WorldWideScience

Sample records for central nuclear para

  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. Engineering for new-built nuclear power plant projects; Ingenieria para proyectos de nuevas centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Lopez, A.

    2012-11-01

    This article reviews the opportunities existing in the market (electrical utilities and reactor vendors) for an engineering company with the profile of Empresarios Agrupados (EA) in new-built nuclear power plant projects. To do this, reference is made to some representative examples of projects in which EA has been participating recently. the article concludes sharing with the reader some lessons learned from this participation. (Author)

  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. Experiences in the computerized control rooms design for Nuclear Power Plants; Experiencias en el diseno de salas de control computarizadas para centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Moyano de la Heras, N.; Fernandez Illobre, L.; Valdivia Martin, C.

    2010-07-01

    This paper presents Tecnatom experiences obtained during the control rooms design for the Fuming and Fangjiasham Nuclear Power Plants (CPR type). These are two different locations where two pressurized water reactors, with three loops each one, will be installed.

  5. 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)

  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. Model of automatic fuel management for the Atucha II nuclear central with the PUMA IV code; Modelo de gestion automatica de combustible para la Central Nuclear Atucha II con el codigo PUMA IV

    Energy Technology Data Exchange (ETDEWEB)

    Marconi G, J.F.; Tarazaga, A.E.; Romero, L.D. [CNEA, Av. Gral. Paz 1499 San Martin-Bs. As. (Argentina)]. e-mail: marconi@cnea.gov.ar

    2007-07-01

    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)

  8. 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)

  9. Métodos de análisis de sucesos notificables en centrales nucleares para su valoración como sucesos iniciadores de accidentes y su clasificación en la escala de seguridad INES. Aplicación en las centrales nucleares catalanas

    OpenAIRE

    2005-01-01

    En la actualidad, la explotación de las centrales nucleares españolas está sujeta al cumplimiento por parte de los titulares de una serie de condiciones sobre seguridad nuclear y protección radiológica según Orden Ministerial vigente. De este modo, entre los requisitos a cumplir por parte de las instalaciones nucleares figura la obligación de remitir al organismo responsable (Consejo de Seguridad Nuclear, CSN) una serie de información sobre el funcionamiento de cada central, ex...

  10. Technical and economic proposal for the extension of the Laguna Verde Nuclear Power plant with an additional nuclear reactor; Propuesta tecnica y economica para la ampliacion de la Central Nucleoelectrica Laguna Verde con un reactor nuclear adicional

    Energy Technology Data Exchange (ETDEWEB)

    Leal C, C.D.; Francois L, J.L. [Facultad de Ingenieria, UNAM, Circuito Interior, C.U. Coyoacan, 04510 Mexico D.F. (Mexico)]. e-mail: carlosdanielleal@yahoo.com.mx

    2006-07-01

    The increment of the human activities in the industrial environments and of generation of electric power, through it burns it of fossil fuels, has brought as consequence an increase in the atmospheric concentrations of the calls greenhouse effect gases and, these in turn, serious repercussions about the environment and the quality of the alive beings life. The recent concern for the environment has provoked that industrialized countries and not industrialized carry out international agreements to mitigate the emission from these gases to the atmosphere. Our country, like part of the international community, not is exempt of this problem for what is necessary that programs begin guided toward the preservation of the environment. As for the electric power generation, it is indispensable to diversify the sources of primary energy; first, to knock down the dependence of the hydrocarbons and, second, to reduce the emission of polluting gases to the atmosphere. In this item, the nucleo electric energy not only has proven to be safe and competitive technical and economically, able to generate big quantities of electric power with a high plant factor and a considerable cost, but rather also, it is one of the energy sources that less pollutants it emits to the atmosphere. The main object of this work is to carry out a technical and economic proposal of the extension of the Laguna Verde Nuclear power plant (CNLV) with a new nuclear reactor of type A BWR (Advanced Boiling Water Reactor), evolutionary design of the BWR technology to which belong the two reactors installed at the moment in the plant, with the purpose of increasing the installed capacity of generation of the CNLV and of the Federal Commission of Electricity (CFE) with foundation in the sustainable development and guaranteeing the protection of the environment by means of the exploitation of a clean and sure technology that counts at the moment with around 12,000 year-reactor of operational experience in more of

  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. 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.

  13. Introduction of fuel GE14 in the nuclear power plant of Laguna Verde for the extended increase of power; Introduccion del combustible GE14 en la central nuclear Laguna Verde para el aumento de potencia extendido

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, N.; Vargas A, A. F.; Cardenas J, J. B.; Contreras C, P. [CFE, Central Nuclear Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5 (Mexico)]. e-mail: natividad.hernandez@cfe.gob.mx

    2008-07-01

    The project of extended increase of power responds to a necessity of electrical energy in the country, increasing the thermal exit of the reactors of the nuclear power plant of Laguna Verde of 2027 MWt to 2317 MWt. In order to support this transition, changes will make in the configuration of the reactor core and in the operation strategies of the cycle, also they will take initiatives to optimize the economy in fuel cycle. At present in both reactors of the nuclear plant of Laguna Verde fuel GE12 is used. The fuel GE14 presents displays with respect to the GE12, some improvements in the mechanical design and consequently in its performance generally. Between these improvements we can mention: 1. Spacers of high performance. 2. Shielding with barrier. 3. Filter for sweepings {sup d}ebris{sup a}nd 4. Fuel rods of minor partial length. The management of nuclear power plants has decided to introduce the use of fuel GE14 in Laguna Verde in the reload 14 for Unit 1 and of the reload 10 for Unit 2. The process of new introduction fuel GE14 consists of two stages, first consists on subjecting the one new design of fuel to the regulator organism in the USA: Nuclear Regulatory Commission, in Mexico the design must be analyzed and authorized by the National Commission of Nuclear Safety and Safeguards, for its approval of generic form, by means of the demonstration of the fulfillment with the amendment 22 of GESTAR II, the second stage includes the specific analyses of plant to justify the use of the new fuel design in a reload core. The nuclear plant of Laguna Verde would use some of the results of the security analyses that have been realized for the project of extended increase of power with fuel GE14, to document the specific analyses of plant with the new fuel design. The result of the analyses indicates that the reload lots are increased of 116-120 assemblies in present conditions (2027 MWt) to 140-148 assemblies in conditions of extended increase of power (2317 MWt

  14. 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.

  15. 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)

  16. 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)

  17. 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)

  18. Westinghouse experiences with HTR as the basis for design of the New Generation of Nuclear Power Plants (NGNP); Experiencias de Estinghouse con el HTR como Base para el diseno de la Nueva Generacion de Centrales Nucleares (BGNP)

    Energy Technology Data Exchange (ETDEWEB)

    Schoning, J.; Esch, M.; Knoche, D.; Freis, D.; Finken, H.; Drifhout, F.

    2010-07-01

    For more than three decades Germany had a very ambitious High Temperature Reactor (HTR) program which included numerous research activities and the construction and operation of two HTRs. The whole program had a volume of more than 6 billion D-Marks and covered activities of industry, research centres and universities. Within this program the physical feasibility of a pebble bed HTR was power for the first time in the Arbeitsgemeinschaft Versuchsreaktor (AVR) research reactor at Research Centre Julich (FZJ). Later it served as a test bed for new developed fuel as well as test reactor for numerous successful experiments on the inherent safety of this special type of nuclear reactor. The subsequent power plant THTR-300 with a rated electrical power of 300 MWel at Hamm-Uentrop was constructed as a demonstration plant. With THTR-300 the feasibility of a large commercial pebble bed reactor was demonstrated. Both reactors were built in the state of North-Rhine Westphalia with its traditional resources of coal and its heavy and chemical industry. HTRs were specifically meant to provide process heat to these industries and with the Project Nuclear Process Heat (PNP) a plant was developed to serve this means. Based on this HTR specific expertise and on actual experience from AP1000TM development and construction, Westinghouse has the overall expertise in house to design a generation IV reactor system in the near term future. On HTR specific systems and components the maturity of the technology was demonstrated with THTR-300. Potential design approaches for future HTR concepts for process heat generation are discussed. (Author) 1 refs.

  19. 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…

  20. Jose Cabrera NPP; Central Nuclear Jose Cabrera

    Energy Technology Data Exchange (ETDEWEB)

    Diez, P.

    2004-07-01

    During 2003, the Jose Cabrera nuclear power plant (JCNPP) operated without any incidents involving an undue risk to the population or environment. The year 2003 was the Plant's 35th year of operation, and during that time it has provided 33.209 million kilowatt-hours to the electric grid. The Plant set a record for continuous operation with 386 days of uninterrupted operation. The Plant had an outage for the 27th refueling and for equipment and systems maintenance, inspection and testing activities. The Plant reported nine events to the Administration that were classified as zero on the International Nuclear Event Scale (INES) and another event classified as level 1. AENOR performance the audit for renewing certificate UNE-EN ISO-9001, and for tracking environmental management systems as per UNE-EN ISO 14001, with satisfactory results. The dose around the Plant caused by plant operation has been insignificant. For the first time in the Spanish industry, the Plant has implemented an integrated safety system that encompasses all the plant's safety-related activities.

  1. 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.

  2. Dosimetry in nuclear power plants; Dosimetria en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lastra B, J. A. [CFE, Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)

    2008-12-15

    To control the occupationally exposed personnel dose working at the Laguna Verde nuclear power plant, two types of dosemeters are used, the thermoluminescent (TLD) which is processed monthly, and the direct reading dosemeter that is electronic and works as daily control of personal dose. In the case of the electronic dosemeters of direct reading conventional, the readings and dose automatic registers and the user identity to which he was assigned to each dosemeter was to carry out the restricted area exit. In activities where the ionizing radiation sources are not fully characterized, it is necessary to relocate the personal dosemeter or assigned auxiliary dosemeters (TLDs and electronics) to determine the dose received by the user to both whole body and in any specific area of it. In jobs more complicated are used a tele dosimetry system where the radiation protection technician can be monitoring the user dose to remote control, the data transmission is by radio. The dosimetry activities are documented in procedures that include dosemeter inventories realization, the equipment and dosemeters calibration, the dosimetry quality control and the discrepancies investigation between the direct reading and TLD systems. TLD dosimetry to have technical expertise in direct and indirect dosimetry and two technicians in TLD dosimetry; electronic dosimetry to have 4 calibration technicians. For the electronic dosemeters are based on a calibrator source of Cesium-137. TLD dosemeters to have an automatic radiator, an automatic reader which can read up to 100 TLD dosemeters per hour and a semiautomatic reader. To keep the equipment under a quality process was development a process of initial entry into service and carried out a periodic verification of the heating cycles. It also has a maintenance contract for the equipment directly with the manufacturer to ensure their proper functioning. The vision in perspective of the dosimetry services of Laguna Verde nuclear power plant

  3. Projects of Modifications of design for mitigation of accidents outside the design Bases on nuclear Central PWR Siemens-KWU and Westinghouse; Proyectos de Modificaciones de Sieno para Mitigacion de Accidentes fuera de la Bases de Diseno en Centrales Nucleares PWR Siemens-KWU y Westinghouse

    Energy Technology Data Exchange (ETDEWEB)

    Dominguez Gonzalez, G.; Cano Rodriguez, L. A.; Arguello Tara, A.

    2014-07-01

    Following the accident at the Japanese Fukushima-Daiichi NPP, the different regulators of nuclear power generation have required numerous reports regarding the evaluation and modification of the capacity of the plants to face accidents with severities beyond that established in their Design Bases. Under this new scenario, with multiple new demands and commitments, EA has carried out the required works for the implementation of strategies to mitigate the consequences of beyond Design Basis accidents for utilities owning Siemens-KWU and Westinghouse PWR nuclear power plants. (Author)

  4. Technological evaluation for the extension of the operation license to the nuclear power plant of Laguna Verde; Evaluacion tecnologica para la extension de la licencia de operacion de la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Arganis J, C. R.; Medina A, A. L., E-mail: carlos.arganis@inin.gob.m [ININ, Departamento de Tecnologia de Materiales, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-07-01

    At the present time one of the tendencies in the nuclear industry is the renovation of operation licenses of the nuclear power plants, with the purpose of prolonging their operation 20 years more than the time settled down in their original license, which is of 30 years for the case of the nuclear power plant of Laguna Verde. This allows the electric power generation for a major period of time and to a relatively low price, giving this way a bigger competitiveness to the power stations of nuclear power. However, to request the license extension of the nuclear power plant requires to get ready the documentation and necessary studies for: to maintain a high level of security, to optimize the operation, maintenance and service life of the structures, systems and components, to maintain an acceptable level of performance, to maximize the recovery of the investment about the service of the nuclear power plant and to preserve the sure conditions for a major operation period at the license time. This paper describes the studies conducted by the Materials Technology Department of the Instituto Nacional de Investigaciones Nucleares (ININ) to substantiate the required documentation for obtaining the extension of operating license of the nuclear power plant. These studies are focused mainly in the reactor pressure vessels of both units, as well as in the deposit of noble metals and the influence of the sludges (crud s) in this deposit. (Author)

  5. Decontamination equipment for the bottom of the cavity NPP during refueling operations; Equipo para la descontaminacion del fondo de la cavidad de centrales nucleares durante las operaciones de recarga de combustible

    Energy Technology Data Exchange (ETDEWEB)

    Vaquer, J. I.; Pastor, I.; Pascual, A.; Garcia Martinez, A.

    2014-04-01

    In this work the DEMOS robot is displayed, as a designed and developed equipment by Grupo Dominguis in order to carry out the decontamination of the cavity background in Nuclear Power Plants during the refueling operations. the aim of the project is executing the decontamination of the cavity ground, in case of flood pool, by means of brushing and aspirated after the fuel movement operation, in order to reduce the operational dose of the workers. In the activities that are carried out after while in the cavity. Eventually, the obtained results of the operative experience in many Nuclear Power Plants will be displayed. (Author)

  6. 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)

  7. 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)

  8. 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)

  9. 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)

  10. 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)

  11. 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

  12. 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)

  13. 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)

  14. GE Nuclear Hitachi Energy is prepared for the nuclear Renaissance; GE Hitachi Nuclear Energy se prepara para el renacimiento nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Carelli, J. M.

    2008-07-01

    GE Hitachi Nuclear Energy (GEH) is offering two technologies to meet the needs of utilities planning new nuclear projects. An aging workforce, new technological developments and forecasts of considerable new construction projects, raise questions for the entire industry regarding our human resources. In order to prepare for the coming resurgence in new nuclear projects, GEH taking positive action to ensure that adequate human resources are available. From early learning programs that encourage young students to pursue careers in science and technology, to hands-on vocational and engineering programs, GEH works with communities and young people to recruit and train the workforce that will enable our success. (Author)

  15. 75 FR 9576 - Civil Nuclear Policy Mission to Central and Eastern Europe

    Science.gov (United States)

    2010-03-03

    ... nuclear training institutions; and, small modular reactor technologies. Commercial Setting The Central and... achieve its aggressive goal of having a nuclear reactor online by 2020. In terms of infrastructure... Republic's nuclear tender allows for the awarded company to have the opportunity to build reactors...

  16. Revision of documents guide to obtain the renovation of licence of the nuclear power plant of Laguna Verde, Units I and II; Revision de documentos guia para obtener la renovacion de licencia de la Central Nuclear Laguna Verde Unidades 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G. [ININ 52750 La Marquesa, Estado de Mexico (Mexico); Fernandez S, G. [CFE, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin s/n (Km. 7.5), Dos Bocas, 54270 Veracruz (Mexico)]. e-mail: giarvio@yahoo.com.mx

    2008-07-01

    Unquestionably the renovation of license of the nuclear power plants , it this converting in a promising option to be able to gather in sure, reliable form and economic those requests about future energy in the countries with facilities of this type. This work it analyzes four documents guide and their application for the determination of the renovation of it licenses in nuclear plants that will serve of base for their aplication in the Nuclear Power Plant of Laguna Verde Units I and 2. The four documents in question are: the one Inform Generic of Learned Lessons on the Aging (NUREG - 1801), the Standard Revision Plan for the Renovation of License (NUREG - 1800), the Regulatory Guide for Renovation of License (GR-1.188), and the NEI 95-10, developed by the Institute of Nuclear Energy that is an Industrial Guide to Implement the Requirements of the 1OCFR Part 54-the Rule of Renovation of It licenses. (Author)

  17. Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

    Energy Technology Data Exchange (ETDEWEB)

    Duran, Felicia Angelica [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.; Waymire, Russell L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Security Systems Analysis Dept.

    2013-10-01

    Sandia National Laboratories (SNL) is providing training and consultation activities on security planning and design for the Korea Hydro and Nuclear Power Central Research Institute (KHNPCRI). As part of this effort, SNL performed a literature review on computer security requirements, guidance and best practices that are applicable to an advanced nuclear power plant. This report documents the review of reports generated by SNL and other organizations [U.S. Nuclear Regulatory Commission, Nuclear Energy Institute, and International Atomic Energy Agency] related to protection of information technology resources, primarily digital controls and computer resources and their data networks. Copies of the key documents have also been provided to KHNP-CRI.

  18. 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)

  19. 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.

  20. 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)

  1. 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.

  2. Reevaluation of environmental monitoring program for radiological emergency at Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro - Brazil; Reavaliacao do programa de monitoracao ambiental para emergencias radiologicas na Central Nuclear Almirante Alvaro Alberto, Angra dos Reis, Rio de Janeiro - Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1996-07-01

    In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra dos Reis, Rio de Janeiro, the Emergency Response Team of the Institute for Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. The purpose of this program is to define a monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measures in case of a radiological accident, taking into account atmospheric diffusion, population conglomerates and their habits, water and land use, contemplating the entire Emergency Planning Zone of 15 km radius. This program has been reevaluated recently, aiming to optimize it and keep it up to date to assure adequacy of environmental surveillance data in support to a prompt response in case of an emergency situation in the nuclear power plant. It has been organized in the form of a handbook to facilitate handling by field teams. Future revisions will be necessary to incorporate additional pertinent information and keep the handbook up to date, since Angra dos Reis is a summer resort region, subject to constant changes. This paper discusses the structure of the environmental monitoring program and describes the content and preparation of this handbook. (author)

  3. 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.

  4. 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)

  5. Refueling outage services in Spanish Nuclear Power Plants; Servicios en recargas de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Landete, J. L.; Soto, M.; Nunuez, A.

    2007-07-01

    DOMINGUIS Group, through its 75 years of business development, has positioned as the Spanish leader Group in Services for the Nuclear Energy and Petrochemical Sectors. In this article, we present the most significant services summary that, through the companies that constitute DOMINGUIS Group, we have developed in Refueling Outage in Spanish Nuclear Power Plants. (Author)

  6. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Ek, P.; Andersson, Sarmite [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Wredberg, L. [ILG Consultant Ltd., Vienna (Austria)

    2000-06-15

    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

  9. Nuclear Stopping in Central Au+Au Collisions at RHIC Energies

    Directory of Open Access Journals (Sweden)

    Ying Yuan

    2014-01-01

    Full Text Available Nuclear stopping in central Au+Au collisions at relativistic heavy-ion collider (RHIC energies is studied in the framework of a cascade mode and the modified ultrarelativistic quantum molecular dynamics (UrQMD transport model. In the modified mode, the mean field potentials of both formed and “preformed” hadrons (from string fragmentation are considered. It is found that the nuclear stopping is increasingly influenced by the mean-field potentials in the projectile and target regions with the increase of the reaction energy. In the central region, the calculations of the cascade model considering the modifying factor can describe the experimental data of the PHOBOS collaboration.

  10. 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)

  11. Centrality and multiparticle production in ultrarelativistic nuclear collisions

    Science.gov (United States)

    Drozhzhova, T. A.; Kovalenko, V. N.; Seryakov, A. Yu.; Feofilov, G. A.

    2016-09-01

    A critical analysis of methods for selecting central events in high-energy proton-nucleus ( pA) and nucleus-nucleus ( AA) collisions is presented. A sample of event classes in which background fluctuations associated with the dispersion of the impact parameter of each event or the number of participant nucleons are minimal is examined. At the SPS and LHC energies, the numbers of nucleon-nucleon collisions are estimated with the aid of the Monte Carlo event generators HIJING and AMPT, which take into account energy-momentum conservation, and on the basis of a non-Glauber model involving string fusion and a modified Glauber model. The results obtained in this way demonstrate the need for revising the extensively used application of the Glauber model in normalizing multiplicity yields in experimental data on pA and AA collisions in the soft region of the spectrum.

  12. 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)

  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. 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)

  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. Radiological protection in nuclear power plants; La proteccion radiologica en las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zorrilla R, S. [CFE. Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)

    2008-12-15

    This presentation sharing experiences which correspond to the nuclear power plant of Laguna Verde. This nuclear power plant is located at level 2 of four possible, in the classification performance of the World Association of Nuclear Operators (WANO), which means the mexican nuclear power plant is classified in terms of its performance indicators and above the average achieved by their counterparts americans and canadians. In the national context, the nuclear power plant of Laguna Verde has also been honored with several awards such as the National Quality Award, the Clean Industry Certificate, the distinction of Environmental Excellence and others of similar importance. For the standards of WANO, the basic idea is that there are shortcomings in one of nuclear power plant concern to all partners. The indicators used for the classification will always go beyond more compliance with regulations, which are assumed, and rather assume come or a path to excellence. Among the most important indicators are: the collective dose, the percentage of areas declared as contaminated, the number, type and tendency of contamination personal cases, the number of dosimetry alarms, the number of unplanned exposures, loss control of high radiation areas and the release of contaminated material outside the restricted areas. Furthermore, as already indicated, nuclear power plants are of special care situations, such as, carrying out work in areas with radiation fields of more than 15 mSv h{sup -1}, the movement of spent fuel in the reload floor. The consideration of the minimum total effective dose equivalent as a criterion for prescribing tools that reduce exposures, but may increase the external cases of contaminated casualties, the experience in portals such as workers subject to radiology, where exposure in industrial radiography, and so on. Special mention deserve the conditions generated during fuel reload stops, which causes a massive personnel movement, working simultaneously on

  17. 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

  18. Centrality and system size dependence of multiplicity fluctuations in nuclear collisions at 158 AGeV

    CERN Document Server

    Alt, C; Baatar, B; Barna, D; Bartke, J; Betev, L; Bialkowska, H; Blume, C; Boimska, B; Botje, M; Bracinik, J; Bramm, R; Buncic, P; Cerny, V; Christakoglou, P; Chvala, O; Cramer, J G; Csató, P; Dinkelaker, P; Eckardt, V; Flierl, D; Fodor, Z; Foka, P; Friese, V; Gazdzicki, M; Georgopoulos, G; Gladysz-Dziadus, E; Grebieszkow, K; Gál, J; Hegyi, S; Höhne, C; Kadija, K; Karev, A; Kliemant, M; Kniege, S; Kolesnikov, V I; Kornas, E; Korus, R; Kowalski, M; Kraus, I; Kreps, M; Laszlo, A; Litov, L; Lungwitz, B; Lévai, Peter; Makariev, M; Malakhov, A I; Mateev, M; Melkumov, G L; Mischke, A; Mitrovski, M; Molnár, J; Mrówczynski, S; Nicolic, V; Panagiotou, A D; Panayotov, D; Petridis, A; Pikna, M; Prindle, D; Pálla, G; Pühlhofer, F; Renfordt, R; Roland, C; Roland, G; Rybczynski, M; Rybicki, A; Sandoval, A; Schmitz, N; Schuster, T; Seyboth, P; Siklér, F; Sitár, B; Skrzypczak, E; Stefanek, G; Stock, R; Strabel, C; Ströbele, H; Susa, T; Szentpétery, I; Sziklai, J; Szymanski, P; Trubnikov, V; Van Leeuwen, M; Varga, D; Vassiliou, M; Veres, G I; Vesztergombi, G; Vranic, D; Wetzler, A; Wlodarczyk, Z; Yoo, I K; Zimányi, J

    2007-01-01

    The centrality and system size dependence of multiplicity fluctuations of charged particles produced in nuclear collisions at 158 AGeV was studied by the NA49 collaboration. Centrality selected Pb+Pb collisions, semi-central C+C and Si+Si collisions as well as inelastic p+p interactions were analyzed. The number of projectile participants determined on event-by-event basis was used to characterize the collision centrality. The scaled variance of the multiplicity distribution obtained in the forward rapidity region (1.1 centrality with a maximum for semi-peripheral Pb+Pb interactions of about 30 projectile participants. The results are similar for negatively and positively charged particles and about 50% larger for all charged particles. String-hadronic models of nuclear reactions without the fusion process do not reproduce the rise of fluctuations from central towards peripheral collisions. The measured centrality dependence can be reproduced in superpos...

  19. 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)

  20. 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)

  1. Quality Assurance in Nuclear Power Plants; La garantia de calidad en la Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zamarron Casinello, J. M. (CC.AA. Almaraz-Trillo); Gasca Pinilla, R. (Asociacion Nuclear Asco-Vandellos II); Sala Candela, A. (IBERDROLA); Valle Pena (NUCLENOR); Ruiz Rodriguez, C. (UNION FENOSA)

    2000-07-01

    In 1970, 10CFR50 Appendix B. Quality Assurance Criteria for Nuclear Power Plants & Fuel Reprocessing Plants, was approved in USA. This is based on 18 criteria and requires American nuclear power plants to establish as quickly as possible a Quality Assurance Program (QAP) specifying how to comply with the criteria contained in this Appendix. The Ministry of Industry required that this standard be observed in Spanish plants. In The first-generation plants (Jose Cabrera, Santa Maria de Garona and Vandellos 1), which were built before this new standard was developed, the concept of Quality Assurance has only been applied to the operating phase, whereas in second-generation plants (Almaraz, Asco3 and Cofrentes) and third-generation plants (Vandellos 2 and Trillo), the concept was applied from the very beginning of the project: design phases, construction and finally plant operation. In 1979, the IAEA publihed practical code 50-C-QA as an international reference document. It contains 13 criteria that coincide with and complement those established in Appendex B of 10CFR50. As a result, the nuclear power plants in all neighboring countries will be enforcing similar Quality Assurance criteria. (Author)

  2. Nuclear-nuclear collision centrality determination by the spectators calorimeter for the MPD setup at the NICA facility

    Energy Technology Data Exchange (ETDEWEB)

    Golubeva, M. B.; Guber, F. F.; Ivashkin, A. P. [Russian Academy of Sciences, Institute for Nuclear Research (Russian Federation); Isupov, A. Yu. [Joint Institute for Nuclear Research (Russian Federation); Kurepin, A. B. [Russian Academy of Sciences, Institute for Nuclear Research (Russian Federation); Litvinenko, A. G., E-mail: litvin@moonhe.jinr.ru; Litvinenko, E. I.; Migulina, I. I.; Peresedov, V. F. [Joint Institute for Nuclear Research (Russian Federation)

    2013-01-15

    The work conditions of the hadron calorimeter for spectators registration (Zero Degree Calorimeter, ZDC) were studied for the heavy nuclei collisions with the several GeV invariant energy. The ZDC simulations were performed for the MPD (Multi-Purpose Detector) at the NICA (Nuclotron-based Ion Collider fAcility) collider, which are under developement at the Joint Institute for Nuclear Research (JINR, Dubna). Taking into account the spectator nuclear fragments leads to a nonmonotonic dependence of the ZDC response on the impact parameter. The reason for this dependence studied with several event generators is the primary beam hole in the ZDC center. It is shown, that the ZDC signal should be combined with a data from other MPD-NICA detector subsystems to determine centrality.

  3. Nuclear relations with administrations of industry services; Relaciones de las centrales nucleares con las administraciones de los Servicios de Industria

    Energy Technology Data Exchange (ETDEWEB)

    Bernardez Garcia, A.

    2011-07-01

    The object of the article is to try to answer to the following question that can arise to the holder of a nuclear power station: What Administration of Industry must I myself direct to be able to support my complementary facilities of Industrial Security inside the in force legality?. The raised discussion arise between if the competent administration for the legal steps, is the Central Administration across his delegates and sub delegates of government, or is of the Territorial Services of Industry of Autonomous communities. (Author)

  4. 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)

  5. Preparation of feasibility studies for nuclear power plants; Elaboracion de estudios de viabilidad de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Andujar Sagredo, R.

    2013-07-01

    The feasibility study falls within the pre-purchase of a new nuclear plant jobs. This is a key process for the early identification of risks associated with the construction of the same, and the investment needed and the time within which such investment return, taking into account that this is a complex industrial project with an iron control and accurate high inputs of capital. Set the risks in these early stages of the project can make the difference in keeping both the budget and the execution time initially considered.

  6. Electronic instrumentation for the nuclear radiation measurement; Instrumentacion electronica para la medicion de la radiacion nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez J, F.J

    2005-07-01

    This work presents the obtained results in the research, development and construction of the electronic instrumentation required for the measurement of the essential characteristics of the nuclear radiation: The quantity of radiation and its energy components. With this information, many practical instruments can be developed and applied in different fields of science and technology. In this work, some instruments were developed for their application in the areas of medicine, industry, and particle physics research. Several measurement systems based on PIN type diodes are proposed for: a) the measurement of the operational characteristics of the X-ray machines and the X-rays emitted in medical radio-diagnostic, b) X-ray spectroscopy and c) radiation spectroscopy of charged particles. The contribution of this work is, precisely, the development of new instruments that use the PIN diode as the sensorial element. In this way, existing problems in nuclear instrumentation are overcame, specially in the fields of medical physics and particle physics. Likewise, different types of charge and current preamplifiers, with a high signal-to-noise ratio, were developed for these instruments. (Author)

  7. 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)

  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. 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.

  10. 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)

  11. 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.

  12. Fertilization in Torenia fournieri: actin organization and nuclear behavior in the central cell and primary endosperm

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    Studies of the living embryo sacs of Torenia fournieri reveal that the actin cytoskeleton undergoes dramatic changes that correlate with nuclear migration within the central cell and the primary endosperm. Before pollination, actin filaments appear as short bundles randomly distributed in the cortex of the central cell. Two days after anthesis, they become organized into a distinct actin network. At this stage the secondary nucleus, which is located in the central region of the central cell, possesses an associated array of short actin filaments. Soon after pollination, the actin filaments become fragmented in the micropylar end and the secondary nucleus is located next to the egg apparatus. After fertilization, the primary endosperm nucleus moves away from the egg cell and actin filaments reorganize into a prominent network in the cytoplasm of the primary endosperm. Disruption of the actin cytoskeleton with latrunculin A and cytochalasin B indicates that actin is involved in the migration of the nucleus in the central cell. Our data also suggest that the dynamics of actin cytoskeleton may be responsible for the reorganization of the central cell and primary endosperm cytoplasm during fertilization.

  13. Propuesta de un cuadro de mando integral para la empresa Central Veterinaria S.A.

    OpenAIRE

    Vargas-Sarquís, Adrián

    2011-01-01

    Tesis de maestría -- Universidad de Costa Rica. Posgrado en Administración y Dirección de Empresas. Maestría Profesional en Administración y Dirección de Empresas con énfasis en Gerencia, 2011 El objetivo general del trabajo es desafiar un modelo de Cuadro de Mando Integral para la empresa Central Veterinaria S.A., mediante un análisis de situación, con el fin de facilitar la toma de decisiones a la alta direcci6n. Esta empresa se dedica a la fabricación, venta y distribución de productos ...

  14. Assessment of individual radionuclide distributions from the Fukushima nuclear accident covering central-east Japan.

    Science.gov (United States)

    Kinoshita, Norikazu; Sueki, Keisuke; Sasa, Kimikazu; Kitagawa, Jun-ichi; Ikarashi, Satoshi; Nishimura, Tomohiro; Wong, Ying-Shee; Satou, Yukihiko; Handa, Koji; Takahashi, Tsutomu; Sato, Masanori; Yamagata, Takeyasu

    2011-12-01

    A tremendous amount of radioactivity was discharged because of the damage to cooling systems of nuclear reactors in the Fukushima No. 1 nuclear power plant in March 2011. Fukushima and its adjacent prefectures were contaminated with fission products from the accident. Here, we show a geographical distribution of radioactive iodine, tellurium, and cesium in the surface soils of central-east Japan as determined by gamma-ray spectrometry. Especially in Fukushima prefecture, contaminated area spreads around Iitate and Naka-Dori for all the radionuclides we measured. Distributions of the radionuclides were affected by the physical state of each nuclide as well as geographical features. Considering meteorological conditions, it is concluded that the radioactive material transported on March 15 was the major contributor to contamination in Fukushima prefecture, whereas the radioactive material transported on March 21 was the major source in Ibaraki, Tochigi, Saitama, and Chiba prefectures and in Tokyo.

  15. Role of Nuclear Receptors in Central Nervous System Development and Associated Diseases

    Science.gov (United States)

    Olivares, Ana Maria; Moreno-Ramos, Oscar Andrés; Haider, Neena B.

    2015-01-01

    The nuclear hormone receptor (NHR) superfamily is composed of a wide range of receptors involved in a myriad of important biological processes, including development, growth, metabolism, and maintenance. Regulation of such wide variety of functions requires a complex system of gene regulation that includes interaction with transcription factors, chromatin-modifying complex, and the proper recognition of ligands. NHRs are able to coordinate the expression of genes in numerous pathways simultaneously. This review focuses on the role of nuclear receptors in the central nervous system and, in particular, their role in regulating the proper development and function of the brain and the eye. In addition, the review highlights the impact of mutations in NHRs on a spectrum of human diseases from autism to retinal degeneration. PMID:27168725

  16. 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)

  17. 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)

  18. 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.

  19. Validation of a new version of software for monitoring the core of nuclear power plant of Laguna Verde Unit 2, at the end of Cycle 10; Validacion de una nueva version del software para monitoreo del nucleo de la Central Laguna Verde Unidad 2, al final del Ciclo 10

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez, G.; Calleros, G.; Mata, F. [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Cardel-Nautla Km 42.5, Veracruz (Mexico)], e-mail: gabriel.hernandez05@cfe.gob.mx

    2009-10-15

    This work shows the differences observed in thermal limits established in the technical specifications of operation, among the new software, installed at the end of Cycle 10 of Unit 2 of nuclear power plant of Laguna Verde, and the old software that was installed from the beginning of the cycle. The methodology allowed to validate the new software during the coast down stage, before finishing the cycle, for what could be used as tool during the shutdown of Unit 2 at the end of Cycle 10. (Author)

  20. 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)

  1. 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

  2. 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

  3. On the Hydrodynamic Interplay Between a Young Nuclear Starburst and a Central Super Massive Black Hole

    CERN Document Server

    Hueyotl-Zahuantitla, F; Wünsch, R; Silich, S; Palouš, J

    2010-01-01

    We present 1D numerical simulations, which consider the effects of radiative cooling and gravity on the hydrodynamics of the matter reinserted by stellar winds and supernovae within young nuclear starbursts with a central supermassive black hole (SMBH). The simulations confirm our previous semi-analytic results for low energetic starbursts, evolving in a quasi-adiabatic regime, and extend them to more powerful starbursts evolving in the catastrophic cooling regime. The simulations show a bimodal hydrodynamic solution in all cases. They present a quasi-stationary accretion flow onto the black hole, defined by the matter reinserted by massive stars within the stagnation volume and a stationary starburst wind, driven by the high thermal pressure acquired in the region between the stagnation and the starburst radii. In the catastrophic cooling regime, the stagnation radius rapidly approaches the surface of the starburst region, as one considers more massive starbursts. This leads to larger accretion rates onto th...

  4. 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.

  5. 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.

  6. 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)

  7. 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

  8. Application of Pressure Equipment Standard at nuclear power plants; Aplicacion del Reglamento de Equipos a Presion a las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Mostaza, J. M.

    2011-07-01

    Regarding with the paper presented on 9{sup t}h June 2011 referred to the Industrial Security standard in Nuclear Plants, it was about the application of Pressure Equipment standard to mentioned Nuclear Plants, this article is an extract of the paper going to be exposed. (Author)

  9. Project of a new circuit for nuclear fuel irradiation; Projeto de um novo circuito para irradiacao de combustiveis nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zeituni, Carlos A.; Terremoto, Luis A.A.; Perrotta, Jose A.; Silva, Jose E.R. da [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). Centro de Engenharia Nuclear. Div. de Engenharia do Combustivel. E-mail: czeituni@usp.br

    2000-07-01

    This paper reports information about the operation of the old Irradiated Fuel Assembly for nuclear miniplates irradiation in the reactor IEA-R1, named CICON (Circuit for Nuclear Fuels Irradiation), and presents the project of the new one. This paper also describes the problems of the old capsule and which details we will change in the new project. (author)

  10. 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)

  11. The nuclear bulge. I. K band observations of the central 30 PC

    Science.gov (United States)

    Philipp, S.; Zylka, R.; Mezger, P. G.; Duschl, W. J.; Herbst, T.; Tuffs, R. J.

    1999-08-01

    Out of ~ 500 individual source images we have constructed a mosaic map of the K band surface brightness in an area Delta alphax Delta delta ~ 650''x710'' (R_equiv ~ 15.8 pc for R_0 = 8.5 kpc) centered approximately on Sgr A*. An observing technique was used which allows us to recover an extended background emission. To separate sources from an unresolved background continuum we fitted Lorentzian distributions to the sources and find that about one half of an integrated, not dereddened K band flux density of 752 Jy is contributed by ~ 6*E(4) stars with flux densities S_K(') >~ 100 mu Jy and the remainder is contributed by an extended continuum provided by about 6*E(8) stars too weak to be observed as individual sources. We estimate that >~ 80% of the integrated flux density of the mosaic is contributed by stars in the Nuclear Bulge (NB; R 3 kpc). We determine the K band luminosity functions (KLF) of the mosaic and of subareas dominated by Nuclear Bulge, Galactic Bulge and Disk stars, respectively, and construct difference KLFs which relate to the specific stellar populations of these regions. The detection limit is S_K(') ~ 100 mu Jy, for the completeness limit we estimate S_K(') ~ 2 000 mu Jy. We find that the stellar population of the Nuclear Bulge contains considerably more bright stars (i.e. with reddened K band flux densities S_K(') >~ 5*E(3 mu ) Jy), most of which are probably early O stars, Giants and Supergiants. The stellar population of the Galactic Bulge on the other hand is dominated by stars which appear to be lower mass (Main Sequence (MS) stars. A model KLF constructed with a Salpeter Initial Mass Function (IMF) for stars of spectral type O9 or later (S_K(') masses ranging from 0.06 to 6 M_sun account for the unresolved continuum. Combining observed and model KLF we obtain a mosaic KLF which increases ~ S_K({') - 1} for 10(6) >~ S_K('/mu ) Jy >~ 10(3) and ~ S_K({') - 0.6} for 10(3) >~ S_K('/mu ) Jy >~ 3*E(-3) . For radii R relatively young generation

  12. Life management plants at nuclear power plants PWR; Planes de gestion de vida en centrales nucleares PWR

    Energy Technology Data Exchange (ETDEWEB)

    Esteban, G.

    2014-10-01

    Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

  13. 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.

  14. 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

  15. 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.

  16. The rapidity and centrality dependence of nuclear modification factors at RHIC - what does bulk particle production tell us about the nuclear medium?

    CERN Document Server

    Samset, B H; Bearden, I G; Beavis, D; Besliu, C; Budick, B; Bøggild, H; Chasman, C; Christensen, C H; Christiansen, P; Cibor, J; Debbe, R; Enger, E; Gaardhøje, J J; Germinario, M; Hagel, K; Ito, H; Jipa, A; Jundt, F; Jordre, J I; Jorgensen, C E; Karabowicz, R; Kim, E J; Kozik, T; Larsen, T M; Lee, J H; Lee, Y K; Lindal, S; Løvhøiden, G; Majka, Z; Makeev, A; McBreen, B; Mikelsen, M; Murray, M; Natowitz, J B; Neumann, B; Nielsen, B S; Norris, J; Ouerdane, D; Planeta, R; Rami, F; Ristea, C; Ristea, O; Röhrich, D; Sandberg, D; Sanders, S J; Scheetz, R A; Staszel, P; Tveter, T S; Videbaek, F; Wada, R; Yin, Z; Zgura, I S

    2004-01-01

    The BRAHMS experiment at RHIC has measured the production of charged hadrons as a function of pseudorapidity and transverse momentum in Au+Au, d+Au and p+p collisions at a common energy of sqrt(s_NN)=200GeV, and from these spectra we construct the nuclear modification factors for both ``hot'' and ``cold'' nuclear matter. In this contribution I will show how these factors evolve with pseudorapidity and collision centrality. We see a Cronin-like enhancement in d+Au collisions at midrapidity, going to a strong suppression at eta >= 2. In central Au+Au collisions we find a suppression both at mid- and forward rapidities that vanishes for peripheral collisions. We interpret this as signs of several different medium related effects modifying bulk particle production in Au+Au and d+Au collisions at RHIC energies.

  17. 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.

  18. 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.)

  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. 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

  1. Producción de leche en pastoreo de praderas cultivadas: una alternativa para el Altiplano Central

    Directory of Open Access Journals (Sweden)

    Carlos Arriaga Jordán

    1999-01-01

    Full Text Available Se presentan resultados que definen a la producción de leche en pastoreo intensivo de praderas cultivadas como alternativa para una ganadería competitiva y sostenible en el Altiplano Central de México. Se revisan resultados del efecto en los rendimientos de leche del tipo de pradera, el sistema de pastoreo y la respuesta a la suplementación con concentrados.

  2. Nuclear energy, energy for the present and the future; Energia nuclear, una energia para el presente y el futuro

    Energy Technology Data Exchange (ETDEWEB)

    Arredondo S, C. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: cas@nuclear.inin.mx

    2008-07-01

    In this work we will try to show that nuclear energy can contribute to the generation energy in the present and the future, considering that its effect on the climatic change is relatively low and that the fuels that uses are available a large scale. At the moment it is had already commercial thermal fission reactors , there are also them of fast fission that allow the fuel rearing, although these last ones in much smaller number, with both types of fission nuclear reactors can be obtained a very important contribution to the generation of energy at world-wide level during the time that is necessary so that it is developed, constructs and operates the first commercial fusion reactor. The energy that is generated in the present and future must come from different sources, which require to be reliable, to have little effect on the environment, to have wide reserves of fuels and to be viable from an economic and social point of view, they must be viable and safe. Between possible alternative energies it is counted on the lot, the wind one, the geothermal one, originating of the tides and some others. An energy that must be considered so that it has arrived at his maturity and he is already able to contribute widely to cover the present needs and future it is nuclear energy, as much the originating one of the fission of a heavy centre like obtained when fusing two light centers. On base in the nuclear fuel reserves at world-wide level a simple calculation takes control of the lapse in which energy by means of the nuclear fission in rearing can be generated reactors expresses demonstrating that the time sufficient to finish to the investigation and development of fusion reactors which they generate energy in economic, safe and reliable form. Combining these two options the nuclear energy can be considered the future like for the present and the future with practically null effects in the climatic change. (Author)

  3. 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)

  4. 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.

  5. 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)

  6. Individual dose monitoring of the nuclear medicine departments staff controlled by Central Laboratory for Radiological Protection.

    Science.gov (United States)

    Szewczak, Kamil; Jednoróg, Sławomir; Krajewski, Paweł

    2013-01-01

    Presented paper describes the results of the individual doses measurements for ionizing radiation, carried out by the Laboratory of Individual and Environmental Doses Monitoring (PDIS) of the Central Laboratory for Radiological Protection in Warsaw (CLOR) for the medical staff employees in several nuclear medicine (NM) departments across Poland. In total there are48 NM departments in operation in Poland [1] (consultation in Nuclear Atomic Agency). Presented results were collected over the period from January 2011 to December 2011 at eight NM departments located in Krakow, Warszawa (two departments), Rzeszow (two departments), Opole, Przemysl and Gorzow Wielkopolski. For radiation monitoring three kinds of thermo luminescence dosimeters (TLD) were used. The first TLD h collected information about whole body (C) effective dose, the second dosimeter was mounted in the ring (P) meanwhile the third on the wrist (N) of the tested person. Reading of TLDs was performed in quarterly periods. As a good approximation of effective and equivalent dose assessment of operational quantities both the individual dose equivalent Hp(10) and the Hp(0.07) were used. The analysis of the data was performed using two methods The first method was based on quarterly estimations of Hp(10)q and Hp(0.07)q while the second measured cumulative annual doses Hp(10)a and Hp(0.07)a. The highest recorded value of the radiation dose for quarterly assessments reached 24.4 mSv and was recorded by the wrist type dosimeter worn by a worker involved in source preparation procedure. The mean values of Hp(10)q(C type dosimeter) and Hp(0.07)q (P and N type dosimeter) for all monitored departments were respectively 0.46 mSv and 3.29 mSv. There was a strong correlation between the performed job and the value of the received dose. The highest doses always were absorbed by those staff members who were involved in sources preparation. The highest annual cumulative dose for a particular worker in the considered time

  7. Methodology for gathering nuclear energy literature; Metodologia de coleta para alimentacao de uma base de dados em energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, Maria B.M.A.

    1996-12-31

    Several activities related to gathering information and documents -conventional and non-conventional primary literature - to include in a bibliographic nuclear energy database are described and arranged, using as model the communication and information process in science and technology and the analysis of the indexed documents in the database. Methodological steps are identified and a collecting system model is presented. 112 refs., 4 tabs.

  8. Fundaments for creation of national radiation protection standard for nuclear gauges; Fundamentos para implantacao de norma nacional de protecao radiologica para medidores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Luiz Cavalcante

    2016-11-01

    The present work It aims to provide fundaments for the creation of a national standard of practice, safety and responsible use of nuclear gauges in accordance with the recommendations already existing national and international. The work deals with the protection against ionizing radiation, an outline of a proposal for a standard that discriminates in its articles and paragraphs, the basic principles of a proposal for a standard that discriminates in its articles and paragraphs, the basic principles of safety and security, and some pointes that are also relevant such as the responsibilities of those involved in acquisition and nuclear gauge operation, storage, maintenance, testing and emergency situations. The result is to provide a means to limit the dose of operators and people from the public and maintain these limits within the recommended by CNEN, reducing exposure do ionizing radiation, and having greater control in operating the equipment. (author)

  9. 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.

  10. 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.

  11. 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

  12. Safe closure for the Barsebaeck Nuclear Power Plant (Sweden); Clasusura segura de la central nuclear de Barseback (Suecia)

    Energy Technology Data Exchange (ETDEWEB)

    Lexberg, A.

    2003-07-01

    In February, 1998, the Swedish Government entrusted the Swedish Regulatory Body (SKI) with the supervision of the first shut-down of the two reactors at the Barsebaeck Nuclear Power Plant, which finally took place in November of 1999. Now that the data of the closure of the second reactor is uncertain, but assured, there arises and uncertainty brought about by the prolonged decision making process, which may be detrimental to the safety culture at the site, reduce motivation and cause the loss of key personnel. (Author)

  13. 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

  14. 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.)

  15. 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.

  16. 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)

  17. 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.

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

    Science.gov (United States)

    Green, J.R.; Cecil, L.D.; Synal, H.-A.; Santos, J.; Kreutz, K.J.; Wake, C.P.

    2004-01-01

    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) 36Cl 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 36Cl 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 36Cl 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 36Cl peak concentration from 1958, the year during the mid-1900s nuclear-weapons-tests period when 36Cl 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 ?? 105 atoms of 36Cl/gram (g) of ice. Peak 36Cl concentrations from Dye-3, Guliya and the Upper Fremont glacial sites were 7.1 ?? 105, 5.4 ?? 105 and 0.7 ?? 105 atoms of 36Cl/g of ice, respectively. Measurements of 36Cl preserved in ice cores improve estimates of historical worldwide atmospheric deposition of this isotope and allow the sources of 36Cl in ground water to be better identified. ?? 2004 Published by Elsevier B.V.

  19. 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

  20. 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.

  1. 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.

  2. Elaboración de procedimientos para el mantenimiento electrico en la central hidroeléctrica pucara

    OpenAIRE

    Saritama Luzuriaga, Diego; Chiriboga, Jorge

    2009-01-01

    Hoy en día las Centrales de Generación eléctrica necesitan contar con un eficiente programa de mantenimiento preventivo, el cual sea conocido por todo el personal para que se lleve a cabo de la mejor manera. Y si a esto le sumamos la implementación de un programa de mantenimiento asistido por computador, que nos permita mejorar la gestión del mantenimiento en nuestra empresa, estaremos trabajando correctamente en la búsqueda del Mantenimiento Productivo Total. Y si al personal de mantenimi...

  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. Internal dosimetry for occupationally exposed personnel in nuclear medicine; Dosimetria interna para personal ocupacionalmente expuesto en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, M.T.; Alfaro, L.M.M.; Angeles, C.A., E-mail: teodoro.garcia@inin.gob.mx, E-mail: mercedes.alfaro@inin.gob.mx, E-mail: arturo.angeles@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares Carrelera Mexico-Toluca, Ocoyoacac, MX (Mexico)

    2013-10-01

    Internal dosimetry plays an important role in nuclear medicine dosimetry control of personnel occupationally exposed, and that in recent years there has been a large increase in the use of radionuclides both in medical diagnosis as radiotherapy. But currently, in Mexico and in many parts of the world, this internal dosimetry control is not performed. The Instituto Nacional de lnvestigaciones Nucleares de Mexico (ININ) together with the Centro Oncologico de Toluca (ISEMMYM) have developed a simple and feasible methodology for monitoring of personnel working in these facilities. It was aimed to carry out the dosimetry of the personnel, due to the incorporation of I-131, using the spectrometric devices that the hospital has, a gamma camera. The first step in this methodology was to make a thyroid phantom to meet the specifications of the ninth ANSI. This phantom is compared under controlled conditions with RMC- II phantom used for system calibration of the ININ internal dosimetry (ACCUSCAN - Ll), and with another phantom developed in Brazil with ANSI specifications, in order to determine the variations in measurements due to the density of the material of each of the phantoms and adjust to the system ACCUSCAN, already certificate. Furthermore, necessary counts were performed with the gamma camera of the phantom developed at ININ, with a standard source of {sup 133}Ba which simulates the energy of {sup 131}I. With these data, were determined the counting efficiencies for a distance of 15 to 20 cm between the surface of the phantom and the the plate of the detectors. Another important aspect was to determine the lower limit of detection (LLD). In this paper we present the results obtained from the detectors calibration of the gamma camera of the hospital.

  6. Experimental determination of nuclear parameters for RP-0 reactor core; Determinacion experimental de los parametros nucleares para el nucleo tipo MTR del reactor nuclear RP-0

    Energy Technology Data Exchange (ETDEWEB)

    Cajacuri, Rafael A. [Sao Paulo Univ., SP (Brazil). Inst. de Fisica

    2000-07-01

    In the nuclear reactor for investigations RP-0 which is in Lima, Peru, that is a open pool class reactor with 1 to 10 watts of power and as a nuclear fuel uranium 238 enriched to 20% constituted by elements of Material Testing Reactor fuel class. This has reflectors of graphite and moderator of water demineralized. In 1996/1997 was measured in this reactor the following parameters: position of the control bar that make critic the reactor, critic height of moderator, excess of reactivity of the nucleus, parameter of reactivity for vacuum, parameter of reactivity for temperature, reactivity of its control bar, levels of doses in the reactor. (author)

  7. 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)

  8. 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.

  9. 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)

  10. NATO Nuclear Reductions and the Assurance of Central and Eastern European Allies

    Science.gov (United States)

    2013-10-01

    Virginia -class attack submarines.79 Europe necessarily becomes a lower priority. The rebalance is enabled by the belief in Washington, even if not...eng.pdf. 117 Amy F. Woolf , Nonstrategic Nuclear Weapons, RL32572 (Washington, D.C.: Congressional Research Service, December 19, 2012), p. 17...Eastern European Perspectives, op. cit., p. 8. 166 Woolf , Nonstrategic Nuclear Weapons, op. cit., p. 17. 167 Durkalec, NATO’s Defence and Deterrence

  11. 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)

  12. Design of a tool for the nuclear fuel management; Diseno de una herramienta para el manejo de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Carbajal S, M

    2002-07-01

    This work is divided into six chapters. Chapter 1 describes in a general form what the radiation is, how it is produced and also how it is detected, as well as, the unities which are used for quantifying it. In chapter 2 some issues and considerations are treated which were thought before to initiate the design of the tool for handling the nuclear fuel such as: to know the facilities of the TRIGA Mark III Reactor as well as the equipment with which it counts. All of this with the purpose of designing the tool which were more appropriated for its necessities. Chapter 3 treats about the necessity of having the reactor as well as the specifications and considerations of design. After, the generation of solution options are presented, for later making the evaluation and selection of solution alternatives. Consequently in chapter 4 these alternatives were treated as well as the parts which form the tool. It is made a detailed description of the parts and commercial components including the type of materials used for its manufacture, tolerances, surface finished, dimensions and so. In chapter 5 it is made a tool description and of the procedure of handling of irradiated fuels of the reactor pool to the hot cells with aforementioned tool. Finally, chapter 6 analyses the obtained results proposing the general conclusions of this work. It is important to mention that with this project the Mexican technology has contributed in the developing of manufacture of this kind of tools or instruments. (Author)

  13. 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)

  14. 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

  15. ¿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?

  16. Qualified Coatings in Nuclear Power Plants. Commercial products; Qualified Coatings in Nuclear Power Plants. Commercial products. Pinturas homologadas en centrales nucleares. Productos comerciales

    Energy Technology Data Exchange (ETDEWEB)

    Barcena, J.; Nunez, B.; Romero, M.; Baladiam, M.

    2014-07-01

    Recently, the supplier of paints that were qualified for use in nuclear applications as protective coatings have ceased to supply in Spain the paints that was used in areas or components with special requirements for nuclear power plants (NPPs). This lack of the common commercial products called for the search for and homologation of other products. A study was performed on the current status of the homologation of commercial products for NPPs and on the codes and standards governing them. The criteria to be met have been defined and the results of the tests performed on the selected paints have been compared against the established criteria so as to allow the homologation of the paints. (Author)

  17. Study of fuel assemblies for the nuclear reactor GFR; Estudio de ensambles de combustible para el reactor nuclear GFR

    Energy Technology Data Exchange (ETDEWEB)

    Reyes R, R.; Martin del Campo M, C.; Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, Jiutepec, Morelos 62550 (Mexico)]. e-mail: ricarera@yahoo.com.mx

    2008-07-01

    In the present work the criticality calculations for two models of fuel assembly were realized to study the nuclear reactor cooled by gas (Gas Fast Reactor) of IV Generation. Model 1 is an assembly with hexagonal adjustment of fuel rods with reflector in the axial ends higher and lower, the coolant flows between the rods. Model 2 is an hexagonal assembly type block with spheres dispersion and cylindrical channels for where the coolant with reflector in the axial ends also flows. The materials selected for each component of the assemblies, should be resistant to the radiation of fast neutrons and high operation temperatures, for what in both models the following materials were chosen: a mixture of uranium carbide more plutonium for the fuel; a mixture of silicon carbide in different theoretical density percentages for structures and shieldings; helium gas like coolant and a zirconium carbide mixture like reflector, which fulfill the restrictions of being resistant to the high operation temperatures and means of irradiation. General considerations were taken, which are common parameters to both types of assemblies, like size and materials used in the different parts of each model of assembly. The criticality calculations were obtained with the help of the MCNPx code, based on the Monte Carlo method. It was realized a validation of the atomic density data of each component of the assemblies, to have the certainty of the proportionate values that they were introduced of correct way in the code. The results show that model 1 makes better use of the fissile material in a assembly that has the same dimensions externally. That is to say, that from the only considered viewpoint, the neutron one, model 1 is better than model 2. (Author)

  18. 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

  19. Para entender los procesos electorales en América Central: elecciones, violencia y credibilidad

    OpenAIRE

    2012-01-01

    En este articulo, el autor parte de un concepto parcial y operativo de democracia electoral, utilizando los aportes fundamentales de Schumpeter, Sartori, Popper y Bobbio. Se plantea, asimismo, el problema de la participaci6n de la oposici6n en los procesos electorales realizados en sociedades atravesadas por conflictos armados y las condiciones requeridas para que los eventuales perdedores acepten los resultados de esos procesos, a la luz de la reflexión sociológica de Georg Simmel. Destaca e...

  20. ALBICAMPO, VARIEDAD DE FRIJOL DE TEMPORAL PARA VALLES ALTOS DE LA MESA CENTRAL

    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...

  1. 77 FR 37936 - Central Vermont Public Service Corporation, Gaz Métro Limited Partnership, Dominion Nuclear...

    Science.gov (United States)

    2012-06-25

    ... License I Dominion Nuclear Connecticut, Inc. (DNC or the licensee) is authorized to act as the agent for... operator of MPS3 is DNC, which owns 93.4707%. The remaining 4.7990% of the license is owned by... Wholesale Electric Company's ownership or DNC's ownership and operation of the facility. No physical...

  2. Centrality Dependence of Hadron Multiplicities in Nuclear Collisions in the Dual Parton Model

    CERN Document Server

    Capella, A

    2001-01-01

    We show that, even in purely soft processes, the hadronic multiplicity in nucleus-nucleus interactions contains a term that scales with the number of binary collisions. In the absence of shadowing corrections, this term dominates at mid rapidities and high energies. Shadowing corrections are calculated as a function of impact parameter and the centrality dependence of mid-rapidity multiplicities is determined. The multiplicity per participant increases with centrality with a rate that increases between SPS and RHIC energies, in agreement with experiment.

  3. Thermodynamic cycles of nuclear power plants; Les cycles thermodynamiques des centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Normand, T.; Andreani, J.; Tejedor, V.

    2010-07-01

    Above all a nuclear power plant is a thermal system whose efficiency relies on the thermodynamic cycle that turns the heat produced by the fission of uranium nuclei into electricity. The thermodynamic yield is an essential parameter to dimension a power plant. This book is dedicated to the presentation of the thermodynamic cycles that have been chosen in the different types of French PWR: CP0, P4, N4 and EPR. These cycles are classical steam cycles that have been used and optimized for 40 years, but they are physically limited and do not respond to the expectations of future generations of reactors. The last part deals with the thermodynamic cycles that might be involved in the fourth generation of nuclear reactors: cycles with super-critical steam, direct cycles for high temperature gas, indirect gas cycles, and cycles with super-critical CO{sub 2}. The first part of the book gives an account of the situation of nuclear power in France. (A.C.)

  4. 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)

  5. Diseño de receptor de torre central para generación directa de vapor con perfil de potencia variable longitudinal y transversalmente

    OpenAIRE

    Losada Godoy, Carlos

    2014-01-01

    En este estudio se ha realizado el diseño de un receptor de una central de Torre Central de energía solar para generación directa de vapor, mediante el uso de métodos numéricos, con un perfil de potencia incidente variable longitudinal y transversalmente. Para ello se ha dividido la geometría del receptor según el método de diferencias finitas, y se ha procedido a resolver las ecuaciones del balance de energía. Una vez resuelto el sistema de ecuaciones se dispone de la distribución de tempe...

  6. Desarrollo de nuevos aceros ferríticos ODS para aplicaciones nucleares

    OpenAIRE

    García Rodríguez, Nerea

    2016-01-01

    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...

  7. 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

  8. 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...

  9. El cultivo organotípico tridimensional de Sistema Nervioso Central como modelo para el estudio de la respuesta cerebral frente a Listeria monocytogenes

    OpenAIRE

    Remuzgo Martínez, Sara

    2014-01-01

    RESUMEN: Apenas se han utilizado cultivos organotípicos tridimensionales (3D-OC) para el análisis de la interacción entre las bacterias y el tejido cerebral, por ello, hemos estudiado por primera vez la infección de 3D-OC de cerebros de rata con L. monocytogenes. L. monocytogenes es un organismo modelo para microbiólogos e inmunólogos, por lo que resulta interesante utilizar esta bacteria para el estudio ex vivo de las interacciones con el sistema nervioso central (SNC). En este sentido, hemo...

  10. 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)

  11. Trends of Nuclear Power Plant support engineering in the Early 21st century; Tendencias de la ingenieria de apoyo a las centrales nucleares a principios del siglo XXI centrales nucleares a principios del siglo XXI

    Energy Technology Data Exchange (ETDEWEB)

    Cerezo, L. M.

    2001-07-01

    The rapid shift towards deregulation in the Electricity Industry in the 21st Century is placing a dramatic new emphasis on mid-term returns on generation investments. The economic pressures on capital-intensive generation systems such as hydraulic, coal and in particular nuclear are escalating significantly. In the old regulated system, the only concern was with marginal production costs, not total costs, as the return on the investment was ensured. Marginal production costs of Nuclear Power Plants are very low, which makes these plants ideal for base operation, but when the costs of recovering the investment are included, the total nuclear Kwh costs are relatively high. In addition, this industry is characterized by some specific economic risks resulting from the following: the risk of accidents, which, though not very probable, have a significant impact on the whole industry; the risk of prolonged, unscheduled outages involving prohibitively high costs, given the ratio of fixed/variable costs, the risk that outages are extended for refueling; and regulatory risks, which have major economic repercussions. (Author)

  12. 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.

  13. Strategies and actions for the mitigation of the phenomenon DENTING in the tube sheet (TTS Denting) steam generators of the NPP Asco Denting at the top of the SG tube sheet (TTS tube denting) has recently been experienced in new and replacement SGs at several plants; Estrategias y acciones para la mitigacion del fenomeno DENTING en la placa tubular de generadores de vapor (TTS DENTING) de la Central Nuclear de Asco

    Energy Technology Data Exchange (ETDEWEB)

    Espanol Villar, J.

    2013-07-01

    It is highly likely that the accumulation of sludge (deposits) on the tube sheet is clearly associated with the denting occurrence. More specifically, it is commonly believed that an aggressive crevice environment formed within the deposits or in the shallow tight tube sheet to tube crevice below the deposits is at the origin of the denting (tube deformation), and, when present, the consequent stress corrosion cracking (SCC). There are described a set of strategies that have been followed since the emergence of the TTS denting phenomenon on Steam Generator of the Nuclear Power Plants Asco I and II, influenced by the presence of hard sludge in the tube plate of Steam Generators, their results and the evolution of the phenomenon in relation to the various measures taken.

  14. The PRONUCLEAR role (1976-1986) in the human resource training for the nuclear area in Brazil: science history; O papel do PRONUCLEAR (1976 -1986) na formacao de recursos humanos para a area nuclear no Brasil: historia da ciencia

    Energy Technology Data Exchange (ETDEWEB)

    Schmiedecke, Winston Gomes

    2006-07-01

    In 1975, an agreement between the governments of Brazil and West-Germany was signed for the construction of nuclear power plants in Brazil as well as the extraction, processing and enrichment of uranium. As the result of the first oil crisis and facing the perspective of a continuous world energy crisis, the Brazilian government decided to turn to nuclear power as an alternative supply for the country's energy needs. However, serious limitations were present regarding the transfer of nuclear technology for a third world country. This paper analyzes some aspects of the process involved in the creation of the specialized human resources during the extent of the agreement between Brazil and West Germany. Since its inception, the agreement received harsh criticism from the Brazilian nuclear physics and related fields scientific communities. Because the planning and implementation of the agreement took place during a period of military dictatorship, the decisions relating to the agreement were never debated between the policy makers and the scientific community. Not surprisingly, the agreement received plenty of criticism that ranged from the actual need for nuclear power to technical feasibility and suspicious of possible military uses and even the very policies created to prepare human resources to work in the nuclear area. One of the most important tools of these policies was the Programa de Recursos Humanos para o Setor Nuclear - PRONUCLEAR (Nuclear Sector Human Resources Program), implemented in 1976 and gradually deactivated starting in 1983. (author)

  15. Quantification of aquifer properties with surface nuclear magnetic resonance in the Platte River valley, central Nebraska, using a novel inversion method

    Science.gov (United States)

    Irons, Trevor P.; Hobza, Christopher M.; Steele, Gregory V.; Abraham, Jared D.; Cannia, James C.; Woodward, Duane D.

    2012-01-01

    Surface nuclear magnetic resonance, a noninvasive geophysical method, measures a signal directly related to the amount of water in the subsurface. This allows for low-cost quantitative estimates of hydraulic parameters. In practice, however, additional factors influence the signal, complicating interpretation. The U.S. Geological Survey, in cooperation with the Central Platte Natural Resources District, evaluated whether hydraulic parameters derived from surface nuclear magnetic resonance data could provide valuable input into groundwater models used for evaluating water-management practices. Two calibration sites in Dawson County, Nebraska, were chosen based on previous detailed hydrogeologic and geophysical investigations. At both sites, surface nuclear magnetic resonance data were collected, and derived parameters were compared with results from four constant-discharge aquifer tests previously conducted at those same sites. Additionally, borehole electromagnetic-induction flowmeter data were analyzed as a less-expensive surrogate for traditional aquifer tests. Building on recent work, a novel surface nuclear magnetic resonance modeling and inversion method was developed that incorporates electrical conductivity and effects due to magnetic-field inhomogeneities, both of which can have a substantial impact on the data. After comparing surface nuclear magnetic resonance inversions at the two calibration sites, the nuclear magnetic-resonance-derived parameters were compared with previously performed aquifer tests in the Central Platte Natural Resources District. This comparison served as a blind test for the developed method. The nuclear magnetic-resonance-derived aquifer parameters were in agreement with results of aquifer tests where the environmental noise allowed data collection and the aquifer test zones overlapped with the surface nuclear magnetic resonance testing. In some cases, the previously performed aquifer tests were not designed fully to characterize

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

    Institute of Scientific and Technical Information of China (English)

    LIU Jian; CHU Yan-Yun; REN Zhong-Zhou; WANG Zai-Jun

    2012-01-01

    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.

  17. 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

  18. 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.

  19. 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)

  20. Aplicação de um modelo fuzzy DEA para priorizar modos de falha em sistemas nucleares

    Directory of Open Access Journals (Sweden)

    Pauli Adriano de Almada Garcia

    2009-08-01

    Full Text Available Neste artigo apresenta-se a aplicação de um modelo híbrido, baseado na análise envoltória de dados e em conjuntos fuzzy, para estabelecer uma priorização dos modos de falha levantados numa análise dos modos e efeitos de falha. O objetivo principal é ilustrar a aplicabilidade da modelagem para analisar sistemas complexos, como o sistema de controle químico e volumétrico de uma usina nuclear do tipo água pressurizada, onde uma grande quantidade de modos de falha deve ser avaliada. O modelo apresentado possibilita tratar variáveis linguísticas, i.e., permite que se tratem as opiniões de especialistas de modo mais efetivo num contexto de análise de riscos industriais quando há poucos dados disponíveis, como pode ocorrer em projetos com inovação tecnológica. Os resultados obtidos demonstram o potencial e a viabilidade de se utilizar uma modelagem híbrida para se estabelecer uma ordem de prioridade entre os diferentes modos de falha associados a um sistema complexo.In this paper one presents a data envelopment analysis and fuzzy sets based hybrid model application, in order to establish a priority ranking for the failure modes evaluated in a failure mode and effect analysis. The main objective is to present the applicability of this hybrid model to analyze complex systems, as the chemical and volumetric control system of a pressurized water reactor power plant, where a great bunch of failure modes must typically be evaluated. The presented modeling makes it possible the consideration of linguistic variables, i.e., it permits that one considers most effectively expert opinion in a risk analysis context when scarce data is available, as may occur in the plant design phase. The results obtained demonstrated the powerfulness and the viability of use of the proposed hybrid modeling to establish a priority ranking among many failure modes concerning a complex system.

  1. 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)

  2. Full waveform inversion of seismic reflection data from the Forsmark planned repository for spent nuclear fuel, eastern central Sweden

    Science.gov (United States)

    Zhang, Fengjiao; Juhlin, Christopher

    2014-02-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has been carrying out extensive studies at the planned repository for spent nuclear fuel at the Forsmark site in the eastern part of central Sweden since 2002. Identification of subhorizontal to gently dipping seismic reflections is especially important since these may represent transport routes for radionuclides. Studies have shown that such reflections can be generated by water filled fracture zones that have a lower velocity than the surrounding bedrock. Lithological changes, that is, mafic sills, may also be responsible for reflections in some cases. At the Forsmark site, it is difficult to distinguish fracture zones from mafic sills in the standard reflection seismic processed sections. However, since mafic sills usually have a positive velocity contrast with the background velocity field compared to fractures zones that have a negative one, the two possibilities could be differentiated if we could reconstruct the underground velocity field. Seismic full waveform inversion has the potential to perform this reconstruction, allowing us to discriminate between fractures zones and mafic sills. In this study, we apply a 2-D waveform inversion code on crooked line data sets acquired at the Forsmark site. This implies we are dealing with a 3-D geometry. We handle this problem by applying 3-D to 2-D coordinate projections. First, we perform a synthetic benchmark test with a similar geometry to that of the projected real data. We test both amplitude and phase inversion and phase only inversion on the synthetic data. The results show that the phase only inversion has fewer artefacts and is more stable. After successful application on the synthetic data, we apply the phase only waveform inversion on the real data. The resulting velocity fields show more details compared with the starting model based on first arrival traveltime tomography. Time domain synthetic data sets generated from the final velocity fields

  3. 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)

  4. Propuestas para el desarrollo de la internacionalización de los Gobiernos No Centrales (GNC): hacia el fortalecimiento de la paradiplomacia

    OpenAIRE

    Mario Edgar López-Ramírez; Jorge Alberto Quevedo-Flores

    2014-01-01

    El presente artículo examina los principales componentes para la formulación de la internacionalización de los Gobiernos No Centrales (GNC), que puede derivar en el fortalecimiento de la paradiplomacia. En este sentido se parte de explicar las bases de la internacionalización en forma general de los GNC, para después identificar los principales factores por los cuales los GNC deciden la internacionalización de sus regiones. Lo anterior ayuda a clarificar la estructura de la internacionalizaci...

  5. 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)

  6. Elaboración de un plan de aseguramiento de calidad para la fabricación de sistemas de tuberías para una central turbo - generadora de 100mw

    OpenAIRE

    2013-01-01

    En la ciudad de Quevedo, provincia de Los Ríos, se construye una central turbogeneradora que producirá una potencia nominal de 100 MW que serán entregados al sistema nacional interconectado; se requiere la fabricación, inspección y pruebas de sistemas de tuberías de los diferentes servicios que intervienen en el funcionamiento de esta central, para este fin se elaborara y pondrá en práctica un plan de aseguramiento de la calidad, el cual se incluirá procedimientos de inspecciones y pruebas, b...

  7. 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)

  8. 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

  9. 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.

  10. Strategic planning 2007-2011, an opportunity for quality, competitiveness and excellence of the Laguna Verde Central; Planeacion estrategica 2007-2011, una oportunidad para la calidad, competitividad y excelencia de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Rivera C, A. [CFE, Central Laguna Verde, Kilometro 42.5 Cardel Nautla, Veracruz (Mexico)]. e-mail: arr99999@cfe.gob.mx

    2007-07-01

    The reason is to give to know to the nuclear community in Mexico the good results that it located in the 2006 to the Laguna Verde Nucleo electric Central in the classification of the World Association of Nuclear Operators (WANO) like one of the best in the worldwide scale, and their Strategic Plan 2007-2011 like an opportunity to continue improving the Quality, the Competitiveness and the Excellency in their Generating Units. It stands out that the fuel reloads are carried out in systemic form in less than 30 days, and also other achievements like it is the certificate granted by PROFEPA of Clean Industry, the renovation of the Certifications of the ISO-9001 and the ISO-14001, as well as the accredit of the Laboratories, and they will give data of the project of the increment of power that their power rose in 15%. For those results in the Strategic Planning 2007-2011 are pointed out that the Laguna Verde Central is a highly viable option in Mexico, when continuing with reloads that will allow a capacity factor up of 90%, and the other concepts that will give the obtaining of the qualification level 1 of WANO in this strategic period. Finally I will conclude with the good news for the Nuclear Industry in Mexico that published the Reforma newspaper at November 01, 2006: 'To the president of Mexico, Felipe Calderon, interests him to impel during his command the alternating energy sources to the hydrocarbons, known it is that the hydrocarbons (petroleum, coal or natural gas) they are finite, while the appetite of the world for the energy is infinite. As you they know, Mexico possesses a nuclear plant that generates energy starting from enriched uranium: the famous Laguna Verde Thermonuclear Central. He declared that Mexico can and it should advance for the one on the way to the energy generation for the nuclear road.' (Author)0.

  11. 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)

  12. Turquía en Asia Central: un área geoestratégica para la Unión Europea

    OpenAIRE

    Pérez Fernández, David

    2011-01-01

    Asia Central representa un objetivo primordial en la actual política exterior turca, al igual que para la diplomacia rusa, china, estadounidense y europea. Turquía ha fortalecido su acercamiento hacia las ex-repúblicas soviéticas firmando importantes acuerdos que pueden ayudar a la Política de Vecindad que desarrolla la Unión Europea en la región. Pero Turquía, tampoco se olvida de Rusia, actor fundamental de Asia Central, con quién ha estrechado relaciones desde la llegada del AKP al poder. ...

  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. Modernization of the system integrated ERIS computer (SIEC) of the nuclear power plant Cofrentes; Modernizacion del sistema integrado ERIS computador (SIEC) de la Central Nuclear de cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, R.; Ramos, M.; Mendez, J.; Zuriaga, J. V.

    2011-07-01

    The complete replacement of the SIEC of Nuclear Power Cofrentes is framed within the process of modernization of systems instrumentation and control in which the Spanish nuclear power plants are immersed, process caused by an increase in security, as well as the obsolescence and lack of spare parts.

  15. Legal framework for the restoration of contaminated areas following nuclear accidents; Marco normativo para la restauracion de zonas contaminadas despues de un accidente nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ramos Salvador, L. M.

    2013-06-01

    The accident that occurred at the Fukushima Dai-ichi nuclear power plant in Japan has underlined the need to strengthen the principles, criteria and standards of radiological protection applicable to programmes for the restoration and long-term surveillance of areas affected by nuclear accidents. (Author)

  16. Legal framework for the restoration of contaminated areas following nuclear accidents; Marco normativo para la restauracion de zonas contaminadas despues de un accidente nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ramos Salvador, L. M.

    2013-09-01

    The accident that occurred at the Fukushima Dai-ichi nuclear power plant in Japan has underlined the need to strengthen the principles, criteria and standards of radiological protection applicable to programmes for the restoration and long-term surveillance of areas affected by nuclear accidents. (Author)

  17. Comparative study on storage and disposal of liquid waste in nuclear medicine diagnostic; Estudio comparativo sobre almacenamiento y eliminacion de residuos liquidos para diagnostico en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Vazquez Vazquez, R.; Sanchez Garcia, M.; Santamarina Vazquez, F.; Soto Bua, M.; Montoya Pastor, A.; Luna Vega, V.; Mosquera Suueiro, J.; Otero Martinez, C.; Lobato Busto, R.; Pombar Camean, M.

    2011-07-01

    The aim of this paper presents a comparative study on the total activity of material discharge to public sewers and the activity concentration in the final point of discharge, for a typical installation of Nuclear Medicine, in the case of having no deposit or storage of liquid radioactive waste from diagnostic techniques, based on actual data from the Nuclear Medicine Department of our hospital.

  18. Nuclear safety and renewals of authorisations for operation of plants nuclear in the law of sustainable economy; La seguridad nuclear y las renovaciones de las autorizaciones de funcionamiento de las centrales nucleares en la ley de economia sostenible

    Energy Technology Data Exchange (ETDEWEB)

    Bello Paredes, S. A.

    2011-07-01

    Depending on the nature of the activity to develop, the legislation establishes a different typology of administrative authorizations that must ensure the adaptation to law for all activity relating to nuclear facilities, from the planning stage of activity, to its closing and dismantling.

  19. Corrosão de liga 800GN em ambiente do circuito secundário da Central Nuclear de Angra 2

    OpenAIRE

    Fabio Abud Mansur

    2015-01-01

    A liga 800GN (grau nuclear) é um material utilizado na fabricação de geradores de vapor para reatores de água pressurizada (PWR) de usinas nucleares devido à sua elevada resistência à corrosão. A resistência à corrosão da liga 800GN é devida ao caráter protetor da película de óxido formada na superfície do tubo em contato com a água pressurizada à alta temperatura. No entanto, a corrosão tem sido a principal causa de falhas nos tubos dos geradores de vapor de usinas nucleares. Os problemas ge...

  20. 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.

  1. 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)

  2. Interesting tools for the cybersecurity plan of a nuclear power plant; Herramientas de utilidad para el plan de Ciberseguridad de una Planta Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pareja, I.; Carrasco, J. A.; Cerro, F. J. del

    2012-07-01

    The use of digital technologies in monitoring and control systems of nuclear power plants and their connectivity requirements, originate cybersecurity difficulties that should be addressed in a cybersecurity plan. This plan should guide the policies and procedures followed during the design maintenance and operation of the systems inside a nuclear power plant. It also should refer to adequate tools able to reach the established cybersecurity requirements. The combination of Datadiodes and tools for publishing video (like tVGA2web), permit an isolation and remote maintenance in a 100% safety way and their use should be disseminated. In the paper other type of tools useful for nuclear power plants are also mentioned.

  3. 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

  4. On the evolution of the nuclear modification factors with rapidity and centrality in d+Au collisions at $\\sqrt{s_{NN}} = 200 GeV

    CERN Document Server

    Arsene, I; Beavis, D; Besliu, C; Budick, B; Bøggild, H; Chasman, C; Christensen, C H; Christiansen, P; Cibor, J; Debbe, R; Enger, E; Gaardhøje, J J; Germinario, M; Hagel, K; Ito, H; Jipa, A; Jundt, F; Jordre, J I; Jorgensen, C E; Karabowicz, R; Kim, E J; Kozik, T; Larsen, T M; Lee, J H; Lee, Y K; Lindal, S; Lystad, R; Løvhøiden, G; Majka, Z; Makeev, A; Mikelsen, M; Murray, M; Natowitz, J B; Neumann, B; Nielsen, B S; Ouerdane, D; Planeta, R; Rami, F; Ristea, C; Ristea, O; Röhrich, D; Samset, B H; Sandberg, D; Sanders, S J; Scheetz, R A; Staszel, P; Tveter, T S; Videbaek, F; Wada, R; Yin, Z; Zgura, I S

    2004-01-01

    We report on a study of the transverse momentum dependence of nuclear modification factors $R_{dAu}$ for charged hadrons produced in deuteron + gold collisions at $\\sqrt{s_{NN}=\\unit[200]{GeV}$, as a function of collision centrality and of the pseudorapidity ($\\eta = 0,1,2.2,3.2 $) of the produced hadrons. We find significant and systematic decrease of $R_{dAu}$ with increasing rapidity. The midrapidity enhancement and the forward rapidity suppression are more pronounced in central collisions relative to peripheral collisions. These results are relevant to the study of the possible onset of gluon saturation at RHIC energies.

  5. 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.

  6. The dilemmas of nuclear energy in Spain; Los dilemas de la energia nuclear en Espana. Alargamiento de la vida de las centrales y nuevas inversiones

    Energy Technology Data Exchange (ETDEWEB)

    Aranzadi, C.

    2008-07-01

    This article reviews the economic basis of some controversial political choices concerning the future of nuclear energy in Spain: authorisation or refusal of existing nuclear power plants life extension and investment in new ones. These decisions are to be taken in an environment characterised by a reluctant public opinion that feel uninformed and whose risk perception differs deeply from experts assessment, but prefers not to be consulted. (Author) 19 refs.

  7. Exploitation of the nuclear plant Asco and the benthic community of the river Ebro; Explotacion de la central nuclear Asco y la comunidad bentonica del rio Ebro

    Energy Technology Data Exchange (ETDEWEB)

    Esparza Martin

    2015-07-01

    The Ebro river passing through the town of Asco in the province of Tarragona, provides the necessary water for the operation of the nuclear plant. water of circulation flows and service components are returned completely to the river, or if operation of cooling towers, decreased in a small part. Evaporative losses account for approximately 1% of the total flow used for two nuclear groups. (Author)

  8. 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)

  9. The integripennis species group of Geocharidius Jeannel, 1963 (Carabidae, Bembidiini, Anillina) from Nuclear Central America: a taxonomic review with notes about biogeography and speciation

    OpenAIRE

    Igor Sokolov; David Kavanaugh

    2014-01-01

    Abstract Our review recognizes 15 species of the integripennis species group of Geocharidius from Nuclear Central America, include three species previously described ( Geocharidius gimlii Erwin, Geocharidius integripennis (Bates) and Geocharidius zullinii Vigna Taglianti) and 12 described here as new. They are: Geocharidius andersoni sp. n. (type locality: Chiapas, Chiapas Highlands, Cerro Huitepec) and Geocharidius vignatagliantii sp. n. (type locality: Chiapas, Motozintla, Sierra Madre de C...

  10. Propuesta de mejora para el Complejo Hospitalario de Navarra, Hospital D: manual de procedimientos para la Central de Esterilización

    OpenAIRE

    2014-01-01

    La esterilización es una ciencia en la que se emplean tecnologías muy variadas con el fin de lograr la destrucción de todos los microorganismos. Una vez que se ha esterilizado todo el material, debe mantenerse esa condición hasta el momento de “uso” de los equipos. La central de esterilización (en adelante CE o Central), es una unidad de vital importancia dentro de la estructura de un hospital. Recibe una enorme cantidad y variedad de instrumental quirúrgico que debe ser recogido, limpiad...

  11. Retraining of inspection systems for Swedish nuclear power plants; Recualificacion de sistemas de inspeccion para centrales suecas

    Energy Technology Data Exchange (ETDEWEB)

    Gomez, P.; Serrano, P.; Regidor, J. J.

    2012-07-01

    Currently the project is in its final part documentary level was achieved by passing the PAT (acceptance test procedure) approved by Oskarshamn and ending once the body Swedish qualification, SQC, review, send your comments and after evaluation, approve all documentation.

  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. 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...

  14. 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

  15. 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.

  16. 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)

  17. 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)

  18. 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)

  19. Improvements MOIRA system for application to nuclear sites Spanish river; Mejoras en el sistema MOIRA para suaplicacion a los emplazamientos nucleares fluviales espanoles

    Energy Technology Data Exchange (ETDEWEB)

    Gallego Diaz, E.; Iglesias Ferrer, R.; Dvorzhak, A.; Hofman, D.

    2011-07-01

    Possible consequences of a nuclear accident must have radioactive contamination in the medium and long-term freshwater aquatic systems. Faced with this problem, it is essential to have a realistic assessment of the radiological impact, ecological, social and economic potential management strategies, to take the best decisions rationally. MOIRA is a system of decision support developed in the course of the European Framework Programmes with participation of the UPM, which has been improved and adapted to Spanish nuclear sites in recent years in the context ISIDRO Project, sponsored by the Council Nuclear, with the participation of CIEMAT and UPM. The paper focuses on these advances, primarily related to complex hydraulic systems such as rivers Tajo, Ebro and Jucar, which are located several Spanish plants.

  20. The modernization of the process computer of the Trillo Nuclear Power Plant; Modernizacion del ordenador de proceso de la Central Nuclear de Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Martin Aparicio, J.; Atanasio, J.

    2011-07-01

    The paper describes the modernization of the Process computer of the Trillo Nuclear Power Plant. The process computer functions, have been incorporated in the non Safety I and C platform selected in Trillo NPP: the Siemens SPPA-T2000 OM690 (formerly known as Teleperm XP). The upgrade of the Human Machine Interface of the control room has been included in the project. The modernization project has followed the same development process used in the upgrade of the process computer of PWR German nuclear power plants. (Author)

  1. 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)

  2. 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

  3. Management of distortion channels in the Cofrentes NPP; Gestion de la deformacion de canales en la central nuclear de Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Albendea, J. C.; Garcia, P. J.; Iglesias, J.; Mascarell, R.

    2015-07-01

    Fuel channels distortion in BWR (Boiling Water Reactor) reactors may have implication for safety. This phenomenon is complex and, at the present time it is not known in detail. This article provides the Iberdrola Generacion Nuclear SAU ongoing activities to know, predict and mitigate the consequences that this phenomenon may cause in Cofrentes Nuclear Power Plant. (Author)

  4. 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...

  5. Las comunidades virtuales de expertos como mecanismo para transmitir el conocimiento: una propuesta metodológica para el Banco Central de Costa Rica

    OpenAIRE

    2013-01-01

    Se describe la investigación teórica y práctica realizada con el fin de obtener un planteamiento metodológico para crear una comunidad de colaboración virtual como nuevo espacio de aprendizaje organizacional, que propicie el intercambio de conocimientos y experiencia práctica, moderados por quienes mejor conocen de un tema: los expertos, asistiendo a quienes lo requieran en el momento oportuno. Esta propuesta se apoya en el uso de un portal virtual como herramienta de comuni...

  6. Aplicativo multimídia em plataforma móvel para o ensino da mensuração da pressão venosa central

    Directory of Open Access Journals (Sweden)

    Elizabeth Correia Ferreira Galvão

    2012-10-01

    Full Text Available O objetivo do estudo foi desenvolver e avaliar um aplicativo multimídia em plataforma móvel para o ensino da Mensuração da Pressão Venosa Central (PVC. A pesquisa foi desenvolvida em três fases (Levantamento das necessidades; Metodologia de desenvolvimento do aplicativo multimídia e Avaliação do aplicativo multimídia. A multimídia foi o método escolhido por favorecer um ambiente motivador e dinâmico, integrar imagens e textos num aplicativo disponível para celulares, constituindo-se um meio móvel e autônomo de aprendizagem. Os resultados permitem demonstrar a viabilidade do desenvolvimento da ferramenta para subsidiar a prática pedagógica e abrem perspectivas para acreditar que, na educação em Enfermagem, a tecnologia disponível pode descortinar novos modos de aprender significativamente.

  7. The determinist nature of the annalist of accidents at nuclear power plants; El caracter determinista del analisis de accidentes en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Pelayo, F.; Mendizabal, R.

    2005-07-01

    This article develops the concept of determinist approximation or method to the analysis of accidents at nuclear facilities and explains how the aim was fulfilled with respect to the protection of workers at these facilities and the public in general. (Author) 11 refs.

  8. 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)

  9. 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)

  10. 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)

  11. Whole study of nuclear matter collective motion in central collisions of heavy ions of the FOPI detector; Etude complete du mouvement collectif de la matiere nucleaire dans les collisions centrales d'ions lourds avec le detecteur FOPI

    Energy Technology Data Exchange (ETDEWEB)

    Bendarag, A

    1999-07-09

    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)

  12. 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...

  13. Propuesta de evaluación del desempeño, basado en competencias para el Instituto Nacional de Aprendizaje, unidad regional Pacífico Central

    OpenAIRE

    Chacón-Naranjo, Dixiana

    2011-01-01

    Tesis de maestría -- Universidad de Costa Rica. Posgrado en Administración y Dirección de Empresas. Maestría Profesional en Administración y Dirección de Empresas, 2011 El objetivo general es evaluar el proceso de gestión y evaluación del desempeño en el Instituto Nacional de Aprendizaje, Unidad Regional Pacífico Central, para plantear una propuesta de soluciones a los problemas que se identifiquen. El tipo de investigación es descriptiva, con uso de la metodología analítico-sint...

  14. Un análisis de variables fiscales del Gobierno Central del Uruguay para el período 1989-2006

    OpenAIRE

    Elena Ganón; Ina Tiscordio

    2007-01-01

    Este trabajo estudia el comportamiento trimestral de las variables fiscales del Gobierno Central del Uruguay en el período 1989.I–2006.IV. Se realiza un análisis descriptivo de las variables fiscales y se elaboran modelos univariados de series de tiempo con el objetivo de predecir el comportamiento de las mismas. Se incluye además un seguimiento y evaluación de las predicciones realizadas para el año 2006 y se analiza la vinculación del ciclo de cada variable con el del PIB. Estas prediccione...

  15. Simulación de condensación en pared con ANSYS CFX para aplicaciones de seguridad nuclear

    OpenAIRE

    2016-01-01

    La condensación es el proceso donde ocurre un cambio de fase gaseosa a líquida. El modelado de la condensación de vapor es muy importante en diversas aplicaciones de ingeniería, por ejemplo, en seguridad nuclear. Este proyecto estudia las posibilidades de modelar la condensación en la pared de una contención nuclear con ANSYS CFX. En presencia de gases no condensables, este fenómeno es de gran relevancia en los sistemas de seguridad pasiva en reactores nucleares. La condensación en las est...

  16. 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.

  17. 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.

  18. 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)

  19. Sustainability indicators for innovation and research institutes of nuclear area in Brazil; Indicadores de sustentabilidade para institutos de pesquisa e inovacao da area nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alves, S.F.; Barreto, A.A.; Rodrigues, P.C.H.; Feliciano, V.M.D., E-mail: sfa@cdtn.br, E-mail: aab@cdtn.br, E-mail: pchr@cdtn.br, E-mail: vmfj@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2016-11-01

    Indicators are relevant tools for measuring sustainability process. In this study, the relevance of sustainability indicators appropriate for research and innovation institutes in Brazil is discussed. As reference for case study, nuclear research and innovation institutes were chosen. Sixty-nine sustainability indicators were considered. Some of these indicators were obtained from lists in the literature review, distributed between the dimensions environmental, economic, social, cultural and institutional. The other indicators were developed through discussions between professionals from nuclear, environmental, economic, social and cultural areas. Among the investigated indicators, 32 were selected as being the most relevant. Discrepancies were found during the analysis the opinions of the experts in relation to sustainability dimensions proposed. (author)

  20. 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)

  1. Risks and challenges associated with the design and construction of a nuclear power plant; Control de riesgos y retos asociados al diseno y construccion de una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Liebana Martinez, B.; Armas Garcia, A.; Martinez Gozalo, I.

    2011-07-01

    The construction of a nuclear power plant project, considering the period prior to the operation of the plant, requires a very strict risk control to ensure compliance with a series of challenges. The present paper identifying the most important challenges facing the construct ability and license requirements of the process, identifying the interfaces and proposing a methodology of construction to meet the challenge of a construction process in 5 years.

  2. 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

  3. 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)

  4. 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.

  5. Calculation methods of reactivity using derivatives of nuclear power and Filter fir; Metodos para o calculo da reatividade usando derivadas da potencia nuclear e o filtro FIR

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, Daniel Suescun

    2007-07-01

    This work presents two new methods for the solution of the inverse point kinetics equation. The first method is based on the integration by parts of the integral of the inverse point kinetics equation, which results in a power series in terms of the nuclear power in time dependence. Applying some conditions to the nuclear power, the reactivity is represented as first and second derivatives of this nuclear power. This new calculation method for reactivity has special characteristics, amongst which the possibility of using different sampling periods, and the possibility of restarting the calculation, after its interruption associated it with a possible equipment malfunction, allowing the calculation of reactivity in a non-continuous way. Apart from this reactivity can be obtained with or without dependency on the nuclear power memory. The second method is based on the Laplace transform of the point kinetics equations, resulting in an expression equivalent to the inverse kinetics equation as a function of the power history. The reactivity can be written in terms of the summation of convolution with response to impulse, characteristic of a linear system. For its digital form the Z-transform is used, which is the discrete version of the Laplace transform. In this method it can be pointed out that the linear part is equivalent to a filter named Finite Impulse Response (Fir). The Fir filter will always be, stable and non-varying in time, and, apart from this, it can be implemented in the non-recursive way. This type of implementation does not require feedback, allowing the calculation of reactivity in a continuous way. The proposed methods were validated using signals with random noise and showing the relationship between the reactivity difference and the degree of the random noise. (author)

  6. 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)

  7. 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.

  8. Dendrogramas de densidade para Hovenia dulcis Thunberg na região central do estado do Rio Grande do Sul, Brasil

    Directory of Open Access Journals (Sweden)

    Gerson Luiz Selle

    2010-09-01

    Full Text Available O objetivo principal deste trabalho foi elaborar dendrogramas para o manejo de densidade (DMD, em populações de Hovenia dulcis localizadas na região central do estado do Rio Grande do Sul, Brasil. Para tanto, foram utilizadas informações de dois povoamentos, com idades de 25 anos, localizado na Fundação de Pesquisa Agropecuária (FEPAGRO e de uma população de árvores livres, com DAPs variando de 5 a 45 cm, localizado no campus da Universidade Federal de Santa Maria (UFSM, RS. Nos povoamentos sob concorrência, os dados foram coletados em árvores dos estratos dominante, intermediário e dominado, pelo método da densidade pontual. As árvores livres de concorrência foram coletadas sob a forma de censo. Como conclusão obteve-se que o modelo de Reineke ajustou-se satisfatoriamente para estimar as linhas de densidade de fechamento do dossel e de autodesbaste, com os coeficientes angulares se aproximando de -1,5, comprovando que a lei da potência de -3/2 de autodesbaste foi contemplada e que a hipótese postulada por Reineke tambem foi satisfeita. A densidade populacional, para a lotação do dossel, foi de 42,5% do número máximo de árvores, sendo possível construir diagramas para o manejo da densidade, dos 5 aos 31 cm de diâmetro da árvore de área basal média.

  9. 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)

  10. 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).

  11. 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)

  12. 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.

  13. 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

  14. 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

    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...

  15. Economic impact associated with the decommissioning process of Vandellos I Nuclear Power Plant; Informe final. Impacto economico del desmantelamiento de la central nuclear Vandellos I

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Silva, M.

    2005-07-01

    This economic study examines the economic impact associated with the decommissioning process of the Vandellos I Nuclear Power Plant, measured in terms of the global income that generated the ending of the Nuclear Power Plant activity, on the territory. To this end, we will take into account the total investment that has been necessary to complete the process of decommissioning. The economic impact is calculated using the Input- Output methodology. Briefly, the Input-Output model defines a group of accounting relationships that reflect the links taking place within the production system. The Input-Output model is based on the assumption that given an increase (decrease) in the final demand of one sector, this sector should produce more (less) to satisfy this new demand. At the same time, this will lead to demand more (less) intermediate consumption goods from the remainder sectors of the economy. Then, these sectors should produce more (less) and use more (less) intermediate inputs, and so on. Therefore, an increase (decrease) in the final demand of one sector multiplies the effect throughout the economy, following the interdependency relationships that exist among the productive activities. We will start by collecting an exhaustive economic information. This information covers the whole decommissioning process and the whole economic and productive activity of the province of Tarragona. Next, this information is used with the objective of building an Input-Output table of the province that will serve as a base to establish the global economic impact of Vandellos I. The incomes and employment generation has been evaluated in the province of Tarragona that, following the main assumptions, correspond to the global effects of the decommissioning. In addition, we have evaluated the income and employment generation within the region where the nuclear power plant is located. The total income impacts show a high multiplier effect due to the investment carried out during the

  16. 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)

  17. 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.

  18. Nuclear modification factor for charged pions and protons at forward rapidity in central Au + Au collisions at 200 GeV

    Science.gov (United States)

    Brahms Collaboration; Arsene, I.; Bearden, I. G.; Beavis, D.; Besliu, C.; Budick, B.; Bøggild, H.; Chasman, C.; Christensen, C. H.; Christiansen, P.; Debbe, R.; Enger, E.; Gaardhøje, J. J.; Germinario, M.; Hagel, K.; Holm, A.; Ito, H.; Jipa, A.; Jundt, F.; Jørdre, J. I.; Jørgensen, C. E.; Karabowicz, R.; Kim, E. J.; Kozik, T.; Larsen, T. M.; Lee, J. H.; Lee, Y. K.; Lindal, S.; Lystad, G.; Løvhøiden, G.; Majka, Z.; Makeev, A.; Mikelsen, M.; Murray, M.; Natowitz, J.; Nielsen, B. S.; Ouerdane, D.; Płaneta, R.; Rami, F.; Ristea, C.; Ristea, O.; Röhrich, D.; Samset, B. H.; Sandberg, D.; Sanders, S. J.; Staszel, P.; Tveter, T. S.; Videbæk, F.; Wada, R.; Yang, H.; Yin, Z.; Zgura, I. S.

    2007-07-01

    We present spectra of charged pions and protons in 0 10% central Au + Au collisions at s=200 GeV at mid-rapidity (y=0) and forward pseudorapidity (η=2.2) measured with the BRAHMS experiment at RHIC. The spectra are compared to spectra from p+p collisions at the same energy scaled by the number of binary collisions. The resulting nuclear modification factors for central Au + Au collisions at both y=0 and η=2.2 exhibit suppression for charged pions but not for (anti-) protons at intermediate p. The p¯/π ratios have been measured up to p˜3 GeV/c at the two rapidities and the results indicate that a significant fraction of the charged hadrons produced at intermediate p range are (anti-) protons at both mid-rapidity and η=2.2.

  19. 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.

  20. 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)

  1. 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)

  2. 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

  3. 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.)

  4. 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.

  5. Desarrollo de modelos 3D de los edificios de contención de la Central Nuclear de Almaraz y de la Central Nuclear de Trillo con el código GOTHIC 8.0

    OpenAIRE

    Jiménez Varas, Gonzalo; Bocanegra Melián, Rafael; Fernández Cosials, Kevin; Barreira Pereira, Pilar; Rey Peinado, Luis; Posada Barral, Jose María; Martínez-Murillo Méndez, Juan Carlos

    2014-01-01

    El análisis de los accidentes tipo LOCA o MSLB en una contención PWR-W normalmente se simulan con la opción de volúmenes de control con parámetros agrupados en GOTHIC, ya que es lo que hasta ahora se ha considerado adecuado para el análisis de licencia. Sin embargo, para el estudio de detalle del comportamiento termo-hidráulico de cada recinto de la contención, podría ser más adecuado contar con un modelo tridimensional que representase más fielmente la geometría de la contención. E...

  6. Treze passos para o juízo final: a nova era do desarmamento nuclear dos Estados Unidos e da Rússia Thirteen steps to judgement day: the new era of Russian and North American nuclear disarmament

    Directory of Open Access Journals (Sweden)

    Diego Santos Vieira de Jesus

    2008-08-01

    Full Text Available Este artigo procura explicar por que os líderes dos EUA e da Rússia não implementaram total e efetivamente o plano de ação de treze pontos práticos para o desarmamento nuclear, estabelecido na Conferência de Revisão do Tratado de Não-Proliferação Nuclear em 2000. As decisões relacionadas aos treze pontos, tomadas pelos membros dos Executivos das duas maiores potências nucleares, são vistas como resultado da conciliação de imperativos internos e externos por esses indivíduos, que enfrentam oportunidades e dilemas estratégicos distintos simultaneamente nos âmbitos doméstico e internacional. São consideradas as escolhas políticas de membros dos Executivos nacionais e estrangeiros, Legislativos e principais grupos de interesse desses países, bem como a distribuição de poder sobre a formulação da decisão nacional, estabelecida pelas instituições políticas domésticas. As hipóteses apontam que os membros dos Executivos desses países - apoiados por grande parte dos membros dos Legislativos e dos principais grupos de interesse envolvidos, como as Forças Armadas - procuraram garantir autonomia para definir a estrutura e a composição de forças estratégicas e táticas, modernizar arsenais atômicos e operar uma força capaz de lidar com contingências que envolvam não apenas potências nucleares tradicionais, mas principalmente novos Estados detentores de armas de destruição em massa e organizações terroristas.This article aims to explain why U.S. and Russian leaders have not implemented totally and effectively the thirteen practical-step plan of action on nuclear disarmament agreed at the 2000 Nuclear Non-Proliferation Treaty Review Conference. The decisions with regard to the thirteen steps, taken by members of U.S. and Russian Executives, are seen as the result of the conciliation of internal and external imperatives by those individuals, who face distinctive strategic opportunities and dilemmas simultaneously

  7. 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)

  8. Nuclear magnetic resonance system with continuous flow of polarized water to obtain the traceability to static magnetic fields; Sistema de ressonancia magnetica nuclear com fluxo continuo de agua polarizada para obtencao da rastreabilidade para campos magneticos estaticos

    Energy Technology Data Exchange (ETDEWEB)

    Martin, Ramon Valls; Nazarre, Diego Joriro, E-mail: ramon@ipt.br [Instituto de Pesquisas Tecnologicas (IPT), Sao Paulo, SP (Brazil)

    2013-07-01

    We have developed a system to obtain the traceability of field or magnetic induction intensity in the range of 2 μT up to 2 T, even in the presence of magnetic field gradients or noisy environments. The system is based on a nuclear magnetic resonance magnetometer, built in streaming water. The calibration procedure of a coil for magnetic field generation is described, as well as the results obtained and the estimated uncertainty (author)

  9. Nuclear power plants of ENDESA: strategical and operational fields. Research and Development. Centrales Nucleares de ENDESA Campos de actuacion estrategica y operativa. Investigacion y desarrollo

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, E. (Empresa Nacional de Electricidad. ENDESA. (Spain))

    1994-01-01

    The total nuclear power installed at ENDESA plants amounts 1467 Mw. Environmental management is focused onto waste management, emissions management and safety during operation. The strategy of ENDESA is related with actions to improve research and development in advanced power reactors and passive power plants like AP-600 and SBWR. There is also a collaboration with EPRI to define the specifications for future reactors. ENDESA participates within the European NPI program for evolutive reactors to develop the French EPRI reactor. R+D in materials is organized in: steam generators projects, analysis of neutronic irradiation of the vessel in Light Water Reactors, analysis of cladding and fuel rods subjected to high burning, inspection of cracks in vessel PWR.

  10. 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)

  11. Dispositivo de posicionamiento de muestras biológicas para su irradiación en un canal radial de un reactor nuclear // Biological samples positioning device for irradiations on a radial channel at the nuclear research reactor

    Directory of Open Access Journals (Sweden)

    Maritza Rodríguez - Gual

    2010-05-01

    Full Text Available ResumenPor la demanda de un dispositivo experimental para el posicionamiento de las muestras biológicaspara su irradiación en un canal radial de un reactor nuclear de investigaciones en funcionamiento, seconstruyó y se puso en marcha un dispositivo para la colocación y retirada de las muestras en laposición de irradiación de dicho canal. Se efectuaron las valoraciones económicas comparando conotro tipo de dispositivo con las mismas funciones. Este trabajo formó parte de un proyectointernacional entre Cuba y Brasil que abarcó el estudio de los daños inducidos por diferentes tipos deradiación ionizante en moléculas de ADN. La solución propuesta es comprobada experimentalmente,lo que demuestra la validez práctica del dispositivo. Como resultado del trabajo, el dispositivoexperimental para la irradiación de las muestras biológicas se encuentra instalado y funcionando yapor 5 años en el canal radial # 3(BH#3 Palabras claves: reactor nuclear de investigaciones, dispositivo para posicionamiento de muestras,___________________________________________________________________________AbstractFor the demand of an experimental device for biological samples positioning system for irradiationson a radial channel at the nuclear research reactor in operation was constructed and started up adevice for the place and remove of the biological samples from the irradiation channels withoutinterrupting the operation of the reactor. The economical valuations are effected comparing withanother type of device with the same functions. This work formed part of an international projectbetween Cuba and Brazil that undertook the study of the induced damages by various types ofionizing radiation in DNA molecules. Was experimentally tested the proposed solution, whichdemonstrates the practical validity of the device. As a result of the work, the experimental device forbiological samples irradiations are installed and operating in the radial beam hole #3(BH#3

  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. 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)

  14. 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

  15. 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)

  16. 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)

  17. 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.

  18. Simulación de operación de una central nuclear con el simulador gráfico interactivo: LOCA en rama fría en BOL, MOL y EOL

    OpenAIRE

    Penche Alonso, Marta

    2016-01-01

    La energía nuclear convencional se basa en reacciones de fisión producidas cuando los átomos de uranio absorben neutrones. Se tratan de reacciones autosostenidas en el combustible del reactor nuclear. Este trabajo se enmarca dentro del campo de la seguridad nuclear, estudiando, mediante simulaciones, el desarrollo del accidente base de diseño LOCA. En la seguridad de una central nuclear hay varios niveles: - Primer nivel: la prevención de accidentes. - Segundo nivel: el control de la...

  19. Los retos para la Banca Central en el desarrollo de un programa de estabilización

    OpenAIRE

    Arista, José

    1989-01-01

    El principal objetivo de este trabajo es examinar a la luz de la experiencia de los últimos procesos de estabilización, los principales problemas que tiene que resolver la Banca Central durante la transición de un contexto de alta inflación a otro donde existe mayor estabilidad en los precios. Nuestra conclusión final es que el desarrollo de una política monetaria, similar al de una economía estable, tiende a generar mecanismos de transferencia de ingreso, altas tasas de interés, inestabilida...

  20. 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

  1. 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)

  2. Estructura metálica del edificio para la central hortofrutícola de «Frutas Ponche», en Corbera. Valencia/España

    Directory of Open Access Journals (Sweden)

    Ferrer y Ferrer, Carlos M.

    1982-12-01

    Full Text Available Not available.La solución estructural elegida para el edificio de la central hortofrutícola de «Frutas PONCHE», que ocupa una superficie de 50 x 86 m2, es la de un pórtico a dos aguas, en el cual se evita el descenso de la cumbrera por medio de soportes en los pórticos principales y de jácenas trianguladas en los pórticos secundarios. Las dos marquesinas del edificio, de mucho canto y 8,5 m de voladizo, facilitan el desagüe y. Junto con el cielorraso de chapa lacada, forman un óptimo conjunto arquitectónico.

  3. Algunas hipótesis para el estudio de la resistencia campesina en la región central de Colombia. Siglo XIX

    Directory of Open Access Journals (Sweden)

    Guiomar Dueñas Vargas

    2012-07-01

    Full Text Available Las formas corrientes de resistencia entre los campesinos incluyen el disimulo, la lentitud en el ejercicio de sus tareas, el fingimiento de ignorancia, el hurto de pequeñas cosas y el sabotaje. Otras formas de acción campesina comprende los desafíos a la usurpación de sus asentamientos por empresarios de tierras. A través de estas formas de resistencia los campesinos prepararon el escenario para el desarrollo de la conciencia de clase campesina en épocas posteriores. La historiografía colombiana ha subestimado la importancia de los campesinos en el Siglo XLX en la región Central colombiana debido posiblemente al reducido número de revueltas rurales, hecho que contrasta con la atención que se ha puesto en el estudio de los levantamientos campesinos del siglo XX.

  4. 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)

  5. 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)

  6. Advantages of using 3D design tools in the nuclear power plants projects; Ventajas del uso de herramientas de diseno 3D en los proyectos de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Roldan, P.; Melendro, J.; Gomez, A.; Hermana, I.

    2011-07-01

    It there is anything that distinguished Iberdrola Ingeneria y Construccion, as part of the Iberdrola Group, it is its firm commitment to innovation and continuous improvement. This is the philosophy that led the company to its interest in three-dimensional design tools back when they were in an early stage of development : very little international implementation, lack of integration with other applications, absence of previous experiences to understand the best possible configuration for each case, etc. Nevertheless, the company was able to see the tremendous advantage of having a construction program in the early months of a project- a detailed program that could predict, and therefore avoid, the problems that, if not anticipated, would arise in the construction phase when they result in higher costs, longer time frames and a multitude of complications. This is precisely what 3D design tools offer prediction and this has been proven in the latest combined cycle projects executed with these tools. A project executed without errors not only decreases cost and time overruns, but also necessarily increases the quality of the end result. Efficiency and quality: these are both basic goals of Iberdrola Ingenieria y Construccion. The knowledge of and skill in the use of these tools have grown at the same time that their development has reached increasingly higher levels. As a result, Iberdrola Ingenieria y Conctruccion now has intensive experience in the use of 3D design tools and is preprared for the future challenges posed by these tools, the capabilities of which have attained such heights that it is possible to take on one of the most technically challenging projects that exists a nuclear power plant. And we are ready. (Author)

  7. 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)

  8. 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.

  9. Identificação dos fatores de risco para o transtorno do processamento auditivo (central em pré-escolares Identification of risk factors for the (central auditory processing disorder in preschool children

    Directory of Open Access Journals (Sweden)

    Daniela Musskopf da Luz

    2011-08-01

    Full Text Available OBJETIVOS: identificar os fatores de risco para o Transtorno do Processamento Auditivo (Central TPA(C em 79 pré-escolares. MÉTODOS: aplicou-se um questionário para 79 pais , de crianças que cursavam a pré-escola ou o primeiro ano do ensino fundamental, das redes municipal, estadual e particular de Porto Alegre. O questionário continha questões referentes ao desenvolvimento infantil. RESULTADOS: a pesquisa mostra como principais resultados a ocorrência do uso de chupeta (73,4%; do tempo de aleitamento materno (36%; da realização dos exames audiológicos (17,8%; do tempo em frente a televisão (59%; e da quantidade de repetições de instruções (54%; Em relação aos testes de correlação o estudo mostrou a utilização da chupeta (p=0,006 e maior ocorrência de otites (p=0,007 por meninas. As crianças mais velhas realizavam leitura espontânea (p=0,007 e recontavam histórias ordenadamente (p=0,035. CONCLUSÃO: Identificou-se as variáveis: maior número de irmãos (p=0,005, maior solicitação de repetições (pPURPOSE: to identify the risk factors for (Central Auditory Processing Disorder in a group of 79 preschool children. METHODS: we applied a questionnaire to 79 parents or guardians of children attending preschool or first year of elementary school of the municipal, state and private schools in Porto Alegre. The questionnaire contained questions related to child development. RESULTS: the research shows as the main results the use of a pacifier use (73.4%; the duration of breastfeeding (36%; the conduction of audiological testing (17.8%; the time watching TV (59%; and the number of repetitions of instructions (54%; For the correlation tests the study showed the pacifier use (p=0.006 and the higher incidence of otitis (p=0.007 by girls. Older children performed spontaneous reading (p=0.007 and retold stories neatly (p=0.035. CONCLUSION: the risk factors for (Central Auditory Processing Disorder were identified, being the

  10. Fatigue damage in nuclear power plants: cases study; Endommagement par fatigue dans les centrales nucleaires: illustration par quelques cas rencontres

    Energy Technology Data Exchange (ETDEWEB)

    Goltrant, O.; Thebault, Y. [Electricite de France (EDF/GDL), 93 - Saint-Denis (France). Groupe des Labs; Cipiere, M.F. [FRAMATOME, 92 - Paris-La-Defense (France)

    2001-07-01

    Some fatigue cracks have been detected on nuclear power plants components. Generally they appears under local solicitations not correctly predicted. Two cases are presented in this paper to illustrate the problem: the pitting during mechanical fatigue where the stresses are induced by the pumps vibrations or by fluid flow; the mixing zones of RRA circuit (N4 bearing) where the stresses are induced by the flow of different temperature fluids. The examination allowed the identification of the cracking origin and the development of corrective solutions. (A.L.B.)

  11. 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)

  12. 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.

  13. DAILY MAXIMA PRECIPITATIONS EXPECTED FOR CENTRAL AND SOUTHEAST REGIONS OF THE GOIÁS STATE, BRAZIL PRECIPITAÇÕES MÁXIMAS DIÁRIAS ESPERADAS PARA AS REGIÕES CENTRAL E SUDESTE DE GOIÁS

    Directory of Open Access Journals (Sweden)

    Nori Paulo Griebeler

    2009-03-01

    :Section1;} -->

    Em projetos hidroagrícolas, principalmente aqueles relacionados à acumulação ou condução de água, é fundamental o conhecimento das precipitações esperadas para as diferentes condições. Neste sentido, este trabalho teve por objetivo a determinação da precipitação máxima esperada, para diferentes períodos de retorno (TR, para as regiões central e sudeste do Estado de Goiás. Foram utilizados dados diários de precipitação de 36 estações pluviométricas. Os dados foram obtidos a partir da base de dados da Agência Nacional de Águas (ANA, sendo organizados em planilha eletrônica e tratados com base na metodologia de Kimball, para a determinação do TR. Os resultados indicaram que as diferenças entre os valores extremos de precipitações máximas, para um mesmo TR, ultrapassaram, em 50%, a menor precipitação e que as regiões noroeste e sudeste da área estudada apresentam valores de precipitação esperados maiores, enquanto, nas regiões central e leste, os valores mostraram-se menores. Estes resultados enfatizam a necessidade de adoção de valores locais para o planejamento de obras hidráulicas.

     

    PALAVRAS-CHAVE: Chuva; hidrologia; período de retorno.

  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. 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.)

  16. 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.

  17. Development of the national report of the Mexican United States for the Convention on Nuclear Safety of the IAEA; Desarrollo del informe nacional de los Estados Unidos Mexicanos para la Convencion sobre seguridad nuclear del OIEA

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz L, P. [Jefe del Area de Ingenieria, Departamento de Evaluacion, Gerencia de Seguridad Nuclear, Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)

    2006-07-01

    In this work the content of the National Report of the Mexican United States in it revision 2 is presented, which was presented for it exam by the member countries of the Convention on Nuclear Safety, in April, 2005. The conclusion of this Report, with base in the existent objective evidence, is that the Laguna Verde Central continues maintaining a level of similar safety to that of other nuclear power plants of its type, not existing conditions at the moment that they can be identified as adverse for a sure operation and that, therefore, plans don't exist to advance the closing of this installation, before the end of its useful life. The questions that the member countries formulated to the Report of Mexico, the answers that were provided to these questions, as well as the conclusions of the 3 Exam Meeting of April, 2005 are also included. The next National Report, in it revision 3, it will cover the period from the January 1, 2004 to December 31, 2006, it was developed from January to August, 2007, it delivered to the IAEA on September of the same year and it was presented in the IAEA Headquarters (IAEA) in the 4 Exam Meeting on April, 2008. (Author)

  18. 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

  19. 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)

  20. Confronting fluctuations of conserved charges in central nuclear collisions at the LHC with predictions from Lattice QCD

    Science.gov (United States)

    Braun-Munzinger, P.; Kalweit, A.; Redlich, K.; Stachel, J.

    2016-12-01

    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 √{sNN} = 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 Tc ≃ 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 μB = 0, the comparisons with LHC data are the most direct due to the vanishing baryon transport to midrapidity at these high energies.

  1. Populations genetic analysis of nuclear and mitochondrial loci in skin biopsies collected from central and northeastern North Atlantic humpback whales (Megaptera novaeangliae): population identity and migratory destinations.

    Science.gov (United States)

    Larsen, A H; Sigurjónsson, J; Oien, N; Vikingsson, G; Palsbøll, P

    1996-11-22

    It has been speculated that humpback whales, Megaptera novaeangliae, from the northeastern North Atlantic breed in tropical waters off the coast of West Africa and therefore that they represent a separate breeding population from that which winters in the West Indies. We determined the genotype at six microsatellite loci as well as the sequence of the first 288 nucleotides in the mitochondrial control region of 133 skin biopsies collected from humpback whales in the central North Atlantic (Iceland and Jan Mayen) and the northeastern North Atlantic (Bear Island and the northern coast of Norway). We detected no significant deviations from Hardy-Weinberg proportions nor any differences in genotype frequencies between localities at the nuclear loci. However, the mitochondrial analyses revealed two distinct matrilineal aggregations: the central and the northeastern North Atlantic. Our findings were not compatible with the idea of a separate eastern North Atlantic breeding ground unless one has been established recently. The proposed alternative hypothesis of a common North Atlantic panmictic population (wintering primarily in the West Indies) in which individual whales display maternally directed site-fidelity to specific feeding grounds was supported by re-sightings of two northeastern North Atlantic humpback whales in the West Indies.

  2. 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.

  3. 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)

    S. Nakatsuka

    2013-02-01

    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 broad area in the western and central North Pacific in July, 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 were detected at 94 stations out of 123 stations and 137Cs was detected at all stations. The high 134Cs and 137Cs concentrations more than 10 mBq kg−1 were observed in the area where the northern part of Kuroshio extension at 144° E and 155° E in July 2011, in the area 147° E–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 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 FNPP during study period is suggested from temporal change in the activity ratio of 134Cs/137Cs which was decay corrected at 6 April 2011, and relationships between radioactive Cs and temperature.

  4. Study of indicators aggregation techniques for the selection of a new nuclear reactor for Mexico; Estudio de tecnicas de agregacion de indicadores para la seleccion de un nuevo reactor nuclear para Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Barragan M, A.M.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, 04510 Mexico D.F. (Mexico)]. e-mail: ale_bar_m@yahoo.com.mx

    2007-07-01

    A study on several aggregation techniques that can be used as multi criteria analysis methods, like important part of the methodology developed for the selection of a nuclear reactor for Mexico is described. In an arbitrary way three reactors were selected to be compared, these they are the AP1000 (Advance Passive from 1000 MWe), the PBMR (Pebble Bed Modular Reactor) and the GT-MHR (Gas Turbine Modular Helium). The evaluation approaches were classified in three categories: Economic, Socio-political and of safety and environment. In each category they were defined the more important evaluation indicators and then it was built a matrix with those values of each reactor. The four studied aggregation methods are described: Normalization, Linear deliberation, Fuzzy Logic and AHP (Analytic Hierarchy Process). The well-known aggregation mechanisms are those that are obtained of the lineal deliberation and of the normalization, which have demonstrated to give good results before the simplicity of their use. The fuzzy logic has the advantage that it allows to manage qualitative and quantitative information simultaneously without the aggregation problems that are presented since in a conventional system the semantic pattern on that is based, it is provided by the theory of the diffuse groups that has demonstrated in other areas of the knowledge a better approach to the reality, when admitting that the nature has shades and that the decisions take in function of a wide range of possibilities and of approaches in contradictory occasions or in conflict, all equally worth. The Analytic Hierarchical Process (AHP) that consists in formalizing the intuitive understanding of a multi criteria complex problem, by means of the construction of a hierarchical model that allows the decision agent to structure the problem in visual form, giving him the form of a hierarchy of attributes (global objective of the problem, approaches and alternative). Finally, using the matrix of initiators

  5. Confronting fluctuations of conserved charges in central nuclear collisions at the LHC with predictions from Lattice QCD

    Directory of Open Access Journals (Sweden)

    P. Braun-Munzinger

    2015-07-01

    Full Text Available We construct net baryon number and strangeness susceptibilities as well as correlations between electric charge, strangeness and baryon number from experimental data at midrapidity of the ALICE Collaboration at CERN. The data were taken in central Pb–Pb collisions at sNN=2.76 TeV and cover one unit of rapidity. The resulting fluctuations and correlations are consistent with Lattice QCD results at the chiral crossover pseudocritical temperature Tc≃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. The volume of the fireball for one unit of rapidity at Tc is found to exceed 3000 fm3. A detailed discussion on uncertainties in the temperature and volume of the fireball is presented. The results are linked to pion interferometry measurements and predictions from percolation theory.

  6. Confronting fluctuations of conserved charges in central nuclear collisions at the LHC with predictions from Lattice QCD

    CERN Document Server

    AUTHOR|(CDS)2072944; 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.

  7. 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

  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. 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.

  10. A simple model to evaluate the impact of the thermal power plants emissions; Un modelo simple para evaluar el impacto de las emisiones de centrales termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Rodas Grapain, Arturo; Salcido, Alejandro [Instituto de Investigaciones Electricas, Temixco, Morelos (Mexico)

    2000-07-01

    Formulation and validation of a dispersion model for relative plumes are presented in this paper. This model (MOTTQUIP: Modelo de Transporte Turbulento y Quimico de Plumas) was developed to assess the environmental impact of power generation. The theoretical formulation if this model is based on the integral form of the mass balance equation. MOTTQUIP can simulate (in two dimensions) the turbulent dispersion and chemical transformation phenomena of a nitrogen oxides (Nox) non-buoyant plume in an ozone (O{sub 3}) atmosphere. The results produced by MOTTQUIP, however, can run in a personal computer consuming relatively short CPU times. [Spanish] En este trabajo se presentan la formulacion y la validacion de un modelo (MOTTQUIP: Modelo de Transporte Turbulento y Quimica de Plumas) para evaluar el impacto de las emisiones de contaminantes reactivos de centrales termoelectricas. Este modelo se formula a partir de la forma integral de la ecuacion de balance de masa, y no de su forma diferencial, como se procede generalmente. MOTTQUIP simula, en dos dimensiones, la dispersion turbulenta y transformacion quimica de una pluma no flotante de oxidos de nitrogeno (Nox), misma que se interna paulatinamente en un ambiente de ozono (O{sub 3}). Los resultados obtenidos son comparados con los de modelos alternos que simulan el mismo sistema reactivo, encontrandose una concordancia bastante aceptable. Una ventaja de MOTTQUIP, sin embargo, es que puede utilizarse en sistemas de computo pequenos, empleando tiempos de CPU relativamente cortos.

  11. 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.

  12. Características de uso de plaguicidas químicos y riesgos para la salud en agricultores de la sierra central del Perú

    Directory of Open Access Journals (Sweden)

    Ymelda Montoro

    2009-10-01

    Full Text Available 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 reportados en ambas provincias. Los agricultores no cuentan con ropa de protección y manipulan directamente los plaguicidas durante su preparación y aplicación; asimismo, muchas veces no toman medidas preventivas a pesar de conocer los riesgos relacionados. El comercio de los plaguicidas se ubica en los centros urbanos, cerca de restaurantes y tiendas de abarrotes, además, los plaguicidas más vendidos pertenecen a las categorías extremadamente y altamente peligrosos, tales como Tamaron® y Furadan®, esto representa un peligro para la salud de los agricultores. Los casos de intoxicación por estos productos en las provincias bajo estudio, se han incrementado entre los años 2001 a 2004.

  13. 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...

  14. The Aconcagua River as another barrier to Liolaemus monticola (Sauria: Iguanidae chromosomal races of central Chile El río Aconcagua como otra barrera para las razas cromosómicas de Liolaemus monticola (Sauria: Iguanidae de Chile central

    Directory of Open Access Journals (Sweden)

    MADELEINE LAMBOROT

    2003-03-01

    Full Text Available ABSTRACT Univariate and multivariate statistical analyses of 28 meristic characters recorded for 19 samples of the lizard Liolaemus monticola monticola were used to compare geographical variation in morphology with chromosomal races north and south of the Maipo River, and north and south of the Aconcagua River in central Chile, plus some affluent. This extends a previous morphological study that confirmed that the Maipo River is a biogeographical barrier that separates chromosomal races "Southern, 2n=34" and "Northern, 2n=38-40", and reports for the first time the importance of the Aconcagua River as another biogeographical barrier between the chromosomal races "Northern, 2n=38-40" and the "Multiple Fission, 2n=42-44". The phenetic variation among samples is sufficient to differentiate the three chromosomal races, and also distinguishes populations within the chromosomal races such as the ones separated by the Colorado River, an affluent of the Aconcagua River. A possible historical sequence of events that accounts for the pattern of morphological differentiation is advanced.Se emplearon análisis estadísticos univariados y multivariados de 28 caracteres merísticos de 19 poblaciones de Liolaemus monticola monticola para comparar la variación geográfica morfológica en las razas cromosómicas, tanto al sur y norte del río Maipo, como al sur y norte del río Aconcagua, más algunos afluentes. Este estudio es una extensión de trabajos previos que demuestran que el río Maipo constituye una barrera biogeográfica que separa las razas cromosómicas "Sur, 2n=34" y "Norte, 2n=38-40" y destaca por primera vez la importancia del río Aconcagua como otra barrera geográfica entre las razas cromosómicas "Norte, 2n=38-40" y "Múltiples Fisiones, 2n=42-44". La variación fenética entre las muestras es suficiente para diferenciar las tres razas cromosómicas, y también permite distinguir poblaciones dentro de cada raza, como por ejemplo las que

  15. Diseño de un tambor perforado de mezcla para el proceso de compostaje aerobio realizado en la planta de beneficio de la Central Ganadera de Medellín

    OpenAIRE

    Ossa Vásquez, Karla Andrea

    2008-01-01

    En este trabajo se diseñó y construyó un tambor perforado de mezcla para la optimización del proceso de compostaje aerobio realizado en la Central Ganadera de Medellín. Para el diseño se identificaron previamente las etapas de compostaje de este proceso, mediante mediciones de humedad, densidad y temperatura; se caracterizó cada una de ellas mediante análisis organolépticos, fisicoquímicos, microbiológicos, de tamaño de partícula y fitotóxicos. Además se identificaron los materiales y sist...

  16. Selection of mother wavelets for the detection of the oscillation frequencies in power signals of nuclear reactors; Seleccion de wavelets madres para la deteccion de las frecuencias de oscilacion en senales de potencia de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Amador G, R.; Castillo D, R.; Ortiz V, J. [ININ, Carretera Mexico-Toluca S/N La Marquesa, 52750 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: ramador@nuclear.inin.mx

    2007-07-01

    Diverse types of transitory events can lead to oscillations of power in nuclear reactors. In such events, the power monitors provide a signal that contains important characteristics of the transitory one, as the oscillation frequency, tendencies, changes and the instants or periods in those that important events are presented. This characteristics are detected by means of diverse analysis techniques, as Autoregressive methods, Fourier Transform, Fourier Transform in Short Time, Wavelets Transform, among others. Presently work is used the one Wavelets Continuous Transform because it allows to carry out studies of the stationary, quasi-stationary and transitory signals in the Time-scale and Time-scale-spectrum planes. Contrary to other similar works, this work describes a methodology for the selection of the scales and the Wavelet mother to be applied the one Wavelets Continuous Transform, with the objective of detecting to the dominant frequencies of the system. To prove the proposal a broadly well-known real signal of an event of power oscillations it has been used. The obtained results correspond to three families of Wavelets mothers that fulfilled the conditions of scales and central frequency of the proposal. The results show that the value of the certain frequency oscillation in this work is practically the same one reported in other studies with other techniques. (Author)

  17. Consequences of a {lambda}{sub c}/D enhancement effect on the non-photonic electron nuclear modification factor in central heavy ion collisions at RHIC energy

    Energy Technology Data Exchange (ETDEWEB)

    Martinez-Garcia, G. [SUBATECH, IN2P3/CNRS, Ecole des Mines, Universite de Nantes, Nantes (France)], E-mail: gines.martinez@subatech.in2p3.fr; Gadrat, S. [SUBATECH, IN2P3/CNRS, Ecole des Mines, Universite de Nantes, Nantes (France)], E-mail: sebastien.gadrat@subatech.in2p3.fr; Crochet, P. [Laboratoire de Physique Corpusculaire, IN2P3/CNRS, Universite Blaise Pascal, Clermont-Ferrand (France)], E-mail: philippe.crochet@clermont.in2p3.fr

    2008-05-15

    The RHIC experiments have measured the nuclear modification factor R{sub AA} of non-photonic electrons in Au+Au collisions at {radical}(s{sub NN})=200 GeV. This R{sub AA} exhibits a large suppression for p{sub t}>2 GeV/c which is commonly attributed to heavy-quark energy loss. It is expected that the heavy-quark radiative energy loss is smaller than the light quark one because of the so-called dead-cone effect. An enhancement of the charm baryon yield with respect to the charm meson yield, as it is observed for light and strange hadrons, can explain part of the suppression. This phenomenon has been put forward in a previous work. We present in this Letter a more complete study based on a detailed simulation which includes electrons from charm and bottom decay, charm and bottom quark realistic energy loss as well as a more realistic modeling of the {lambda}{sub c}/D enhancement. We show that a {lambda}{sub c}/D ratio close to unity, as observed for light and strange quarks, could explain 20-25% of the suppression of non-photonic electrons in central Au+Au collisions. This effect remains significant at relatively high non-photonic electron transverse momenta of 8-9 GeV/c.

  18. 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.

  19. 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

  20. UTILIZACIÓN DE TÉCNICAS NUCLEARES PARA ESTIMAR LA EROSIÓN HÍDRICA EN PLANTACIONES DE TABACO EN CUBA

    Directory of Open Access Journals (Sweden)

    Reinaldo H. Gil

    2015-01-01

    Full Text Available La erosión del suelo es un elemento importante en la degradación de tierras, provocando impactos negativos a varios niveles (parcela, finca, cuenca, etc. El cultivo del tabaco en el occidente del país se ha visto negativamente afectado por la erosión hídrica asociado a factores naturales y antrópicos. Un elemento fundamental para implementar una estrategia de manejo sostenible de tierras es la cuantificación de las pérdidas de suelo, ya que permiten establecer políticas de conservación de suelos. Las técnicas nucleares en la evaluación de la erosión, poseen ventajas en comparación con los métodos tradicionales y han sido aplicadas en diferentes agrosistemas a nivel mundial. En la provincia Pinar del Río, los suelos dedicados al cultivo del tabaco, presentan elevados niveles erosivos, por lo que es importante utilizar técnicas que permitan la cuantificación de las tasas de erosión de suelos. El trabajo muestra el uso de la técnica del 137 Cs para caracterizar el estado de la erosión de suelos en dos sectores de una granja con plantaciones de tabaco, ubicadas en la Llanura Suroccidental de la provincia de Pinar del Río. La estrategia de muestreo incorporó la evaluación de transectas seleccionadas en dirección de la pendiente, siendo tomadas muestras de suelos que incluyeron todo el 137 Cs del perfil. Se emplearon varios modelos de conversión; el Modelo de Balance de Masa II proporcionó los mejores resultados, obteniéndose una tasa de redistribución de suelos con valores de -18,28 a 8,15 t ha -1 año -

  1. La posición energética de China en Asia Central ante la pérdida progresiva de influencia de Rusia: consecuencias para los intereses de la UE

    OpenAIRE

    Blanc-Altemir, A. (Antonio)

    2012-01-01

    Durante los últimos años, China está reforzando sus posiciones en Asia Central con el objetivo primordial de diversificar sus fuentes de suministro de hidrocarburos. Tanto el petróleo kazajo, como el gas turkmeno se han constituido como factores muy relevantes para incrementar la seguridad energética china. Esta progresiva presencia de China en Asia Central coincide con una pérdida, también progresiva, de la influencia de Rusia en la región centroasiática. Hasta el momento, la presencia de...

  2. 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.

  3. 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

  4. 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.

  5. Central adiposity in children born small and large for gestational age Adiposidad central en niños que nacieron con poco o con excesivo peso para su edad gestacional

    Directory of Open Access Journals (Sweden)

    M. Biosca

    2011-10-01

    Full Text Available Objective: To evaluate body composition differences between children that were born small (SGA or large for gestational age (LGA compared with their counterparts born adequate for gestational age (AGA. Methods: Body composition was assessed in 124 healthy Caucasian children (50% girls aged 6-10, classified according to their birth weight for gestational age as AGA, SGA and LGA. Fat mass (FM, percentage of FM, lean mass (LM, bone mineral content (BMC and bone mineral density were measured by dual-energy X-ray absorptiometry (DXA in the whole body and at different body regions. Results: LM (adjusted for age and sex and total BMC (adjusted for age, sex and weight were both significantly higher in LGA children and lower in SGA when compared with those born AGA. After adjustments for height, LM and BMC differences between groups were not significant. In SGA children, truncal (P Objetivo: Evaluar las diferencias que existen en la composición corporal de aquellos niños que nacieron pequeños (PEG o grandes para su edad gestacional (GEG en comparación con los que presentaban un peso adecuado al nacer (AEG. Métodos: La composición corporal se valoró en 124 niños caucásicos (50% niñas con edades entre 6 y 10 años, clasificados según su peso al nacer como AEG, PEG y GEG. La masa grasa (MG, el porcentaje de MG, la masa magra (MM, el contenido mineral óseo (CMO y la densidad mineral ósea se midieron mediante absorciometría dual de rayos X (DXA tanto globalmente como en las diferentes regiones corporales. Resultados: La MM (ajustada por edad y sexo y el CMO (ajustado por edad, sexo y peso fueron mayores en los GEG y menores en los PEG al compararlos con los AEG; al ajustar la MM el CMO por la altura, dichas diferencias ya no fueron significativas. En los PEG, la grasa abdominal (p < 0,01 y en el tronco (p < 0,05 eran mayores que en los AEG y que en los GEG tras ajustar por edad, sexo y altura. No existían diferencias en el porcentaje de MG

  6. 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.

  7. 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.

  8. Cesium-134 and 137 activities in the central North Pacific Ocean after the Fukushima Dai-ichi Nuclear Power Plant accident

    Science.gov (United States)

    Kameník, J.; Dulaiova, H.; Buesseler, K. O.; Pike, S. M.; Št'astná, K.

    2013-09-01

    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.

  9. 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)

  10. 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

  11. The CEIDEN technology platform. A collaborative effort to promote nuclear R and D in Spain; La Plataforma Tecnologica Ceiden. Un esfuerzo colaborativo para promover la I+D nuclear en Espana

    Energy Technology Data Exchange (ETDEWEB)

    Carmena Servet, P.

    2012-11-01

    The Spanish fission nuclear energy research and development Technological Platform, CEIDEN, is an entity aimed to coordinate the R and D needs and efforts related to fission nuclear technology in all the Spanish nuclear sector. Its activities are aimed to propose and develop joint projects by the partners that have to deal with similar problems and to present a single national position related to international proposals and compromises. All the Sectors related to the Spanish nuclear R and D are represented in the CEIDEN Technological Platform, that is involved both in plants in operation and future reactor designs. (Author)

  12. 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

  13. Em nome da autonomia e do desenvolvimento: Brasil e a não-proliferação, o desarmamento e os usos pacíficos da energia nuclear

    Directory of Open Access Journals (Sweden)

    Diego Santos Vieira de Jesus

    2012-01-01

    Full Text Available O objetivo é examinar as posições defendidas pelo Brasil quanto à não-proliferação, ao desarmamento e aos usos pacíficos da energia nuclear neste início de século. O argumento central aponta que o Brasil almeja pressionar os Estados nuclearmente armados para que cumpram suas obrigações de desarmamento, enquanto procura preservar a autonomia para desenvolver atividades nucleares pacíficas.   The objective is to examine the positions adopted by Brazil on nuclear non-proliferation, disarmament and peaceful uses of nuclear energy in the beginning of this century. The central argument indicates that Brazil aims to pressure the nuclear-weapon states to fulfill their disarmament obligations, while seeks to preserve autonomy to develop peaceful nuclear activities.

  14. 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)

  15. 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

  16. 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)

  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. 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

    Abstract Our review recognizes 15 species of the integripennis species group of Geocharidius from Nuclear Central America, include three species previously described (Geocharidius gimlii Erwin, Geocharidius integripennis (Bates) and Geocharidius zullinii Vigna Taglianti) and 12 described here as new. They are: Geocharidius andersoni sp. n. (type locality: Chiapas, Chiapas Highlands, Cerro Huitepec) and Geocharidius vignatagliantii sp. n. (type locality: Chiapas, Motozintla, Sierra Madre de Chiapas, Benito Juárez) from Mexico; Geocharidius antigua sp. n. (type locality: Sacatepéquez, 5 km SE of Antigua), Geocharidius balini sp. n. (type locality: Suchitepéquez, 4 km S of Volcan Atitlán), Geocharidius erwini sp. n. (type locality: Quiché Department, 7 km NE of Los Encuentros), Geocharidius jalapensis sp. n. (type locality: Jalapa Department, 4 km E of Mataquescuintla), Geocharidius longinoi, sp. n. (type locality: El Progreso Department, Cerro Pinalón), and Geocharidius minimus sp. n. (type locality: Sacatepéquez Department, 5 km SE of Antigua) from Guatemala; and Geocharidius celaquensis sp. n. (type locality: Lempira Department, Celaque National Park), Geocharidius comayaguanus sp. n. (type locality: Comayagua Department, 18 km ENE of Comayagua), Geocharidius disjunctus sp. n. (type locality: Francisco Morazán, La Tigra National Park), and Geocharidius 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

  19. The integripennis species group of Geocharidius Jeannel, 1963 (Carabidae, Bembidiini, Anillina from Nuclear Central America: a taxonomic review with notes about biogeography and speciation

    Directory of Open Access Journals (Sweden)

    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

  20. 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!.

  1. Perspective about the US license Renewal for NNPP's; Perspectiva sobre la renovacion de licencia para centrales nucleares en los Estados Unidos

    Energy Technology Data Exchange (ETDEWEB)

    Lehnert, D. F.

    2004-07-01

    This article provides and overview of the US License Renewal Rule, 10 CFR 54, and its implementation in the US leading to the preparation and review of a license renewal application. The key regulatory documents and the industry's methodology and guidance for successfully implementing the Rule are discussed. While the process still undergoes change and optimization, it has become predictable and reliable, such that utilities can establish realistic schedules and budgets to complete the license renewal process. Nearly 60% of the US operating units have either received and extended operating license, have submitted their application for review, or have committed to submit an application in the next few years. The article concludes with a discussion of lessons learned from this wealth of experience and some emerging issues that may affect license renewal process. (Author)

  2. 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).

  3. Sistema de medición, control y compensación activa para ciclado de campo magnético en aplicaciones de resonancia magnética nuclear

    OpenAIRE

    Forte, Guillermo Omar

    2013-01-01

    Tesis (DCI)--FCEFN-UNC, 2013 Analiza aspectos de la instrumentación asociada a la técnica de Resonancia Magnética Nuclear (RMN) con Ciclado Rápido de Campo Magnético (FFC, por sus siglas en inglés), los que afectan directamente la calidad de las mediciones realizadas. Se implementó un método para la corrección estática de la dependencia espacial del campo magnético generado por el electroimán principal del sistema, dentro de un volúmen determinado.

  4. 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.

  5. 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)

  6. 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)

  7. central t

    Directory of Open Access Journals (Sweden)

    Manuel R. Piña Monarrez

    2007-01-01

    Full Text Available Dado que la Regresión Ridge (RR, es una estimación sesgada que parte de la solución de la regresión de Mínimos Cuadrados (MC, es vital establecer las condiciones para las que la distribución central t de Student que se utiliza en la prueba de hipótesis en MC, sea también aplicable a la regresión RR. La prueba de este importante resultado se presenta en este artículo.

  8. Aprovechamiento del río pita en la provincia de bolívar para la construcción de una central hidroeléctrica (proyecto caluma bajo)

    OpenAIRE

    Benites, Manuel; Jimenez, Antonio; Saavedra, Juan; Ochoa, Jimmy

    2009-01-01

    El desarrollo de este tópico básicamente se refiere a la actualización de los Estudios realizados por el antiguo INECEL para la construcción de una Central Hidroeléctrica sobre el Río Pita. Todos los Datos referentes a hidrología se han obtenido haciendo una correlación de caudales entre estaciones Hidrométricas cercanas, mientras que lo que se refiere a presupuesto, los costos han sido actualizados utilizando los costos que posee el Consejo Provincial del Guayas. Mediante el uso de un simula...

  9. Aplicación del formato Dublin Core para la descripción de los recursos en la biblioteca virtual del CDICT- Universidad Central de Las Villas (Cuba)

    OpenAIRE

    Lic. Ramón A. Manso Rodríguez; Lic. Marilyn Lorenzo Rodríguez; Tec. María C. Vázquez

    2002-01-01

    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 ut...

  10. Modelo económico para el aprovechamiento de los residuos organicos de mango y banano generados en la Central Mayorista de Antioquia

    OpenAIRE

    Ramírez Vergara, Jaime de Jesús; Mejía Echeverry, Astrid Elena

    2013-01-01

    Tesis (Maestría en Desarrollo Sostenible y Medio Ambiente). Universidad de Manizales. Facultad de Ciencias Contables, Económicas y Administrativas, 2013 Este trabajo presenta un modelo que permite simular el impacto de las alternativas de aprovechamiento de los residuos orgánicos de dos frutas, banano y mango , en la Central Mayorista de Antioquia, en el municipio de Itagüí Antioquia, Colombia Los Maestrantes que presentan la tesis y la Central Mayorista de Antioquia

  11. 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)

  12. 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

  13. Estudo comparativo de detectores de HPGe, NaI(TI), CdZnTe para aplicações em segurança e para resposta a ameaças nucleares e radiológicas

    OpenAIRE

    Marques, Luís Miguel Cabeça

    2011-01-01

    Tese de mestrado em Engenharia Física, apresentada à Universidade de Lisboa, através da Faculdade de Ciências, 2011 Após ataques terroristas recentes, aumentou a preocupação internacional sobre as ameaças de índole nuclear e radiológica (NR), associadas ao tráfico ilícito não apenas de materiais nucleares e à sua possível aplicação em engenhos nucleares improvisados, mas também de outros materiais radioactivos (utilizados em aplicações na indústria, medicina e investigação) de possível apl...

  14. 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)

  15. Nuevo registro de Gomphotherium hondurensis (Frick, 1933 (Proboscidea, Gomphoteriidae para el Mioceno Superior de El Salvador, América Central A new record of Gomphotherium hondurensis (Frick, 1933 (Proboscidea, Gomphoteriidae on the Upper Miocene of El Salvador, Central America

    Directory of Open Access Journals (Sweden)

    Daniel H. Aguilar

    2011-12-01

    Full Text Available Se describe un molar inferior, aislado, del proboscídeo endémico de América Central Gomphotherium hondurensis (Frick, 1933, recuperado en el valle del río Torola en la localidad fosilífera de Corinto, la cual fue estudiada y caracterizada en los años 70 por los paleontólogos estadounidenses David S. Webb y Stephen Perrigo; la fauna local de Corinto es considerada una de las más importantes localidades fosilíferas del Mioceno Superior de América Central.An isolated lower molar of the endemic Central America Proboscidea Gomphotherium hondurensis (Frick, 1933, recovered at the Valley of Torola River is described here. This locality corresponds with the outcrops of the Corinto local fauna, previously studied and defined by the American paleontologists David S. Webb and Stephen Perrigo during the 70’s years; which is considered as one of the most important fossiliferous localities of the Upper Miocene of Central America

  16. 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)

  17. Aplicación de la teoría de perturbación método diferencial al estudio de sensibilidad en generadores de vapor de centrales nucleares tipo PWR

    OpenAIRE

    Giol, Roberto

    1989-01-01

    En este trabajo se presenta una ampliación del formalismo diferencial de la teoría de perturbación a un modelo homogéneo de simulación del comportamiento estacionario de generadores de vapor de centrales nucleares PWR. El programa PERGEVAP, desarrollado a partir del modelo del código GEVAP de Souza, permite realizar cálculos de la sensibilidad de funciones lineales (como la temperatura media del primario) y no-lineales (como el flujo de calor medio) a variaciones en los parámetros termohidráu...

  18. 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)

  19. Gamma spectroscopy with LaBr{sub 3} and Lyso for its application in nuclear medicine; Espectroscopia gamma con LaBr{sub 3} y LYSO para su aplicacion en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez V, M.; Murrieta, T.; Martinez D, A. [UNAM, Instituto de Fisica, Apdo. Postal 20-364, 01000 Mexico D. F. (Mexico); Alva S, H., E-mail: mercedes@fisica.unam.m [UNAM, Facultad de Medicina, Unidad PET/CT-Ciclotron, Edificio de Investigacion P. B., Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2011-07-01

    Image formation in nuclear medicine is based on the detection of radiation emitted from a small quantity of a radiopharmaceutical administered to patients. This requires high detection efficiency, good spatial resolution and the ability to identify the energy of the incident radiation. These and other properties of detector materials for gamma radiation are reviewed. Standard detector calibration and characterization procedures are described, and the results from gamma spectroscopy measurements for sodium iodide (NaI:Tl), conventional scintillator widely used in nuclear medicine applications, and two other novel scintillation crystals, lanthanum bromide (LaBr{sub 3}) and lutetium-yttrium oxy orthosilicate (Lyso) are presented. Both materials showed a linear energy response from 80 to 1332 KeV, and within this energy interval, LaBr{sub 3} had a superior energy resolution compared to Lyso and NaI:Tl. These and other new materials are expected to replace those used in current detectors for nuclear medicine scanners. (Author)

  20. 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)

  1. 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)

  2. Heat treatments in a conventional steel to reproduce the microstructure of a nuclear grade steel; Tratamientos termicos en un acero convencional para reproducir la microestructura de un acero grado nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Rosalio G, M.

    2014-07-01

    The ferritic steels used in the manufacture of pressurized vessels of Boiling Water Reactors (BWR) suffer degradation in their mechanical properties due to damage caused by the neutron fluxes of high energy bigger to a Mega electron volt (E> 1 MeV) generated in the reactor core. The materials with which the pressurized vessels of nuclear reactors cooled by light water are built correspond to low alloy ferritic steels. The effect of neutron irradiation on these steels is manifested as an increase in hardness, mechanical strength, with the consequent decrease in ductility, fracture toughness and an increase in temperature of ductile-brittle transition. The life of a BWR is 40 years, its design must be considered sufficient margin of safety because pressure forces experienced during operation, maintenance and testing of postulated accident conditions. It is necessary that under these conditions the vessel to behave ductile and likely to propagate a fracture is minimized. The vessels of light water nuclear reactors have a bainite microstructure. Specifically, the reactor vessels of the nuclear power plant of Laguna Verde (Veracruz, Mexico) are made of a steel Astm A-533, Grade B Class 1. At present they are carrying out some welding tests for the construction of a model of a BWR, however, to use nuclear grade steel such as Astm A-533 to carry out some of the welding tests, is very expensive; perform these in a conventional material provides basic information. Although the microstructure present in the conventional material does not correspond exactly to the degree of nuclear material, it can take of reference. Therefore, it is proposed to conduct a pilot study to establish the thermal treatment that reproduces the microstructure of nuclear grade steel, in conventional steel. The resulting properties of the conventional steel samples will be compared to a JRQ steel, that is a steel Astm A-533, Grade B Class 1, provided by IAEA. (Author)

  3. Influence of communication systems to support the services in nuclear power plants; Influencia de los sistemas de comunicaciones en el apoyo a los servicios prestados a las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Moron, P.; Ruiz, J. C.; Guerra, F. J.

    2005-07-01

    The continuous technological advances related to communications infrastructures and mobility solutions, increasingly within reach of the companies, are leading to upgrade most of the associated processes within a service company. Tecnatom is not irrelevant to it and is carrying out a technological development for the intercommunication between its facilities, and the spanish nuclear power plants. Consequently is carrying out and adjustment and optimization of their services. All the performances are included in a corporate project to three years named ARCOM. Along 2004 the first results have been obtained, remote analysis of data has been made and the access to the management information systems from the nuclear power stations has been facilitated. (Author)

  4. How the organization and human factors positively impact the contractors of nuclear power plants; Como la organizacion y los factores humanos repercuten positivamente en las empresas contratistas de las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Arnaldos, A.; Shannon, M.; Walter, J.; Mendoza, J.

    2012-11-01

    It is recognised that organisations that pay attention to creating a robust nuclear safety culture are likely to be a lower risk than those who do not. the same concept can be applied to contractors. In this article we will focus on the implementation of safety culture and programs to reduce human error in nuclear sector contractors and, on how these programs have a beneficial impact to achieve the safety goals, not only for the company, but for the client who owns the work site. (Author)

  5. 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

  6. 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.

  7. Validade e precisão do Questionário de Relacionamento Central 6.0 (CRQ 6.0 para adultos com hepatite C crônica

    Directory of Open Access Journals (Sweden)

    Gustavo Risso

    2010-08-01

    Full Text Available Portadores de hepatite C têm grande probabilidade de apresentar sintomas psicopatológicos e conflitos no relacionamento amoroso. Objetivou-se medir a precisão (consistência interna e a validade (convergente e discriminante do Questionário de Relacionamento Central 6.0 - CRQ 6.0, para adultos com hepatite C crônica. O CRQ 6.0, de autorrelato, avalia o padrão de relacionamento do indivíduo, segundo três componentes: Desejos (D, Respostas do Outro (RO, Respostas do Eu (RE. Participaram do estudo pacientes ambulatoriais com hepatite C crônica (G1, n = 61 e acompanhantes de pacientes (G2, n= 40. Todos responderam ao CRQ 6.0 e à Escala de Avaliação de Sintomas-40 (EAS-40. Os resultados indicaram consistência interna aceitável para os componentes do CRQ 6.0. Eles se correlacionaram significantemente com sintomas psicopatológicos pela EAS-40. Os escores do CRQ 6.0 foram significantemente mais elevados para participantes de G1, quando comparados aos de G2 (RO e RE, participantes sob medicação (RE e mulheres (D e RE.

  8. REDES EMPRESARIALES EN EL SECTOR TURISMO Y SERVICIOS PARA LA MEJORA DE COMPETITIVIDAD EN CIUDAD JUÁREZ, CHIHUAHUA, MÉXICO: CASO PARQUE CENTRAL HERMANOS ESCOBAR Y PYMES ALEDAÑAS

    Directory of Open Access Journals (Sweden)

    Jesús Alberto Urrutia de la Garza

    2016-01-01

    Full Text Available La presente investigación, muestra la cooperación y relación que existe entre las pequeñas y medianas empresas (Pymes del sector turismo y servicios circunvecinos al Parque Central Hermanos Escobar (PCHE en Ciudad Juárez, Chihuahua (CJS, y su colaboración con este último. Se destacan las relaciones derivadas entre empresas y actores de la zona bajo el marco de la competitividad. En los resultados se presenta la red informal existente, así como la red que se generaría si estas empresas trabajaran bajo condiciones de cooperación, coordinación e intercambio de información y clientes entre los actores involucrados. También, se destaca la iniciativa empresarial para la creación de una red que formalice las relaciones, pero una falta de liderazgo para dirigirla, así como un distanciamiento con el gobierno. Sin embargo, se perciben oportunidades para potenciar las capacidades de aprendizaje e innovación, la reproducción de iniciativas empresariales exitosas y la conformación de redes.

  9. Electric failure on the reactor n.3 of the nuclear power plant of Dampierre; Defaillance electrique sur le reacteur n. 3 de la centrale nucleaire de Dampierre

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-05-15

    This note of information resumes the progress of the electric failure on the reactor n.3 of the nuclear power plant of Dampierre, the organization during the incident, it establishes then a comparison with the incident arisen to Forsmark in 2006 and reminds that it lead in an inspection on behalf of the Asn which noticed that all the procedures had been respected by the operators and did not noticed any abnormality in the maintenance. This event was classified at the level 1 of the international nuclear event scale (INES). (N.C.)

  10. Revival of nuclear power engineering in the Central-Eastern Europe in response to rising power demand and the problem of CO2 emission

    Energy Technology Data Exchange (ETDEWEB)

    Rozkosz, Grazyna; Kaszowski, Bartosz

    2010-09-15

    Safety and reliability of electric power supply is guarantee for stable development. Necessity of decommissioning of largely depreciated power plants and rising power demands (average ca. 3% per year) may cause energy deficit in CE Europe. Decision on construction new power plants is determined mainly by power energy generation costs. Nuclear power generation cost forecast is significantly lower than cost of energy from fossil fuels. Such factors offer a new view on source of ''clean and safe'' nuclear energy.

  11. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  12. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs.

  13. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-15

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  14. 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.

  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. 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.

  17. 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)

  18. Nuclear power history calculation for subcritical systems using Euler-MacLaurin formula; Calculo do historico de potencia nuclear para sistemas subcriticos utilizando a formula de Euler-MacLaurin

    Energy Technology Data Exchange (ETDEWEB)

    Henrice Junior, Edson; Goncalves, Alessandro da Cruz, E-mail: ejunior@nuclear.ufrj.br, E-mail: alessandro@nuclear.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Departamento de Engenharia Nuclear; Palma, Daniel Arthur Pinheiro, E-mail: dapalma@cnen.gov.br [Comissao Nacional de Energia Nucleara (CNEN), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    This paper presents an efficient method for calculating the reactivity using inverse point kinetic equation for subcritical systems by applying the Euler-MacLaurin summation formula to calculate the nuclear power history. In accordance with the accuracy of the numerical results, this method does not require a large number of points for calculation, providing accurate results with low computational cost. (author)

  19. The Aconcagua River as another barrier to Liolaemus monticola (Sauria: Iguanidae) chromosomal races of central Chile El río Aconcagua como otra barrera para las razas cromosómicas de Liolaemus monticola (Sauria: Iguanidae) de Chile central

    OpenAIRE

    MADELEINE LAMBOROT; LAFAYETTE EATON; BASILIO A CARRASCO

    2003-01-01

    ABSTRACT Univariate and multivariate statistical analyses of 28 meristic characters recorded for 19 samples of the lizard Liolaemus monticola monticola were used to compare geographical variation in morphology with chromosomal races north and south of the Maipo River, and north and south of the Aconcagua River in central Chile, plus some affluent. This extends a previous morphological study that confirmed that the Maipo River is a biogeographical barrier that separates chromosomal races "Sout...

  20. A geographic information system and multi criteria analysis method for site selection of spent nuclear fuel disposal; Metodologia baseada em sistemas de informacao geografica e analise multicriterio para a selecao de areas para a construcao de um repositorio para o combustivel nuclear usado

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Vivian Borges

    2009-07-01

    This thesis aims to develop a site selection methodology for the construction of final repository for the spent nuclear fuel disposal, by using geographic information systems (GIS) and multi-criteria decision analysis. Decision making processes of this kind are often complex, given the great number of space parameters to consider and also the typically conflicting opinions of the diverse stake holders. By using GIS, data from different space parameters can be quickly and reliably stored, treated and analyzed. Multi-criteria techniques allow for the incorporation of different stake holders' opinions. These tools, when jointly used, allow for the decision process to be more transparent, quick and reliable. The method developed was applied to the particular case of the state of Rio de Janeiro. Weights obtained from an expert panel and also by using the Hierarchical Analysis Method and cartographic data were combined in the GIS. The application showed that it is possible not only to select and classify areas as to their aptness for the proposed objective, but also to exclude those clearly inadequate areas, thus optimizing the selection process by reducing the search space and consequently minimizing costs and the time spent in the search. (author)

  1. Super-resolution imaging visualizes the eightfold symmetry of gp210 proteins around the nuclear pore complex and resolves the central channel with nanometer resolution

    NARCIS (Netherlands)

    Löschberger, A.; Van de Linde, S.; Debauvalle, M.C.; Rieger, B.; Heilemann, M.; Krohne, G.; Sauer, M.

    2012-01-01

    One of the most complex molecular machines of cells is the nuclear pore complex (NPC), which controls all trafficking of molecules in and out of the nucleus. Because of their importance for cellular processes such as gene expression and cytoskeleton organization, the structure of NPCs has been studi

  2. 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)

  3. Obtenção de microesferas de (U,ThO2 para o combustível do reator nuclear de alta temperatura

    Directory of Open Access Journals (Sweden)

    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.

  4. 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)

  5. 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.

  6. 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)

  7. Líneas generales para el entendimiento de las centrales de compra. Una experiencia desde el mercado de las medias femeninas

    OpenAIRE

    Bedoya, Laura; Carrillo, Carlos; Martínez,Carolina; Molina, Nathali

    2013-01-01

    A través de una investigación en torno al proceso de venta a grandes superficies desarrollado por una empresa de ropa interior femenina, este artículo presenta, de manera general, el funcionamiento de una central de compras en Colombia. Se abordan aspectos como el proceso de codificación, las condiciones de la negociación, los términos de pago, los procesos de selección, entre otros.

  8. La cocina de Pozuzo como eje central de una ruta gastronómica para su desarrollo turístico

    OpenAIRE

    Morcia Rivera, Frida Lina

    2013-01-01

    En la provincia de Oxapampa, departamento de Pasco, está ubicado el distrito llamado Pozuzo, cuyos pobladores de origen austro-alemán han hecho de este lugar una interesante propuesta para disfrutar de una cultura suspendida en el tiempo —donde la tradición se ha mantenido a través de más de un siglo— y de un turismo no convencional muy especial vinculado directamente a la naturaleza en la cual, aprovechando las tendencias actuales, sería posible el desarrollo de otras modalidades de turismo ...

  9. LA PARTICIPACIÓN SOCIAL COMO ESTRATEGIA CENTRAL DE LA NUTRICIÓN COMUNITARIA PARA AFRONTAR LOS RETOS ASOCIADOS A LA TRANSICIÓN NUTRICIONAL

    OpenAIRE

    José Carlos Suárez-Herrera; José Joaquín O´Shanahan Juan; Lluis Serra-Majem

    2009-01-01

    Las sociedades modernas vienen experimentando en las últimas décadas un proceso de transición nutricional acelerada que favorece la aparición, a escala planetaria, de problemas nutricionales de naturaleza contradictoria, tales como la obesidad y la desnutrición. Estos problemas suponen un auténtico desafío para los responsables de la Salud Pública, que adoptan gradualmente una serie de estrategias bajo una perspectiva poblacional. Sin embargo, la naturaleza colectiva de estas estrategias pued...

  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. 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

  12. 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

  13. 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)

  14. 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)

  15. 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

  16. Cluster Formation during Expansion of Hot and Compressed Nuclear Matter Produced in Central Collisions of Au on Au at 250 A MeV

    Science.gov (United States)

    Petrovici, M.; Herrmann, N.; Legrand, I.; Gobbi, A.; Hildenbrand, K. D.; Reisdorf, W.; Buta, A.; Freifelder, R.; Jeong, S. C.; Krämer, M.; Moisa, D.; Schüll, D.; Simion, V.; Sodan, U.; Teh, K.; Wessels, J. P.; Wienold, T.; Alard, J. P.; Amouroux, V.; Basrak, Z.; Bastid, N.; Belyaev, I. M.; Berger, L.; Blaich, Th.; Boussange, S.; Čaplar, R.; Cerruti, C.; Cindro, N.; Coffin, J. P.; Donà, R.; Dupieux, P.; Erö, J.; Fintz, P.; Fodor, Z.; Fraysse, L.; Guillaume, G.; Hölbling, S.; Houari, A.; Jundt, F.; Kecskemeti, J.; Koncz, P.; Korchagin, Y.; Kotte, R.; Kuhn, C.; Ibnouzahir, M.; Lebedev, A.; Maguire, C.; Manko, V.; Mösner, J.; Montarou, G.; Montbel, I.; Morel, P.; Neubert, W.; Pelte, D.; Rami, F.; Ramillien, V.; Sadchikov, A.; Seres, Z.; Sikora, B.; Smolyankin, S.; Tezkratt, R.; Trzaska, M.; Vasiliev, M. A.; Wagner, P.; Wilhelmi, Z.; Wohlfarth, D.; Zhilin, A. V.

    1995-06-01

    Complete distributions of the light and intermediate mass fragments ( Z = 1-6) produced within the polar angular range 1∘<=Θlab<=30∘ in highly central collisions of 250 A MeV Au + Au are presented. The results of this measurement and a model analysis are used to study the expansion and clustering of the hot and compressed transient state formed in central collisions of such a heavy system. The influence of the initial conditions on the final observables is discussed.

  17. Cluster formation during expansion of hot and compressed nuclear matter produced in central collisions of Au on Au at 250{ital A} MeV

    Energy Technology Data Exchange (ETDEWEB)

    Petrovici, M.; Herrmann, N.; Legrand, I.; Gobbi, A.; Hildenbrand, K.D.; Reisdorf, W.; Buta, A.; Freifelder, R.; Jeong, S.C.; Kraemer, M.; Moisa, D.; Schuell, D.; Simion, V.; Sodan, U.; Teh, K.; Wessels, J.P.; Wienold, T.; Alard, J.P.; Amouroux, V.; Basrak, Z.; Bastid, N.; Belyaev, I.M.; Berger, L.; Blaich, T.; Boussange, S.; Caplar, R.; Cerruti, C.; Cindro, N.; Coffin, J.P.; Dona, R.; Dupieux, P.; Eroe, J.; Fintz, P.; Fodor, Z.; Fraysse, L.; Guillaume, G.; Hoelbling, S.; Houari, A.; Jundt, F.; Kecskemeti, J.; Koncz, P.; Korchagin, Y.; Kotte, R.; Kuhn, C.; Ibnouzahir, M.; Lebedev, A.; Maguire, C.; Manko, V.; Moesner, J.; Montarou, G.; Montbel, I.; Morel, P.; Neubert, W.; Pelte, D.; Rami, F.; Ramillien, V.; Sadchikov, A.; Seres, Z.; Sikora, B.; Smolyankin, S.; Tezkratt, R.; Trzaska, M.; Vasiliev, M.A.; Wagner, P.; Wilhelmi, Z.; Wohlfarth, D.; Zhilin, A.V. [Gesellschaft fuer Schwerionenforschung, Darmstadt (Germany)]|[Institute for Physics and Nuclear Engineering, Bucharest (Romania)]|[Central Research Institute for Physics, Budapest (Hungary)]|[Laboratoire de Physique Corpusculaire/IN2P3-CNRS/Universite Blaise Pascal, Clermont-Ferrand (France)]|[Physikalisches Institut der Universitaet Heidelberg, Heidelberg (Germany)]|[Universitaet Mainz, Mainz (Germany)]|[Institute for Theoretical and Experimental Physics, Moscow (Russian Federation)]|[Kurchatov Institute for Atomic Energy, Moscow (Russian Federation)]|[Forschungszentrum Rossendorf, Rossendorf (Germany)]|[Centre de Recherches Nucleaires/Universite Louis Pasteur, Strasbourg (France)]|[Institute of Experimental Physics, University of Warsaw, Warsaw (Poland)]|[Rudjer Boskovic Institute, Zagreb (Croatia)]|[Laboratori Nationali di Legnaro, Legnaro (Italy); (FOPI Collaboration)

    1995-06-19

    Complete distributions of the light and intermediate mass fragments ({ital Z}=1--6) produced within the polar angular range 1{sup {circ}}{le}{Theta}{sub lab}{le}30{sup {circ}} in highly central collisions of 250{ital A} MeV Au+Au are presented. The results of this measurement and a model analysis are used to study the expansion and clustering of the hot and compressed transient state formed in central collisions of such a heavy system. The influence of the initial conditions on the final observables is discussed.

  18. Quality Assurance in the Vandellos 1 Nuclear Power Plant Dismantling and Decommissioning Project; La garantia de calidad en el proyecto de desmantelamiento y clausura de la Central Nuclear de Vandellos I

    Energy Technology Data Exchange (ETDEWEB)

    Soto Lanuza, A.

    2000-07-01

    General description of the Quality Assurance System established and implemented for the efficient development of the current activities specified in the Dismantling and Decommissioning Plan for Vandellos I Nuclear Power Plant. Aspects related to the Quality organization, scope and applicability on the established Quality Assurance Manual, availability of requirements and recommendations on quality as well as actions to be taken for the correct verification on the quality and practical application of the Manual should be described. (Author)

  19. CAGE: A standard design application to nuclear power plants of Cofrentes, Almaraz and Trillo; CAGE: Un diseno estandar de aplicacion a las centrales nucleares de Cofrentes, Almaraz y Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Cubian Martinez, B.; Gomez Gomez, M.; Zornoza Garcia-Andrade, J.; Turrion Lopez, F.; Barrio, M. A. del; Cobos Perabad, A.; Garcia-Serrano, J. L.

    2016-08-01

    Design, engineering, supply, construction, assembly, supervision and quality control, construction management and commissioning of Alternative Emergency Management Centres (CAGES) of nuclear power plants Cofrentes (CNC), Almaraz (CNA) and Trillo (CNT) were awarded in the first half of 2014 to Iberdrola Engineering and Construction (IIC). After obtaining the required building permits issued by municipalities, following the delivery of the corresponding, basic project and execution, in January 2015, began civil works at CNA, CNT and in February of this year in CNC. (Author)

  20. Assessment of occupational radiation protection conditions during power enhancement of the Angra-2 nuclear power plant; Avaliacao das condicoes de radioprotecao ocupacional durante a elevacao de potencia na Unidade 2 da Central Nuclear Almirante Alvaro Alberto - Angra-2

    Energy Technology Data Exchange (ETDEWEB)

    Azevedo, Eduardo M.; Rocha, Antonio Carlos S.; Ferreira, Paulo R.R.; Mouco, Charles Dickens C.L.; Godoy, Jose M.O.; Matta, Luiz E.S.C. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    2001-07-01

    This paper intend to analyse the occupational radioprotection conditions of the Angra-2 nuclear power plant, from the startup up to reach 100% of the nominal power. To perform this work a group of dose rates measures was made including beta/gamma and neutron radiation, particulates and iodine monitoring, and surface contamination, during the whole process. These measures were made inside of the three main buildings: the reactor buildings (UJA - reactor core and UJB) and the Reactor Auxiliary Building (UKA). (author)

  1. New technologies of information treatment in the ERP of the Almaraz and Trillo nuclear power plants; Nuevas tecnologias de tratamiento de la informacion en el ERP de las centrales nucleares de Almaraz y Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Martin Lopez-Suevos, C.; Gonzalez Crego, E.

    2013-03-01

    The Almaraz and Trillo Nuclear Power Plants are equipped with an Integrated Operation Management System (SIGE), which covers practically all of their transactional and management needs in all areas, with the exception of some specific engineering and simulation tools. In recent years, applications based on new computer technologies have been developed and integrated into the SIGE, including a Maintenance Dashboard, an Admissions Office ant the use of bar code readers, all of which are described in this article. (Author)

  2. A model of objects based on KKS for the processing of alarms at the Angra 2 nuclear power plant; Um modelo de objetos baseado em KKS para o processamento de alarmes da usina nuclear de Angra 2

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Paulo Adriano da

    2000-03-01

    The purpose of this work is to present a new model of the alarm annunciation system of the Angra 2 nuclear power plant, using concepts of object based modeling and having as basic the Angra 2 Systems and Components Identification System - KKS. The present structure of the Computerized Alarm System - CAS of Angra 2 does not permit a fast visualization of the incoming alarms in case that a great number of them go off, because the monitors can only show 7 indications at a time. The herein proposed model permits a fast identification of the generated alarms, making possible for the operator to have a general view of the current nuclear power plant status. Its managing tree structure has an hierarchical dependence among its nodes, from where, the presently activated alarms are shown. Its man-machine interface is easy interaction and understand because it is based on structure well known by the Angra 2 operators which is the Angra 2 Systems and Components Identification System - KKS. The project was implemented in the format of an Angra 2 Alarms Supervision System (SSAA), and, for purpose of simulation, 5 system of the Angra 2 Nuclear Power Plant have been chosen. The data used in the project like measurement KKS, measurement limits, unity, setpoints, alarms text and systems flow diagrams, are actual data of the Angra 2 Nuclear Power Plant. The Visual Basic programming Language has been used, with emphasis to the object oriented programming, which and modification, without modifying the program code. Event hough using the Visual Basic for programming, the model has shown, for its purpose, a satisfactory real time execution. (author)

  3. Study of a brazilian cask and its installation for PWR spent nuclear fuel dry storage; Estudo de um casco nacional e sua instalacao para armazenagem seca de combustivel nuclear queimado gerado em reatores PWR

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, Luiz Sergio

    2009-07-01

    Spent nuclear fuel (SNF) is removed from the nuclear reactor after the depletion on efficiency in generating energy. After the withdrawal from the reactor core, the SNF is temporarily stored in pools at the same site of the reactor. At this time, the generated heat and the short and medium lived radioactive elements decay to levels that allow removing SNF from the pool and sending it to temporary dry storage. In that phase, the fuel needs to be safely and efficiently stored, and then, it can be retrieved in a future, or can be disposed as radioactive waste. The amount of spent fuel increases annually and, in the next years, will still increase more, because of the construction of new nuclear plants. Today, the number of new facilities back up to levels of the 1970's, since it is greater than the amount of decommissioning in old installations. As no final decision on the back-end of the nuclear fuel cycle is foreseen in the near future in Brazil, either to recover the SNF or to consider it as radioactive waste, this material has to be isolated in some type of storage model existing around the world. In the present study it is shown that dry SNF storage is the best option. A national cask model for SNF as well these casks storage installation are proposed. It is a multidisciplinary study in which the engineering conceptual task was developed and may be applied to national SNF removed from the Brazilian power reactors, to be safely stored for a long time until the Brazilian authorities will decide about the site for final disposal. (author)

  4. Neuro-fuzzy models for systems identification applied to the operation of nuclear power plants; Sistemas neuro-fuzzy para identificacao de sistemas aplicados a operacao de centrais nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Antonio Carlos Pinto Dias

    2000-09-01

    A nuclear power plant has a myriad of complex system and sub-systems that, working cooperatively, make the control of the whole plant. Nevertheless their operation be automatic most of the time, the integral understanding of their internal- logic can be away of the comprehension of even experienced operators because of the poor interpretability those controls offer. This difficulty does not happens only in nuclear power plants but in almost every a little more complex control system. Neuro-fuzzy models have been used for the last years in a attempt of suppress these difficulties because of their ability of modelling in linguist form even a system which behavior is extremely complex. This is a very intuitive human form of interpretation and neuro-fuzzy model are gathering increasing acceptance. Unfortunately, neuro-fuzzy models can grow up to become of hard interpretation because of the complexity of the systems under modelling. In general, that growing occurs in function of redundant rules or rules that cover a very little domain of the problem. This work presents an identification method for neuro-fuzzy models that not only allows models grow in function of the existent complexity but that beforehand they try to self-adapt to avoid the inclusion of new rules. This form of construction allowed to arrive to highly interpretative neuro-fuzzy models even of very complex systems. The use of this kind of technique in modelling the control of the pressurizer of a PWR nuclear power plant allowed verify its validity and how neuro-fuzzy models so built can be useful in understanding the automatic operation of a nuclear power plant. (author)

  5. Instruction by virtual reality to operation and security of a nuclear power plant of IV generation; Instruccion por realidad virtual a la operacion y seguridad de una central nuclear de generacion IV

    Energy Technology Data Exchange (ETDEWEB)

    Neri O, J. C.; Baltasar M, J.; Valle H, J. [Facultad de Ingenieria, Division de Estudios de Posgrado, Campus Morelos, UNAM, Paseo Cuauhnahuac 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico)], e-mail: neriunam@ieee.org

    2009-10-15

    The purpose of LaNuVi project which is developing in the Engineering Faculty of National Autonomous University of Mexico, to have a virtual laboratory of nuclear reactors as tool of multidisciplinary education at basic and advanced levels in nuclear engineering area, involves training resources in audio visual and interactive form that allow to form a comprehension more realistic of operation of different systems and components. In this work is proposed to use educational resources, as the employees in the U.S. Army and in some centers of advanced education of medicine, where have been come proving concepts like projected reality, increased reality, tele transparency and others that present big benefits to learning-education process. The proposal here is to include the resource knew as serious game based learning. The focal point of stage that is presented is of a nuclear reactor PBMR like desalination and generator of controlled alternating energy and efficient that should put on in operation to allow the subsistence of a community in a desolated region of beginning second quarter of X XI century. For this purpose the designs are initiated and programmed several subsystems that allow the three-dimensional modeling of main components of a PBMR as well as of surrounding facilities. The obtained results and reaches of this design are presented. The product is in tests for a first version and it is hope to achieve a free and integral resource of national distribution for different cultural groups, interested in this type of advanced technology. (Author)

  6. 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

  7. 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.)

  8. Diagnosis and suggestions for the knowledge management applied to a nuclear installation: the uranium hexafluoride production unit; Diagnostico e sugestoes para a gestao do conhecimento aplicada a uma instalacao nuclear: a unidade de producao de hexafluoreto de uranio

    Energy Technology Data Exchange (ETDEWEB)

    Marchesini, Paulo Roberto de Andrade

    2008-07-01

    It has been more than 25 years since Brazilian Navy started applying resources and staff in a nuclear power program in which the main objective is the necessary technology for project and construction of a nuclear power reactor and nuclear fuel production for naval propulsion. A long period project tends to be susceptible to loss of essential parcels of knowledge. The objective of the present research is to identify actions and initiatives that may improve learning and dissemination of knowledge in an organization that develops complexes projects during a long period of time. The revision of the literature about Knowledge Management allowed the researcher to select a reference that indicates how people involved in a project gets the necessary information and knowledge for developing their activities and uses them to add value and to learn how to contribute for the organization, in order to prevent nature difficulties. The adopted methodology was a case study on the implantation of the {sup U}nidade de Hexafluoreto de Uranio{sup ,} which is being developed by the Centro Tecnologico da Marinha in Sao Paulo. With the application of structured and opened interviews, it was possible to identify some factors related with the attainment and dissemination of knowledge that can be developed. The result of this work was a proposal of action and initiatives that will improve the attainment of the knowledge, its structure and maintenance by the organization and the contribution by the people, of the knowledge acquired. (author)

  9. Innovation and knowledge generation in cooperation nets: challenges for regulations in the nuclear safety area in Brazil; Inovacao e geracao de conhecimento nas redes de cooperacao: desafios para a regulacao na area de seguranca nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Staude, Fabio

    2014-07-01

    The importance of inter-organisational cooperation within the innovation process has been increasingly recognized. In fact, all organisations, at some point, need to look to external sources for inputs to the process of building up technological competence. In this sense, through a detailed case study, this thesis examine theoretical and empirically how collaborative initiatives have supported the Brazilian nuclear regulatory body in the development and implementation of innovations, in order to verify the positive relationship between the collaboration and the organisational innovation performance. Emphasizing the importance of both internal sources of knowledge and external participation, the study encompasses documentary analysis, a preliminary survey and semi-structured interviews with the regulatory body employers in charge of controlling medical and research facilities and activities involving radiation sources. The thesis demonstrates that innovations developed and implemented in the Brazilian nuclear safety and security area are associated with collaborative initiatives, in order to improve the organizational capability to fulfill safety obligations, providing some important implications for regulatory body managers concerned with the management of innovation. The findings also identified actors with a significant degree of influence in the innovation process. The result reveals that the support provided by these actors has a significant influence on the innovation performance of the Brazilian nuclear regulatory body, suggesting that Brazil should adopt more interactive models of innovation and knowledge transfer. In addition, the findings show that these key actors can play a very distinctive role in the context of sectoral systems of innovation information regime. (author)

  10. Organization and management of maintenance in the NPP's Asco and Vandellos II; Organizacion y gestion del mantenimiento en las centrales nucleares Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Folguera, M.; Corral, A.

    2014-04-01

    The article starts with a description of the international framework that, using technical instructions, guides and guidelines, regulates the maintenance of nuclear power plants. It also outlines the characteristics of the organization and management of maintenance in the NPP's operated by ANAV. Such management is supported in a variety of processes and programs among which are: work management, training and qualification, operational experience, supervision, foreign material exclusion, work management in RP areas and outage preparation. (Author)

  11. 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)

  12. Implementation of the project of equipment reliability in the nuclear power plant of Laguna Verde; Implementacion del proyecto de confiabilidad de equipo en la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Rios O, J. E.; Martinez L, A. G. [CFE, Central Laguna Verde, Subgerencia General de Operacion, Veracruz (Mexico)]. e-mail: jrios@cfe.gob.mx

    2008-07-01

    A equipment is reliable if it fulfills the function for which was designed and when it is required. To implement a project of reliability in a nuclear power plant this associate to a process of continuous analysis of the operation, of the conditions and faults of the equipment. The analysis of the operation of a system, of the equipment of the same faults and the parts that integrate to equipment take to identify the potential causes of faults. The predictive analysis on components and equipment allow to rectify and to establish guides to optimize the maintenance and to guarantee the reliability and function of the same ones. The reliability in the equipment is without place to doubts a wide project that embraces from the more small component of the equipment going by the proof of the parts of reserve, the operation conditions until the operative techniques of analysis. Without place of doubt for a nuclear power plant the taking of decisions based on the reliability of their systems and equipment will be the appropriate for to assure the operation and reliability of the same one. In this work would appear the project of reliability its processes, criteria, indicators action of improvement and the interaction of the different disciplines from the Nuclear Power Plant of Laguna Verde like a fundamental point for it put in operation. (Author)

  13. 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.

  14. Design under uncertainty of a centralized Solar System for the ACS production; Diseno bajo incertidumbre de un sistema solar centralizado para la produccion de ACS

    Energy Technology Data Exchange (ETDEWEB)

    Dominguez Munoz, F.; Cejudo Lopez, J. M.; Carrillo Andres, A.

    2008-07-01

    Solar installations are usually sized by using simulation programs that calculate the annual solar fraction for a given design. While theoretically well founded, these programs require exact values for all the input factors. However, much of these factors are actually uncertain, so they can not be defined by a single value. In order to work out this contradiction, we propose the use of stochastic simulation methods. A centralized solar hot water system is analysed. The uncertainties in the problem are identified, estimated and propagated through a dynamic deterministic model. Finally, a sensitivity analysis is performed so as to figure out which uncertain factors have the largest effect on the solar fraction. (Author)

  15. LA PARTICIPACIÓN SOCIAL COMO ESTRATEGIA CENTRAL DE LA NUTRICIÓN COMUNITARIA PARA AFRONTAR LOS RETOS ASOCIADOS A LA TRANSICIÓN NUTRICIONAL

    Directory of Open Access Journals (Sweden)

    José Carlos Suárez-Herrera

    2009-01-01

    Salud como guía para una integración sistémica de la participación social en los procesos de planificación, implementación y evaluación de los programas de nutrición comunitaria. De este modo, contemplamos la integración de la participación social en los esfuerzos destinados al desarrollo de competencias individuales, al refuerzo de la acción colectiva, a la creación de entornos favorables, a la reorganización de servicios y sistemas de salud y, finalmente, a la elaboración de políticas en materia de nutrición y salud pública.

  16. 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.

  17. Um planejamento de experimentos para a avaliação do fluxo de calor crítico de reatores nucleares a água pressurizada de pequena escala.

    OpenAIRE

    2014-01-01

    Um dos parâmetros termo-hidráulicos de segurança mais importantes no projeto e operação de reatores a água pressurizada é o fluxo de calor crítico (FCC). O FCC ocorre quando se atinge uma região de instabilidade na mudança de mecanismo de transferência de calor de uma parede aquecida para um fluido, aumentado drasticamente a temperatura da parede. Transientes em um reator nuclear podem afetar a taxa de geração de calor ou a fluxo de refrigerante no núcleo, prejudicando a retirada de calor das...

  18. 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

  19. 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.

  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. Evaluación financiera de las alternativas para finalizar la implementación de un sistema integral de control interno en el Banco Central de Costa Rica

    OpenAIRE

    Jiménez Chacón, Carolina

    2013-01-01

    Tesis de maestría -- Universidad de Costa Rica. Posgrado en Administración y Dirección de Empresas. Maestría Profesional en Administración y Dirección de Empresas con énfasis en Finanzas, 2013 Resumen Jiménez Chacón; Carolina. EVALUACIÓN FINANCIERA DE LAS ALTERNATIVAS PARA FINALIZAR LA IMPLEMENTACIÓN DE UN SISTEMA INTEGRAL DE CONTROL INTERNO EN EL BANCO CENTRAL DE COSTA RICA Programa de Posgrado en Administración y Dirección de Empresas.-San José, CR.: C. Jiménez C., 2013. 95 h.- 37 il.- 6...

  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. Analysis of environmental impact phase in the life cycle of a nuclear power plant; Analisis de la fase de impacto ambiental en el ciclo de vida de una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez del M, C.

    2015-07-01

    The life-cycle analysis covers the environmental aspects of a product throughout its life cycle. The focus of this study was to apply a methodology of life-cycle analysis for the environmental impact assessment of a nuclear power plant by analyzing international standards ISO 14040 and 14044. The methodology of life-cycle analysis established by the ISO 14044 standard was analyzed, as well as the different impact assessment methodologies of life cycle in order to choose the most appropriate for a nuclear power plant; various tools for the life-cycle analysis were also evaluated, as is the use of software and the use of databases to feed the life cycle inventory. The functional unit chosen was 1 KWh of electricity, the scope of analysis ranging from the construction and maintenance, disposal of spent fuel to the decommissioning of the plant, the manufacturing steps of the fuel were excluded because in Mexico is not done this stage. For environmental impact assessment was chosen the Recipe methodology which evaluates up to 18 impact categories depending on the project. In the case of a nuclear power plant were considered only categories of depletion of the ozone layer, climate change, ionizing radiation and formation of particulate matter. The different tools for life-cycle analysis as the methodologies of impact assessment of life cycle, different databases or use of software have been taken according to the modeling of environmental sensitivities of different regions, because in Mexico the methodology for life-cycle analysis has not been studied and still do not have all the tools necessary for the evaluation, so the uncertainty of the data supplied and results could be higher. (Author)

  4. Modification and updating of documentation in equipment of panels of control room in nuclear power plant operation; Modificacion y actualizacion de documentacion en aparatos de paneles de sala de control en una central nuclear en operacion

    Energy Technology Data Exchange (ETDEWEB)

    Agudo Montero, L.

    2013-07-01

    The present paper describes a case very unique specific design of interactive 2D-CAD application, that has been developed by Empresarios Agrupados as engineering support to the nuclear power plants, aware of the problem that exists with the documentation of the instruments and devices that are on the panels of Control room, and that only have the documentation generated in its day by the manufacturers of these panels. To this end, an application (application DOPAB) has been developed to help solve the problem of management, design and modification of wiring and wiring devices existing in the Control room control panels.

  5. Proficiency tests for evaluation of the {sup 99}Tc{sup m} measurements in the nuclear medicine; Aplicacao de teste de proficiencia para avaliacao da medicao de {sup 99}Tc{sup m} na medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Iwahara, Akira; Tauhata, Luiz; Oliveira, Antonio Eduardo de, E-mail: iwahara@ird.gov.b, E-mail: tauhata@ird.gov.b, E-mail: aedu@ird.gov.b [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Nicoli, Ieda Gomes, E-mail: ieda@ird.gov.b [Comissao Nacional de Energia Nuclear (CNEN/DF), Brasilia, DF (Brazil). Escritorio de Brasilia; Alabarse, Frederico Gil; Xavier, Ana Maria, E-mail: falabarse@ird.gov.b, E-mail: axavier@ird.gov.b [Comissao Nacional de Energia Nuclear (ESPOA/CNEN-RS), Porto Alegre, RS (Brazil). Escritorio de Porto Alegre

    2009-07-01

    This work performs the performance evaluation of 55 Brazilian nuclear medicine services in activity measurement of radiopharmaceutical containing {sup 99}Tc{sup m}. Proficiency tests based on the acceptance criteria of the Regulation ISO/IEC Guide 43-1 and on the accuracy of the brazilian Regulation CNEN-NN-3.05 were applied in 63 results of activity measurements in radionuclide calibrators used by those services. The performance services has shown that the criteria of the ISO/IEC 43-1, nevertheless to be more restrictive, presents results very consistent with the accuracy criteria requested by the Brazilian regulation

  6. THE EFFECT OF LEARNING ORIENTATION IN THE ORGANIZATIONAL PERFORMANCE OF ENTERPRISES IN RS EL EFECTO DE LA ORIENTACIÓN PARA EL APRENDIZAJE EN EL DESEMPEÑO ORGANIZATIVO DE LAS EMPRESAS DE LA REGIÓN CENTRAL DE RS O EFEITO DA ORIENTAÇÃO PARA A APRENDIZAGEM NO DESEMPENHO ORGANIZACIONAL DAS EMPRESAS DA REGIÃO CENTRAL DO RIO GRANDE DO SUL

    Directory of Open Access Journals (Sweden)

    Eduardo Botti Abbade

    2013-01-01

    Full Text Available This study aims to identify the influence of learning orientation on organizational performance ofenterprises in the central region of Rio Grande do Sul. The method employed was a survey of 123 of these enterprises which were mostly classified as small and medium. The data collection instrument was developed using the scale of Learning Orientation developed by Sinkula, Baker and Noordewier (1997, adapted byBaker and Sinkula (1999 and items of organizational performance evaluation proposed by Narver and Slater (1990 and Baker and Sinkula (1999. Correlation Analysis, multiple regression and factor analysis aswell as elaboration of a structural equation model were made. It was found that these enterprises present amoderately high level of learning orientation and organizational performance. It was also noted thatLearning Orientation, in general, presents a positive and significant influence on organizationalperformance. However, more specifically, only the dimension Open Mind of the scale presented astatistically positive significance. The other two dimensions (Commitment to Learning and Shared Visionhad a positive, however not significant, impact.El presente estudio tiene como objetivo identificar la influencia de la orientación para el aprendizaje enel desempeño organizativo de las empresas de la región central de Rio Grande do Sul. El método empleadofue una investigación  de levantamiento con 123 empresas de la región central de RS. El instrumento decolecta de datos fue elaborado utilizándose la escala de Orientación para el Aprendizaje de Sinkula, Baker yNoordewier (1997, adaptada por Baker y Sinkula (1999, e ítems de evaluación del desempeño organizativopropuestos por Narver y Slater (1990 y Baker y Sinkula (1999. Fueron realizados análisis de correlación,regresión linear múltipla y análisis factorial, además de la ecuación estructural del modelo de estudio. Lasempresas investigadas fueron, en su mayoría, clasificadas

  7. Update of foundation design modifications of data cables and piping in nuclear power plants in operation; Actualizacion de modificaciones de sieno de bases de datos de cables y conducciones en centrales nucleares en operacion

    Energy Technology Data Exchange (ETDEWEB)

    Perez Pereira, J.

    2013-07-01

    The scope of this application is the manage the life cycle of cables electrical and pipes of cables in Trillo NPP. The application is integrated in a configuration Control system, so both cables and conduits become elements of configuration and management of life and history associated with the of the relevant modifying documents. The guarantees criteria of physical separation of wires for jobs and for independent networks designed according to the redundancy of the Central System.

  8. The cycle of the nuclear fuel used in EDF power plants; Le cycle du combustible nucleaire utilise dans les centrales EDF

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    This document briefly indicates the different stages of the nuclear fuel cycle, from the purchase of natural uranium to waste storage. It also indicates the main responsibilities of EDF regarding this fuel cycle (to secure supplies, to organise material transportation, to process and store used fuels and associated wastes). It presents the different associated processes: uranium extraction, purification and concentration, conversion or fluoridation, enrichment. It briefly describes the fuel assembly fabrication, and indicates the main uranium producers in the world. Other addressed steps are: the transportation of fuel assembly, fuel loading, and spent fuel management, the processing of spent fuel and radioactive wastes

  9. Análisis de estabilidad para el rendimiento de híbridos de maíz (Zea mays en la Región Central del Litoral Ecuatoriano

    Directory of Open Access Journals (Sweden)

    Daniel Vera Aviles

    2013-01-01

    Full Text Available El objetivo de este estudio fue determinar la estabilidad de híbridos experimentales y comerciales de maíz en la Región Central del Litoral Ecuatoriano. Durante el periodo de diciembre de 2010 a abril de 2011 se evaluaron ensayos uniformes de rendimiento en cuatro localidades con ambientes contrastantes. El material genético estuvo constituido por cinco híbridos experimentales y tres comerciales. El diseño experimental utilizado fue bloques completo al azar con cuatro repeticiones, las parcelas experimentales consistieron en dos surcos de 5,0 m de largo, separados a 0,90 m. El análisis de varianza combinado propuesto por Eberhart y Russell, se encontró significancia estadística tanto como para genotipo e interacción. El rendimiento promedio mostró que entre los híbridos experimentales se destacaron el (SM45 x SSD08SV39 y (SM45 x SV15SV39 con promedios superiores a la 7,0 t ha-1, mientras que el híbrido comercial que sobresalió fue el AG-003 con rendimiento de 7,48 t ha-1. Los mejores rendimientos y los mejores índices ambientales, se registraron para las localidades de Quevedo y Vinces, los índices ambientales más bajos fueron para Balzar y Ventanas. En relación a las tendencias de respuesta de genotipos sobresalientes en los cuatro ambientes de evaluación, particularmente se observó que los genotipos son deseables, en virtud de los resultados sobresalientes tanto en los ambientes favorables como en los desfavorables.

  10. Fenología, rendimiento y tamaño de grano de tres variedades comerciales de maní (Arachis hypogaea L. en condiciones de campo para la zona central de la provincia de Córdoba, Argentina

    Directory of Open Access Journals (Sweden)

    J.M Gamba

    2014-06-01

    Full Text Available Los requerimientos de los mercados internacionales y el desplazamiento del área de siembra tradicional de maní, determinaron la necesidad de incorporar nuevas variedades de este cultivo en el sistema de producción argentino. Sin embargo, no se ha evaluado aún el comportamiento a campo de las variedades más difundidas (ASEM 484 INTA, ASEM 485 INTA, Granoleico en el área central de Córdoba. El objetivo de este trabajo fue comparar estas tres variedades comerciales de maní en términos de fenología, rendimiento y tamaño de grano en condiciones de campo para dicha zona. Para ello se evaluaron parámetros fenológicos (emergencia de plántulas, ciclo de las variedades y estado de madurez de vainas y productivos (rendimiento y tamaño de grano. No se detectaron diferencias entre ASEM 484 y 485, pero sí respecto a Granoleico ya que esta última necesitó mayor tiempo térmico para alcanzar los estadios R1 y R2, lo que determinó menor proporción de vainas maduras al final del periodo evaluado. La variedad Granoleico alcanzó más tardíamente el periodo de llenado de grano. Aunque no hubo diferencias en el rendimiento entre las variedades, Granoleico presentó la menor proporción de granos de mayor calibre (HPS.

  11. UTILIZACIÓN DE TÉCNICAS NUCLEARES PARA ESTIMAR LA EROSIÓN HÍDRICA EN PLANTACIONES DE TABACO EN CUBA

    OpenAIRE

    Reinaldo H. Gil; José L. Peralta; Jorge Carrazana; Mario Riverol; Yulaidis Aguilar; Yilian M. Morejón; Jorge Oliveira; Gema Fleitas

    2015-01-01

    La erosión del suelo es un elemento importante en la degradación de tierras, provocando impactos negativos a varios niveles (parcela, finca, cuenca, etc). El cultivo del tabaco en el occidente del país se ha visto negativamente afectado por la erosión hídrica asociado a factores naturales y antrópicos. Un elemento fundamental para implementar una estrategia de manejo sostenible de tierras es la cuantificación de las pérdidas de suelo, ya que permiten establecer políticas de conservaci...

  12. Hidrocarburos en Kazajastán: nuevas realidades y enfoques para el estudio de las relaciones energéticas de Asia Central

    Directory of Open Access Journals (Sweden)

    Aurèlia Mañé Estrada

    2011-10-01

    Full Text Available 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 siguen siendo los mismos que en la década de 1970.Después de explicar por qué han quedado obsoletas estas premisas, el objetivo del artículo es triple: a mostrar por qué los hidrocarburos de Asia Central constituyen un nuevo tipo de caso de estudio en la economía mundial contemporánea; b describir la realidad de las relaciones energéticas en Kazajastán y cuál podría ser el futuro modelo de alianzas con el mundo de la Compañías Petroleras Internacionales (IOC y Nacionales (NOC, tanto de países consumidores y productores, e c inferir de este caso de estudio algunos de los elementos constitutivos de un nuevo paradigma energético-más centrado en la idea de estructura de governanza que en el PED.

  13. Remifentanilo vs. bloqueo central epidural para control del dolor postoperatorio en cirugía vascular de urgencias Remifentanyl versus epidural central blockade for the management of postoperative pain in emergency vascular surgery

    Directory of Open Access Journals (Sweden)

    A. Quirante

    2004-12-01

    Full Text Available El correcto tratamiento del dolor postoperatorio constituye una prioridad dentro de los objetivos del anestesiólogo. En pacientes con patología vascular severa quirúrgica, el tratamiento analgésico efectivo se suele realizar mediante bloqueo continuo epidural. Sin embargo, la administración de analgésicos, tanto opiáceos como no opiáceos, por vía intravenosa, es una alternativa a la vía epidural cuando esta es desestimada. Caso clínico: Presentamos el caso de un paciente varón de 63 años portador de un bypass fémoro-poplíteo a primera porción en miembro inferior izquierdo, el cual es intervenido quirúrgicamente y con carácter urgente tras el diagnóstico de falso aneurisma séptico de arteria iliaca izquierda con rotura de anastomosis fémoro-poplítea. Se optó por una anestesia general basada en la analgesia con remifentanilo frente a bloqueo central epidural dado el carácter urgente de la cirugía y la ingesta habitual de antiagregantes plaquetarios. Se planificó como estrategia analgésica postoperatoria la administración de remifentanilo a dosis sedoanalgésicas (Introduction: The appropriate management of postoperative pain is a priority among the objectives of the anesthesiologist. In patients with severe surgical vascular pathology, an effective analgesic treatment is usually provided with epidural continuous blockade. However, the intravenous administration of analgesics, either opiates or non opiates, is an alternative to the epidural route when this has to be dismissed. Clinical case: We present the case of a 63-years old male patient carrying a femoro-popliteus bypass in the first portion of the left lower limb that underwent emergency surgery after being diagnosed of a false septic aneurysm in the left iliac artery with breakage of the femoro-popliteus anastomosis. General anesthesia based on remifentanyl was decided instead of epidural central blockade due to the urgent nature of the surgery and the regular

  14. Questions to the reactors power upgrade of the Nuclear Power Plant of Laguna Verde; Cuestionamientos al aumento de potencia de los reactores de la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Salas M, B., E-mail: salasmarb@yahoo.com.mx [UNAM, Facultad de Ciencias, Departamento de Fisica, Circuito exterior s/n, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2014-08-15

    The two reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) were subjected to power upgrade labors with the purpose of achieving 20% upgrade on the original power; these labors concluded in August 24, 2010 for the Reactor 1 and in January 16, 2011 for the Reactor 2, however in January of 2014, the NNP-L V has not received by part of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the new Operation License to be able to work with the new power, because it does not fulfill all the necessary requirements of safety. In this work is presented and analyzed the information obtained in this respect, with data provided by the Instituto Federal de Acceso a la Informacion Publica y Proteccion de Datos (IFAI) and the Comision Federal de Electricidad (CFE) in Mexico, as well as the opinion of some workers of the NPP-L V. The Governing Board of the CFE announcement that will give special continuation to the behavior on the operation and reliability of the NPP-L V, because the frequency of not announced interruptions was increased 7 times more in the last three years. (Author)

  15. A methodology for semiautomatic taxonomy of concepts extraction from nuclear scientific documents using text mining techniques; Metodologia para extracao semiautomatica de uma taxonomia de conceitos a partir da producao cientifica da area nuclear utilizando tecnicas de mineracao de textos

    Energy Technology Data Exchange (ETDEWEB)

    Braga, Fabiane dos Reis

    2013-07-01

    This thesis presents a text mining method for semi-automatic extraction of taxonomy of concepts, from a textual corpus composed of scientific papers related to nuclear area. The text classification is a natural human practice and a crucial task for work with large repositories. The document clustering technique provides a logical and understandable framework that facilitates the organization, browsing and searching. Most clustering algorithms using the bag of words model to represent the content of a document. This model generates a high dimensionality of the data, ignores the fact that different words can have the same meaning and does not consider the relationship between them, assuming that words are independent of each other. The methodology presents a combination of a model for document representation by concepts with a hierarchical document clustering method using frequency of co-occurrence concepts and a technique for clusters labeling more representatives, with the objective of producing a taxonomy of concepts which may reflect a structure of the knowledge domain. It is hoped that this work will contribute to the conceptual mapping of scientific production of nuclear area and thus support the management of research activities in this area. (author)

  16. 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. 

  17. Revision of by-laws about effluents of EdF's nuclear power plants; Revision des arretes de rejets des centrales nucleaires d'EDF

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    In France, in application of the clean water law from January 3, 1992 and since the decree 95-540 from May 4, 1995, each basic nuclear facility receives a single permission which covers both its water takes and its radioactive and non-radioactive effluents. This decree, initially dedicated to new facilities has been enlarged to all existing installations for which the prefectorial by-laws have reached their date-line. Thus, up to now, five inter-ministerial by-laws have renewed the permissions of water takes and effluents evacuation of the power plants of Saint-Laurent-des-Eaux (Loir-et-Cher), Flamanville (Manche), Paluel (Seine-Maritime), Belleville (Cher) and Saint-Alban (Isere). These by-laws foresee an important abatement of the effluents and concern more particularly the tritium, {sup 14}C, the iodine isotopes and also some other non-radioactive chemical compounds. This document is a compilation of all revised by-laws about effluents and concerning the nuclear power plants listed above. (J.S.)

  18. Monitoring rainwater and seaweed reveals the presence of (131)I in southwest and central British Columbia, Canada following the Fukushima nuclear accident in Japan.

    Science.gov (United States)

    Chester, A; Starosta, K; Andreoiu, C; Ashley, R; Barton, A; Brodovitch, J-C; Brown, M; Domingo, T; Janusson, C; Kucera, H; Myrtle, K; Riddell, D; Scheel, K; Salomon, A; Voss, P

    2013-10-01

    Detailed analysis of (131)I levels in rainwater and in three species of seaweed (Fucus distichus Linnaeus, Macrocystis pyrifera, and Pyropia fallax) collected in southwest British Columbia and Bella Bella, B.C., Canada was performed using gamma-ray spectroscopy following the Fukushima nuclear power plant accident on March 11, 2011. Maximum (131)I activity was found to be 5.8(7) Bq/L in rainwater collected at the campus of Simon Fraser University in Burnaby, B.C. nine days after the accident. Concomitantly, maximum observed activity in the brown seaweed F. distichus Linnaeus was observed to be 130(7) Bq/kg dry weight in samples collected in North Vancouver 11 days following the accident and 67(6) Bq/kg dry weight in samples collected from the Bamfield Marine Sciences Centre on Vancouver Island 17 days following the accident. The (131)I activity in seaweed samples collected in southwest B.C. following the Fukushima accident was an order of magnitude less than what was observed following Chernobyl. Iodine-131 activity in F. distichus Linnaeus remained detectable for 60 days following the accident and was detectable in each seaweed species collected. The Germanium Detector for Elemental Analysis and Radioactivity Studies (GEARS) was modeled using the Geant4 software package and developed as an analytical tool by the Nuclear Science group in the Simon Fraser University Department of Chemistry for the purpose of these measurements.

  19. Use of technical based in 3D models for development of design changes in operating nuclear power plants; Empleo de tecnicas basadas en modelos 3D para el desarrollo de modificaciones de diseno en centrales nucleares en operacion

    Energy Technology Data Exchange (ETDEWEB)

    Munoz Portela, V.

    2012-07-01

    The present paper is to describe and analyze the use of these techniques and three-dimensional tools and results obtained with them, showing the extensive possibilities offered in this type of installation, based on the experience gained in recent years.

  20. 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)

  1. Screening of Central and South American plant extracts for antimycobacterial activity by the Alamar Blue test Triagem de extratos de plantas das Américas Central e do Sul para atividade antimicobacteriana pelo teste do Alamar Blue

    Directory of Open Access Journals (Sweden)

    Suzana G. Leitão

    2006-03-01

    Full Text Available Forty eight ethanolic crude extracts and fractions (hexane, dichloromethane, ethyl acetate and n-butanol from ten Brazilian plants (Leguminosae, Monimiaceae and Verbenaceae, 1 from Costa Rica (Verbenaceae and 1 from Argentina (Verbenaceae were screened for anti-mycobacterium activity against Mycobacterium tuberculosis (ATCC-27294H37Rv, by the Alamar Blue test, at a fixed concentration of 100 µg/mL. Out of the forty eight, seven were active at this concentration, corresponding to Lantana trifolia (hexane and dichloromethane extracts from leaves, Vitex cooperi (methanol:water, 1:1 extract from barks, Lippia lacunosa (hexane and dichloromethane extracts from leaves and Lippia rotundifolia (hexane and dichloromethane extracts from leaves, all from the Verbenaceae family.Quarenta e oito extratos brutos etanólicos e frações (em hexano, diclorometano, acetato de etila e n-butanol de dez plantas brasileiras pertencentes às famílias Leguminosae, Monimiaceae e Verbenaceae; uma da Costa Rica (Verbenaceae e uma da Argentina (Verbenaceae foram ensaiados para verificação da atividade anti-micobacteriana contra Mycobacterium tuberculosis (ATCC-27294H37Rv, pelo teste do Alamar Blue, a uma concentração fixa de 100 µg/mL. Dentre os quarenta e oito extratos e frações estudados, sete mostraram-se ativos na concentração ensaiada - frações em hexano e diclorometano de folhas de Lantana trifolia, extrato em metanol:água, 1:1 de cascas de Vitex cooperi, frações em hexano e diclorometano de folhas de Lippia lacunosa e de Lippia rotundifolia, sendoque todas essas plantas pertencem à família Verbenaceae.

  2. 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

  3. Sampling and description of the resins stockpiles in the Kozloduy Nuclear Power Plant large tanks; Muestreo y caracterizacion de resinas almacenadas en tanques de grandes dimensiones de la Central Nuclear de Kozloduy (Bulgaria)

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Fernandez, L.; Gonzalez Gandal, R.; Herrera, J. A.

    2012-11-01

    The consortium ENSA-Gas Natural Fenosa Engineering has a contract with Kozloduy Nuclear Power Plant (KNPP) for the retrieval and conditioning of the resins, which were generated during the operation of the plant. The project deals with resins characterization for which its necessary to define a proper methodology that fulfills the Bulgarian authorities requirements. Also, it will be included the design, fabrication, supply and installation of the required equipment to carry out the sampling and measurements of the resins, updating the facilities and the specific training of the personnel in order to perform by themselves every activities. This article reflects how the consortium will deal with the management of this damaging project, which involves a wide range of activities, including the management of each implicated are of both KNPP and external organizations. (Author)

  4. Environmental concerns regarding a materials test reactor fuel fabrication facility at the Nuclear and Energy Research Institute - IPEN; Atomos para el desarrollo de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Santos, G. R. T.; Durazzo, M.; Carvalho, E. F. U. [IPEN, CNEN-SP, P.O. Box 11049, CEP 05422-970, Sao Paulo (Brazil); Riella, H. G. [Universidade Federal de Santa Catarina, Departamento de Engenharia Quimica, Campus Universitario, Florianopolis, CEP 88040-900 (Brazil)]. e-mail: grsantos@ipen.br

    2008-07-01

    The aim of the industrial activities success, front to a more and more informed and demanding society and to a more and more competitive market demands an environmental administration policy which doesn't limit itself to assist the legislation but anticipate and prevent, in a responsible way, possible damages to the environment. One of the maim programs of the Institute of Energetic and Nuclear Research of the national Commission of Nuclear Energy located in Brazil, through the Center of Nuclear Fuel - CCN - is to manufacture MTR-type fuel elements using low-enrichment uranium (20 wt% {sup 2}35U), to supply its IEA-RI research reactor. Integrated in this program, this work aims at well developing and assuring a methodology to implant an environment, health and safety policy, foreseeing its management with the use of detailed data reports and through the adoption of new tools for improving the management, in order to fulfil the applicable legislation and accomplish all the environmental, operational and works aspects. The applied methodology for the effluents management comprises different aspects, including the specific environmental legislation of a country, main available effluents treatment techniques, process flow analyses from raw materials and intakes to products, generated effluents, residuals and emissions. Data collections were accomplished for points gathering and tests characterization, classification and compatibility of the generated effluents and their eventual environmental impacts. This study aims to implant the Sustainable Concept in order to guarantee access to financial resources, allowing cost reduction, maximizing long-term profits, preventing and reducing environmental accident risks and stimulating both the attraction and the keeping of a motivated manpower. Work on this project has already started and, even though many technical actions have not still ended, the results have being extremely valuable. These results can already give to

  5. Shields calculations for teletherapy equipment. Regulatory approach of the National Center of Nuclear Safety; Calculos de blindajes para equipos de teleterapia, enfoque regulatorio del Centro Nacional de Seguridad Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Fuente P, A. de la; Dumenigo G, C.; Quevedo G, J.R.; Lopez F, Y. [Centro Nacional de Seguridad Nuclear, Calle 28 No. 504 e/5 y 7 Ave. Miramar, Playa, Ciudad de la Habana (Cuba)]. e-mail: andres@orasen.co.cu

    2006-07-01

    The evaluation of applications of construction licenses for the new services of radiotherapy has occupied a significant space in the activity developed by the National Center of Nuclear Safety (CNSN) in the last 2 years. Presently work the experiences of the authors in the evaluation of the required shield for the local where cobalt therapy equipment and lineal accelerators of medical use are used its are exposed, the practical problems detected are approached during the application of the methodologies recommended in both cases and its are discussed which have been the suppositions of items accepted by the Regulatory Authority for the realization of these shield calculations. The accumulated experience allows to assure that the realistic application of the item data and the rational use of the engineering logic makes possible to design local for radiotherapy equipment that fulfill the established dose restrictions in the in use legislation in Cuba, without it implies an excessive expense of construction materials. (Author)

  6. Prospective conceptual qualification of hybrid centrifugation/distillatory for {sup 6}LI nuclear fusion technology scaled supply demands; Calificacion conceptual prospectiva de centrifugador/destilador hibrido para produccion de {sup 6}Li a demanda de la tecnologia Nuclear Fusion

    Energy Technology Data Exchange (ETDEWEB)

    Sedano, L.; Herranz, J. L.; Casado, J. L.; Castro, P.; Xiberta, J.

    2013-07-01

    The change in the demand for exploitation of lithium as a resource appears during the last decade, related to the development of the ion-Li batteries market and with the requirements of Nuclear Fusion fuels (deuterium and lithium) as coming energy option. A prospective analysis of synergistic demands of both markets, in its technical and in its economic aspects appears of prospective interest. The civil market {sup 6}Li/{sup 7}Li enrichment demand is analyzed. Specific technological developments permitting on-line production according to demand is discussed. A [centrifugation /thermal diffusion / combined distillation] technique is selected and qualified as technologically viable option for scaled production of litiated-forms. A conceptual design of a production plant is finally proposed according to the new technical capability.

  7. Probes for inspections of heat exchanges installed at nuclear power plants type PWR by eddy current method; Sondas para inspecao de trocadores de calor instalados em usinas nucleares tipo PWR pelo metodo de correntes parasitas

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Alonso F.O. [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Dept. de Enghenharia Mecanica]. E-mail: kauzz21@yahoo.com; Alencar, Donizete A. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mail: daa@cdtn.br

    2007-07-01

    From all non destructive examination methods usable to perform integrity evaluation of critical equipment installed at nuclear power plants (NPP), eddy current test (ET) may be considered the most important one, when examining heat exchangers. For its application, special probes and reference calibration standards are employed. In pressurized water reactor (PWR) NPPs, a particularly critical equipment is the steam generator (SG), a huge heat exchanger that contains thousands of U-bend thin wall tubes. Due to its severe working conditions (pressure and temperature), that component is periodically examined by means of ET. In this paper a revision of the operating fundamentals of the main ET probes, used to perform SG inspections is presented. (author)

  8. A study of digital hardware architectures for nuclear reactors protection systems applications - reliability and safety analysis methods; Um estudo de arquiteturas de hardware para aplicacao em sistemas digitais de protecao de reatores nucleares - metodos de analise de confiabilidade e seguranca

    Energy Technology Data Exchange (ETDEWEB)

    Benko, Pedro Luiz

    1997-07-01

    A study of digital hardware architectures, including experience in many countries, topologies and solutions to interface circuits for protection systems of nuclear reactors is presented. Methods for developing digital systems architectures based on fault tolerant and safety requirements is proposed. Directives for assessing such conditions are suggested. Techniques and the most common tools employed in reliability, safety evaluation and modeling of hardware architectures is also presented. Markov chain modeling is used to evaluate the reliability of redundant architectures. In order to estimate software quality, several mechanisms to be used in design, specification, and validation and verification (V and V) procedures are suggested. A digital protection system architecture has been analyzed as a case study. (author)

  9. Nuclear energy as culture: a practical process for preparation of the agents responsible for that transformation; Energia nuclear como cultura: um processo pratico para preparacao dos agentes desta transformacao

    Energy Technology Data Exchange (ETDEWEB)

    Aquino, Afonso Rodrigues de; Vieira, Martha Marques Ferreira [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: araquino@ipen.br, e-mail: mmvieira@ipen.br; Soares, Wellington Antonio [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: soaresw@cdtn.br

    2008-08-15

    In Brazil research and development are supported mainly by the government, meaning it is public money So it is important to share the knowledge and benefits from the research with the society. Another important question is the scientific analphabetism that raise difficulties for the comprehension of science and technology related matters. One way to improve the understanding process is the creation of workshops for science popularization which presented outstanding results. Participants of a workshop held by the Nuclear Technology Development Center CDTN - BH evaluated with grade 8.8 (from zero to ten) evincing the excellence of the applied model, simple in its essence: a group comprising scientific researchers, journalists and high school teachers attended several specific talks and was asked to prepare material for science divulgation according to the presented criteria. (author)

  10. Characterization of a Planetary Boundary Layer model to evaluate radionuclides releases in nuclear installations; Caracterizacao de um modelo de camada limite planetaria para avaliar liberacoes de radionuclideos em instalacoes nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Molnary, Leslie de

    1993-07-01

    A two layer bulk model is used to simulate numerically the time and spatial evolution of concentration of radionuclides in the Planetary Boundary Layer (PBL) for convective and stable conditions. In this model, the closure hypothesis are based on the integrated version of the Turbulent Kinetics Energy (TKE) equation (Smeda,1979). This type of model was adopted here because it is numerically simple to be applied operationally in routine and emergency support systems of atmospheric releases at nuclear power plants, and the hypothesis of the efficiency of the vertical mixing seems to be physically reasonable to simulated PBL evolution for high wind conditions and stable conditions in Subtropical latitudes regions. In order to validate the model to the nuclear power plants of the Centro Experimental Aramar (CEA), located in Ipero, State of Sao Paulo, Brazil, numerical simulations were carried out with initial and boundary conditions based on vertical profiles of temperature and horizontal wind speed and direction obtained from tethered balloon soundings, synoptic charts at 850 hPa and surface observations. Comparisons between a 24 hour long numerical simulation and observations indicate that the model is capable of reproduce the diurnal evolution of temperature and horizontal wind during the convective regime. During stable conditions, the slab model was able to simulate the intensity of the surface inversion as a difference between the mixed layer and surface temperatures. The simulated mixed layer height matches with observations during the convective and stable regime. A daytime release of radionuclides was simulated for CEA region and the results indicated that the maximum relative concentration reaches a distance about 15 Km in 1 hour, varing from 100 times background at the moment of the release to 15 times the background. For night releases, the maximum concentration reaches the same distance in 45 minutes, varing from 100 to 30 times the background values

  11. Elements to evaluate the intention in the non-compliance s or violations to the regulatory framework in the national nuclear facilities; Elementos para evaluar la intencionalidad en los incumplimientos o violaciones al marco regulador en las instalaciones nucleares nacionales

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa V, J. M.; Gonzalez V, J. A., E-mail: jmespinosa@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

    Inside the impact evaluation process to the safety of non-compliance s or violations, developed and implanted by the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS), the Guide for the Impact Evaluation to the Safety in the National Nuclear Facilities by Non-compliance s or Violations to the Regulatory Framework was developed, which indicates that in the determination of the severity (graveness level) of a non-compliance or violation, four factors are evaluated: real and potential consequences to the safety, the impact to the regulator process and the intention. The non-compliance s or intentional violations are of particular interest, since the development of the regulatory activities of the CNSNS considers that the personnel of the licensees, as well as their contractors, will act and will communicate with integrity and honesty. The CNSNS cannot tolerate intentional non-compliance s, for what this violations type can be considered of a level of more graveness that the subjacent non-compliance. To determine the severity of a violation that involves intention, the CNSNS also took in consideration factors as the position and the personnel's responsibilities involved in the violation, the graveness level of the non-compliance in itself, the offender's intention and the possible gain that would produce the non-compliance, if exists, either economic or of another nature. The CNSNS hopes the licensees take significant corrective actions in response to non-compliance s or intentional violations, these corrective actions should correspond to the violation graveness with the purpose of generating a dissuasive effect in the organizations of the licensees. The present article involves the legal framework that confers the CNSNS the attributions to impose administrative sanctions to its licensees, establishes the definition of the CNSNS about what constitutes a non-compliance or intentional violation and finally indicates the intention types (deliberate

  12. Evaluation of sensitivity evaluation of a contamination monitor for use in monitoring of internal exposure of workers in nuclear medicine; Avaliacao da sensibilidade de um monitor de contaminacao para aplicacao em monitoracao da exposicao interna de trabalhadores em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Dantas, Bernando Maranhao; Assis, Janima Cruz de; Oliveira, Salomao Marques de; Dantas, Ana Leticia Almeida, E-mail: bmdantas@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. de Monitoracao In Vivo. Div. de Dosimetria

    2014-07-01

    In practice of nuclear medicine, expert personnel routinely handle radiopharmaceuticals for diagnosis and radiotherapy. The control of intakes of radionuclides by workers can be performed through internal dosimetry techniques, as an integral part of the radiation protection program of the installation. The use of radiopharmaceuticals for diagnostic and therapeutic purposes in vivo and in vitro in Brazil is regulated by CNEN-NE Standards and 3:05 CNEN-NN 3.01. The International Atomic Energy Agency (IAEA) recommends the establishment of an internal monitoring program on workers, especially those subject to possible exposure to annual effective doses greater than 1 mSv. Note that, currently, in Brazil, are not available qualified laboratories to provide internal monitoring services in all regions in the country, if it were applied by CNEN, the requirement for internal monitoring of workers. This paper presents the development of a simple and low-cost methodology for in vivo monitoring of {sup 131}I in the thyroid. The proposed methodology is the use of portable monitor of surface contamination, equipment available and routinely used in all nuclear medicine services in Brazil. The monitor is calibrated with neck-thyroid simulator developed at the Laboratory of In Vivo Monitoring of IRD/CNEN-RJ. The equipment tested is suitable for application in in vivo occupational monitoring thyroid. This conclusion is based on the fact that the detection system has sufficient sensitivity for monitoring up to seven days after the incorporation of the radionuclide and guarantees {sup 131}I detection in values that result in effective doses below 1 mSv for the exposure scenarios adopted.

  13. 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; Rapport sur le controle de la surete et de la securite des installations nucleaires. Deuxieme partie: la reconversion des stocks de plutonium militaire. L'utilisation des aides accordees aux pays d'Europe centrale et orientale et aux nouveaux etats independants

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2002-07-01

    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.)

  14. A study on the nuclear foreign policy

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Jae Soo; Lee, H. M.; Jun, E. J.; Lee, D. H.; Lee, B. W.; Won, B. C.; Kim, H. J.

    2011-12-15

    This study addresses four arenas to assist national nuclear foreign policies under international nuclear nonproliferation regimes. Firstly, this study analyzes the trends of the international nuclear non-proliferation regime, which includes the Treaty on the Non-proliferation of Nuclear Weapons (NPT), the international nuclear export control regime, and fissile material cut-off treaty. Secondly, this study analyzes the trends of international nuclear organizations and fora, which include the International Atomic Energy Agency (IAEA) as a central body of international nuclear diplomacy and technical cooperation and International Framework for Nuclear Energy Cooperation (IFNEC) as a forum for international nuclear cooperation. Thirdly, this study analyzes the nuclear foreign policy of the U. S. Administration and reviews bilateral nuclear cooperation agreement between the ROK and the other countries including the U. S. Lastly, this study analyzes the nuclear issues of North Korea and Iran and multilateral nuclear approaches as assurances of nuclear fuel supply.

  15. Organismo de Energía Atómica aprueba plan de acción para fortalecer seguriidad en reactores nucleares

    OpenAIRE

    Vargas, Celso

    2013-01-01

    En la primera parte de este artículo, publicada en el número anterior de Investiga.TEC, nos referimos a los eventos ocurridos en Fukushima,Japón, entre marzo y abril del año 2011, sus efectos en algunos de los reactores de las plantas nucleares instaladas en el noroeste del país y las lecciones aprendidas a raíz de este evento y del de Chernóbil.En esta segunda parte, y final, nos ocuparemos de los elementos del plan de acción aprobado por el Organismo Internacional de Energía Atómica (OIEA) ...

  16. Nuclear Confidence

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident provides valuable lessons for China national nuclear Corp.as it continues to expand its operations AS Japan’s Fukushima nuclear crisis sparks a global debate over nuclear safety,China National Nuclear Corp. (CNNC),the country’s largest nuclear plant operator, comes under the spotlight.

  17. An experimental model for the transplantation of fetal central nervous system cells to the injured spinal cord in rats Modelo experimental de transplante de células do sistema nervoso central fetal para lesão de medula espinal em ratos

    Directory of Open Access Journals (Sweden)

    Tarcísio Eloy Pessoa de Barros Filho

    2002-01-01

    Full Text Available INTRODUCTION: Traumatic spinal cord injury is one of the most disabling conditions occurring in man and thus stimulates a strong interest in its histopathological, biochemical, and functional changes, primarily as we search for preventive and therapeutic methods. PURPOSE: To develop an experimental model for transplantation of cells from the fetal rat central nervous system to the site of an injured spinal cord of an adult rat in which the transplanted cells survive and become integrated. This experimental model will facilitate investigations of factors that promote regeneration and functional recovery after spinal cord trauma. MATERIAL AND METHODS: Fifteen adult Wistar rats underwent laminectomy, and an spinal cord lesion was made with microdissection. Fetal spinal cord tissue was then transplanted to the site of the injury. The rats were monitored over a 48-hour period, and then their vertebral column was completely removed for histological analysis. RESULTS: In 60% of transplanted rats, the fetal tissue at the injured site remained viable in the site of the lesion.INTRODUÇÃO: A lesão traumática da medula espinal consiste numa das mais incapacitantes lesões que o ser humano pode sofrer e tem despertado grande interesse no conhecimento das alterações histopatológicas, bioquímicas, funcionais e principalmente na busca de métodos de prevenção e tratamento. OBJETIVO: Propor um modelo experimental de transplante de células do sistema nervoso fetal de ratos para o sítio de lesão medular de ratos adultos que permitisse sua sobrevivência e integração para possibilitar protocolos de pesquisa para identificar outros fatores de regeneração e recuperação funcional pós trauma raquimedular. MATERIAL E MÉTODOS: Utilizaram-se 15 ratos adultos que foram submetidos a laminectomia e lesão de 5mm de hemimelula realizada com auxílio de microscópio óptico. Os ratos tiveram seu sítio de lesão medular transplantado com células do

  18. TAMANHO E FORMAS DE PARCELAS PARA INVENTÁRIOS FLORESTAIS DE ESPÉCIES ARBÓREAS NA AMAZÔNIA CENTRAL

    Directory of Open Access Journals (Sweden)

    Milena Marmentini de Oliveira

    2014-01-01

    Full Text Available One of the main tools to quantify and to qualify the forest potentials is the forest inventory. During its planning phase it is necessary to define the sampling intensity as well as the sizes and shapes of sample units to minimize data collection costs while increasing the precision of the forest inventory. This study aimed to test different sizes and shapes of sample units for different diameters at breast height (DBH size categories. The study was carried out in the Manaus region including INPA and EMBRAPA experimental station areas around BR-174 road, in the state of Amazonas, Brazil. Five categories of DBH were considered, as following: above 5cm, 10cm, 20cm, 25cm and 45cm. For all DBH categories, twenty-three different sizes were tested, from 100m2 to 10,000m2. The number of samples was defined as n = 30 for all size simulations to qualify for the use of the central limit theorem assumptions. Basal area was used to estimate uncertainty in relation to the true value of mean for comparison among different sizes for each DBH category. Almost all sample plot sizes in all categories of DAP obtained uncertainties below 10%. The best sample sizes were 1,000m 2 , 800m², 1,200m², 2,000m² and 10,000m², respectively for minimum DBH of 5, 10, 20, 25 and 45cm. Most of exploratory forest inventories in the state of Amazonas have been done for trees with DBH greater than 10cm, and sizes have varied from 1,000 to 2,000 m2. The findings of this work demonstrated that the size for exploratory inventory is adequate. However, different size should be used for DBH greater than 45cm, which is usually the minimum DBH for logging plans.

  19. Precision laboratory measurements in nuclear astrophysics

    Energy Technology Data Exchange (ETDEWEB)

    Gai, M. [Connecticut Univ., Storrs, CT (United States). Dept. of Physics

    2000-07-01

    After reviewing some of the basic concepts, nomenclatures and parametrizations of astronomy, astrophysics, cosmology, and nuclear physics, we introduce a few central problems in nuclear astrophysics, including the hot-CNO cycle, helium burning and solar neutrinos. We demonstrate that in this new era of precision nuclear astrophysics secondary or radioactive nuclear beams allow for progress. (orig.)

  20. Development of sealed radioactive sources immobilized in epoxy resin for verification of detectors used in nuclear medicine; Desenvolvimento de fontes radioativas seladas imobilizadas em resina epoxi para verificacao de detectores utilizados em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Tiezzi, Rodrigo

    2016-07-01

    The radioactive sealed sources are used in verification ionization chamber detectors, which measure the activity of radioisotopes used in several areas, such as in nuclear medicine. The measurement of the activity of radioisotopes must be made with accuracy, because it is administered to a patient. To ensure the proper functioning of the ionization chamber detectors, standardized tests are set by the International Atomic Energy Agency (IAEA) and the National Nuclear Energy Commission using sealed radioactive sources of Barium-133, Cesium-137 and Cobalt-57. The tests assess the accuracy, precision, reproducibility and linearity of response of the equipment. The focus of this work was the study and the development of these radioactive sources with standard Barium-133 and Cesium-137,using a polymer, in case commercial epoxy resin of diglycidyl ether of bisphenol A (DGEBA) and a curing agent based on modified polyamine diethylenetriamine (DETA), to immobilize the radioactive material. The polymeric matrix has the main function of fix and immobilize the radioactive contents not allowing them to leak within the technical limits required by the standards of radiological protection in the category of characteristics of a sealed source and additionally have the ability to retain the emanation of any gases that may be formed during the manufacture process and the useful life of this artifact. The manufacturing process of a sealed source standard consists of the potting ,into bottle standardized geometry, in fixed volume of a quantity of a polymeric matrix within which is added and dispersed homogeneously to need and exact amount in activity of the radioactive materials standards. Accordingly, a study was conducted for the choice of epoxy resin, analyzing its characteristics and properties. Studies and tests were performed, examining the maximum miscibility of the resin with the water (acidic solution, simulating the conditions of radioactive solution), loss of mechanical and

  1. Proposal of a methodology to be applied for the characterization of external exposure risk of employees in nuclear medicine services; Proposta de uma metodologia para caracterizacao de risco de exposicao externa de funcionarios de servicos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Simoes, Rafael Figueiredo Pohlmann

    2010-07-01

    Nuclear medicine procedure requires the administration of radioactive material by injection, ingestion or inhalation. After incorporation, the patient becomes a mobile source of radiation and, after their examination; they can irradiate everyone on their way out of the Nuclear Medicine Service (NMS). A group of workers in this path is considered a critical group, but there are no conviction on this classification, because there are not measurements available. Thus, workers claiming for occupationally exposed individual's (OEI) rights are common. Employers are always in a complex situation, because if they decided to undertake the individual external monitoring of the critical working groups, the Court considers all as OEI and employers are taxed. On the other hand, if they do not provide monitoring, it is impossible to prove that these workers were not exposed to effective doses higher than individual annual public's limit and they lose the actions, too. This work proposes a methodology to evaluate, using TLD environmental monitors, air kerma rate at critical staff points in a NMS. This method provides relevant information about critical groups' exposure. From these results, the clinic or hospital may prove technically, without individual monitoring of employees, the classification of areas and can estimate the maximum flow of patients in the free areas which guarantees exposures below the public individual dose limit. This methodology has been applied successfully to a private clinic in Rio de Janeiro, which operates a NMS. The only critical group that received exposure statistically different from clinic background radiation was that on the antechamber of the NMS. This is a site that should be characterized as a supervised area and the group of workers in this environment as OEI, as the estimated extrapolated annual effective dose in this position was 1.2 +- 0.7 mSv/year, above the public annual limit (1,0 mSv/year). Normalizing by the number of

  2. Methodological proposal for the construction of the labor profiles of inspectors of the Nuclear Regulatory Authority; Propuesta metodologica para la construccion de los perfiles laborales de inspectores de la Autoridad Regulatoria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Larcher, A.M.; Maceiras, E.; Degiovanni, G.; Perrin, C.; Sajaroff, P. [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)]. e-mail: alarcher@sede.arn.gov.ar

    2006-07-01

    The Argentine Nuclear Regulatory Authority (ARN) like essential part of their strategic institutional plan and in the mark of the modernization of the National Public Administration (NPA), identify the necessity to modify their functional organization, introducing the administration for processes and defining more flexible and better guided structures to the work in team. Starting from the definition of a new institutional flowchart it decided to proceed to a general reorganization of the human resources and on January, 2005 it was prepared the creation of a process whose serious objective to sit down the bases for the development of the professional career of the ARN. To such an end, it was thought about a work outline by stages, the first one of which had as final objective the elaboration of the Labor Profiles of the Institution. The work group for this first stage was integrated by a group of professionals of long trajectory in the institution and not belonging to the sector of Human Resources (RRHH). By this way it was organized as an independent group that it worked in narrow collaboration with the specific sector and informed directly to the maximum institutional direction. For the construction of the profiles a 'mixed' model was chosen that included the requirements of each position (that to make) and the competitions to complete them (how to make it), since a focus purely of competitions has not been seen as the more appropriate for the public administration and in particular for the ARN. In this work it is given to know a part of the results obtained during six months of effective work of the PerLa Group (denominated as well as an acronym of the expression Labor Profiles) putting emphasis in the defined profiles for the inspectors of those different regulatory branches that constitute the environment of competition of the RNA, this is Radiological Protection, Nuclear Safety, Safeguards and Physical Protection. The idea that underlies to the

  3. 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)

  4. 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

  5. Albitization and quartz dissolution in Paleoproterozoic metagranite, central Sweden — Implications for the disposal of spent nuclear fuel in a deep geological repository

    Science.gov (United States)

    Petersson, Jesper; Stephens, Michael B.; Mattsson, Håkan; Möller, Charlotte

    2012-09-01

    Hydrothermal alteration resulting in albitization and quartz dissolution has been identified in Paleoproterozoic metagranites down to - 1000 m elevation at Forsmark, Sweden. The alteration features were discovered during investigations to locate a site for the disposal of spent nuclear fuel in a deep geological repository. In general, albitization occurs extensively, but it is also observed locally adjacent to minor intrusive bodies of amphibolite. The altered rocks show a marked decrease in K-feldspar and an increase in quartz relative to the unaltered equivalents, resulting in an epitonalitic composition. Plagioclase is metamorphic in character and generally richer in albite than in the unaltered rocks. It is inferred that albitization was triggered by the input of basic or intermediate melts into the crust during igneous activity close to the peak of regional metamorphism at 1.87-1.86 Ga. The mineralogy of the epitonalites gives rise to an increased thermal conductivity and, thereby, a positive influence for the design and safety of a deep geological repository for spent nuclear fuel. However, the increased frequency of low conductive amphibolite in the albitized volumes, consistent with the proposed mechanism for alteration, gives a negative influence. In sharp contrast to the albitization, a majority of the occurrences of quartz dissolution, which resulted in the formation of episyenite, are located along fracture zones. Quartz dissolution took place between or after 1.8-1.7 Ga, when the bedrock was able to respond to deformation in a brittle manner. Most of the vugs left after the removal of quartz are, to a variable extent, refilled by hydrothermal assemblages, including quartz, albite, K-feldspar, hematite, chlorite and calcite. The geometry and spatial distribution of episyenite argue against an extreme fluid/rock ratio and it is inferred that the fluids had at least a moderate salinity with a temperature in excess of 300 °C. The dissolution process was

  6. Pacientes assintomáticos apresentam infecção relacionada ao cateter venoso utilizado para terapia nutricional parenteral Asymptomatic patients present infection related to the central venous catheter used for total parenteral nutrition

    Directory of Open Access Journals (Sweden)

    Juliana Deh Carvalho Machado

    2009-12-01

    Full Text Available OBJETIVO: Avaliar a freqüência de infecção relacionada ao cateter venoso central em pacientes submetidos a terapia nutricional parenteral. MÉTODOS: Foram analisados os cateteres venosos centrais de pacientes em terapia nutricional parenteral que tiveram a indicação de retirada do cateter venoso central por infecção, alta hospitalar, ou trombose. Os pacientes com infecção foram denominados de Grupo 1 e os demais de Grupo 2. RESULTADOS: Não houve diferença estatisticamente significante quanto ao estado nutricional dos 18 pacientes analisados. Foram analisados 28 cateteres e destes 68% estavam infectados, sendo 72% do Grupo 1 e 28% do Grupo 2 (assintomáticos. No Grupo 1, houve infecção sistêmica em 70% dos casos, já no Grupo 2 a hemocultura foi positiva em 17% dos casos. A colonização por Staphylococcus sp. ocorreu em 48% dos casos, seguida de Candida sp. (21%, Enterococcus faecalis (16%, Pseudomonas aerurginosa (10% e Proteus sp.(5%. CONCLUSÃO: A contaminação de cateter venoso central utilizado para terapia nutricional parenteral é freqüente. Mesmo pacientes assintomáticos recebendo nutrição parenteral têm uma incidência maior de infecção por Candida sp. Portanto é necessária a criação de barreiras que impeçam a colonização destes cateteres venosos centrais, a fim de diminuir a morbimortalidade de pacientes dependentes deste tipo de terapia.OBJECTIVE: The aim of this study was to evaluate the frequency of central venous catheter-related infections in hospitalized patients receiving total parenteral nutrition. METHODS: Central venous catheters were analyzed immediately after removal due to infection, hospital discharge or thrombosis. The patients with catheter-related infection were named Group 1 and the other patients were named Group 2. RESULTS: Eighteen patients were studied. There was no statistically significant difference in nutritional status between the two groups. A total of 28 catheters were analyzed

  7. Corrosion in nuclear power plants and it implication in the leak before break criteria; Corrosion en centrales nucleares y su implicacion en el criterio de fuga antes de ruptura

    Energy Technology Data Exchange (ETDEWEB)

    Martinez M, E

    1992-05-15

    The corrosion in a general way can be defined like a chemical or electrochemical reaction, which is carried out in the surface of the metallic materials exposed to a specific medium. Due to the operation conditions in the nuclear power plants are practically fixed and its modification in most of the cases is difficult or expensive, the natural tendency to prevent the corrosion has been generally directed toward the selection of materials. Numerous materials have been employees as substitute of the traditional steels, among other the stabilized stainless steels, those of extra low carbon and numerous nickel base alloys. The basic evaluation that establishes the approach Leak before break (LBB) it involves the analysis by means of 'fracture mechanics' of a postulated crevice that it crosses the thickness of the material, which causes a same flight, with a margin of safety, to the detection limit that it has for a shutdown of the reactor. Due to the crevice size postulated, it cannot be established highly starting from the mechanical properties of the material since these its will be affected by the corrosion mechanisms that can settle down, it was determined that the implementation of the LBB criteria, it cannot be established for components or systems that its are susceptible of suffering corrosion. (Author)

  8. Radiological surveillance in Mexico, derived of the accident of the Fukushima Daiichi nuclear power plant; Vigilancia radiologica en Mexico, derivado del accidente en la central nuclear de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    Aguirre G, J.; Nohpal J, X., E-mail: jaguirre@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Departamento de Vigilancia Radiologica, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    March 11, 2011 an earthquake of 9.0 grades in the Richter scale, originated in the coast of Tohoku, Japan, in the Pacific Ocean gave origin to a tsunami that caused an accident in the Fukushima Daiichi nuclear power plant. Due to this accident, derived of the loss of the reactor cooling system, as well as of the prolonged absence of alternating and direct current, radiological protection actions were realized without being able to avoid the liberation of radioactive material to the atmosphere and ocean. The radiological impact of these liberations, not only in Japan but around the world, mainly in the north hemisphere of the Earth, was analyzed by means of environmental dose measurements and radionuclide concentrations in soil and water, among others. In the Mexico case, air samples data were obtained, as well as environmental dose celerity and full-length counts of the people coming from Japan near the disaster area. The present work contains the obtained results of the realized measurements in Mexico, same that have been used to make a summary and analysis of the dispersion in the environment in several countries of the world. (Author)

  9. Aid system in the attention direction for accidents diagnosis at nuclear power plants based on artificial intelligence; Sistema de auxilio para o direcionamento da atencao no diagnostico de acidentes em usinas nucleares baseado em inteligencia artificial

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Rafael Gomes da

    2009-07-01

    Transient identification in Nuclear Power Plant (NPP) is often a very hard task and may involve a great amount of human cognition. The early identification of unexpected departures from steady state behavior is an essential step for the operation, control and accident management in NPPs. The bases for the transient identification relay on the evidence that different system faults and anomalies lead to different pattern evolution in the involved process variables. During an abnormal event, the operator must monitor a great amount of information from the instruments that represents a specific type of event Several systems based on specialist systems, neural-networks, and fuzzy logic have been developed for transient identification. In the work, we investigate the possibility of using a Neuro Fuzzy modeling tool for efficient transient identification, aiming to helping the operator crew to take decisions relative to the procedure to be followed in situations of accidents/transients at NPPs. The proposed system uses artificial neural networks (ANN) as first level transient diagnostic After the ANN has done the preliminary transient type identification, a fuzzy-logic system analyzes the results emitting reliability degree of it. A preliminary evaluation of the developed system was made at the Human-System Interface Laboratory (LABIHS). The obtained results show that the system can help the operators to take decisions during transients/accidents in the plant (author)

  10. The project of the Spanish Nuclear Industry Forum to develop an interactive educational material on Radiological Protection; El Proyecto de Foro de la Industria Nuclear espanola para elaborar un material didactico interactivo sobre Proteccion Radiologica

    Energy Technology Data Exchange (ETDEWEB)

    Real, A.; Cruz, T. de la; Girona, L.; Montesinos, L.; Sanchez, P.

    2012-07-01

    The Training Department of the Spanish Nuclear Industry Forum has undertaken a new project to develop an interactive educational material on Radiological Protection. The objective was to develop an attractive, comprehensive and interactive material, to facilitate students and teachers of Elementary, Middle and High schools, to become familiar with ionising radiations. The novelly of the project, is that based on the European framework of key competencies for file long learning, which are defined as a set of knowledge, skills and altitudes that all individuals need for personal fulfilment and employment. The material presented in this paper, is based in an integrated structure of tasks, activities and exercises, which will facilitate the acquisition of as may key competencies as possible. Besides, the material also includes reference texts, links to pertinent web sites and videos. Students, through the development of a specific task (and related activities and exercises), will learn the differences between ionizing and non ionising radiation, the origin, characteristics and types of types of ionising radiation, how to detect and measure them, the potential detrimental health effects, the principles of radiation protection and the beneficial applications can have for man. The material is freely available in www.rinconeducativo.org. (Author) 4 refs.

  11. Study of a fuel assembly for the nuclear reactor of IV generation cooled with supercritical water; Estudio de un ensamble de combustible para el reactor nuclear de generacion IV enfriado con agua supercritica

    Energy Technology Data Exchange (ETDEWEB)

    Barragan M, A.; Martin del Campo M, C.; Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Espinosa P, G., E-mail: albrm29@yahoo.com [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Area de Ingenieria en Recursos Energeticos, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (MX)

    2011-11-15

    In this work a neutron study is presented about a square assembly design of double line of fuel rods, with moderator box to the center of the arrangement, for a nuclear reactor cooled with supercritical water (SCWR). The SCWR reactor was chosen by the characteristics of its design, mainly because is based in light water reactors (PWR and BWR), and the operational experience that has of them allow to use models and similar programs to simulate the fuel and the nucleus of this type of reactors. To develop the necessary models and to carry out the design and analysis of the SCWR reactor, the neutron codes MCNPX and Helios were used. The reason of using both codes, is because the code MCNPX used thoroughly in the neutron simulation of these reactors, it has been our reference code to analyze the results obtained with the Helios code which results are more efficient because its calculation times are minors. In the nucleus design the same parameters for both codes were considered. The results show that the design with Helios is a viable option to simulate these reactors since their values of the neutrons multiplication factor are very similar to those obtained with MCNPX. On the other hand, it could be corroborated that the CASMO-4 code is inadequate to simulate the fuel to the temperature conditions and water pressure in the SCWR. (Author)

  12. Calibration factor determination for solid nuclear track detectors CR-39 type exposed to Rn-222; Determinacao do fator de calibracao para detectores solidos de tracos nucleares tipo CR-39 expostos a Rn-222

    Energy Technology Data Exchange (ETDEWEB)

    Cazula, Camila Dias; Campos, Marcia Pires de; Mazzilli, Barbara Paci, E-mail: cdcazula@ipen.br, E-mail: mpcampos@ipen.br, E-mail: mazzilli@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2014-07-01

    In the detection method with solid nuclear track detector, when a heavy particle rests on the detector surface, causes a breakdown in their molecular structure forming a trace. One of the typical applications of these detectors is the measurement of the concentration of Rn -222 in air, a noble radioactive gas, part of the U-238 series, emitting alpha particles and important in epidemiological studies to protect individuals from natural radiation. To determine the concentration of Rn -222 in the air in a room is necessary to know the density of lines (traces / cm{sup 2}) on the detector surface, the exposure time and the calibration factor. The determination of the calibration factor for CR-39 detectors was taken from the exposure of these to a known concentration of Rn-222. Therefore, the detectors were placed inside a cell of Lucas adapted and subsequently exposed to a concentration of Rn-222 15 kBq / m{sup 3}, by means of the apparatus RN-150 Pylon Electronics Incorporation, which has a source of Ra-226 and releases known concentrations of Rn-222. Six calibration factor determinations were performed, the average value obtained was 0.0534 ±0.0021 (traces / cm{sup 2} per Bq / m{sup 3} day). The results are consistent with literature values for the same type of detector and showed good reproducibility.

  13. Application of COMSOL in the solution of the neutron diffusion equations for fast nuclear reactors in stationary state; Aplicacion de COMSOL en la solucion de las ecuaciones de difusion de neutrones para reactores nucleares rapidos en estado estacionario

    Energy Technology Data Exchange (ETDEWEB)

    Silva A, L.; Del Valle G, E., E-mail: evalle@ipn.mx [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico)

    2012-10-15

    This work shows an application of the program COMSOL Multi physics Ver. 4.2a in the solution of the neutron diffusion equations for several energy groups in nuclear reactors whose core is formed by assemblies of hexagonal transversal cut as is the cas of fast reactors. A reference problem of 4 energy groups is described of which takes the cross sections which are processed by means of a program that prepares the definition of the constants utilized in COMSOL for the generic partial differential equations that this uses. The considered solution domain is the sixth part of the core which is applied frontier conditions of reflection and incoming flux zero. The discretization mesh is elaborated in automatic way by COMSOL and the solution method is one of finite elements of Lagrange grade two. The reference problem is known as the Knk with and without control rod which led to propose the calculation of the effective multiplication factor in function of the control rod fraction from a value 0 (completely inserted control rod) until the value 1 (completely extracted control rod). Besides this the reactivity was determined as well as the change of this in function of control rod fraction. The neutrons scalar flux for each energy group with and without control rod is proportioned. The reported results show a behavior similar to the one reported in other works but using the discreet ordinates S{sub 2} approximation. (Author)

  14. Economic analysis of extended cycles in the Laguna Verde nuclear power plant; Analisis economico de ciclos de extendidos en la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez N, H.; Hernandez M, J.L.; Francois L, J.L. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: hermilo@correo.unam.mx

    2004-07-01

    The present work presents a preliminary analysis of economic type of extended cycles of operation of the Unit One in the Laguna Verde nuclear power plant. It is analysed an equilibrium cycle of 18 months firstly, with base to the Plan of Use of Energy of the Federal Commission of Electricity, being evaluated the cost of the energy until the end of the useful life of the plant. Later on an alternative recharge scenario is presented with base to an equilibrium cycle of 24 months, implemented to the beginning of the cycle 11, without considering transition cycles. It is added in both cycles the cost of the substitution energy, considering the unitary cost of the fuel of a dual thermoelectric power station of 350 M We and evaluating in each operation cycle, in both scenarios, the value of the substitution energy. The results show that a reduction of the days of recharge in the cycle of 24 months could make this option but favorable economically. The duration of the period of recharge rebounds in considerable grade in the cost of energy generation for concept of fuel. (Author)

  15. High temperature fast reactor for hydrogen production in Brazil; Reator nuclear rapido de altissima temperatura para producao de hidrogenio no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Nascimento, Jamil A. do; Ono, Shizuca; Guimaraes, Lamartine N.F. [Centro Tecnico Aeroespacial (CTA-IEAv), Sao Jose dos Campos, SP (Brazil). Inst. de Estudos Avancados]. E-mail: jamil@ieav.cta.br

    2008-07-01

    The main nuclear reactors technology for the Generation IV, on development phase for utilization after 2030, is the fast reactor type with high temperature output to improve the efficiency of the thermo-electric conversion process and to enable applications of the generated heat in industrial process. Currently, water electrolysis and thermo chemical cycles using very high temperature are studied for large scale and long-term hydrogen production, in the future. With the possible oil scarcity and price rise, and the global warming, this application can play an important role in the changes of the world energy matrix. In this context, it is proposed a fast reactor with very high output temperature, {approx} 1000 deg C. This reactor will have a closed fuel cycle; it will be cooled by lead and loaded with nitride fuel. This reactor may be used for hydrogen, heat and electricity production in Brazil. It is discussed a development strategy of the necessary technologies and some important problems are commented. The proposed concept presents characteristics that meet the requirements of the Generation IV reactor class. (author)

  16. Regulatory approach of the monitoring the effectiveness of maintenance at nuclear power plants program; Abordagem regulatoria do programa de monitoracao da eficacia da manutencao para usinas nucleoeletricas

    Energy Technology Data Exchange (ETDEWEB)

    Vajgel, Stefan

    2009-03-15

    The electrical power generation using nuclear power plants requires this installation being safety, reliable and available for the working periods. For this purpose, an adequate, effective and well conducted maintenance program makes an essential and useful tool to the owner of the plant. However, it is necessary to follow the regulatory requirements for this program implementation which monitories this maintenance effectiveness. There are Brazilian norms requirements which must be followed. The international regulatory guides establish these requirements in good details but it is necessary to verify if this methodology for implementing can be totally applied here in Brazil. Then, the american guide NUMARC 93-01 which details how can be implemented a program for this monitoring, shows some methods for using. In this thesis, the Delphi and Probabilistic Safety Analysis were briefly included because they were preferred for implementing this monitoring.in a Brazilian plant. The results which are being obtained show that, looking the regulatory aspects, the NUMARC 93-01 follows our regulations and gives good results for the plant management. (author)

  17. 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

    Beltrán Custodio, Ana María

    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).

  18. "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".

  19. Nuclear moments

    CERN Document Server

    Kopferman, H; Massey, H S W

    1958-01-01

    Nuclear Moments focuses on the processes, methodologies, reactions, and transformations of molecules and atoms, including magnetic resonance and nuclear moments. The book first offers information on nuclear moments in free atoms and molecules, including theoretical foundations of hyperfine structure, isotope shift, spectra of diatomic molecules, and vector model of molecules. The manuscript then takes a look at nuclear moments in liquids and crystals. Discussions focus on nuclear paramagnetic and magnetic resonance and nuclear quadrupole resonance. The text discusses nuclear moments and nucl

  20. Nuclear safeguards; Salvaguardias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zurron, O.

    2015-07-01

    Safeguards control at the Juzbado Plant is implemented through the joint IAEA/EURATOM partnership approach in force within the European Union for all nuclear facilities. this verification agreement is designed to minimize burden on the operators whilst ensuring that both inspectorate achieve the objectives related to their respective safeguards regimes. This paper outlines the safeguards approaches followed by the inspectorate and the particularities of the Juzbado Plants nuclear material accountancy and control system. (Authors)

  1. Study of environmental noise in a BWR plant like the Nuclear Power Plant Laguna Verde; Estudio de ruido ambiental en una planta BWR como la Central Nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Cruz G, M.; Amador C, C., E-mail: francisco.tijerina@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Cardel-Nautla Km. 42.5, Alto Lucero, Veracruz (Mexico)

    2013-10-15

    In all industry type the health costs generated by the noise are high, because the noise can cause nuisance and to harm the capacity to work when causing tension and to perturb the concentration, and in more severe cases to reach to lose the sense of the hearing in the long term. The noise levels in the industry have been designated for the different types of use like residential, commercial, and industrial and silence areas. The noise can cause accidents when obstructing the communications and alarm signs. For this reason the noise should be controlled and mitigated, at a low level as reasonably is possible, taking into account that the noise is an acoustic contamination. The present study determines a bases line of the environmental noise levels in a nuclear power plant BWR-5 as Laguna Verde, (like reference) to be able to determine and to give pursuit to the possible solutions to eliminate or to limit the noise level in the different job areas. The noise levels were registered with a meter of integrative noise level (sonometer) and areas of noise exposure levels mapping the general areas in the buildings were established, being the registered maximum level of 96.94 dba in the building of the Reactor-elevation 0.65 m under the operation conditions of Extended Power Up rate (EPU) of 120% PTN. Knowing that the exposition to noises and the noise dose in the job place can influence in the health and in the safety of the workers, are extensive topics that they should be analyzed for separate as they are: to) the effects in the health of the exposure to the noise, b) how measuring the noise, c) the methods and technologies to combat and to control the noise in the industry by part of engineering area and d) the function of the industrial safety bodies as delegates of the health and safety in the task against the noise in the job. (author)

  2. Specification and development of the sharing memory data management module for a nuclear processes simulator; Especificacion y desarrollo del modulo de administracion de datos de memoria compartida para un simulador de procesos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Telesforo R, D. [UNAM, DEPFI, Campus Morelos, Jiutepec, Morelos (Mexico)]. e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    Actually it is developed in the Engineering Faculty of UNAM a simulator of nuclear processes with research and teaching purposes. It consists of diverse modules, included the one that is described in the present work that is the shared memory module. It uses the IPC mechanisms of the UNIX System V operative system, and it was codified with C language. To model the diverse components of the simulator the RELAP code is used. The function of the module is to generate locations of shared memory for to deposit in these the necessary variables for the interaction among the diverse ones processes of the simulator. In its it will be able read and to write the information that generate the running of the simulation program, besides being able to interact with the internal variables of the code in execution time. The graphic unfolding (mimic, pictorials, tendency graphics, virtual instrumentation, etc.) they also obtain information of the shared memory. In turn, actions of the user in interactive unfolding, they modify the segments of shared memory, and the information is sent to the RELAP code to modify the simulation course. The program has two beginning modes: automatic and manual. In automatic mode taking an enter file of RELAP (indta) and it joins in shared memory, the control variables that in this appear. In manual mode the user joins, he reads and he writes the wanted control variables, whenever they exist in the enter file (indta). This is a dynamic mode of interacting with the simulator in a direct way and of even altering the values as when its don't exist in the board elements associated to the variables. (Author)

  3. Development of a model for strategic evaluation of the global performance of the Brazilian Nuclear Energy Commission; Desenvolvimento de um modelo para avaliacao estrategica do desempenho global da Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Staude, Fabio

    2003-07-01

    A conscious, effective course of action, now essential to several areas and organizations, has become a must in the public administration. In this sense, modem managerial practices may contribute significantly for governmental organism to take up an attitude shifted to results in the society, without losing its eminently public function. In order to measure the social impact of the activities of the State as a whole, institutions must use mechanisms that allow self-evaluations of their performance, so as to verify the return obtained as a result of their efforts. However, most institutions do not have structured tools for such evaluation. The present study proposes to the Comissao Nacional de Energia Nuclear a model to measure its global performance, offering a proposed architecture for the measurement system in accordance with the results of the planning process of the Institution. The methodology presented also comprises the definition of cause-and-effect critical models between the strategic objectives of the organization and its respective factors critic ai for success, as well as related performance indicators. This work also includes the breakdown of the measurement system for the macro processes of the organization, optimizing resource sharing and the flow of information, avoiding redundant efforts and bringing forth further advantages aiming at creating a organizational 'unit'. Within this context, the developed model may offer substantial help for the improvement of the maturity of the organization in goal-oriented management, considering that the proposed global performance measurement follows a planned structure, with a systemic approach of the organization, allowing that the process be carried out in a way that is transparent and objective. (author)

  4. Adaptation of the dynamic model for radiological assessment of nuclear accident in rural area under conditions of tropical climate; Adaptacao do modelo dinamico para avaliacao radiologica de acidente nuclear em area rural nas condicoes de clima tropical

    Energy Technology Data Exchange (ETDEWEB)

    Vinhas, Denise Martins

    2004-07-01

    Following an accidental release of radionuclides to the atmosphere that leads to the contamination of large areas, a detailed and fast methodology to assess the prognosis of public exposure is needed, in order to estimate radiological consequences and propose and optimize decisions related to the protection of the public. The model ECOSYS has been chosen to integrate the SIEM, the Integrated Emergency System developed by IRD/CNEN, to assess the doses at the short, medium and long term to the public after an accidental contamination of rural areas. The objective of this work is to perform the adaptation of the model ECOSYS to be used in Brazil to assess public exposure and support decision processes regarding the implementation of protective measures but also to guide the need for studies and research aiming to improve the adequacy of estimates to the actual Brazilian situation. The area select for reference to this work consists on the 50 km radius area surrounding the Brazilian nuclear power plants, located at Angra dos Reis County, in the state of Rio de Janeiro. The methodology included the definition of criteria to select agricultural cultures and animals to be simulated, taking into account both the availability of the production at the selected area and the relevance of the food to the population regional diet. Radionuclides included in this study were {sup 137}Cs, {sup 90} Sr and {sup 131} I. A large survey has been performed to gather data related to both agricultural practices and behavior of radionuclides in the selected agricultural-systems. The results of simulation indicated the relevance of the knowledge of local aspects on the estimated doses. Important factors included the kind of products produced, seasonality, agricultural practices, animals feed practices, kind of soil, and ingestion habits of the population. (author)

  5. Protocol for therapy of people who suffered wounds from radioactive material in radiological and nuclear accidents; Protocolo para trato de pessoas que sofreram ferimentos com material radioativo em acidentes radiologicos e nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lopes, Amanda Gomes

    2015-07-01

    The handling of glassware in ampoules, containing solution is very common in research or production laboratories. During manipulation, there is a likelihood of occurrence of incidents such as the breaking of ampoules or glass vials containing material in liquid or powdered form which may cause a wound to the possibility of contamination with handled material. When the solution is radioactive there is a concern due to the risk of incorporation of that material. According to NCRP 156, the scientific literature contains over 2100 cases of wounds contaminated with radionuclides and more than 90% of the reported cases occurred in the hands and arms, but mainly on the fingers. Despite having no cases of wounds reported radioactive material in Brazil or a protocol developed by the National Agencies, applications and hence the manipulation of radionuclides is increasing in the country, rising the possibility of wound occurrence contaminated by radionuclides. In this work was proposed a methodology for management of individuals who suffered wounds from radioactive material in cases of nuclear accidents and radiological emergencies that present intake, which consisted of four steps: definition of the accident scenario, individual triage of the public or workers, proper measurements with detectors PRD, IdentiFINDER2 and germanium in different thicknesses material tissue-equivalent, and later adoption of first aid measures consisting of attendance, monitoring of contaminated personnel, evaluation of effective dose and direct to specialized medical center. As an example of results it follows the case of {sup 241}Am where the best performance was obtained by measurements with the shielded HPGe (7%) and the shielded and collimation of 0.5 cm IdentiFINDER2 (10%). While, unshielded PRD, unshielded or shielded side IdentiFINDER2 and unshielded TeCd showed performance ranging from 30 to 70%. In general, the uncertainties obtained had values below 1.5%. In this work a protocol for

  6. On the applicability of a correlation of critical heat flux prediction for advanced nuclear fuel from Angra-1; Confirmando a aplicabilidade de uma correlacao de previsao do fluxo de calor critico para o combustivel nuclear avancado de Angra-1

    Energy Technology Data Exchange (ETDEWEB)

    Palheiros, Franklin L.; Gomes, Sydney [Industrias Nucleares do Brasil SA, Rio de Janeiro, RJ (Brazil). Gerencia de Analise Tecnica do Combustivel]. E-mail: franklin@inb.gov.br; sydney@inb.gov.br

    2005-07-01

    To establish the nuclear core operation limits it is requested that the safe condition of heat transfer between the fuel rod and the primary system coolant shall be well known. Those limits are set based on the critical heat flux marking the upper limit of nucleate boiling where the interaction of the coolant causes a departure from nucleate boiling - DNB [1]. For the new fuel type (16NGF) to be used at the Angra-1, the Kori-2, and the Krsko sites, the Critical Heat Flux must be characterized as well. Compared to the 16x16STD fuel (a 25+ year old Westinghouse design), the 16NGF design has many new features, including: three Intermediate Flow Mixers (IFM's) were added in the grid spans 4, 5 and 6 to improve the mixing behavior and consequently the thermal margin; an optimized vane pattern was used as well as an improved vane design (RFA Mod-1 vane). Others important thermal characteristics are the use of an optimized fuel rod diameter- from the U/H ratio point of view (0.360'' instead of 0.374'') and others features (Reference 2).Therefore, to demonstrate the applicability of an existing CHF correlation for the 16NGF design, two tests were performed in the Columbia University's Heat Transfer Research Facility, New York City (HTRF). Denominated Tests number 112 and number 113, they employed a 5x5 bundle array with a heated length of 12 ft. and cosine axial power shape. The purpose of this paper is then to present the data analysis from the 16NGF CHF tests and demonstrate, through a statistical evaluation, that the resulting data when evaluated is 'poolable' (combinable) with the WRB-2 database. In so doing, it can be thus stated that the WRB-2 correlation is applicable to 16 NGF Fuel Assemblies. (author)

  7. 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

  8. A Study on the Nuclear Foreign Policy

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Wook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Oh, K. B.; Yang, M. H.; Lee, K. S

    2007-12-15

    This study approaches the international trends related to nuclear non-proliferation in four aspects. First, this study analyzes the trend of the international nuclear non-proliferation regime, which includes the Treaty on the Non-proliferation of Nuclear Weapons (NPT), the international nuclear export control regime and proposals for assurance of nuclear fuel supply. Second, this study analyzes the trend of international nuclear organizations, which includes the International Atomic Energy Agency (IAEA), a central body of development of nuclear technology and international nuclear diplomacy, and the Organization for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA), a intergovernmental organization to consist of a group of nuclear advanced countries. Third, this study analyzes the trends of the U.S.'s nuclear foreign policies, particularly nuclear non-proliferation. Fourth, this study analyzes the nuclear issues of North Korea and Iran as they cause serious concerns to a international society.

  9. Heparina para desobstrução de cateter venoso central de inserção periférica no recém-nascido: estudo in vitro

    Directory of Open Access Journals (Sweden)

    Talita Balaminut

    2015-09-01

    Full Text Available ResumoObjetivo:Comparar a eficácia de duas concentrações de heparina para a desobstrução por coágulo do cateter venoso central de inserção periférica (CCIP neonatal in vitro.Métodos:Estudo experimental in vitro quantitativo que usou 76 CCIPs neonatais de tamanho 2 French coagulados in vitro. Os cateteres foram divididos em dois grupos com 38 CCIPs cada. Ambos os grupos receberam infusão de heparina de baixo peso molecular, com dose de 25UI/mL no Grupo I e de 50UI/mL no Grupo II. Os cateteres de ambos os grupos foram submetidos à técnica de pressão negativa com cinco, 15 e 30 minutos e com quatro horas e testou-se sua permeabilidade. Usou-se a análise de sobrevivência para verificar o desfecho dos grupos conforme os intervalos de tempo.Resultados:A comparação dos dois grupos no intervalo de tempo de cinco minutos mostrou um número maior de desobstrução de cateteres no Grupo II (57,9% em relação ao grupo 1 (21,1%. A análise de Kaplan Meier indicou menor tempo para desobstrução dos cateteres quando a heparina em maior concentração (50UI/mL foi usada (p<0,001.Conclusões:O uso de heparina de baixo peso molecular na concentração de 50UI/mL foi mais eficaz na restauração da permeabilidade de CCIPs neonatais ocluídos in vitro por coágulo e situou-se tal concentração dentro da margem de segurança indicada na literatura científica.

  10. 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.

  11. Habilidad de estimación de los métodos de evapotranspiración para una zona semiárida del centro de México Suitability of evapotranspiration estimation methods for semiarid central Mexico

    Directory of Open Access Journals (Sweden)

    Rebeca Vásquez-Méndez

    2011-06-01

    , respectivamente, indicando la posibilidad de usar modelos de regresión para condiciones semiáridas.In arid and semiarid areas, the evapotranspiration process constitutes a major loss of water to the atmosphere, prompting the need for a better understanding and quantification of this phenomenon, especially in semiarid environments where water resources are scarce. There are many available methods to estimate evapotranspiration; however, their performance in specific environments must be evaluated before making a selection. A weather station was used to collect data from a semiarid zone of Central Mexico with the purpose to evaluate eight different methods for daily, weekly and monthly periods of observation. The estimated results were compared with measured data from an ET gage company, as this device has been calibrated and proven to be closely associated to reference evapotranspiration data. The mean absolute error, root mean squared error, regression line intercept and slope, as well as determination coefficient R², were obtained to statistically evaluate the performance of evaluated methods. A poor performance for all time scales was found for the Oudin, McGuinness, Jensen and Haise, and Romanenko methods, with high values of mean absolute error and root mean squared error. Low values of the intercept, slope and R² parameters were also obtained for such methods, making them not suitable and consequently not suited for the study area. On the other hand, the Penman-Monteith and Penman methods, showed the best performance in different time scales. Similar results have been fund by other authors, supporting Penman-Monteith as a method of reference. A multiple regression equation to predict reference from climatic variables was also obtained with R²= 0.8, 0.82 and 0.91 for daily, weekly and monthly scales, respectively, indicating the possibility of using regression models for semiarid conditions.

  12. Helium desorption in EFDA iron materials for use in nuclear fusion reactors; Desorcion de helio en materiales de fierro EFDA para su aplicacion en los reactores de fusion nuclear