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Sample records for central nuclear para

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

    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. Safety related terms for advanced nuclear plants; Terminos relacionados con la seguridad para centrales nucleares avanzadas

    NONE

    1995-12-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety.

  3. Cybersecurity: new challenge for nuclear power plants; Ciberseguridad: nuevo reto para las centrales nucleares

    Mirambel Boquera, J.

    2011-07-01

    The purpose of this protective strategy is to ensure ability to detect, contain, respond and recover digital systems for monitoring, control and protection and thus ensure business continuity. A defensive strategy that consists of multiple levels is implemented to protect digital systems from unauthorized access, modification erroneous, misuse or any threat that could pose a risk to the Nuclear Security, Physical Security of people and the Radiological Protection, and the Environment.

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

    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)

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

    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).

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

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

    1992-12-31

    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).

  7. Development of a simulator for personnel training on nuclear power plants. The authors` experience in the Federal Republic of Germany; Desarrollo de un simulador para entrenamiento de personal de centrales nucleares. Experiencia de los autores en la Republica Federal de Alemania

    Hacker, P; Kogan, A; Garzon, D

    1991-12-31

    This work describes the stages necessary to carry out the development of a full scope simulator for personnel training on nuclear power plants operation. (Author). [Espanol] Este trabajo describe los pasos o etapas necesarios para llevar adelante el desarrollo de un simulador de amplio alcance (full scope simulator) para entrenamiento de personal de operacion de centrales nucleares. (Autor).

  8. Diseño y evaluación de un procedimiento on-line para la biorremediación de aguas radiactivas en centrales nucleares

    Belinchón Vergara, Julio Angel

    2016-01-01

    Recientemente se ha demostrado la existencia de microorganismos en las piscinas de almacenamiento de combustible nuclear gastado en las centrales nucleares utilizando técnicas convencionales de cultivo en el laboratorio. Estudios posteriores han puesto de manifiesto que los microorganismos presentes eran capaces de colonizar las paredes de acero inoxidable de las piscinas formando biopelículas. Adicionalmente se ha observado la capacidad de estas biopelículas de retener radionúclidos, lo que ...

  9. Power Nuclear Reactors: technology and innovation for development in future; Centrales Nucleares de Potencia: tecnologias actuales e innovaciones para el futuro

    Suarez Antola, R [Universidad Catolica del Uruguay, Montevideo(Uruguay); Ministerio de Industria Energia y Minerria, Montevideo(Uruguay)

    2009-07-01

    The conference is about some historicals task of the fission technology as well as many types of Nuclear Reactors. Enrichment of fuel, wastes, research reactors and power reactors, a brief advertisment about Uruguay electric siystem and power generation, energetic worldwide, proliferation, safety reactors, incidents, accidents, Three-Mile Island accident, Chernobil accident, damages, risks, classification and description of Power reactors steam generation, nuclear reactor cooling systems, future view.

  10. Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition); Analisis determinista de seguridad para centrales nucleares. Guia de Seguridad Especifica

    NONE

    2012-12-15

    The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

  11. Nuclear Energy in Central Europe 98, Proceedings

    Ravnik, M.; Jencic, I.; Zagar, T.

    1998-01-01

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

  12. Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants; Limitations de l'Efficacite de la Detection des Defauts par Essais Non Destructifs de Tubes de Bouilleurs pour Centrales Nucleaires; Predely ehffektivnosti nedestruktivnoj defektoskopii trub parogeneratorov yadernykh ehlektrostantsij; Limites para Distinguir los Defectos en el Ensayo No Destructivo de Tubo para Generadores de Vapor Destinados a Centrales Nucleares

    Kuhlmann, A.; Adamsky, F. -J. [Technischer Ueberwachungs-Verein Reinland e.V., Cologne (Germany)

    1965-10-15

    -Verein' de Rhenanie qui a ete charge de surveiller et de controler la fabrication et le montage des bouilleurs, pour garantir que cet element de la centrale soit aussi exempt que possible de defauts. L'experience acquise dans l'execution de ces travaux peut etre tres utile pour la fabrication et le montage des bouilleurs de n'importe quel type de centrale nucleaire. Le memoire traite des limitations de l'efficacite des essais non destructifs de tubes de bouilleurs. Les auteurs discutent plus particulierement les essais ci-apres: a) Controle automatique par ultrasons de tubes droits dans l'usine de production; b) Controle combine, par ultrasons et par radiographie, de tubes coudes et de soudures; c) Autres controles non destructifs. (author) [Spanish] En la Republica Federal de Alemania se estan construyendo reactores nucleares con generadores de vapor situados en el interior del tanque de presion. Las caracteristicas de este modelo dificultan considerablemente la reparacion de los tubos del generador que puede llegar a paralizar la central nuclear por largos periodos. Como es bien sabido, muchas de las dificultades para mantener en funcionamiento las centrales nucleares de tipo clasico provienen de averias en los tubos del generador de vapor. Por ello, y teniendo tambien en cuenta como razon no menos importante el elevado costo total de esos reactores, es preciso construir los generadores de vapor de tal manera que el factor carga de la central sea lo mas elevado posible. El Technischer Ueberwachungs-Verein Rheinland se encarga de dirigir e inspeccionar la fabricacion y la construccion de generadores de vapor para que esa parte de las instalaciones carezca en lo posible de defectos. La experiencia adquirida a ese respecto ofrece ademas interes para la fabricacion y construccion de los generadores de vapor que se destinan a las centrales nucleares en general. En la presente memoria se examinan los limites de rendimiento del ensayo no destructivo de los tubos para generadores

  13. Nuclear insurance in Central and Eastern Europe

    Warren, G.

    1998-01-01

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

  14. 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

    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)

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

    Flach, G.; Bonitz, M.

    1979-12-01

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

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

    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)

  17. Central Bureau for Nuclear Measurements

    1991-01-01

    The main task of CBNM is defined as the specific programme Nuclear Measurements and Reference Materials. In the field of neutron data for standards, for fission and for fusion application, the nuclear charge distribution and odd-even effects for mass, charge and neutron number in the cold spontaneous fission of 252 Cf were determined. X- and γ-ray emission probabilities were evaluated in the frame of an IAEA coordinated Research Project. The subthermal fission cross section measurements of 235 U, 233 U and 239 Pu, were finalised. The dependence of the experimental weighting function of C 6 D 6 detectors on thickness of several 56 Fe samples was determined. Fusion data studies involved the development of a light-ion telescope with improved time - and energy resolution. Double differential cross-sections of 9 Be were analysed. Radionuclide metrology dealt with the response of silicon detectors, as well as with the standardization of 192 Ir sources. Project Reference Materials reports the EC Certification of nuclear reference materials 210 (PuO 2 ), 523 (Al), 525 (Nb) and 526 (Nb). Progress was achieved in the preparation of dried solid spikes of uranium and plutonium for undiluted reprocessing input solution analysis. 10 B and 6 Li deposits were prepared for a redetermination of the neutron lifetime. Preliminary studies on speciation of trace metals in biological fluids were successful. Radioactive waste barrels were analysed by γ-scanning and blood samples were irradiated with 0.6 MeV neutrons. Exploratory research resulted in first measurements of transition radiation properties

  18. Nuclear Electric's central dose record service

    Goldfinch, E.P.; Mullarkey, D.T.; McWhan, A.W.; Risk, G.; Vaughan, L.

    1991-01-01

    This paper describes the conception, development and operation of the Nuclear Electric Central Dose Record Service, including the initial philosophy considered necessary for a database for a large multi-site organisation, the setting up of the data and current routine operation. Lessons learned are briefly described. CDRS holds 35,000 records in a high security environment. The database includes records of radiation doses received by contractor's employees working at Nuclear Electric sites as well as dose records and dose histories for classified and non classified Nuclear Electric employees. (Author)

  19. Central depression of nuclear charge density distribution

    Chu Yanyun; Ren Zhongzhou; Wang Zaijun; Dong Tiekuang

    2010-01-01

    The center-depressed nuclear charge distributions are investigated with the parametrized distribution and the relativistic mean-field theory, and their corresponding charge form factors are worked out with the phase shift analysis method. The central depression of nuclear charge distribution of 46 Ar and 44 S is supported by the relativistic mean-field calculation. According to the calculation, the valence protons in 46 Ar and 44 S prefer to occupy the 1d 3/2 state rather than the 2s 1/2 state, which is different from that in the less neutron-rich argon and sulfur isotopes. As a result, the central proton densities of 46 Ar and 44 S are highly depressed, and so are their central charge densities. The charge form factors of some argon and sulfur isotopes are presented, and the minima of the charge form factors shift upward and inward when the central nuclear charge distributions are more depressed. Besides, the effect of the central depression on the charge form factors is studied with a parametrized distribution, when the root-mean-square charge radii remain constant.

  20. Nuclear Safety in Central and Eastern Europe

    2001-04-01

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

  1. Perspectives for nuclear electricity in Central Africa

    Wa Kalenga, M.

    1977-01-01

    The paper analyses the energy system of the Central African countries and evaluates the projected global demand of energy. It compares the economy of the nuclear solution for satisfying future demands in relation to other forms of energy available in the region. Finally, it discusses the role that the countries involved can play in the fuel cycle (supply of raw material, possibilities of fuel enrichment). (author)

  2. Perspectives for nuclear electricity in central Africa

    Wa Kalenga, M.

    1977-01-01

    The paper analyses the energetic system of Central African countries and evaluate the projected global demand of energy. It compares the economy of the nuclear solution for the satisfaction of future demand versus other forms of energy available in the region. It appreciates finally the role that the countries involved can play in the fuel cycle (supply of raw material, possibilities of fuel enrichment) [fr

  3. Application of digital solutions to help the safe and efficient operation of nuclear power plants; Aplicacion de soluciones digitales para la ayuda a la operacion segura y eficiente de las centrales nucleares

    Ortega P, F.; Fernandez F, S., E-mail: fortega@tecnatom.es [Tecnatom S. A., Av. Montes de Oca 1, 28703 San Sebastian de los Reyes, Madrid (Spain)

    2017-09-15

    In the search for excellence, the emergence of solutions to digitize nuclear power plants is an opportunity to optimize the operation and safety of them. The new technologies available today in the market, applied under a global vision of the operation, can contribute to the excellent operation of nuclear power plants in terms of efficiency and effectiveness. Tecnatom has a long experience in various areas related to the operation of the plants, giving the aforementioned global vision, essential to develop global solutions that pursue the safe and efficient operation of the operation. (Author)

  4. 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

    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.

  5. 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

    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

  6. 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

    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)

  7. 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

    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)

  8. 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

    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)

  9. Analysis of the implementation of a sand bed type filter for the venting of a nuclear power plant; Analisis de la implementacion de un filtro tipo lecho de arena para el venteo de una central nuclear

    Cuevas V, D.; Sainz M, E.; Ortiz V, J., E-mail: delfy.cu@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    The filtered venting of the containment has been adopted in European countries to mitigate the consequences derived from the excess pressure of the containment during a severe accident. When venting has taken place, the fission products are released directly into the environment, unless a filter is placed in the path of the same, so various types of filters are used to trap the fission products. The containment venting filters currently installed use different filtering technologies that involve more than one medium. Those who use water as the first stage of filtration are called wet systems, are equipped with additional stages to eliminate water drops and emissions of fine aerosols, and may even be equipped with an element that contains certain means of absorption for the gaseous iodine species filtration. Other designs, based on deep bed filtration as the main retention stage, called dry filters; use metal fiber, ceramic or sand filtration media to trap aerosols. The present work evaluates the hydraulic characteristics of the sand bed type filter designed by EDF as a candidate to be installed in the containment of the BWR Mark II (primary containment type of the Laguna Verde nuclear power plant). The evaluation of the sand bed filter was performed using the OpenFOAM open source software package. Models of each zone of the filtering device were generated and by means of a series of parametric calculations of computational fluid mechanics, the relevant hydrodynamic characteristics of the device were obtained, such as pressure drops against mass flow and pressure fields and velocity under different operating conditions. On the other hand, the validation of the sand bed filter model was made when comparing the results of experimental tests carried out in a sand column of the PITEAS program (1985-1986) against the simulation in OpenFOAM. The results obtained are very close to those obtained experimentally. (Author)

  10. Central depression of the nuclear charge distribution

    Friedrich, J.; Voegler, N.; Reinhard, P.G.

    1986-01-01

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

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

    Mavko, B; Cizelj, L [eds.; Nuclear Society of Slovenia (Slovenia)

    1997-07-01

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

  12. Central Institute of Nuclear Research Rossendorf 25 years old

    Hohmuth, K.; Kaun, K.H.; Schmidt, A.; Hennig, K.; Brinckmann, H.F.; Lehmann, E.; Rossbander, W.; Bitterlich, H.; Weibrecht, R.; Fuelle, R.; Nebel, D.; Reetz, T.; Beyer, G.J.; Muenze, R.

    1981-12-01

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

  13. Site of the First Spanish Nuclear Power Stations; Los Emplazamientos de las Primeras Centrales Nucleares Espanolas

    Pascual, F.; Alonso, A.; Norena, S.; Sevilla, A. [Junta de Energia Nuclear, Madrid (Spain)

    1967-09-15

    (e), con reactor de agua en ebullicion y contencion por condensacion de vapor, y la central de Vandellos, de 480 MW(e), con reactor grafito-gas y diseno integrado del tipo EDF-4. Los dos primeros estan situados en el interior del pais, el tercero en la costa mediterranea. Se discuten los criterios convencionales y los relacionados con la seguridad, que se han utilizado en la seleccion. Se pone de relieve la influencia de la orografia espanola en el transporte del equipo pesado y su repercusion en la seleccion de emplazamientos para centrales nucleares. Se hace referencia a la experiencia obtenida en el transporte del equipo de la central de Zorita. Se analizan las dificultades practicas encontradas al aplicar unas determinadas normas de seguridad a emplazamientos de centrales de tipo y caracteristicas de diseno diferentes. Ya que el tipo de reactor y su sistema de contencion influyen en el valor practico de la aplicacion de unas determinadas normas que, ademas, han de adaptarse a las caracteristicas peculiares de cada nacion, se indica la conveniencia de utilizar de forma adecuada y flexible las normas de seguridad para el analisis de los emplazamientos de centrales nucleares. Se describen las caracteristicas geologicas y meteorologicas de los tres emplazamientos y se resumen los trabajos e investigaciones realizados en estos campos. En especial, se destacan los estudios de hidrologia realizados en el caso de Zorita y Santa Maria de Garofia, y se describen las estaciones meteorologicas montadas en ambos emplazamientos, los experimentos de difusion con globos equilibrados realizados en el caso de Santa Maria de Garofia y los resultados de estas investigaciones. (author)

  14. 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

    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.

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

    Stritar, A.; Jencic, I.

    1996-01-01

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

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

    Stritar, A; Jencic, I [Nuclear Society of Slovenia (Slovenia); eds.

    1996-07-01

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

  17. THERMOS, district central heating nuclear reactors

    Patarin, L.

    1981-02-01

    In order to expand the penetration of uranium in the national energy balance sheet, the C.E.A. has been studying nuclear reactors for several years now, that are capable of providing heat at favourable economic conditions. In this paper the THERMOS model is introduced. After showing the attraction of direct town heating by nuclear energy, the author describes the THERMOS project, defines the potential market, notably in France, and applies the lay-out study to the Grenoble Nuclear Study Centre site with district communal heating in mind. The economic aspects of the scheme are briefly mentioned [fr

  18. A contribuicao do direito nuclear para o melhor aproveitamento da energia nuclear para fins pacifico

    Puig, D.E.

    1983-01-01

    The text describes the contribution of nuclear law in order to improve the nuclear energy utiliation for peaceful uses. The actuation of the nuclear law as mediator between the nuclear progress and its consequences aiming to get better life conditions and education as base for developing are shown [pt

  19. Nuclear energy in central and eastern Europe

    Cognet, G.; Billaud, E.; Battista, L.; Pascal, J.

    2010-01-01

    Bulgaria, Hungary, Czech Republic, Romania, Slovakia and Slovenia have all nuclear power plants on their soil, their entry to the European Union has counter-balanced the number of member states that are not in favour of nuclear energy. All these countries committed themselves to upgrade their installations to European safety standards. This work is going on and new programs for service life extension and for construction of new units have been launched. All these countries have a strong culture and know-how in nuclear engineering inherited from soviet era. They stay very active in this field, for instance the ALLEGRO project that is carried out by a collaboration between Hungarian, Slovak, Czech research institutes and western partners aims at building the first demonstration plant of the future fourth generation reactor: a fast reactor cooled by gas. The situation of each country plus Croatia (that is a candidate to full E.U. membership) is reviewed. (A.C.)

  20. 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

    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)

  1. Radiopharmaceuticals for nuclear cardiology; Radiofarmacos para cardiologica nuclear

    Leon Cabana, Alba [Universidad de la Republica, Facultad de Quimica (Uruguay)

    1994-12-31

    One of the diagnostic technique periodically used in Nuclear Medicine is the angiographic studi e, employee for detect cardiovascular diseases. The radiopharmaceutical more used in the angiographic ones is 99mTc. Between thetopics described in the present work it find: myocardial infarction, radiopharmaceuticals classification for cardiac studies, labelled proceedings, cardiovascular diseases.

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

    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…

  3. Optimization and improvement of the technical specifications for Santa Maria de Garona and Cofrentes nuclear power plants; Optimizacion y mejora de las especificaciones tecnicas de funcionamiento para las centrales de Santa Maria de Garona y Cofrentes

    Norte Gomez, M D [Empresarios Agrupados, A.I.E., Madrid (Spain); Alcantud, F [Iberdrola C.N., Cofrentes, (Spain); Hoyo, C del [Nuclenor C.N., Santa Maria de Garona (Spain)

    1993-12-15

    Technical Specifications (TS) form one of the basic documents necessary for licensing nuclear power plants and are required by the Government in accordance with Article 26 of the Regulation for Nuclear and Radioactive Facilities. They contain specific plant characteristics and operating limits to provide adequate protection for the safety and health of operators and the general public. For operator actuation, TS include all the surveillance requirements and limiting operating conditions (operation at full power, startup, hot and cold shutdown, and refueling outage) of safety-related systems. They also include the conventional support systems which are necessary to keep the plant in a safe operating conditioner to bring it to safe shutdown in the event of incidents or hypothetical accidents. Because of the large volume of information contained in the TS, the NRC and American utility owners began to simplify and improve the initial standard TS, which has given way to the development of a TS Optimization Program in the USA under the auspices of the NRC. Empresarios Agrupados has been contracted by the BWR Spanish Owners' Group (GPE-BWR) to develop optimized TS for the Santa Maria de Garona and Cofrentes Nuclear Power Plants. The optimized and improved TS are simplified versions of the current ones and facilitate the work of plant operators. They help to prevent risks, and reduce the number of potential transients caused by the large number of tests required by current TS. Plant operational safety is enhanced and higher effective operation is achieved. The GPE-BWR has submitted the first part of the optimized TS with their corresponding Bases to the Spanish Nuclear Council (CSN), for comment and subsequent approval. Once the TS are approved by the Spanish Nuclear Council, the operators of the Santa Maria de Garona and Cofrentes Nuclear Power Plants will be given a training and adaptation course prior to their implementation. (author)

  4. Central eastern Europe approach to the security over nuclear materials

    Smagala, G.

    2002-01-01

    Full text: This paper presents an overview of the national approaches to physical protection of nuclear materials in Central Eastern Europe (CEE), with an emphasis on Poland. Soviet influence in the past led to inadequate safety culture in nuclear activities and insufficient security of nuclear materials and facilities in the region. In the centralized economies all aspects of nuclear activities, including ownership of the nuclear facilities, were the responsibility of the state with no clear separation between regulating and promoting functions. During the last decade a significant progress has been made in the region to clean up the legacy of the past and to improve practices in physical protection of nuclear materials. The countries of Central Eastern Europe have had many similar deficiencies in nuclear field and problems to overcome, but cannot be viewed as a uniform block. There are local variations within the region in a size of nuclear activities, formulated respective regulations and adopted measures to secure nuclear materials and facilities. Nevertheless, all twelve nations, with nuclear reactors and without nuclear facilities, have joined the convention on the physical protection of nuclear material and most of them declare that they have followed the IAEA recommendations INFCIRC/225/Rev.4 to elaborate and implement their physical protection systems of nuclear materials and facilities. The largest request for an international advisory mission (IPPAS) to review states' physical protection systems and to address needs for improvement was received from the countries of Central Eastern Europe. Poland belongs to the beneficiaries where the IPPAS mission and later follow-up consultations resulted in physical protection upgrade of the research reactor under the IAEA/US/UK technical assistance project. A powerful incentive to the progress made in a number of CEE countries was the goal of accession to the European Union. The physical protection of nuclear

  5. Jose Cabrera NPP; Central Nuclear Jose Cabrera

    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.

  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

    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. 30 years of Central Institute for Nuclear Research at Rossendorf

    Scheler, W.; Flach, G.; Hennig, K.; Collatz, S.; Muenze, R.; Baldeweg, F.

    1986-10-01

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

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

    1976-01-01

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

  9. Nuclear Power in South-Central Brazil

    Cintra do Prado, L.

    1966-01-01

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

  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

    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. 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

    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)

  12. Nuclear spin noise in the central spin model

    Fröhling, Nina; Anders, Frithjof B.; Glazov, Mikhail

    2018-05-01

    We study theoretically the fluctuations of the nuclear spins in quantum dots employing the central spin model which accounts for the hyperfine interaction of the nuclei with the electron spin. These fluctuations are calculated both with an analytical approach using homogeneous hyperfine couplings (box model) and with a numerical simulation using a distribution of hyperfine coupling constants. The approaches are in good agreement. The box model serves as a benchmark with low computational cost that explains the basic features of the nuclear spin noise well. We also demonstrate that the nuclear spin noise spectra comprise a two-peak structure centered at the nuclear Zeeman frequency in high magnetic fields with the shape of the spectrum controlled by the distribution of the hyperfine constants. This allows for direct access to this distribution function through nuclear spin noise spectroscopy.

  13. New wireless system for fire protection (detection) during dismantling works in Jose Cabrera NPP (CNJC); Nuevo Sistema Inalámbrico de detección contraincendios para el desmantelamiento de a Central Nuclear José Cabrera

    Núñez, F.J.; Gómez Rodríguez, C.A.

    2016-07-01

    José Cabrera Nuclear Power Plant is currently in an advanced stage in the process of dismantling and decommissioning. As part of that process, it is necessary to remove the maximum possible interference with operating systems, which are still needed to support the works ongoing or to ensure the safety. With that goal it has been installed a new wireless fire detection system that substitutes the old wired one. The coverage of this new system was initially focused on the containment building, establishing a first phase of analysis of signal coverage, and location of the different components in the building and a second phase of implementation (monitoring and testing) to demonstrate the reliability and robustness of the system in a building with such a complex geometry configuration. Currently the WIFI system is in operation, providing coverage to the containment building and other external facilities (laundry, control room, etc) that have been incorporated to support the process of dismantling.

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

    2009-06-01

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

  15. The innovation of nuclear science and technology supporting for the central plains economic zone construction

    Yang Xiaowei

    2014-01-01

    This paper discusses the nuclear agronomy support for the central plains economic zone construction, radiation chemical new material support for the central plains economic zone construction, nuclear medical support for the central plains economic zone construction, nuclear instrument and meter industry support for the central plains economic zone construction and the development trend of related disciplines. (author)

  16. Accounting for and control of nuclear material at the Central Institute of Nuclear Research, Rossendorf

    Heidel, S.; Rossbander, W.; Helming, M.

    1983-01-01

    A survey is given of the system of accounting for and control of nuclear material at the Central Institute for Nuclear Research, Rossendorf. It includes 3 material balance areas. Control is implemented at both the institute and the MBA levels on the basis of concepts which are coordinated with the national control authority of the IAEA. The system applied enables national and international nuclear material control to be carried out effectively and economically at a minimum of interference with operational procedures. (author)

  17. 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

    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)

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

    Koelzer, W.

    1993-05-01

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

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

    Stritar, A; Jencic, I [eds.; Nuclear Society of Slovenia (Slovenia)

    1996-12-31

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

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

    Stritar, A.; Jencic, I.

    1995-01-01

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

  1. Welding with the TIG automatic process of the end fittings for the execution of the Embalse nuclear power plant fuel channel rechange; Soldadura con proceso TIG automatico de los accesorios extremos (end fitting) para la ejecucion de un recambio de canal de combustible en el reactor de la Central Nuclear Embalse

    Suarez, P O

    1991-12-31

    The present work describes the methodology for the cutting of the existing welding and subsequent welding applied by the TIG process of the coupling composed by the shroud ring and the end fitting ring from one of Embalse nuclear power plant`s fuel channels. The replacement will be previously determined by the SLAR-ETTE mechanism where a displacement operated among the Gartner Spring rings, the pressure tubes are separated from the Calandria tubes. The welding to be carried out has the function of stamping the CO{sub 2} annular gas (thermal insulator) circulating between the pressure tube and the Calandria one during the functioning of the plant. (Author). [Espanol] El presente trabajo describe la metodologia de corte de la soldadura existente y la posterior soldadura aplicada mediante proceso TIG de la junta compuesta por el aro de fuelle y el anillo del `end fitting`, de uno de los canales de combustibles del reactor de la Central Nuclear Embalse. El reemplazo, se determinara previamente mediante el mecanismo de SLAR-ETTE con lo cual se observara el desplazamiento operado entre los anillos garten spring que separan los tubos de presion de los tubos de calandria. La soldadura a efectuar cumple la funcion de sellar el gas anular CO{sub 2} (aislante termico) circulante entre el tubo de presion y el tubo de calandria durante el funcionamiento de la planta. (Autor).

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

    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)

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

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

    1984-05-01

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

  5. Nuclear legislation in central and eastern europe and the NIS

    2003-01-01

    This study presents the current state of legislation and regulations governing the peaceful uses of nuclear energy in the central and eastern European countries (CEEC) and the New Independent States (NIS). It also contains information on the national bodies responsible for the regulation and control of nuclear energy. The nuclear energy sector has not escaped from the changes that have affected the political, economic and social climates over the past fifteen years. Under the former socialist regime, activities in this field came within the sole remit of the State administration. In the legal area, it had not been deemed necessary in most of these countries to enact laws guaranteeing democratic control of electronuclear programmes and establishing a clear distinction between activities promoting this source of energy and regulatory control, while ensuring that safety imperatives take priority over all other considerations. With the arrival of new political forces came the will to remedy this situation promptly by creating new regulatory structures and drafting legislative texts based on those used in western countries. This evolution was all the more necessary given that, at the same time, the new policy of accountability had revealed safety defects in numerous nuclear installations in these countries, thus rendering international assistance indispensable. From the legal point of view, the outcome of these years of effort is remarkably positive: almost all countries of Eastern Europe pursuing electronuclear programmes have established institutions capable of exercising efficient control over nuclear power plants and other installations. Accession to the international conventions which form the backbone of nuclear law has become widespread. Modern legislation is henceforth in place in almost all of these states. (author)

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

    Koelzer, W.

    1994-04-01

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

  7. Centralized operation and monitoring system for nuclear power plants

    Kudo, Mitsuru; Sato, Hideyuki; Murata, Fumio

    1988-01-01

    According to the prospect of long term energy demand, in 2000, the nuclear power generation facilities in Japan are expected to take 15.9% of the total energy demand. From this fact, it is an important subject to supply nuclear power more stably, and in the field of instrumentation and control, many researches and developments and the incessant effort of improvement have been continued. In the central operation and monitoring system which is the center of the stable operation of nuclear power plants, the man-machine technology aiding operators by electronic and computer application technologies has been positively developed and applied. It is considered that hereafter, for the purpose of rationally heightening the operation reliability of the plants, the high quality man-machine system freely using the most advanced technologies such as high reliability digital technology, optical information transmission, knowledge engineering and so on is developed and applied. The technical trend of operation and monitoring system, the concept of heightening operation and monitoring capability, the upgrading of operation and monitoring system, and the latest operation, monitoring and control systems for nuclear power plants and waste treatment facilities are described. (K.I.)

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

    2000-01-01

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

  9. Proceedings of the 2000 International Conference on Nuclear Energy in Central Europe

    Mavko, B.; Cizelj, L.; Kovac, M.

    2000-01-01

    International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 108 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: thermal hydraulics, severe accidents, probabilistic safety assessment (PSA), nuclear waste, safety analyses, nuclear power plant operation, structural integrity and aging, nuclear energy and public, other related topics, research reactors, education and training and Monte Carlo transport calculations

  10. Nuclear instrumentation for research reactors; Instrumentacion nuclear para reactores nucleares de investigacion

    Hofer, Carlos G.; Pita, Antonio; Verrastro, Claudio A.; Maino, Eduardo J. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Unidad de Actividades de Reactores y Centrales Nucleares. Sector Instrumentacion y Control

    1997-10-01

    The nuclear instrumentation for research reactors in Argentina was developed in 70`. A gradual modernization of all the nuclear instrumentation is planned. It includes start-up and power range instrumentation, as well as field monitors, clamp, scram and rod movement control logic. The new instrumentation is linked to a computer network, based on real time operating system for data acquisition, display and logging. This paper describes the modules and whole system aspects. (author). 2 refs.

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

    Myers, L.C.

    1993-11-01

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

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

    Widell, C.-O.

    1978-06-01

    The central dose register for the nuclear industry in Sweden has been in operation since 1974. The system contains today about 18 000 persons in the register. The dose information is stored on discs on a CDC Cyber 172 computer and all information to and from the system is handled by terminals at the different nuclear sites. The terminals are connected to the computer by normal telephone lines. Most doses are recorded on TLD. The data from the TLD readers is automatically transferred to the computer via punched tape and the local computer terminal. The dose results are stored under the person's unique social security number. It is also possible to use social security number systems of other countries. The dose register system also supervises the condition of the readers and their calibration by circulation dosimeters which have been given a reference dose. The information from the system can be obtained on many different types of lists, for example, annual, quarterly, monthly, departementally, personal history, job number. (author)

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

    Myers, L C [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

    1993-11-01

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

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

    Matsumoto, Masaru

    1977-01-01

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

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

    Gortnar, O; Stritar, A [Nuclear Society of Slovenia (Slovenia)

    1999-07-01

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

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

    Gortnar, O.; Stritar, A.

    1999-01-01

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

  17. Nuclear and radiation safety of the centralized spent fuel storage facility in Ukraine

    Grigorash, O.V.; Dibach, O.M.; Panchenko, A.V.; Shugajlo, Ol-r P.; Kovbasenko, YU.P.; Vishemyirskij, M.P.; Bogorad, V.I.; Belykh, D.O.; Shendrovich, V.Ya.

    2017-01-01

    The paper presents the analysis of ensuring nuclear and radiation safety in the management of spent nuclear fuel at the Centralized SFSF and activities planned for Centralized SFSF life cycle stages. There are results of comparing requirements of U.S. regulatory documents used by the HOLTEC Company to design Centralized SFSF equipment staff with relevant requirements of Ukrainian regulations, results based on analysis of the most important factors of Centralized SFSF safety (strength and reliability, nuclear safety, thermal regimes and biological protection) and verified expert calculations of the SSTC NRS. The paper includes issues to be considered in further implementation of Centralized SFSF project.

  18. 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

    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)

  19. 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

    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)

  20. Centralized digital computer control of a research nuclear reactor

    Crawford, K.C.

    1987-01-01

    A hardware and software design for the centralized control of a research nuclear reactor by a digital computer are presented, as well as an investigation of automatic-feedback control. Current reactor-control philosophies including redundancy, inherent safety in failure, and conservative-yet-operational scram initiation were used as the bases of the design. The control philosophies were applied to the power-monitoring system, the fuel-temperature monitoring system, the area-radiation monitoring system, and the overall system interaction. Unlike the single-function analog computers currently used to control research and commercial reactors, this system will be driven by a multifunction digital computer. Specifically, the system will perform control-rod movements to conform with operator requests, automatically log the required physical parameters during reactor operation, perform the required system tests, and monitor facility safety and security. Reactor power control is based on signals received from ion chambers located near the reactor core. Absorber-rod movements are made to control the rate of power increase or decrease during power changes and to control the power level during steady-state operation. Additionally, the system incorporates a rudimentary level of artificial intelligence

  1. Uso de detectores de neutrinos para el monitoreo de reactores nucleares Uso de detectores de neutrinos para el monitoreo de reactores nucleares

    Gerardo Moreno

    2012-02-01

    Full Text Available Se estudia la factibilidad del uso de los detectores de antineutrinos para el monitoreo de reactores nucleares. Usando un modelo sencillo de cascada de fisión a dos componentes, se ilustra la dependencia del número de antineutrinos detectados a una distancia L del reactor según la composición nuclear del combustible. Se explica el principio de detección de neutrinos de reactores en base al decaimiento beta inverso y se describe como los detectores de neutrinos pueden emplearse para el monitoreo de la producción de materiales fisibles en el reactor. Se comenta como generalizar este análisis al caso real de un reactor nuclear in situ y uno de los principales experimentos internacionales dedicados a este propósito. We study the feasibility to use antineutrinos detectors for monitoring of nuclear reactors. Using a simple model of fission shower with two components, we illustrate how the numbers of antineutrinos detected at a distance L from the reactor depend on the composition of the nuclear combustible. We explain the principles of reactor neutrino detection using inverse beta decays and we describe how neutrinos detectors can be used for monitoring the production of fissile materials within the reactors. We comment how to generalize this analysis to the realistic case of a nuclear reactor in situ and one of the main international experiments dedicated to study the use of neutrinos detectors as nuclear safeguards.

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

    Jencic, I.; Glumac, B.

    2001-01-01

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

  3. 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

    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.

  4. 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

    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)

  5. CENTRAL NUCLEAR ELECTRIC, A FUTURE OF ROMANIAN ENERGY

    Gabriel I. NĂSTASE

    2010-05-01

    Full Text Available Official statistics show the year increasing the share of electricity produced in nuclear power plants. The most developed nuclear energy programs are: the United States, France, Japan, Germany and Canada. Although Romania was among the first countries in Eastern Europe that had a nuclear research program, switching to nuclear power reactors has been extremely difficult and slow. The implications of this decisionmaking process were the first political and then economic. There were a series of oscillations between Wer system offered by the USSR and the CANDU-PHWR supplied by Canada. Considering nuclear reactors Wer insufficiently protected against a nuclear accident, and the total requested by the former Soviet Union on the nuclear fuel cycle, the decision of us have opted for CANDU reactor, fueled with natural uranium, moderated and cooled with heavy water.

  6. Safeguards at the Central Institute for Nuclear Research at Rossendorf/GDR

    Helming, M.; Rehak, W.; Schillert, B.

    1989-01-01

    Experience in the implementation of domestic and international safeguards at the Central Institute for Nuclear Research at Rossendorf is reported covering the following topics: overview of the main nuclear installations belonging to the Institute; structure of its material balance areas; responsibilities for the different aspects of accounting for and control of nuclear material at facility level; the various types of nuclear materials handled and their flow, accessibility and strategic significance; the assessment of IAEA safeguards effectiveness. 2 tabs., 2 figs. (author)

  7. The Staffing of Central Electricity Generating Board Nuclear Power Stations; Organigramme des centrales nucleaires du central electricity generating board; Politika v oblasti kadrov na atomnykh ehlektrostantsiyakh CEGB; El personal de las plantas nucleoelectricas de la central electricity generating board.

    Bartlett, J. S.; Shepherd, G. T. [Central Electricity Generating Board, Western Division, Bristol (United Kingdom)

    1963-10-15

    An account is given of the staffing requirements and organization at a CEBG nuclear power station. The training of staff and licensing requirements for reactoroperating staff are discussed. Experience gained to data of the outcome of pre-operating training and detailed planning in the operational sphere is given. (author) [French] Le memoire donne un apercu de l'organigramme d'une centrale nucleaire du CEGB et des conditions auxquelles doit satisfaire le personnel (formation, qualifications requises pour la fonction d'operateur). Il rend compte egalement de l'experience acquise a ce jour quant a l'interet qu'il y a a former le personnel au prealable et a etablir des plans d'operation detailles. (author) [Spanish] La memoria informa sobre la organizacion de las centrales nucleoelectricas de la CEGB y sobre la plantilla de personal que estas requieren. Discute la formacion del personal y los requisitos para obtener la licencia de operador de reactores. Describe la experiencia adquirida hasta el presente en materia de formacion previa del personal y de organizacion detallada de las operaciones. (author) [Russian] Daetsya otchet o trebovaniyakh, pred{sup y}avlyaemykh k personalu, i organizatsiya nabora personala na atomnykh ehlektrostantsiyakh Tsentral'nogo upravleniya proizvodstva ehlektroehnergii (CEGB). Obsuzhdayutsya voprosy podgotovki personala i normativnykh trebovanij, pred{sup y}avlyaemykh k ehkspluatatsionnomu personalu. Izlagaetsya opyt, nakoplennyj k nastoyashchemu vremeni v rezul'tate osushchestvleniya predehkspluatatsionnoj podgotovki i podrobnogo planirovaniya v usloviyakh ehkspluatatsii. (author)

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

    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.

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

    Duran, Felicia Angelica; Waymire, Russell L.

    2013-01-01

    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.

  10. 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

    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)

  11. First-order effects of a nuclear moratorium in Central Europe

    Messner, S.; Strubegger, M.

    1986-12-01

    An energy supply model developed at IIASA previously is used to investigate the consequences of a hypothetical nuclear power phaseout in Central Europe. It is assumed that no new nuclear power plants will be built in Central Europe after 1990 but the existing ones will be used for a planned lifetime of 25 years. Energy-specific consequences, import dependence, emissions, energy prices and investments from the energy sector are considered. (G.Q.)

  12. Collective phenomena in non-central nuclear collisions

    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.

  13. Collective phenomena in non-central nuclear collisions

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

    2008-01-01

    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

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

    1979-09-01

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

  15. Behavioral Determinants of Russian Nuclear State-Owned Enterprises in Central and Eastern European Region

    Vlcek, Tomas; Jirusek, Martin

    2015-01-01

    Rosatom State Nuclear Corporation play a substantial role in the energy sector of the Central and Eastern European region and the behavioral characteristics of the company forms the basis of this article. Rosatom is positioned as the dominant provider of nuclear technology and fuel supplies to the region, in large part stemming from the Soviet legacy in CEE countries. Compounding this challenge, nuclear energy is one of the major sources of power generation in CEE. Given the long-time, near m...

  16. Central Scientific and Research Institute of Nuclear Information as the branch centre of information on nuclear science and engineering

    Arkhangel'skij, I.A.; Sokolov, D.D.; Kalinin, V.F.; Nikiforov, V.S.

    1982-01-01

    The main tasks are considered in the scope of the Central Scientific-Research Institute for Information and Technological and Economic Studies on Nuclear Science and Technology. (TsNIIAtominform). The institute coordinates scientific research and information activity of information agencies of all the USSR organizations engaged in nuclear science and technology, excercises a centralized completion of their libraries, develops and puts into practice the most progressive methods for the information servicing. The institute is a national INIS center of the USSR. Here a system for the automatic information dissemination has been successfully elaborated and employed. Much of the institute activity is given to the estimation and analysis of information and to the determination of tendencies in the nuclear science and technology development. A conclusion is drawn to the effect that TsNIIAtominform, within 15 years of its existence, has formed as a center ensuring functioning of the system of scientific and technical information on nuclear science and technology

  17. Current experience with central-station nuclear cogeneration plants

    1981-10-01

    In considering the potential of the HTGR for nuclear cogeneration, a logical element for investigation is the recent history of nuclear cogeneration experience. Little is found in recent literature; however, the twin nuclear cogeneration plant at Midland is nearing completion and this milestone will no doubt be the basis for a number of reports on the unique cogeneration facility and operating experiences with it. Less well known in the US is the Bruce Nuclear Power Development in Ontario, Canada. Originally designed to cogenerate steam for heavy water production, the Bruce facility is the focus of a major initiative to create an energy park on the shores of Lake Huron. To obtain an improved understanding of the status and implications of current nuclear cogeneration experience, GCRA representatives visited the Ontario Hydro offices in Toronto and subsequently toured the Midland site near Midland, Michigan. The primary purpose of this report is to summarize the results of those visits and to develop a series of conclusions regarding the implications for HTGR cogeneration concepts

  18. Dangerous liaisons: Western involvement in the nuclear power industry of central and eastern Europe

    1992-12-01

    The state of the nuclear industry in central and eastern Europe is an issue of global concern. However, despite all the political talk and corporate hype since the collapse of communist regimes in the region, this study demonstrates that little has so far been done to change the situation. Moreover, the limited level of finance and support which has been offered has tended to support the expansion of nuclear power programmes in central and eastern Europe, rather than address immediately safety concerns relating to existing nuclear reactors and develop more environmentally acceptable and economically efficient energy systems. (author)

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

    Buglova, E.; Crick, M.; Reed, J.; Winkler, G. L.; Martincic, R.

    2000-01-01

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

  20. Nuclear DNA content variation among central European Koeleria taxa

    Pečinka, A.; Suchánková, Pavla; Lysák, Martin; Trávníček, B.; Doležel, Jaroslav

    2006-01-01

    Roč. 98, - (2006), s. 117-122 ISSN 0305-7364 R&D Projects: GA MŠk(CZ) LC06004 Institutional research plan: CEZ:AV0Z50380511 Keywords : Chromosome number * nuclear DNA content * flow cytometry Subject RIV: EB - Genetics ; Molecular Biology Impact factor: 2.448, year: 2006

  1. Nuclear magnetic resonance imaging of the central nervous system

    Knaap, M.S. van der; Valk, J.

    1989-01-01

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

  2. Undergraduate teaching of nuclear medicine: a comparison between Central and Eastern Europe and European Union countries

    Lass, P.; Scheffler, J.; Bandurski, T.

    2003-01-01

    This paper overviews the curricula of nuclear medicine (NM) undergraduate training in 34 Central and Eastern European (CEE) and 37 European Union (EU) medical faculties. The data show enormous variation in the number of hours devoted to nuclear medicine, varying between 1-2 to 40 hours and highly differentiated concepts/ideas of nuclear medicine training in particular countries. In most EU countries this teaching is integrated with that of radiology or clinical modules, also with training in clinical physiology. In many CEE countries teaching and testing of NM are independent, although integration with other teaching modules is frequent. The paper discusses the differences in particular approaches to nuclear medicine teaching. (author)

  3. AP1000, a nuclear central of advanced design

    Hernandez M, N.; Viais J, J.

    2005-01-01

    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)

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

    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

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

    Ek, P.; Andersson, Sarmite; Wredberg, L.

    2000-06-01

    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

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

    Paulin, Ph.

    2006-01-01

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

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

    Souza, Jair Albo Marques de

    1993-12-31

    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.

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

    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.

  9. Evaluation of seismic input for nuclear power plants; Evaluacion del input sismico para plantas nucleares

    Saragoni, G. R.

    2012-07-01

    The accident that affected the Fukushima Daiichi nuclear power plant on March 11th 2011 was the result of the Tohoku earthquake (Japan), the fifth largest ever registered in the world. The characteristics of the event will be a subject for study by the nuclear and seismology communities for many years to come. (Author)

  10. Staff Organization in Nuclear Power Stations; Organisation du personnel des centrales nucleaires; Organizatsiya personala na atomnykh ehlektrostantsiyakh; Organizacion del personal de las centrales nucleares

    Scuricini, G. B. [Comitato Nazionale Energia Nucleare, Roma (Italy)

    1963-10-15

    This paper deals with the organization of operating and maintenance staff at nuclear power stations in Italy and manpower variations, either because the plants themselves differ or are organized in some special way. Staff doing jobs for which a specific training is required are given special consideration in the paper. (author) [French] Dans le memoire, on examine l'organisation du personnel d'exploitation et d'entretien des centrales nucleaires italiennes et les differences existant dans les effectifs, differences dues soit aux caracteristiques des centrales memes, soit aux particularites d'organisation des entreprises. Le personnel charge de fonctions determinees pour lesquelles un entrainement special est requis, fait l'objet d'une attention particuliere. (author) [Spanish] En la memoria se examina la organizacion del personal de explotacion y conservacion de las centrales nucleares italianas y las diferencias que existen entre sus efectivos, diferencias que se deben a las caracteristicas de las mismas centrales o a las particularidades de organizacion de las empresas. El autor dedica especial atencion al personal encargado de funciones que requieren una formacion profesional especial. (author) [Russian] Issleduyutsya voprosy organizatsii personala, zanimayushchegosya ehkspluatatsiej ital'yanskikh atomnykh ehlektrostantsij i ukhodom za nimi, a takkhe razlichiya v sostave personala, vytekayushchie libo iz kharakternykh osobennostej samikh stantsij, libo iz osobennostej organizatsii predpriyatij. Osoboe vnimanie udelyaetsya personalu, kotoromu porucheny opredelennye funktsii, trebuyushchie spetsial'noj pod go tovki. (author)

  11. Sea transport of used nuclear fuel and radiactive disposals to a Swedish central store

    1977-10-01

    Sea transport of used nuclear fuel and radioactive disposals to a Swedish central store. A vessel for transporting used nuclear fuel and radioactive disposals from the power stations at Ringhals, Barsebaeck, Simpevarp and Forsmark to a central store has been projected. Safety aspects, technical and economical aspects have been taken into consideration with regard to the actual volume of goods to be transported. Three different types of vessels are presented and a specification is given for the main alternative. A safety study of the main alternative is shown, regarding collision safety, fire risks and fire extinguishing equipment. (author)

  12. Annual report 89. Central Bureau for nuclear measurements

    1990-01-01

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

  13. Possible uses of nuclear energy in central heating of Ankara

    Agirsoy, L.

    1987-01-01

    In this master thesis, a study was carried out for the district heating of the plateau region where the population and air pollution densities are the highest. First the heat requirements of differently populated regions were calculated, then by taking different temperature decreases of hot water in buildings; flow rates, pipe diameters and pressure losses corres-ponding to these temperature decreases were obtained. An optimum division of total heat load as peak and base loads was studied and it was seen that the unit heat cost could be lowered by employing two stations for the heating of buildings. The optimum division and unit heat cost calculations were carried out for various alternative heating systems and it was seen that nuclear combined cycle base-load station and a peak-load station operating on fuel-oil was obtained to be the most advantageous system from an economic point of view. (author)

  14. Sharing of responsibilities between central and local authorities with regard to the licensing of nuclear installations

    Peltzer, P.

    1986-01-01

    With regard to sharing of responsibility in the field of nuclear licensing between central and local authorities, the Belgian State has entered into a new phase of regionalisation since the enactment of the law of August 8, 1980. This might entail a conflict of competence in case of the licensing of nuclear power plants. A general survey of foreign legislations seems to indicate that a similar risk also exists in other countries. (CW) [de

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

    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)

  16. Central depression in nucleonic densities: Trend analysis in the nuclear density functional theory approach

    Schuetrumpf, B.; Nazarewicz, W.; Reinhard, P.-G.

    2017-08-01

    Background: The central depression of nucleonic density, i.e., a reduction of density in the nuclear interior, has been attributed to many factors. For instance, bubble structures in superheavy nuclei are believed to be due to the electrostatic repulsion. In light nuclei, the mechanism behind the density reduction in the interior has been discussed in terms of shell effects associated with occupations of s orbits. Purpose: The main objective of this work is to reveal mechanisms behind the formation of central depression in nucleonic densities in light and heavy nuclei. To this end, we introduce several measures of the internal nucleonic density. Through the statistical analysis, we study the information content of these measures with respect to nuclear matter properties. Method: We apply nuclear density functional theory with Skyrme functionals. Using the statistical tools of linear least square regression, we inspect correlations between various measures of central depression and model parameters, including nuclear matter properties. We study bivariate correlations with selected quantities as well as multiple correlations with groups of parameters. Detailed correlation analysis is carried out for 34Si for which a bubble structure has been reported recently, 48Ca, and N =82 , 126, and 184 isotonic chains. Results: We show that the central depression in medium-mass nuclei is very sensitive to shell effects, whereas for superheavy systems it is firmly driven by the electrostatic repulsion. An appreciable semibubble structure in proton density is predicted for 294Og, which is currently the heaviest nucleus known experimentally. Conclusion: Our correlation analysis reveals that the central density indicators in nuclei below 208Pb carry little information on parameters of nuclear matter; they are predominantly driven by shell structure. On the other hand, in the superheavy nuclei there exists a clear relationship between the central nucleonic density and symmetry energy.

  17. Cáncer y mitocondria: un aspecto central para el desarrollo y crecimiento tumoral

    Sofía Isabel Freyre-Bernal

    2017-04-01

    Full Text Available Se sabe que las células tumorales consumen más glucosa que las no tumorales. Además, las células tumorales expresan isoformas embrionarias de enzimas para la glucólisis, permitiendo su mayor actividad y obtención de energía en los diversos procesos cancerígenos. Algunos autores han sugerido que la hipoxia del tumor actúa como regulador del metabolismo energético y que puede redirigir a las células tumorales a utilizar la glucólisis como fuente de provisión de ATP cuando hay limitación de oxígeno. Otros autores sugieren que ese es el resultado de mutaciones en oncogenes, genes supresores y enzimas de la vía glucolítica o del metabolismo oxidativo mitocondrial (Myc, Akt, p53, HIF1-α. La aplicación de la tomografía de emisión de positrones (PET en los servicios de medicina nuclear y radiología ha permitido usar la mitocondria como un organelo para el diagnóstico de cáncer cuantificando una mayor captación de glucosa por las células tumorales respecto del tejido no tumoral adyacente, mediante el uso del análogo radioactivo no metabolizable de la glucosa (18FDG, 18F-2-desoxiglucosa. Así pues, las investigaciones se han centrado en el metabolismo alterado como parte del desarrollo y crecimiento tumoral con el objetivo de inhibir la progresión a la metástasis de esta patología en los pacientes que no se pueden recuperar recibiendo tratamiento con quimioterapia y la radioterapia. El objetivo de esta revisión documental consiste en resaltar las generalidades e importancia de las mitocondrias en los mecanismos que promueven el cáncer.

  18. Termodinámica Utilitaria (para Centrales Termoeléctricas

    A Calvo

    2011-03-01

    Full Text Available Cuando se necesita profundizar en una asignatura terminal de una disciplina y se carece de tiempo de docencia directa,muchas veces se aumenta la cantidad de materia a estudiar individualmente, Pero cuando este material a su vez necesitade un análisis previo del profesor, es posible lograr un incremento de tiempo a partir de la reorganización de la imparticiónde la disciplina base (fundamentación teórica. La reorganización se basa en la utilización de la aplicación para ladeducción de las leyes generales. Se gana entonces en tiempo de familiarización y profundización teórica específica,con la aplicación específica deseada, permitiendo el incremento en información que facilita abordar situaciones ycálculos más complejos y una participación más amplia del especialista. El nivel teórico de la asignatura base semantiene al generalizar las leyes deducidas en la aplicación (perteneciente a la asignatura terminal que sirvió de puntode partida La introducción del concepto Termodinámica utilitaria (para Centrales Termoeléctricas, permite profundizaren temas que anteriormente era imposible abordar y que requieren de tratamiento adecuado en actividades lectivas.  When is needed deepen in a terminal subject of a discipline and teaching lecture time lacks, many times is increasedthe quantity of matter assigned to individually study. But when the material needs of the teacher previous analysis, itis possible to achieve an increment of time starting from the reorganization of the preceding subject (theoreticalfoundation. The reorganization is based on the deduction of the general laws using application examples. Then it iswon the time of familiarize (acquaint and the specific theoretical deepening with the wanted specific application,allowing the increment in information facilitating the approach to the more complex situations and calculations andthen a wider specialist participation. The theoretical level of the preceding subject

  19. 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

    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.

  20. 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

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

    1999-12-31

    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.

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

    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)

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

    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)

  3. Propuesta para la gestión de mantenimiento de la Central Hidroeléctrica Ocaña

    Gómez Muñoz, Geovanny Patricio; Méndez Peñaloza, Gino Fabricio

    2011-01-01

    Hoy en día las Centrales de Generación Eléctrica necesitan contar con un eficiente programa de mantenimiento, 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 permitirá mejorar la gestión del mantenimiento en la Central. Con el contenido de este proyecto y como resultado es un plan de mantenimiento concreto que permite organizar de manera eficiente...

  4. The risk of nuclear power plants for man. O risco das usinas nucleares para o homem

    Freire-Maia, A [UNESP, Botucatu, SP (Brazil)

    1981-01-01

    The author analyzes the risk of nuclear power plants for man with respect to biological radiation effects, sources, level and radiation effects in man. He uses the three Mile Island accident as lesson in order to illustrate a situation potentially dangerous. (C.M.).

  5. 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)

    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)

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

    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.

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

    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)

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

    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)

  9. EFFECT OF CENTRAL MASS CONCENTRATION ON THE FORMATION OF NUCLEAR SPIRALS IN BARRED GALAXIES

    Thakur, Parijat; Jiang, I.-G.; Ann, H. B.

    2009-01-01

    We have performed smoothed particle hydrodynamics simulations to study the response of the central kiloparsec region of a gaseous disk to the imposition of nonaxisymmetric bar potentials. The model galaxies are composed of three axisymmetric components (halo, disk, and bulge) and a nonaxisymmetric bar. These components are assumed to be invariant in time in the frame corotating with the bar. The potential of spherical γ-models of Dehnen is adopted for the bulge component whose density varies as r -γ near the center and r -4 at larger radii and, hence, possesses a central density core for γ = 0 and cusps for γ>0. Since the central mass concentration of the model galaxies increases with the cusp parameter γ, we have examined here the effect of the central mass concentration by varying the cusp parameter γ on the mechanism responsible for the formation of the symmetric two-armed nuclear spirals in barred galaxies. Our simulations show that the symmetric two-armed nuclear spirals are formed by hydrodynamic spiral shocks driven by the gravitational torque of the bar for the models with γ = 0 and 0.5. On the other hand, the symmetric two-armed nuclear spirals in the models with γ = 1 and 1.5 are explained by gas density waves. Thus, we conclude that the mechanism responsible for the formation of symmetric two-armed nuclear spirals in barred galaxies changes from hydrodynamic shocks to gas density waves as the central mass concentration increases from γ = 0 to 1.5.

  10. Prospects for a nuclear-weapon-free zone in Central Asia

    Potter, W.C.

    1997-01-01

    This paper examines the concept of a Nuclear-Weapon-Free Zone (NWFZ) as an approach to nuclear nonproliferation with special reference to Central Asia . 20 More specifically, it describes the evolution of a NWFZ in the region, the potential benefits of a zone, the principal obstacles in the path of its implementation, and the practical steps that need to be taken if a NWFZ in Central Asia is to be realized. The paper concludes that a NWFZ in Central Asia, as with prior NWFZ, would likely lead to advances in the application of an important nonproliferation approach. One innovative aspect of the zone in Central Asia might be its treatment of environmental issues. Although it will not be a simple process to rally support from all of the P-5 states for a new NWFZ, all countries of Central Asia - as well as global community of nations - should profit from creation of a zone which reinforces the international nonproliferation regime improves prospects for political and economic stability in a region of growing importance

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

    Leite, Teresa Cristina Sampaio de Barros; Silva, Ilson Peixoto Medeiros da; Jannuzzi, Denise Maria Souza; Higino, Thiago Nunes; Santos, Tatiana Rodrigues dos

    2011-05-01

    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

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

    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

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

    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.

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

    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)

  15. The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

    Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

    2001-07-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

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

    Gustafsson, M.; Webb, G.A.M.; )

    1998-01-01

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

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

    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)

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

    Idrisov, E.A.; Eleukenov, D.Sh.

    1997-01-01

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

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

    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.

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

    Yussup, F.; Ibrahim, M. M.; Soh, S. C.; Hasim, H.; Haris, M. F.; 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

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

    Goetzke, R.E.

    1987-01-01

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

  2. 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

    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)

  3. Asco 2044 nuclear power plant: management system; Central nuclear Asco 2044: sistema de gestion

    Ramos Pellejero, J.L.

    2010-07-01

    Due to their complexity and involvement in safety related matters, Nuclear Power Plants have highly eliable management organisations where safety is top priority. To achive this, there are many elements specific to this type of organisation that are available and which are integrated within a Management System that comprises the necessary meassures to ensure and adequate level of safety in the facility, in such a way that it promotes continual improvement, a strengthening of the safety culture and good results in this field. (Author).

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

    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. Cooperation in peaceful uses of nuclear energy among Turkey, Caucasian and Central Asian countries

    Zafer, A.

    2006-01-01

    Full text: On the first call for expanding peaceful uses of nuclear energy, Turkey was one of the first countries to start activities in the nuclear field. Turkish Atomic Energy Authority (TAEK) was established in 1956 and became the member of the International Atomic Energy Agency (IAEA) established in 1957 by the United Nations for spreading the use of nuclear energy to contribute peace, health and prosperity throughout the world, in the same year. TAEK was established to support, co-ordinate and perform the activities in peaceful uses of nuclear energy and act as a regulatory body and establish cooperation with other countries and international organizations. In the late 1990's, TAEK, besides building cooperation with various countries, has involved in cooperating with related institutes of Azerbaijan, Kazakhstan, Kyrgyzstan and Uzbekistan for establishment of bilateral and multilateral scientific and technical cooperation in peaceful use of nuclear energy and signed protocols with Academy of Science of Azerbaijan, Nuclear Physics Institute of Kazakhstan, National Academy of Science of Kyrgyzstan and Institute of Nuclear Physics of Uzbekistan Academy of Science. Turkey is a candidate state to join the European Union and has already signed Custom Union Agreement, also part of the Eurasia Region. So, there are significant developments in the cultural, social, technical, economical and trade relations owing to our common historical and cultural values with the countries in the region and Central Asia. These protocols enable parties to organize joint projects, conferences, seminars, training programs, establish laboratories for the joint studies and make joint efforts to seek support from their governments and international organizations for these activities. The joint activities carried out mainly are given as follows: Eurasia Conference on Nuclear Science and Its Application - First Conference organized in the year 2000 in Turkey, Second Conference at Almaty? in

  6. 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

    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)

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

    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)

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

    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.

  9. 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)

    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

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

    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.

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

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

    1996-12-31

    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.

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

    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.

  13. Comparison between a finite difference model (PUMA) and a finite element model (DELFIN) for simulation of the reactor of the atomic power plant of Atucha I; Comparacion entre un modelo de diferencias finitas (PUMA) y uno de elementos finitos (DELFIN) para la simulacion del reactor de la CNA-I (central nuclear Atucha-I)

    Grant, C R [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

    1997-12-31

    The reactor code PUMA, developed in CNEA, simulates nuclear reactors discretizing space in finite difference elements. Core representation is performed by means a cylindrical mesh, but the reactor channels are arranged in an hexagonal lattice. That is why a mapping using volume intersections must be used. This spatial treatment is the reason of an overestimation of the control rod reactivity values, which must be adjusted modifying the incremental cross sections. Also, a not very good treatment of the continuity conditions between core and reflector leads to an overestimation of channel power of the peripherical fuel elements between 5 to 8 per cent. Another code, DELFIN, developed also in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and current among elements and a more realistic representation of the hexagonal lattice of the reactor. A comparison between results obtained using both methods in done in this paper. (author). 4 refs., 3 figs.

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

    Wendel, Marcelo

    2010-08-15

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

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

    Pande, Savita

    1998-01-01

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

  16. Flow of ideal fluid through a central region of a nuclear reactor wire-spaced fuel subassembly

    Schmid, J.

    1991-04-01

    The results are given of calculations of the flow of an ideal fluid through the central region of a nuclear reactor wire-spaced fuel subassembly. The computer code used is briefly described. (author). 10 figs., 4 refs

  17. Mixed wastes treatment in Atucha I; Tratamiento de residuos mixtos de la CNA I (central nuclear Atucha I)

    Varani, J L; Comandu, J F [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

    1998-07-01

    una emulsion de limpieza mecanica y lubricantes provenientes de la limpieza de la maquina, portadores de la contaminacion radiactiva. El tratamiento de esta emulsion tuvo como objeto el reciclado de un residuo toxico consistente en el solvente organico componente de la emulsion y la reduccion de volumen de la masa residual. Se realizaron pruebas de laboratorio tendientes a aumentar la fuerza ionica del medio para romper la emulsion. Se probaron distintas sales y temperaturas de trabajo hasta establecer que la combinacion del agregado del 1% de sulfato de sodio y una temperatura de 40 grados C era la optima teniendo en cuenta el equipamiento disponible en la instalacion nuclear y consideraciones de costos. El proceso se efectuo en modo batch y se obtuvieron 3 corrientes residuales, una acuosa que se envio al sistema de tratamiento de aguas residuales de la Central, una organica consistente en hidrocarburos descontaminados aptos para posteriores trabajos de limpieza y una solida con la mayoria de la contaminacion radiactiva, consistente en jabones insolubles que forman parte de las grasas lubricantes. Como resultado del proceso se logro una reduccion de volumen superior al 90% y la separacion del solvente apto para su reutilizacion. (autor)

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

    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. Status of the initiative to create a nuclear-weapon-free space in Central and Eastern Europe

    Sychou, A.

    1997-01-01

    The aims of Belarus proposal for creating the nuclear-weapon-free zone in Central and Eastern Europe which has already been reflected in official documents of the 51st session of the UN General Assembly are described. This could reaffirm the intention of the European States to move towards the final goal of achieving general and complete nuclear disarmament under efficient international control

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

    Ventura, M.

    2006-01-01

    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)

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

    Tomik, L.; Kichev, E.

    2003-01-01

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

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

    Kubota, Ryuji; Satoh, Hiroyuki; Sasajima, Katsuhiro; Kawano, Ryutaro; Shibuya Shinya

    1999-01-01

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

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

    Hendricks, J.R.

    1996-01-01

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

  4. Potencialidad de Cedrela odorata (Meliaceae para estudios dendrocronológicos en la selva central del Perú

    Manuel Jesús Pereyra Espinoza

    2014-08-01

    Full Text Available En este trabajo determinamos el potencial de Cedrela odorata para estudios dendrocronológicos en la Selva Central del Perú. Para ello, analizamos las características anatómicas que definen los anillos de crecimiento, desarrollamos una cronología de ancho de anillos y relacionamos el crecimiento de los árboles con los registros de precipitación. La cronología de ancho de anillos está compuesta por 47 series de 27 árboles y cubre el período 1795-2009. Los anillos están claramente delimitados por porosidad semicircular, asociados a bandas de parénquima marginal y paratraqueal. El crecimiento de los árboles estuvo relacionado con las precipitaciones de la estación lluviosa previa y con las de finales de la estación seca del corriente período de crecimiento. Así mismo, observamos una estrecha relación entre el crecimiento y las precipitaciones totales, considerando el ciclo hidrológico de diciembre a setiembre, para el periodo 1990-2009. Estos resultados indican la influencia de las precipitaciones en el crecimiento radial de C. odorata. La buena discriminación de los anillos anuales, la fuerte relación con la precipitación, el amplio rango de distribución y la longevidad de los árboles, hacen de C. odorata una especie promisoria para estudios dendrocli-matológicos y dendroecológicos en los bosques tropicales y subtropicales de América.

  5. 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

    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.

  6. Reinforcement of planning and response to emergencies inside nuclear power plants; Refuerzo de la planificación y respuesta ante emergencias en el interior de las centrales nucleares

    Cortés, M.A.; Garcés, J.M.; Bolaños, J.; Fernández, J.; Gutiérrez, C.; Pontejo, A.; Rosell, B.

    2015-07-01

    Fukushima Daichi nuclear accident (11th march of 2011) required a rapid and effective response of nuclear industry, in order to guarantee that current safety margins were enough to cope with events like this or even worse. In Europe, stress tests were carried out to comply with that objective, evaluating if every nuclear plant was able to succeed managing design basis accidents or even beyond. Stress-test results were satisfactory, although several areas for improvement where identified. Improvements in emergency response and management have been developed in several phases. First, increasing emergency response capacity by implementing modifications in existing equipment. Later, installing new equipment (generally portable) which would be used in even more degraded conditions. This must be held by the revision of emergency response personnel and their training. Finally, external support has been reinforced to help in longstanding emergencies, with the establishment of CAE (Regional Center), and collaboration protocols with the Army. These actions, supervised and approved by the Regulator Body (CSN) will lead to increase plants safety margins and their emergency response capacities in order to reduce probability and consequences of a nuclear accident to the minimum. [Spanish] El accidente nuclear ocurrido el 11 de marzo de 2011 en Fukushima Daichi requirió de una pronta y efectiva respuesta de la industria nuclear, que garantizase que los márgenes de seguridad eran los adecuados para hacer frente a sucesos de estas características o incluso peores. Con ese objetivo se planteó, a nivel europeo, la realización de unas pruebas de resistencia que valorasen si las centrales podían hacer frente con garantías a una serie de accidentes dentro y más allá de las bases de diseño. Los resultados fueron satisfactorios, si bien se identificaron varios aspectos de mejora. La mejora en la respuesta y gestión de emergencias de las centrales nucleares se ha planteado en

  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

    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. 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

    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)

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

    Getzner, M.

    2003-01-01

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

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

    Scibile, L. [ITER Organization, CS 90 046, St. Paul-lez-Durance, Cedex (France); Ambrosino, G. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); De Tommasi, G., E-mail: detommas@unina.i [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); Pironti, A. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy)

    2010-07-15

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

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

    Scibile, L.; Ambrosino, G.; De Tommasi, G.; Pironti, A.

    2010-01-01

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

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

    Scibile, L. [ITER Organization, 13 - St. Paul lez Durance (France); Ambrosino, G.; De Tommasi, G.; Pironti, A. [Euratom-ENEA-CREATE, Universita di Napoli Federico II, Napoli (Italy)

    2009-07-01

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

  13. Procedures simulation in Nuclear Power Plants (SIMPROC); Codigo para la simulacion de procedimientos humanos en centrales nucleares: SIMPROC

    Izquierdo, J. M.; Hortal, J.; Sanchez, M.; Melendez, E.; Queral, C.; Ibanez, L.; Gil, J.; Fernandez, I.; Murcia, S.; Gomez, J.

    2010-07-01

    SIMPROC, a procedure simulator support in rules, is an Indizen product whose procedure computerization is based in XML. It's a compliment for the traditional methods of procedures evaluation and it's connected to SCAIS (Code System for an Integrate Security Analysis).

  14. Nuclear energy in central and eastern Europe; L'energie nucleaire en Europe centrale et orientale

    Cognet, G.; Billaud, E.; Battista, L.; Pascal, J. [CEA/Ambassade de France a Budapest (Hungary)

    2010-07-15

    Bulgaria, Hungary, Czech Republic, Romania, Slovakia and Slovenia have all nuclear power plants on their soil, their entry to the European Union has counter-balanced the number of member states that are not in favour of nuclear energy. All these countries committed themselves to upgrade their installations to European safety standards. This work is going on and new programs for service life extension and for construction of new units have been launched. All these countries have a strong culture and know-how in nuclear engineering inherited from soviet era. They stay very active in this field, for instance the ALLEGRO project that is carried out by a collaboration between Hungarian, Slovak, Czech research institutes and western partners aims at building the first demonstration plant of the future fourth generation reactor: a fast reactor cooled by gas. The situation of each country plus Croatia (that is a candidate to full E.U. membership) is reviewed. (A.C.)

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

    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)

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

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

    2013-07-01

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

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

    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.

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

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

    2006-02-01

    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

  19. Diffusion tensor analysis with nuclear magnetic resonance in human central nervous system

    Nakayama, Naoki

    1998-01-01

    Nuclear magnetic resonance has been used to measure the diffusivity of water molecules. In central nervous system, anisotropic diffusion, which is characterized by apparent diffusion tensor D app ξ , is thought to be related to neuronal fiber tract orientation. For precise observation of anisotropic diffusion, it is needed to determine the diagonal and off-diagonal elements of D app ξ . Once D app ξ is estimated from a series of diffusion weighted images, a tissue's orthotropic principal axes and diffusivity of each direction are determined from eigenvalues and eigenvectors of D app ξ . There are several methods to represent anisotropic diffusion with D app ξ . Examples are diffusion ellipsoids constructed in each voxel depicting both these principal axes and the mean diffusion length in these directions, trace invariant values and its mapping image, largest eigenvalue, and ratio of largest eigenvalue to the other eigenvalue. In this study, the author investigated practical procedure to analyze diffusion tensor D app ξ using both of spin-echo end echo-planer diffusion weighted imagings with 3-tesla magnetic resonance machine in human brain. The ellipsoid representation provided particularly useful information about microanatomy including neuronal fiber tract orientation and molecular mobility reflective of microstructure. Furthermore, in the lesion of Wallerian degeneration, the loss of anisotropy of local apparent diffusion was observed. It is suggested that the function of axons can be observed via degree of anisotropy of apparent diffusion. Consequently, diffusion tensor analysis is expected to be a powerful, noninvasive method capable of quantitative and functional evaluation of the central nervous system. (author)

  20. The ATC, the centralized temporary storage facility for the spanish nuclear spend fuel; El ATC, la instalación de Almacenamiento Temporal Centralizado de Combustible Nuclear Gastado Español

    González Fernández-Conde, A.; Gónzalez Gandal, R.; Larrosa Peruga, O.; Medinilla Téllez, G.; Navarro Santos, M.

    2016-07-01

    The ATC, strategic project contained in the Sixth Radioactive Waste General Plan approved by the Government in 2006, is the temporary storage facility of centralized nature intended to store the spent nuclear fuel generated by Spanish NPP during their operation life, for other so-called special waste arising either from the ATC operation itself or from NPP dismantling, and for vitrified waste generated as a result of fuel reprocessing from Vandellós 1 NPP. The main functions of the ATC are the reception of transport casks, encapsulation of spent fuel, and storage of such canister in dry vaults with passive cooling by natural convection; and additionally, the temporary storage of storage casks with spent fuel, of other special waste in canisters, and finally of secondary waste generated during the operation of the facility. The facility estimated operation lifetime is 60 years, and its safety structures, systems and components are designed considering the requirements according to the Spanish nuclear regulations and using best international practices. In the detailed design, major Spanish and some foreign nuclear sector engineering companies are taking part. [Spanish] El ATC, proyecto estratégico recogido en el Sexto Plan General de Residuos Radiactivos aprobado por el Gobierno en 2006, es la instalación de almacenamiento temporal de carácter centralizado destinada para el combustible nuclear gastado generado por las centrales nucleares españolas durante su proceso de operación, así como de otros residuos denominados especiales originados por la propia operación o durante el desmantelamiento de las citadas centrales nucleares, así como los residuos vitrificados originados como consecuencia del reproceso del combustible de la central nuclear de Vandellós I. Las principales funciones del ATC son la recepción de los contenedores de transporte, encapsulado del combustible y almacenamiento de dichas cápsulas en bóvedas en seco con refrigeración pasiva por

  1. 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

    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

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

    Gortnar, O.; Stritar, A.

    1999-01-01

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

  3. Simulation of the electric systems of the Laguna Verde nuclear power station; Simulacion de los sistemas electricos de la Central Laguna Verde

    Rodriguez Lozano, Saul; Ruiz Ponce, Gerardo E [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1992-03-01

    In this article, the electric system models of the Laguna Verde Nuclear Power Station (CNLV) simulator, are presented. These models permit the functioning simulation, in the different operation modes of the main generator (Ruiz and Rodriguez 1991a), of the auxiliaries system and of the substation (Ruiz and Rodriguez 1991b), and of the emergency diesel generators system (Ruiz and Rodriguez 1991c). The general characteristics of such systems, considered as the basis to obtain the representative models, which were developed as modules in an independent way to be integrated in the simulator, are also described. [Espanol] En este articulo, se presenta los modelos de los sistemas electricos del simulador de la Central Laguna Verde (CLV). Estos modelos permiten simular el funcionamiento, en los diferentes modos de operacion del generador principal (Ruiz y Rodriguez, 1991a), del sistema de auxiliares y de la subestacion (Ruiz y Rodriguez, 1991b) y del sistema de generadores diesel de emergencia (Ruiz y Rodriguez, 1991c). Asimismo, se describen las caracteristicas generales de tales sistemas, consideradas como la base para obtener los modelos representativos, los cuales fueron desarrollados como modulos en forma independiente para integrarse al simulador.

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

    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)

  5. Ground beetles (Coleoptera, Carabidae of the Hanford Nuclear Site in south-central Washington State

    Chris Looney

    2014-04-01

    Full Text Available In this paper we report on ground beetles (Coleoptera: Carabidae collected from the Hanford Nuclear Reservation and Hanford National Monument (together the Hanford Site, which is located in south-central Washington State. The Site is a relatively undisturbed relict of the shrub-steppe habitat present throughout much of the western Columbia Basin before the westward expansion of the United States. Species, localities, months of capture, and capture method are reported for field work conducted between 1994 and 2002. Most species were collected using pitfall traps, although other capture methods were employed. Trapping results indicate the Hanford Site supports a diverse ground beetle community, with over 90% of the 92 species captured native to North America. Four species collected during the study period are newly recorded for Washington State: Bembidion diligens Casey, Calosoma obsoletum Say, Pseudaptinus rufulus (LeConte, and Stenolophus lineola (Fabricius. Based on these data, the Site maintains a diverse ground beetle fauna and, due to its size and diversity of habitats, is an important repository of shrub-steppe biodiversity.

  6. Ground beetles (Coleoptera, Carabidae) of the Hanford Nuclear Site in south-central Washington State.

    Looney, Chris; Zack, Richard S; Labonte, James R

    2014-01-01

    Carabidae) collected from the Hanford Nuclear Reservation and Hanford National Monument (together the Hanford Site), which is located in south-central Washington State. The Site is a relatively undisturbed relict of the shrub-steppe habitat present throughout much of the western Columbia Basin before the westward expansion of the United States. Species, localities, months of capture, and capture method are reported for field work conducted between 1994 and 2002. Most species were collected using pitfall traps, although other capture methods were employed. Trapping results indicate the Hanford Site supports a diverse ground beetle community, with over 90% of the 92 species captured native to North America. Four species collected during the study period are newly recorded for Washington State: Bembidion diligens Casey, Calosoma obsoletum Say, Pseudaptinus rufulus (LeConte), and Stenolophus lineola (Fabricius). Based on these data, the Site maintains a diverse ground beetle fauna and, due to its size and diversity of habitats, is an important repository of shrub-steppe biodiversity.

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

    Mendoza L, A.; Flores C, E.; Lopez G, C.P.F.

    1995-01-01

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

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

    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.

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

    Aguiar, J.C.; Fernandez, J.

    2006-01-01

    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

  10. 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

    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

  11. INPRO Methodology to evaluate the Mexico nuclear energy system; Metodologia INPRO para evaluar el sistema de energia nuclear de Mexico

    Cruz S, R. R.; Martin del C, C., E-mail: crzslns.ricardoruben@gmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2016-09-15

    The International Atomic Energy Agency has developed the so-called International Project on Fuel Cycles and Innovative Nuclear Reactors (INPRO), in order to make nuclear energy available to meet the energy needs of the 21 century, in a sustainable way. One of the tasks of the project is the evaluation of the nuclear systems, to check whether they meet the objectives of the project and whether they are sustainable. This paper explains the rationale and general characteristics of the project in the evaluation of nuclear energy systems based on the concept of sustainable development. It describes the methodology developed to carry out this evaluation, divided into seven areas, such as economic, environmental, security, etc., which together make up the sustainable development of energy through nuclear systems. The economic area is analyzed and the evaluation criteria and parameters established by INPRO are discussed, in order to evaluate the Mexican nuclear energy system using Nest (software developed within the same project) as a tool to support the economic evaluation of nuclear systems. Based on the energy strategy proposed by the Energy Secretary of the Mexican Government which seeks to reduce the greenhouse gas emissions from the national electricity generation park, two types of reactor of currently available technology (A BWR and AP1000), were compared and these in turn with other alternative energy generation technologies, such as combined cycle, geothermal and wind plants. Also, the results of the application of the INPRO methodology are presented. Finally, the recommendations on actions that could lead the Mexican nuclear energy system towards sustainable development and conclusions on the application of the methodology to the Mexican case are mentioned. (Author)

  12. Identification of uranium signatures in swipe samples on verification of nuclear activities for nuclear safeguards purposes; Identificacao de assinaturas de uranio em amostras de esfregacos (swipe samples) para verificacao de atividades nucleares para fins de salvaguardas nucleares

    Pestana, Rafael Cardoso Baptistini

    2013-07-01

    The use of environmental sampling for safeguards purposes, has been applied by the International Atomic Energy Agency–IAEA since 1996 and are routinely used as a complementary measure to strengthen the traditional nuclear safeguards procedures. The aim is verify if the states signatory to the safeguards agreements are not diverging their peaceful nuclear activities for undeclared nuclear activities. This work describes a new protocol of collect and analysis of the swipe samples for identification of nuclear signatures that may be related to the nuclear activities developed in the inspected facility. This work was used as a case of study a real uranium conversion plant of the nuclear fuel cycle of IPEN. The strategy proposed uses different analytical techniques, such as alpha radiation meter, SEM-EDX and ICP-MS to identify signatures of uranium adhered to the swipe samples. In the swipe samples analysis, it was possible to identify particles of UO{sub 2}F{sub 2} and UF4 through the morphological comparison and semi-quantitative analyses performed by SEM-EDX technique. In this work, methods were used that as a result has the average isotopic composition of the sample, in which the enrichment ranged from 1.453 ± 0.023 to 18.24 % ± 0.15 % in the {sup 235}U isotope. Through these externally collections, a non-intrusive sampling, it was possible to identify enriched material handling activities with enrichment of 1.453 % ± 0.023 % to 6.331 ± 0.055 % in the isotope {sup 235}U, as well as the use of reprocessed material, through the identification of the {sup 236}U isotope. The uncertainties obtained for the n({sup 235}U)/n({sup 238}U) ratio varied from 0.40% to 0.86 % for the internal swipe samples. (author)

  13. Internet applications in nuclear power plant operation management; Aplicaciones de internet en la gestion de la explotacion de centrales nucleares

    Munoz, M. [Empresarios Agrupados, A. I. E. Madrid (Spain)

    2000-07-01

    The use of the Internet is quickly becoming widespread in practically all areas of business and industry. The nuclear industry should not remain indifferent to this new trend. This paper analyses some of the Internet applications that can be easily adapted to nuclear power plant operation management, including. (Author)

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

    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)

  15. The Technical Training Programme for Nuclear Power Station Personnel; Programme de formation technique du personnel des centrales nucleaires; Programma tekhnicheskoj podgotovki personala yadernoj ehlektrostantsii; El programa de formacion tecnica del personal de una central nucleoelectrica

    Howey, G. R. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

    1963-10-15

    de ingenieros con considerable experiencia en trabajos nucleares, centrales termicas y produccion de electricidad; b) Se selecciono entre especialistas altamente calificados otro grupo de operadores y de personal encargado del mantenimiento del equipo; c) Los componentes de ambos grupos siguieron un curso especial sobre centrales nucleoelectricas y termicas, con clases teoricas y practicas a cargo de ingenieros de la central NPD; d) Se creo un centro de formacion en tecnicas nucleares con objeto de seleccionar y capacitar mas personal y de someterle a los examenes pertinentes. El personal fue sometido ademas a un examen por la Atomic Energy Control Board, que es otro organismo federal. Se esta formando personal de cinco categorias: a) Directores: ingenieros encargados de la explotacion, el mantenimiento y la administracion; cambian periodicamente de puesto para familiarizarse con todos estos aspectos del trabajo; b) Operadores: cuatro grados de formacion, segun el trabajo que hayan de realizar; c) Encargados del equipo de control: cuatro grados de formacion; este personal es responsable del mantenimiento de todos los instrumentos, del equipo de control y del equipo electrico; d) Encargados del equipo mecanico: con diversos grados de formacion y varias especialidades (soldadura, fresado, ajuste, etc.); este personal es responsable del mantenimiento de todo el equipo mecanico; e) Personal auxiliar: encargado de una gran variedad de trabajos menos especializados que no requieren un alto grado de formacion. Se necesitan, ademas, algunos otros especialistas, entre ellos quimicos y expertos en proteccion radiologica. El autor de la memoria expone la forma en que esta organizado el personal de la central NPD y examina la cuestion de la formacion profesional teniendo en cuenta las necesidades que crea el desarrollo de la energia nucleoelectrica. (author) [Russian] Atomnaya demonstratsionnaya ehlektrostantsiya Kanady (NPD), vvedennaya v stroj federal'nym agentstvom ''Atomik

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

    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.)

  17. Procedimiento para determinación y definición del valor central. Su aplicación en la gestión de la calidad

    Aimara Rodríguez Fernández

    2017-06-01

    de la calidad. La metodología empleada se caracteriza por estar basada en métodos y técnicas con amplia aceptación por parte de la comunidad científica y otras valía dentro de la dirección. Los resultados apuntan al cumplimiento del objetivo, logrando determinar el valor central y su concepto para el proceso de gestión de la calidad de una instalación hotelera. Podemos concluir que determinar el valor central de una empresa es de suma importancia en el mundo organizacional para éxito de las empresas con un enfoque humanista.

  18. Ordenar para controlar. Ordenamiento espacial y control político en las Llanuras del Caribe y en los Andes Centrales Neogranadinos. siglo XVIII

    Beatriz Patiño Millán

    2002-01-01

    Full Text Available Marta Herrera Ángel. Ordenar para Controlar. Ordenamiento espacial y control político en las Llanuras del Caribe y en los Andes Centrales Neogranadinos. Siglo XVIII. Bogotá: Instituto Colombiano de Antropología e Historia - Academia Colombiana de Historia, 2002, pp. 343. En este libro Marta Herrera estudia la estructuración del ordenamiento espacial y político durante el siglo XVIII de las llanuras del Caribe, nombre con el cual denomina el ámbito espacial correspondiente a las gobernaciones de Cartagena y Santa Marta,  y los Andes Centrales, apelativo que utiliza para referirse a los territorios de la provincia de Santafé y la jurisdicción de la ciudad de Tunja.

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

    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)

  20. Elecnuc. Nuclear power plants worldwide; Elecnuc. Les centrales nucleaires dans le monde

    NONE

    1998-07-01

    This small folder presents a digest of some useful information concerning the nuclear power plants worldwide and the situation of nuclear industry at the end of 1997: power production of nuclear origin, distribution of reactor types, number of installed units, evolution and prediction of reactor orders, connections to the grid and decommissioning, worldwide development of nuclear power, evolution of power production of nuclear origin, the installed power per reactor type, market shares and exports of the main nuclear engineering companies, power plants constructions and orders situation, evolution of reactors performances during the last 10 years, know-how and development of nuclear safety, the remarkable facts of 1997, the future of nuclear power and the energy policy trends. (J.S.)

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

    Peltzer, P.

    1983-01-01

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

  2. US central station nuclear electric generating units: significant milestones (status as of January 1, 1979)

    1979-03-01

    Construction and operational milestones are tabulated for US nuclear power plants. Data are presented on nuclear steam supply system orders. A schedule of commercial operation and projected capital costs through 1990 is given

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

    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)

  4. Phylogenetics of Ogyges Kaup and the biogeography of Nuclear Central America (Coleoptera, Passalidae)

    Cano, Enio B.; Schuster, Jack C.; Morrone, Juan J.

    2018-01-01

    Abstract A phylogenetic morphological analysis of the genus Ogyges Kaup, distributed in Nuclear Central America, from Chiapas, Mexico, to northwestern Nicaragua was undertaken. Five species of Proculejus Kaup, distributed north of the Isthmus of Tehuantepec in Mexico, were selected as outgroup. Ogyges was recovered as monophyletic with three species groups: championi, laevissimus, and crassulus. Each species group shows a distinct, generally allopatric distribution. The O. championi species group, with ten species, is distributed in the Maya block, more specifically in the mountainous system north of the Motozintla-Comaltitlán fault in Chiapas, and north of the dry valleys of the Cuilco and Motagua rivers in Guatemala. The two remaining species groups are distributed in the Chortis block. The O. laevissimus species group, including seven species, ranges mostly along the Pacific Volcanic Chain from Guatemala to El Salvador, and from southeastern Honduras to the northwestern area of Nicaragua. The O. crassulus species group, with ten species, is distributed from northeastern Guatemala (Merendón) to northern Honduras. The Isthmus of Tehuantepec in Mexico, the Motagua-Cuilco and Motozintla-Comaltitlán sutures zones in Chiapas and Guatemala, the lowland valleys of Colón and Comalí rivers between Nicaragua and Honduras (or, perhaps, the northern suture of the Siuna Terrane in Nicaragua), the Guayape fault system in Honduras, and the intricate dry valleys of Ulúa-Chamelecón-Olancho in Honduras, are hypothesized to have acted as barriers that affected the geographical distribution of Ogyges, as well as probably other montane organisms. PMID:29674874

  5. Climatologia no Entorno da Central Nuclear de Angra dos Reis, RJ

    João Batista Araujo Figueiredo

    Full Text Available Resumo Este trabalho tem por objetivo caracterizar os ciclos diurno e sazonal médios no entorno da Central Nuclear de Angra dos Reis. As condições médias são derivadas de dados horários, do período de janeiro de 2005 a dezembro de 2012. O local conta com quatro torres A, B, C e D. A Torre A mede vento e temperatura do ar a 10, 60 e 100 m e também precipitação, enquanto as demais torres medem somente vento a 15 m de altura. A atmosfera apresenta condições predominantemente estáveis ao longo do dia, com redução a partir das 6 e 7 h, sendo que condições instáveis predominam entre às 8 e 16 h no verão e primavera. Os ventos da região são predominantemente fracos, a maior frequência ocorre nas intensidades entre 1,5 e 2 m/s. O mínimo de intensidade dos ventos a 10 m ocorre no momento da entrada da brisa marítima, às 9 h. Os ventos catabáticos produzem um forte cisalhamento vertical dos ventos na região. Nas demais torres a máxima intensidade ocorre entre 13 e 15 h local. Ventos mais intensos e chuvas mais intensas foram registrados no outono (MAM, o que sugere ser este o período de tempestades mais intensas.

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

    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)

  7. The CNA-1 (Nuclear Power Plant Atucha-1) QK-01 repairing project; Proyecto de reparacion del QK-01 de CNA-1 (Central Nuclear Atucha-1)

    Pizzaferri, J C [Nucleoelectrica Argentina S.A. (NASA), Buenos Aires (Argentina); Cabot, P [Comision Nacional de Energia Atomica, San Martin (Argentina). Centro Atomico Constituyentes

    1998-12-31

    The repair/maintenance of the CNA-1 QK-01 Moderator Cooler will be a leading case of the repair of a class 1 nuclear component in a high radiation environment; utilizing for the work, sophisticated remotely operated equipment. This paper describes the component, the repair-maintenance objective, and the equipment-procedures developed for the intervention. (author) 9 refs., 5 figs. [Espanol] La reparacion/mantenimiento del enfriador del moderador QK-01 de CNA-1 sera un caso sobresaliente de reparacion de un componente nuclear clase 1 en un ambiente de alta radiacion, utilizando equipamiento sofisticado de accion remota. En este trabajo se describen caracteristicas de diseno del componente, objetivos del mantenimiento, y las facilidades y procedimientos desarrollados en el marco del proyecto para realizar la tarea en cuestion. (autor)

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

    Souza, C.A.F. de; Pessoa, M.A.R.; Utchitel, S.

    1988-01-01

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

  9. Nuclear energy and opportunity to strengthen the sustainable electricity sector; Energia nuclear una oportunidad para fortalecer el sector electrico sustentable

    Robles N, A. G. [Comision Federal de Electricidad, Direccion de Proyectos de Inversion Financiada, Gerencia de Proteccion Ambiental, Paseo de la Reforma No. 164, Col. Juarez, 06600 Ciudad de Mexico (Mexico)

    2016-09-15

    The beginning of electricity in Mexico was through the use and exploitation of natural resources; as the demand grew, more generation power plants were required with great capacity and at the same time the fuels used varied, although, oil continued to be the main fuel. At present, due to the effects of climate change, the Conference of the Parties has proposed to reduce the consumption of fossil fuels to give way to clean energy (wind, solar, geothermal, nuclear, etc.), which entails gradually modifying the energy matrix of the electricity sector. The National Development Plan and the National Electricity Sector Development Program, this coordinated by the Energy Secretariat in Mexico, establish policies to promote sustainable development, increasing electricity generation through clean energy sources, including nuclear energy. However, such plans are not accurate in the strategy to be followed to ensure compliance with the increased participation of nuclear energy. This article proposes a nuclear program for the Mexican electricity sector, under the terms of a State policy, aimed at crystallizing a sustainable electricity development 2015-2036; considering that the application to the electricity sector constitutes a representative and justified example of the incorporation of environmental aspects in decision processes for the preservation of the environment. In order to determine the quantity and type of reactors, as well as the number of nuclear power plants and increase of the installed capacity, the general planning scheme of the electric sector was used, taking as reference the modeling criteria of the WASP planning system. Finally, is concluded that the electricity generated by fission of radioactive elements is an opportunity to fulfill the commitments made by Mexico at COP 21 and to meet in an environmentally friendly way the energy requirement that our country needs. (Author)

  10. 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

    Carretero, Yunta; 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.

  11. 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

    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)

  12. 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

    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

  13. 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

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

    1998-12-31

    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

  14. 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

    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)

  15. 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

    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)

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

    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

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

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

    2012-01-01

    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

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

    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)

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

    Garde Sesma, Idoia

    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...

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

    Ritch, J.

    2006-01-01

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

  1. 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

    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

  2. Calculation of reactivity for safety in nuclear reactors; Calculo de la reactividad para seguridad en reactores nucleares

    Suescun D, D. [Universidad Surcolombiana, Av. Pastrana Borrero - Carrera 1, Neiva, Huila (Colombia); Rojas A, O., E-mail: daniel.suescun@usco.edu.co [Universidad Popular Autonoma del Estado de Puebla, Av. 9 Pte 1908, Barrio de Santiago, 72410 Puebla (Mexico)

    2017-09-15

    The measurement of reactivity is a function of time and its calculation results from the variation in nuclear power from the inverse equation of punctual kinetics. This equation is a differential integral, where the term of the integral conserves the historical power and the differential part is directly related to the period of the reactor. In practice, in a nuclear plant, sensors are required to record the signals. For example, the movements of the control rods that cause the fluctuations of nuclear power over time commonly generate signals with noise, an event that makes difficult to estimate the reactivity. Thus is necessary and very useful to build digital reactivity meters in real time, since allows a reactor to be operated with greater security. The calculation of the reactivity is carried out using punctual kinetics, especially the concentration of delayed neutron precursors. In this work we present a new way to reduce the fluctuations in the calculation of the reactivity, for the high precision we propose the generalization of the predictor and corrector of the Adams-Bashforth-Moulton (ABM) method of order 4 to solve numerically the equations of the point kinetics for the calculation of the reactivity, without using the power history, due to the nature of the equations of the punctual kinetics, the modifiers of the different predictors are used to increase the accuracy in the approximation obtained accompanied by the filter known as Savitzky-Golay (Sg), allow to reduce the fluctuations of reactivity. It is known that the Sg filter softens and does not attenuate the nuclear power regardless of its shape, guarantees to reduce noise levels up to σ = 0.01, with a calculation time step of σ = 0.01, s. This formulation uses a polynomial approximation of Gram, with a degree d = 2, to calculate the convolution coefficients by means of an analytical formula that is implemented computationally and avoids problems of bad conditioning, caused by the inversion of a

  3. Proposal for a reformulation in the Brazilian nuclear strategy; Proposta para a reformulacao da estrategia nuclear brasileira

    Ferreira, Omar Campos; Urban, Carlos Werth; Mello, Jair Carlos; Ribeiro, Leonardo Marcio Vilela; Ferreira, Angela Fortini Macedo [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear

    1995-12-31

    By the projections of the populational growth and electrical energy demand in Brazil, may be expected that from 2010 to 2015 the nuclear energy will play an important role in electrical energy supply. The PWR technology do not may support the social and economic growth of the country by more than two or three decades. Will be necessary to develop a breeder reactor technology. The new technology must be more economic in primary resources and safer in respect to accidents and fissile material proliferation. The Molten Salt Thermal Breeder Reactor seems fulfill these conditions. (author). 11 refs., 2 tabs.

  4. Proyecto de rehabilitación de un edificio subutilizado para generar vivienda en el área central de la ciudad de San José

    Felipe Pina Castillo

    2016-01-01

    Full Text Available Reseña del proyecto arquitectónico titulado “Rehabilitación de un edificio subutilizado para generar vivienda en el área central de San José”. El tema del proyecto tiene la voluntad de ser una referencia para el proceso de ejecución del Plan de Regeneración y Repoblamiento de la ciudad de San José. Esta investigación se llevó a cabo como parte del proyecto final de graduación para optar por el grado de Licenciatura en Arquitectura y Urbanismo del Instituto Tecnológico de Costa Rica. This is a review of the architectural project entitled “Rehabilitation of vacant buildings to generate housing in the central area of San José”. The subject of the project described here is intended to be a point of reference for the implementation an area of a Regeneration and Repopulation Plan of the city of San Jose. This research was undertaken as part of final graduation project in Architecture and Urbanism at the Costa Rica Institute of Technology.

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

    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.

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

    Raupach, Michael J; Astrin, Jonas J; Hannig, Karsten; Peters, Marcell K; Stoeckle, Mark Y; Wägele, Johann-Wolfgang

    2010-09-13

    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. 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. 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.

  7. 75 FR 9576 - Civil Nuclear Policy Mission to Central and Eastern Europe

    2010-03-03

    .... civil nuclear industry. Increasing energy demands, dependence on Russian fossil fuels, and a small but aging fleet of Russian reactor technologies is colliding with pressure from the EU to meet stricter..., language included in the Czech Republic's nuclear tender allows for the awarded company to have the...

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

    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.)

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

    1980-09-01

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

  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

    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. Ionizing radiation, nuclear energy and radiation protection for school; Radiacao ionizante, energia nuclear e protecao radiologica para a escola

    Lucena, E.A.; Reis, R.G.; Pinho, A.S.; Alves, A.S.; Rio, M.A.P.; Reis, A.A., E-mail: arlene@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Silva, J.W.S. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Paula, G.A. de; Goncalves Junior, M.A. [Escola Sesc de Ensino Medio, Rio de Janeiro, RJ (Brazil)

    2017-04-01

    Since the discovery of X-rays in 1895, ionizing radiation has been applied in many sectors of society, such as medicine, industry, safety, construction, engineering and research. However, population is unaware of both the applications of ionizing radiation and their risks and benefits. It can be seen that most people associate the terms 'radiation' and 'nuclear energy' with the atomic bomb or cancer, most likely because of warlike applications and the stealthy way radioactivity had been treated in the past. Thus, it is necessary to clarify the population about the main aspects related to the applications, risks and associated benefits. These knowledge can be disseminated in schools. Brazilian legislation for basic education provides for topics such as nuclear energy and radioactivity to high school students. However, some factors hamper such an educational practice, namely, few hours of class, textbooks do not address the subject, previous concepts obtained in the media, difficulty in dealing with the subject in the classroom, phobia, etc. One solution would be the approximation between schools and institutions that employ technologies involving radioactivity, which would allow students to know the practices, associated radiological protection, as well as the risks and benefits to society. Currently, with the increasing application of ionizing radiation, especially in medicine, it is necessary to demystify the use of radioactivity. (author)

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

    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.

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

    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)

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

    Ferguston, C.D.; Ouagrham, S.B.

    2002-01-01

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

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

    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

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

    Bendarag, A.

    1999-01-01

    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)

  17. Methodology if inspections to carry out the nuclear outages model; Metodologia de inspeccciones para cumplir el modelo de paradas nucleares

    Aycart, J.; Mortenson, S.; Fourquet, J. M.

    2005-07-01

    Before the nuclear generation industry was deregulated in the United States, refueling and maintenance outages in nuclear power plants usually lasted orotund 100 days. After deregulation took effect, improved capability factors and performances became more important. As a result, it became essential to reduce the critical path time during the outage, which meant that activities that had typically been done in series had to be executed in parallel. The new outage model required the development of new tools and new processes, The 360-degree platform developed by GE Energy has made it possible to execute multiple activities in parallel. Various in-vessel visual inspection (IVVI) equipments can now simultaneously perform inspections on the pressurized reactor vessel (RPV) components. The larger number of inspection equipments in turn results in a larger volume of data, with the risk of increasing the time needed for examining them and postponing the end of the analysis phase, which is critical for the outage. To decrease data analysis times, the IVVI Digitalisation process has been development. With this process, the IVVI data are sent via a high-speed transmission line to a site outside the Plant called Center of Excellence (COE), where a team of Level III experts is in charge of analyzing them. The tools for the different product lines are being developed to interfere with each other as little as possible, thus minimizing the impact of the critical path on plant refueling activities. Methods are also being developed to increase the intervals between inspection. In accordance with the guidelines of the Boiling Water Reactor Vessel and Internals project (BWRVIP), the intervals between inspections are typically longer if ultrasound volumetric inspections are performed than if the scope is limited to IVVI. (Author)

  18. Multichannel analyzer for nuclear spectrometry with FPGA using Vivado; Analizador multicanal para espectrometria nuclear con FPGA utilizando Vivado

    Garcia D, A.; Hernandez D, V. M.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98060 Zacatecas, Zac. (Mexico); Ordaz G, O. O.; Ibarra D, S. [Universidad de Cordoba, Campus de Rabanales, Carretera Nacional IV, km 396, 14014 Cordoba (Spain); Bravo M, I., E-mail: angelogarciad@hotmail.com [Universidad de Alcala, Departamento de Electronica, Campus Universitario s/n, 28805 Alcala de Henares, Madrid (Spain)

    2017-09-15

    The different applications of ionizing radiation have made this a very significant and useful tool, in turn can be dangerous for living beings if they are exposed to uncontrolled doses. However, due to its characteristics, cannot be perceived by the five senses, in such a way that in order to know the presence of it, radiation detectors and additional devices are required that allow to quantify and classify it. This is the case of the multichannel analyzer that is responsible for separating the different pulse heights that are generated in the detectors, in a certain number of channels; according to the number of bits of the analog to digital converter. The development or conditioning of nuclear technology has increased considerably due to the demand of the applications; therefore this allows developing systems that cover some commercial requirements, cost and volume in relation to the user needs. The objective of the work was to design and implement an intellectual property core (IP Core) which functions as a multichannel analyzer for nuclear spectrometry. For the IP Core design methodology, its components were created in VHDL hardware description language and packaged in the Vivado design suite, making use of resources such as the ARM processor cores that the Zynq chip contains. Likewise, for the first phase of the implementation, the hardware architecture was embedded in the FPGA and the application for the ARM processor was programmed in C language. For the second phase, the management, control and visualization of the results, a virtual instrument was developed in the LabView programming platform. The data obtained as a result of the development and implementation of the IP Core was observed graphically in a histogram that is part of the aforementioned virtual instrument. (Author)

  19. Adenovirus oncolíticos como estrategia terapéutica para tumores del sistema nervioso central

    Vera-Cano, B. (Beatriz); Alonso M.M. (Marta Maria); Saez-Castresana, J. (Javier)

    2018-01-01

    La descripción de los distintos tumores cerebrales y sus alteraciones genéticas ha demostrado ser una herramienta importante para la mejora en el diagnóstico y clasificación de los pacientes que los padecen. Sin embargo, los avances en el tratamiento de estas enfermedades no han ido a la par y a pesar de todos los esfuerzos terapéuticos estos pacientes siguen sucumbiendo a la enfermedad. Los adenovirus oncolíticos diseñados para replicarse y destruir a las células tumorales representan una es...

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

    Wang Feng

    2010-01-01

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

  1. Communications Received from Certain Member States Regarding Guidelines for the Export of Nuclear Material, Equipment and Technology. Nuclear Transfers and Nuclear-Related Dual-Use Transfers; Comunicaciones Recibidas De Diversos Estados Miembros Relativas A Las Directrices Para La Exportacion De Tecnologia, Equipo Y Materiales Nucleares. Transferencias Nucleares Y Transferencias De Equipo, Materiales V Tecnologia Afin Al Doble Uso En Materia Nuclear

    NONE

    1993-04-15

    The Director General has received a Note Verbale dated 5 March 1993 from the Ministry of Foreign Affairs of the Slovak Republic. The purpose of the Note Verbale is to provide information on that Governments' guidelines for Nuclear Transfers and for Transfers of of Nuclear-related Dual-use Equipment, Material and Related Technology. In the light of the wish expressed at the end of each Note Verbale, the text of the Note Verbale is annexed hereto [Spanish] El Director General ha recibido una nota verbal de fecha 5 de marzo de 1993 del Ministerio de Relaciones Exteriores de la RepUblica Eslovaca. El objetivo de la nota verbal es proporcionar informaciOn sobre las Directrices para las transferencias nucleares y las Directrices para la transferencia de equipo, materiales y tecnologia afin al doble uso en materia nuclear, de dicho Gobierno. Atendiendo a los deseos expresados al final de la nota verbal, se adjunta al presente documento el texto de la nota verbal.

  2. 1989 annual report of the Rossendorf Central Institute of Nuclear Research

    Fromm, W.; Kaun, K.H.; Moeller, K.; Naehring, F.; Schulz, H.; Winter, G.; Heidel, I.; Breiter, S.

    1990-01-01

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

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

    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...

  4. Comparing flowmeter, aquifer test, and surface nuclear magnetic resonance data in Central Nebraska

    Irons, T.; Abraham, J. D.; Cannia, J. C.; Steele, G.; Hobza, C. M.; Li, Y.; McKenna, J. R.

    2011-12-01

    Traditionally the only means of estimating the hydraulic properties of aquifers has involved drilling boreholes. The logistical and economic requirements of aquifer tests has limited the ability of hydrologists to construct the detailed groundwater models needed for resource management. As such, water policy decisions are often based on sparse aquifer tests combined with geologic interpretation and extrapolation. When dealing with complicated groundwater systems these extrapolations are often not accurate at the scale required to characterize the groundwater system, and additional information is needed to make better informed resource decisions. Surface nuclear magnetic resonance (SNMR) is a geophysical technique which allows for non-invasive estimates of hydraulic permeability and transmissivity. Protons in a volume of liquid water form a weak bulk magnetic moment as they align and precess about the earth's magnetic field. This moment is too small to be measured directly but may be observed by tipping it away from equilibrium using radio-frequency pulses oscillating at the same frequency as its precession (the Larmor frequency). After a short tipping pulse, the moment continues to precess around the static field, although at a tipped angle, slowly returning to its equilibrium state. The decay of these spinning magnetic moments can be observed inductively using loops of wire on the surface of the earth. In the simplest experiment a time series is recorded after a single tipping pulse. By varying the strength of the tipping pulse, different regions of the subsurface can be probed. The amplitude of the signal is directly proportional to the amount of water in the investigated volume. The decay rate of the signal is related to pore geometry and interconnectivity and can be used to estimate hydraulic conductivity. However, this relationship cannot be universally defined as it is affected by additional factors including the mineralogy of the host rock and homogeneity of

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

    Fernandez-Bolanos, M.

    2008-07-01

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

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

    Gillen, V.

    1993-12-01

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

  7. I and C upgrades resulting from the systematic evaluation program carried out at the Central Nuclear Jose Cabrera

    Humphrey, J.C.

    1985-01-01

    Central Nuclear Jose Cabrera, also known as Zorita, is a 160 MWe nuclear power plant owned and operated by UNION ELECTRICA-FENOSA, S.A. The plant was supplied by Westinghouse Electric Corporation and commissioned in 1968. It features a unique one loop Pressurized Water Reactor design. The Spanish Licensing Authorities requested C.N. Jose Cabrera to carry out a review of their plant. The main objectives were to reassess the safety adequacy of the operating systems, provide a documented comparison of the plant design versus present day criteria and establish a rationale for departures. Another important objective was to provide prompt identification of any significant deficiency. The review known as phase 1 of the C.N. Jose Cabrera Systematic Evaluation Program, was completed and documented by April 1980

  8. Estimación de modelos lineales para el control predictivo de pequeñas centrales hidroeléctricas

    Estrada-Viana, I. D. (Iván Darío); Peña-Palacio, J. A. (Juan Alejandro); Guarnizo-Lemus, C. (Cristian)

    2012-01-01

    En este artículo se lleva a cabo el modelamiento de una Pequeña Central Hidroeléctrica (PCH), mediante la obtención de modelos lineales de predicción. El modelo matemático de la central, contempla todo su sistema hidráulico, el cual va desde el tanque de captación, pasando por el túnel para el transporte del recurso hídrico, las tuberías de carga, hasta llegar a las unidades de generación. Posteriormente, se procede al modelamiento del sistema, mediante la utilización de un con...

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

    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)

  10. 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

    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.

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

    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.

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

    Amato, N.M.; Arata, N.; Maldonado, R.H.C.

    1987-01-01

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

  13. Multiplicity Fluctuations in Central Nuclear Reaction of Pb + AgBr Events at 158A GeV

    Mohammad Ayaz Ahmad

    2017-12-01

    Full Text Available In the present articles an attempt has been made for the study of multiplicity fluctuations of the secondary charged particles produced in central relativistic nuclear collisions of (Pb+AgBr at an energy 158A GeV, to find the first-order phase transition (QGP to hadron phase state. This study has been carried out for the experimental data along with the theoretical prediction of FRITIOF simulation program and Monte-Carlo (RanMC simulation. The theoretical model predictions were found in good agreements.

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

    1977-01-01

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

  15. 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

    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.

  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

    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. 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

    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.

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

    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. Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant. Simulacao do sistema nuclear de geracao de vapor de uma central PWR

    Reis Martins Junior, L.L. dos.

    1980-01-01

    The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author).

  20. Nuclear power planning study for Venezuela. Estudio de planificacion nucleoelectrica para Venezuela

    1978-01-01

    The optimum capacity for nuclear power plants that might be built in Venezuela in the period 1985-2000 and the best time for incorporating them into the electric system is defined. The most recent forecasts regarding growth of the population and demand, and of the economy in general, and the taking into account the costs for the fossil-fuel and hydroelectric resources known to exist in Venezuela, as compared with the costs of importing uranium, are discussed.

  1. Decree N0 73-322 of 15 March 1973 concerning insurance and reinsurance of exceptional and nuclear risks by the Central Reinsurance Fund

    1973-01-01

    This Decree provides that the Central Reinsurance Fund may cover, with the State guarantee, risks for which operators of nuclear ships and installations are liable and concerning which State intervention is provided for by legislation. These operations relate in particular to goods carried, nuclear installations and property on the site of such installations. The Decree sets up an Advisory Commission for the Central Reinsurance Fund regarding security for exceptional and nuclear risks and repeals a 1967 Decree on insurance of exceptional risks. (NEA) [fr

  2. Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition); Realizacion de operaciones en centrales nucleares. Guia de seguridad

    NONE

    2012-04-15

    This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

  3. Operating Experience with Indian Point Nuclear Electric Generating Station; Experience d'exploitation de la centrale nucleaire d'Indian point; Opyt ehkspluatatsii Indian-pojntskoj yadernoj ehlektrostantsii; Experiencia adquirida con la explotacion de la central nucleoelectrica de Indian point

    Beattie, W. C.; Freyberg, R. H. [Consolidated Edison Company of New York, Inc., New York, NY (United States)

    1963-10-15

    potencia, hasta 5 MW(t), a la temperatura ambiente y a temperaturas elevadas, y el 16 de septiembre de ese ano el turbogenerador se conecto por primera vez a la red de la Consolidated Edison. Hasta entrado el mes de noviembre, prosiguieron los ensayos a potencias de hasta 50% del valor teorico, con frecuentes detenciones automaticas, originadas en gran parte por perturbaciones en la seccion ''clasica'' de la central. En cuanto a la seccion nuclear, fueron sobre todo las fallas del mecanismo de mando de las barras de control que contribuyeron a la caida automatica de las barras y a las demoras en la reiniciacion de la marcha despues del paro. El 14 de noviembre de 1962 se detuvo la marcha de la central para proceder a los cambios previstos en las tuberias de la seccion ''clasica'' y para modificar y perfeccionar el mecanismo de mando de las barras de control. Esta ultima operacion comprendia la instalacion de un dispositivo de purga a base de nitrogeno seco para las cajas de los mecanismos de las barras de control, a fin de reducir al minimo los efectos de los escapes de agua, a traves de las juntas. Al parecer, dichas perdidas eran la causa principal de las indicaciones erroneas registradas en el sistema de control del reactor. La central se volvio a poner en servicio el lc de enero de 1963. El 27 de enero de 1963, se dio fin a los ensayos del reactor, con potencias hasta el 100%, en condiciones de carga constante. Los resultados de los ensayos concordaron satisfactoriamente con las previsiones. En la primavera de 1963 se continuaran las pruebas, para estudiar la manera en que el reactor responde a fluctuaciones rapidas de la demanda. (author) [Russian] Blok No. 1 Indian-pojntskoj yadernoj ehlektrostantsii sostoit iz reaktora s vodoj pod davleniem moshchnost'yu 585 mgvt, chetyrekh pervichnykh konturov okhlazhdeniya s gorizontal'nymi teploobmennikami, dvukh rabotayushchikh ka nefti paroperegrevatelej proizvoditel'nost'yu 1 100 tys. funtov/chas i turbogeneratora moshchnost

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

    José Rovira Collado

    2012-09-01

    Full Text Available http://dx.doi.org/10.5007/2175-795X.2012v30n3p789 Para analizar la recepción de las obras de literatura infantil y juvenil en internet, los blogs continúan siendo un espacio fundamental para la opinión crítica, la reflexión académica y la práctica docente configurándose como eje central del concept oLIJ 2.0. Después de analizar dicho concepto, se presentarán en primer lugar los principales blogs de la LIJ en castellano, donde encontramos espacios de escritores e ilustradores, propuestas de animación a la lectura, repositorios de obras y críticaliteraria, centrándonos más en la parte de difusión y animación a la lectura que en lade creación literaria. Posteriormente se presentarán el recorrido didáctico realizado alo largo de cinco años en la Universidad de Alicante para explotar dichas herramientas en distintos niveles educativos.

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

    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.

  6. Aplicación de la metodología de Análisis Probabilístico de la Seguridad al procedimiento de evaluación de las Funciones Clave de Seguridad en parada de una central nuclear de agua a presión

    Viñals Atienza, Òscar

    2008-01-01

    El Proyecto Final de Carrera “Aplicación de la metodología de Análisis Probabilístico de la Seguridad al procedimiento de evaluación de las Funciones Clave de Seguridad en parada de una central nuclear de agua a presión” se enmarca en un convenio de colaboración entre el Departament de Física i Enginyeria Nuclear y una central nuclear para la investigación y aplicación de los APS en decisiones basadas en el riesgo. El hilo conductor de este proyecto ha sido la petición por parte del depart...

  7. The Centralized Reliability Data Organization (CREDO); an advanced nuclear reactor reliability, availability, and maintainability data bank and data analysis center

    Knee, H.E.

    1991-01-01

    The Centralized Reliability Data Organization (CREDO) is a data bank and data analysis center, which since 1985 has been jointly sponsored by the US Department of Energy's (US DOE's) Office of Technology Support Programs and Japan's Power Reactor and Nuclear Fuel Development Corporation (PNC). It focuses on reliability, availability and maintainability (RAM) data for components (e.g. valves, pumps, etc.) operating in advanced nuclear reactor facilities. As originally intended, the purpose of the CREDO system was to provide a centralized source of accurate, up-to-date data and information for use in RAM analyses necessary for meeting DOE's data needs in the areas of advanced reactor safety assessments, design and licensing. In particular, creation of the CREDO system was considered an essential element needed to fulfill the DOE Breeder Reactor Safety Program's commitment of 'identifying and exploiting areas in which probabilistic methods can be developed and used in making reactor safety Research and Development choices and optimizing designs of safety systems'. CREDO and its operation are explained. (author)

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

    1979-01-01

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

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

    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)

  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

    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. Para-hydrogen raser delivers sub-millihertz resolution in nuclear magnetic resonance

    Suefke, Martin; Lehmkuhl, Sören; Liebisch, Alexander; Blümich, Bernhard; Appelt, Stephan

    2017-06-01

    The precision of nuclear magnetic resonance spectroscopy (NMR) is limited by the signal-to-noise ratio, the measurement time Tm and the linewidth Δν = 1/(πT2). Overcoming the T 2 limit is possible if the nuclear spins of a molecule emit continuous radio waves. Lasers and masers are self-organized systems which emit coherent radiation in the optical and micro-wave regime. Both are based on creating a population inversion of specific energy states. Here we show continuous oscillations of proton spins of organic molecules in the radiofrequency regime (raser). We achieve this by coupling a population inversion created through signal amplification by reversible exchange (SABRE) to a high-quality-factor resonator. For the case of 15N labelled molecules, we observe multi-mode raser activity, which reports different spin quantum states. The corresponding 1H-15N J-coupled NMR spectra exhibit unprecedented sub-millihertz resolution and can be explained assuming two-spin ordered quantum states. Our findings demonstrate a substantial improvement in the frequency resolution of NMR.

  12. Consequences of the nuclear energy moratorium as demanded by the F.D.P. central committee

    1977-08-01

    If the construction of nuclear power plants is to be tied to the first partial construction licence for the Germany reprocessing centre, as the F.D.P. especially demands lately (note: superseded since the Party Congress) then this would lead unavoidably to a 3- to 10-year nuclear energy moratorium with extremely serious consequences for the electricity supply and the employment situation in the FRG. In view of the significance of the impending energy policy decisions, the Deutsches Atomforum urges all those responsible in Bund and Laender, to take these interconnections very seriously. Only by solving the apparent conflict between further nuclear energy expansion and reprocessing, can preconditions be created for the realization of an adequate electricity supply which, at the same time, is not harmful to the environment, without serious consequences for energy and employment policies. The fact that these consequences will not be visible until in the eighties, may not be a reason for postponing decisions which have to be taken now. (orig./HP) [de

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

    2013-10-01

    Founding Act on Mutual Relations, Cooperation and Security Between NATO and the Russian Federation, signed in Paris , May 27, 1997, Section IV. Political...in Central Europe,” in Bruno Tertrais, ed., Perspectives on Extended Deterrence, Researches and Documents No. 3 ( Paris : Fondation pour la Rescherche...I. • • • • • • Wrodaw 0 Lo~t Radom L bl’ o u 1n ·= ... 0 Brest 0 Pinsk

  14. 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

    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.

  15. 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

    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)

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

    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. Licence prolongations of US nuclear power plants; Les prolongations de licence des centrales nucleaires americaines

    NONE

    2004-04-01

    Licences of US nuclear reactors were initially attributed for a 40 years duration. However, the vast majority of the reactors can benefit of a licence prolongation for a period of 20 years maximum. This article recalls first the procedure to follow for the licence prolongation demands (safety analysis, components aging, environmental impact statement), and then it makes a status of the accepted prolongations, of the demands under examination, and of the demands that should be presented in the next 5 years. (J.S.)

  18. NRPA develops regulatory cooperation with Central Asian authorities for nuclear safety and radiation protection

    2009-01-01

    With the support of the Norwegian Ministry of Foreign Affairs, the NRPA has initiated a regional regulatory cooperation project with Kazakhstan, Kyrgyzstan and Tajikistan to improve regulations on nuclear safety, radiation protection and environmental issues, and assist the countries in re mediating radioactively contaminated sites. There is a critical lack in the regulatory basis for carrying out such remediation work, including a lack of relevant radiation and environmental safety norms and standards, licensing procedures and requirements for monitoring, as well as expertise to transform such a basis into practice. (Author)

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

    Marconi G, J.F.; Tarazaga, A.E.; Romero, L.D.

    2007-01-01

    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)

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

    Novara, Oscar; LaFuente, Jose; Large, Steve; Andes, Trent; Messick, Charles

    2000-01-01

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

  1. Web design and development for centralize area radiation monitoring system in Malaysian Nuclear Agency

    Ibrahim, Maslina Mohd; Yussup, Nolida; Haris, Mohd Fauzi; Soh @ Shaari, Syirrazie Che; Azman, Azraf; Razalim, Faizal Azrin B. Abdul; Yapp, Raymond; Hasim, Harzawardi; Aslan, Mohd Dzul Aiman

    2017-01-01

    One of the applications for radiation detector is area monitoring which is crucial for safety especially at a place where radiation source is involved. An environmental radiation monitoring system is a professional system that combines flexibility and ease of use for data collection and monitoring. Nowadays, with the growth of technology, devices and equipment can be connected to the network and Internet to enable online data acquisition. This technology enables data from the area monitoring devices to be transmitted to any place and location directly and faster. In Nuclear Malaysia, area radiation monitor devices are located at several selective locations such as laboratories and radiation facility. This system utilizes an Ethernet as a communication media for data acquisition of the area radiation levels from radiation detectors and stores the data at a server for recording and analysis. This paper discusses on the design and development of website that enable all user in Nuclear Malaysia to access and monitor the radiation level for each radiation detectors at real time online. The web design also included a query feature for history data from various locations online. The communication between the server's software and web server is discussed in detail in this paper.

  2. 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

    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

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

    Amato, N.M.; Arata, N.; Maldonado, R.H.C.

    1986-01-01

    A cosmic-ray induced nuclear event detected in the emulsion chamber is described. The event consists of 217 shower cores with ΣEγ = 1,275 TeV. In log scale, energy and particles are emitted most densely at the small lateral distance corresponding to 0.5 mm; 77 % of the total energy and 61 % of the total multiplicity are inside the radius of 0.65 cm. The shower cores in the central region show exponential-type energy distribution and non-isotropic azimuthal distribution. This event indicates a possibility that phenomena of large transverse momentum could happen to produce a strong concentration of energy and particles in the very forward direction. (Authors) [pt

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

    Murata, Takashi

    1999-01-01

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

  5. Análisis y propuesta de un modelo pedagógico para el aprendizaje organizacional: central hidroeléctrica de caldas-chec

    Luisa Inés Arias-Mosquera

    2014-01-01

    Full Text Available El objetivo principal de esta investigación es determinar cómo aprenden los trabajadores del área de Gestión Humana y Organizacional de la Central Hidroeléctrica de Caldas S.A. E.S.P. (CHEC. Se utilizó un enfoque descriptivo para lo cual se aplicaron dos instrumentos, el cuestionario Honey-Alonso de estilos de aprendizaje – CHAEA e Inteligencias múltiples y el cuestionario de autoevaluación – CAIM, a 45 trabajadores adscritos al área de Gestión Humana y Organizacional de la empresa estudiada. Como resultado, se hace una aproximación a un modelo pedagógico para el aprendizaje significativo, que responde a las exigencias empresariales y a las características del público objetivo. La investigación permite concluir que el modelo pedagógico que más se ajusta a las necesidades de los trabajadores estudiados se fundamenta en el aprendizaje significativo.

  6. New instrument for the confirmation of declared power histories of central station nuclear power plants

    Dowdy, E.J.; Robba, A.A.; Hastings, R.D.; France, S.W.

    1979-01-01

    An operationally simple, portable, microprocessor-based, unattended reactor power monitor was developed for International Atomic Energy Agency inspector use in confirming operator records of the power history of nuclear power plants. The monitor is based on the principle that the leakage neutron flux outside the biological shield is proportional to the thermal power level. The leakage flux is detected and compared with the leakage flux from the same reactor for a confirmed calibration period. Several output options are available, and a record of more than three months of hourly measurements of the themal power of the plant can be obtained. The monitor has battery backup power for interruptions of host power of duration up to 18 hours

  7. Mitochondrial content is central to nuclear gene expression: Profound implications for human health.

    Muir, Rebecca; Diot, Alan; Poulton, Joanna

    2016-02-01

    We review a recent paper in Genome Research by Guantes et al. showing that nuclear gene expression is influenced by the bioenergetic status of the mitochondria. The amount of energy that mitochondria make available for gene expression varies considerably. It depends on: the energetic demands of the tissue; the mitochondrial DNA (mtDNA) mutant load; the number of mitochondria; stressors present in the cell. Hence, when failing mitochondria place the cell in energy crisis there are major effects on gene expression affecting the risk of degenerative diseases, cancer and ageing. In 2015 the UK parliament approved a change in the regulation of IVF techniques, allowing "Mitochondrial replacement therapy" to become a reproductive choice for women at risk of transmitting mitochondrial disease to their children. This is the first time that this technique will be available. Therefore understanding the interaction between mitochondria and the nucleus has never been more important. © 2015 The Authors. BioEssays Published by WILEY Periodicals, Inc.

  8. Suicide plane crash against nuclear power plants; Avion suicide contre centrales nucleaires

    Richard, A

    2002-12-01

    Cea (French atomic energy commission) and EDF (Electricity of France) are reassessing their safety standards concerning suicide plane attacks against nuclear facilities. The general idea is to study the non-linear behaviour of reinforced concrete in case of mechanical impact. American studies carried out in 1988 show that a F-14 phantom crashing into a 3,6 meter thick wall at a speed of 774 km/h penetrates only the first 5 cm of the wall. More recent studies performed in Germany and based on computerized simulations show that the reactor containment can sustain impacts from a F15 plane or even from a 747-Boeing but contiguous buildings like the one which houses spent fuels might be more easily damaged because of their metal roofing. (A.C.)

  9. USO DE BLOQUES NUTRICIONALES COMO COMPLEMENTO PARA OVINOS EN EL TROPICO SECO DEL ALTIPLANO CENTRAL DE MEXICO

    Paulina Vazquez-Mendoza

    2012-01-01

    Full Text Available El objetivo del estudio fue evaluar el comportamiento productivo de ovinos complementados con bloques nutricionales en confinamiento y pastoreo. Se llevaron a cabo dos experimentos, el Experimento 1 se realizó con ovinos en confinamiento, el Experimento 2 se realizó con ovinos en pastoreo continuo en pastizales nativos. Para ambos experimentos 1 y 2 se utilizaron quince ovinos F1 (Dorper x Pelibuey, con un peso inicial de 17±3 y 26 ± 3 kg respectivamente. Los tratamientos en el experimento 1 fueron: T1= dieta basal + BN1 (conteniendo L. Leucocephala T2= dieta basal + BN2 (conteniendo salvado de trigo y T3= Dieta basal (Testigo. Los tratamientos en el Experimento 2 fueron: T1= Pastoreo + BN1, T2= Pastoreo + BN2 y T3= Pastoreo (control. Las variables respuestas en ambos experimentos fueron: ganancia diaria de peso (GDP, consumo de bloque nutricional (CBN, consumo de dieta basal (CDB consumo total (CT, digestibilidad aparente de la materia seca de bloques nutricionales (DAMSBN, digestibilidad aparente de la materia seca de la dieta basal (DAMSDB. En ambos experimentos los datos se analizaron mediante un diseño completamente al azar. En el Experimento 1 se encontraron diferencias en la GDP (P

  10. Insights from Siting New Nuclear Power Plants in the Central and Eastern United States

    Munson, Clifford G.; Kugler, Andrew J.

    2011-01-01

    The staff of the U.S. Nuclear Regulatory Commission (NRC) has completed its review for four early site permits and for four standard reactor designs. It is currently reviewing applications for fourteen combined license applications and three additional reactor designs. The staff is applying lessons it has learned from the reviews to date to the review work going forward. The licensing process being used by current applicants differs significantly from that used by the current operating fleet. The previous process required two steps. First an applicant had to obtain a construction permit to build the plant. Then, near the end of construction, the applicant had to obtain an operating license. Under the process in Part 52, an applicant can apply for a combined license (COL) that allows construction and (once certain conditions are met) operation of a new plant - a one-step process. An applicant for a COL may reference an early site permit (ESP13), a standard design certification, both, or neither. In addition to developing Part 52, the NRC also revised CFR Part 100 by adding Subpart B, which includes sections 100.21, 'Non-seismic siting criteria', and 100.23, 'Geologic and seismic siting criteria'. The NRC staff also revised the Standard Review Plan (NUREG-0800) and developed Regulatory Guide (RG) 1.206, 'Combined License Applications for Nuclear Power Plants (LWR Edition).' The NRC staff incorporated into the revision of NUREG-0800 and development of RG 1.206 some early lessons learned from its review of the first three ESPs. Staff work begins before the application is received, as the staff interacts with the applicant to identify issues that will require special treatment or specific staff resources. After the application is submitted, if the NRC finds the application acceptable, the safety and environmental reviews begin, proceeding in parallel. The safety review culminates in the issuance of a safety evaluation report (SER) after it

  11. 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

    Nori Paulo Griebeler

    2009-03-01

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    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.

  12. 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

    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

  13. Intelligent system for accident identification in NPP; Sistema inteligente para la identificacion de accidentes en centrales nucleares

    Hernandez, J L [Centro Nacional de Seguridad Nuclear, La Habana (Cuba)

    1999-12-31

    Accidental situations in NPP are great concern for operators, the facility, regulatory bodies and the environmental. This work proposes a design of intelligent system aimed to assist the operator in the process of decision making initiator events with higher relative contribution to the reactor core damage occur. The intelligent System uses the results of the pre-operational Probabilistic safety Assessment and the Thermal hydraulic Safety Analysis of the NPP Juragua as source for building its knowledge base. The nucleus of the system is presented as a design of an intelligent hybrid from the combination of the artificial intelligence techniques fuzzy logic and artificial neural networks. The system works with variables from the process of the first circuit, second circuit and the containment and it is presented as a model for the integration of safety analyses in the process of decision making by the operator when tackling with accidental situations

  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

    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. 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

    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)

  16. 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

    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)

  17. 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

    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.

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

    Bellaize, N.

    2000-01-01

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

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

    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

  20. 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

    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)

  1. AGATISFLAVONA, UM BIFLAVONOIDE COM APLICAÇÕES FARMACOLÓGICAS PARA O SISTEMA NERVOSO CENTRAL: REVISÃO

    Anderson Wilbur Lopes Andrade

    2018-03-01

    Full Text Available Os compostos fenólicos formam uma das principais classes de metabólitos secundários sintetizados por plantas e, entre estes, é possível destacar os flavonoides. Os biflavonoides, uma das classes de flavonoides, possuem diversas propriedades biológicas inerentes ao grupo, como antioxidante, anti-inflamatória, antitumoral, dentre outras. A agatisflavona é um biflavonoide que demonstrou, em estudos anteriores, in vitro e in vivo, atividades: neuroprotetora e antiepiléptica. O objetivo desta pesquisa foi realizar uma prospecção científica e tecnológica sobre o biflavonoide agatisflavona e suas aplicações farmacêuticas em algumas patologias relacionadas ao Sistema Nervoso Central (SNC. O EndNote-X5 software foi utilizado como referência, com as palavras-chave: agatisflavona, antioxidante, ansiolítico, neuroprotetor, antidepressivo e suas correlações em Inglês e Português. Foram utilizados documentos publicados nos bancos de dados PubMed, Science Direct, Scopus, Periódicos da Coordenação de Aperfeiçoamento de Pessoal de Nível Superior, Web of Science e American Chemical Society Publications, no Banco Europeu de Patentes, da Organização Mundial de Propriedade Intelectual, no Banco Americano de Marcas e Patentes e do Instituto Nacional de Propriedade Industrial do Brasil. Do ponto de vista científico, a agatisflavona apresenta um extenso número de publicações no que se refere à suas atividades farmacológicas (antimicrobiana, antivirais, anticarcinogênica e se destaca como composto potencialmente ativo sobre o SNC (neurogênese e diminuição da excitabilidade do SNC. Porém, não foram verificados depósitos de patentes que correlacionam o biflavonoide agatisflavona a desordens neurológicas. Este fato, por sua vez, permite o desenvolvimento de pesquisas inovadoras referentes às ações farmacológicas da agatisflavona, em especial ao SNC.

  2. The nuclear bomb carbon curve recorded in tree-rings and lake sediments near Taal Volcano, Central Philippines

    Liou, M. S.; Li, H. C.; Huang, S. K.; Guan, B. T.

    2017-12-01

    Dendrochronologies built from precisely dated annual rings have shown to record the regional bomb pulse and the C-14 concentration variations caused by local events. In this study, we collected teak trees Tectona grandis near the Lake Taal, Central Philippines in 2011 for dendrochronological analysis and radiocarbon dating. The tree-ring sample contains 90 rings dated from 1922 to 2011. Currently, 28 selected subsamples have been measured by AMS 14C on bulk carbon with a few samples on holocellulose. The 14C results of the samples indicate that: 1) the results of AMS 14C dating between holocellulose and whole wood from the same ring are similar, so we select whole wood for AMS 14C dating. 2) The nuclear bomb 14C pulse was clearly recorded in the Tectona grandis growth rings. The Δ14C values rose dramatically in 1960 and reached a maximum of 692‰ in 1966. The magnitude and the peak year of the bomb curve in the Tectona grandis tree-ring record are comparable to other published tree-ring records in the tropical regions. 3) The Δ14C values suddenly dropped in 1950, 1964 and 1968, probably affected by CO2 gas releasing due to the Taal volcanic activities. Further study on the tree-ring 14C dating will allow us to evaluate the bomb pulse trends more precisely, and the volcanic activities of Pinatubo and Taal Volcanoes. The tree-ring Δ14C record not only confirms existence of the bomb curve in Taal Lake area, but also allows us compare to the Δ14C record in the lake sediment for chronological construction. A 120-cm gravity core, TLS-2, collected from Lake Taal in 2008, shows the nuclear bomb carbon curve in the TOC of the core. However, the magnitude of the nuclear bomb 14C pulse in the TOC of TLS-2 is much lower than that in the tree-ring records, due to mixing effect of different organic carbon sources, smoothing effect of 14CO2 in multiple years plant growths, local old CO2 emission from volcanic activity, degassing from the lake bottom, and industrial and city

  3. A report on recent progress of Central Analytical Laboratory (NRI Rez plc.) for upgrading capabilities for identification of illicit nuclear materials

    Malek, Z.; Sus, F.

    2002-01-01

    Full text: In the first half of the 90's, the State Office for Nuclear Safety (SONS) -- in close co-operation with other state organizations and following the IAEA's extended safeguards system - strengthened its attention to the development of procedures for the characterization of unknown nuclear materials. This problem become important in the context of increasing danger of illicit trafficking of nuclear material which emerged with the political changes in former 'Comecon' countries during late 80's and 90's. Particular attention has been drawn to the upgrade of the counter-potential in possible transit countries situated in Central Europe. The Central Analytical Laboratory as the main Czech institution working in the field of nuclear material analytical chemistry participated in the development and upgrading of analytical procedures for detailed identification and characterization of nuclear material samples. The special methods for the determination of uranium content, isotopic composition, swipe sample analysis, determination of age and long-lived radioisotopes were developed. In second half of the 90's within the IAEA Project entitled 'Special Analytical Methods for Determination of Traces Radioactivity and Detection of Undeclared Nuclear Activities' basic procedures were prepared for the determination of: - selected isotopes of the natural disintegration series in the samples of water, sediments and technological waste solutions after termination of the uranium ores mining, - age of uranium and plutonium materials based on the 230 Th/ 234 Th, 226 Ra/ 234 U and 241 Am/ 241 Pu pairs, studies on the application of the 231 Pa/ 235 U pair were started. In 1998 PHARE PH5.01/95 project, 'Assistance in setting up special analytical services including a data bank for analysis of radioactive substances and nuclear materials of unknown origin' was started. The project was funded from the European Commission's PHARE Programme. The activities were performed at the

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

    Mello, Luiz A. de; Monteiro Filho, Joselio S.; Belem, Lilia M.J.; Torres, Luiz F.B.

    2009-01-01

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

  5. Instruction of 27 March 1973 concerning implementation of Decree No 73-278 of 13 March 1973 setting up a Higher Council for Nuclear Safety and a Central Service for the Safety of Nuclear Installations

    1973-01-01

    This Instruction specifies, on the basis of the 1973 Decree, the duties, in particular regarding licensing, of the Central Service for the Safety of Nuclear Installations. The Service is assisted in its work by the Atomic Energy Commission (CEA) and advisory groups.(NEA) [fr

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

    Carpenter, A.V.; Flanders, W.D.; Frome, E.L.; Crawford-Brown, D.J.; Fry, S.A.

    1987-03-01

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

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

    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.

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

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

    1997-12-31

    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.

  9. Relationships between nuclear magnetic resonance parameters used to characterize weathering spilled oil and soil toxicity in central Patagonia.

    Ríos, Stella Maris; Barquin, Mercedes; Katusich, Ofelia; Nudelman, Norma

    2014-01-01

    Oil spill in the Central Patagonian zone was studied to evaluate if any relationship exists between the parameters used to characterize weathering spilled oil and soil toxicity for two plant species and to evaluate if the phytotoxicity to local species would be a good index for the soil contamination. Nuclear magnetic resonance (NMR) structural indexes and column chromatography compositional indexes were determined to characterize the oil spill in the soil samples. Bioassays were also carried out using Lactuca sativa L (reference) and Atriplex lampa (native species) as test organisms. Measurements of the total petroleum hydrocarbon (TPH) and the electrical conductivity (EC) of the soil were carried out to evaluate the effect on the bioassays. The principal components analysis of the parameters determined by NMR, compositional indexes, EC, TPH, and toxicology data shows that the first three principal components accounted for the 78% of the total variance (40%, 25%, and 13% for the first, second, and third PC, respectively). A good agreement was found between information obtained by compositional indexes and NMR structural indexes. Soil toxicity increases with the increase of EC and TPH. Other factors, such as, the presence of branched and aromatic hydrocarbons is also significant. The statistical evaluation showed that the Euclidean distances (3D) between the background and each one of the samples might be a better indicator of the soil contamination, compared with chemical criterion of TPH.

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

    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.

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

    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.

  12. 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

    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.

  13. Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

    Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

    1966-02-15

    matieres nucleaires ne se limite pas S de simples travaux d'inventaire mais sert de base a beaucoup d'autres activites qui font partie integrante du programme d'operations de tout reacteur, par exemple les expeditions de combustible irradie, le traitement chimique du combustible epuise et la comptabilite du combustible recupere et des matieres produites au cours du fonctionnement du reacteur, et l'institution et l'application d'un regime d'assurance satisfaisant. (author) [Spanish] Combustible relativamente nuevo y sumamente valioso para la produccion de energia electrica, el uranio requiere un control muy minucioso desde el momento en que la direccion de una central asume la responsabilidad financiera inherente a su posesion hasta que como combustible parcialmente agotado se transfiere a otra instalacion en la que se recupera la parte que no se ha consumido. Antes de que se descubriera la posibilidad de emplear la energia nuclear para producir electricidad, la mayor parte de las empresas que actualmente explotan centrales nucleares explotaban centrales alimentadas con combustibles fosiles y hablan establecido sistemas de control relativamente completos y adecuados para los combustibles de ese tipo. Los responsables de las centrales nucleoelectricas deben disponer de sistemas no menos adecuados para controlar los materiales nucleares especiales que utilizan. La explotacion de los reactores de potencia no es una ciencia antigua, pero durante el tiempo relativamente corto que ha transcurrido desde que se inicio su empleo los ingenieros y hombres de ciencia han mejorado continuamente el diseflo del equipo y los metodos de trabajo con objeto de disminuir los costos de produccion y de lograr que las centrales nucleares puedan competir en el plano economico con las centrales clasicas. La administracion de los materiales nucleares debe efectuarse con metodos modernos y eficientes a fin de que los adelantos tecnologicos que han permitido reducir los costos no resulten inutiles

  14. Control democrático sobre el manejo de la banca central. Un reto para la política del conocimiento económico

    Carlo Tognato

    2004-07-01

    Full Text Available La globalización económica ha acelerado la transformación de la racionalidad económica en racionalidad política. Durante esta transformación, la naturaleza de la pregunta del control democrático sobre las agencias económicas ha cambiado de forma radical. Lo que antes era puramente una cuestión institucional, hoy se ha convertido en una cuestión epistémica. Para reestablecer un control democrático efectivo sobre las agencias económicas, la democracia debe penetrar los fundamentos de la racionalidad económica misma, pilar sobre la cual la tecnocracia económica basa su operación. En otras palabras, es necesario practicar controles democráticos de carácter epistémico. Esta visión implica un giro Foucaultiano con respecto a la literatura tradicional sobre el diseño de las instituciones económicas. Además, llama al analista a mirar a la tecnocracia económica como una faceta organizacional de una formación discursiva, y a reconocer que un cambio en la operación de la tecnocracia económica requiere un cambio de otras facetas de su propia formación discursiva. Aquí daré cuenta de algunos de los cambios que implica la democratización de una de las tecnocracias económicas más impermeables al escrutinio democrático externo - la banca central independiente. En particular, mostraré que la democratización de la banca central independiente tiene implicaciones reflexivas importantes sobre la estructura argumentativa económica que la sostiene así como sobre la organización de la disciplina económica que articula dicha argumentación. En otras palabras, la democratización del objeto de análisis llama a una democratización del proceso de generación del conocimiento por medio del cual el objeto se constituye. PALABRAS CLAVES. Globalización banca central, control democrático.

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

    Luis Sánchez Vázquez

    2011-06-01

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

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

    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...

  17. Fundamental bases to implementation the specific national norm for nuclear gauges; Bases fundamentais para a implantação de norma nacional específica para medidores nucleares

    Ferreira, L.C.; Silva, E.R.; Ferreira, R.; Peixoto, J.G.P., E-mail: luizxiii@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The aims of this work is to provide grounds for creation a national standard practice security and responsibility in the use of nuclear gauges in accordance with the national recommendation already exist, following the basic security principles, responsibilities of these involved in the acquisition, operation, storage, maintenance and post-emergency on use of nuclear gauges. (author)

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

    de la Paz Blanco, Carlos

    2012-01-01

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

  19. 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

    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...

  20. Bases para el estudio de la competitividad de la produccion de papa de las agroempresas campesinas de la region central de Boyaca

    Rodriguez Luis Felipe

    1997-06-01

    Full Text Available

    Para el Departamento de Boyacá, la problemática más relevante en los aspectos tecnologico y socioeconómico en el contexto del Sector Agropecuario, se centra en el gremio de los productores de papa, especialmente en los pequeños agroempresarios. En esta región, existe un marcado predominio de los pequeños cultivos de papa, atendidos básicamente por sus dueños, arrendatarios o aparceros. La demasiada parcelación del terreno ha sido un factor determinante para su bajo nivel de mecanizaci6n. En Boyacá, se resalta la existencia de varias zonas donde el cultivo de papa se constituye en el epicentro, en torno al cual gravita la actividad productiva de una gran cantidad de pequeñas agroempresas de carácter campesino, que operan en este departamento. Dentro de tales zonas, la zona central de Boyacá se constituye en un espacio geográfico representativo de la produccion agropecuaria campesina, donde la población dedicada a la producción de papa presenta un deficiente nivel de vida, como consecuencia de los bajos niveles de productividad y de la problemática comercial que tienen que enfrentar en la fase de posproduccion de tal especie agrícola.

    Palabras claves: Agroempresas campesinas, productor, productividad, cultivos múltiples, rentabilidad, comercialización.

  1. Sector activities related to spent nuclear fuel in the spanish nuclear power plants; Actuaciones sectoriales en relaci@n con el combustible nuclear gastado en las centrales nucleares espa@olas.

    Francia, L.

    2016-07-01

    Royal Decree 102/2014 of February 21 defines spent nuclear fuel as the irradiated nuclear fuel in the reactor core that is permanently removed from it. Spent nuclear fuel can be considered either as a usable resource that can be reprocessed, or else as a radioactive waste destined for final disposal. Likewise, spent nuclear fuel management refers to all the activities related to handling, temporary storage, reprocessing and final storage. The article presents all the plans and actions taken by the nuclear power plants, which can be divided into the following two categories: Actions taken by the plants themselves to not only maintain the fuel in stable, safe conditions, but also to characterize and process it for the subsequent management routes established by the current General Radioactive Waste Plan. Activities undertaken under the UNESA umbrella to help implement the above mentioned management routes.

  2. Software for the nuclear reactor dynamics study using time series processing; Software para el estudio de la dinamica de reactores nucleares mediante el procesamiento de series temporales

    Valero, Esbel T.; Montesino, Maria E. [Instituto Superior de Ciencia y Tecnologia Nuclear (ISCTN), La Habana (Cuba)

    1997-12-01

    The parametric monitoring in Nuclear Power Plant (NPP) permits the operational surveillance of nuclear reactor. The methods employed in order to process this information such as FFT, autoregressive models and other, have some limitations when those regimens in which appear strongly non-linear behaviors are analyzed. In last years the chaos theory has offered new ways in order to explain complex dynamic behaviors. This paper describes a software (ECASET) that allow, by time series processing from NPP`s acquisition system, to characterize the nuclear reactor dynamic as a complex dynamical system. Here we show using ECASET`s results the possibility of classifying the different regimens appearing in nuclear reactors. The results of several temporal series processing from real systems are introduced. This type of analysis complements the results obtained with traditional methods and can constitute a new tool for monitoring nuclear reactors. (author). 13 refs., 3 figs.

  3. The nuclear power stations of the French atomic energy programme (1960); Les centrales nucleaires de puissance du programme francais (1960)

    Leduc, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Roux, J P [Electricite de France (EDF), 75 - Paris (France)

    1960-07-01

    After recalling the entry of nuclear energy into energy production in France, the paper emphasizes the evolution of techniques applied in the designing of French nuclear power plants and describes the means employed for reducing costs per kWh of EDF2 and EDF3 compared with EDF1: the electric power per ton of uranium varies from 493 kW/t for EDF1 to 970 kW/t for EDF3. For this purpose the thermal power and electric power of units are changed respectively from 290 MWt for EDF1 to 1200 or 1600 MWt for EDF3 and from 28 to 250 MW. The results are obtained by an improvement in neutronic characteristics, developments in nuclear fuel technology, and simplification of the system of charging the reactor, whose means of maintenance are increased; the EDF2 heat-exchangers have been so designed as to increase the unit power of the elements, which will attain 9 MWt, as against 3 for EDF1. For EDF3 an advance project forecasts a thermodynamic layout with only one pressure stage. The paper ends with a description of the burst-slug detection systems, and an appendix gives a detailed comparative table of EDF1, EDF2 and EDF3 plant characteristics. (author) [French] Apres avoir rappele l'integration de l'energie nucleaire parmi les moyens de production de l'energie en France, les auteurs se penchent surtout sur l'evolution des techniques appliquees dans l'equipement des centrales nucleaires francaises et decrivent les moyens mis en oeuvre pour reduire les prix de revient du kWh d'EDF2 et d'EDF3 par rapport a EDF1: la puissance electrique par tonne d'uranium varie de 493 kW/t pour EDF1 a 970 kW/t pour EDF3. C'est dans ce but que les puissances thermiques et la puissance unitaire des groupes turbo-alternateurs passent respectivement de 290 MWt pour EDF1 a 1200 ou 1600 MWt pour EDF3 et de 82 a 250 MW. Les resultats sont obtenus par une amelioration des caracteristiques neutroniques, des progres realises sur la technologie des elements combustibles, une simplification du systeme de

  4. 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

    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)

  5. Suggestions of radiation protection instruments in ships used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants

    Warenmo, G.

    1979-01-01

    Some radiation protection measures are necessary in ships which will be used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants in order to protect the crew from unnecessarily high radiation doses and to ensure that not allowable values occur. Such measures are discussed in this report as well as suitable radiation protection instruments for such ships. (E.R.)

  6. Temperature and density of nuclear matter in central CC interactions at P=4.2 GeV/c per nucleon

    Didenko, L.A.; Grishin, V.G.; Kowalski, M.; Kuznetsov, A.A.

    1984-01-01

    An estimation of the temperature and density of nuclear matter in central carbon-carbon interactions at P/A=4.2 GeV/c is presented. It is shown that at energies of about 4 GeV per nucleon it is possible to reach the transitional region between hadronic matter and quark-gluon plasma. The results could be however more convincing if one uses heavier ions than carbon

  7. 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

    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

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

    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.

  9. 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

    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)

  10. 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

    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.

  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

    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. Basic information to improve public acceptance to nuclear energy in Brazil; Subsidios para a melhoria da aceitacao da energia nuclear no Brasil

    Gibelli, Sonia M.O.; Lima e Silva, Pedro Paulo de; Xavier, Ana Maria [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    In Brazil, the current production of nuclear energy is restricted to Angra I plant, a 657 MW pressurized water reactor, in operation since 1982. Among the eight units predicted in 1975 within the Brazil Germany nuclear agreement, only two have been effectively contracted, namely Angra 2 and 3. The nuclear alternative, likewise all other energy sources, is very much dependable on the assessment of their own benefits compared to the associated risks posed to the population and the environment. The main goal of this article is to provide information to enable the improvement of public acceptance of the use of nuclear energy in the country, by comparing risks associated with different sources as well as pointing out aspects related to risk perception by the public. (author) 18 refs., 5 figs.; e-mail: sonia at cnen.gov.br; lima-e-silva at pobox.com; axavier at cnen.gov.br

  13. 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

    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)

  14. 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

    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.

  15. 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

    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.

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

    Batista, Wagner Fonseca

    2011-07-01

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

  17. Software development for managing nuclear material database; Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear

    Tondin, Julio Benedito Marin

    2011-07-01

    In nuclear facilities, the nuclear material control is one of the most important activities. The Brazilian National Commission of Nuclear Energy (CNEN) and the International Atomic Energy Agency (IAEA), when inspecting routinely, regards the data provided as a major safety factor. Having a control system of nuclear material that allows the amount and location of the various items to be inspected, at any time, is a key factor today. The objective of this work was to enhance the existing system using a more friendly platform of development, through the VisualBasic programming language (Microsoft Corporation), to facilitate the operation team of the reactor IEA-R1 Reactor tasks, providing data that enable a better and prompter control of the IEA-R1 nuclear material. These data have allowed the development of papers presented at national and international conferences and the development of master's dissertations and doctorate theses. The software object of this study was designed to meet the requirements of the CNEN and the IAEA safeguard rules, but its functions may be expanded in accordance with future needs. The program developed can be used in other reactors to be built in the country, since it is very practical and allows an effective control of the nuclear material in the facilities. (author)

  18. 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

    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.

  19. Calculation of absorbed dose for skin contamination imparted by beta radiation through the VARSKIN modified code for 122 interesting isotopes for nuclear medicine, nuclear power plants and research; Calculo de dosis absorbida para contaminacion en piel impartida por radiacion beta mediante el codigo VARSKIN modificado para 122 isotopos de interes para medicina nuclear, plantas nucleares e investigacion

    Alvarez R, J T [Depto. de Metrologia, ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1991-07-01

    In this work the implementation of a modification of the VARSKIN code for calculation of absorbed dose for contamination in skin imparted by external radiation fields generated by Beta emitting is presented. The modification consists on the inclusion of 47 isotopes of interest even Nuclear Plants for the dose evaluation in skin generated by 'hot particles'. The approach for to add these isotopes is the correlation parameter F and the average energy of the Beta particle, with relationship to those 75 isotopes of the original code. The methodology of the dose calculation of the VARSKIN code is based on the interpolation, (and integration of the interest geometries: punctual or plane sources), of the distribution functions scaled doses in water for beta and electrons punctual sources, tabulated by Berger. Finally a brief discussion of the results for their interpretation and use with purposes of radiological protection (dose insurance in relation to the considered biological effects) is presented.

  20. Nuclear

    2014-01-01

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

  1. Relationships between central and prefectural government for the nuclear energy development in the era of decentralization. Lesson from Germany

    Murata, Takashi

    1999-01-01

    In spite of the fact that nuclear power covers one third of the Japanese electric demand, siting of the nuclear installations faces very difficult problems to cope with. Among the reasons there is a lack of the consensus of the people at large on the legal and administrative procedures for the construction of the facilities in the context of decentralization of political system. Referring the federal legal system under the German Basic Law and its relationship with nuclear energy development, this paper analyzes and proposes several legal and administrative improvements in Japanese political integration system for the nuclear development in the era of Decentralization. (author)

  2. 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

    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

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

    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.

  4. Design of the HMI for the operation of a nuclear research reactor; Diseno del HMI para la operacion de un reactor nuclear de investigacion

    Bucio V, F. J.; Celis del Angel C, L.; Palacios H, J. C., E-mail: francisco.bucio@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    The Instituto Nacional de Investigaciones Nucleares (ININ) participated in an international tender published by the Colombian Geological Service for the modernization of the Nuclear Reactor Control Console Ian-R1, the participating institutions were: General Atomics (USA), INVAP (Argentina) and ININ (Mexico). The proposal made by the ININ had an important characteristic, the independence of the manufacturer, since it was a project based on modular elements. One of the elements was the Human-Machine Interface (HMI), where the development was proposed under the Free Software (Gnu-GLP) scheme. Java was the programming language on which the HMI was developed to operate the nuclear reactor in Bogota, Colombia. The instrumentation that allows the interaction with the sensors and/or actuators is based on the use of PLC's (programmable logic controllers) with which the computers of the HMI communicate through a local network using the Mod bus protocol over Ethernet. (Author)

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

    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)

  6. Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Spanish Edition); Seguridad de las centrales nucleares: Diseno. Requisitos de seguridad especificos

    NONE

    2012-04-15

    This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

  7. Modernization of the pre-treatment plants in Almaraz and Trillo Nuclear Power Plants; Actualizacion de las plantas de pretratamiento en las centrales nucleares de Almaraz y Trillo

    Pascual Carballo, N.

    2010-07-01

    Description of the modernization project carried out in Almaraz and Trillo Nuclear Power Plants where EEAA. participates supporting and monitoring the RFQ, the design and the supplies as well as the documentary update and the design of new plants interconnection.

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

    Chiripus, Vlad-Ionut

    2004-01-01

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

  9. Arrangements for preparedness for a nuclear or radiological emergency. Safety guide (Spanish Edition); Disposiciones de preparacion para emergencias nucleares o radiologicas. Guia de seguridad

    NONE

    2010-07-15

    Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and available results of research relating to response to such emergencies. The primary objectives of this Safety Guide, co-sponsored by FAO, OCHA, ILO, PAHO and WHO, are to provide guidance on preparedness and response for a nuclear or radiological emergency, to describe appropriate responses to a range of emergencies, and to provide background information on past experience, thus helping the user to better implement arrangements that address the underlying issues.

  10. 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

    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

  11. 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

    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)

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

    Lorenz, A.

    1982-12-01

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

  13. Estimation of the costs of electricity generation in nuclear and other types of power stations; Estimacion de costes de generacion de electricidad en centrales nucleares y otros tipos de centrales

    Col Buti, P.; Tapia Fernandez, C.

    2002-07-01

    (Study of the Nuclear Power Sector in the Context of the Energy Study in Catalonia to the 2020 Horizon) prepared by the same authors, which analyses the characteristics of the nuclear sector in Catalonia. This an other studies has provided the basis for the preparation of the Pla de l'Energia a Catalunya a l'Horitzo de l'Any 2010 (Catalonia Energy Plan to the 2010 Horizon). (Author)

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

    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)

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

    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)

  16. 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?

    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)

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

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

    2015-07-01

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

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

    Cradduck, T.D.; Driedger, A.A.

    1981-01-01

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

  19. 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

    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

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

    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)

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

    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)

  2. 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

    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)

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

    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)

  4. Proposal of guidelines for structuring an independent regulation body for the Brazilian nuclear sector; Proposta de diretrizes para estruturacao de um orgao de regulacao independente para o setor nuclear brasileiro

    Nicoll Junior, Ricardo

    2016-07-01

    Regulatory bodies are responsible for regulation in various sectors of society. In Brazil, they work in various areas for the development of the country and have as main objective the social, economic and national development. The progress of new technologies in the nuclear field and their commercialization underscores the need for regulation according to international safety standards. The present research searches through an extensive review of the literature identify the international guidelines for regulatory bodies and make a comparative analysis between Brazil and five countries that have independent regulatory bodies in the nuclear sector. The purpose of the work is to contribute to the Brazilian public sectors, with an evaluation of the country's regulation in the perception of specialists and propose guidelines for the structuring of an independent regulatory body, respecting international agreements and the legislation in force in the country. (author)

  5. 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

    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)

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

    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.

  7. 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

    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)

  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

    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. 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?

    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)

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

    National Frederic Joliot-Curie Research Institute for Radiobiology and Radiohygiene

    2007-01-01

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

  11. Reactor inventory monitoring system for Angra-1 reactor; Sistema de monitoracao de inventario do reator para usina nuclear Angra I

    S Neto, Joaquim A.; Silva, Marcos C.; Pinheiro, Ronaldo F.M. [Furnas Centrais Eletricas S.A., Rio de Janeiro, RJ (Brazil); Soares, Milton [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Martinez, Aquilino; Comerlato, Cesar A.; Oliveira, Eugenio A. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Lab. de Monitoracao de Processos

    1996-07-01

    This work describes the project of Reactor Inventory Monitoring System, which will be installed in Angra I Nuclear Power Plant. The inventory information is important to the operators take corrective actions in case of an incident that may cause a failure in the core cooling. (author)

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

    Pham Duy Hien; Ngo Quang Huy; Vu Hai Long; Tran Khanh Mai

    1994-01-01

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

  13. 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

    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)

  14. 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

    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

  15. 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

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

    1998-12-31

    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

  16. Cenozoic biogeography and evolution in direct-developing frogs of Central America (Leptodactylidae: Eleutherodactylus) as inferred from a phylogenetic analysis of nuclear and mitochondrial genes.

    Crawford, Andrew J; Smith, Eric N

    2005-06-01

    We report the first phylogenetic analysis of DNA sequence data for the Central American component of the genus Eleutherodactylus (Anura: Leptodactylidae: Eleutherodactylinae), one of the most ubiquitous, diverse, and abundant components of the Neotropical amphibian fauna. We obtained DNA sequence data from 55 specimens representing 45 species. Sampling was focused on Central America, but also included Bolivia, Brazil, Jamaica, and the USA. We sequenced 1460 contiguous base pairs (bp) of the mitochondrial genome containing ND2 and five neighboring tRNA genes, plus 1300 bp of the c-myc nuclear gene. The resulting phylogenetic inferences were broadly concordant between data sets and among analytical methods. The subgenus Craugastor is monophyletic and its initial radiation was potentially rapid and adaptive. Within Craugastor, the earliest splits separate three northern Central American species groups, milesi, augusti, and alfredi, from a clade comprising the rest of Craugastor. Within the latter clade, the rhodopis group as formerly recognized comprises three deeply divergent clades that do not form a monophyletic group; we therefore restrict the content of the rhodopis group to one of two northern clades, and use new names for the other northern (mexicanus group) and one southern clade (bransfordii group). The new rhodopis and bransfordii groups together form the sister taxon to a clade comprising the biporcatus, fitzingeri, mexicanus, and rugulosus groups. We used a Bayesian MCMC approach together with geological and biogeographic assumptions to estimate divergence times from the combined DNA sequence data. Our results corroborated three independent dispersal events for the origins of Central American Eleutherodactylus: (1) an ancestor of Craugastor entered northern Central America from South American in the early Paleocene, (2) an ancestor of the subgenus Syrrhophus entered northern Central America from the Caribbean at the end of the Eocene, and (3) a wave of

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

    1993-01-01

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

  18. Pointing Out Main Factors from Design, Construction and Operating Experience of Existing Nuclear Plants for Assisting in Shaping Future Nuclear Power Programmes; Les principaux criteres degages de l'etude, de la construction et de l'exploitation des centrales nucleaires existantes et leur interet pour l'elaboration des futurs programmes d'energie d'origine nucleaire; Ukazanie osnovnykh faktorov proektirovaniya, stroitel'stva i opyta ehkspluatatsii sushchestvuyutsikh atomnykh ehlektrostantsij, chto dolzhno pomoch' pri sostavlenii budushchikh programm atomnoj ehnergetiki; Principales consideraciones relativas al diseno, construccion y explotacion de centrales nucleares, encaminadas a facilitar la preparacion de programas futuros de energia nucleoelectrica

    Dalla Volta, F. [Comitato Nazionale per l' Energia Nucleare, Rome (Italy)

    1963-10-15

    incessamment entrer en service en Italie, aideraient a etablir les plans des installations futures. Il suggere la possibilite de prevoir des maintenant des cycles de combustible pour une plus longue periode. (author) [Spanish] En la memoria se examinan las principales consideraciones de caracter tecnico y eco nomico relativas al diseno, construccion y explotacion de las primeras centrales nucleoelectricas a plena escala, y que mas pueden ayudar a preparar los planes futuros de expansion nuclear, con especial referencia a las condiciones que reinan en Italia. El estado actual de la tecnologia de los reactores y su evolucion continua en la ejecucion de los proyectos hasta ahora realizados, muestra una neta tendencia hacia la reduccion de los costos del ciclo de combustible y de los elementos componentes de las centrales. Contribuye a esta evolucion la tendencia cada vez mas acusada a construir centrales de mayores dimensiones, y el hecho de que las previsiones acerca de las condiciones futuras de la red electrica sugieren la conveniencia de instalar centrales nucleares de mayor capacidad que las centrales clasicas, en razon de la disminucion que experimentaran los gastos de produccion gracias a la puesta en servicio de esas nuevas unidades. En lo que se refiere a la experiencia adquirida en e l diseno, construccion y pruebas de las centrales en funcionamiento, la memoria estudia los principales factores que han de tenerse en cuenta en la preparacion de planes para el futuro, tambien desde e l punto de vista de los programas de construccion y de pruebas. El autor insiste en el problema del confinamiento, en razon de la favorable influencia que sobre la elecion del emplazamiento de las centrales puede ejercer el perfeccionamiento de blindajes muy seguros, que podrian construirse sin aumento sensible del costo, teniendo en cuenta la especial situacion de Italia en lo que se refiere a ciertos aspectos del problema. En cuanto a la experiencia adquirida en la explotacion de centrales

  19. Benchmarking on the management of radioactive waste in the Spanish Nuclear Power; Benchmarking sobre la gestion de residuos radiactivos en las Centrales Nucleares Espanola

    Rodriguez, M. A.; Gonzalez, R.; Gomez, N.

    2012-07-01

    The main objective of this project is to perform a comparative evaluation of the practices carried out in the field of waste management in the Spanish nuclear power plants. Once compared such practices have been established recommendations that may be of interest for application in other plants.

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

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

    2010-07-01

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

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

    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)

  2. 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

    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)

  3. 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

    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

  4. Mapa de cuidados para pacientes sometidos a procedimientos en servicios de medicina nuclear Care map for patients under nuclear medicine procedures

    Cayetano Fernández Sola

    2009-03-01

    Full Text Available Objetivo: desarrollar un instrumento que facilite la sistematización, registro y continuidad del cuidado en servicios de medicina nuclear. Metodología: investigación desarrollada durante 2004 en el servicio de Medicina Nuclear en un Hospital de Almería, España. A partir de la revisión bibliográfica y de la práctica clínica, se realizó búsqueda de problemas de enfermería y de colaboración y se procedió a la estandarización y codificación del lenguaje según taxonomías NANDA, NOC y NIC. Luego de la valoración inicial, focalizada por necesidades básicas, se formularon diagnósticos de enfermería y de complicaciones; y las intervenciones asociadas a los diagnósticos y a problemas de colaboración. Finalmente se realizó seguimiento, evaluación e informe de continuidad de cuidados. Resultados: los diagnósticos de enfermería prevalentes fueron: conocimientos deficientes, temor, interrupción de la lactancia materna y riesgo de lesión. Los resultados esperados, expresados según taxonomía NOC, fueron: Conocimientos del procedimiento, Autocontrol del miedo Lactancia materna: Destete y Control del riesgo; y las Intervenciones de enfermería: Enseñanza del procedimiento, Disminución de la ansiedad, Supresión de la lactancia, Manejo ambiental de seguridad e Intervenciones asociadas a problemas de colaboración. Conclusión: el mapa de cuidados facilita el trabajo, utiliza el proceso de enfermería y ayuda a registrar las intervenciones practicadas en pacientes sometidos a procedimientos en servicios de medicina nuclear.Objective: the development of a tool that provides the systematic, registration and care continuity in the nuclear medicine services. Methodology: this research was developed during 2004 as a result of the creation of the Nuclear Medicine Service in the Torrecárdenas Hospital, in Almeria, Spain. A nursing problem review was undertaken from the data that captured in the bibliography review and clinical practice

  5. 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

    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.

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

    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.

  7. 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

    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)

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

    Gautheron, S.; Laborier, J.C.; Robert-Gnansia, E.; Chevrier, C.

    2005-01-01

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

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

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

    2006-01-01

    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)

  10. 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

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

    1990-12-31

    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).

  11. 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

    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).

  12. 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

    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

  13. Study on the efficiency of a central neutron source for the 300-MW(e)-THTR-Nuclear Power Station Schmehausen

    Gutsch, U.; Scherer, W.; Gerwin, H.

    1976-03-01

    The loading and starting phase of the THTR-300 is controlled by an external neutron source. The possible positions of this source result from the requirement to fulfil certain criteria concerning the intensity and the interpretation of the detector-signal. In this study it is investigated how far a source centrally inserted into the reactor can be equal to this task and whether it is possible to go over to a non-central position at a later point of time. It is shown that the central source can fulfil all discussed demands. A source position lying in the vicinity of the side reflector demands a special choice of the detector position, which can be exactly determined only by further three-dimensional calculations. Beyond that, this study shows that during the loading phase in the subcritical range the spatial neutron flux distribution is expected to be completely different from that of the critical reactor. (orig.) [de

  14. 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

    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)

  15. DTN and international cooperation of the Spanish Nuclear Sector in nuclear technology development processes

    Acero, M.

    1995-01-01

    The Spanish electrical utilities with interests in the Nuclear Sector-IBERDROLA, ENDESA,FUERZAS ELECTRICAS DE CATALU=A5A (FECSA), UNION ELECTRICA FENOSA S.A., COMPA=A5IA SEVILLANA DE ELECTRICIDAD S.A., AND HIDROELECTRICA DEL CANTABRICO S.A.-created on September 26, 1994 the ''Agrupacion Electrica para el Desarrollo Tecnologico Nuclear, A.I.E. (DTN)'' (Electrical Society for Nuclear technology Development A.I.E.) for the purpose of promoting and managing Nuclear Nechnology Development, and integrating and coordinating the efforts of the Nuclear Electrical Sector with industrial companies and other related institutions in spain and abroad. This mission is primarily accomplished by establinhing a common strategy for the Nuclear Electrical Sector in the different areas of responsibility of DTN, centralizing actions by implementing a clear and coherent policy, and ensuring the presence of the entire Electrical Sector in all those fora deemed to be strategic to the Nuclear Sector

  16. Nuclear power generation in competition with other sources for base load electricity generation; La generacion nuclear en competencia con otras fuentes para generacion electrica de base

    Notari, C; Rey, F C [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

    1997-12-31

    The latest studies performed by OECD and IAEA on the subject were analyzed in order to clarify the international context. Nuclear, gas and coal are compared. The general conclusion is that nuclear power is competitive for electricity generation considering new plants to be commissioned around year 2000. If the discount rate is 5% per annum it is considered the best option in most of the countries included in the studies. If 10% is chosen the levelized costs favour the gas option. In the Argentine case, the analysis of possible plants for the near future shows a clear advantage for the gas projects. This is mainly due to the low capital costs and low local gas prices. The possible evolution of this situation is considered: gas prices will most probably increase because they should approach the price of fuel oil or diesel oil which are used as substitutes in winter for electricity generation and the export projects to Chile and Brasil will also push prices up. The environmental aspects of the question and its influence on regulations and costs is a matter of speculation. Some countries have already penalized greenhouse gases emissions but it is not clear how and when this trend will affect local prices. (author). 4 refs., 6 tabs.

  17. An image analyzer system for the analysis of nuclear traces; Un sistema analizador de imagenes para el analisis de trazas nucleares

    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)

  18. Quality control in nuclear fuel fabrication on the inspection basis; Control de calidad para fabricacion de combustible nuclear en base a inspecciones

    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)

  19. Quality control in nuclear fuel fabrication on the inspection basis; Control de calidad para fabricacion de combustible nuclear en base a inspecciones

    Fuentes S, A [Instituto Tecnologico de Toluca, Toluca (Mexico)

    1998-12-31

    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)

  20. Practical approach in training (on-the-job) for workers in nuclear industries; Abordagem pratica no treinamento (on-the-job) para trabalhadores em industrias nucleares

    Vianna, Vilson Bedim; Rocha, Janine Gandolpho da [Industrias Nucleares do Brasil SA, Rio de Janeiro, RJ (Brazil)

    2005-07-01

    This work approaches the 'on-the-job training' - a method of practical training - used in nuclear industries for workers who handle radioactive nuclides. The required training must, in accordance with the ISO 9000 standard, be geared to meet the needs of the organization, including the minimization of errors in operation with radionuclides, which involves various aspects (standard, social, environmental, personal and process safety etc.). Therefore, the training process must have the commitment of everybody and have a logical and documented sequence, where both the individual and the needs of the company are raised and analyzed. The clear identification of the radiological risks associated to the hands-on training is critical to the safety of who is being trained and should be part of the training content. However, the greatest challenge is a mechanism allowing to transform the hands-on training in practical learning. The role of training in the modern nuclear industry should not be restricted to provide conditions for better training or development of the employee, but also motivate the continuous improvement of the company and of the productive process.

  1. The modernization of the nuclear power plants of Asco and Vandellos II; Modernizacion de las centrales nucleares de Asco y Vandellos II

    Martinez Anton, L.

    2011-07-01

    Since the beginning of their commercial operation, the nuclear power plants of Asco and Vandellos have made design modifications aimed at improving the safety, reliability and operation of the plants. From the moment the management of the three plants was brought together within the Association Nuclear Asco-Vandellos II, and within the assets management process, joint strategic modernisation and improvement plans have been developed on the basis of the status of equipment, the evaluation of their ageing, obsolesce, degradations, manufacturers recommendations and/or the application of new regulations. The article lists the mos important actions already carried out or in the project phase for the 3 plants in the primary and secondary system, electrical and instrumentation systems and auxiliary systems, highlighting the problems and the solutions adopted in the most relevant modifications. (Author)

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

    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)

  3. Application of the weld in maintenance mechanics at the Nuclear Power Station Atucha I; Aplicaciones de soldadura en mantenimiento de la Central Nuclear Atucha I

    Cosentino, R E

    1988-12-31

    The application of the `weld procedures`, in the field of activity of nuclear power is an special chapter of weld. The so called `Nuclear Installations` are actually under control from their contruction up to their life extension operation to special control programs and quality assurance. This situation obliges the implementation of procedures to assure the fulfilment of the programs for the need to make the reparations or mechanics construction. This paper describes the considerations that has been taken into account to repare some components of the plant. The works carried out constitute applications to the TIG weld procedure. The `lip weld` is a mechanic component required in pressurized systems subject to air pressure. (Author).

  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

    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

    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. 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

    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.

  7. Proposal for implementation of alternative source term in the nuclear power plant of Laguna Verde; Propuesta de implementacion del termino fuente alternativo en la central nuclear Laguna Verde

    Bazan L, A.; Lopez L, M.; Vargas A, A.; Cardenas J, J. B. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km. 7.5 Carretera Veracruz-Medellin, Dos Bocas, Veracruz (Mexico)], e-mail: ariadna.bazan@cfe.gob.mx

    2009-10-15

    In 2010 the nuclear power plant of Laguna Verde will implement the extended power upbeat in both units of the plant. Agree with methodology of NEDC-33004P-A, (constant pressure power up rate), and the source term of core, for accidents evaluations, were increased in proportion to the ratio of power level. This means that for the case of a design basis accident of loss of coolant an increase of power of 15% originated an increase of 15% in dose to main control room. Using the method of NEDC-33004P-A to extended power upbeat conditions was determined that the dose value to main control room is very near to regulatory limit established by SRP 6.4. By the above and in order to recover the margin, the nuclear power plant of Laguna Verde will calculate an alternative source term following the criteria established in RG 1.183 (alternative radiological source term for evaluating DBA at nuclear power reactor). This approach also have a more realistic dose value using the criterion of 10-CFR-50.67, in addition is predicted to get the benefit of additional operational flexibilities. This paper present the proposal of implementing the alternative source term in Laguna Verde. (Author)

  8. Integrated plant safety assessment: systematic evaluation program. Oyster Creek nuclear generating station. GPU Nuclear Corporation and Jersey Central Power and Light Company. Docket No. 50-219

    1982-09-01

    The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Oyster Creek Nuclear Generating Station (located in Ocean County, New Jersey), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  9. Possible uses and applications of drones in a nuclear power plant; Posibles usos y aplicaciones de los drones en una central nuclear

    Celis del A, L.; Palacios, J.; Rivero, T.; Valero, D., E-mail: lina.celis@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    The versatility of drones is one of the strengths that have led to the rapid development of this technology, as they adapt relatively easily to new applications, presenting considerable advantages such as greater energy efficiency, longer life and a significant lower operation cost than manned systems. The current applications of the drones, in addition to the military, are very wide and varied. The nuclear industry represents an important area of opportunity for drones, mainly in response to radiological emergencies, since in this case there is a latent risk of the general population being exposed to high radiation doses. Drones can be used in environments with high chemical and radiological toxicity without endangering human lives. Some of the possible applications of the drones in a nuclear power plant are: perimeter surveillance in physical security, where equipped with a high definition camera can be used as support to physical security systems in general; visual inspection at sites, structures, equipment and pipelines, etc., as part of preventive maintenance in order to avoid the loss of material due to corrosion, oxidation, cracking, subsidence; the visual inspection through thermo-graphic images to be able to detect hot spots in some critical element; measurement and radiological mapping on surfaces to maintain monitoring of radiological safety at nuclear power plant facilities; the monitoring of environmental parameters and the Environmental Impact Assessment to obtain important information to determine the environmental impact of a given area; and accident support by providing information that allows staff to size the magnitude of the damage. (Author)

  10. 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

    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.

  11. Public debate about the EPR nuclear power plant at Flamanville; Debat public sur la centrale nucleaire EPR a Flamanville

    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.)

  12. Public debate about the EPR nuclear power plant at Flamanville; Debat public sur la centrale nucleaire EPR a Flamanville

    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.)

  13. Propuesta de implementación de una guía de procedimientos para mejorar la eficiencia en los procesos de la Central de Esterilización del Hospital "Dr. Teodoro Maldonado Carbo" de la ciudad de Guayaquil.

    Payez Freire, Eva Cristina

    2015-01-01

    La presente investigación se desarrolló en la central de esterilización del Hospital Teodoro Maldonado Carbo de la ciudad de Guayaquil, perteneciente al Instituto Ecuatoriano de Seguridad Social, con la finalidad de evaluar el nivel de aplicación de los procedimientos obligatorios de esterilización y su relación con el nivel de eficiencia en los resultados obtenidos. Para el logro de los objetivos planteados se desarrolló una investigación de campo aplicando encuestas y entrevistas al...

  14. Nuclear future: thinking for building. Proceedings of the 5. Brazilian national meeting on nuclear applications; 8. General congress on nuclear energy; 12. Brazilian national meeting on reactor physics and thermal hydraulics; Futuro nuclear: refletindo para construir. Anais do 5. Encontro nacional de aplicacoes nucleares; 8. Congresso geral de energia nuclear; 12. Encontro nacional de fisica de reatores e termo-hidraulica

    NONE

    2000-07-01

    These proceedings, for the first time, present jointly the 12. Brazilian national meeting on reactor physics and thermal hydraulics (12. ENFIR), the 8. General congress on nuclear energy (8. CGEN), and the 5. Brazilian national meeting on nuclear applications (5. ENAN). The main theme of discussion was: 'Nuclear Future: thinking for building'. The papers have analysed the progresses of peaceful utilization of nuclear technology and its forecasting for the beginning of the new millennium. The construction of Angra-3 nuclear power plant have been discussed.

  15. Nuclear future: thinking for building. Proceedings of the 12. Brazilian national meeting on reactor physics and thermal hydraulics; 8. General congress on nuclear energy; 5. Brazilian national meeting on nuclear applications; Futuro nuclear: refletindo para construir. Anais do 12. Encontro nacional de fisica de reatores e termo-hidraulica; 8. Congresso geral de energia nuclear; 5. Encontro nacional de aplicacoes nucleares

    NONE

    2000-07-01

    These proceedings, for the first time, present jointly the 12. Brazilian national meeting on reactor physics and thermal hydraulics (12 ENFIR), 8. General congress on nuclear energy (8. CGEN), and 5. Brazilian national meeting on nuclear applications (5. ENAN). The main theme of discussion was: 'Nuclear Future: thinking for building'. The papers have analysed the progresses of peaceful utilization of nuclear technology and its forecasting for the beginning of the new millennium. The construction of Angra-3 nuclear power plant have been discussed.

  16. Virtual reality for training of occupationally exposed individuals in nuclear medicine; Realidade virtual para treinamento de indivíduos ocupacionalmente expostos na medicina nuclear

    Carvalho, J.S.; Carvalho, J.B.; Silveira, J.L.; Nascimento, A.C.H.; Mol, A.C.A.; Suita, J.C.; Marins, E.R., E-mail: julianedesacarvalho@gmail.com [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    Applications in virtual environments have been an important tool for education and training of skills in several areas. In Nuclear Medicine Services (NMS), whose environment is susceptible to exposure to ionizing radiation, virtual simulation is a complementary tool to the traditional way of training, able to have the required content by norm, good laboratory practices and radioprotection, interactive form without the exposure of the user. The study consists of the research and unification of recommendations, norms and procedures, collected in the scientific literature and in loco, on the activities of professionals of NMS's radiopharmacy, to define the minimum content for training in order to guide the simulations of a virtual environment.

  17. 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

    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)

  18. Europa central

    Karel BARTOSEK

    2010-02-01

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

  19. 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

    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 systematizing

  20. 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

    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

  1. 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

    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)

  2. 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

    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)

  3. 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

    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)

  4. Iodine prophylaxis following nuclear accidents - a concept how to distribute potassium-iodide tablets out of the central stocks in the event of an accident

    Portius, U.

    2007-01-01

    With its recommendation ''Iodine prophylaxis following nuclear accidents'' (1996) and its reports of 1997 and 2001 the German Commission on Radiological Protection (SSK) followed the recommendations of the WHO ''Guidelines for iodine prophylaxis following nuclear accidents'' of 1989. The intervention levels were lowered (50 mSv for children/adolescents (up to the age of 18 years) and pregnant women, 250 mSv for adults), the iodine prophylaxis was restricted to persons up to the age of 45 years and the recommended dosage of stable iodine was changed. Due to the lowered reference levels the radius of 25 km around a nuclear power plant that had been the planning radius for the distribution of iodine tablets so far was extended to 100 km. Based on these recommendations the German authorities began to set up new strategies for the provision and distribution of potassium-iodide tablets (iodine tablets). Since 2004, within the radius of 25 km the iodine tablets are pre-distributed to households and/or stored at several points in the municipality for persons up to the age of 45 years. For the new planning radius of 25-100 km iodine tablets are stored in 8 central stocks in Germany for children/adolescents (up to the age of 18 years) and pregnant women. A working group with representatives from federal and Laender authorities has developed a distribution strategy for the distribution out of these central stocks in the event of an accident. It describes a possibility of organising and implementing the distribution of the iodine tablets within the radius of 25-100 km in a nationwide standardised way. (orig.)

  5. Anatomía de anillos de crecimiento de 80 especies arbóreas potenciales para estudios dendrocronológicos en la Selva Central, Perú

    Lizandro Adal Beltrán Gutiérrez

    2013-09-01

    Full Text Available El conocimiento acerca de la existencia de anillos anuales en árboles tropicales, se conoce desde principios del siglo pasado, pero fue ignorado por muchos científicos durante largo tiempo. La investigación fue realizada en el Laboratorio de Tecnología de la Madera e Industrias Forestales de la Universidad Nacional del Centro del Perú, con la finalidad de caracterizar anatómicamente los anillos de crecimiento de 80 especies arbóreas potenciales para estudios dendrocronológicos; provenientes de las provincias de Satipo y Chanchamayo en la Selva Central del Perú. Para el estudio se consideraron las normas COPANT 30:1-019, Normas Técnicas Peruanas (NTP 251-008 y la Lista Estándar de la IAWA 1989. Entre los resultados más sobresalientes tenemos: el 30% de las ochenta especies estudiadas tienen buen potencial para estudios dendrocronológicos. La mayoría de estas especies, están delimitadas por una banda de fibras acortadas radialmente. Entre los problemas encontrados, se puede destacar la presencia de anillos con dificultad para ser visualizados, la presencia de anillos irregulares y la presencia de parénquima en bandas. Las características microscópicas, muestran que la variación significativa en dimensiones de fibras y vasos entre zonas de crecimiento (madera temprana y madera tardía, de las especies potenciales para dendrocronología, tienen una producción de células en forma periódica, lo que podría sugerir la formación anual de cada anillo.

  6. Formulación de un proyecto de instalación de un ciclotrón para la producción de radioisótopos de uso en medicina nuclear

    Zegarra Mayo, Lourdes Lidania; Zegarra Mayo, Lourdes Lidania

    2012-01-01

    El Instituto Peruano de Energía Nuclear (IPEN) como Organismo rector de la energía nuclear en el país, promueve todas las aplicaciones nucleares pacíficas que conduzcan al desarrollo del país, principalmente en la salud que busca el bienestar del ciudadano peruano. En este marco el IPEN promociona la tecnología nuclear en el ámbito de la medicina nuclear para el acceso a la tomografía por emisión de positrones (PET), técnica de diagnóstico médico que se ha desarrollado rápidamente en el mundo...

  7. 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

    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

  8. What they have in common the engineering from the Spanish nuclear power plants?; Que tienen en comun las ingenierias de las centrales nucleares espanolas

    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)

  9. The added value of the replica simulators in the exploitation of nuclear power plants; El valor anadido de los simuladores replica en la explotacion de las centrales nucleares

    Diaz Giron, P. a.; Ortega, F.; Rivero, N.

    2011-07-01

    Nuclear power plants full scope replica simulators were in the past solely designed following operational personnel training criteria. Nevertheless, these simulators not only feature a high replica control room but also provide an accurate process response. Control room replica simulators are presently based on complex technological platforms permitting highest physical and functional fidelity, allowing to be used as versatile and value added tools in diverse plants operation and maintenance activities. In recent years. Tecnatom has extended the use of such simulators to different engineering applications. this article intends to identify the simulators use in training and other applications beyond training. (Author)

  10. Modernization of electric power systems of the Laguna Verde Nuclear Power Plant; Modernizacion de los sistemas electricos de potencia de la Central Nuclear de Laguna Verde

    Gabaldon, M. A.; Gonzalez, J. J.; Prieto, I.

    2011-07-01

    The Power Increase Project of Laguna Verde Nuclear Plant has entailed the replacement, in one unique outage, of the main power electrical systems of the Plant (Isolated Phase Bars, Generator Circuit Breaker and Main Transformer) as well as the replacement of the Turbo-group. The simultaneous substitution of these entire system has never been done by any other Plant in the world, representing an engineering challenge that embraced the design of the new equipment up to the planning, coordination and management of the construction and commissioning works, which were successfully carried out by Iberdrola within the established outage period /47 days) for both units. (Author)

  11. The role of nuclear power plants in the wholesale electricity market; El papel de las centrales nucleares en el mercado mayorista de electricidad

    Alonso, J c; Alonso, J; Gonzalez, A; Gonzalez, R

    2009-07-01

    The Spanish electricity market has been running foe eleven years and its rules and procedures have proven compatible with a safe and stable operation of the nuclear power plants, helped by a wide portfolio of technologies in the Spanish system. In the near future, two issues emerge as a potential threat: the increase in renewable (mainly wind) production and its volatility and the development of new network infrastructure around the plants owned by third parties. Stricter rules on network development and operation and greater respect to the plants operational needs have to be pushed forward by the industry to succeed in life extension programs. (Author)

  12. Following to the occupational dose in a nuclear power plant. Second part; Seguimiento de la dosis ocupacional en una central nuclear. Segunda parte

    Medrano L, M A [Gerencia de Seguridad Radiologica, Instituto Nacional de Investigaciones Nucleares, Salazar (Mexico)

    1991-07-01

    The pursuit of the occupational doses in any installation where radioactive material is managed it allows to those responsible for the radiological safety, to know those practices or places in which should focus its efforts so that the doses received by their workers are controlled and minimized. In this work another form of pursuit of the occupational doses is presented making emphasis in the practices, places and devices or teams that produce the doses to the exposed personnel to diverse radiation sources inside a typical nuclear power station.

  13. Nuclear

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  14. 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

    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

  15. Implementation of the monitoring Plan of the State and behavior of the systems in the Central Nuclear Almaraz

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

    2013-01-01

    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.

  16. ECED 2013: Eastern and Central Europe Decommissioning. International Conference on Decommissioning of Nuclear Facilities. Conference Guide and Book of Abstracts

    2013-01-01

    The Conference included the following sessions: (I) Opening session (2 contributions); (II) Managerial and Funding Aspects of Decommissioning (5 contributions); (III) Technical Aspects of Decommissioning I (6 contributions); (IV) Experience with Present Decommissioning Projects (4 contributions); (V) Poster Session (14 contributions); (VI) Eastern and Central Europe Decommissioning - Panel Discussion; (VII) Release of Materials, Waste Management and Spent Fuel Management (6 contributions); (VIII) Technical Aspects of Decommissioning II (5 contributions).

  17. central t

    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.

  18. Development of an area monitor for neutrons using solid state nuclear track detector; Desenvolvimento de um monitor de area para neutrons utilizando detector solido de tracos nucleares

    Zahn, G.S.

    1994-12-31

    An area monitor for neutrons composed of the solid state nuclear track detector (SSNTD) Makrofol DE, together with a (n,{alpha}) converter, in the center of a 25 cm diameter polyethylene sphere, is developed. The optimal electrochemical etching conditions for the detection of thermal neutrons by the Makrofol DE using the BN converter are studied, leading to the choice of 55 min, at 30{sup 0} C, under a 44,2 kV.cm{sup -1} electric field with oscillation frequency of 2,0 khz. The response of this system to thermal neutrons, in the optimal conditions, is of 2,76(10)x 10{sup -3} tr/n. Changing from the BN converter to a 2,73(3)g compressed boric acid tablet this value lowers to 3,88(17)x 10{sup -4} tr/n. The performance of the whole monitor in the detection of fast neutrons is examined using the BN converter and neutrons from a {sup 241} Am Be source, with a response of 4,4(2)x 10{sup 3} tr.mSv{sup -1}.cm{sup -2} and operational limits between 7(3){mu}Sv and 5,6(2)mSv. The result of the monitoring of the control room of the IPEN Cyclotron accelerator are also presented as a final test for the viability of the practical use of the monitor. (author). 34 refs, 15 figs, 6 tabs, 1 app.

  19. New recommendations from the IAEA for medical exposures: impact on nuclear medicine in Brazil; Novas recomendacoes da IAEA para exposicoes medicas: impacto em medicina nuclear no Brasil

    Sa, Lidia Vasconcellos de; Kodlulovich, Simone, E-mail: lidia@ird.gov.br, E-mail: simone@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2013-10-01

    An assessment of the current national standards was performed in order to verify compliance with the new recommendations, taking into account the number of available facilities and medical physicists to meet the requirements. It was found that compliance with the requirements of protocol optimization and individualization of doses, as well as the assignment of responsibility shared by all professionals involved were not disclosed. In Brazil, there is no reference levels established as also there is not a government program to obtain them. The functions and responsibilities of the medical physicist in conducting dosimetry individual patient, quality control and acceptance tests of equipment and also the calibration is not defined in the standard. Currently in Brazil there are 31 certified Medical Physicists in Medicine Nuclear power to meet approximately 390 facilities, representing only 8% required. As a member state of the IAEA, the Brazilian rules governed by CNEN is based on BSS-115, must come to terms with the GSR. The concern is now meeting the requirements, especially those relating to patients, since we have established benchmarks and individualized dosimetry. Beyond addition, the number of medical physicists are not enough to show the country's demand. (author)

  20. Self-Reliance and Sustainability of Nuclear Analytical Laboratories in Small States of Central Europe: The Slovenian Case

    Korun, M.

    2013-01-01

    The Jožef Stefan Institute is the largest research institution in Slovenia devoted to research in many fields of science and technology. Within the Institute several nuclear analytical laboratories operate, making it the largest nuclear research institution in Slovenia. The Laboratory for Radiation Measuring Systems and Radioactivity Measurements belongs to the Department for Medium and Low Energy Physics, which is engaged mainly in nuclear physics, interactions of radiation with matter and its applications, and in providing a service in radiation measurements and dosimetry. The laboratory was founded almost thirty years ago, when the three accelerators, which formed the basis of the research infrastructure of the department, came to the end of their working lives. The personnel took the opportunity to participate in the programme of radioactivity monitoring of the Krško Nuclear Power Plant, which at that time went into operation. The equipment, i.e., the detectors, electronics and computers, was available, but the expertise was limited to the techniques of measurement and analysis in gamma-ray spectrometry. The absence of the expertise in radiochemistry was a serious drawback, therefore new methods in detector calibration had to be developed. In the following years the laboratory participated not only in the monitoring programme of the nuclear power plant but also in other radioactivity monitoring programmes in Slovenia. Since its foundation the laboratory did not receive any financial support either from the state or from the department. Support in equipment and expertise was received from the International Atomic Energy Agency, the Government of the United States and the United Nations Development Programme. The laboratory is engaged mainly in gamma-ray spectrometric measurements of samples from the natural, living and working environments. The main customers are the Krško Nuclear Power Plant and governmental organizations and agencies. The work for these

  1. Contribuição da medicina nuclear para a avaliação dos linfomas

    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.

  2. Emergency medical training for health promoters in Central and South America Entrenamiento médico en urgencias para promotores de salud de América Central y América del Sur

    Robert Partridge

    2007-12-01

    Full Text Available Los promotores de salud, las parteras y otros proveedores de cuidados médicos básicos trabajan en comunidades locales de todo el mundo para mejorar y facilitar la atención sanitaria. No hay suficiente información que describa los programas educacionales dirigidos a mejorar los conocimientos y las habilidades de los promotores de salud y sobre su impacto sanitario a largo plazo. Muchas iniciativas educacionales dirigidas a los promotores de salud consisten en intervenciones aisladas que permiten evaluar sus conocimientos inmediatamente después de la intervención, pero no miden los progresos a largo plazo en la base de conocimientos o la atención sanitaria. La Alianza Pediátrica Global -una organización sin ánimo de lucro basada en los EE.UU. que trabaja con personal médico y sanitario local- creó un programa educacional para promotores sanitarios y parteras en Ecuador, Guatemala, México y Nicaragua con un enfoque centrado en reducir la mortalidad materna e infantil y en mejorar la atención primaria y de urgencias. En este artículo se describen estas iniciativas educacionales diseñadas para mejorar las habilidades de los promotores de salud y las parteras mediante un entrenamiento médico avanzado y sostenible, ajustadas a las necesidades específicas de cada comunidad.

  3. The Text of a Regional Co-operative Agreement for Research, Development and Training related to Nuclear Science and Technology. Latest Status. Declarations/Reservations; Texto de un Acuerdo de Cooperacion Regional Para la Investigacion, el Desarrollo y la Capacitacion en Materia de Ciencias y Tecnologia Nucleares

    NONE

    1972-08-18

    The text of a Regional Co-operative Agreement for Research, Development and Training Related to Nuclear Science and Technology between the Agency and Member States is reproduced herein for the information of all Members. Section 9 thereof specifies the Members that may become party to it [Spanish] Para conocimiento de todos los Estados Miembros en el presente documento se transcribe el texto de un Acuerdo de Cooperacion Regional para la investigacion, el desarrollo y la capacitacion en materia de ciencias y tecnologia nucleares entre el Organismo y los Estados Miembros. En la Seccion 9 se especifican los Estados Miembros que pueden ser partes en el Acuerdo.

  4. Methodology for maintenance analysis based on hydroelectric power stations reliability; Metodologia para realizar analisis de mantenimiento basado en confiabilidad en centrales hidroelectricas

    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.

  5. Acordos de paz para a América Central nos anos 1980: a busca pela solução negociada 10.5102/uri.v13i1.3088

    Vanessa Braga Matijascic

    2015-07-01

    Full Text Available As negociações de paz na América Central nos anos 1980 envolveram uma série de iniciativas diplomáticas que contemplaram o Grupo de Contadora e o Grupo de Apoio a Contadora, o grupo de países de Tegucigalpa e, por fim, o desfecho proposto pelas cúpulas centro-americanas. No contexto da política externa de Ronald Reagan foi de extrema importância a iniciativa dos países de Contadora para evitar a primazia da solução proposta pelos Estados Unidos, que era o desfecho da vitória militar perante as guerrilhas nicaraguenses e salvadorenhas. O objetivo deste estudo é possibilitar a compreensão sobre como as iniciativas de Contadora ofereceram outro caminho que, quando acrescidas do escândalo Irã-contras, possibilitou o encaminhamento das cúpulas centro-americanas para o desfecho negociado e pacífico. Para a realização do estudo foi feita revisão bibliográfica e uso de fontes primárias resultantes dos diversos encontros diplomáticos.

  6. 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

    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.

  7. 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

    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)

  8. Need for a probabilistic fire analysis at nuclear power plants; Necesidad de un analisis probabilista de incendios en una central nuclear

    Calabuig Beneyto, J L [Empresarios Agrupados, A.I.E., Madrid (Spain); Ibanez Aparicio, J [Asociacion Nuclear ASCO, Barcelona (Spain)

    1993-12-15

    Although fire protection standards for nuclear power plants cover a wide scope and are constantly being updated, the existence of certain constraints makes it difficult to precisely evaluate plant response to different postulatable fires. These constraints involve limitations such as: - Physical obstacles which impede the implementation of standards in certain cases; - Absence of general standards which cover all the situations which could arise in practice; - Possible temporary noncompliance of safety measures owing to unforeseen circumstances; - The fact that a fire protection standard cannot possibly take into account additional damages occurring simultaneously with the fire; Based on the experience of the ASCO NPP PSA developed within the framework of the joint venture, INITEC-INYPSA-EMPRESARIOS AGRUPADOS, this paper seeks to justify the need for a probabilistic analysis to overcome the limitations detected in general application of prevailing standards. (author)

  9. Data acquisition and management system for a nuclear processes simulator; Sistema de adquisicion y manejo de datos para un simulador de procesos nucleares

    Gonzalez M, J A; Santiago C, J [Facultad de Ingenieria, UNAM, Campus Morelos (Mexico)

    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)

  10. More child leukemia near nuclear power plants; Plus de leucemies chez l'enfant pres des centrales nucleaires

    Anon.

    2012-03-15

    A French study shows that there are more cases of child leukemia near nuclear power plants but the statistics is low: only 14 cases detected. The same study shows that the excess is not due to the releases of gaseous effluents from the plant, there is no relationship between the excess and a particular type of plant or even a particular plant. Some experts suggest that it might be the movement and intermingling of populations in the plant area that ease the propagation of infectious agents involved in child acute leukemia. A similar result was obtained in Germany a few years ago. (A.C.)

  11. Lineamientos de un plan estratégico para el mejoramiento de la calidad del servicio brindado en el Hospital Militar Central de Lima

    Cabrera Rioja, Luis Alberto

    2007-01-01

    El presente estudio, realizado en el Hospital Militar Central (HMC) de Lima, está dirigido al diseño de los lineamientos de un plan estratégico que permita formular la misión y visión del HMC, analizar el entorno e intorno organizacional y formular objetivos estratégicos orientados al mejoramiento continuo de la calidad del servicio. A fin de superar las dificultades económicas, logísticas y de personal que afronta actualmente el Hospital Militar Central, debido a los recortes presupuestales ...

  12. Improvements related with the safety required by the Argentine Regulatory Authority to the Atucha I Nuclear Central; Mejoras relacionadas con la seguridad requeridas por la Autoridad Regulatoria Argentina a la Central Nuclear Atucha I

    Calvo, J.; Michelin, C.; Navarro, R.; Waldman, R. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250, 1429- Ciudad de Buenos Aires (Argentina)]. e-mail: jcalvo@sede.arn.gov.ar

    2006-07-01

    The Argentinean Nuclear Regulation Authority (ARN) verified the existence of changes in the state of some internal components of the reactor of the Atucha I Nuclear Power station that, of continuing in the time, it could take to an inconvenient degradation for the safety operation of the installation. In consequence, to the effects of preventing that reach this situation, at the end of 1999, the ARN required to the Responsible Entity for the operation of this power station the implementation of an important improvements program in the internal components of the reactor. Additionally, and based on the results of the Probabilistic Safety analysis, it was added the one mentioned improvements program the implementation of an alternative cooling system of the reactor core denominated Second Drain of Heat, due to it was determined that, for some accidental sequences, their performance would reduce considerably the probability of damage to the core. The concretion of the improvements program implied to the Responsible Entity the realization of an important quantity of engineering studies, tests and specific inspections that allowed to carry out changes on the control bars of the reactor and its guide tubes; the coolant channels; the sensors of neutron flow; and diverse components of the primary and moderator systems. On the other hand also it was implemented the system Second Drain of Heat, what represents a considerable effort to make compatible the instrumentation and control of last generation, with the instrumentation and existent control systems in the power station. Also, it was requested to be carried out an integrity of the pressure recipient for to demonstrate the existence of an acceptable margin for the difference among the acceptable limit temperatures and of ductile/fragile transition of the material for all the possible accidental scenarios during the useful life of the reactor. (Author)

  13. Proposta de um software-protótipo para uso na assistência a pacientes com cateter central de inserção periférica (PICC Proposal for a software-prototype to assist patients with peripherally inserted central catheter (PICC

    Luiz Célio Martins Freitas

    2017-04-01

    Full Text Available Objetivo: Propor um software-protótipo como estratégia para melhorar o processo de comunicação e os registros relativos ao cuidado de enfermagem a pacientes com cateter central de inserção periférica (PICC e descrever os passos para a construção de um protótipo de software. Método: Utilizou-se da Pesquisa de Intervenções, na modalidade de Processo de Intervenção e como método de operacionalização a Prototipação associados a instrumentos de informática. Resultado: Foi criado um modelo computadorizado de interface gráfica simples e projetado para uso em redes abertas ou fechadas. Conclusão: O desenvolvimento do software-protótipo para funcionar em rede web tornará o processo de implantação mais prático. Acrescenta-se que validação com equipe de saúde será realizada antes da utilização.

  14. Application of Nuclear Analytical Techniques in Elemental Characterization of Wadi El-Nakhil Alabaster, Central Eastern Desert, Egypt

    Zain M. Alamoudi; A. El-Taher

    2016-01-01

    Instrumental neutron activation analysis (INAA) is a powerful technique for trace element determination in rocks. Nine alabaster samples were collected from Wadi El-Nakhil located at the intersection of lat. 26°10′50′′N and long. 34°03′40′′E, central Eastern Desert, Egypt, for investigation by INAA and Energy Depressive X-Ray Fluorescence (EDXRF). The samples were irradiated by thermal neutrons at the TRIGA Mainz research reactor at a neutron flux of 7 × 1011 n/cm2·s. Twenty-two elements were...

  15. 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

    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

  16. Aseismatic design and safety of nuclear power generation facilities. Research in Central Research Institute of Electric Power Industry

    1995-01-01

    In order to contribute to the aseismatic design of nuclear power generation facilities, this Research Institute has carried out the observation on the site of buildings in Matsushiro earthquake, the experiment on a large vibration table, the vibration experiment on actual buildings and so on, thus made clear the method of evaluating the dynamic model of buildings and foundation grounds. Also it cooperated in the determination of input earthquake motion which is important for aseismatic design by carrying out the evaluation of the activity of faults the observation of strong earthquakes, and the elucidation and evaluation of the characteristics of earthquake motion. It has made the standard for evaluating the fault activity and the stability in earthquakes of the foundation and surrounding grounds of power stations. The development of new underground location technology, the location on Quaternary grounds and the location on the sea, and the research on developing the aseismatic construction of FBRs are in progress. The survey and evaluation of fault activities, the evaluation of earthquake input, the limit state design of important outdoor structures, the new location technology for nuclear power stations, and the development of the buckling and base isolation design of FBRs are reported. (K.I.)

  17. Aplicación de Resonancia Magnética Nuclear para la caracterización de fracciones pesadas del petróleo en el proceso de desasfaltado por extracción (DEMEX)

    Avella Moreno, Eliseo

    2011-01-01

    En la literatura, se encontró una gran variedad de criterios para la preparación de muestras y para la adquisición y el procesamiento de los espectros de resonancia magnética nuclear de hidrógeno-1 (RMN 1H) o de carbono-13 (RMN 13C) de petróleos, carbones y sus fracciones. Se definieron 33 nuevos intervalos de integración en los espectros de RMN 1H y 47, en los espectros de RMN 13C. Se unificaron sus límites inferior y superior mediante un tratamiento estadístico realizado con ...

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

    Murata, Takashi [Graduate School of Energy Sci., Kyoto Univ., Kyoto (Japan)

    1999-12-01

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

  19. Quantitative Evaluation of Nuclear Power Station Siting from the Point of View of Safety; Evaluacion Cuantitativa del Emplazamiento de Centrales Nucleoelectricas desde el Punto de Vista de la Seguridad

    Serment Cabrero, V. [Comision Nacional de Energia Nuclear y Universidad Nacional Autonomia de Mexico (Mexico); Velez, C. [Instituto Politecnico Nacional y Comision Federal de Electricidad (Mexico)

    1967-09-15

    Apart from the minimum operational and safety requirements for the siting of nuclear power stations, the paper proposes introducing the total mean dose to the general population as an additional criterion. Although the calculation of this dose presupposes a detailed knowledge of the main pathways by which the population may be irradiated in case of an accident, the present state of power reactor technology makes it possible to tackle the problem already. An estimate of the total mean dose per unit time involves the safety aspects of the reactor, the features of the site considered, and the way in which these features affect safety. The authors derive the general formula expressing the total mean dose as a function of all the parameters concerned. It is pointed out that in the case of accidents in which the release of fission products is independent of the mechanisms of irradiation, this formula is considerably simplified and makes it possible to establish a classification of the relative suitability, from the safety point of view, of the sites proposed, without touching upon the difficult problem of the definition of accidents and their probabilities of occurrence. A further simplification accrues when there exist predominant mechanisms governing the accidental irradiation of the population. The approach adopted is particularly well suited to calculations with digital computers, and helps to identify the areas in which information is lacking and to direct research intended to remove these deficiencies. (author) [Spanish] Ademas de los requisitos mfnimos opecacionales y de seguridad para el emplazamiento de centrales nucleoelectricas, se sugiere utilizar como criterio adicional la dosis total promedio a la poblacion. Aunque el calculo de esa dosis implica el conocimiento detallado de los caminos principales por los cuales la poblacion puede ser irradiada en el caso de un accidente, el estado actual de la tecnologia de los reactores nucleares de potencia permite ya

  20. Distribuição de frequência da chuva para região Centro-Sul do Ceará, Brasil Frequency distribution of rainfall for the South-Central region of Ceará, Brazil

    Ítalo Nunes Silva

    2013-09-01

    Full Text Available Foram analisadas sete distribuições de probabilidade Exponencial, Gama, Log-normal, Normal, Weibull, Gumbel e Beta para a chuva mensal e anual na região Centro-Sul do Ceará, Brasil. Para verificação dos ajustes dos dados às funções densidade de probabilidade foi utilizado o teste não-paramétrico de Kolmogorov-Smirnov com nível de 5% de significância. Os dados de chuva foram obtidos da base de dados da SUDENE registrados durante o período de 1913 a 1989. Para a chuva total anual teve ajuste satisfatório dos dados às distribuições Gama, Gumbel, Normal e Weibull e não ocorreu ajuste às distribuições Exponencial, Log-normal e Beta. Recomenda-se o uso da distribuição Normal para estimar valores de chuva provável anual para a região, por ser um procedimento de fácil aplicação e também pelo bom desempenho nos testes. A distribuição de frequência Gumbel foi a que melhor representou os dados de chuva para o período mensal, com o maior número de ajustes no período chuvoso. No período seco os dados de chuva foram melhores representados pela distribuição Exponencial.Seven probability distributions were analysed: Exponential, Gamma, Log-Normal, Normal, Weibull, Gumbel and Beta, for monthly and annual rainfall in the south-central region of Ceará, Brazil. In order to verify the adjustments of the data to the probability density functions, the non-parametric Kolmogorov-Smirnov test was used with a 5% level of significance. The rainfall data were obtained from the database at SUDENE, recorded from 1913 to 1989. For the total annual rainfall, adjustment of the data to the Gamma, Gumbel, Normal and Weibull distributions was satisfactory, and there was no adjustment to the Exponential, Log-normal and Beta distributions. Use of Normal distribution is recommended to estimate the values of probable annual rainfall in the region, this being a procedure of easy application, performing well in the tests. The Gumbel frequency

  1. Fiabilidad de la Tomografía de coherencia óptica de dominio espectral para la medición del espesor Corneal Central

    Correa Pérez, María Encarnación

    2013-01-01

    La paquimetría es la medida del grosor corneal en cualquiera de sus localizaciones. Resulta indispensable en la evaluación y monitorización de algunas enfermedades oculares. El Paquimétro Ultrasónico de contacto se considerada “gold standard”. En los últimos años, la paquimetría se ha incluido en equipos diagnósticos complejos no específicamente diseñados para ello, sin precisar contacto corneal. Ejemplo de ésto son los sistemas de Tomografía de Coherencia Óptica (OCT) de Dominio Espectral...

  2. Communication dated 11 September 2006 from the Permanent Mission of the Republic of Kazakhstan regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia signed on 8 September 2006

    2007-01-01

    The Secretariat has received a Note Verbale, dated 11 September 2006, from the Permanent Mission of the Republic of Kazakhstan to the IAEA regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia signed on 8 September 2006 in Semipalatinsk by the leaders of Kazakhstan, Kyrgyzstan, Tajikistan, Turkmenistan and Uzbekistan. The Note Verbale and, as requested therein, the enclosed information regarding the Treaty on a Nuclear-Weapon-Free Zone in Central Asia, is reproduced herewith for the information of Member States

  3. Nuclear power plant of Fessenheim: evaluation of the seismic risk; Centrale Nucleaire de Fessenheim: appreciation du risque sismique

    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.)

  4. CNE (central nuclear en Embalse): probabilistic safety study. Loss-of-coolant accidents. Analysis through events sequence

    Layral, S.I.

    1987-01-01

    The aim of this study was to perform for the Embalse nuclear power plant, a probabilistic evaluation of loss-of-coolant accidents (LOCA) to identify the risks associated with them and to determine their acceptability in accordance with norms. This study includes all ruptures in the primary system that produce the automatic activation of 'emergency core cooling system'. Three starting events were selected for the probabilistic evaluation: 100% rupture of an input collector; 5% rupture of an input collector; 1.2% rupture of an input collector. At this stage the evaluation is focussed on the identification and quantization of the main failure sequences that follow a LOCA and lead to an uncontrolled reactor state or 'core meltdown'. The most important contribution to the core meltdown due to LOCA is the failure of supplies that are required for the emergency core cooling system. (Author)

  5. Improvements related with the safety required by the Argentine Regulatory Authority to the Atucha I Nuclear Central

    Calvo, J.; Michelin, C.; Navarro, R.; Waldman, R.

    2006-01-01

    The Argentinean Nuclear Regulation Authority (ARN) verified the existence of changes in the state of some internal components of the reactor of the Atucha I Nuclear Power station that, of continuing in the time, it could take to an inconvenient degradation for the safety operation of the installation. In consequence, to the effects of preventing that reach this situation, at the end of 1999, the ARN required to the Responsible Entity for the operation of this power station the implementation of an important improvements program in the internal components of the reactor. Additionally, and based on the results of the Probabilistic Safety analysis, it was added the one mentioned improvements program the implementation of an alternative cooling system of the reactor core denominated Second Drain of Heat, due to it was determined that, for some accidental sequences, their performance would reduce considerably the probability of damage to the core. The concretion of the improvements program implied to the Responsible Entity the realization of an important quantity of engineering studies, tests and specific inspections that allowed to carry out changes on the control bars of the reactor and its guide tubes; the coolant channels; the sensors of neutron flow; and diverse components of the primary and moderator systems. On the other hand also it was implemented the system Second Drain of Heat, what represents a considerable effort to make compatible the instrumentation and control of last generation, with the instrumentation and existent control systems in the power station. Also, it was requested to be carried out an integrity of the pressure recipient for to demonstrate the existence of an acceptable margin for the difference among the acceptable limit temperatures and of ductile/fragile transition of the material for all the possible accidental scenarios during the useful life of the reactor. (Author)

  6. The Central Research Institute of Electric Power Industry and nuclear energy. Real images and views for compatibility of specialty and sociality

    Sato, Motohide

    2004-01-01

    The Central Research Institute of Electric Power Industry (CRIEPI) has been a motive power supporting electric energy and rich society in Japan as a center of electric power field in Japan under always challenging technologies advancing at a step since beginning of business as a special research institute on electrical power technology in Japan. And, on today receiving whole of liberalization on electric business, CRIEPI plans to carry out new development closer to society and nationals under a flag of 'contribution to society' by making its specialty and sociality compatible. Therefore, when social discussion on nuclear energy constructing basis of electric energy in Japan is noisy, here were summarized efforts, actual results, and topics for individual researching subjects shown as follows under showing basic attitude of CRIEPI to the nuclear energy: maintenance and administration techniques to rationally secure soundness of the light water reactor apparatuses; intermediate storage technique on spent fuels (concrete cask storage); survey, design and safety evaluation techniques supporting landfill disposal business of high level radioactive wastes; dry recycle technique and metal fuel fast reactors applicable to spent fuel processing at light water reactors; and small size fast reactors (4S reactors) usable for diverse applications. (G.K.)

  7. 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

    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)

  8. Desenvolvimento de software e hardware para irrigação de precisão usando pivô central Development of software and hardware for precision irrigation using the center pivot

    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

  9. La ciudad central de la Ciudad de México: ¿espacio de oportunidad laboral para la metrópoli?

    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.

  10. Possibilities and limitations of analogue methods for studying the dynamics of nuclear power stations; Possibilites et limitations du calcul analogique pour les etudes dynamiques de centrales nucleaires

    Caillet, C; Deat, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    1. Introduction: the present paper is devoted to analog simulation of problems related to nuclear reactors other than the simulation of the kinetic equations which is well known. 2. Thermodynamic problems: various problems relative to temperature evolution in a reactor, in a pipe, in an exchanger, in a turbine, are studied, and simulation techniques used by earlier authors are critically reviewed. 3. Pipe simulators: it is shown that this problem can be solved by the use of specialized simulators which will be described and analysed. 4. Rotating machine simulators: the particular aspect of rotating machine calculations introducing frequent use of diagrams is emphasized. A simulator requiring both digital and analogue methods is described. 5. The study of a nuclear power station: as an example it is proposed to discuss problems a rising in connection with the preceding elements (a, b, c, d) when simulating the behaviour of large nuclear plants. The part played by ordinary computing elements for the simulation of the different servomechanism transfer functions is considered and process of regulation is outlined. 6. Conclusion: the necessity of the use of high quality simulators and computers is underlined and the accuracy of the solutions is discussed. (author)Fren. [French] 1. Cinetique des reacteurs: la simulation des equations cinetiques d'un reacteur nucleaire ne pose desormais plus de probleme. II est donc possible de faire le point des differentes applications de la technique analogique dans ce domaine. 2. Les problemes thermodynamiques: on discute les differents problemes poses par l'evolution des temperatures dans un reacteur, dans une tuyauterie, dans un echangeur, dans une turbine, et on passe en revue les techniques de simulation proposees jusqu'a ce jour. 3s simulateurs de tuyauteries: on montre comment les differents problemes poses ci-dessus peuvent etre resolus, pour une classe tres vaste de reacteurs par l'emploi de simulateurs speciaux que l

  11. Gestão estratégica de pessoas para a inovação: o caso da Frimesa Cooperativa Central INNOVATION-ORIENTED STRATEGIC MANAGEMENT OF PEOPLE: FRIMESA COOPERATIVA CENTRAL CASE

    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

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

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

    2016-01-01

    We construct net baryon number and strangeness susceptibilities as well as correlations between electric charge, strangeness and baryon number from experimental data on the particle production yields at midrapidity of the ALICE Collaboration at CERN. The data were taken in central Pb-Pb collisions at $\\sqrt{s_{\\rm NN}}$~=~2.76~TeV and cover one unit of rapidity. We show that the resulting fluctuations and correlations are consistent with Lattice QCD results at the chiral crossover pseudocritical temperature $T_{c} \\simeq$ 155 MeV. This agreement lends strong support to the assumption that the fireball created in these collisions is of thermal origin and exhibits characteristic properties expected in QCD at the transition from the quark gluon plasma to the hadronic phase. Since Lattice QCD calculations are performed at a baryochemical potential of $\\mu_{B}$ = 0, the comparisons with LHC data are the most direct due to the vanishing baryon transport to midrapidity at these high energies.

  13. Application of Nuclear Analytical Techniques in Elemental Characterization of Wadi El-Nakhil Alabaster, Central Eastern Desert, Egypt

    Zain M. Alamoudi

    2016-01-01

    Full Text Available Instrumental neutron activation analysis (INAA is a powerful technique for trace element determination in rocks. Nine alabaster samples were collected from Wadi El-Nakhil located at the intersection of lat. 26°10′50′′N and long. 34°03′40′′E, central Eastern Desert, Egypt, for investigation by INAA and Energy Depressive X-Ray Fluorescence (EDXRF. The samples were irradiated by thermal neutrons at the TRIGA Mainz research reactor at a neutron flux of 7 × 1011 n/cm2·s. Twenty-two elements were determined, namely, As, Ba, Ca, Co, Cr, Sc, Fe, Hf, K, Mg, Mn, Na, Rb, U, Zn, Zr, Lu, Ce, Sm, La, Yb, and Eu. The chemical analysis of alabaster indicated having high contents of CaO and MgO and LOI and low contents of SiO2, Al2O3, Na2O, K2O, MnO, and Fe2O3.

  14. Report on the Fourth Reactor Refueling. Laguna Verde Nuclear Central. Unit 1. April-May 1995; Informe de la Cuarta Recarga de Combustible. Central Laguna Verde. Unidad 1. Abril-Mayo 1995

    Mendoza L, A; Flores C, E; Lopez G, C P.F.

    1996-12-31

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

  15. 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

    Reyes L, C; Munoz Ledo, C R [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1993-12-31

    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.

  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

    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. 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

    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)

  18. Auscultación de movimientos de ladera para la implementación de sistemas de alerta: ejemplos del Pirineo y Prepirineo central y oriental

    Hurlimann Ziegler, Marcel; Moya Sánchez, José; Abanco Martínez de Arenzana, Claudia; Vilajosana Guillen, Ignasi

    2013-01-01

    En la presente contribución se describen los sistemas de auscultación de cuatro tipos de movimientos de ladera (corriente de derrubios, deslizamiento profundo, deslizamiento superficial y desprendimiento). El énfasis se ha puesto en la descripción de la instrumentación de corrientes de derrubios en la cuenca El Rebaixader (Pirineo Central) y los resultados obtenidos durante los últimos 4 años. La auscultación de los otros tres tipos de movimientos se presenta de manera resumida. El s...

  19. La restricción intertemporal del presupuesto. Una evaluación empírica para el Gobierno Nacional Central de Colombia, 1950-2010

    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.

  20. Soropositividade para Mycoplasma hyopneumoniae em suínos abatidos em frigoríficos da região central do estado de São Paulo

    A.F. Vicente

    2013-12-01

    Full Text Available Mycoplasma hyopneumoniae is the etiologic agent of enzootic pneumonia in pigs and causes large economic losses in the swine industry. There is little data on the positivity of this disease in Brazil. The objective of this study was to evaluate the seropositivity for this agent in 200 serum samples collected from pigs in a slaughterhouse located in the central region of São Paulo. A high percentage (52% of positivity was found indicating the presence of the agent and the need to implement control measures.

  1. 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

    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)

  2. 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

    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)

  3. Multielemental analysis of soil samples from the Assin District of Central Region in Ghana using nuclear and related techniques

    Agyemang, O.

    2008-06-01

    Macronutrients, micronutrients, pH, salinity and moisture content were determined in soil samples from six farms in two farming towns in Assin North District in the Central Region of Ghana namely Assin Akonfudi and Assin Bereku. Soil samples were taken from cocoa farms, orange farms and palm oil plantations at three different depths. The nutrients determined were Primary macronutrients that was K, Secondary macronutrients that were Ca, Mg and Micronutrients that were, Cl, Co, Cu, Fe, Mn, Mo, Zn, Na and Se and Neutron Activation method and Atomic Absorption Spectrometry were used for the elemental analysis. The pHs were within the acidic range, ranging from 4.50-6.44. The top soil (0-5cm) had the higher pH followed by soil at the depth of 5-30cm and then soil at the depth of 30-40cm that is the pH decreased with depth. The salinity rather increased with depth ranging from 0.3l-2.98dS/m and the moisture content also ranged from 0.5-2.04%. For the soil samples taken from the cocoa farms, K recorded the highest concentration and Mo recorded the lowest concentration in the soil. For soil samples taken from orange farms, Ca recorded the highest concentration and Se recorded the lowest concentration in the soil and for soil samples taken from the palm oil plantations, Fe recorded the highest concentration and Mo recorded the lowest concentration in soil. The macronutrients ranged from 28591.19-6.49 mg/kg and the micronutrients ranged from <0.0004-20344.50 mg/kg. Soils in the cocoa farms were found to be more rich in nutrients and the soils in the palm oil plantations were found to be least rich in nutrients

  4. 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

    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

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

    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.

  6. Communication dated 30 May 2014 received from the Permanent Mission of Uzbekistan to the Agency regarding the implementation of the initiative of the President of Uzbekistan on Establishing a Nuclear-Weapon-Free Zone in Central Asia

    2014-01-01

    The Director General has received a note verbale dated 30 May 2014 from the Permanent Mission of Uzbekistan to the Agency regarding the implementation of the initiative of the President of Uzbekistan, HE Mr Islam Karimov, on Establishing a Nuclear-Weapon-Free Zone in Central Asia. The note verbale and its attachment are circulated herewith for information, as requested by the Permanent Mission

  7. Centrality dependence of the nuclear modification factor of charged pions, kaons, and protons in Pb-Pb collisions at root s(NN)=2.76 TeV

    Adam, J.; Adamová, Dagmar; Bielčík, J.; Bielčíková, Jana; Brož, M.; Čepila, J.; Contreras, J. G.; Eyyubova, G.; Ferencei, Jozef; Křelina, M.; Křížek, Filip; Kučera, Vít; Kushpil, Svetlana; Mareš, Jiří A.; Petráček, V.; Pospíšil, Jan; Schulc, M.; Špaček, M.; Šumbera, Michal; Vajzer, Michal; Vaňát, Tomáš; Závada, Petr

    2016-01-01

    Roč. 93, č. 3 (2016), s. 034913 ISSN 0556-2813 R&D Projects: GA MŠk(CZ) LG13031 Institutional support: RVO:68378271 ; RVO:61389005 Keywords : ALICE collaboration * heavy ion collisions * centrality dependece Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders; BF - Elementary Particles and High Energy Physics (FZU-D) Impact factor: 3.820, year: 2016

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

    Ymelda Montoro; Rocío Moreno; Luis Gomero; Maria Reyes

    2009-01-01

    Con el objetivo de conocer las características sobre el uso e impactos en la salud de los plaguicidas químicos de uso agrícola en las provincias de Chupaca y Concepción en los andes centrales del Perú, se desarrolló un estudio descriptivo transversal entre abril y junio del año 2005, por medio de un cuestionario aplicado a 435 agricultores. Asimismo, se exploró la ubicación de los centros de expendio y la frecuencia de ventas de productos, además, se evaluó los casos de intoxicación reportado...

  9. A central region in the minor capsid protein of papillomaviruses facilitates viral genome tethering and membrane penetration for mitotic nuclear entry.

    Inci Aydin

    2017-05-01

    Full Text Available Incoming papillomaviruses (PVs depend on mitotic nuclear envelope breakdown to gain initial access to the nucleus for viral transcription and replication. In our previous work, we hypothesized that the minor capsid protein L2 of PVs tethers the incoming vDNA to mitotic chromosomes to direct them into the nascent nuclei. To re-evaluate how dynamic L2 recruitment to cellular chromosomes occurs specifically during prometaphase, we developed a quantitative, microscopy-based assay for measuring the degree of chromosome recruitment of L2-EGFP. Analyzing various HPV16 L2 truncation-mutants revealed a central chromosome-binding region (CBR of 147 amino acids that confers binding to mitotic chromosomes. Specific mutations of conserved motifs (IVAL286AAAA, RR302/5AA, and RTR313EEE within the CBR interfered with chromosomal binding. Moreover, assembly-competent HPV16 containing the chromosome-binding deficient L2(RTR313EEE or L2(IVAL286AAAA were inhibited for infection despite their ability to be transported to intracellular compartments. Since vDNA and L2 were not associated with mitotic chromosomes either, the infectivity was likely impaired by a defect in tethering of the vDNA to mitotic chromosomes. However, L2 mutations that abrogated chromatin association also compromised translocation of L2 across membranes of intracellular organelles. Thus, chromatin recruitment of L2 may in itself be a requirement for successful penetration of the limiting membrane thereby linking both processes mechanistically. Furthermore, we demonstrate that the association of L2 with mitotic chromosomes is conserved among the alpha, beta, gamma, and iota genera of Papillomaviridae. However, different binding patterns point to a certain variance amongst the different genera. Overall, our data suggest a common strategy among various PVs, in which a central region of L2 mediates tethering of vDNA to mitotic chromosomes during cell division thereby coordinating membrane

  10. 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

    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

  11. 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

    Arevalo Osorio, Luis [Empresa de Energia de Bogota, Bogota (Colombia)

    1997-12-31

    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

  12. Atomic Transport Problems of Interest in Nuclear Systems; Problemes de Transport Atomique Presentant un Interet dans les Systemes Nucleaires; Problemy perenosa atomov, predstavlyayushchie interes v yadernykh sistemakh; Problemas de Transporte Atomico de Interes para la Ingenieria Nuclear

    Lundy, T. S.; Winslow, F. R. [Oak Ridge National Laboratory, TN (United States)

    1966-02-15

    sur la diffusion dans un metal. Leurs resultats sont en bon accord avec les calculs theoriques fondes sur un modele de 1)annihilation de l'excedent de defauts ponctuels (lacunes et interstices) par trois mecanismes, savoir la migration vers des puits fixes dont la distribution est homogene tels que les dislocations, la migration vers une surface libre et la recombinaison de defauts. (author) [Spanish] Se analizan en la memoria varios problemas encontrados al aplicar los datos basicos sobre difusion a sistemas de interes practico para la ingenierfa nuclear. Estos problemas se refieren a experimentos de difusion isotermica, difusion por gradiente termico y efectos de la radiacion sobre los procesos de difusion. La mayor parte de la informacion fidedigna sobre la difusion en solidos proviene de casos donde no existe, en esencia, gradiente alguno de concentracion de las especies que se difunden. Los sistemas que interesan a los ingenieros nucleares, en cambio, presentan casi invariablemente gradientes de concentracion. Asf, pues, para evaluarlos coeficientes adecuados es necesario contar con un conocimiento practico de la relacion existente entre los coeficientes de autodifusiOn y de difusion quimica. Ademas, es preciso conocer los coeficientes de actividad termodinamica como funciones de la composicion. Recientemente se ha demostrado sin lugar a dudas que el uso indiscriminado de una expresion del tipo de la de Arrhenius para describir la manera en que los datos de difusion dependen de la temperatura, puede introducir graves errores en el calculo de los coeficientes de difusion. Se analizan en la memoria las consecuencias de ese hecho, haciendo especial hincapie en los sistemas cubicos centrados en el cuerpo/ del tipo refractario. Los autores han estudiado teorica y experimentalmente el efecto de un gradiente termico sobre la redistribucion de impurezas sustitutivas en un metal. Ese trabajo ha contribuido a un mejor conocimiento de la importancia de este efecto en los

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

    Nathália Carvalho

    2013-07-01

    Abstract. Aiming to observe the viability of a new method for sampling acridoideos (by commonly known locusts and the ideal distance and number of samples for the study sample was proposed. The surveys were conducted in two areas of native grassland in Sao Sepe, in Central Depression, Rio Grande do Sul State. Samples were collected during the summer of 2009 with the help of a network of collection adapted. The distances were measured 5, 10, 15, 20 and 25m, with eight repetitions each, of which 40 samples per area, sampling was random. The response variables were: adults, nymphs, and total number of species of insects. Descriptive statistics were calculated, Chi-square test and used the median ratio/pseudo-sigma methodology combined with Jackknife resampling. We collected 969 specimens representing 22 species, 17 Genres and three distinct families Acrididae, Proscopiidae and Romaleidae, and also two Superfamilies (Acridoidea and Eumastacoidea. It was evident relative efficiency of the proposed method. The distance traveled of 25 m coupled with the number seven samples proved to be ideal for collecting of grasshoppers.

  14. Brief communication: Ancient nuclear DNA and kinship analysis: the case of a medieval burial in San Esteban Church in Cuellar (Segovia, Central Spain).

    Gamba, Cristina; Fernández, Eva; Tirado, Mirian; Pastor, Francisco; Arroyo-Pardo, Eduardo

    2011-03-01

    The aim of this work was to investigate a very common situation in the archaeological and anthropological context: the study of a burial site containing several individuals, probably related genetically, using ancient DNA techniques. We used available ancient DNA and forensic protocols to obtain reliable results on archaeological material. The results also enabled molecular sex determination to be compared with osteological data. Specifically, a modified ancient DNA extraction method combined with the amplification of nuclear markers with the AmpFlSTR®MiniFiler™ kit(Applied Biosystems) was used. Seven medieval individuals buried in four niches dated in the 15th Century at San Esteban Church in Cuellar (Segovia, Central Spain) were analyzed by the proposed method, and four of seven provided complete autosomal short tandem repeat (STRs) profiles. Kinship analyses comprising paternity and sibship relations were carried out with pedigree-specific software used in forensic casework. A 99.98% paternity probability was established between two individuals, although lower percentages (68%) were obtained in other cases, and some hypothetical kinship relations were excluded. The overall results could eventually provide evidence for reconstructing the historical record. Copyright © 2010 Wiley-Liss, Inc.

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

    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)

  16. The Text of the Agreement between Iran and the Agency for the Application of Safeguards in connection with the Treaty on the Non-Proliferation of Nuclear Weapons; Texto Del Acuerdo Concertado Entre El Iran Y El Organismo Para La Aplicacion De Salvaguardias En Relacion Con El Tratado Sobre La No Proliferacion De Las Armas Nucleares

    NONE

    1974-12-17

    The text of the agreement between Iran and the Agency for the application of safeguards in connection with the Treaty on the Non-Proliferation of Nuclear Weapons is reproduced in this document for the information of all Members [Spanish] Para informacion de todos los Estados Miembros, en el presente documento se trans cribe el texto del Acuerdo concertado entre el Iran y el Organismo para la aplicacion de salvaguardias en relacion con el Tratado sobre la no proliferacion de las armas nucle ares.

  17. Nuclear future: thinking for building. Proceedings of the 5. Brazilian national meeting on nuclear applications; 8. General congress on nuclear energy; 12. Brazilian national meeting on reactor physics and thermal hydraulics; Futuro nuclear: refletindo para construir. Anais do 5. Encontro nacional de aplicacoes nucleares; 8. Congresso geral de energia nuclear; 12. Encontro nacional de fisica de reatores e termo-hidraulica

    NONE

    2000-07-01

    The VII General Congress on Nuclear Energy (VII CGEN) decided on another approach, in order to promote nuclear energy (NE) for the average public. Instead of promoting an event for the nuclear area, the VII CGEN was open to the general public, aiming at high schools of the city of Belo Horizonte, where the meeting was held. The papers submitted were classified to two poster sessions, one called journalistic, open to the public, and technical, for the congressmen. The authors of the former session were asked to make their posters understandable for an average person. The present article shows the strategies used in dealing with local high schools, which includes the preparation of two series of posters, one dealing with the history of NE until 1945, and the other with applications of NE, due to the lack of this kind of material in Portuguese. The results of these efforts are shown and discussed, in terms of a better public image for NE and her community in Brazil. The public response showed that there is more than enough public for this kind of event, but not events enough. (author)

  18. 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

    Birraux, C.

    2002-01-01

    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.)

  19. The Problems of Controlling Defects in the Materials Used for the First Czechoslovak Nuclear-Power Station; Problemes de Controle des Defauts dans les Materiaux Utilises a la Premiere Centrale Nucleaire de Tchecoslovaquie; Problemy defektoskopicheskogo kontrolya stroitel'nykh materialov reaktora pervoj chekhoslovatskoj atomnoj ehlektrostantsii; Problemas de Control de Defectos en los Materiales Utilizados en la Primera Central Nuclear de Checoslovaquia

    Radislav, Filipp [Zavody Im.V.I. Lenina, Pl' zen, Czechoslovakia (Czech Republic)

    1965-09-15

    Pilsen, on a elabore a cet effet un instrument special grace auquel on peut faire des controles a haute temperature avec une grande precision. Le controle non destructif des pieces soudees peut se faire egalement par radioscopie. La verification de petites epaisseurs et celle, a haute temperature, de la base d'une soudure longitudinale sont realisees a l'aide des rayons X provenant d'un appareil a emanation circulaire, et de cassettes speciales. Pour la radioscopie des pieces soudees de grande epaisseur, on a recours a un betratron de fabrication tchecoslovaque. L'auteur decrit les methodes d'essai, indique les resultats obtenus et fait une etude comparative entre le betatron tchecoslovaque de 15 MeV et celui de Siemens. (author) [Spanish] En la memoria se describe brevemente el cuerpo del reactor de la primera central nuclear de Checoslovaquia. Las rigurosas normas seguidas en su construccion (acero inoxidable de baja aleacion, de 650 mm de espesor) exigieron elaborar un metodo de 'testigos'para proceder al control no destructivo del material basico y de las soldaduras. Para el control de calidad del material basico y de las soldaduras se recurrio en gran medida al metodo de impulsos ultrasonicos, utilizando una sonda. En la memoria se describe la tecnica empleada y se evaluan los datos obtenidos; tambien se expone el metodo de control de calidad de las piezas soldadas electricamente con formacion de escorias y de las soldadas en atmosfera de anhidrido carbonico, asf como las soldadas a mano mediante arco electrico. La integridad de las placas forjadas o laminadas se controla automaticamente en una instalacion de defectoscopia de fabricacion checoslovaca, qoe consta de dos partes: un mecanismo movil y un defectoscopio de ultrasonidos U1D-A2. La instalacion se distingue por poseer varios elementos nuevos. La influencia ejercida por la distancia sobre la amplitud de la sen al originada por el defecto se compensa de manera que la altura de la senal permanece constante

  20. 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

    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