudio de efectos cuánticos nucleares y química muónica. Nuestros resultados muestran que incluir correlación núcleo-electrón incrementa la precisión de l...

  3. A importância da contra-imunoeletroforese na detecção de antígenos nucleares extraíveis para o diagnóstico de doenças reumáticas sistêmicas The importance of counterimmunoelectrophoresis in the detection of extractable nuclear antigens for the diagnosis of systemic rheumatic diseases

    OpenAIRE

    Rita de Cassia Siqueira Bruder; Izaíra Máximo de Carvalho Prudente; Maria Isabel Corrêa da Silva; Julio Defaveri

    2004-01-01

    Os antígenos nucleares extraíveis (ENAs) são encontrados no soro da maioria dos pacientes com doença reumática sistêmica. Os principais ENAs estudados são SS-A/Ro, SS-B/La, RNP, Sm, Scl-70 e Jo-1. Objeti-vou-se neste trabalho: a) padronizar a técnica de contra-imunoeletroforese (CIE) para a detecção de ENAs; b) padronizar o substrato antigênico (ENAs) para a CIE a partir de baço de cão; c) comparar os resultados da CIE com as técnicas de imunofluorescência indireta (IFI) e Elisa para esses an...

  4. Information system for data management of civil buildings instrumentation in generating power stations; Sistema de informacion para el manejo de datos de la instrumentacion de las obras civiles de las centrales generadoras

    Energy Technology Data Exchange (ETDEWEB)

    Alvarado, Alonso; Escamilla, Juan Carlos; Alaniz, Felipe de Jesus [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Gonzalez, Francisco; Mena, Enrique [Comision Federal de Electricidad, Mexico, D. F. (Mexico)

    1997-12-31

    A relevant task performed by Comision Federal de Electricidad (CFE) is the analysis of the structural behavior and safety assessment of the country`s large electric energy generating stations. This task is performed capturing, revising an analyzing the information generated by measuring instruments installed in the power station civil structures. Such activity generates a large amount of data and the collection, analysis and assessment is a long and tiresome process; additionally, the generated information is kept in plain isolated files, that causes sluggishness in the process and delays in the access to the information. This article describes the characteristics of the Information System for Structure Measurements (Sistema de Informacion de Medicion de Estructuras) (SIME), developed by the Instituto de Investigaciones Electricas (IIE) for CFE in order to enhance the opportunity for the information management. SIME captures, arranges, stores and reports the data obtained from the measurements at the works with great efficiency and flexibility. This system is part of another of greater scope with which CFE will ensure an optimum operation condition of its civil buildings. [Espanol] Una tarea relevante que realiza la Comision Federal de Electricidad (CFE) es analizar el comportamiento estructural y evaluar la seguridad de las grandes obras generadoras de energia electrica del pais. Esta tarea la realiza capturando, revisando y analizando la informacion que generan instrumentos de medicion instalados en las estructuras civiles de las centrales. Tal actividad genera gran cantidad de datos y el proceso de recopilacion, analisis y evaluacion es tardado y tedioso; ademas, la informacion que se genera se guarda en archivos planos aislados, lo que ocasiona lentitud en el proceso y retraso en el acceso a la informacion. Este articulo describe las caracteristicas del Sistema de Informacion de Medicion de Estructuras (SIME) desarrollado por el Instituto de Investigaciones

  5. Rol del fallo mecánico en la optimización del mantenimiento en una central nuclear//Role of the mechanical failure during the maintenance optimization in the nuclear power plant

    Directory of Open Access Journals (Sweden)

    Antonio Torres-Valle

    2012-05-01

    Full Text Available Entre las más recientes aplicaciones del Análisis Probabilista de Seguridad (1997 – 2003 de la Central Nuclear Embalse en Argentina, está el Programa de Mantenimiento Orientado a la Seguridad (2006– 2009 el cual se ha desarrollado con el empleo de la metodología de Mantenimiento Centrado en la Confiabilidad (RCM en inglés. El objetivo general del artículo es demostrar la alta contribución de los fallos mecánicos en el diseño de las políticas de mantenimiento de varios sistemas de la instalación a través del empleo de la metodología RCM. La composición, estructura y políticas de explotación de los sistemas tecnológicos de muchas instalaciones con riesgo asociado, similares a las de los sistemas analizados en este estudio, permite inferir que los resultados que se obtendrán serán equivalentes de aplicarse la metodología RCM en dichas instalaciones. Palabras claves: mantenimiento centrado en la confiabilidad, mantenimiento predictivo, mantenimiento preventivo, fallo mecánico, seguridad, confiabilidad, riesgo.______________________________________________________________________________ Abstract One of the most recent applications of Probabilistic Safety Analysis (1997 – 2003 to Embalse Nuclear Power Plant in Argentina, is the Safety Oriented Maintenance Program (2006 – 2009 developed with employment of the Reliability Centered Maintenance (RCM methodology. The general objective of the paper is to demonstrate the high contribution of the mechanical failures in the maintenance program design through the RCM methodology. The composition, structure and operation strategies of the technological systems of many risk associated facilities, similar to the analysed systems included in this study, allow deduce that the results will equivalent in case of application of RCM methodology in such facilities. Key words: reliability centered maintenance (RCM, predictive maintenance, preventive maintenance, mechanical failure, safety

  6. Nuevo esquema estratigráfico para los depósitos marinos mio-pliocenos del área de Navidad (33º00'-34º30'S, Chile central New stratigrafic scheme for the Mio-Pliocene marine deposits of the Navidad area (33º00'-34º30'S, central Chile

    Directory of Open Access Journals (Sweden)

    Alfonso Encinas

    2006-07-01

    Full Text Available Varios autores han propuesto diferentes esquemas estratigráficos para los depósitos sedimentarios neógenos marinos que afloran en la zona costera de Chile central entre Valparaíso (~33°00'S y Punta Topocalma (~34°30'S, sin que exista un consenso al respecto. Tampoco existe acuerdo respecto a las correlaciones entre los depósitos que afloran en la parte norte de dicha zona, entre Valparaíso y San Antonio (~33°30'S con aquellos que aparecen en la parte sur, entre San Antonio y Punta Topocalma. Sobre la base de nuevos estudios estratigráficos, sedimentológicos y paleontológicos se propone, de manera formal, un nuevo esquema estratigráfico para estos depósitos. De acuerdo con este nuevo esquema se definen la Formación Navidad (Mioceno Superior-Plioceno Inferior y las formaciones Licancheu, Rapel y La Cueva (Plioceno. Se propone la elevación de las tres primeras unidades (Navidad, Licancheu y Rapel, generalmente consideradas como miembros en clasificaciones anteriores, al rango de formaciones debido a que se encuentran separadas por discontinuidades (paraconformidades de escala regional. En el presente trabajo se definen estas unidades, se revisan los esquemas anteriores y se justifica la proposición de este nuevo esquemaDifferent stratigraphic schemes have been proposed by various authors for the Neogene marine sedimentary deposits cropping out along the central Chilean coast between Valparaíso (~33°00'S and Punta Topocalma (~34°30'S, without any consensus having been reached. Neither does any agreement exist with respect to the correlation between the deposits cropping out in the northern part of this area, between San Antonio (~33°30'S and Valparaíso, and those of the southern part, between San Antonio and Punta Topocalma. Based on new stratigraphic, sedimentologic and paleontologic studies we propose a formal, new stratigraphic classification for this area. According to this scheme we define the Navidad Formation (Upper

  7. La estimulación eléctrica de la corteza motora para el tratamiento del dolor central y dolor periférico por desaferentización Electrical stimulation of the motor cortex for the management of central pain and peripheral pain caused by desafferentiation

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    J. V. Pesudo

    2004-09-01

    Full Text Available El dolor central y el dolor periférico por desaferentización son de difícil tratamiento incluso con fármacos de última generación. La estimulación eléctrica sobre diversas estructuras ha demostrado en general ser poco efectiva. La estimulación sobre la corteza motora es una técnica relativamente nueva que parece ofrecer resultados prometedores en estos cuadros. Aunque desde el punto de vista quirúrgico es una técnica sencilla, no lo es tanto la localización adecuada de la corteza motora, lo cual es una condición importante para su efectividad. En este trabajo ofrecemos una revisión bibliográfica sobre ella. Sus indicaciones fundamentales actualmente son el dolor central fundamentalmente talámico, y el dolor trigeminal por desaferentización. La respuesta a barbitúricos sin respuesta a opioides, la conservación relativa de las vías motoras y sensitivas, y la respuesta a la estimulación magnética transcraneal predicen un buen resultado. Diversos métodos son utilizados para determinar la zona a estimular: PESS, estimulación intraoperatoria, neuronavegación, RNM funcional. Los parámetros de estimulación recomendados varían de unos autores a otros. Su mecanismo de actuación no es en la actualidad bien conocido aunque las teorías más aceptadas son la activación de zonas que modulan el dolor y la inhibición de la transmisión de los estímulos nociceptivos a nivel medular.Central pain and peripheral pain caused by desafferentation are difficult to treat even with last generation drugs. Electric stimulation of several structures has shown to be scarcely effective in general. Stimulation of motor cortex is a relatively new technique that seems to offer promising results in these disorders. While it is a simple technique from the surgical point of view, the adequate location of the motor cortex is not so easy, this being a significant condition for its effectiveness. In this paper we review the literature that has been

  8. Variabilidade na determinação do ponto externo de referência para a medida de pressão venosa central em crianças Variability in the establishment of an external reference point for central venous pressure measurement in children

    Directory of Open Access Journals (Sweden)

    Aline S. C. Belela

    2006-10-01

    Full Text Available OBJETIVO: Verificar variabilidade na determinação da linha axilar média como ponto externo de referência (PER, por diferentes profissionais de saú de, para a aferição de pressão venosa central em crianças. MÉTODOS: Estudo descritivo e de correlação realizado em uma unidade de cuidados intensivos pediátricos de um hospital universitário. Durante a determinação da linha axilar média como PER para a aferição da pressão venosa central, cinco avaliações realizadas no mesmo paciente por profissionais de saúde e uma realizada por um avaliador treinado foram comparadas. O resultado foi um total de 120 indicações de 44 profissionais de saúde, 17 (38,6% auxiliares e técnicos de enfermagem, 16 (36,3% enfermeiros e 11 (25,1% médicos, além de 24 identificações realizadas por avaliador treinado. Os dados foram analisados utilizando os testes do qui-quadrado, ANOVA, Kruskall-Wallis e teste t, fixando o nível de significância em 5%. RESULTADOS: Houve diferença significante entre as identificações realizadas pelos profissionais de saúde e pelo avaliador (p OBJECTIVE: To investigate the variability in the establishment of the midaxillary line as external reference point (ERP, by different healthcare workers, for the measurement of central venous pressure in children. METHODS: Descriptive and correlational study carried out in a pediatric intensive care unit of a teaching hospital. During the establishment of the midaxillary line as ERP for central venous pressure measurement, five assessments of the same patient made by healthcare workers and one assessment made by a trained evaluator were compared. A total of 120 assessments were made by 44 healthcare workers, 17 (38.6% by nursing assistants and nursing technicians, 16 (36.3% by nurses and 11 (25.1% by physicians, in addition to 24 assessments made by the trained evaluator. The data were analyzed using the chi-square test, ANOVA, Kruskal-Wallis test and t test. Significance

  9. Regionalização das temperaturas mínimas do ar prejudiciais à fecundação das flores de arroz para a região climática da depressão central, RS Minimum air temperatures probabilities harmful to the fecundation of rice flowers in the central region of Rio Grande do Sul, Brazil

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    Galileo Adeli Buriol

    2000-03-01

    Full Text Available Foram mapeadas as probabilidades de ocorrência de temperaturas mínimas do ar prejudiciais à fecundação das flores de arroz na Região Climática da Depressão Central do Estado do Rio Grande do Sul. Utilizaram-se os valores de probabilidade de ocorrência de temperaturas mínimas do ar iguais ou inferiores a 13, 15 e 17°C em um ou mais dias, cinco ou mais dias e dei ou mais dias para os meses de dezembro, janeiro, fevereiro e março. As isolinhas de probabilidade foram traçadas em um mapa ipsométrico da região. Os resultados mostram que as menores probabilidades se situam nas partes de menor altitude como nos vales dos rios Ibicuí, Jacuí, Taquari, estuário do Guaíba e seus afluentes e que o período de menor periculosidade das temperaturas mínimas do ar ocorre nos meses de janeiro e fevereiro.The probability of occurency of minimum air temperatures harmful to the fecundation of rice flowers in the Central Region of Rio Grande do Sul State was shown in a map. Minimum air temperatures lower or equal to 13, 15 e 17°C occuring during one or more days, five or more days and ten or more days in December, Jannary, February and March were used. The isolines of probability were drown on a map. The results showed that the lower probabilities are located in the parts of the land with lower altitude like the valley of Ibicui, Jacui, Taquari, and Guaiba rivers. Besides, January and February are the months where the risks of low temperatures to rice flowering is lower.

  10. Diseño de una unidad didáctica, basada en el diseño experimental, como estrategia para la Enseñanza de las Medidas de tendencia central, utilizando el entorno de programación R. Caso de Estudio grado 10A de la Institución Educativa José Horacio Betancur

    OpenAIRE

    Rendón Mesa, Victoria Eugenia

    2015-01-01

    Resumen: La presente investigación desarrolla una unidad para la Enseñanza de las Medidas de tendencia central basada en el diseño experimental y utilizando el entorno de programación R. Con esta estrategia se pretende lograr un aprendizaje significativo de las medidas de tendencia central y potenciar la competencia interpretativa en Estadística descriptiva e inferencial en los estudiantes del grado 10A de la Institución Educativa José Horacio Betancur, ubicado en el sector San Javier L...

  11. The integripennis species group of Geocharidius Jeannel, 1963 (Carabidae, Bembidiini, Anillina from Nuclear Central America: a taxonomic review with notes about biogeography and speciation

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    Igor Sokolov

    2014-09-01

    Full Text Available Our review recognizes 15 species of the integripennis species group of Geocharidius from Nuclear Central America, include three species previously described (G. gimlii Erwin, G. integripennis (Bates and G. zullinii Vigna Taglianti and 12 described here as new. They are: G. andersoni sp. n. (type locality: Chiapas, Chiapas Highlands, Cerro Huitepec and G. vignatagliantii sp. n. (type locality: Chiapas, Motozintla, Sierra Madre de Chiapas, Benito Juárez from Mexico; G. antigua sp. n. (type locality: Sacatepéquez, 5 km SE of Antigua, G. balini sp. n. (type locality: Suchitepéquez, 4 km S of Volcan Atitlán, G. erwini sp. n. (type locality: Quiché Department, 7 km NE of Los Encuentros, G. jalapensis sp. n. (type locality: Jalapa Department, 4 km E of Mataquescuintla, G. longinoi, sp. n. (type locality: El Progreso Department, Cerro Pinalón, and G. minimus sp. n. (type locality: Sacatepéquez Department, 5 km SE of Antigua from Guatemala; and G. celaquensis sp. n. (type locality: Lempira Department, Celaque National Park, G. comayaguanus sp. n. (type locality: Comayagua Department, 18 km ENE of Comayagua, G. disjunctus sp. n. (type locality: Francisco Morazán, La Tigra National Park, and G. lencanus sp. n. (type locality: Lempira Department, Celaque National Park from Honduras. For all members of the group, adult structural characters, including male and female genitalia, are described, and a taxonomic key for all members of the integripennis species group is presented based on these characters. Behavioral and biogeographical aspects of speciation in the group are discussed, based on the morphological analysis. In all cases of sympatry, pairs of closely related species show greater differences in sizes than pairs of more remotely related species. Integripennis group species occupy six different montane areas at elevations above 1300m, with no species shared among them. Major faunal barriers in the region limiting present species distributions

  12. The integripennis species group of Geocharidius Jeannel, 1963 (Carabidae, Bembidiini, Anillina) from Nuclear Central America: a taxonomic review with notes about biogeography and speciation.

    Science.gov (United States)

    Sokolov, Igor M; Kavanaugh, David H

    2014-01-01

    Our review recognizes 15 species of the integripennis species group of Geocharidius from Nuclear Central America, include three species previously described (Geocharidiusgimlii Erwin, Geocharidiusintegripennis (Bates) and Geocharidiuszullinii Vigna Taglianti) and 12 described here as new. They are: Geocharidiusandersoni sp. n. (type locality: Chiapas, Chiapas Highlands, Cerro Huitepec) and Geocharidiusvignatagliantii sp. n. (type locality: Chiapas, Motozintla, Sierra Madre de Chiapas, Benito Juárez) from Mexico; Geocharidiusantigua sp. n. (type locality: Sacatepéquez, 5 km SE of Antigua), Geocharidiusbalini sp. n. (type locality: Suchitepéquez, 4 km S of Volcan Atitlán), Geocharidiuserwini sp. n. (type locality: Quiché Department, 7 km NE of Los Encuentros), Geocharidiusjalapensis sp. n. (type locality: Jalapa Department, 4 km E of Mataquescuintla), Geocharidiuslonginoi, sp. n. (type locality: El Progreso Department, Cerro Pinalón), and Geocharidiusminimus sp. n. (type locality: Sacatepéquez Department, 5 km SE of Antigua) from Guatemala; and Geocharidiuscelaquensis sp. n. (type locality: Lempira Department, Celaque National Park), Geocharidiuscomayaguanus sp. n. (type locality: Comayagua Department, 18 km ENE of Comayagua), Geocharidiusdisjunctus sp. n. (type locality: Francisco Morazán, La Tigra National Park), and Geocharidiuslencanus sp. n. (type locality: Lempira Department, Celaque National Park) from Honduras. For all members of the group, adult structural characters, including male and female genitalia, are described, and a taxonomic key for all members of the integripennis species group is presented based on these characters. Behavioral and biogeographical aspects of speciation in the group are discussed, based on the morphological analysis. In all cases of sympatry, pairs of closely related species show greater differences in sizes than pairs of more remotely related species. Integripennis group species occupy six different montane areas at

  13. Status of the nuclear sector in Spain Situación del sector nuclear en España

    Directory of Open Access Journals (Sweden)

    Antonio González Jiménez

    2010-12-01

    ó a desarrollarse en los años sesenta, como consecuencia de la decisión de construir las centrales nucleares de José Cabrera, Santa María de Garoña y Vandellós I. En la siguiente etapa, en la década de los años setenta, se construyeron las centrales de Almaraz, Ascó y Cofrentes. Durante la tercera etapa, en la década de los años ochenta, se construyeron las centrales de Vandellós II y Trillo I. Actualmente, la industria nuclear española, experta y eficaz, es garantía de que la tecnología nuclear se conserva en España no solo para apoyar a las centrales nucleares en operación, sino para atender un mercado nuclear reactivado a nivel internacional. España dispone de la infraestructura necesaria, la capacidad técnica, los recursos financieros y la voluntad de las empresas en el empeño común de proporcionar a los españoles una energía eléctrica fiable, barata y sostenible, con respeto al medio ambiente y seguridad para los ciudadanos. La energía nuclear es, en definitiva, una pieza clave hoy y lo será en el futuro.

  14. Annual report from the realization of the Central Program of the Fundamental Studies no 01.09. ''Studies of elementary particles and nuclear processes'' in 1987

    International Nuclear Information System (INIS)

    Report on the realization of research program in the domain of high and medium energy physics, structural studies by means of nuclear physics methods, nuclear chemistry and high-energy instrumentation in 1987 is presented. Program is coordinated by Institute of Nuclear Physics in Cracow, Institute of Physics of Jagiellonian University in Cracow and Institute of Nuclear Studies in Swierk. The information on international cooperation and costs of the realization of the program are given. Lists of the 487 most important publications are presented. (M.F.W.)

  15. Development of a computer program of fast calculation for the pre design of advanced nuclear fuel 10 x 10 for BWR type reactors; Desarrollo de un program de computo de calculo rapido para el prediseno de celdas de combustible nuclear avanzado 10 x 10 para reactores de agua en ebullicion

    Energy Technology Data Exchange (ETDEWEB)

    Perusquia, R.; Montes, J.L.; Ortiz, J.J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: mrpc@nuclear.inin.mx

    2005-07-01

    In the National Institute of Nuclear Research (ININ) a methodology is developed to optimize the design of cells 10x10 of assemble fuels for reactors of water in boil or BWR. It was proposed a lineal calculation formula based on a coefficients matrix (of the change reason of the relative power due to changes in the enrichment of U-235) for estimate the relative powers by pin of a cell. With this it was developed the computer program of fast calculation named PreDiCeldas. The one which by means of a simple search algorithm allows to minimize the relative power peak maximum of cell or LPPF. This is achieved varying the distribution of U-235 inside the cell, maintaining in turn fixed its average enrichment. The accuracy in the estimation of the relative powers for pin is of the order from 1.9% when comparing it with results of the 'best estimate' HELIOS code. With the PreDiCeldas it was possible, at one minimum time of calculation, to re-design a reference cell diminishing the LPPF, to the beginning of the life, of 1.44 to a value of 1.31. With the cell design with low LPPF is sought to even design cycles but extensive that those reached at the moment in the BWR of the Laguna Verde Central. (Author)

  16. Instalación eléctrica en baja tensión para energizar motores de giro en los colectores cilíndricos parabólicos de una planta termosolar de 50 MWe

    OpenAIRE

    Cárdenas Pellecer, Juan Pablo

    2011-01-01

    Las centrales con colectores cilindro‐parabólicos son una de las tecnologías más utilizada comercialmente para el aprovechamiento de la energía solar en centrales de gran potencia. Al igual que en centrales térmicas con combustibles convencionales y algunas nucleares, la potencia se genera en las centrales solares térmicas con una turbina a vapor y un generador acoplado. No obstante, el vapor requerido no se obtiene mediante combustión de fuentes de energía fósiles, sino con ayuda de la energ...

  17. en los pivotes centrales

    Directory of Open Access Journals (Sweden)

    Reynaldo Roque Rodés

    2005-01-01

    Full Text Available Se hace una revisión y comentarios sobre las ventajas y limitantes del empleo del LEPA (Low Enery Precision Aplication en los sistemas de riego de pivotes centrales. Estos sistemas o filosofía de manejo del agua para condiciones de escasez o mala calidad del líquido es una alternativa viable para la producción de alimentos. Introducida en la década del 80 en las planicies del sur de Texas, donde la alta evaporación del agua y la necesidad de regar grandes áreas con pivotes centrales obligaba a la búsqueda de una alternativa para incrementar al máximo la eficiencia de aplicación del riego. Aún en fase de estudio e introducción en Cuba para áreas específicas, puede ser una solución de incremento de los rendimientos de los cultivos, empleando menos agua y aguas con calidad limitada

  18. Obtenção de microesferas de (U,ThO2 para o combustível do reator nuclear de alta temperatura

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    Fernando Soares Lameiras

    2004-09-01

    Full Text Available Variantes do Processo Sol-Gel foram utilizadas com sucesso para obter microesferas de (Th,UO2 com os requisitos exigidos para seu uso em reatores HTGR. O Processo Hidrólise foi empregado para obtenção de microesferas de UO2 e o Processo de Gelação Externa foi empregado para obtenção de microesferas de (Th,UO2 com teores de urânio de até 25%. O Processo Hidrólise ainda necessita de otimização das condições de síntese.Sol-Gel processes were successfully used to obtain (Th,UO2 microspheres with the properties required for its use in HTGR reactors. The Hydrolysis Process was used to obtain UO2 microspheres, and the External Gelation Process was used to obtain (Th,0-25%UO2 microspheres. Optimization of synthesis conditions is still required for the Hydrolysis Process.

  19. DISEÑO CONCEPTUAL DE UN SISTEMA CONTROLADO POR UN ACELERADOR PARA TRANSMUTACIÓN DE RESIDUOS NUCLEARES Y APLICACIONES ENERGÉTICAS

    OpenAIRE

    GARCIA FAJARDO, LAURA

    2012-01-01

    Las posibilidades de desarrollo de la energía nuclear aumentan considerablemente con el incremento de la demanda energética mundial. Sin embargo, el manejo de los residuos provenientes del combustible nuclear gastado de las plantas nucleares convencionales es actualmente uno de los principales problemas que enfrenta el uso de esta fuente de energía. El objetivo del presente trabajo consistió en realizar el diseño conceptual del TADSEA (Transmutation Advanced Device for Sustainable Energy Appl...

  20. Outlook to nonproliferation activities in the world and cooperation in peaceful uses of nuclear energy among Turkey, Caucasus and Central Asia

    International Nuclear Information System (INIS)

    Full text: Following the First Geneva Conference in 1955 for expanding peaceful uses of nuclear energy, Turkey was one of the first countries to start activities in the nuclear field. Turkish Atomic Energy Authority (TAEK) was established in 1956 and Turkey became a member of the International Atomic Energy Agency established in 1957. TAEK was established to support, co-ordinate and perform the activities in peaceful uses of nuclear energy and act as a regulatory body and establish cooperation with countries and international organizations. In the late nineteen-ninetieth, TAEK, besides the cooperation with various countries, has involved in cooperating with nuclear institutes of Azerbaijan, Kazakhstan, Kyrgyzstan, Uzbekistan and Turkmenistan for establishment of bilateral and multilateral scientific and technical cooperation in peaceful uses of nuclear energy and signed protocols with Scientific Organisations of Azerbaijan, Kazakhstan, Kyrgyzstan and Uzbekistan. These protocols enable parties to organize joint projects, conferences, seminars, training programs, establish laboratories for the joint studies and make joint efforts to seek support from their governments and international organizations for these activities. Also, an executive committee has been set up with delegates from each organization under TAEK that also provides the secretarial service for organizing the joint activities. Turkey supports the non-proliferation activities that do not prevent the peaceful uses of nuclear energy and in this respect as signed Non-Proliferation Treaty (NPT) and Comprehensive Nuclear Test Ban Treaty (CTBT). Azerbaijan, Kazakhstan, Kyrgyzstan and Uzbekistan have also signed these Treaties following their independence and, except Kyrgyzstan, have become members to IAEA

  1. Methodology for implementation of a national metrology net of radionuclides used in nuclear medicine; Metodologia para a implementacao de uma rede de referencia para metrologia de radiofarmacos no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Joyra Amaral dos

    2004-01-15

    The National Laboratory for Ionizing Radiation Metrology, of the Institute of Radiation Protection and Dosimetry, of the National Commission on Nuclear Energy (IRD/CNEN), comes leading a comparison program for activity measurements of radiopharmaceuticals administered to patients in the Nuclear Medicine Services (NMS) with the purpose to promote the quality control. This work presents a quality assurance program for the performance of such measurements, evaluated in the comparison runs between hospitals and LNMRI, under the statistic point of view and the compliment of regulatory authority norms. The performance of the radionuclides {sup 67}Ga, {sup 123}I, {sup 131}I,{sup 99m}Tc and {sup 210}Tl were evaluated and {sup 201}TI have been standardized by absolute methods. Besides, it was established the traceability of the radioactivity standards used in nuclear medicine and a methodology for implementation of a national metrology net of radionuclides. The comparison results prove that the implementation of a radionuclide metrology net is viable, important and feasible. (author)

  2. Estudio piloto para el análisis del riesgo asociado a un Almacén Temporal Individualizado. Aplicación de la metodología APS

    OpenAIRE

    Díaz Bayona, Pedro

    2012-01-01

    El Proyecto Final de Carrera “Estudio piloto para el análisis del riesgo asociado a un Almacén Temporal Individualizado. Aplicación de la metodología APS” se enmarca en un convenio de colaboración entre una central nuclear y el Departament de Física i Enginyeria Nuclear de la Universitat Politècnica de Catalunya (UPC) para la investigación y aplicación de los APS en decisiones basadas en el riesgo. El proyecto se basa en la metodología descrita en la guía reguladora NUREG/CR-23...

  3. A new record of Equus (Mammalia: Equidae from the Late Pleistocene of central-south Chile Un nuevo registro de Equus (Mammalia: Equidae para el Pleistoceno Superior de Osorno, Chile

    Directory of Open Access Journals (Sweden)

    OMAR P RECABARREN

    2011-12-01

    Full Text Available Fourteen dental and bone parts of a horse excavated from the Pilauco paleontological site, Osorno (40°39' S-73°07' W are analysed and interpreted. This site was formed in association with a peat bog located on the banks of the old Damas River and has conserved abundant late Pleistocene mammalian fauna and flora materials. A date of 11457 ± 140 14C yrs B.P. was obtained from a molar and agrees with our stratigraphic age model. We have identified the fossils as pertaining to the species Equus (Amerhippus andium, which confirms its presence in central-south Chile. Furthermore, the recorded geographic location indicate that the metapodial adaptations of the specimens previously described agree with the reconstructed late Pleistocene landscape of Pilauco, dominated by soft volcanic soils and isolated forest patches over large extensions of grasslands.Se analizan e interpretan 14 fósiles correspondientes a dientes y huesos de caballo registrados en el sitio Pilauco, Osorno (40°39' S-73°07' W. El sitio se formó asociado a un pantano en un borde del antiguo río Damas; en él se ha conservado abundante material de mastofauna y flora pleistocénica. Una fecha radiocarbónica de 11457 ± 140 A.P obtenida de un molar, es concordante con el modelo de edad del sitio. La identificación taxonómica permite asociar a los fósiles a la especie Equus (Amerhippus andium, lo que confirma la presencia de la especie en el centro-sur de Chile. Por otra parte, la posición geográfica de los hallazgos y la reconstrucción del paisaje indicarían que se trata de ejemplares cuyas adaptaciones en los metapodios son concordantes para el paisaje pleistocénico de Pilauco dominado por suelos volcánicos blandos, con presencia de bosquetes dispersos en grandes extensiones de praderas de gramíneas.

  4. Equações de sortimentos para Tectona grandis na região centro–sul de Mato Grosso Assortment of Tectona grandis in south–central region of Mato Grosso, Brazil

    Directory of Open Access Journals (Sweden)

    Cyro Matheus Cometti Favalessa

    2012-12-01

    Full Text Available O objetivo desse estudo foi comparar a acurácia das estimativas dos volumes ao longo do fuste de Tectona grandis L.f propiciadas por ajustes de modelos polinomiais segmentados e não segmentados, para um povoamento na região Centro-Sul de Mato Grosso. Foram cubadas 114 árvores de Tectona grandis, pela metodologia de Hohenadl com 16 seções. Os modelos não segmentados testados foram o do quinto grau proposto por Schöepfer em 1966 e o de Haradetzky de 1976 e os modelos segmentados, foram o de Max e Burkhart de 1976 e de Clark et al. de 1991. A acuracia dos modelos foi avaliada pelo desvio, desvio padrão das diferenças, somatório de quadrado dos resíduos relativos e a porcentagem dos resíduos. A equação do quinto grau é a mais acurada na estimativa dos volumes ao longo dos fustes de Tectona grandis, e a equação de Max e Burkhart estima com acurácia os volumes da base dos fustes. The aim of this study was to compare the accuracy of volume estimative along the stem of Tectona grandis L. f obtained by adjustment of non–segmented and segmented polynomial models, for a forest stand in South–Central region of Mato Grosso State, Brazil. Data from rigorous tree scaling of Tectona grandis, using One hundred and fourtheen trees were measured by Hohenadl method, using 16 sections. The non–segmented models tested were the fifth-degree proposed by Schöepfer in 1966 and the Haradetzky from 1976 model. The segmented models tested were the Max and Burkhart from 1976 and the Clark et al. from 1991. The models accuracy along the stem were evaluated by the deviation, the standard deviations of differences, sum of squares of relative residues and percentage of residues The fifth-degree equation is the most accurate to estimate the volumes along the stem of Tectona grandis, and Max and Burkhart equation accurately estimated the volumes of the stem basis.

  5. A stable regulatory frame, a key for the health and safety in nuclear renaissance; Un marco regulador estable, clave para la salud y la seguridad en el renacimiento nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Klein, D.

    2008-07-01

    Thirty one nations currently operate 439 reactors, and there are 34 reactors under construction in 11 nations. In addition, the U.S. Department of Energy (DOE) estimates that in a little more than two decades, 55 countries will operate 630 reactors and that by mid-century, 86 countries could have operating commercial reactors. Any measure, a nuclear renaissance is upon us. According to U.S. government estimates, within the next two decades 24 countries will be building and operating nuclear reactors for the first time. One concern for me is that many of these nations have neither a nuclear infrastructure nor nuclear experience. The current nuclear resurgence brings with it the unique opportunity to enhance the safety and security of the new reactors. (Author)

  6. Chemical, physical and isotopic characterization of U{sub 3}Si{sub 2}, for nuclear forensics purposes; Caracterizacao quimica, fisica e isotopica de U{sub 3}Si{sub 2} para fins forenses nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Rosa, Daniele Scarpim

    2011-07-01

    In the early 1990's, the first illicit trafficking of nuclear and radioactive materials was observed mainly in Europe. A decade marked by numerous cases of seizures of these materials. As a result, these events have become the subject of criminal forensic investigations and develop from there, nuclear forensics. In Brazil there are no illicit trafficking official records of nuclear material, however, is widely known the extraction and illegal transportation of radioactive geological materials, and the materials pieces attachment used as shielding for radioactive sources. One of the main tools used in nuclear forensics is the nuclear materials databases establishment. These documents must contain the most information as possible about the physical, chemical and nuclear material seized, allowing the identification of their origin, manufacturing process or age. Thus, it sets characteristic composition standards of each material, called 'chemical signatures' (chemical finger print). In this work nuclear forensic protocol was adopted as well as the three stages of assessment suggested by International Atomic Energy Agency (IAEA) in identifying the origin of uranium silicide (U{sub 3}Si{sub 2}). Assays were performed in order to make physical, chemical and isotopic characterization of the studied materials and compared the data with those obtained for other uranium compounds (Uranium tetrafluoride, UF{sub 4}; uranium oxide, UO{sub 2} and U{sub 3}O{sub 8}; Yellow cake) by establishing a characteristic signature for each one. Through the assays the uranium compounds were classify by origin groups, as far as they are from different manufactured process and/ or origin. It was also possible to show the importance of a nuclear forensic database during an investigation of a nuclear forensic event. (author)

  7. New Technologies for a sustainable nuclear energy and your effect in the management of radioactive waste; Nuevas tecnologias para una energia nuclear sostenible y su efecto en la gestion de residuos radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Romero, E. M.

    2009-07-01

    The probable worldwide increase and distribution of nuclear energy for electricity generation, replacing partially fossil fuels, is promoting the development of technologies that foster its long-term sustain ability. Fast neutron system, combined with closed fuel cycles, are the key elements for the sustain ability. When combined, they can provide a significant reduction on the final high level wastes of the nuclear generation. In particular, Partitioning and Transmutation of actinides would allow the reduction of the nuclear wastes radiotoxicity, their content in fissile material and the heat load to the repository. (Author) 8 refs.

  8. Evaluación de procedimientos desde la perspectiva probabilistica para la seguridad nuclear: aplicación a un reactor Westinghouse PWR

    OpenAIRE

    Martínez Cid, Manuel

    2012-01-01

    Probabilistic Risk Assessment for the evaluation of procedures in the Nuclear Safety field. Application to a pressurized water reactor. The studies contained in this PhD are involved in the Nuclear Safety research field. Both are related to the Risk Informed philosophy with the improvement of the risk decision-making as a main target. Probabilistic Safety Assessment is the main tool for the development of the PhD and it is also the common research field for the assessment of its applicatio...

  9. De "átomos para la paz" a los reactores de potencia: Tecnología y política nuclear en la Argentina (1955-1976)

    OpenAIRE

    Diego Hurtado de Mendoza

    2005-01-01

    Durante el período 1955-76, el programa nuclear argentino se integró a la arena internacional; su Comisión Nacional de Energía Atómica construyó cuatro reactores de investigación, adquirió a una empresa alemana y puso en marcha el primer reactor de potencia Atucha I, y compró a una empresa canadiense un segundo reactor de potencia. En este artículo se examinan estos desarrollos en relación con el contexto político local y con el panorama nuclear internacional. En particular, se analizan la po...

  10. National Report presented by the Mexican United States to satisfy the compromises of the Nuclear Safety Convention; Informe Nacional que presentan los Estados Unidos Mexicanos para satisfacer los compromisos de la Convencion de Seguridad Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    National Commission of Nuclear Safety and Safeguards, Mexico City (Mexico); Federal Commission for Electricity, Mexico City (Mexico)

    1998-12-31

    In order to satisfy to the compromises derived of the ratification by part of the Mexican Government for the Nuclear Safety Convention it is presented this National Report which is based on the directives proposed as a result of the preparatory meetings held in the IAEA Headquarters in the city of Vienna, Austria. This National Report represents a document summary and activities realized at present in relation with the only nuclear facility in Mexico: the Nuclear Power Plant in Laguna Verde, Veracruz. This report consists of two parts: In the first one it is described how have been satisfied each one of the compromises. The second one talks about the Laws and Regulations on nuclear activities in the country. (Author)

  11. The continuous improvement system of nuclear power plant of Laguna Verde; El sistema de mejora continua de la central nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Rivera C, A. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km. 42.5 Cardel-Nautla, Veracruz (Mexico)], e-mail: arr99999@cfe.gob.mx

    2009-10-15

    This paper describes the continuous improvement system of nuclear power plant of Laguna Verde and the achievements in implementing the same and additionally two study cases are presents. In February 2009 is noteworthy because the World Association of Nuclear Operators we identified as a learning organization, qualification which shows that the continuous improvement system has matured, and this system will expose as I get to learn to capitalize on our own experiences and external experiences diffused by the nuclear industry. In 2007 the management of nuclear power plants integrates its improvement systems and calls it continuous improvement system and is presented in the same extensive report that won the National Quality Award. This system is made up of 5 subsystems operating individually and are also related 1) human performance; 2) referential comparison or benchmarking; 3) self-assessment; 4) corrective action and 5) external operating experience. Five subsystems that plan, generate, capture, manage, communicate and protect the knowledge generated during the processes execution of nuclear power plant of Laguna Verde, as well as from external sources. The target set in 2007 was to increase the intellectual capital to always give response to meeting the security requirements, but creating a higher value to quality, customer, environment protection and society. In brief each of them, highlighting the objective, expectations management, implementation and some benefits. At the end they will describe two study cases selected to illustrate these cases as the organization learns by their continuous improvement system. (Author)

  12. Prevalencia de anticuerpos anti envoltura nuclear y sus isotipos en sueros positivos para anticuerpos antinucleares Prevalence of antinuclear envelope antibodies and their isotypes in sera positive for antinuclear antibodies

    Directory of Open Access Journals (Sweden)

    Miriam Arcavi

    2006-08-01

    Full Text Available Los anticuerpos antinucleares detectados por inmunofluorescencia indirecta en células HEp-2 presentan una gran variedad de imágenes, entre ellas el patrón de envoltura nuclear que suele ser un hallazgo poco frecuente. Se procesaron 2594 sueros en los cuales se detectó un 37.6% de anticuerpos antinucleares. La prevalencia de anticuerpos anti-envoltura nuclear (ANEA fue del 1.2% presentando una alta asociación con hepatopatías autoinmunes (83% y baja con lupus eritematoso sistémico. En los 21 sueros de los pacientes que presentaron ANEA no se detectaron anticuerpos anti-ADNn hallándose 28.6% de anticuerpos anti-músculo liso y 19% de anticuerpos anti-mitocondriales. El corte triple de tejido de rata mostró ser un sustrato menos sensible que HEp-2 para la detección de ANEA. Al utilizar conjugados dirigidos contra diferentes isotipos de anticuerpos para la detección de ANEA, se encontró: 90.5% de IgG, 66.6% de IgA y 9.5% de IgM. Dos de los pacientes presentaron ANEA-IgA a altos títulos (³1:160 en ausencia de ANEA-IgG. En este trabajo se destaca la importancia de realizar pruebas complementarias que detecten anticuerpos anti-músculo liso, anti-mitocondriales y anti-ADNn, para orientar el diagnóstico clínico de los pacientes que presentan ANEA. Además, sostiene la postura de utilizar como conjugado para IFI-HEp2 anticuerpos anti-inmunoglobulinas totales en lugar de anti-IgG hasta tanto se clarifique el rol que juegan los anticuerpos IgA en estas enfermedades autoimunes.Antinuclear antibodies detected in HEp-2 cells by indirect immunofluorescence assay display a great variety of images, including the nuclear envelope pattern. This is quite a less frequent finding. Two thousand five hundred and ninety-four sera were processed, and 37.6% of ANA were detected. The prevalence of anti-nuclear envelope antibodies (ANEA was of 1.2%, with a high association with autoimmune liver diseases (83% and a low association with systemic lupus

  13. Optimal nuclear magnetic resonance excitation schemes for the central transition of a spin 3/2 in the presence of residual quadrupolar coupling.

    Science.gov (United States)

    Lee, Jae-Seung; Regatte, Ravinder R; Jerschow, Alexej

    2008-12-14

    Optimal control theory is applied for enhancing the intensity of the central peak of a spin 3/2 signal in the presence of a residual quadrupolar coupling. While a maximum enhancement is always possible in the regime omega(rf) control and test these with (23)Na NMR in this regime. In addition to enhancing the intensity of the central transition signal, the satellite peaks can be effectively suppressed, which is a useful feature for the implementation in (23)Na imaging sequences. PMID:19071931

  14. Methodology of aging management in structures, systems and components of a nuclear power plant and its application to a pilot program in Laguna Verde; Metodologia de la gestion del envejecimiento en estructuras, sistemas y componentes de una central nuclear y su aplicacion a un programa piloto en Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Fernandez S, G. [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, Dos Bocas, 54270 Veracruz (Mexico)], e-mail: gfdezs@cfe.gob.mx

    2009-10-15

    From its origin the nuclear power plants confront the effects of time and of environment, giving as result the aging of its structures, systems and components. In this document the general process is described for the establishment of Aging Management Program developed by IAEA. Following the program methodology is guaranteed that a nuclear power plant manages the aging effects appropriately and to make decisions for its solution, assuring the characteristic functions of structures, systems and components of same nuclear power plant. On the other hand, the implantation of an aging management program constitutes the base for development of a licence renovation program, like it can be the specific case of the Central Laguna Verde Units 1 and 2. (Author)

  15. Procedures and techniques for monitoring the radiation detection, signalization and alarm systems in the centralized ambience monitoring systems of the basic nuclear facilities of the CEN Saclay

    International Nuclear Information System (INIS)

    After referring to the regulations governing the 'systematic ambience monitoring' in the basic nuclear facilities, the main radiation detection, signalization and alarm devices existing at present in these facilities of the Saclay Nuclear Study Centre are described. The analysis of the operating defects of the measuring channels and detection possibilities leads to the anomalies being classified in two separate groups: the anomalies of the logical 'all or nothing' type of which all the possible origins are integrated into a so-called 'continuity' line and the evolutive anomalies of various origins corresponding to poor functioning extending possibly to a complete absence of signal. The techniques for testing the detection devices of the radiation monitoring board set up in the 'Departement de Rayonnements' at the Saclay Nuclear Study Centre are also described

  16. Using fecal profiles of bile acids to assess habitat use by threatened carnivores in the Maulino forest of central Chile Empleo del perfil de ácidos biliares fecales para evaluar uso del hábitat por carnívoros amenazados en el bosque maulino de Chile central

    Directory of Open Access Journals (Sweden)

    CARLA GUERRERO

    2006-03-01

    Full Text Available The distribution and habitat use by carnivores can be assessed by studying their tracks or feces. If these methods are to be used confidently, they should not only unequivocally discriminate among species, but should also render the same patterns of spatial distributions. We assessed the fulfillment of these requirements with five carnivores inhabiting the Maulino forest of central Chile: Galictis cuja, Oncifelis guigna, Pseudalopex culpaeus, Pseudalopex griseus, and Puma concolor. Fecal bile acid thin layer chromatographic profiles were assessed, and shown to be species-specific, invariant within samples of a given individual and among individuals of a given species, but consistently different across species. The spatial distribution of feces in mixed stands of native forests and exotic pine plantations in the coastal Maule region of central Chile was compared with the expected distribution according to habitat offer, and also with the expected distribution based on earlier track records. The results revealed that Pseudalopex culpaeus makes extensive use of pine plantations; Oncifelis guigna prefers native forests, and Pseudalopex griseus thrives in pine plantations, native forests, and patches of native forest, in proportion to habitat availability. Results from scat distribution were similar to those obtained by tracks records. Feces and tracks were thus useful indicators of habitat use by carnivores, and could be used complementarily to study species with conservation problemsEl uso del hábitat por carnívoros puede ser examinado a partir de la distribución de sus huellas y fecas. Para que ambas aproximaciones sean usadas en forma segura y complementaria, ellas deberían no solamente discriminar inequívocamente entre especies, sino que también deberían entregar la misma información sobre los patrones de distribución espacial. Analizamos el cumplimiento de estos requisitos con cinco especies de carnívoros en el bosque maulino de Chile

  17. Preliminary analysis of the inclusion of security passive systems to reduce the impact of accidents in nuclear power plants; Analisis preliminar de la inclusion de sistemas pasivos de seguridad para reducir el impacto de accidentes en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez J, J.; Morales S, J. B. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Espinosa P, G., E-mail: jersonsanchez@gmail.com [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (MX)

    2011-11-15

    In this work is presented a conceptual analysis of possible benefits and limitations that potentially represents the introduction of security passive systems to reduce the events impact of very low probability and high risk to the systems of radioactive material confinement of a light water reactor. These events are related with the possibility that a hydrogen explosion is presented as consequence of the accumulation of the same hydrogen in the contention of the reactor, in a scenario of severe accident. This accumulated hydrogen can be liberated in the reactor building or primary contention, where the conditions of their atmosphere make but prone the combustion. The catalytic recombination represents a viable option for the hydrogen concentrations decrease and because this recombination is highly exothermic, is important to analyze and to know if the recombined vapor to high temperature can be used in combination with vapor injectors that in turn, they are passive systems. In the following sections an explanation is presented about the use of the mentioned systems, as well as some results on the behavior of the vapor injectors. (Author)

  18. APMO: UN PROGRAMA COMPUTACIONAL PARA EL ESTUDIO DE EFECTOS CUÁNTICOS NUCLEARES MEDIANTE LA TEORÍA DEL ORBITAL MOLECULAR ELECTRÓNICO Y NO ELECTRÓNICO.

    Directory of Open Access Journals (Sweden)

    Sergio González

    2009-04-01

    Full Text Available Con el fin de estudiar teóricamente fenómenos en donde los núcleos atómicos presentan comportamiento cuántico, hemos desarrollado el paquete computacional APMO (Any-Particle Molecular Orbital. Este implementa el método de orbitales moleculares nucleares y electrónicos (OMNE a un nivel de teoría Hartree-Fock (HF, en el que tanto núcleos como electrones se representan como funciones de onda.Para comprobar la correcta implementación del método, se realizaron  cálculos de estructura electrónica regular y núcleo-electrónica de las moléculas H2 y LiH. Las componentes de energía calculadas siguen las  tendencias y están en el mismo orden de magnitud de cálculos similares reportados en la literatura.A diferencia de otros paquetes que implementan el método OMNE, el nuestro fué diseñado para estudiar sistemas con cualquier número de especies cuánticas. 

  19. Practical training in the operation of nuclear power plants with Interactive Graphic Simulator of Zorita; Formacion practica en la operacion de centrales nucleares con el Simulador Grafico Interactivo de Zorita

    Energy Technology Data Exchange (ETDEWEB)

    Cuervo, D.; Garcia-Herranz, N.; Garcia, S.; Davila, R.; Ahnert, C.; Aragones, J. M.; Cabellos, O.; Gallego, E.; Lorente, A.; Minguez, E.; Rebollo, L.; Blanco, J.

    2010-07-01

    In April 2008 a collaboration agreement was signed between Gas Natural Union Fenosa and the Universad Politecnica de Madrid for the creation of the Aula Jose Cabrera dedicated to train professionals in the field of nuclear technology. The Classroom located in the Department of Nuclear Engineering, has been equipped with the Interactive Graphic Simulator of Zorita (SGIZ). The use of the simulator intended to improve the quality of teaching in the area of Nuclear Engineering. It integrates in the teachings of Industrial Engineering degree and the Master of Nuclear Science and Technology. Different manuals are under preparation to make it a suitable tool for teaching purpose. These manuals will guide the student so that learning takes place both through the guidance of the teacher as independently. (Author) 3 refs.

  20. Economic evaluation of application of nuclear power, fossil and biomass for seawater desalination in the case of Mexico; Evaluacion economica de la aplicacion de la potencia nuclear, fosil y biomasa para desalar agua de mar en el caso de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Palacios G, N.; Gomez A, R.; Vazquez R, R.; Espinosa P, G. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Depto. de Ingenieria de Procesos e Hidraulica, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)], e-mail: rvr@xanum.uam.mx

    2009-10-15

    In this work the fresh water production costs are compared on base to the seawater desalination, taking advantage of the heat or the electricity generated by means of the nuclear fission, the energy fossil result of the combustion of natural gas, fuel oil and coal, as well as the electricity generated by the bio-fuels combustion. The option of generating electricity and at the same time to produce drinking water is discussed. Using electricity, the best combination of technologies as for costs, the option more cheap, it is the distillation by means of a distillation combined process of multiple effects combined with reverse osmosis using nuclear energy coming from a gas cooled reactor using a cycle Brayton. While using direct heat was as the option more economic the use of nuclear vapor of low pressure exchanging heat in a vapor generator of low pressure, as energy source of a flash distillation process of several stages. In this last case, the energy source or nuclear vapor will be the result of the operation of a nuclear power plant cooled and moderate with water and operating in a cycle Rankine. (Author)

  1. Valinia INIA, a New Early Storage Onion Variety for Central South Chile Valinia INIA, una Nueva Variedad de Cebolla de Guarda Precoz para la Zona Centro Sur de Chile

    Directory of Open Access Journals (Sweden)

    María Inés González A

    2012-03-01

    Full Text Available In Central South Chile, storage onion varieties (Allium cepa L. sold domestically usually begin the maturation process in March, which implies that a large proportion of bulbs do not mature adequately and do not resist prolonged storage. This situation led the Quilamapu vegetable program of the Instituto de Investigaciones Agropecuarias INIA to select an early maturing onion variety. This breeding method involved a recurrent selection with free plant crossing that began in 1994 on a population of 2000 plants of the 'Valenciana' commercial variety. Plants were first selected when they reached physiological maturity (tops down before 28 February, and then for shape, size, storage capacity, and single-centered bulbs. The result of the program was 'Valinia INIA', a type of Valenciana onion variety: early maturing, medium-sized bulb, spherical, yellow, and resistant to sprouting during storage. From the 2001-2002 to the 2008-2009 season, variety assays were carried out to compare 'Valinia INIA' with commercial cultivars, i.e., 'Sintética 14', 'Grano de Oro', and 'Valenciana Cobra'. 'Valinia INIA' precocity exceeded the other varieties in all seasons with a mean of 1.5 wk ahead of 'Sintética 14', which is the earliest commercial variety and more than 2 wk ahead of the other two. Its yield is similar to 'Valenciana Cobra' and higher than the other two varieties. Its storage capacity is similar to 'Grano de Oro' and 'Sintética 14', but greater than 'Valenciana Cobra'.En la zona centro sur de Chile es habitual que las variedades de cebolla (Allium cepa L. de guarda que se comercializan en el pais inicien el proceso de maduración preferentemente en marzo, lo que conlleva a que una gran proporción de bulbos no madure adecuadamente, no resistiendo el almacenaje por un tiempo prolongado. Esta situación llevó al programa de hortalizas del Instituto de Investigaciones Agropecuarias INIA Quilamapu a la selección de una variedad de cebolla de madurez

  2. Centrality dependence of the nuclear modification factor of charged pions, kaons, and protons in Pb-Pb collisions at $\\sqrt{s_{NN}}$ = 2.76 TeV

    CERN Document Server

    Adam, Jaroslav; Aggarwal, Madan Mohan; Aglieri Rinella, Gianluca; Agnello, Michelangelo; Agrawal, Neelima; Ahammed, Zubayer; Ahn, Sang Un; Aimo, Ilaria; Aiola, Salvatore; Ajaz, Muhammad; Akindinov, Alexander; Alam, Sk Noor; Aleksandrov, Dmitry; Alessandro, Bruno; Alexandre, Didier; Alfaro Molina, Jose Ruben; Alici, Andrea; Alkin, Anton; Millan Almaraz, Jesus Roberto; Alme, Johan; Alt, Torsten; Altinpinar, Sedat; Altsybeev, Igor; Alves Garcia Prado, Caio; Andrei, Cristian; Andronic, Anton; Anguelov, Venelin; Anielski, Jonas; Anticic, Tome; Antinori, Federico; Antonioli, Pietro; Aphecetche, Laurent Bernard; Appelshaeuser, Harald; Arcelli, Silvia; Armesto Perez, Nestor; Arnaldi, Roberta; Arsene, Ionut Cristian; Arslandok, Mesut; Audurier, Benjamin; Augustinus, Andre; Averbeck, Ralf Peter; Azmi, Mohd Danish; Bach, Matthias Jakob; Badala, Angela; Baek, Yong Wook; Bagnasco, Stefano; Bailhache, Raphaelle Marie; Bala, Renu; Baldisseri, Alberto; Baltasar Dos Santos Pedrosa, Fernando; Baral, Rama Chandra; Barbano, Anastasia Maria; Barbera, Roberto; Barile, Francesco; Barnafoldi, Gergely Gabor; Barnby, Lee Stuart; Ramillien Barret, Valerie; Bartalini, Paolo; Barth, Klaus; Bartke, Jerzy Gustaw; Bartsch, Esther; Basile, Maurizio; Bastid, Nicole; Basu, Sumit; Bathen, Bastian; Batigne, Guillaume; Batista Camejo, Arianna; Batyunya, Boris; Batzing, Paul Christoph; Bearden, Ian Gardner; Beck, Hans; Bedda, Cristina; Behera, Nirbhay Kumar; Belikov, Iouri; Bellini, Francesca; Bello Martinez, Hector; Bellwied, Rene; Belmont Iii, Ronald John; Belmont Moreno, Ernesto; Belyaev, Vladimir; Bencedi, Gyula; Beole, Stefania; Berceanu, Ionela; Bercuci, Alexandru; Berdnikov, Yaroslav; Berenyi, Daniel; Bertens, Redmer Alexander; Berzano, Dario; Betev, Latchezar; Bhasin, Anju; Bhat, Inayat Rasool; Bhati, Ashok Kumar; Bhattacharjee, Buddhadeb; Bhom, Jihyun; Bianchi, Livio; Bianchi, Nicola; Bianchin, Chiara; Bielcik, Jaroslav; Bielcikova, Jana; Bilandzic, Ante; Biswas, Rathijit; Biswas, Saikat; Bjelogrlic, Sandro; Blair, Justin Thomas; Blanco, Fernando; Blau, Dmitry; Blume, Christoph; Bock, Friederike; Bogdanov, Alexey; Boggild, Hans; Boldizsar, Laszlo; Bombara, Marek; Book, Julian Heinz; Borel, Herve; Borissov, Alexander; Borri, Marcello; Bossu, Francesco; Botta, Elena; Boettger, Stefan; Braun-Munzinger, Peter; Bregant, Marco; Breitner, Timo Gunther; Broker, Theo Alexander; Browning, Tyler Allen; Broz, Michal; Brucken, Erik Jens; Bruna, Elena; Bruno, Giuseppe Eugenio; Budnikov, Dmitry; Buesching, Henner; Bufalino, Stefania; Buncic, Predrag; Busch, Oliver; Buthelezi, Edith Zinhle; Bashir Butt, Jamila; Buxton, Jesse Thomas; Caffarri, Davide; Cai, Xu; Caines, Helen Louise; Calero Diaz, Liliet; Caliva, Alberto; Calvo Villar, Ernesto; Camerini, Paolo; Carena, Francesco; Carena, Wisla; Carnesecchi, Francesca; Castillo Castellanos, Javier Ernesto; Castro, Andrew John; Casula, Ester Anna Rita; Cavicchioli, Costanza; Ceballos Sanchez, Cesar; Cepila, Jan; Cerello, Piergiorgio; Cerkala, Jakub; Chang, Beomsu; Chapeland, Sylvain; Chartier, Marielle; Charvet, Jean-Luc Fernand; Chattopadhyay, Subhasis; Chattopadhyay, Sukalyan; Chelnokov, Volodymyr; Cherney, Michael Gerard; Cheshkov, Cvetan Valeriev; Cheynis, Brigitte; Chibante Barroso, Vasco Miguel; Dobrigkeit Chinellato, David; Chochula, Peter; Choi, Kyungeon; Chojnacki, Marek; Choudhury, Subikash; Christakoglou, Panagiotis; Christensen, Christian Holm; Christiansen, Peter; Chujo, Tatsuya; Chung, Suh-Urk; Zhang, Chunhui; Cicalo, Corrado; Cifarelli, Luisa; Cindolo, Federico; Cleymans, Jean Willy Andre; Colamaria, Fabio Filippo; Colella, Domenico; Collu, Alberto; Colocci, Manuel; Conesa Balbastre, Gustavo; Conesa Del Valle, Zaida; Connors, Megan Elizabeth; Contreras Nuno, Jesus Guillermo; Cormier, Thomas Michael; Corrales Morales, Yasser; Cortes Maldonado, Ismael; Cortese, Pietro; Cosentino, Mauro Rogerio; Costa, Filippo; Crochet, Philippe; Cruz Albino, Rigoberto; Cuautle Flores, Eleazar; Cunqueiro Mendez, Leticia; Dahms, Torsten; Dainese, Andrea; Danu, Andrea; Das, Debasish; Das, Indranil; Das, Supriya; Dash, Ajay Kumar; Dash, Sadhana; De, Sudipan; De Caro, Annalisa; De Cataldo, Giacinto; De Cuveland, Jan; De Falco, Alessandro; De Gruttola, Daniele; De Marco, Nora; De Pasquale, Salvatore; Deisting, Alexander; Deloff, Andrzej; Denes, Ervin Sandor; D'Erasmo, Ginevra; Di Bari, Domenico; Di Mauro, Antonio; Di Nezza, Pasquale; Diaz Corchero, Miguel Angel; Dietel, Thomas; Dillenseger, Pascal; Divia, Roberto; Djuvsland, Oeystein; Dobrin, Alexandru Florin; Dobrowolski, Tadeusz Antoni; Domenicis Gimenez, Diogenes; Donigus, Benjamin; Dordic, Olja; Drozhzhova, Tatiana; Dubey, Anand Kumar; Dubla, Andrea; Ducroux, Laurent; Dupieux, Pascal; Ehlers Iii, Raymond James; Elia, Domenico; Engel, Heiko; Erazmus, Barbara Ewa; Erdemir, Irem; Erhardt, Filip; Eschweiler, Dominic; Espagnon, Bruno; Estienne, Magali Danielle; Esumi, Shinichi; Eum, Jongsik; Evans, David; Evdokimov, Sergey; Eyyubova, Gyulnara; Fabbietti, Laura; Fabris, Daniela; Faivre, Julien; Fantoni, Alessandra; Fasel, Markus; Feldkamp, Linus; Felea, Daniel; Feliciello, Alessandro; Feofilov, Grigorii; Ferencei, Jozef; Fernandez Tellez, Arturo; Gonzalez Ferreiro, Elena; Ferretti, Alessandro; Festanti, Andrea; Feuillard, Victor Jose Gaston; Figiel, Jan; Araujo Silva Figueredo, Marcel; Filchagin, Sergey; Finogeev, Dmitry; Fiore, Enrichetta Maria; Fleck, Martin Gabriel; Floris, Michele; Foertsch, Siegfried Valentin; Foka, Panagiota; Fokin, Sergey; Fragiacomo, Enrico; Francescon, Andrea; Frankenfeld, Ulrich Michael; Fuchs, Ulrich; Furget, Christophe; Furs, Artur; Fusco Girard, Mario; Gaardhoeje, Jens Joergen; Gagliardi, Martino; Gago Medina, Alberto Martin; Gallio, Mauro; Gangadharan, Dhevan Raja; Ganoti, Paraskevi; Gao, Chaosong; Garabatos Cuadrado, Jose; Garcia-Solis, Edmundo Javier; Gargiulo, Corrado; Gasik, Piotr Jan; Germain, Marie; Gheata, Andrei George; Gheata, Mihaela; Ghosh, Premomoy; Ghosh, Sanjay Kumar; Gianotti, Paola; Giubellino, Paolo; Giubilato, Piero; Gladysz-Dziadus, Ewa; Glassel, Peter; Gomez Coral, Diego Mauricio; Gomez Ramirez, Andres; Gonzalez Zamora, Pedro; Gorbunov, Sergey; Gorlich, Lidia Maria; Gotovac, Sven; Grabski, Varlen; Graczykowski, Lukasz Kamil; Graham, Katie Leanne; Grelli, Alessandro; Grigoras, Alina Gabriela; Grigoras, Costin; Grigoryev, Vladislav; Grigoryan, Ara; Grigoryan, Smbat; Grynyov, Borys; Grion, Nevio; Grosse-Oetringhaus, Jan Fiete; Grossiord, Jean-Yves; Grosso, Raffaele; Guber, Fedor; Guernane, Rachid; Guerzoni, Barbara; Gulbrandsen, Kristjan Herlache; Gulkanyan, Hrant; Gunji, Taku; Gupta, Anik; Gupta, Ramni; Haake, Rudiger; Haaland, Oystein Senneset; Hadjidakis, Cynthia Marie; Haiduc, Maria; Hamagaki, Hideki; Hamar, Gergoe; Hansen, Alexander; Harris, John William; Hartmann, Helvi; Harton, Austin Vincent; Hatzifotiadou, Despina; Hayashi, Shinichi; Heckel, Stefan Thomas; Heide, Markus Ansgar; Helstrup, Haavard; Herghelegiu, Andrei Ionut; Herrera Corral, Gerardo Antonio; Hess, Benjamin Andreas; Hetland, Kristin Fanebust; Hilden, Timo Eero; Hillemanns, Hartmut; Hippolyte, Boris; Hosokawa, Ritsuya; Hristov, Peter Zahariev; Huang, Meidana; Humanic, Thomas; Hussain, Nur; Hussain, Tahir; Hutter, Dirk; Hwang, Dae Sung; Ilkaev, Radiy; Ilkiv, Iryna; Inaba, Motoi; Ippolitov, Mikhail; Irfan, Muhammad; Ivanov, Marian; Ivanov, Vladimir; Izucheev, Vladimir; Jacobs, Peter Martin; Jadlovska, Slavka; Jahnke, Cristiane; Jang, Haeng Jin; Janik, Malgorzata Anna; Pahula Hewage, Sandun; Jena, Chitrasen; Jena, Satyajit; Jimenez Bustamante, Raul Tonatiuh; Jones, Peter Graham; Jung, Hyungtaik; Jusko, Anton; Kalinak, Peter; Kalweit, Alexander Philipp; Kamin, Jason Adrian; Kang, Ju Hwan; Kaplin, Vladimir; Kar, Somnath; Karasu Uysal, Ayben; Karavichev, Oleg; Karavicheva, Tatiana; Karayan, Lilit; Karpechev, Evgeny; Kebschull, Udo Wolfgang; Keidel, Ralf; Keijdener, Darius Laurens; Keil, Markus; Khan, Kamal; Khan, Mohammed Mohisin; Khan, Palash; Khan, Shuaib Ahmad; Khanzadeev, Alexei; Kharlov, Yury; Kileng, Bjarte; Kim, Beomkyu; Kim, Do Won; Kim, Dong Jo; Kim, Hyeonjoong; Kim, Jinsook; Kim, Mimae; Kim, Minwoo; Kim, Se Yong; Kim, Taesoo; Kirsch, Stefan; Kisel, Ivan; Kiselev, Sergey; Kisiel, Adam Ryszard; Kiss, Gabor; Klay, Jennifer Lynn; Klein, Carsten; Klein, Jochen; Klein-Boesing, Christian; Kluge, Alexander; Knichel, Michael Linus; Knospe, Anders Garritt; Kobayashi, Taiyo; Kobdaj, Chinorat; Kofarago, Monika; Kollegger, Thorsten; Kolozhvari, Anatoly; Kondratev, Valerii; Kondratyeva, Natalia; Kondratyuk, Evgeny; Konevskikh, Artem; Kopcik, Michal; Kour, Mandeep; Kouzinopoulos, Charalampos; Kovalenko, Oleksandr; Kovalenko, Vladimir; Kowalski, Marek; Koyithatta Meethaleveedu, Greeshma; Kral, Jiri; Kralik, Ivan; Kravcakova, Adela; Krelina, Michal; Kretz, Matthias; Krivda, Marian; Krizek, Filip; Kryshen, Evgeny; Krzewicki, Mikolaj; Kubera, Andrew Michael; Kucera, Vit; Kugathasan, Thanushan; Kuhn, Christian Claude; Kuijer, Paulus Gerardus; Kulakov, Igor; Kumar, Ajay; Kumar, Jitendra; Lokesh, Kumar; Kurashvili, Podist; Kurepin, Alexander; Kurepin, Alexey; Kuryakin, Alexey; Kushpil, Svetlana; Kweon, Min Jung; Kwon, Youngil; La Pointe, Sarah Louise; La Rocca, Paola; Lagana Fernandes, Caio; Lakomov, Igor; Langoy, Rune; Lara Martinez, Camilo Ernesto; Lardeux, Antoine Xavier; Lattuca, Alessandra; Laudi, Elisa; Lea, Ramona; Leardini, Lucia; Lee, Graham Richard; Lee, Seongjoo; Legrand, Iosif; Lehas, Fatiha; Lemmon, Roy Crawford; Lenti, Vito; Leogrande, Emilia; Leon Monzon, Ildefonso; Leoncino, Marco; Levai, Peter; Li, Shuang; Li, Xiaomei; Lien, Jorgen Andre; Lietava, Roman; Lindal, Svein; Lindenstruth, Volker; Lippmann, Christian; Lisa, Michael Annan; Ljunggren, Hans Martin; Lodato, Davide Francesco; Lonne, Per-Ivar; Loginov, Vitaly; Loizides, Constantinos; Lopez, Xavier Bernard; Lopez Torres, Ernesto; Lowe, Andrew John; Luettig, Philipp Johannes; Lunardon, Marcello; Luparello, Grazia; Ferreira Natal Da Luz, Pedro Hugo; Maevskaya, Alla; Mager, Magnus; Mahajan, Sanjay; Mahmood, Sohail Musa; Maire, Antonin; Majka, Richard Daniel; Malaev, Mikhail; Maldonado Cervantes, Ivonne Alicia; Malinina, Liudmila; Mal'Kevich, Dmitry; Malzacher, Peter; Mamonov, Alexander; Manko, Vladislav; Manso, Franck; Manzari, Vito; Marchisone, Massimiliano; Mares, Jiri; Margagliotti, Giacomo Vito; Margotti, Anselmo; Margutti, Jacopo; Marin, Ana Maria; Markert, Christina; Marquard, Marco; Martin, Nicole Alice; Martin Blanco, Javier; Martinengo, Paolo; Martinez Hernandez, Mario Ivan; Martinez-Garcia, Gines; Martinez Pedreira, Miguel; Martynov, Yevgen; Mas, Alexis Jean-Michel; Masciocchi, Silvia; Masera, Massimo; Masoni, Alberto; Massacrier, Laure Marie; Mastroserio, Annalisa; Masui, Hiroshi; Matyja, Adam Tomasz; Mayer, Christoph; Mazer, Joel Anthony; Mazzoni, Alessandra Maria; Mcdonald, Daniel; Meddi, Franco; Melikyan, Yuri; Menchaca-Rocha, Arturo Alejandro; Meninno, Elisa; Mercado-Perez, Jorge; Meres, Michal; Miake, Yasuo; Mieskolainen, Matti Mikael; Mikhaylov, Konstantin; Milano, Leonardo; Milosevic, Jovan; Minervini, Lazzaro Manlio; Mischke, Andre; Mishra, Aditya Nath; Miskowiec, Dariusz Czeslaw; Mitra, Jubin; Mitu, Ciprian Mihai; Mohammadi, Naghmeh; Mohanty, Bedangadas; Molnar, Levente; Montano Zetina, Luis Manuel; Montes Prado, Esther; Morando, Maurizio; Moreira De Godoy, Denise Aparecida; Moretto, Sandra; Morreale, Astrid; Morsch, Andreas; Muccifora, Valeria; Mudnic, Eugen; Muhlheim, Daniel Michael; Muhuri, Sanjib; Mukherjee, Maitreyee; Mulligan, James Declan; Gameiro Munhoz, Marcelo; Murray, Sean; Musa, Luciano; Musinsky, Jan; Nandi, Basanta Kumar; Nania, Rosario; Nappi, Eugenio; Naru, Muhammad Umair; Nattrass, Christine; Nayak, Kishora; Nayak, Tapan Kumar; Nazarenko, Sergey; Nedosekin, Alexander; Nellen, Lukas; Ng, Fabian; Nicassio, Maria; Niculescu, Mihai; Niedziela, Jeremi; Nielsen, Borge Svane; Nikolaev, Sergey; Nikulin, Sergey; Nikulin, Vladimir; Noferini, Francesco; Nomokonov, Petr; Nooren, Gerardus; Cabanillas Noris, Juan Carlos; Norman, Jaime; Nyanin, Alexander; Nystrand, Joakim Ingemar; Oeschler, Helmut Oskar; Oh, Saehanseul; Oh, Sun Kun; Ohlson, Alice Elisabeth; Okatan, Ali; Okubo, Tsubasa; Olah, Laszlo; Oleniacz, Janusz; Oliveira Da Silva, Antonio Carlos; Oliver, Michael Henry; Onderwaater, Jacobus; Oppedisano, Chiara; Orava, Risto; Ortiz Velasquez, Antonio; Oskarsson, Anders Nils Erik; Otwinowski, Jacek Tomasz; Oyama, Ken; Ozdemir, Mahmut; Pachmayer, Yvonne Chiara; Pagano, Paola; Paic, Guy; Pajares Vales, Carlos; Pal, Susanta Kumar; Pan, Jinjin; Pandey, Ashutosh Kumar; Pant, Divyash; Papcun, Peter; Papikyan, Vardanush; Pappalardo, Giuseppe; Pareek, Pooja; Park, Woojin; Parmar, Sonia; Passfeld, Annika; Paticchio, Vincenzo; Patra, Rajendra Nath; Paul, Biswarup; Peitzmann, Thomas; Pereira Da Costa, Hugo Denis Antonio; Pereira De Oliveira Filho, Elienos; Peresunko, Dmitry Yurevich; Perez Lara, Carlos Eugenio; Perez Lezama, Edgar; Peskov, Vladimir; Pestov, Yury; Petracek, Vojtech; Petrov, Viacheslav; Petrovici, Mihai; Petta, Catia; Piano, Stefano; Pikna, Miroslav; Pillot, Philippe; Pinazza, Ombretta; Pinsky, Lawrence; Piyarathna, Danthasinghe; Ploskon, Mateusz Andrzej; Planinic, Mirko; Pluta, Jan Marian; Pochybova, Sona; Podesta Lerma, Pedro Luis Manuel; Poghosyan, Martin; Polishchuk, Boris; Poljak, Nikola; Poonsawat, Wanchaloem; Pop, Amalia; Porteboeuf, Sarah Julie; Porter, R Jefferson; Pospisil, Jan; Prasad, Sidharth Kumar; Preghenella, Roberto; Prino, Francesco; Pruneau, Claude Andre; Pshenichnov, Igor; Puccio, Maximiliano; Puddu, Giovanna; Pujahari, Prabhat Ranjan; Punin, Valery; Putschke, Jorn Henning; Qvigstad, Henrik; Rachevski, Alexandre; Raha, Sibaji; Rajput, Sonia; Rak, Jan; Rakotozafindrabe, Andry Malala; Ramello, Luciano; Raniwala, Rashmi; Raniwala, Sudhir; Rasanen, Sami Sakari; Rascanu, Bogdan Theodor; Rathee, Deepika; Read, Kenneth Francis; Real, Jean-Sebastien; Redlich, Krzysztof; Reed, Rosi Jan; Rehman, Attiq Ur; Reichelt, Patrick Simon; Reidt, Felix; Ren, Xiaowen; Renfordt, Rainer Arno Ernst; Reolon, Anna Rita; Reshetin, Andrey; Rettig, Felix Vincenz; Revol, Jean-Pierre; Reygers, Klaus Johannes; Riabov, Viktor; Ricci, Renato Angelo; Richert, Tuva Ora Herenui; Richter, Matthias Rudolph; Riedler, Petra; Riegler, Werner; Riggi, Francesco; Ristea, Catalin-Lucian; Rivetti, Angelo; Rocco, Elena; Rodriguez Cahuantzi, Mario; Rodriguez Manso, Alis; Roeed, Ketil; Rogochaya, Elena; Rohr, David Michael; Roehrich, Dieter; Romita, Rosa; Ronchetti, Federico; Ronflette, Lucile; Rosnet, Philippe; Rossi, Andrea; Roukoutakis, Filimon; Roy, Ankhi; Roy, Christelle Sophie; Roy, Pradip Kumar; Rubio Montero, Antonio Juan; Rui, Rinaldo; Russo, Riccardo; Ryabinkin, Evgeny; Ryabov, Yury; Rybicki, Andrzej; Sadovskiy, Sergey; Safarik, Karel; Sahlmuller, Baldo; Sahoo, Pragati; Sahoo, Raghunath; Sahoo, Sarita; Sahu, Pradip Kumar; Saini, Jogender; Sakai, Shingo; Saleh, Mohammad Ahmad; Salgado Lopez, Carlos Alberto; Salzwedel, Jai Samuel Nielsen; Sambyal, Sanjeev Singh; Samsonov, Vladimir; Sanchez Castro, Xitzel; Sandor, Ladislav; Sandoval, Andres; Sano, Masato; Sarkar, Debojit; Scapparone, Eugenio; Scarlassara, Fernando; Scharenberg, Rolf Paul; Schiaua, Claudiu Cornel; Schicker, Rainer Martin; Schmidt, Christian Joachim; Schmidt, Hans Rudolf; Schuchmann, Simone; Schukraft, Jurgen; Schulc, Martin; Schuster, Tim Robin; Schutz, Yves Roland; Schwarz, Kilian Eberhard; Schweda, Kai Oliver; Scioli, Gilda; Scomparin, Enrico; Scott, Rebecca Michelle; Seger, Janet Elizabeth; Sekiguchi, Yuko; Sekihata, Daiki; Selyuzhenkov, Ilya; Senosi, Kgotlaesele; Seo, Jeewon; Serradilla Rodriguez, Eulogio; Sevcenco, Adrian; Shabanov, Arseniy; Shabetai, Alexandre; Shadura, Oksana; Shahoyan, Ruben; Shangaraev, Artem; Sharma, Ankita; Sharma, Mona; Sharma, Monika; Sharma, Natasha; Shigaki, Kenta; Shtejer Diaz, Katherin; Sibiryak, Yury; Siddhanta, Sabyasachi; Sielewicz, Krzysztof Marek; Siemiarczuk, Teodor; Silvermyr, David Olle Rickard; Silvestre, Catherine Micaela; Simatovic, Goran; Simonetti, Giuseppe; Singaraju, Rama Narayana; Singh, Ranbir; Singha, Subhash; Singhal, Vikas; Sinha, Bikash; Sarkar - Sinha, Tinku; Sitar, Branislav; Sitta, Mario; Skaali, Bernhard; Slupecki, Maciej; Smirnov, Nikolai; Snellings, Raimond; Snellman, Tomas Wilhelm; Soegaard, Carsten; Soltz, Ron Ariel; Song, Jihye; Song, Myunggeun; Song, Zixuan; Soramel, Francesca; Sorensen, Soren Pontoppidan; Spacek, Michal; Spiriti, Eleuterio; Sputowska, Iwona Anna; Spyropoulou-Stassinaki, Martha; Srivastava, Brijesh Kumar; Stachel, Johanna; Stan, Ionel; Stefanek, Grzegorz; Steinpreis, Matthew Donald; Stenlund, Evert Anders; Steyn, Gideon Francois; Stiller, Johannes Hendrik; Stocco, Diego; Strmen, Peter; Alarcon Do Passo Suaide, Alexandre; Sugitate, Toru; Suire, Christophe Pierre; Suleymanov, Mais Kazim Oglu; Sultanov, Rishat; Sumbera, Michal; Symons, Timothy; Szabo, Alexander; Szanto De Toledo, Alejandro; Szarka, Imrich; Szczepankiewicz, Adam; Szymanski, Maciej Pawel; Takahashi, Jun; Tambave, Ganesh Jagannath; Tanaka, Naoto; Tangaro, Marco-Antonio; Tapia Takaki, Daniel Jesus; Tarantola Peloni, Attilio; Tarhini, Mohamad; Tariq, Mohammad; Tarzila, Madalina-Gabriela; Tauro, Arturo; Tejeda Munoz, Guillermo; Telesca, Adriana; Terasaki, Kohei; Terrevoli, Cristina; Teyssier, Boris; Thaeder, Jochen Mathias; Thomas, Deepa; Tieulent, Raphael Noel; Timmins, Anthony Robert; Toia, Alberica; Trogolo, Stefano; Trubnikov, Victor; Trzaska, Wladyslaw Henryk; Tsuji, Tomoya; Tumkin, Alexandr; Turrisi, Rosario; Tveter, Trine Spedstad; Ullaland, Kjetil; Uras, Antonio; Usai, Gianluca; Utrobicic, Antonija; Vajzer, Michal; Vala, Martin; Valencia Palomo, Lizardo; Vallero, Sara; Van Der Maarel, Jasper; Van Hoorne, Jacobus Willem; Van Leeuwen, Marco; Vanat, Tomas; Vande Vyvre, Pierre; Varga, Dezso; Vargas Trevino, Aurora Diozcora; Vargyas, Marton; Varma, Raghava; Vasileiou, Maria; Vasiliev, Andrey; Vauthier, Astrid; Vechernin, Vladimir; Veen, Annelies Marianne; Veldhoen, Misha; Velure, Arild; Venaruzzo, Massimo; Vercellin, Ermanno; Vergara Limon, Sergio; Vernet, Renaud; Verweij, Marta; Vickovic, Linda; Viesti, Giuseppe; Viinikainen, Jussi Samuli; Vilakazi, Zabulon; Villalobos Baillie, Orlando; Vinogradov, Alexander; Vinogradov, Leonid; Vinogradov, Yury; Virgili, Tiziano; Vislavicius, Vytautas; Viyogi, Yogendra; Vodopyanov, Alexander; Volkl, Martin Andreas; Voloshin, Kirill; Voloshin, Sergey; Volpe, Giacomo; Von Haller, Barthelemy; Vorobyev, Ivan; Vranic, Danilo; Vrlakova, Janka; Vulpescu, Bogdan; Vyushin, Alexey; Wagner, Boris; Wagner, Jan; Wang, Hongkai; Wang, Mengliang; Wang, Yifei; Watanabe, Daisuke; Watanabe, Yosuke; Weber, Michael; Weber, Steffen Georg; Wessels, Johannes Peter; Westerhoff, Uwe; Wiechula, Jens; Wikne, Jon; Wilde, Martin Rudolf; Wilk, Grzegorz Andrzej; Wilkinson, Jeremy John; Williams, Crispin; Windelband, Bernd Stefan; Winn, Michael Andreas; Yaldo, Chris G; Yang, Hongyan; Yang, Ping; Yano, Satoshi; Yin, Zhongbao; Yokoyama, Hiroki; Yoo, In-Kwon; Yurchenko, Volodymyr; Yushmanov, Igor; Zaborowska, Anna; Zaccolo, Valentina; Zaman, Ali; Zampolli, Chiara; Correia Zanoli, Henrique Jose; Zaporozhets, Sergey; Zardoshti, Nima; Zarochentsev, Andrey; Zavada, Petr; Zavyalov, Nikolay; Zbroszczyk, Hanna Paulina; Zgura, Sorin Ion; Zhalov, Mikhail; Zhang, Haitao; Zhang, Xiaoming; Zhang, Yonghong; Zhao, Chengxin; Zhigareva, Natalia; Zhou, Daicui; Zhou, You; Zhou, Zhuo; Zhu, Hongsheng; Zhu, Jianhui; Zhu, Xiangrong; Zichichi, Antonino; Zimmermann, Alice; Zimmermann, Markus Bernhard; Zinovjev, Gennady; Zyzak, Maksym

    2016-01-01

    Transverse momentum ($p_{\\rm{T}}$) spectra of pions, kaons, and protons up to $p_{\\rm{T}} = 20$ GeV/$c$ have been measured in Pb-Pb collisions at $\\sqrt{s_{\\rm NN}} = 2.76$ TeV using the ALICE detector for six different centrality classes covering 0-80%. The proton-to-pion and the kaon-to-pion ratios both show a distinct peak at $p_{\\rm{T}} \\approx 3$ GeV/$c$ in central Pb-Pb collisions that decreases towards more peripheral collisions. For $p_{\\rm{T}} > 10$ GeV/$c$, the nuclear modification factor is found to be the same for all three particle species in each centrality interval within systematic uncertainties of 10-20%. This suggests there is no direct interplay between the energy loss in the medium and the particle species composition in the hard core of the quenched jet. For $p_{\\rm{T}} < 10$ GeV/$c$, the data provide important constraints for models aimed at describing the transition from soft to hard physics.

  3. Visual system of recovering and combination of information for ENDF (Evaluated Nuclear Data File) format libraries; Sistema visual de recuperacao e combinacao de informacoes para bibliotecas no formato ENDF (Evaluated Nuclear Data File)

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Claudia A.S. Velloso [Centro Tecnico Aeroespacial, Sao Jose dos Campos, SP (Brazil); Corcuera, Raquel A. Paviotti [Instituto Nacional de Pesquisas Espaciais (INPE), Sao Jose dos Campos, SP (Brazil)

    1997-04-01

    This report presents a data information retrieval and merger system for ENDF (Evaluated Nuclear Data File) format libraries, which can be run on personal computers under the Windows {sup TM} environment. The input is the name of an ENDF/B library, which can be chosen in a proper window. The system has a display function which allows the user to visualize the reaction data of a specific nuclide and to produce a printed copy of these data. The system allows the user to retrieve and/or combine evaluated data to create a single file of data in ENDF format, from a number of different files, each of which is in the ENDF format. The user can also create a mini-library from an ENDF/B library. This interactive and easy-to-handle system is a useful tool for Nuclear Data Centers and it is also of interest to nuclear and reactor physics researchers. (author)

  4. BUTREN-RC an hybrid system for the recharges optimization of nuclear fuels in a BWR; BUTREN-RC un sistema hibrido para la optimizacion de recargas de combustible nuclear en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz S, J.J.; Castillo M, J.A. [ININ, Carretera Mexico-Toluca Km. 36.5, 52045 Estado de Mexico (Mexico); Valle G, E. del [IPN, ESFM, 07738 Mexico D.F. (Mexico)

    2004-07-01

    The obtained results with the hybrid system BUTREN-RC are presented that obtains recharges of nuclear fuel for a BWR type reactor. The system has implemented the methods of optimization heuristic taboo search and neural networks. The optimization it carried out with the technique of taboo search, and the neural networks, previously trained, were used to predict the behavior of the recharges of fuel, in substitution of commercial codes of reactor simulation. The obtained recharges of nuclear fuel correspond to 5 different operation cycles of the Laguna Verde Nuclear Power plant, Veracruz in Mexico. The obtained results were compared with the designs of this cycles. The energy gain with the recharges of fuel proposals is of approximately 4.5% with respect to those of design. The time of compute consumed it was considerably smaller that when a commercial code for reactor simulation is used. (Author)

  5. Integrated scheme of long-term for spent fuel management of power nuclear reactors; Esquema integrado de largo plazo para la administracion de combustible gastado de reactores nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-15

    After of irradiation of the nuclear fuel in the reactor core, is necessary to store it for their cooling in the fuel pools of the reactor. This is the first step in a processes series before the fuel can reach its final destination. Until now there are two options that are most commonly accepted for the end of the nuclear fuel cycle, one is the open nuclear fuel cycle, requiring a deep geological repository for the fuel final disposal. The other option is the fuel reprocessing to extract the plutonium and uranium as valuable materials that remaining in the spent fuel. In this study the alternatives for the final part of the fuel cycle, which involves the recycling of plutonium and the minor actinides in the same reactor that generated them are shown. The results shown that this is possible in a thermal reactor and that there are significant reductions in actinides if they are recycled into reactor fuel. (Author)

  6. Apoyo a la innovación tecnológica en América Central: La experiencia del Fondo para la Modernización Tecnológica y Empresarial de Panamá

    OpenAIRE

    Pablo Angelelli; Nicolo Gligo

    2002-01-01

    En el presente documento se evalúan los resultados de una reciente experiencia de apoyo a la innovación en Centroamérica, el Fondo para la Modernización Tecnológica y Empresarial de Panamá (FOMOTEC), y se los compara con los del Fondo Nacional de Desarrollo Tecnológico y Productivo de Chile (FONTEC). A partir de ello se identifican lecciones y recomendaciones de política para el diseño de políticas de innovación tecnológica en la pequeña empresa, en particular para los países de América Latin...

  7. Recursos genéticos de los hongos del maguey (pleurotus sp.) de la región central de México: caracterización y selección de genotipos con potencial para la producción rural.

    OpenAIRE

    Ramírez Carrasco, Angelina Patricia

    2011-01-01

    México cuenta con una gran diversidad biológica, sin embargo, poco se han aprovechado los recursos genéticos nativos para la producción comercial de hongos comestibles. En esta investigación se recolectaron y caracterizaron diversos genotipos de Pleurotus que crecían silvestres sobre plantas de Agave en el altiplano de la región central de México. Estos hongos comestibles son consumidos por las comunidades locales durante la época de lluvias, a los cuales denominan como “Hongos del Maguey”. ...

  8. Commercial nuclear power 1989

    International Nuclear Information System (INIS)

    This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. 39 tabs

  9. Life time of nuclear power plants and new types of reactors; La duree de vie des centrales nucleaires et les nouveaux types de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-01

    This report, realized by the Evaluation Parliamentary Office of scientific and technological choices, aims to answer simple but fundamental questions for the french electric power production. What are the phenomena which may limit the exploitation time of nuclear power plants? How can we fight against the aging, at which cost and with which safety? The first chapter presents the management of the nuclear power plants life time, an essential element of the park optimization but not a sufficient element. The second chapter details the EPR and the other reactors for 2015 as a bond between the today and tomorrow parks. The last chapter deals with the necessity of efforts in the research and development to succeed in 2035 and presents other reactors in project. (A.L.B.)

  10. Desarrollo de una metodología de simulación de secuencias en accidente en centrales nucleares de agua ligera considerando actuaciones del operador

    OpenAIRE

    Expósito Lorenzo, Antonio

    2006-01-01

    This thesis presents the work carried out to develop a simulation system for nuclear power plants, denominated TRETA / COPMA-III integrated simulator, which allows the simulation of the thermalhydraulic processes that take place in this type of facilities, in normal operation and emergency operation, as well as the control room crew actions related with the management of the emergency situations. The simulation of the thermalhydraulic processes is carried out by means of the TR...

  11. Preparation of the Improved Technical Specifications of Nuclear Almaraz, Asco and Vandellos; Procedimiento de elaboracion de las Especificaciones Tecnicas Mejoradas de las Centrales de Almaraz Asco y Vandellos

    Energy Technology Data Exchange (ETDEWEB)

    Fuente, I.; Mirallas, F.; Garcia, M. D.

    2012-07-01

    In 2010 the Nuclear Almaraz, Asco and Vandellos agreed with the CSN start the transition project to the Improved Plant Technical Specifications (IPTSs), with reference the Rev. 3.1 of NUREG-1431. In April 2012 has been published the Rev. 4.0 of NUREG and have decided to adapt the IPTSs to the content of this new revision. The project for the three plants is developed in parallel, which allows to optimize the process.

  12. Factor analysis for the adoption of nuclear technology in diagnosis and treatment of chronic diseases; Analise de fatores para adocao da tecnologia nuclear no diagnostico e tratamento de doencas cronicas

    Energy Technology Data Exchange (ETDEWEB)

    Sato, Renato Cesar, E-mail: rcsato@unifesp.br [Universidade Federal de Sao Paulo - UNIFESP, Sao Paulo (SP), (Brazil); Zouain, Desiree Moraes [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2012-07-01

    To identify and evaluate latent variables (variables that are not directly observed) for adopting and using nuclear technologies in diagnosis and treatment of chronic diseases. The measurement and management of these latent factors are important for health care due to complexities of the sector. Methods: An exploratory factor analysis study was conducted among 52 physicians practicing in the areas of Cardiology, Neurology and Oncology in the State of Sao Paulo who agreed to participate in the study between 2009 and 2010. Data were collected using an attitude measurement questionnaire, and analyzed according to the principal component method with Varimax rotation. Results: The component matrix after factor rotation showed three elucidative groups arranged according to demand for nuclear technology: clinical factors, structural factors, and technological factors. Clinical factors included questionnaire answers referring to medical history, previous interventions, complexity and chronicity of the disease. Structural factors included patient age, physician's practice area, and payment ability. Technological factors included prospective growth in the use of nuclear technology and availability of services. Conclusions: The clinical factors group dimension identified in the study included patient history, prior interventions, and complexity and chronicity of the disease. This dimension is the main motivating for adopting nuclear technology in diagnosis and treatment of chronic diseases. (author)

  13. Thermodynamic study of residual heat from a high temperature nuclear reactor to analyze its viability in cogeneration processes; Estudio termodinamico del calor residual de un reactor nuclear de alta temperatura para analizar su viabilidad en procesos de cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Santillan R, A.; Valle H, J.; Escalante, J. A., E-mail: santillanaura@gmail.com [Universidad Politecnica Metropolitana de Hidalgo, Boulevard acceso a Tolcayuca 1009, Ex-Hacienda San Javier, 43860 Tolcayuca, Hidalgo (Mexico)

    2015-09-15

    In this paper the thermodynamic study of a nuclear power plant of high temperature at gas turbine (GTHTR300) is presented for estimating the exploitable waste heat in a process of desalination of seawater. One of the most studied and viable sustainable energy for the production of electricity, without the emission of greenhouse gases, is the nuclear energy. The fourth generation nuclear power plants have greater advantages than those currently installed plants; these advantages have to do with security, increased efficiencies and feasibility to be coupled to electrical cogeneration processes. In this paper the thermodynamic study of a nuclear power plant type GTHTR300 is realized, which is selected by greater efficiencies and have optimal conditions for use in electrical cogeneration processes due to high operating temperatures, which are between 700 and 950 degrees Celsius. The aim of the study is to determine the heat losses and the work done at each stage of the system, determining where they are the greatest losses and analyzing in that processes can be taken advantage. Based on the study was appointed that most of the energy losses are in form of heat in the coolers and usually this is emitted into the atmosphere without being used. From the results a process of desalination of seawater as electrical cogeneration process is proposed. This paper contains a brief description of the operation of the nuclear power plant, focusing on operation conditions and thermodynamic characteristics for the implementation of electrical cogeneration process, a thermodynamic analysis based on mass and energy balance was developed. The results allow quantifying the losses of thermal energy and determining the optimal section for coupling of the reactor with the desalination process, seeking to have a great overall efficiency. (Author)

  14. Evolution of Technology Laser Scanner. Implications for use in Nuclear Power and Radioactive Facilities; Evolucion de la Tecnologia Laser Escaner. Implicaciones en uso en Centrales Nucleares e Instalaciones Radioactivas

    Energy Technology Data Exchange (ETDEWEB)

    Sarti Fernandez, F.; Bonet, J.

    2012-07-01

    The main technical factors affecting these teams their actual implementation in nuclear power plants will be analyzed: data acquisition speed, sensitivity, laser power, autonomy, contamination of equipment, radiation effect, etc. In conclusion, the real difference is displayed in the data collection in function of various technologies, embodied in field time, and costs.

  15. Follow-up of the results of the nuclear power plant stress tests and action plan.; Seguimiento de los resultados de las pruebas de resistencia de las centrales nucleares y plan de accion

    Energy Technology Data Exchange (ETDEWEB)

    Mellado Jimenez, I.

    2012-07-01

    The results of the stress tests carried out by the European nuclear power plants in the wake of the Fukushima Daiichi accident, subsequently subjected to peer reviews, have made it possible to identify the measures to be applied to improve safety. Action plans have been put in place to implement these measures within appropriate time frames. (Author)

  16. Aplicación del modelo Servqual y herramientas de ingeniería de la calidad para la planificación del servicio en la Biblioteca Central de la Universidad de Antioquia

    OpenAIRE

    Uriel Pineda; Margarita Estrada; Carlos Mario Parra

    2011-01-01

    This article is the result of research conducted at the University of Antioquia Central Library in 2010. The formulated questions were: what are the fundamentals that affect the quality of service perceived by users of the Central Library of the University of Antioquia? How to establish adequate service standards to meet the requirements of users overcome the practice of only meeting the minimum quality requirements? The research design was descriptive type. The SERVQUAL model was applied wit...

  17. The political economics of the permanent war and the political economics of the nuclear war. Strategic approaches for Latin America; La economia politica de la guerra permanente y la economia politica de la guerra nuclear. Aproximaciones estrategicas para America Latina

    Energy Technology Data Exchange (ETDEWEB)

    Gomez L, I.I

    2005-07-01

    This work treats on the hypothesis that the American imperialism uses its nuclear arsenal for reforming geographical spaces that allow him to impel its economic development in the context of the progressive exhaustion of the natural resources of the planet and of the ferocious dispute for market niches and investment destinations, and like the political and military decisions crawl to the different scenarios of economic competition. In the chapter 1 it is insinuated like has been reproduced the Warlike-industrial Complex (CBI) American from the second world postwar period until the present time in the idea of explaining like it is that it is valorized to the capital in scale enlarged starting from the denominated sector producing of destruction means and understanding that the system specifically capitalist is a system where continually the is destroyed previously taken place to manufacture a new merchandise in a luck of creative destruction. In the chapter 2, the topic of the specific contradictions of the CBI is approached that disable him to be the tip of lance of the world imperialism. The chapter 3 try on the productive linkages in the production of nuclear bombs, as well as in the production of the vectors of nuclear transportation and on the implications derived for the world security of the different industries associated to the nuclear energy (as the petroleum, the electricity, the natural gas) and to the transportation vectors of these locating which you/they are the different States where the world supremacy is disputed and that they have like one of its so many negotiation-confrontation letters its nuclear strategic arsenals. What is looked for in a thermonuclear war is the enemy's total elimination, from their offensive capacity, their defensive capacity, until their supplies, their reservations, etc., with the result that the chapters 4 and 5 of this thesis are presented to offer a better understanding that they mean the nuclear arsenals in the

  18. Nuclear fragmentation in central collisions: Ni + Au from 32 to 90 A*MeV; Fragmentation dans les collisions centrales du systeme Ni + Au de 32 a 90 A MeV

    Energy Technology Data Exchange (ETDEWEB)

    Bellaize, N

    2000-11-03

    Heavy ion collisions are one of tools for studying nuclear system far away from its equilibrium state. This work concerns the most violent collisions in the Ni + Au system for incident energies ranging from 32 up to 90 AMeV. These events were detected with the multidetector INDRA and selected by the Principal Component Analysis (multidimensional analysis). This method classifies the events according their detection features and their degree of dissipation. We observed two deexcitation mechanisms: a fusion/fission - evaporation process and a multifragmentation process. Those two coexist from 32 to 52 AMeV whereas only one subsists at 90 AMeV. For those two mechanisms, an component was observed which seems to be linked to the initial phase of the reaction. The energy fluctuations of this component leads to variations in the energy deposit which determines the deexcitation of the system. The experimental multifragmentation data of the Ni + Au system (52 and 90 AMeV) were compared to the predictions of a statistical model and to the experimental data of the system Xe + Sn at 50 AMeV (also detected with INDRA). These comparisons show the lack of collective radial energy for fragments (Z{>=}10) in the Ni + Au system, and show that the degree of multifragmentation depends of the thermal excitation energy. Mean kinetic energies of particles and lights fragments (Z{>=}10) are larger in the Ni + Au system than the Xe + Sn system. This observation shows that these particles are more sensitive to the entrance channel for an asymmetric system than for a symmetric system (for the same number of nucleons). (author)

  19. Validation of a methodology for the study of generation cost of electric power for nuclear power plants; Validacion de una metodologia para el estudio de costos de generacion de electricidad de plantas nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Ortega C, R.F.; Martin del Campo M, C. [Facultad de Ingenieria, UNAM, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550, Jiutepec, Morelos (Mexico)]. E-mail: rfortega@mexis.com

    2004-07-01

    It was developed a model for the calculation of costs of electric generation of nuclear plants. The developed pattern was validated with the one used by the United States Council for Energy Awareness (USCEA) and the Electric Power Research Institute (EPRI), in studies of comparison of alternatives for electric generation of nuclear plants and fossil plants with base of gas and of coal in the United States described in the guides calls Technical Assessment Guides of EPRI. They are mentioned in qualitative form some changes in the technology of nucleo electric generation that could be included in the annual publication of Costs and Parameters of Reference for the Formulation of Projects of Investment in the Electric Sector of the Federal Commission of Electricity. These changes are in relation to the advances in the technology, in the licensing, in the construction and in the operation of the reactors called advanced as the A BWR built recently in Japan. (Author)

  20. Nuclear energy in Mexico as alternative for the reduction of CO{sub 2} emissions; Energia nuclear en Mexico, como alternativa para la reduccion de emisiones de CO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, G.; Ramirez, J. R.; Palacios, J. C., E-mail: gustavo.alonso@inin.gob.m [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2011-07-01

    One of the main concerns related with global warming is the reduction of the green house emissions. Mexico is taking steps to solve this problem, in its recent National Energy Strategy has considered to increase the use of clean electricity sources up to a 35% the share to be meat at 2024, currently this participation in electricity generation is 23.9%. In 2008 the Mexican Electrical Network produced 0.466 tons of CO{sub 2}/MWh, this index is above the OECD 0.45 CO{sub 2}/MWh average value. The current study considers the use of nuclear energy as part of the addition of clean energy to the Electrical grid; it proposes the capacity and the numbers of nuclear reactors to be used and it provides the emissions scenario generated with this proposal. (Author)