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Sample records for central nuclear de zorita-1

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

    Directory of Open Access Journals (Sweden)

    DOMINGO QUILICI

    2013-06-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Andujar Sagredo, R.

    2013-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Torralbo, J. R.

    2016-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Bernardez Garcia, A.

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

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

    OpenAIRE

    2005-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Lopez, A.

    2012-11-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    Directory of Open Access Journals (Sweden)

    J.A. Menéndez

    2009-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Esteban, G.

    2014-10-01

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

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

    OpenAIRE

    Giol, Roberto

    1989-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Lexberg, A.

    2003-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    OpenAIRE

    Penche Alonso, Marta

    2016-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Ibanez, M.

    2013-09-01

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

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

    OpenAIRE

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

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Mostaza, J. M.

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Bello Paredes, S. A.

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Aranzadi, C.

    2008-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Martin Aparicio, J.; Atanasio, J.

    2011-07-01

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

  13. Improvements to the wastewater treatment from the beginning of the operation of Nuclear Asco; Mejoras en la depuracion de aguas residuales desde el inicio de la explotacion de la Central Nuclear de Asco

    Energy Technology Data Exchange (ETDEWEB)

    Esparza Martin, J. L.; Boronat Medico, M.

    2014-07-01

    Sanitary sewage in the Central Nuclear de Asco (CNA), are subject to a series of physico-chemical and biological processes in the wastewater waste (WWTP) before being discharged to the River Ebro. Since the beginning of the exploitation of CNA, the number of workers and administrative restrictions have evolved so that they have forced the execution of modifications of lowest and highest wingspan to comply with applicable legal requirements in the field of discharges. The overall objective of this work is to present the different stages of evolution of the WWTP of CNA from the start of operation of the plant up to the present day. The specific objective is to show the latest enhancements implanted in the sewage treatment plant and the benefits obtained. With technical improvements carried out in the WWTP of CNA, fixed the problem of disposal coming from the central nitrogen, one of the key problems and reason of failure to comply with the parameters imposed by the administration. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Dumas, H.; Sesma, J. L.

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Cerezo, L. M.

    2001-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  18. 30 years in the Veracruz state coast landscape: Laguna Verde nuclear power station. 1. ed.; 30 anos de paisaje costero veracruzano: Central Nucleoelectrica Laguan Verde

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

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

    OpenAIRE

    Fabio Abud Mansur

    2015-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Peco, J.

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Cano, J. C.; Ruiz, S.

    2013-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  9. Cleaning chemical and mechanical of heat exchangers in french nuclear plants; Limpieza mecanica y quimica de intercambiadores de calor en centrales nucleares francesas

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz, J. t.; Guerra, P.; Carreres, C.

    2013-03-01

    This project was carried out under the frame of the approval of LAINSA as a supplier of EDF in France. The inspection performed on systems called the moisture separator reheaters (GSS) of CPO series reactor of EDF nuclear power plants has shown evidence of significant clogging due to deposits of magnetite inside the tubes of tube bundle. The pressure drop between inlet and outlet of the heating was close to maximum design criterion. This effect could result in equipment damage and loss of plant productivity. The aim of the work was the design, development, approval and implementation of a procedure for un blocking the tubes of the GSS respecting the integrity of materials and ensuring the harmlessness of cleaning procedures. The procedure used was to completely remove magnetite deposits in order to recover a passage diameter and a surface finish equivalent to the origin, thus avoiding the replacement of the GSS and obtaining a considerable reduction of costs. The achieve these objectives we have developed a procedure that is basically a mechanical pre-cleaning of all tubes of the GSS in order to unblock tem, followed by a chemical cleaning where magnetite is dissolved and crawled out of the tube bundle. The main results were: -Corrosion less than 10 microns. 100-110 Kg of magnetite removed by heat exchanger. -Final pressure drop similar to that of new equipment. -Waste water: 70 m{sup 3} per exchanger, which were managed by an authorized waste management company. This procedure has been applied successfully in 14 GSS type heat exchangers in Fessenheim and Bugey nuclear power plants in France between 2009 and 2011. This project demonstrates that the long experience of LAINSA in the Spanish nuclear industry along with the knowledge and experience in chemical cleaning of SOLARCA, have served to successfully work demanding and mature markets such as the French nuclear market, solving the problem of deposits of magnetite with an effective and safe method for the treated

  10. Establishment and evolution of Radiological Environmental Monitoring Programmes in nuclear power plants; Establecimiento y evolucion de los programas de vigilancia radiologica ambiental en las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Marugan, I.; Luque, S.; Martin, J. L.; Rey, C.; Salas, R.; Sterling, A.; Ramos, L. M.

    2013-09-01

    This article presents a brief overview of how the Radiological Environmental Monitoring Programmes carried out around nuclear power plants have evolved associated to different reasons as the legal framework, operational phases of the facilities, development on the detection and measurement of low levels of radiation due to the state of art and best available technologies, changes within sites as well as in their surroundings and accident taken place inside and outside of our borders. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-08-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-01-01

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

  16. Regulatory challenges in the management of aging of structural materials in nuclear power plants; Retos reguladores en la gestion del envejecimiento de los materiales estructurales de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Castelo, C.; Mendoza, C.; Mas, E.; Conde, J. M.

    2013-07-01

    The article discusses two major pathways by which a regulatory body, and in particular the CSN, may participate in the acquisition of the necessary knowledge on mechanisms of aging of nuclear structural materials: to participate in forums to share operational experience and R and R project, both nationally and internationally. It notes the importance of this participation to carry out its regulatory function based on the knowledge acquired and the unique challenge of transferring that knowledge to rules and guidelines for their application. The article discusses various R and D projects in which the CSN participates directly. It calls for the presence of regulatory bodies in R and D project funded by the EU and the transfer of the results of such projects to codes, standards or guidelines for feasible implementation. (Author)

  17. Project development: testing of heat exchange of cooling system and cleaning fuel pool of NPP Cofrentes; Desarrollo del proyecto Prueba de Intercambio Termico del Sistema de Enfriamiento y Limpieza de la Piscina de combustible (G41) de Central Nuclear de Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Lopez, B.; Vaquer, J. I.; Mota, M.; Reyes, S.; Palomo, M.; Ruiz, G.; Rebollo, C.

    2012-07-01

    Heat exchanger tests were carried out and data in the thermodynamic models developed, turned and can verify that the efficiency of heat exchange met the requirements. The work concluded complying at all times with the technical specifications and quality proposals by the Department of engineering at the Central Nuclear de Cofrentes.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  20. Follow-up of the results of the nuclear power plant stress tests and action plan.; Seguimiento de los resultados de las pruebas de resistencia de las centrales nucleares y plan de accion

    Energy Technology Data Exchange (ETDEWEB)

    Mellado Jimenez, I.

    2012-07-01

    The results of the stress tests carried out by the European nuclear power plants in the wake of the Fukushima Daiichi accident, subsequently subjected to peer reviews, have made it possible to identify the measures to be applied to improve safety. Action plans have been put in place to implement these measures within appropriate time frames. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Cicero, R.; Corchon, F.

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Esparza Martin

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

    This work aims to present the implementation process of the Monitoring of the State and behavior of the systems in the Nuclear plan Almaraz. Will define the scope, process, frequencies and criteria of evaluation of the State and behavior of the systems included in the Plan of reliability, as well as the documentary requirements of this evaluation. Cases will also be collected practical real phenomena detected during monitoring degradation made and will explain the actions taken prior to the failure.

  4. Practical training in the operation of nuclear power plants with Interactive Graphic Simulator of Zorita; Formacion practica en la operacion de centrales nucleares con el Simulador Grafico Interactivo de Zorita

    Energy Technology Data Exchange (ETDEWEB)

    Cuervo, D.; Garcia-Herranz, N.; Garcia, S.; Davila, R.; Ahnert, C.; Aragones, J. M.; Cabellos, O.; Gallego, E.; Lorente, A.; Minguez, E.; Rebollo, L.; Blanco, J.

    2010-07-01

    In April 2008 a collaboration agreement was signed between Gas Natural Union Fenosa and the Universad Politecnica de Madrid for the creation of the Aula Jose Cabrera dedicated to train professionals in the field of nuclear technology. The Classroom located in the Department of Nuclear Engineering, has been equipped with the Interactive Graphic Simulator of Zorita (SGIZ). The use of the simulator intended to improve the quality of teaching in the area of Nuclear Engineering. It integrates in the teachings of Industrial Engineering degree and the Master of Nuclear Science and Technology. Different manuals are under preparation to make it a suitable tool for teaching purpose. These manuals will guide the student so that learning takes place both through the guidance of the teacher as independently. (Author) 3 refs.

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

    Energy Technology Data Exchange (ETDEWEB)

    Perez Pereira, J.

    2013-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Pelayo, F.; Mendizabal, R.

    2005-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Silva, M.

    2005-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Mendez, M.

    2012-11-01

    In recent years, Spain Nuclear Power Plant Engineering have switched their project/task management method to Critical Chain multi-project management, developed by Dr. Goldratt, achieving outstanding results in improving quality and productivity. Multitasking reduction, task and resource synchronizing without the need of exact schedules, implementing a real-time priority information system, relying on the software Concerto, and daily decision making are the basis for the management change that has generated productivity increases of between 20% to 50%, opening new horizons for improvement in other scenarios such as optimizing refueling shutdowns. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The seismic risk taken into account during the sizing of the nuclear power plant of Fessenheim seems to have been under evaluated at this time. The revaluation of the seismic risk, as proposed, until this day by EDF in order to the third ten-year visit of the power plant, planned for 2009, leads to a significant under evaluation of the risk and then is not acceptable. The present expertise details point by point the weaknesses of these revaluation. The power plant has been sized in an elastic manner that is generally strongly for the safety side. It is imperative to proceed the most quickly as possible to a deep control of the seismic resistance of the power plant of Fessenheim and then after having proceeded to a revision of the seismic risk in taking into account the actual knowledge in this field. (N.C.)

  11. Towards Quantum Transport for Central Nuclear Reactions

    CERN Document Server

    Danielewicz, Pawel; Barker, Brent

    2016-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Soto Lanuza, A.

    2000-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Sarandeses, S.

    2014-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez del M, C.

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Agudo Montero, L.

    2013-07-01

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

  17. Control rod cluster drop time anomaly Guandong nuclear power station (Daya bay) and Electricite de France nuclear power stations (1450 MWe N4 Series); Anomalie de temps de chute des grappes de controle centrale de guang dong (daya bay) et centrales d`electricite de France (Palier N4-1450 MWE)

    Energy Technology Data Exchange (ETDEWEB)

    Olivera, J.J.; Naury, S.; Tricot, N.; Tran Dai, P.; Gama, J.M.

    1996-12-31

    The anomaly of control rod cluster drop time revealed at Guandong Nuclear Power Station in Daya Bay and in the Chooz B1 pilot unit for the N4 series, led to the replacement of the M1 type control rod cluster guide tubes with 1300 MWe PWR type guide tubes, adapted to the geometry of the Guandong reactors and the 1450 MWe reactors of the N4 series. The comparison of the drop times obtained with the 1300 MWe type control rod cluster guide 1300 MWe type control rod cluster guide tubes gave satisfactory results. These met the safety criterion for N4 series control rod cluster drop times (2.15 under hot shutdown conditions). The drop time tests which will be carried out in middle of and at the end of cycle 1 of Chooz B1 should make it possible to finally validate the solution already successfully implemented at Guandong. However, this anomaly has revealed the limits of representativeness of the experimental test loops with regard to the real reactor configuration. In view of this, it has been deemed necessary to ask Electricite de France to pursue its analysis both on the understanding of the phenomena which led to this anomaly and on the limits of the representativeness of the experimental test loops. (authors).

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-11-01

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

  19. MOCAT project: support tool to the management of the emergencies in the nuclear power plant of Santa Maria of Garona; Proyecto MOCAT: Herramienta de apoyo a la gestion de las emergencias en la central nuclear de Santa Maria de Garona

    Energy Technology Data Exchange (ETDEWEB)

    Calleja, J. L.

    2010-07-01

    Santa Maria de Garona NPP, as part of its continuous improvement philosophy, has decided to undertake the modernization of its Technical Support Center (CAT with the aim of improving the emergency management, provided in the Internal Emergency Plan. To this end, Tecnatom, applying the know-how acquired and within its line of technological innovation, has designed the Technical Support Center modernization project, MOCAT, in collaboration with Garona NPP. This project is basically the application of new information and communications technologies to the management of the information available on the CAT, and the computerization of the procedures for the responsible from the different areas of the CAT, which it is going to contribute significantly to the improvement of the security, allowing a better understanding of the state of the plant in emergency as well as a faster and smoother decision making, and an improved training and education of those responsible for the CAT in emergency management. (Author) 8 refs.

  20. Projeto de pesquisa Energia Nuclear

    Directory of Open Access Journals (Sweden)

    Marcelo Henrique Barbosa Fiori

    2011-07-01

    Full Text Available Esse  projeto tem como intuito mostrar como pode se útil a utilização da energia nuclear para o abastecimento elétrico de uma escola. Mostrando que a energia nuclear é sim uma fonte viável de produção de energia “[...] meio quilo de urânio, do tamanho da ponta do meu dedo se você conseguir liberar toda a energia equivale a 5.000 barris de petróleo”.

  1. Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved; Cycles de combustibles. Production d'uranium, programme de centrales electriques et effort financier correspondant

    Energy Technology Data Exchange (ETDEWEB)

    Andriot, J.; Gaussens, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author)Fren. [French] L'etude presentee comporte l'examen d'un certain nombre d'hypotheses de programmes de centrales nucleaires de types differents. Ces programmes correspondent a l'utilisation de tonnages d'uranium et de thorium de l'ordre de grandeur de ceux qui seront probablement produits par la France dans les quinze prochaines annees. Comme il est possible de batir un programme de centrales nucleaires, comportant a la fois plusieurs filieres suivant des variantes en nombre infini, on s'est contente d'examiner successivement les resultats ous si on utilisait exclusivement l

  2. The continuous improvement system of nuclear power plant of Laguna Verde; El sistema de mejora continua de la central nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-10-15

    This paper describes the continuous improvement system of nuclear power plant of Laguna Verde and the achievements in implementing the same and additionally two study cases are presents. In February 2009 is noteworthy because the World Association of Nuclear Operators we identified as a learning organization, qualification which shows that the continuous improvement system has matured, and this system will expose as I get to learn to capitalize on our own experiences and external experiences diffused by the nuclear industry. In 2007 the management of nuclear power plants integrates its improvement systems and calls it continuous improvement system and is presented in the same extensive report that won the National Quality Award. This system is made up of 5 subsystems operating individually and are also related 1) human performance; 2) referential comparison or benchmarking; 3) self-assessment; 4) corrective action and 5) external operating experience. Five subsystems that plan, generate, capture, manage, communicate and protect the knowledge generated during the processes execution of nuclear power plant of Laguna Verde, as well as from external sources. The target set in 2007 was to increase the intellectual capital to always give response to meeting the security requirements, but creating a higher value to quality, customer, environment protection and society. In brief each of them, highlighting the objective, expectations management, implementation and some benefits. At the end they will describe two study cases selected to illustrate these cases as the organization learns by their continuous improvement system. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-05-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-07-01

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

  6. Life time of nuclear power plants and new types of reactors; La duree de vie des centrales nucleaires et les nouveaux types de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-01

    This report, realized by the Evaluation Parliamentary Office of scientific and technological choices, aims to answer simple but fundamental questions for the french electric power production. What are the phenomena which may limit the exploitation time of nuclear power plants? How can we fight against the aging, at which cost and with which safety? The first chapter presents the management of the nuclear power plants life time, an essential element of the park optimization but not a sufficient element. The second chapter details the EPR and the other reactors for 2015 as a bond between the today and tomorrow parks. The last chapter deals with the necessity of efforts in the research and development to succeed in 2035 and presents other reactors in project. (A.L.B.)

  7. Analysis of a natural draught tower in the circulation seawater system of nuclear power plant of Laguna Verde; Analisis de una torre de tiro natural en el sistema de agua de circulacion de mar de la central nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Vargas A, A. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, Veracruz (Mexico)], e-mail: francisco.tijerina@cfe.gob.mx

    2009-10-15

    The analysis of a natural draught tower in open circuit for the cooling system of seawater circulation on the nuclear power plant of Laguna Verde, it is based on conditions of 2027 MWt and 2317 MWt, where the flows of circulation water system hardly vary and whose purpose will be, to cool the seawater circulation. The circulation water system is used as heat drain in main condenser of turbo generator to condense the nuclear vapor. The annual average temperature in the seawater at present is of 26 C to the entrance to circulation water system and it is vary in accordance with the time of year. The mean temperature of leaving of circulation water system to the sea is of 41 C. Having a cooling tower to reduce the entrance temperature to the circulation water system, it improves the efficiency of thermal transfer in condenser, it improves the vacuum in condenser giving more operative margin to avoid condenser losses by air entrances and nuclear power plant shutdowns, as well as for to improve the efficiency of operative balance of nuclear power plant, also it prevents the impact in thermal transfer efficiency in condenser by the climatic change. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Bendarag, A

    1999-07-09

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  11. Communication and surrounding of Asco and Vandellos II nuclear power plants; La comunicacion y el entorno de las centrales de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The Asco and Vandellos-II power plants have always been integrated into the regions where they are located, and they take an active part in the development of surrounding towns through quality employment provided by our facilities, social and cultural support and aid to development promoted by regional councils. Communication to media is a corporate priority defined in our strategic plant, to ensure openness, rigour and punctuality. We also attend to the visitors who want to learn more about our facilities in the visitor center, and we have agreements with agrarian institutions in the area so that students can de practical training in the farms we own for agricultural production. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  14. Centralized vs. De-centralized Multinationals and Taxes

    DEFF Research Database (Denmark)

    Nielsen, Søren Bo; Raimondos-Møller, Pascalis; Schjelderup, Guttorm

    2005-01-01

    The paper examines how country tax differences affect a multinational enterprise's choice to centralize or de-centralize its decision structure. Within a simple model that emphasizes the multiple conflicting roles of transfer prices in MNEs - here, as a strategic pre-commitment device and a tax...... manipulation instrument -, we show that (de-)centralized decisions are more profitable when tax differentials are (small) large.Keywords: Centralized vs. de-centralized decisions, taxes, MNEs.JEL-Classification: H25, F23, L23....

  15. Banco Central de Costa Rica

    Directory of Open Access Journals (Sweden)

    Sauter, Franz

    1963-06-01

    Full Text Available This new building is intended to house the various services of the Central Bank of Costa Rica. It has a prestressed concrete structure, and consists of a basement parking space for 105 vehicles, and nine storeys, providing altogether a floor surface of 12,000 ms2. The building rests on a ground area of 40 by 60 ms, and the main structure occupies 22 by 45 ms. This Bank is located in a district of narrow streets, but its main side overlooks a green open space, which will improve its visibility and appearance. The building structure is made up of a framework of prestressed beams and columns. The beams have been concreted at the site, and the joists, which are also prestressed, are factory made. This framework, at each floor level, constitutes the basis of a continuous slab, which renders the total structure exceedingly stiff. The main continuous girders span 11.22 ms spaces, and vary in cross section. The prestressing reinforcements consist of 6 Loeba type cables. This is an original design by Dr. Leonhardt, in which the cables are placed on three horizontal layers, of parabolic outline. Each cable is made up of 12 x 5.4 mm wires, with a breaking stress of 180 kg/mm2 The tensioning stress was 108 kg/mm2, and the total prestress load is 29,700 kgs. The cables run in corrugated metal tubes, and these were kept in precise position with the aid of distance pieces.El nuevo edificio, destinado a agrupar los servicios del Banco Central de Costa Rica, está constituido por una estructura de hormigón pretensado. El inmueble dispone de un sótano, estacionamiento propio para 105 vehículos y nueve plantas, con una superficie total de 12.000 metros cuadrados. Se asienta sobre una base de 40x60 m, donde se levanta un núcleo central de 22x45 metros. Está situado en un barrio de calles estrechas, pero tiene su fachada, principal frente a una zona verde que le proporcionará mayor categoría y visibilidad. La estructura se compone de una retícula de vigas

  16. Decision no. 2011-DC-0213 of the French nuclear safety authority from May 5, 2011, ordering Electricite de France (EDF) company to proceed to a complementary safety evaluation of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0213 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a Electricite de France (EDF) de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to Electricite de France (EDF) company, operator of the French NPPs. (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  18. Jose Cabrera NPP; Central Nuclear Jose Cabrera

    Energy Technology Data Exchange (ETDEWEB)

    Diez, P.

    2004-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-12-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  3. La central electronuclear de Garellano (Italia

    Directory of Open Access Journals (Sweden)

    Morandi, Riccardo

    1965-11-01

    Full Text Available This power station works on the forced circulation, double cycle process. It has a turboalternator of 160,000 kw, and is situated 7 km above the mouth of the river Garellano. The most significant feature of this type of building is the spherical container, within which the reactor is located. The connection between this and the turboalternator hall is also of interest. In addition there is a complex set of other facilities, including the engine hall, workshop, laboratories, offices and stores. Great care has been lavished on the reinforced concrete structure, and on the plastic quality of the whole building, taking care that it fits within the general environment. The need to have the use of a powerful bridge crane, and provide protection against radiation, has involved the construction of reinforced concrete of very large sections, in contrast to the more conventional type of structures. The external paraments are of untreated concrete, with abutments. Administration and executive office buildings are of conventional design.Esta central, de doble ciclo y circulación forzada, dispone de un grupo turboalternador de 160.000 kW. Ha sido construida a unos 7 km aguas arriba de la desembocadura del río Garellano. Lo más característico de este tipo de estructuras industriales es el recipiente esférico, en cuyo interior se halla instalado el reactor y la comunicación entre éste y la sala del turboalternador. El complejo consta de servicios diversos: salas de máquinas, talleres, laboratorios y oficinas, por cuya razón se ha estudiado con esmero no solamente la estructura de hormigón armado, sino el aspecto plástico y estético de todo el edificio, en armonía con el paisaje que lo rodea. La necesidad de disponer de un puente- grúa de gran capacidad y la protección debida contra las radiaciones, han originado secciones poco corrientes en la estructura de hormigón armado, siendo ésta su característica diferencial con respecto a las

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-07-01

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

  8. Analysis of the noise of the jet pumps of the Unit 2 of the Laguna Verde nuclear power plant; Analisis de ruido de las bombas de chorro de la Unidad 2 de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Castillo D, R.; Ortiz V, J.; Ruiz E, J.A. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico); Calleros M, G. [CFE, Central Nucleoelectrica de Laguna Verde, Alto Lucero, Veracruz (Mexico)]. E-mail: rcd@nuclear.inin-mx

    2004-07-01

    The use of the analysis of noise for the detection of badly functioning of the components of a BWR it is a powerful tool in the determination of abnormal conditions of operation, during the life of a nuclear plant of power. From the eighties, some nuclear reactors have presented problems related with the jet pumps and the knots of the recirculation. The Regulatory Commission of the United States, in the I E bulletin 80-07, recommended to carry out a periodic supervision of the pressure drop of the jet pumps, to prevent structural failures. In this work, methods of analysis of noise are used for the detection of abnormal conditions of operation of the jet pumps of a BWR. Signals are analysed to low and high frequency of pressure drop with the NOISE software that is in development. The obtained results show the behavior of the jet pumps of jet 6 and 11 before and after a partial blockade in their throats where the pump 6 return to their condition of previous operation and the pump 11 present a new fall of pressure, inside the limit them permissible of operation. The methodology of the analysis of noise demonstrated to be an useful tool for the badly functioning detection, and you could apply to create a database to supervise the dynamic behavior of the jet pumps of an BWR. (Author)

  9. Decision no. 2011-DC-0220 of the French nuclear safety authority from May 5, 2011, ordering the FBFC company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0220 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a FBFC de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the FBFC (Franco-Belge de Fabrication du Combustible), a daughter fuel fabrication company of Areva NC (France). (J.S.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Martinez M, E

    1992-05-15

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

  11. Feasibility analysis in the expansion proposal of the nuclear power plant Laguna Verde: application of real options, binomial model; Analisis de viabilidad en la propuesta de expansion de la central nucleoelectrica Laguna Verde: aplicacion de opciones reales, modelo binomial

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez I, S.; Ortiz C, E.; Chavez M, C., E-mail: lunitza@gmail.com [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2011-11-15

    At the present time, is an unquestionable fact that the nuclear electrical energy is a topic of vital importance, no more because eliminates the dependence of the hydrocarbons and is friendly with the environment, but because is also a sure and reliable energy source, and represents a viable alternative before the claims in the growing demand of electricity in Mexico. Before this panorama, was intended several scenarios to elevate the capacity of electric generation of nuclear origin with a variable participation. One of the contemplated scenarios is represented by the expansion project of the nuclear power plant Laguna Verde through the addition of a third reactor that serves as detonator of an integral program that proposes the installation of more nuclear reactors in the country. Before this possible scenario, the Federal Commission of Electricity like responsible organism of supplying energy to the population should have tools that offer it the flexibility to be adapted to the possible changes that will be presented along the project and also gives a value to the risk to future. The methodology denominated Real Options, Binomial model was proposed as an evaluation tool that allows to quantify the value of the expansion proposal, demonstrating the feasibility of the project through a periodic visualization of their evolution, all with the objective of supplying a financial analysis that serves as base and justification before the evident apogee of the nuclear energy that will be presented in future years. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-04-01

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

  13. Construction project of Flamanville 3 NPP. The participation of Iberdrola engineering and Construction; El proyecto de construccion de la central nuclear de Flamanville 3. La participacion de Iberdrola Ingenieria y Construccion

    Energy Technology Data Exchange (ETDEWEB)

    Diaz Prada, J. I.; Cubian, B.

    2014-10-01

    Iberdrola Engineering and Construction (IIC) leads several projects mini EPC for the EPR Flamanville 3 NPP for providing important for safety components and auxiliary systems in the pump house and in the turbine island. The realization of this new nuclear project has been a challenge from the technical and organizational perspective because the plant is the first of the new nuclear station (FDAKE) type EPR 1700 MWe series in a highly restrictive environment due to to the large number of particular requirements from the final customer and the meager degree of progress of the design to the date of commencement of construction. (Author)

  14. Pensar la organización del tiempo de trabajo cuando la tecnología cambia: el caso del equipo de trabajo de operación de una central nuclear

    Directory of Open Access Journals (Sweden)

    Sophie Prunier-Poulmaire

    2011-12-01

    Full Text Available The construction of a new generation of nuclear power plant has implied an ergonomics contribution in order to define the shift work schedule for the future operation crew. The study was carried out in three existing nuclear power plants through observation of activities specific to the concerned operating professionals. The data collected highlights major disparities between the performed tasks and their dynamics in terms of physical and mental demands. Furthermore, the same data underlines a strong temporal interdependence amidst the operation crew based on shift work schedules and the maintenance crew organized with set day time schedules. Vast differences are also recorded in terms of physical and mental demands of the tasks performed between day and night shifts as well as between the different stages of nuclear installations. The difficulties of workforce management are also at the source of large differences concerning the theoretical shift work schedule and the shift work schedule in place. In a multifactorial and systemic approach, with the general knowledge of chronobiology and the characteristics of the population involved, the outcomes will be a necessary component to define the shift work schedule for the operation crew of the nuclear power plant in construction.

  15. Los Discursos de Legitimación de la Industria Nuclear Española

    Directory of Open Access Journals (Sweden)

    Luis Sánchez Vázquez

    2009-06-01

    Full Text Available La controversia sobre el uso de la energía nuclear es un tema clave en el actual debate sobre el modelo energético. El análisis de esta situación desde la perspectiva de los estudios de Ciencia y Tecnología para la Paz ayuda a esclarecer ciertos condicionantes de la introducción y desarrollo de opción energética en nuestro país y en el contexto internacional, con objeto de contribuir al esclarecimiento de ciertas posiciones dentro del panorama energético actual. En este marco, el trabajo intenta recoger la evolución del discurso de la industria nuclear española sobre los principales focos conflictivos asociados a la energía nuclear, a través del análisis de las publicaciones del Foro de la Industria Nuclear Española durante el periodo de mayor auge de dicha industria y la comparación con el discurso actual. Para ello han sido escogidos los documentos publicados por el Foro Nuclear en los periodos 1963-1977 y 2000-2004, de cuyo análisis se desprende una evolución notable de las posiciones en temas como la opinión pública o el cambio climático; ciertos cambios en los argumentos sobre los costes de generación nucleares o la seguridad de las centrales; mientras que el discurso permanece muy similar en una cuestión central como los residuos.

  16. Modernization of the Electric Power Systems (transformers, rods and switches) in the Laguna Verde Nuclear Power Plant (Mexico); Modernizacion de los Sistemas Electricos de Potencia (Transformadores de Principales, Interruptor de Generacion, Barras de Fase Aislada) de la Central Nuclear de Laguna Verde (Mexico)

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Solarzano, J. J.; Gabaldon Martin, M. A.; Pallisa Nunez, J.; Florez Ordeonez, A.; Fernandez Corbeira, A.; Prieto Diez, I.

    2010-07-01

    Description of the changes made in the Electric Power Systems as a part of the power increase project in the Laguna Verde Nuclear Power Plant (Mexico). The main electrical changes to make, besides the turbo group, are the main generation transformers, the isolated rods and the generation switch.

  17. Estimation of requirements of eolic energy equivalent to the electric generation of the Laguna Verde nuclear power plant; Estimacion de requerimientos de energia eolica equivalente a la generacion electrica de la Central Nucleoelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Garcia V, M.A.; Hernandez M, I.A. [Facultad de Ingenieria, Division de Ingenieria Electrica, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: maiki27@yahoo.com; Martin del Campo M, C. [Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, UNAM, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2004-07-01

    The advantages are presented that have the nuclear and eolic energy as for their low environmental impact and to the human health. An exercise is presented in the one that is supposed that the electric power generated by the Laguna Verde Nuclear Power plant (CNLV), with capacity of 1365 M W, it should be produced by eolic energy when in the years 2020 and 2025 the units 1 and 2 of the CNLV reach its useful life and be moved away. It is calculated the number of aero generators that would produce the electric power average yearly of the CNLV, that which is equal to install eolic parks with capacity of 2758 M W, without considering that it will also be invested in systems of back generation to produce electricity when the aero generators stops for lack of wind. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-07-01

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

  19. Components production and assemble of the irradiation capsule of the Surveillance Program of Materials of the nuclear power plant of Laguna Verde;Fabricacion de componentes y ensamble de la capsula de irradiacion del Programa de Vigilancia de Materiales de la central nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Medrano, A. [ININ, Departamento de Tecnologia de Materiales, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2009-07-01

    To predict the effects of the neutrons radiation and the thermal environment about the mechanical properties of the reactor vessel materials of the nuclear power plant of Laguna Verde, a surveillance program is implemented according to the outlines settled by Astm E185-02 -Standard practice for design of surveillance programs for light-water moderated nuclear power reactor vessels-. This program includes the installation of three irradiation capsules of similar materials to those of the reactor vessels, these samples are test tubes for mechanical practices of impact and tension. In the National Institute of Nuclear Research and due to the infrastructure as well as of the actual human resources of the Pilot Plant of Nuclear Fuel Assembles Production it was possible to realize the materials rebuilding extracted in 2005 of Unit 2 of nuclear power plant of Laguna Verde as well as the production, assemble and reassignment of the irradiation capsule made in 2006. At the present time the surveillance materials extracted in 2008 of Unit 1 of the nuclear power plant of Laguna Verde are reconstituting and the components are manufactured for the assembles of the irradiation capsule that will be reinstalled in the reactor vessel in 2010. The purpose of the present work is to describe the necessary components as well as its disposition during the assembles of the irradiation capsule for the surveillance program of the reactors vessel of the nuclear power plant of Laguna Verde. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

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

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

    CERN Document Server

    2000-01-01

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

  2. Analysis of the micro-structural damages by neutronic irradiation of the steel of reactor vessels of the nuclear power plant of Laguna Verde. Characterization of the design steel; Analisis de los danos micro-estructurales por irradiacion neutronica del acero de la vasija de los reactores de la Central Nuclear de Laguna Verde. Caracterizacion del acero de diseno

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel y Rodriguez, M.; Garcia B, A. [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Fisica, Av. Luis Enrique Erro s/n, Unidad Profesional Adolfo Lopez Mateos, Col. Lindavista, 07738 Mexico D. F. (Mexico); Longoria G, L. C., E-mail: mmoranchel@ipn.m [ININ, Direccion de Investigacion Cientifica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-09-15

    The vessel of a nuclear reactor is one of the safety barriers more important in the design, construction and operation of the reactor. If the vessel results affected to the grade of to have fracture and/or cracks it is very probable the conclusion of their useful life in order to guarantee the nuclear safety and the radiological protection of the exposure occupational personnel, of the public and the environment avoiding the exposition to radioactive sources. The materials of the vessel of a nuclear reactor are exposed continually to the neutronic irradiation that generates the same nuclear reactor. The neutrons that impact to the vessel have the sufficient energy to penetrate certain depth in function of the energy of the incident neutron until reaching the repose or to be absorbed by some nucleus. In the course of their penetration, the neutrons interact with the nuclei, atoms, molecules and with the same crystalline nets of the vessel material producing vacuums, interstitial, precipitate and segregations among other defects that can modify the mechanical properties of the steel. The steel A533-B is the material with which is manufactured the vessel of the nuclear reactors of nuclear power plant of Laguna Verde, is an alloy that, among other components, it contains atoms of Ni that if they are segregated by the neutrons impact this would favor to the cracking of the same vessel. This work is part of an investigation to analyze the micro-structural damages of the reactor vessels of the nuclear power plant of Laguna Verde due to the neutronic irradiation which is exposed in a continuous way. We will show the characterization of the design steel of the vessel, what offers a comprehension about their chemical composition, the superficial topography and the crystalline nets of the steel A533-B. It will also allow analyze the existence of precipitates, segregates, the type of crystalline net and the distances inter-plains of the design steel of the vessel. (Author)

  3. Análisis de la respuesta estructural del edificio de contención de un reactor nuclear PWR frente a una secuencia de Station Blackout

    OpenAIRE

    2013-01-01

    Después del Accidente que sucedió el 11 de marzo de 2011 en la central nuclear de Daichii-Fukushima, han sido muchos los debates reabiertos acerca de la seguridad que ofrecen los reactores nucleares en operación. Debido a las incertidumbres que este accidente ha suscitado, surge ésta tesina, en la que se pretende conocer y comprender técnicamente que sucedería si un accidente similar al de Fukushima ocurriese en uno de los reactores de nuestro país. Con el principal objetivo de encontrar res...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-11-01

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

  5. Evolution of Technology Laser Scanner. Implications for use in Nuclear Power and Radioactive Facilities; Evolucion de la Tecnologia Laser Escaner. Implicaciones en uso en Centrales Nucleares e Instalaciones Radioactivas

    Energy Technology Data Exchange (ETDEWEB)

    Sarti Fernandez, F.; Bonet, J.

    2012-07-01

    The main technical factors affecting these teams their actual implementation in nuclear power plants will be analyzed: data acquisition speed, sensitivity, laser power, autonomy, contamination of equipment, radiation effect, etc. In conclusion, the real difference is displayed in the data collection in function of various technologies, embodied in field time, and costs.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    OpenAIRE

    2012-01-01

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

  9. Exploitation continuation of Fessenheim nuclear plant nr 1 reactor after thirty years of operation; Poursuite d'exploitation du reacteur n.1 de la centrale nucleaire de fessenheim apres trente annees de fonctionnement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    After having recalled the regulatory framework, this report indicates how the Fukushima accident has been taken into account by the French nuclear safety authority (ASN) for the decision of keeping on operating the Fessenheim nuclear plant. Then, after a general presentation of nuclear installations, the report describes some peculiarities of the Fessenheim power plant with respect to the other French nuclear plants. It comments and discusses various issues: reactor exploitation, fuel management, vessel exploitation, exploitation of the main secondary circuits, of the confinement enclosure, and of other equipment. It recalls significant events, exploitation rules, and modifications brought to the reactor. It gives a global assessment. The authors report the safety re-examination (approach, compliance examination, security re-assessment), controls performed during decennial inspection (main controls and tests, implementation of modifications foreseen by safety re-examination, significant events, monitoring by the ASN, reactor restarting after the third decennial inspection). Perspectives are then discussed for the ten following years in terms of maintenance policy, ageing management, reactor vessel serviceability, and additional actions within the frame of ageing management. The operation continuation is then discussed

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-07-01

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

  12. Methodology of aging management in structures, systems and components of a nuclear power plant and its application to a pilot program in Laguna Verde; Metodologia de la gestion del envejecimiento en estructuras, sistemas y componentes de una central nuclear y su aplicacion a un programa piloto en Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Fernandez S, G. [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, Dos Bocas, 54270 Veracruz (Mexico)], e-mail: gfdezs@cfe.gob.mx

    2009-10-15

    From its origin the nuclear power plants confront the effects of time and of environment, giving as result the aging of its structures, systems and components. In this document the general process is described for the establishment of Aging Management Program developed by IAEA. Following the program methodology is guaranteed that a nuclear power plant manages the aging effects appropriately and to make decisions for its solution, assuring the characteristic functions of structures, systems and components of same nuclear power plant. On the other hand, the implantation of an aging management program constitutes the base for development of a licence renovation program, like it can be the specific case of the Central Laguna Verde Units 1 and 2. (Author)

  13. Nuclear research center transformation experience; Experiencia de transformacion de un centro de investigacion nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, J. L.; Jimenez, J. M.

    2001-07-01

    As consequence of the changes in the energy polities of each countries in the 80th. many of the Nuclear Research Centres suffered a transformation (more of less deep) in other Research and Development Centres with a wider spectrum that the exclusively nuclear one. This year is the 50 anniversary of the Spanish Centre of Nuclear Research-Junta de Energia Nuclear.The JEN the same as other suffered a deep renovation to become the CIEMAT Centro de Investigaciones Energeticas Medioambientales y Tecnologicas (Research Centre for Energy, Environment and Technology). This paper is focussed on the evolution of JEN to CIEMAT besides analysing the reach of this re-foundation considering the political reasons and technical aspect that justified it and the laws in those it is based on. (Author)

  14. Nuclear fragmentation in central collisions: Ni + Au from 32 to 90 A*MeV; Fragmentation dans les collisions centrales du systeme Ni + Au de 32 a 90 A MeV

    Energy Technology Data Exchange (ETDEWEB)

    Bellaize, N

    2000-11-03

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

  15. Settling and growth of D. polymorpha in the raw water circuits of the Cattenom nuclear power plant (Moselle, France); Fixation et croissance de D. Polymorpha dans les circuits d`eau brute de la centrale nucleaire de Cattenom

    Energy Technology Data Exchange (ETDEWEB)

    Moreteau, J.C.; Khalanski, M.

    1994-05-01

    A``biological profile`` of the zebra mussels which are infesting certain circuits of the Cattenom nuclear power plant has been provided by data collected during a three-year measurement programme (1991-1993). The larval settlement periods and the growth of settled mussels were monitored. A simple mathematical model, which calculates the shell growth on the long term, was calibrated with the field data. It is based on three functions representing the effect of the initial size, water temperature and fool availability (plankton chlorophyll a). (authors). 13 refs., 7 figs., 4 tabs.

  16. Plan de empresa Restaurante Central Lunch

    OpenAIRE

    Valencia Ochoa, Marisol

    2015-01-01

    Con el presente documento se pretende dar a conocer el plan de empresa de un restaurante de comida ejecutiva gourmet de nombre Central Lunch, el cual estará ubicado en la ciudad de Pereira y se enfocará en la atención a clientes de estratos 4 y 5 con una gran influencia del uso de nuevas tecnologías para la interacción con el cliente. El trabajo indica en detalle cómo se visualiza la idea de negocio desde su concepción, la forma en que este operará, su cultura en atención al cliente, y por úl...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-10-15

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

  18. Review of progress in modelling for the assessment of the operating life of a nuclear power plant; Panorama des progres de la modelisation au service de la duree de vie des centrales

    Energy Technology Data Exchange (ETDEWEB)

    Monnier, B. [Electricite de France (EDF/RD), 78 - Chatou (France); Gilles, Ph. [FRAMATOME ANP, 92 - Paris-La-Defence (France); Chauliac, Ch. [CEA Saclay, Dir. de l' Energie Nucleaire DEN/DSOE, 91 - Gif sur Yvette (France)

    2004-07-01

    This article reviews the contributions of simulation and modelling to the assessment of the service life of a nuclear power plant. 4 aspects are considered. The first aspect concerns the operating life of the reactor vessel, in order to evaluate its aging a series of more or less intertwined modelling is necessary, they concern thermal-hydraulic transients, neutron fluences, damages due to irradiation and thermal-mechanical behaviour. The second aspect is the use of simulation to optimize non-destructive testing (NDT) particularly to assess the performances and limits of NDT methods in order to assure safety in any situation. The third aspect concerns the simulation of welding in order to assess the risk of defect occurrence, the pile-up of residual stresses and the feasibility of a complex welding. The last aspect is a global simulation of a nuclear unit as a whole involving its main components such as vessel, pumps, steam generators, turbine...; their maintenance, their failure risks in order to define indicator parameters that are relevant to the real state of the plant. (A.C.)

  19. Viabilidade de uso do delineamento composto central

    Directory of Open Access Journals (Sweden)

    Nazaré Barata Mateus

    2001-05-01

    Full Text Available O delineamento composto central é um delineamento simétrico e de segunda ordem, constituído de duas partes: o fatorial 2k, com um ou mais pontos centrais, e a parte axial. O objetivo deste trabalho foi o de verificar, com simulações, a viabilidade do uso desse tipo de delineamento nas áreas de pesquisas de campo, como em Agronomia; em laboratórios de Fitopatologia, Virologia e Entomologia, em pesquisas onde o coeficiente de variação não é superior a 6%; e na indústria química, com coeficiente de variação abaixo de 3%. Através das simulações, verificou-se que seu uso não é conveniente em áreas de pesquisa, cujo coeficiente de variação seja superior a 6%, quando se buscam estimativas de resposta e dos pontos ótimos e também em pesquisas de campo, como na Agronomia, mesmo quando se repetem todos os tratamentos, pois se observam muitas respostas e pontos bem longe do esperado

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

  1. Independencia del Banco Central y estabilidad de precios

    OpenAIRE

    Perez, Fernando; Quispe, Zenon; Rodriguez, Donita

    2007-01-01

    Este artículo analiza uno de los elementos fundamentales de las reformas de las autoridades monetarias, la independencia del banco central, concepto trascendental en el objetivo de mantener la estabilidad de precios.

  2. Development of a severe accident module of a nuclear power plant based in the MELCOR nuclear code and its incorporation to the room simulator; Desarrollo del modulo de accidentes severos de una central nucleoelectrica basado en el codigo nuclear MELCOR y su incorporacion al simulador de aula

    Energy Technology Data Exchange (ETDEWEB)

    Cortes M, F.S.; Ramos P, J.C.; Nelson E, P.; Chavez M, C. [Facultad de Ingenieria, Division de Ingenieria Electrica, Grupo de Ingenieria Nuclear, UNAM, Ciudad Universitaria, Distrito Federal (Mexico)]. E-mail: samuelcortes@correo.unam.mx

    2004-07-01

    This work describes the development of the Severe Accidents Module (MAS) based on the Code MELCOR and its incorporation to the Simulator of Classroom of the Group of Nuclear Engineering of the Engineering Faculty (GrINFI) of the National Autonomous University of Mexico (UNAM). The module of Severe Accidents has the purpose of counting with installed and operational capacity for the simulation of accident sequences with capacitation purposes, training, analysis and design. A shallow description of SimAula is presented, and the philosophy used to obtain the interactive version of MELCOR are discussed, as well as its implementation in the atmosphere of SimAula. Finally, after confirming the correct operation of the development of the tool, some possible topics are discussed for specific applications of the MAS. (Author)

  3. Las conflictivas fronteras de Asia Central

    OpenAIRE

    Stanganelli, Isabel Cecilia

    2002-01-01

    Si bien el gran juego político del siglo XIX definió la frontera entre Rusia y Afganistán mediante un tratado firmado por Rusia y el Reino Unido, la vasta región que hoy constituyen las cinco restantes repúblicas de Asia Central fue incorporada a Rusia zarista en sucesivas etapas y en el período soviético dotada por Moscú de límites con funciones puramente administrativas. La sorpresiva independencia de las repúblicas en diciembre de 1991 transformó a esos límites en internacionales. Lejos...

  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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-07-01

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

  6. 75 FR 9576 - Civil Nuclear Policy Mission to Central and Eastern Europe

    Science.gov (United States)

    2010-03-03

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-07-01

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

  9. Study of the reliability of the Auxiliary Feedwater System of a LWR nuclear power plant through the Fault Tree and Bayesian Network; Estudo de confiabilidade do Sistema Auxiliar de Agua de Alimentacao de uma central nuclear a agua leve por arvore de falhas e rede Bayesiana

    Energy Technology Data Exchange (ETDEWEB)

    Lava, Deise Diana

    2016-10-01

    This paper aims to present a study of the reliability of the Auxiliary Feedwater System (AFWS) through the methods of Fault Tree and Bayesian Network. Therefore, the paper consists of a literature review of the history of nuclear energy and the methodologies used. The AFWS is responsible for providing water system to cool the secondary circuit of nuclear reactors of the PWR type when normal feeding water system failure. How this system operates only when the primary system fails, it is expected that the AFWS failure probability is very low. The AFWS failure probability is divided into two cases: the first is the probability of failure in the first eight hours of operation and the second is the probability of failure after eight hours of operation, considering that the system has not failed within the first eight hours. The calculation of the probability of failure of the second case was made through the use of Fault Tree and Bayesian Network, that it was constructed from the Fault Tree. The results of the failure probability obtained were very close, on the order of 10{sup -3}. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-01

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

  11. Quality studies of the energy in the electric net of the gathering warehouse of reusable parts and contaminate oils of the nuclear power plant Laguna Verde; Estudios de calidad de la energia en la red electrica del almacen de acopio de partes reusables y aceites contaminados (CCAC) de la Central Nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Vargas A, A.; Cardenas J, J., E-mail: francisco.tijerina@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Cardel-Nautla Km 42.5, Veracruz (Mexico)

    2012-10-15

    In the industry exist the high costs by faults of electronic and electric equipment s, due to during the design process, installation, tests and operation of these equipment s, is not had appropriate detection equipment to carry out quality studies of the energy. These studies give an important support to know that occurs in an electric net, the cause of the anomalous behavior of the equipment s and this way to avoid the expensive faults carrying out necessary engineering adaptations in an electric net. The elements of the electricity that are determined are the tension, current and frequency that are inside acceptable operational parameters that facilitate the operation and constant operation of the equipment s, free of interruptions and failures. The application of the quality studies of the energy is growing little by little in Mexico for the problems solution in the equipment s. This field is also developing new techniques and technologies integrated in the equipment s for its monitoring detection and protection. The present work offers the results of the first Quality Study of the Energy in the nuclear power plant of Laguna Verde to solve the problem in the gathering warehouse of reusable parts and contaminate oils, in which the failure of the two radiation monitors of the gassy effluent of ventilation HVAC of the warehouse took place. (Author)

  12. Evaluation of the transfer of {sup 3}H rain to fungi into two areas, near and far from the Almaraz Nuclear Power Plant; Evaluacion de la transferencia del {sup 3}H de la lluvia a los hongos en dos zonas, proxima y alejada de la central nuclear de Almaraz

    Energy Technology Data Exchange (ETDEWEB)

    Baeza, A.; Garcia, E.; Riesgo, R.; Rodriguez, A.; Guillen, J.

    2013-07-01

    The main objective of this work has been to study for two years the incorporation of 3H atmospheric from rainwater to several species of fungi collected in two ecosystems, one in the vicinity of the Almaraz Nuclear Power Plant and one away from it. (Author)

  13. Significados de las medidas de tendencia central : un estudio con alumnos universitarios de carreras de humanidades.

    OpenAIRE

    Sayritupac Gutierrez, Javier

    2013-01-01

    En el presente trabajo de investigación se analiza los significados personales e institucionales de las medidas de tendencia central en un estudio con alumnos de primeros ciclos de las carreras de humanidades de la Pontificia Universidad Católica del Perú. Para realizar este análisis se consideró como marco teórico el Enfoque Ontosemiótico de la Cognición e Instrucción Matemática (EOS), el cual nos brindó las herramientas necesarias para el análisis de nuestro objeto de estu...

  14. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states; Rapport sur le controle de la surete et de la securite des installations nucleaires. Deuxieme partie: la reconversion des stocks de plutonium militaire. L'utilisation des aides accordees aux pays d'Europe centrale et orientale et aux nouveaux etats independants

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2002-07-01

    This report deals with two different aspects of the safety and security of nuclear facilities. The first aspect concerns the reconversion of weapon grade plutonium stocks: the plutonium in excess, plutonium hazards and nuclear fuel potentialities, the US program, the Russian program, the actions of European countries (France, Germany), the intervention of other countries, the unanswered questions (political aspects, uncertainties), the solutions of the future (improvement of reactors, the helium-cooled high temperature reactor technology (gas-turbine modular helium reactor: GT-MHR), the Carlo Rubbia's project). The second aspect concerns the actions carried out by the European Union in favor of the civil nuclear facilities of central and eastern Europe: the European Union competencies through the Euratom treaty, the conclusions of the European audit office about the PHARE and TACIS nuclear programs, the status of committed actions, the coming planned actions, and the critical analysis of the policy adopted so far. (J.S.)

  15. Calculation of the pipes failure probability of the Rcic system of a nuclear power station by means of software WinPRAISE 07; Calculo de la probabilidad de falla de tuberias del sistema RCIC de una central nuclear mediante el software WinPRAISE 07

    Energy Technology Data Exchange (ETDEWEB)

    Jasso G, J.; Diaz S, A.; Mendoza G, G.; Sainz M, E. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Garcia de la C, F. M., E-mail: angeles.diaz@inin.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km 44.5 Carretera Cardel-Nautla, 91476 Laguna Verde, Alto Lucero, Veracruz (Mexico)

    2014-10-15

    The growth and the cracks propagation by fatigue are a typical degradation mechanism that is presented in the nuclear industry as in the conventional industry; the unstable propagation of a crack can cause the catastrophic failure of a metallic component even with high ductility; for this reason, activities of programmed maintenance have been established in the industry using inspection and visual techniques and/or ultrasound with an established periodicity allowing to follow up to these growths, controlling the undesirable effects; however, these activities increase the operation costs; and in the peculiar case of the nuclear industry, they increase the radiation exposure to the participant personnel. The use of mathematical processes that integrate concepts of uncertainty, material properties and the probability associated to the inspection results, has been constituted as a powerful tool of evaluation of the component reliability, reducing costs and exposure levels. In this work the evaluation of the failure probability by cracks growth preexisting by fatigue is presented, in pipes of a Reactor Core Isolation Cooling system (Rcic) in a nuclear power station. The software WinPRAISE 07 (Piping Reliability Analysis Including Seismic Events) was used supported in the probabilistic fracture mechanics principles. The obtained values of failure probability evidenced a good behavior of the analyzed pipes with a maximum order of 1.0 E-6, therefore is concluded that the performance of the lines of these pipes is reliable even extrapolating the calculations at 10, 20, 30 and 40 years of service. (Author)

  16. Collective phenomena in non-central nuclear collisions

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-10-20

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

  17. Themes in nuclear law; Temas de Derecho Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    The nuclear law was analyzed during a workshop. The main aspects were: the law of population to access to information on nuclear energy and the relationship between the Regulator Organism and the nuclear power plants managers.

  18. Reactivity follow of the two first loadings of the Jose Cabrera Reactor; Seguimiento de la ractividad durante las dos primeras cargas del Reactor de la Central Nuclear Jose Cabrera

    Energy Technology Data Exchange (ETDEWEB)

    Bru, A.

    1975-07-01

    In this paper the first two cores together with the in-core measurements taken during the operation of the Nuclear Power Station Jose Cabrera are described. The results of this measurements have been processed with the INCORE and FOLLOW codes. The peaking factors and the boron concentration versus burn-up are displayed. The final burn-up of the fuel elements in these two loading are given, too. (Author)

  19. Decision no. 2011-DC-0219 of the French nuclear safety authority from May 5, 2011, ordering the SOCATRI company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0219 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a SOCATRI de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the SOCATRI company, operator of the nuclear dismantling and waste processing plants of the Tricastin site (France). (J.S.)

  20. New application computer control comprehensive radiological and dosimetry of the Cofrentes nuclear power station and its integration with environment of photo realism; Nueva aplicacion informatica de control integral radiologico y dosimetrico de la central nuclear de Cofrentes y su integracion con entorno de fotorealismo

    Energy Technology Data Exchange (ETDEWEB)

    Fragio, R.; Garcia Vidal, P.; Sollet, E.; Campos, J. J. de; Martinez Avila, M.; Llana, S. de la

    2013-09-01

    At the beginning of 2012, a new integrated information system (AGER) replaced the former software applications that supported the radiation protection service (RPS) in Cofrentes Nuclear Plant. After a deep analysis coordinated by the RPS, the Cofrentes systems IT unit and Everis company, a software solution was designed and developed using the latest IT technologies in order to increase reliability, security, scalability and usability. Furthermore, the system provides new functions that covered recently imposed requirements by official organisms and also many improvements required by the RPS in order to better monitor the individual and collective doses: ALARA Jobs management, alarms for radiation dose accumulations, monitoring of dose estimates in RWPs, integration with a photo realistic model of plant, etc. (Author)

  1. Analysis of the emergency plan of Angra dos Reis Nuclear Power Plants: a critical view related to accessibility and mobility of people with special needs; Analise do plano de emergencia da Central Nuclear de Angra dos Reis: uma visao critica com relacao a acessibilidade e mobilidade de pessoas com necessidades especiais

    Energy Technology Data Exchange (ETDEWEB)

    Correa, Luanda C.A., E-mail: luanda.correa@yahoo.com.br [Universidade Candido Mendes, Rio de Janeiro, RJ (Brazil); Correa, Samanda C.A., E-mail: scorrea@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Santos, Geissa; Souza, Edmilson M., E-mail: edmilsonsouza@uezo.rj.gov.br, E-mail: geissasantosnaval@gmail.com [Universidade Estadual da Zona Oeste (UEZO), Rio de Janeiro, RJ (Brazil)

    2014-07-01

    This work intends to make a critical analysis of the emergency plan of the Angra dos Reis Nuclear Power Plants related to appropriate transportation, accommodation and infrastructure for people with special needs.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  3. Análisis de accidentes severos en contenciones nucleares

    Directory of Open Access Journals (Sweden)

    Goicolea Ruigómez, José María

    1992-04-01

    Full Text Available Analysis for severe accidents has recently been added to the long list of requisites imposed on nuclear power plants. In this work we study the rationale and justiflcation for this type of analysis. Calculations for the structural response of the containment buildings can be performed on the computer using advanced nonlinear Finite Element codes. A state of the art review of these methods is carried out, proposing a methodology based on analysis by numerical methods with experimental validation. Additionally we present some results obtained by the authors for the analysis of both reinforced concrete and steel containments. The concluding remarks show the validity of the proposed methodology, as well as the evidence of a large security margin in the containments, due mainly to the conservatisms in the design stage.

    El análisis frente a accidentes severos ha venido a añadirse recientemente a la larga lista de requisitos impuestos a las centrales nucleares. En este trabajo se pretende estudiar la problemática y justificación de este tipo de análisis. El cálculo de la respuesta de la contención se puede realizar en el ordenador mediante métodos avanzados de elementos finitos no lineales. Se hace una revisión del estado de la técnica en estos métodos, proponiendo una metodología basada en el análisis mediante modelos numéricos con validación experimental. Se presentan asimismo los resultados de análisis realizados, para contenciones tanto de hormigón armado como metálicas. Las conclusiones del trabajo establecen la validez de la metodología empleada, así como la constatación de un amplio margen de seguridad existente en las contenciones evaluadas, debido a los conservadurismos del proceso de diseño original.

  4. Development of an interactive model of the Laguna Verde nuclear power plant based on the RELAP/SCDAP code; Desarrollo del modelo interactivo de la central nucleoelectrica de Laguna Verde basado en el codigo RELAP/SCDAP

    Energy Technology Data Exchange (ETDEWEB)

    Salazar C, J.H.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [LAIRN, FI-UNAM, DEPFI Campus Morelos, Jiutepec, Morelos (Mexico)]. e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    The present work describes the development of an interactive model of the Nuclear power plant of Laguna Verde (CNLV) based on the RELAP/SCDAP nuclear code, and it incorporation to a classroom simulator. The functional prototype it allows to make evaluations for operational transients and postulates accidents, with capacitation purposes, training, analysis and design. It emphasizes on the methodology used to establish the inter activity. Such methodology, is based on a modular structure in the one that multiple processes can be executed in an independent way and where the generated information is stored in segments of shared memory (characteristic that allows the UNIX operating system) and sent to the different processes by means of communication routines developed in C programming language. The utility of the system is demonstrated by means of the use of interactive display graphics (mimic diagrams, pictorials and tendency graphics) for the simultaneous dynamic visualization of the variables more significant that involve to the pattern of a transitory event type (for example failure of the controller of feeding water in a BWR reactor). Near with the interactive module, it was developed a model of the reactor of the CNLV for the code of better estimation RELAP/SCDAP. Finally the evaluation of the model is described, where it is interpreted in general form the behavior of those main variables that describe the stationary state, corroborating that follow the same tendency that those reported in the FSAR (Final Safety Analysis Report) of the Laguna Verde plant. The obtained results allow to conclude that the made development was satisfactory and that it presents enormous advantages regarding the capacity and time of analysis when using tools of visualization in real time of execution. (Author)

  5. Decision no. 2011-DC-0222 of the French nuclear safety authority from May 5, 2011, ordering the Comurhex company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0222 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a Comurhex de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to Comurhex company, operator of the Tricastin uranium conversion plant (France). (J.S.)

  6. Decision no. 2011-DC-0218 of the French nuclear safety authority from May 5, 2011, ordering the EURODIF SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0218 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a EURODIF SA de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the EURODIF SA company, operator of the George Besse I uranium enrichment plant of the Tricastin site (France). (J.S.)

  7. Decision no. 2011-DC-0224 of the French nuclear safety authority from May 5, 2011, ordering the French atomic energy and alternative energies commission (CEA) to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0224 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant au Commissariat a l'Energie Atomique et aux energies alternatives (CEA) de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the French atomic energy commission (CEA). (J.S.)

  8. Decision no. 2011-DC-0221 of the French nuclear safety authority from May 5, 2011, ordering the SET company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0221 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a la SET de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the SET company, operator of the Georges Besse II and RECII uranium enrichment plants of the Tricastin site (France). (J.S.)

  9. Decision no. 2011-DC-0217 of the French nuclear safety authority from May 5, 2011, ordering the AREVA NC group to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0217 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a AREVA NC de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the AREVA NC group. (J.S.)

  10. Decision no. 2011-DC-0223 of the French nuclear safety authority from May 5, 2011, ordering the MELOX SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0223 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a MELOX SA de proceder a une evaluation complementaire de la surete de certaines de ses installations nucleaires de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to MELOX SA company, operator of the Melox MOX fuel fabrication plant of Marcoule (France). (J.S.)

  11. Evaluation of radwaste minimization program of dry and wet active waste in the Laguna Verde Nuclear Power Plant; Evolucion del programa de minimizacion de desechos solidos secos y humedos en la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Luna-Garza, Hector [Comision Federal de Electricidad, Veracruz (Mexico). Central Nucleoeletrica Laguna Verde; Zarate-Montoya, Norma [Instituto Nacional de Investigaciones Nucleares, Veracruz (Mexico)

    2001-07-01

    A growing rate of radwaste volume production combined with an increase of both, costs and associated dose involved in its treatment and disposition processes have created a serious problem to the Laguna Verde Nuclear Power Plant (BWR, two Units, 682 Mwe each) in Mexico. Due the lack of a Final Repository in the country, the solution in the short or long terms relies on the success of a continuous and aggressive minimization program mainly based on modifications and upgrades applied to these processes. Technical and administrative strategies adopted by LVNPP for the reduction of Liquid Effluents and Dry and Wet Active Waste in the next three years are described. Based on the results of the LVNPP current radwaste process systems, an estimated accumulation of 11,502 m{sup 3} by the year 2035 will exceed the actual on-site storage capacity. If the strategies succeed, this production would fall to an expected manageable volume of 4067 m{sup 3}. (author)

  12. Management report 2003 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2003 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-15

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2003, involving the government programs in the areas of nuclear safety, medicine application, technological development, administration and miscellaneous.

  13. Modeling of delayed strains of concrete under biaxial loadings. Application to the reactor containment of nuclear power plants; Modelisation des deformations differees du beton sous sollicitations biaxiales. application aux enceintes de confinement de batiments reacteurs des centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Benboudjema, F

    2002-12-15

    The prediction of delayed strains is of crucial importance for durability and long-term serviceability of concrete structures (bridges, containment vessels of nuclear power plants, etc.). Indeed, creep and shrinkage cause cracking, losses of pre-stress and redistribution of stresses, and also, rarely, the ruin of the structure. The objective of this work is to develop numerical tools, able to predict the long-term behavior of concrete structures. Thus, a new hydro mechanical model is developed, including the description of drying, shrinkage, creep and cracking phenomena for concrete as a non-saturated porous medium. The modeling of drying shrinkage is based on an unified approach of creep and shrinkage. Basic and drying creep models are based on relevant chemo-physical mechanisms, which occur at different scales of the cement paste. The basic creep is explicitly related to the micro-diffusion of the adsorbed water between inter-hydrates and intra-hydrates and the capillary pores, and the sliding of the C-S-H gel at the nano-porosity level. The drying creep is induced by the micro-diffusion of the adsorbed water at different scales of the porosity, under the simultaneous effects of drying and mechanical loadings. Drying shrinkage is, therefore, assumed to result from the elastic and delayed response of the solid skeleton, submitted to both capillary and disjoining pressures. Furthermore, the cracking behavior of concrete is described by an orthotropic elastoplastic damage model. The coupling between all these phenomena is performed by using effective stresses which account for both external applied stresses and pore pressures. This model has been incorporated into a finite element code. The analysis of the long-term behavior is also performed on concrete specimens and prestressed concrete structures submitted to simultaneous drying and mechanical loadings. (author)

  14. Plan empresa productora de audiovisuales : La Central Audiovisual y Publicidad

    OpenAIRE

    Arroyave Velasquez, Alejandro

    2015-01-01

    El presente documento corresponde al plan de creación de empresa La Central Publicidad y Audiovisual, una empresa dedicada a la pre-producción, producción y post-producción de material de tipo audiovisual. La empresa estará ubicada en la ciudad de Cali y tiene como mercado objetivo atender los diferentes tipos de empresas de la ciudad, entre las cuales se encuentran las pequeñas, medianas y grandes empresas.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-06-15

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

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

    Directory of Open Access Journals (Sweden)

    Ying Yuan

    2014-01-01

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

  17. Detection of nuclear radiations; Deteccion de Radiaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Tanarro Sanz, A.

    1967-07-01

    A summary of the lectures about the ordinary detectors of nuclear radiations explained by the author in the courses of Nuclear Engineering held at the J.E.N. up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied Electronics to Nuclear Engineering so it has been intended to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author)

  18. Detection of nuclear radiations; Detectores de radiaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Tanarro Sanz, A.

    1959-07-01

    A summary of the lectures about the ordinary detectors of nuclear radiations given by the author in the Courses of Introduction to Nuclear Engineering held at the JEN up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied electronics to Nuclear Engineering so it has been intent to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author) 8 refs.

  19. Decision no. 2011-DC-0214 of the French nuclear safety authority from May 5, 2011, ordering CIS bio international company to proceed to a complementary safety evaluation of its basic nuclear facility in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0214 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a CIS bio international de proceder a une evaluation complementaire de la surete de son installation nucleaire de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to CIS bio international company, operator of the radiopharmaceuticals fabrication facility (INB 29) of Saclay (France). (J.S.)

  20. Decision no. 2011-DC-0215 of the French nuclear safety authority from May 5, 2011, ordering ITER Organization to proceed to a complementary safety evaluation of its basic nuclear facility in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0215 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a ITER ORGANIZATION de proceder a une evaluation complementaire de la surete de son installation nucleaire de base au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the ITER Organization, operator of the ITER tokamak facility of Cadarache (France). (J.S.)

  1. Decision no. 2011-DC-0216 of the French nuclear safety authority from May 5, 2011, ordering the Laue Langevin Institute to proceed to a complementary safety evaluation of its basic nuclear facility (high flux reactor - INB no. 67) in the eyes of the Fukushima Daiichi nuclear power plant accident; Decision no. 2011-DC-0216 de l'Autorite de surete nucleaire du 5 mai 2011 prescrivant a l'Institut Laue Langevin (ILL) de proceder a une evaluation complementaire de la surete de son installation nucleaire de base (Reacteur a Haut Flux - INB n.67) au regard de l'accident survenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the Laue Langevin Institute, operator of the high flux research reactor (RHF) of Grenoble (France). (J.S.)

  2. Centrality and multiparticle production in ultrarelativistic nuclear collisions

    Science.gov (United States)

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

    2016-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-15

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

  6. Analisis de la microbiota en suelos cultivados del Altiplano central

    OpenAIRE

    Sivila, R.; Hervé, Dominique

    2001-01-01

    Se estudio la poblacion microbina en una rotacion de cultivos con descanso, comun en el Altiplano Central boliviano. Se determino la presencia y densidad de cuatro grupos taxonomicos de microorganismos: bacterias; hongos, actinomicetos y esporas de las micorrizas arbusculares en el suelo rizosferico de cuatro cultivos de la rotacion (papa, quinua, cebada y avena); en las principales especies silvestres perennes (#Stipa ichu, Festuca dolichophylla, Baccharis incarum$) que colonizan las parcela...

  7. Management report 2004 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2004 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2004, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  8. Management report 2006 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2006 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  9. Management report 2005 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2005 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

    This document reports the results of the activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2005, involving the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, institutional management, teaching, administration in general and miscellaneous.

  10. Management report 2007 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2007 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2007, involving the CNEN role in the public policy execution, the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, teaching, administration in general and miscellaneous.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-12-15

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

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

    Institute of Scientific and Technical Information of China (English)

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

    2002-01-01

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

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

    CERN Document Server

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

    2007-01-01

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

  14. Dynamic analysis of the condensate and of the feed water in the Laguna Verde nuclear power station; Analisis dinamico del sistema de condensado y agua de alimentacion de la nucleoelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Macedo Muth, Javier; Sandoval Pena, Ramon [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1988-12-31

    This article shows a non-lineal mathematical model for the condensate, and feed water systems and for feed water heater drains at the Laguna Verde Nuclear Power Station for its simulation in real time. The model allows the calculation of flows and pressures in all the piping system and equipment that integrate the systems. It was obtained by using the force unbalance in the fluid concept and is capable of reproducing its dynamic behavior through variations induced by the different operation modes and more common failures. The final model objective is to form part of the Laguna Verde simulator that will be used for operator training of this Nuclear Power Plant. [Espanol] En este articulo se muestra un modelo matematico no lineal de los sistemas de condensado, agua de alimentacion y drenes de calentadores de la central nuclear de Laguna Verde para su simulacion en tiempo real. El modelo permite calcular los flujos y las presiones en toda la red de tuberias y equipos que integran los sistemas. Se obtuvo utilizando el concepto de desbalance de fuerzas en el fluido, y es capaz de reproducir su comportamiento dinamico ante variaciones inducidas por los diversos modos de operacion y fallas mas comunes. El objetivo final del modelo es formar parte del simulador de Laguna Verde que se empleara para el adiestramiento de los operadores de dicha central nuclear.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-01-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

  17. Closure simulation of the MSIV of Unit 1 of the Laguna Verde nuclear power plant using the Simulate 3K code; Simulacion del cierre de las MSIV de la Unidad 1 de la central nuclear Laguna Verde empleando el codigo Simulate-3K

    Energy Technology Data Exchange (ETDEWEB)

    Alegria A, A., E-mail: aalegria@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2015-09-15

    In this paper the simulation of closure transient of all main steam isolation valves (MSIV) was performed with the Simulate-3K (S-3K) code for the Unit 1 of the Laguna Verde nuclear power plant (NPP-LV), which operates to thermal power of 2317 MWt, corresponding to the cycle 15 of operation. The set points for the performance of systems correspond to those set out in transient analysis: 3 seconds for the closure of all MSIV; the start of Scram when 121% of the neutron flux is reached, respect from baseline before the transient; the opening by peer of safety relief valves (SRV) in relief mode when the set point of the pressure is reached, the shoot of the feedwater flow seconds after the start of closing of the MSIV and the shoot of the recirculation water pumps when the pressure is reached in the dome of 1048 psig. The simulation time was of 57 seconds, with the top 50 to reach the steady state, from which the closure of all MSIV starts. In this paper the behavior of the pressure in the dome are analyzed, thermal power, neutron flux, the collapsed water level, the flow at the entrance of core, the steam flow coming out of vessel and the flow through of the SRV; the fuel temperature, the minimal critical power ratio, the readings in the instrumentation systems and reactivities. Instrumentation systems were implemented to analyze the neutron flux, these consist of 96 local power range monitors (LPRM) located in different radial and axial positions of the core and 4 channels of average power range monitors, which grouped at 24 LPRM each one. LPRM response to the change of neutron flux in the center of the core, at different axial positions is also shown. Finally, the results show that the safety limit MCPR is not exceeded. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  20. Expectativas desagregadas, credibilidade do Banco Central e Cadeias de Markov

    Directory of Open Access Journals (Sweden)

    Diogo Guillén

    2014-06-01

    Full Text Available Propomos e implementamos uma medida da credibilidade do Banco Central do Brasil, fazendo uso de uma base de dados com expectativas desagregadas. A hipótese é de que a heterogeneidade das expectativas de longo prazo advenha de crenças distintas com relação à aversão do Banco Central à inflação. Desse modo, a existência de agentes persistentemente otimistas ou pessimistas indicaria falta de credibilidade. Com base neste argumento, construímos um índice utilizando Cadeias de Markov. Nosso índice inova em relação aos disponíveis na literatura por considerar a dispersão das expectativas. Nossos resultados são comparados com os de outros artigos, corroborando o aprimoramento advindo da nova medida da credibilidade.

  1. Electronic detection of nuclear radiations; Deteccion Electronica de radiaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Campos, J.

    1972-07-01

    This report is the first draft of one of the chapters of a book being prepared under the title: Topics on Practical Nuclear Physics. It is published as a report because of i ts immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  2. The probabilities of nuclear processes; Probabilidades de los procesos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez del Rio, C.

    1972-07-01

    This report is the first draft of one of the chapters of a book being prepared under the title: Topics on Practical Nuclear Physics. It is published as a report because of its immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  3. Emission of {sup 14}C by the Almirante Alvaro Alberto Nuclear Power Plant 1 and 2 and their local effects on the environmental levels; Emissao de {sup 14}C pelas unidades 1 e 2 da Central Nuclear Almirante Alvaro Alberto (CNAAA) e seu efeito local nos niveis ambientais

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Cintia Melazo

    2006-07-01

    {sup 14}C is a is a long-lived beta-emitting nuclide (T{sub 1/2} = 5730 years) produced naturally in the upper atmosphere as a result of reactions between neutrons and stable {sup 14}N({sup 14}N(n,p){sup 14}C). Although in a lesser extent, nuclear power plants produce {sup 14}C as well during their routine operation. Since it is converted in {sup 14}CO{sub 2} and mixed throughout the atmosphere, it is incorporated into plant tissues, via photosynthesis process, and hence in food chain. Because of the biological importance of {sup 14}C and long half-life, it is of interest to quantify the amounts released by nuclear industry. The Brazilian nuclear central named Nuclear Central Admiral Alvaro Alberto (CNAAA) has two nuclear reactors of PWR type in operation, Angra I (657 MWe) and Angra II (1350 MWe), and one under construction, Angra III (1309 MWe PWR). The aim of this study was to determine the strength of the sources and the {sup 14}C content in the environment through analyses of air, vegetation and soils taken within 5 km (the influenced area) of CNAAA. The thesis consists of an extensive review about the subject (part one) and of four papers (part two). The first paper is about the determination of {sup 14}C concentrations released by reactors (source strength). For Angra I, a device was developed in order to sample the gaseous effluents and for Angra II, a commercial monitoring system had already been implemented since its initial operation (2001). The {sup 14}C can be emitted as hydrocarbons, CO or CO{sub 2}, depending on the type of reactor. For PWRs, the main chemical form released is hydrocarbons (80 %). The monitoring system of Angra I was planned to determine both CO{sub 2} and hydrocarbon fractions but in Angra II, all hydrocarbons are converted to CO{sub 2} by using a Pd/Al{sub 2}O{sub 3} catalyst at 450 deg C. The liquid scintillation was the method employed to measure the samples. The second one concerns the atmospheric dispersion of the released

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

    OpenAIRE

    Igor Sokolov; David Kavanaugh

    2014-01-01

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

  5. Implementation of the outcome of the PRISME project on spread of smoke and heat during a fire at the licensing in nuclear power plants; Aplicacion de los resultados del proyecto PRISME sobre propagacion de humos y calor durante un incendio al licenciamiento en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Cordero Garcia, S.; Jimenez Garcia, M. a.; Peco Espinosa, J.

    2013-07-01

    The Spanish regulator (CSN) has actively participated the OECD/NEA PRISME project, whose main objectives and results are summarised in next sections. The project aims at addressing the most relevant aspects related to fire propagation phenomena within multi-compartment geometries, representative of actual configurations present in nuclear facilities, thereby providing an extensive basis for code validation to aid in fire risk analyses.

  6. Problemas centrales del análisis de datos cualitativos

    Directory of Open Access Journals (Sweden)

    Julio Mejía Navarrete

    2011-04-01

    Full Text Available El trabajo examina las operaciones prácticas y las decisiones concretas que enfrenta el trabajo de investigación cualitativa en la etapa del análisis de datos. Interesa subrayar los aspectos centrales del análisis de datos cualitativos que posibiliten abrir una discusión en la investigación metodológica de América Latina

  7. Understanding the corrosion phenomena to organize the nondestructive evaluation programs in the nuclear power plants; Connaitre les phenomenes de corrosion pour organiser les programmes d'end dans les centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Berge, J.Ph. [Federation Europeenne de Corrosion, 75 - Paris (France); Samman, J. [Electricite de France (EDF), Div. du Production Nucleaire, 75 - Paris (France)

    2001-07-01

    The french nuclear power plants used PWR which components revealed many corrosion defects of different shapes as stress corrosion cracks or pits. Understanding the corrosion processes will help the inspection of in service power plants. The following examples describe some corrosion cases and present the corresponding developed control methods: corrosion on condenser, secondary circuit pipes and corrosion-erosion, steam generator pipes, vessels head penetration. (A.L.B.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-01-22

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

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

    Science.gov (United States)

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

    2016-01-01

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

  10. El efecto de los neutrinos degenerados en la transición de materia nuclear a materia de quarks

    Science.gov (United States)

    Lugones, G.; Benvenuto, O. G.

    Se estudia la transicion de materia nuclear a materia de quarks en presencia de un gas degenerado de neutrinos electrónicos y muónicos. Se muestra que la presencia de los neutrinos hace que las densidades de desconfinamiento de quarks sean notablemente mayores que las encontradas en el caso en que no haya neutrinos presentes. Se discuten las posibles consecuencias de este efecto en explosiones de supernova y evolución de proto estrellas de neutrones.

  11. Riesgos ocupacionales en la central de esterilización

    Directory of Open Access Journals (Sweden)

    Martínez de Acosta Carmen

    1992-06-01

    Full Text Available

    Las centrales de esterilización constituyen áreas y unidades operativas dentro del sistema hospitalario. Su objetivo es ofrecer a cada individuo atendido un medio ambiente seguro e instrumentos y materiales estériles que garanticen el control de la infección, además de ofrecer a sus trabajadores óptimas condiciones para la promoción de la salud y la prevención de lesiones temporales o permanentes. Los avances tecnológicos en los procesos de esterilización y por ende la utilización de nuevas técnicas, equipos y procedimientos ha cambiado el tradicional ambiente ''seguro'' de estas unidades, por situaciones de trabajo que generan riesgos de diversa índole.

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

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

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

  13. Caracterizaci??n de la rabia en el departamento central de Paraguay

    OpenAIRE

    1999-01-01

    Se brinda una visi??n de la problem??tica de la rabia de tipo urbano en el departamento Central, que es la predominante en esta regi??n del pa??s. Con este objetivo, son analizados los diagn??sticos laboratoriales en base a una muestra aleatoria, y otra muestra de las fichas de atenci??n a personas v??ctimas de agresiones producidas por animales en el departamento Central de Paraguay, entre los a??os 1992-1997. Es presentado adem??s el n??mero de casos de rabia humana entre 1992-1997, y algun...

  14. Centrales térmicas a pie de mina

    Directory of Open Access Journals (Sweden)

    Seshadri, B.

    1961-10-01

    Full Text Available Ligera descripción de la gran cuenca hullera de carbón pardo, de Victoria (Australia. Esta inmensa cuenca carbonífera está situada a unos 150 km de Melbourne, estado de Victoria, y en la región denominada el Valle del río Latrobe. Se cree que esta cuenca es la mayor del mundo en su género. Estos yacimientos se extienden en una longitud de unos 65 km y una anchura que varía de 8 a 16 km. En un cierto lugar de esta zona, y a unos 27 m de profundidad, se ha perforado una capa de unos 330 m de potencia, lo que, innegablemente, hace de ella la mayor del mundo. Al crearse en 1919 la Comisión Nacional de Electricidad, se previó la construcción de la primera Central a pie de mina para el año 1923, con una capacidad inicial de 50.000 kW de potencia.

  15. Generation of nuclear data bank by interpolation; Generacion de bancos de datos nucleares mediante interpolacion

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    Nuclear Data Bank generation, is a process in which a great amount of resources is required, both computing and humans. If it is taken into account that at some times it is necessary to create a great amount of those, it is convenient to have a reliable tool that generates Data Banks with the lesse resources, in the least possible time and with a very good approximation. In this work are shown the results obtained during the development of INTPOLBI code, used to generate Nuclear Data Banks employing bi-cubic polynomial interpolation, takings as independent variables the uranium and gadolinia percents. Two proposal were worked, applying in both cases the finite element methods, using one element with 16 nodes to carry out the interpolation. In the first proposal the canonic base was employed to obtain the interpolating polynomial and later, the corresponding linear equations systems. In the solution of this system the Gaussian elimination methods with partial pivot was applied. In the second case, the Newton base was used to obtain the mentioned system, resulting in a triangular inferior matrix, which structure, applying elemental operations, to obtain a blocks diagonal matrix, with special characteristics and easier to work with. For the validations test, a comparison was made between the values obtained with INTPOLBI and INTERTEG (created at the Instituto de Investigaciones Electricas with the same purpose) codes, and Data Banks created through the conventional process, with nuclear code normally used. Finally, it is possible to conclude that the Nuclear Data Banks generated with INTPOLBI code constitute a very good approximation that, even though do not wholly replace conventional process, however are helpful in cases when it is necessary to create a great amount of Data Banks.

  16. Nuclear data banks generation by interpolation; Generacion de bancos de datos nucleares mediante interpolacion

    Energy Technology Data Exchange (ETDEWEB)

    Castillo M, J. A

    1999-07-01

    Nuclear Data Bank generation, is a process in which a great amount of resources is required, both computing and humans. If it is taken into account that at some times it is necessary to create a great amount of those, it is convenient to have a reliable tool that generates Data Banks with the lesser resources, in the least possible time and with a very good approximation. In this work are shown the results obtained during the development of INTPOLBI code, use to generate Nuclear Data Banks employing bicubic polynominal interpolation, taking as independent variables the uranium and gadolinia percents. Two proposal were worked, applying in both cases the finite element method, using one element with 16 nodes to carry out the interpolation. In the first proposals the canonic base was employed, to obtain the interpolating polynomial and later, the corresponding linear equation systems. In the solution of this systems the Gaussian elimination methods with partial pivot was applied. In the second case, the Newton base was used to obtain the mentioned system, resulting in a triangular inferior matrix, which structure, applying elemental operations, to obtain a blocks diagonal matrix, with special characteristics and easier to work with. For the validation tests, a comparison was made between the values obtained with INTPOLBI and INTERTEG (create at the Instituto de Investigaciones Electricas (MX) with the same purpose) codes, and Data Banks created through the conventional process, that is, with nuclear codes normally used. Finally, it is possible to conclude that the Nuclear Data Banks generated with INTPOLBI code constitute a very good approximation that, even though do not wholly replace conventional process, however are helpful in cases when it is necessary to create a great amount of Data Banks.

  17. Granuloma central de células gigantes

    OpenAIRE

    Cava-Vergiú, Carlos-Enrique; Flores Cueto, Walter; Cáceres La Torre, Andreé

    2006-01-01

    Este artículo presenta el caso de una paciente que acudió a la Clínica Especializada en Odontología de la Universidad de San Martín de Porres. La paciente requería la exodoncia de las terceras molares inferiores. Mediante el examen radiológico se observó una imagen radiolúcida con bordes definidos a nivel apical de las piezas 4.7 y 4.8. El diagnóstico presuntivo planteado fue granuloma central de células gigantes. La presentación de esta lesión es muy rara y puede ser de crecimiento ...

  18. Results of the benchmarking in radiological protection practices during fuel reloads in the nuclear power plants of Limerick (BWR) and Ginna (PWR) in the United States of North America; Resultados del benchmarking en practicas de proteccion radiologica durante recargas de combustible en las centrales nucleoelectricas de Limerick (BWR) y Ginna (PWR) en los Estados Unidos de Norteamerica

    Energy Technology Data Exchange (ETDEWEB)

    Lara H, M. A., E-mail: marco.lara@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

    2011-11-15

    The nuclear power plant of Laguna Verde, unique in our country, has been imposed several goals related with the continuous improvement of their acting; increase in the quantity of continuous days for operation cycle, improvement in the chemical indexes of the reactor coolant, improvement in the indexes of nuclear security, improvement in the indicators of industrial security, improvement in the standards of radiological protection, etc.; in this last item is precisely where is necessary to search creative solutions to be able to maintain the collective doses of the personnel so low as reasonably it is possible (ALARA) especially due to the last projects of extension of useful life of the nuclear power plant (zinc injection, noble metals and hydrogen) and of power increment of the nuclear power plant of Laguna Verde, same that represent in the short period an increment of collective dose and of exposition levels (until 200%) in very specific points of the primary systems of the reactor. (Author)

  19. Mecanismos moleculares de la tolerancia central

    OpenAIRE

    2007-01-01

    Consultable des del TDX Títol obtingut de la portada digitalitzada Las especificidades del repertorio T se generan mediante la recombinación de segmentos génicos al azar por lo que un porcentaje de células son autoreactivas. La tolerancia del repertorio T hacia las moléculas propias se consigue en primera instancia mediante la selección tímica. El fenómeno de la expresión promiscua consiste en la expresión intratímica de autoantígenos periféricos propios de otros tejidos. Las células me...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-15

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

  1. The Fessenheim nuclear power plant, at the service of a safe, competitive and CO{sub 2}-free power generation in the heart of the Alsace region; La Centrale Nucleaire de Fessenheim, au service d'une production d'electricite sure, competitive et sans CO{sub 2}, au coeur de la region Alsace

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    In less than 20 years, Electricite de France (EDF) has built up a competitive park of 58 nuclear power plants, with no equivalent elsewhere, which represents an installed power of 63.1 GW (85% of EDF's power generation). Inside this nuclear park, the national power generation centre of Fessenheim comprises two production units of 900 MW each (1800 MW as a whole). The facility generated 8.7 billion kWh in 2009, i.e. 70% of the energy consumed in the Alsace region. This brochure presents the life of the power plant under various aspects: power generation, safety priority and culture, maintenance investments, respect of the environment, long-term fuel and wastes management, local economical involvement, transparency and public information, key figures and dates. (J.S.)

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

    Science.gov (United States)

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

    2011-12-01

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

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

    Science.gov (United States)

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

    2015-01-01

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

  4. Isolated Richter's syndrome in central nervous system: case report Sindrome de Richter isolada em sistema nervoso central: relato de caso

    Directory of Open Access Journals (Sweden)

    Lucilene S.R. Resende

    2005-06-01

    Full Text Available Diffuse large cell non Hodgkin's lymphoma associated with chronic lymphoid leukemia (CLL, or Richter's syndrome, is a rare and serious complication. Isolated Richter's syndrome in the central nervous system is very rare; only 12 cases have been reported. We describe a 74-year-old patient with diffuse large cell non Hodgkin's lymphoma in the right frontal region with the appearance of multiform glioblastoma.Linfoma não Hodgkin difuso de grandes células em paciente portador de leucemia linfóide crônica (LLC, ou síndrome de Richter, é complicação rara e grave nesta leucemia. Síndrome de Richter isolada no sistema nervoso central é muito rara, tendo sido encontrados apenas 12 casos descritos. Descrevemos paciente de 74 anos, que apresentou linfoma não Hodgkin difuso de grandes células em região frontal direita, simulando glioblastoma multiforme.

  5. Conformación y particularidades de un grupo de familias nucleares de la ciudad de Bogotá

    Directory of Open Access Journals (Sweden)

    Patricia Isabel Uribe Díaz

    2015-12-01

    Full Text Available El artículo presenta la conformación y las particularidades de un grupo de familias nucleares, como parte del abanico de la diversidad familiar en el contexto latinoamericano y colombiano. Haciendo uso de la metodología cualitativa se pretende entender los rasgos más significativos de este tipo de familias, las cuales continúan ocupando un lugar predominante en la sociedad colombiana. Hecho que muestra la necesidad de realizar una aproximación a sus realidades y dinámicas a partir de las propias experiencias de las familias.

  6. Integración de un centro de transformación de servicios auxiliares de turbinas en una central térmica

    OpenAIRE

    Maestro Juárez, Daniel

    2009-01-01

    La ampliación de la capacidad de generación de una central térmica mediante la integración de nuevas turbinas de gas lleva asociada la realización de múltiples proyectos interdisciplinares de menor entidad que el de la propia integración de las turbinas, que dan soporte al proyecto de ampliación de la central. Dentro de estos proyectos de menor entidad, el problema de garantizar el suministro eléctrico de los servicios auxiliares de las turbinas requiere de un estudio específico debido a su e...

  7. Aquatic macro algae of a region under Almirante Alvaro Alberto nuclear power plant influence. I. Spatial seasonal evaluation; Macroalgas marinhas da regiao sob influencia da Central Nuclear Almirante Alvaro Alberto (CNAAA), Saco de Piraquara de Fora, Angra dos Reis, RJ, Brasil. I. Avaliacao espaco-temporal

    Energy Technology Data Exchange (ETDEWEB)

    Pedrini, A.G. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)]|[Universidade Santa Ursula, Rio de Janeiro, RJ (Brazil). Centro de Ciencias Biologicas; Cassano, V.; Coelho, L.G.; Labronici, G.J. [Universidade do Estado, Rio de Janeiro, RJ (Brazil). Inst. de Biologia

    1994-12-31

    Marine macro algae from the area which is under in fluence of the heated and chlorate liquid effluent to the CNAAA were observed (1981-1983) at 3 collection points: Pingo Dagua, Velho Beach, discharge point. A total of 121 taxa were found: 29 Chlorophyta, 26 Phaeophyta and 66 Rhodophyta. The spring season was the richest in taxa (78) while autumn was the poorest (85). Overall, the data suggest that the point A (Pingo Dagua) macro algae community (which is similar to the discharge point (0,80) is adequate for the control of the CNAAA effluent impact ad Piraquara de Fora. (author). 11 refs, 5 figs, 1 tab.

  8. Forma central da moléstia nervosa de Recklinghausen

    Directory of Open Access Journals (Sweden)

    L. C. Mattosinho França

    1958-06-01

    Full Text Available Os autores apresentam uma sistematização das lesões que podem ser encontradas na moléstia de Recklinghausen. Foram observados 4 casos de forma nervosa central da moléstia. Em todos existiam tumores bilaterais nos ângulos pontocerebelares, constituindo uma das manifestações mais importantes da doença, sendo mesmo a única em um dos casos (forma central pura. Nos demais, portadores de formas mistas, além de outras lesões centrais (neurofibromas, meningeomas, ninhos de células atípicas, havia lesões periféricas discretas. Tumores intrarraquidianos originados nas bainhas radiculares foram os causadores da sintomatologia inicial em 3 pacientes. Em dois casos em que o córtex foi examinado histológicamente, foram encontrados ninhos de células gliais atípicas, característicos da forma central da neurofibromatose. Duas lesões relativamente raras foram encontradas no segundo caso: angioma cortical e neurite intersticial hipertrófica do plexo braquial. Em pacientes portadores de neurofibromatose periférica ou raquídea, como também em seus familiares, devem ser sempre procuradas lesões centrais, principalmente tumores do nervo acústico. O exame neuro-radiológico de escolha para confirmar o diagnóstico dêstes tumores é a iodoventriculografia.

  9. Contenidos de uranio de lavas recientes en el sector sur de los Andes centrales

    Directory of Open Access Journals (Sweden)

    Guerra, N.

    1984-12-01

    Full Text Available We have studied the distribution of U in modern lava -flows of the southern part from the Central Andes (16°-28° S. For a given SiO2, content of the rocks, U abundance increases from west to east in a transects to the Andean Belt, while the depth of the subduction zone increases and the thickness of the continental curst decreases. Besides, U content tends to inerease steadly with the latitude, while the thick of the continental crust and the depth of the seismic zone decreases southward. Thus, on the basis of the available data, we are in a position to suggest that the U behavior in the studied lavas depends on the alkalanity and magmatic history of each volcanic center.

    Se presenta un estudio de distribución de U en lavas modernas del sector sur de los Andes centrales (16°-28° S. Para rocas de contenidos similares en SiO2 la abundancia de U crece de oeste a este en un perfil transversal al cordón andino, mientras que aumenta la profundidad de subducción, y disminuye la potencia de la corteza continental. Además, mientras la potencia de la corteza continental y la profundidad de la zona sísmica de Benioff disminuyen hacia el sur, U tiende a aumentar con la latitud. Así, y basado en los datos disponibles, estamos en posición de sugerir que el comportamiento de U en las rocas estudiadas, depende de la alcalinidad y de la historia magmática de cada centro volcánico.

  10. 4. Mexican School of Nuclear Physics; 4. Escuela Mexicana de Fisica Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Aguilera, E.F.; Hernandez, E.; Hirsch, J.G. (ed.)e-mail: svp@nuclear.inin.mx

    2005-07-01

    The IV Mexican School of Nuclear Physics, organized by the Nuclear Physics Division of the Mexican Physics Society, taken place from June 27 to July 8, 2005 in the Institute of Nuclear Sciences and the Institute of Physics of the UNAM and in the National Institute of Nuclear Research (ININ). This school, as the previous ones, it was guided to the students of the last semesters of the career of Physics, of the Post grade of the same specialty, and of other adjacent careers. To give the students a current vision of some of the topics more important of the nuclear physics and their relationship with other near areas of the physics it was the objective of this School. The School covered a wide range of theoretical and experimental courses, imparted in its majority by Mexican expert professor-investigators in the subject to whom we thank them the one effort and the quality of their presentations, reflected in the content of this document. The answer of the students to the convocation was excellent, 31 students presented application for admission coming from the following institutions: Meritorious Autonomous University of Puebla, National Institute of Nuclear Research, Technological Institute of Orizaba, National Polytechnic Institute, The University of Texas at Brownsville, Autonomous University of the State de Mexico, Autonomous University of the State of Morelos, Autonomous University of Baja California, Autonomous University of San Luis Potosi, University of Guadalajara, University of Guanajuato, National Autonomous University of Mexico, University of Texas, at El Paso and University Veracruzana. They were admitted to those 22 students with the higher averages qualifications of the list of applicants. The organizers of this school thank the financial support granted by the following sponsor institutions: Institute of Nuclear Sciences, UNAM, Institute of Physics, UNAM, Coordination of the Scientific Research, UNAM, National Institute of Nuclear Research, Nuclear

  11. 4. Mexican School of Nuclear Physics. Papers; 4. Escuela Mexicana de Fisica Nuclear. Notas

    Energy Technology Data Exchange (ETDEWEB)

    Aguilera, E.F.; Hernandez, E.; Hirsch, J. (eds.)

    2005-07-01

    The IV Mexican School of Nuclear Physics, organized by the Nuclear Physics Division of the Mexican Physics Society, takes place from June 27 to July 8, 2005 in the Nuclear Sciences and of Physics Institutes of the UNAM and in the National Institute of Nuclear Research (ININ). This school, as the previous ones, it was guided the students of the last semesters of the career of Physics, of the Post grade of the same specialty, and of other adjacent careers. To give the students a current vision of some of the topics more important of the nuclear physics and their relationship with other near areas of the physics it was the objective of this School. The School covered a wide range of theoretical and experimental courses, imparted in its majority by Mexican expert professor-investigators in the matter to who we thank them the one effort and the quality of their presentations, reflected in the content of this document. The answer of the students to the convocation was excellent, 31 students presented application for admission coming from the following institutions: Meritorious Autonomous University de Puebla, National Institute of Nuclear Research, Technological Institute of Orizaba, National Polytechnic Institute, The University of Texas at Brownsville, Autonomous University of the State de Mexico, Autonomous University of the State of Morelos, Autonomous University of Baja California, Autonomous University of San Luis Potosi, University of Guadalajara, University of Guanajuato, National Autonomous University of Mexico, University of Texas, at El Paso and University Veracruzana. They were admitted to the 22 students with the higher averages qualifications of the list of applicants. The organizers of this school thank the financial support granted by the following sponsor institutions: Nuclear Sciences Institute, UNAM, Physics Institute of UNAM, Coordination of the Scientific Research UNAM, National Institute of Nuclear Research, Nuclear Physics Division of the Mexican

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

    OpenAIRE

    Vargas-Sarquís, Adrián

    2011-01-01

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

  13. James Lovelock y el Espejismo Nuclear: De Gaia a Westinghouse

    OpenAIRE

    Coderch, Marcel

    2014-01-01

    A sus 85 años de edad, James Lovelock, padre de la hipótesis Gaia (una especie de ecologismo místico según el cual la Tierra funcionaría como un ser vivo del que los humanos no somos sino una parte mínima, casi un parásito), ha roto una lanza a favor de la energía nuclear en un reciente artículo en The Independent publicado también en El País el pasado 20 de junio, donde ruega a sus «amigos del movimiento (ecologista) que abandonen su equivocada objeción a la energía nuclear». En este artícul...

  14. The impulse influence function for de-centralized control

    Institute of Scientific and Technical Information of China (English)

    ZHONG Wanxie

    2004-01-01

    Impulse influence matrix function is introduced based on that the de-centralized control analysis is analogous to the sub-structural analysis in structural mechanics. The static sub-structural analysis is analogous to the usual de-centralized control, whereas the dynamic sub-structural analysis corresponds to the de-centralized control theory. The reciprocal symmetry for the impulse influence matrix function is proved, and is solved by the precise integration method for time invariant system, giving the results up to computer precision. Based on the impulse influence functions of subsystems, the combination of subsystems can lead to a set of integral equations and be solved numerically. Numerical example demonstrates the effectiveness of the method.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

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

  16. Proyecto de una central eléctrica de biomasa

    OpenAIRE

    Valentín Botija, Sergio

    2011-01-01

    El presente Proyecto de fin de carrera pretende dar una respuesta técnica a la necesidad de abastecimiento e independencia energética mediante una solución basada en las energías renovables y en combustibles vegetales, en concreto aquella basada en la biomasa; así como profundizar en el conocimiento de las mismas y realizar un estudio de viabilidad de estas técnicas en una zona determinada de Castilla-La Mancha. De modo, que mediante este PFC se trata de analizar la viabilidad técnica y econó...

  17. Study and characterization of noble metal deposits on similar rusty surfaces to those of the reactor U-1 type BWR of nuclear power station of Laguna Verde; Estudio y caracterizacion de depositos de metales nobles sobre superficies oxidadas similares a las del reactor de la Central de Laguna Verde (CNLV) U1 del tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Flores S, V. H.

    2011-07-01

    In the present investigation work, were determined the parameters to simulate the conditions of internal oxidation reactor circulation pipes of the nuclear power plant of Laguna Verde in Veracruz. We used 304l stainless steel cylinders with two faces prepared with abrasive paper of No. 600, with the finality to obtain similar surface to the internal circulation piping nuclear reactor. Oxides was formed within an autoclave (Autoclave MEX-02 unit B), which is a device that simulates the working conditions of the nuclear reactor, but without radiation generated by the fission reaction within the reactor. The oxidation conditions were a temperature of 280 C and pressure of 8 MPa, similar conditions to the reactor operating in nuclear power plant of Laguna Verde in Veracruz, Mexico (BWR conditions), with an average conductivity of 4.58 ms / cm and 2352 ppb oxygen to simulate normal water chemistry NWC. Were obtained deposits of noble metal oxides formed on 304l stainless steel samples, in a 250 ml autoclave at a temperature range of 180 to 200 C. The elements that were used to deposit platinum-rhodium (Pt-Rh) with aqueous Na{sub 2}Pt (OH){sub 6} and Na{sub 3}Rh (NO{sub 2}){sub 6}, Silver (Ag) with an aqueous solution of AgNO{sub 3}, zirconium (Zr) with aqueous Zr O (NO{sub 3}) and ZrO{sub 2}, and zinc (Zn) in aqueous solution of Zn (NO{sub 3}){sub 2} under conditions of normal water chemistry. Also there was the oxidation of 304l stainless steel specimens in normal water chemistry with a solution of Zinc (Zn) (NWC + Zn). Oxidation of the specimens in water chemistry with a solution of zinc (Zn + NWC) was prepared in two ways: within the MEX-02 autoclave unit A in a solution of zinc and a flask at constant temperature in zinc solution. The oxides formed and deposits were characterized by scanning electron microscopy, energy dispersive X-ray analysis, elemental field analysis and X-ray diffraction. By other hand was evaluated the electrochemical behavior of the oxides

  18. Organización territorial de los antiguos mayas de Belice Central

    DEFF Research Database (Denmark)

    Helmke, Christophe; Awe, Jaime

    2008-01-01

    Los modelos propuestos para la organización territorial de los mayas del período clásico en Belice Central difieren significativamente de un investigador a otro. Debido a la escasez de datos jeroglíficos, la mayoría de los modelos se han formulado teniendo en cuenta tan solo datos arqueológicos y...

  19. SOVT analysis of the nuclear industry in Mexico; Analisis FODA de la industria nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez R, E.; Hernandez B, M. C., E-mail: edelmiraf@yahoo.com [Instituto Tecnologico de Toluca, Division de Estudios de Posgrado, Av. Instituto Tecnologico s/n, Ex-rancho La Virgen, 52140 Metepec, Estado de Mexico (Mexico)

    2011-11-15

    In this work the analysis of strengths, opportunities, vulnerabilities and threats (SOVT) of the nuclear industry in Mexico is presented. This industry presents among its strengths that Mexico is a highly electrified country and has a good established normative mark of nuclear security. Although the Secretaria de Energia in Mexico, with base to the exposed in the Programa Sectorial de Energia 2007-2012, is analyzing the convenience of the generation starting from this source, considering the strong technological dependence of the exterior and the limited federal budget dedicated to this field. As a result of the analysis of the SOVT matrix, were found a great number of strengths that threats, although the vulnerabilities list is major to the strengths, the opportunities list is the bigger. Therefore, the nuclear industry can be a sustainable industry, taking the necessary decisions and taking advantage of the detected opportunities. (Author)

  20. The International Atomic Energy Agency: orientations for the 21. century. Nuclear facilities exploitation: three questions to Remy Carle. The civil nuclear and the electric power generation in Germany. Usa: the electric power marker deregulation and the perspective of the nuclear energy. The situation of nuclear energy in Japan. Finland.. debate about the 5. reactor. The electronuclear development in China. The last act of the swedish nuclear saga. The Korean nuclear programme. The civil nuclear energy in Eastern Europe... in brief; L'Agence Internationale de l'Energie Atomique: orientations pour le 21. siecle. Exploitation des centrales nucleaires: trois questions a Remy Carle. Le nucleaire civil et la production d'electricite en Allemagne. Etats-Unis: la deregulation du marche de l'electricite et les perspectives du nucleaire. La situation du nucleaire au Japon. Finlande... sur fond de debat a propos du 5. reacteur. Le developpement electronucleaire de la Chine.

    Energy Technology Data Exchange (ETDEWEB)

    Carle, R.; Thiebaud, Ph. [CEA, Direction des Relations Interantionales, 75 - Paris (France); Heuraux, Ch.; Tinturier, B.; Lavergne, B. de [EDF, 75 - Paris (France); Forum Atomique Allemand, Bonn (Germany); Lavigne, J.J. [Ambassade de France au Japon (Japan); Soyer, B. [Ambassade de Chine en France (France); Edin, K.A. [Institut Politique et Social de Stockholm (Sweden); Chaucheprat, P. [Ambassade de France en Coree (Korea, Republic of)

    2000-04-01

    This issue is dedicated to nuclear programmes throughout the world. A few articles give an overview of the major trends of nuclear industry, from the standpoints of economy, industry, environment and international regulations. A few articles give an overview of the major trends of nuclear industry, from the standpoints of economy, industry, environment and international regulations. A few specific countries or groups of countries are then highlighted, together with a typical economic and political backgrounds. The countries dealt with are Germany, China, Korea, the U.S., Finland, Japan and Sweden. Some specific data are given on nuclear industry in Eastern Europe. (author)

  1. L'energia nuclear: pot resoldre el problema de l'escalfament global?

    OpenAIRE

    Puig, Josep

    2006-01-01

    Sovint es diu que l'energia nuclear pot ser la solució pel problema de l'escalfament global: l'article presenta dades i raonaments per concloure que, si tota l'electricitat mundial fos d'origen nuclear, l'escalfament global es reduiria tan sols en un 12%. També s'analitzen els subproductes militars de la indústria de l'energia nuclear "civil" i la problemàtica dels residus radioactius de l'energia nuclear de fissió. També s'analitza l'alt grau de dificultats que presenta l'energia nuclear de ...

  2. Discos en estrellas centrales de nebulosas planetarias

    Science.gov (United States)

    Saker, L.; Gómez, M.

    2016-08-01

    With the aim of investigating the possible existence of disks in the central stars of planetary nebulae (CSPN), in this contribution we present the spectral energy distributions of ten CSPN that show infrared (IR) excesses. Basic parameters of the disks such as internal radius and temperature are derived. When comparing the characteristics of these disks with the previously found around white dwarfs, it was found that the latter are significantly smaller. The disk sizes are compared with associated nebula. In general, disks are very compact and small in relation to the characteristic dimension of the nebula.

  3. Sistema de almacenamiento de energía eléctrica en central de ciclo combinado

    OpenAIRE

    Saez Muñiz, Javier

    2016-01-01

    El presente Proyecto Final de Carrera estudia la implantación de un sistema de almacenamiento de energía eléctrica, adecuado para la instalación en una Central Eléctrica de Ciclo Combinado. Así mismo, su estructura podrá ser aplicable a otros tipos de centrales eléctricas, industrias, o instalaciones con mínimas modificaciones. El objeto incluye el estudio, cálculo y diseño del sistema de almacenamiento de energía, evaluando diferentes tipos de tecnologías existentes en la actu...

  4. Implantación central de biomasa forestal y aprovechamiento de las masas forestales

    OpenAIRE

    Amengual Romaní, Carmen; Triguero Gil, Álvaro

    2013-01-01

    Se estudia la implantación de una central de biomasa en Cataluña, como alternativa energética renovable. Se trata de una instalación industrial diseñada para generar energía a partir de recursos biológicos. Aunque esta sea una tecnología en vías de desarrollo, las perspectivas de futuro son prometedoras. En la primera parte del proyecto, estudiaremos en profundidad el concepto de biomasa, incluyendo una recopilación de datos sobre los tipos que existen, las formas de conversión en energía,...

  5. Coordinated control of a combined cycle thermoelectric central; Control coordinado de una central termoelectrica de ciclo combinado

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Parra, Marino; Castelo Cuevas, Luis [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1998-03-01

    In this paper the coordinated control (CC) of the Distributed Control System (Sistema de Control Distribuido) (SICODI) of the Combined Cycle Central of Gomez Palacio, Durango, is presented. The description of the control scheme and its realization in software is made. From the scheme the operation strategies and automation, supervision and control are described in detail. The software components of the programming are described, the program structure and control data and its implementation in working stations VAX 3100 under the operating system VMS (Virtual Memory System), are described. [Espanol] En este articulo se presenta el control coordinado (CC) del Sistema de Control Distribuido (Sicodi) de la central de ciclo combinado Gomez Palacio, Durango. Se describe el esquema de control y su realizacion en software. Del esquema se detallan las estrategias de operacion y automatizacion, supervision y control. Del software se describen los componentes de la programacion, la estructura de programas y datos del control y su implementacion en estaciones de trabajo VAX 3100 bajo el sistema operativo VMS (Virtual Memory System).

  6. Operator Load Assessment : Een evaluatie van de technische centrale van het LCF

    NARCIS (Netherlands)

    Grootjen, M.; Lindenberg, J .; Greef, T. de; Neerincx, M.A.

    2007-01-01

    De laatste twintig jaar hebben grote veranderingen gebracht in de informatietechnologie. Aan boord van marineschepen zorgt de steeds verdergaande automatisering voor een ingrijpende wijziging in de functie van de operator op de brug, in de commandocentrale en in de technische centrale.

  7. Criptococose do sistema nervoso central. Registro de um caso

    Directory of Open Access Journals (Sweden)

    Adherbal Tolosa

    1956-06-01

    Full Text Available Registro de caso de criptococose do sistema nervoso central, cujo diagnóstico foi estabelecido pelo exame do liqüido cefalorraquidiano. A presença do criptococo, verificada no exame direto, foi confirmada por culturas. O paciente apresentava quadro irritativo meníngeo, ao qual se associaram, ulteriormente, distúrbios encefálicos difusos e síndrome de hipertensão intracraniana. Evolução fatal após 4 meses de doença; foi tentada a sulfamido-terapia, sem resultado. O exame necroscópico confirmou a existência de leptomeningite difusa e micro-abscessos disseminados no córtex cerebral; o óbito foi relacionado à compressão bulbar por hérnia das tonsilas cerebelares.

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

    CERN Document Server

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

    2002-01-01

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

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

    CERN Document Server

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

    2010-01-01

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

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

    Directory of Open Access Journals (Sweden)

    Antonio Torres-Valle

    2012-05-01

    Full Text Available Entre las más recientes aplicaciones del Análisis Probabilista de Seguridad (1997 – 2003 de la Central Nuclear Embalse en Argentina, está el Programa de Mantenimiento Orientado a la Seguridad (2006– 2009 el cual se ha desarrollado con el empleo de la metodología de Mantenimiento Centrado en la Confiabilidad (RCM en inglés. El objetivo general del artículo es demostrar la alta contribución de los fallos mecánicos en el diseño de las políticas de mantenimiento de varios sistemas de la instalación a través del empleo de la metodología RCM. La composición, estructura y políticas de explotación de los sistemas tecnológicos de muchas instalaciones con riesgo asociado, similares a las de los sistemas analizados en este estudio, permite inferir que los resultados que se obtendrán serán equivalentes de aplicarse la metodología RCM en dichas instalaciones. Palabras claves: mantenimiento centrado en la confiabilidad, mantenimiento predictivo, mantenimiento preventivo, fallo mecánico, seguridad, confiabilidad, riesgo.______________________________________________________________________________ Abstract One of the most recent applications of Probabilistic Safety Analysis (1997 – 2003 to Embalse Nuclear Power Plant in Argentina, is the Safety Oriented Maintenance Program (2006 – 2009 developed with employment of the Reliability Centered Maintenance (RCM methodology. The general objective of the paper is to demonstrate the high contribution of the mechanical failures in the maintenance program design through the RCM methodology. The composition, structure and operation strategies of the technological systems of many risk associated facilities, similar to the analysed systems included in this study, allow deduce that the results will equivalent in case of application of RCM methodology in such facilities. Key words: reliability centered maintenance (RCM, predictive maintenance, preventive maintenance, mechanical failure, safety

  11. Propuesta de rehabilitación de la casa de correos y telégrafos central de Badalona

    OpenAIRE

    Torres Sánchez, Victoria

    2015-01-01

    En este proyecto final de grado realizaré una rehabilitación de la casa de Correos y Telégrafos central de Badalona sin efectuar un cambio de uso, dato que se desarrollará en los capítulos siguientes. En una primera parte del trabajo, que he articulado en varios capítulos principales, encontraremos una breve introducción donde se explican los objetivos que se pretenden conseguir y el marco normativo que le afecta. Nos introduciremos en la evolución histórica de Correos y ...

  12. Paracoccidiomicosis en el sistema nervioso central: reporte de un caso

    Directory of Open Access Journals (Sweden)

    Jesús Rojas-Jaimes

    Full Text Available La paracoccidiomicosis es una enfermedad micótica que puede comprometer el sistema nervioso central (SNC. Se presenta el caso de un paciente varón de 45 años, inmunocompetente, de la ciudad de Satipo, que desarrollo paracoccidiomicosis en el SNC sin punto de entrada e infección aparente. El paciente fue diagnosticado por imágenes con un granuloma cerebelar, posteriormente, se realiza una craneotomía de donde se obtiene tejido y secreción del absceso del granuloma, se procedió al diagnóstico histológico y microbiológico, respectivamente, donde se observó la presencia de levaduras en el corte histológico y el crecimiento del hongo en el cultivo. El paciente, inicialmente, recibe antifúngicos, luego adquiere una infección intrahospitalaria, recibe colistina y posteriormente fallece. El caso reportado pone énfasis en la importancia del diagnóstico temprano y correcto para la buena evolución de los casos de paracoccidiomicosis.

  13. Paracoccidiomicosis en el sistema nervioso central: reporte de un caso

    Directory of Open Access Journals (Sweden)

    Jesús Rojas-Jaimes

    2015-01-01

    Full Text Available La paracoccidiomicosis es una enfermedad micótica que puede comprometer el sistema nervioso central (SNC. Se presenta el caso de un paciente varón de 45 años, inmunocompetente, de la ciudad de Satipo, que desarrollo paracoccidiomicosis en el SNC sin punto de entrada e infección aparente. El paciente fue diagnosticado por imágenes con un granuloma cerebelar, posteriormente, se realiza una craneotomía de donde se obtiene tejido y secreción del absceso del granuloma, se procedió al diagnóstico histológico y microbiológico, respectivamente, donde se observó la presencia de levaduras en el corte histológico y el crecimiento del hongo en el cultivo. El paciente, inicialmente, recibe antifúngicos, luego adquiere una infección intrahospitalaria, recibe colistina y posteriormente fallece. El caso reportado pone énfasis en la importancia del diagnóstico temprano y correcto para la buena evolución de los casos de paracoccidiomicosis.

  14. Bofedales: high altitude peatlands of the central Andes Bofedales: turberas de alta montaña de los Andes centrales

    Directory of Open Access Journals (Sweden)

    FRANCISCO A SQUEO

    2006-06-01

    Full Text Available There is an exceptional group of alpine peatlands in the world situated in the arid grasslands of the central Andes. The peatlands in northern Chile occur in the most arid part of their range. Members of the Juncaceae are the primary peat-forming plant species. Fresh and mildly saline groundwaters originate from glaciers, snowmelt and rain are the water sources for the northern Chile peatlands. Paleoecological investigations suggest that some peatlands are recent features of the landscape having developed within the last three thousand years or less. These peatlands are unique, extremely fragile water features sensitive to climate changes and human disturbances such as regional mining activity. Much more work is required to develop scientifically based sound management and conservation programs for the rare plants and animals that live in them and to ensure the future livelihoods of the indigenous peoples who depend on themExiste un grupo excepcional de turberas (bofedales de alta montaña en el mundo situados en la estepa árida de los Andes centrales. Los bofedales en el norte de Chile están presentes en la parte más árida de su rango. Las principales especies de plantas responsables de la formación de turba corresponden a miembros de Juncaceae. El agua fresca y medianamente salina de los bofedales proviene de agua subterránea asociada a riachuelos proveniente de glaciares, derretimiento de nieve y lluvia. Investigaciones paleoecológicas sugieren que algunos bofedales son integrantes recientes del paisaje, habiéndose desarrollado durante los últimos tres mil años o menos. Estos bofedales son entidades únicas, extremadamente frágiles por su dependencia del agua, sensibles a los cambios climáticos y vulnerables a la alteración humana tal como la actividad minera en la región. Se requiere mucho más trabajo para desarrollar programas de manejo y conservación, con sólidas bases científicas, de las plantas y animales que viven en

  15. Prestaciones del Detector Central de Muones del Experimento CMS: las Camaras de Deriva y su Sistema de Trigger (Performance of the Central Muon Detector of the Experiment CMS: the Drift Tube Chambers and its Trigger System)

    CERN Document Server

    Muñoz, Carlos Villanueva

    2007-01-01

    Prestaciones del Detector Central de Muones del Experimento CMS: las Camaras de Deriva y su Sistema de Trigger (Performance of the Central Muon Detector of the Experiment CMS: the Drift Tube Chambers and its Trigger System)

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

    OpenAIRE

    2016-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-15

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

  18. Oficina central de Ralston Purina San Luis – (EE. UU.

    Directory of Open Access Journals (Sweden)

    Hellmuth, George

    1978-03-01

    Full Text Available The tall building housing these main offices is located on a lot with over 56 hectares; it constitutes the first stage of a complex which will consist of a series of auxiliary buildings for the Company. The building has a total constructed surface of 27,400 m2 on 15 floors. The top 12 floors are destined for administrative use with work space for about 1,200 employees and the first three floors are reserved for entrance and reception areas, exhibition room, executive offices and indoor garden areas. This unique utilization of the space is clearly evident in the distinct type of planning adopted. A very interesting characteristic of this building, a requisite from the very beginning, is its high degree of organizational flexibility, achieved by using reticular forging of modules of 1.50 x 1.50 m in which the building's different installations are located, which provides service availability anywhere in the building, independent of the organization or departmental divisions adopted.

    La torre que alberga estas oficinas centrales, situada en una parcela de más de 56 Ha, constituye la primera fase de un complejo que comprenderá una serie de edificios auxiliares para la compañía. Con una edificabilidad total de 27.400 m2 en sus 15 plantas, la torre destina los 12 niveles superiores a uso administrativo, con puestos de trabajo para unos 1.200 empleados, y reserva las tres primeras plantas para los servicios de acceso y recepción, sala de exposiciones, despachos de los directivos y zonas ajardinadas interiores. Esta diferente utilización queda claramente patentizada en el distinto planteamiento formal de plantas y alzados. Una interesante característica de la construcción, exigida en el programa inicial, es el alto grado de flexibilidad organizativa, conferida por el empleo de un forjado reticular, de 1,50 x 1,50 m de módulo, en el que van incluidas las distintas instalaciones del edificio, lo que permite el

  19. Remote system for counting of nuclear pulses; Sistema remoto de conteo de pulsos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Nieves V, J.A.; Garcia H, J.M.; Aguilar B, M.A. [Instituto Nacional de Investigaciones Nucleares, Ingenieria Electronica, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1999-07-01

    In this work, it is describe technically the remote system for counting of nuclear pulses, an integral system of the project radiological monitoring in a petroleum distillation tower. The system acquires the counting of incident nuclear particles in a nuclear detector which process this information and send it in serial form, using the RS-485 toward a remote receiver, which can be a Personal computer or any other device capable to interpret the communication protocol. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

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

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

    OpenAIRE

    Losada Godoy, Carlos

    2014-01-01

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

  2. Diagnóstico ambiental preliminar de la Central Termoeléctrica de Paipa

    Directory of Open Access Journals (Sweden)

    Carlos Magno Martínez Mora

    2010-12-01

    Full Text Available Este trabajo, realizado por el Ingeniero Carlos M. Martínez Mora, como uno de los requisitos para optar al título de Magister Scientiae en Ingeniería ambiental y dirigido por el ingeniero Jorge Ricardo Bernal, tuvo como objetivo analizar las condiciones actuales de operación de la Central Termoeléctrica de Paipa y establecer las bases para la preparación del expediente ambiental exigido por el Código de los Recursos Naturales Renovables y de Protección al Medio Ambiente. Se estableció que en el momento operan tres unidades de generación de 33, 66 Y 74 megavatios. Se utiliza el agua del río Chicamocha, para condensación y transferencia de calor hacia el ambiente. El combustible utilizado es carbón mineral, cuyas emisiones contaminadoras son cenizas y óxidos de azufre. Se llevó a cabo un programa de muestreo de calidad del agua y se hizo un estimativo de calidad del aire, mediante la aplicación de un modelo de dispersión. Definido el estado actual o de referencia, se realizó un análisis de los efectos predecibles que podría causar sobre la calidad ambiental, la instalación de una cuarta unidad generadora de 150 megavatios. Se hacen varias recomendaciones tendientes a minimizar tales posibles efectos negativos.

  3. Presentation of the process External communications on the nuclear facilities operation of the Adjunct Head Office of Nuclear Safety of Comision Nacional de Seguridad Nuclear y Salvaguardias; Presentacion del proceso Comunicaciones externas sobre el funcionamiento de instalaciones nucleares de la Direccion General Adjunta de Seguridad Nuclear de la Comision Nacional de Seguridad Nuclear y Salvaguardias

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa V, J. M., E-mail: jmespinosa@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2012-10-15

    The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in use of their attributions granted by the Regulation Law of the constitutional Art. 27 in nuclear matter began the development of the called process External communications on the nuclear facilities operation, with the purpose of negotiating the evaluation of the concerns related with the safety of the nuclear facilities received these of external people to the CNSNS. The process External communications on the nuclear facilities operation will allow to the public's members and the workers that carry out activities inside the mark regulator imposed by the CNSNS that report to this Commission their concerns related with safety for several means (for example, directly to the personnel of the assigned Office, official and public statements, phone communication, electronic mail, etc.) The present article presents the legal mark confers the CNSNS the attributions to develop the mentioned process and exposes the most important elements that compose it. The term External communication on the nuclear facilities operation is defined and also is described how these communications are received, evaluated and closed by the assigned Office. Of equal way the objectives that intents to reach this process are indicated. The intention of the mentioned process is to strengthen the actions that the CNSNS carries out in the execution of its functions to maintain the safety standards in the operation of the nuclear facilities in Mexico. (Author)

  4. Energy problems of the central systems of air conditioning; Problemas energeticos de los sistemas centrales de climatizacion

    Energy Technology Data Exchange (ETDEWEB)

    Cardero Corria, Gaspar [Cubanacan, S.A., Varadero (Cuba)

    2003-07-01

    The central systems of air conditioning are widely used in air conditioning production for several reasons among which excel: 1) Better aesthetic of the building, 2) Less noise in the air conditioning premises and 3) Greater yield of the consumed energy. This is indeed the third reason in which this paper will try to contribute with elements that will allow reveal the problem and to identify some possible causes that originate it. The centralized systems of air conditioning must produce conditioned air with lesser power cost than the individual systems, it is that saving which allows to recover an investment that normally surpasses them in 3 to 5 times. Nevertheless, the real numbers do not demonstrate that. [Spanish] Los sistemas centrales de climatizacion son ampliamente usados en la produccion de aire acondicionado por varias razones entre las que sobresalen: 1) Mejor estetica del edificio, 2) Menor ruido en los locales climatizados y 3) Mayor rendimiento de la energia consumida. Es precisamente la tercera razon en la cual este trabajo intentara aportar elementos que permitan develar el problema e identificar algunas posibles causas que lo originan. Los sistemas centralizados de climatizacion deben producir aire acondicionado con un menor gasto energetico que los sistemas individuales, es precisamente ese ahorro lo que permite recuperar una inversion que normalmente los supera en 3 a 5 veces. Sin embargo, los numeros reales no demuestran eso.

  5. Materials Laboratory at the Institute of Nuclear Fusion: growth and characterization of coatings with nuclear applications; Laboratorio de Materiales en el Instituto de Fusion Nuclear: crecimiento y caracterizacion de recubrimientos con aplicaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez-Arrabal, R.; Gordillo, N.; Panizo-Laiz, M.; Fernandez-Martinez, I.; Wennberg, A.; Rivera, A.; Pena, O.; Briones, F.; Perlado, J. M.

    2013-07-01

    We report on the capabilities of the new materials lab located at the Instituto de Fusion Nuclear to develop coating for nuclear applications. The main objectives of the lab are described: (a) design of coatings which fulfil industrial requirements and (b) development of the need instrumentation to coat non-planar surfaces, i.e. inner and outer surface of pipes. Some examples of radiation resistance materials (self-healing) will be shown. Moreover, we present some new solution with improved corrosion resistance when facing liquid metals to conform the cooling system of future fission and fusion nuclear reactors. (Author)

  6. Central móvil de hormigón asfáltico

    Directory of Open Access Journals (Sweden)

    Editorial, Equipo

    1959-11-01

    Full Text Available En números anteriores se han publicado varios tipos de centrales hormigoneras, y entre ellas una para la preparación de hormigones asfálticos. El tipo de Central que se describe ligeramente en este trabajo, de la casa Braham Patterson & Benham Ltd, inglesa, presenta su particularidad propia e interés dentro del campo de rendimiento de producción del orden de 25 toneladas por hora.

  7. Early mineralization at Cerro de Pasco (central Peru) revisited

    OpenAIRE

    Rottier, Bertrand; Casanova, Vincent; Fontboté, Lluis; Kouzmanov, Kalin; Alvarez, Hugo; Bendezú, Ronner

    2013-01-01

    The large Cerro de Pasco Cordilleran base metal deposit in central Peru is located on the eastern margin of a Middle Miocene diatreme-dome complex. A striking characteristic is the presence of a N-S trending massive funnel-shape pyrite-quartz replacement ore body that contains pyrrhotite pipes grading outwards to lead-zinc replacement bodies, along the eastern contact of the diatreme-dome complex. Earlier workers interpreted the pyrrhotite pipes as postdating the pyritequartz body. This study...

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

    Science.gov (United States)

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

    1999-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-02-15

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

  10. The repair of an electric generator at the Patla hydro central; Reparacion de un generador de la central hidroelectrica de Patla

    Energy Technology Data Exchange (ETDEWEB)

    Vazquez Hernandez, Roman [Luz y Fuerza del Centro, Mexico, D. F. (Mexico)

    1997-12-31

    This document describes the repair of the Generator Number 1 of the system of the Unit No. 1 of the Patla Hydro Power Central in Mexico. The tests that were conducted to determine the fault and the location of the same are shown. Mention is made of the fault repair options and the stages in one of the options are described, since it is the one that better covers the expectations for the satisfactory repair of the generator. Finally the commissioning test is described and it is concluded that an increment of 92% (14 MW) in the generation capacity of the unit was achieved, being this the first time a repair of this type is made of generating units [Espanol] Este documento describe la reparacion del generador numero 1 del sistema de la unidad numero 1 de la central hidroelectrica de Patla en Mexico. Se muestran las pruebas que se hicieron para determinar la falla y localizacion de la misma. Se mencionan las alternativas de reparacion de la falla y se describen las etapas de una de las alternativas, ya que es la que cubre mejor las expectativas para la reparacion satisfactoria del generador. Por ultimo se describe la prueba de puesta en servicio y se concluye en que se logro un aumento de la capacidad de generacion de la unidad en un 92% (14 MW), siendo la primera vez que se hace una reparacion de este tipo de unidades generadoras

  11. Susceptibilidad de Delia platura a siete aislamientos de nematodos entomopatógenos de la zona Central Andina de Colombia

    Directory of Open Access Journals (Sweden)

    Carolina Jaramillo Contreras

    2013-07-01

    Full Text Available La mosca de la semilla, Delia platura, es una de las principales plagas en los cultivos de espinaca en la sabana de Bogotá. En Colombia la plaga es controlada mediante la aplicación de insecticidas y la información sobre su control sigue siendo limitada. Por ello el objetivo de este trabajo fue evaluar la susceptibilidad de D. platura a siete aislamientos de nematodos entomopatógenos de la zona Central Andina de Colombia. Además de evaluar diferentes dosis y producción de juveniles infectivos (JIs de la especie más virulenta, bajo condiciones de laboratorio. En el laboratorio se estableció la cría en papa amarilla (Solanum phureja para obtener larvas de tercer instar, las cuales se expusieron a 2500 JIs/especie NEPS. Seleccionada la especie más virulenta, se expuso D. platura a 500, 1000, 2000, 4000 y 8000 JIs/larva. Los mejores resultados obtenidos se encontraron con Steinernema sp3 con una mortalidad entre el 75 a 88% en las dosis de 4000 y 8000 JIs encontrando que la DL50 es de 1314JIs/larva y 15259 JIs/larva la DL95. Así mismo, se estableció que Steinernema sp3 se reproduce exitosamente en D. platura, encontrando un promedio de producción 670 ± 7.67 JIs/larva durante un periodo de dieciocho días. La mosca de la semilla es altamente susceptible a Steinernema sp3, el cual puede ser un agente potencial para el control de esta plaga.

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

    CERN Document Server

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

    2004-01-01

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

  13. Las Áreas Centrales de Montevideo: En Procura de una Revitalización Integral

    Directory of Open Access Journals (Sweden)

    María del Huerto Delgado Dopazo

    2004-01-01

    Full Text Available Comenzando por una reseña histórica acerca de la conformación y evolución de la ciudad de Montevideo, capital del Uruguay, el presente artículo profundiza en los procesos de despoblamiento y degradación que sufrieron sus áreas centrales, en las últimas décadas del siglo XX; para finalmente reseñar las acciones y programas que a partir de los ’90 se han propuesto e implementado, para revertir dichos procesos. Del análisis se desprenden las potencialidades y debilidades de áreas centrales y de las propuestas de rehabilitación planteadas y en curso. Las mismas deberían enmarcarse en una planificación estratégica participativa y consensuada por todos los actores involucrados, para lograr un desarrollo local sustentable y sostenible en el tiempo. Es fundamental, para que las áreas centrales vuelvan a ser “centros vivos” de la ciudad y reconstruir la heterogeneidad tradicional del tejido social y funcional de sus barrios, el devolverles la función residencial que han ido perdiendo, y fomentar y fortalecer la participación ciudadana en los distintos niveles de los procesos.

  14. Nuclear study of Melusine; Etude nucleaire de Melusine

    Energy Technology Data Exchange (ETDEWEB)

    Cherot, J. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1959-07-01

    In this report are reviewed - with respect to starting of experiments - the main nuclear characteristics of a 20 per cent enriched uranium lattice, with light water as moderator and reflector. The reactor is to operate at 1 MW. 1) Study of various critical masses. 2) Control. Effectiveness of cadmium. Control rods and of a stainless steel regulating rod. 3) Study of the effect on reactivity of disturbances in the core center. 4) Study of xenon and samarium poisoning. 5) Temperature factor. 6) Heat exchanges in a fuel element. (author) [French] On etudie, dans ce rapport, les principales proprietes nucleaires d'un reseau a uranium enrichi (20 pour cent), dont le moderateur et le reflecteur sont l'eau legere en vue des experiences de demarrage. Ce reacteur devra fonctionner a 1 MW. 1) Etude de diverses masses critiques. 2) Controle. Efficacite des barres de controle en cadmium et d'une barre de reglage en acier inoxydable. 3) Etude de l'effet sur la reactivite de perturbation au centre du coeur. 4) Etude de l'empoisonnement xenon et samarium. 5) Coefficient de temperature. 6) Echanges thermiques dans un element. (auteur)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

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

  16. Public perception of nuclear power in Mexico after Fukushima; Percepcion publica de la energia nuclear en Mexico despues de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Palacios, J. C.; Alonso, G.; Ramirez, R., E-mail: javier.palacios@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    This section presents some of the results of four studies on international public opinion about nuclear energy, the first one made several years before the Fukushima accident, conducted in 2005 by the IAEA through the company Globe Scan Inc. The second study was conducted by the same company in 2011 a few months after the Fukushima accident, including also corresponding results to two studies conducted by the British firm Ipsos Mori (of years 2011 and 2012 respectively). Finally three studies conducted by the Instituto Nacional de Investigaciones Nucleares (ININ) in 2006, 2008 and 2013 are presented. From the results of these studies was determined that the Fukushima accident itself had a negative effect on public opinion in Mexico, as throughout the world, but this trend is reversing. Also it found that public opinion in Mexico on using reactors to generate electricity is favorable, although not still has much support from the government for the construction of new nuclear power plants. (Author)

  17. Community Resources Guide for Central Florida = Una Guia de Recursos en la Comunidad de Florida Central.

    Science.gov (United States)

    Medina, Linda, Comp.

    Designed to orient Hispanic refugees to the services that are available in Central Florida, this bilingual guide consists of a section of general information on living and working in the United States and a section devoted to various public and private agencies. Provided first are addresses and phone numbers of various government agencies:…

  18. RESONANCIA MAGNÉTICA NUCLEAR DEL PRODUCTO GELIFICADO DE LA REACCIÓN DE CANNIZZARO

    Directory of Open Access Journals (Sweden)

    Lilia Fernández Sánchez

    2015-01-01

    Full Text Available Se presenta n los espectros de resonancia magnética nuclear ( RMN de protón 1 H, de carbón 13 C y bidimensionales , del produc to de una síntesis orgánica verde de óxido - reducción en la r eacción de Cannizzaro. El producto fue reportado como un gel triboquímico y elucidado por análisis de infrarrojo IR , ray os X y micrografía de barrido ( SEM . Los resultados en este artículo confirman su estructura a través de diversas técnicas de RMN y evalúan el contenido de benzoato de sodio y alcohol bencílico en la muestra e mpleada en la espectroscopia a través del examen de los valores de las integrales en la s señales de RMN de 1 H. El resultado del estudio indica que el alcohol bencílico se encuentra en un 33.44% mol (fase dispersa con respecto al cont enido de benzoato de sodio (fase continua . Estos resultado s confirma n la estruct ura de gel que con el tiempo pierde a la fase dispersa el alcohol produciendo un xerogel

  19. Control of gaseous emissions in central Costanera S.A. of Argentina; Control de emisiones gaseosas en central Costanera S. A. de Argentina

    Energy Technology Data Exchange (ETDEWEB)

    Brabenec, Edgardo [Unidad de Negocios Central Costanera, S. A., (Argentina)

    1996-12-31

    A description is presented of the equipment utilized at the Central Costanera, S.A. of Argentina, the requirements and the Environmental Management established for this Power Station, and the Standards and the resolutions and law instruments on Environmental issues. Also it is presented the Environmental Management plan of the Ente Nacional Regulador de Electricidad of Argentina as well as the controls and environmental corrective actions implemented at the Central Costanera, S.A. [Espanol] Se presenta una descripcion del equipo utilizado en la Central Costanera S.A. de Argentina, los requerimientos de gestion ambiental establecidos para esta central y las normas, resoluciones e instrumentos juridicos en materia ambiental. Se presenta ademas el plan de gestion ambiental del Ente Nacional Regulador de la Electricidad de Argentina asi como los controles y acciones correctivas ambientales implantadas en la Central Costanera S. A.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

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

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

    Institute of Scientific and Technical Information of China (English)

    Christian Engelmann; Falk Weih; Ronny Haenold

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-05-15

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

  3. Proliferación Nuclear y Estado de Excepción (Nuclear Proliferation and State of Exception

    Directory of Open Access Journals (Sweden)

    Gian Carlo Delgado

    2008-01-01

    Full Text Available Desde el 11.09, es observable un recrudecimiento de las medidas y acciones en la denominada "guerra contra el terrorismo". La concentración de poderes por parte del ejecutivo estadounidense, la erogación o suspensión de diversas Leyes son indicativos, entre otros, de la instauración de facto de un Estado de Excepción que, además se encuentra empantanado en una dinámica de guerra altamente desestabilizadora, sobre todo en términos de la seguridad internacional. Es un contexto en el que la carrera armamentista se viene acelerando, incluyendo su variable nuclear –en parte estimulada por el animado empuje a la nucleoelectricidad como supuesta alternativa viable al cambio climático. En flagrante violación a diversos acuerdos internacionales, pero sobre todo, en este caso, del “Tratado de No Proliferación Nuclear”, Estados Unido viene jugando la carta nuclear de tal modo que ya muchos consideran que, de seguir esta tendencia, estamos en camino hacia una eventual "nueva era nuclear". Y es que debido a la diversidad de actores, variables e intereses involucrados, tanto a nivel global como regional, el orden de probabilidades de una confrontación con armas nucleares cada vez más se incrementa; en especial cuando las posturas de diversos países, pero fundamentalmente de EUA, se tornan cada vez más totalitarias. El reloj del juicio final no en vano ha sido recientemente ajustado dos minutos más cerca de una guerra general termonuclear. Since 11.09, it is observable an upsurge on the measures and actions meant for the progress of the so called “war on terrorism”. The concentration of power in the US Executive, the derogation of diverse laws or the suspension of civil rights, are aspects, among others, that indicate that in fact an State of Exception has been established. One that, what's more, it´s trapped in a highly and increasingly destabilizing dynamic of (petrowar in the Middle East which affects not only international

  4. Proliferación Nuclear y Estado de Excepción (Nuclear Proliferation and State of Exception

    Directory of Open Access Journals (Sweden)

    Gian Carlo Delgado

    2008-01-01

    Full Text Available Desde el 11.09, es observable un recrudecimiento de las medidas y acciones en la denominada "guerra contra el terrorismo". La concentración de poderes por parte del ejecutivo estadounidense, la erogación o suspensión de diversas Leyes son indicativos, entre otros, de la instauración de facto de un Estado de Excepción que, además se encuentra empantanado en una dinámica de guerra altamente desestabilizadora, sobre todo en términos de la seguridad internacional. Es un contexto en el que la carrera armamentista se viene acelerando, incluyendo su variable nuclear –en parte estimulada por el animado empuje a la nucleoelectricidad como supuesta alternativa viable al cambio climático. En flagrante violación a diversos acuerdos internacionales, pero sobre todo, en este caso, del “Tratado de No Proliferación Nuclear”, Estados Unido viene jugando la carta nuclear de tal modo que ya muchos consideran que, de seguir esta tendencia, estamos en camino hacia una eventual "nueva era nuclear". Y es que debido a la diversidad de  actores, variables e intereses involucrados, tanto a nivel global como regional, el orden de probabilidades de una confrontación con armas nucleares cada vez más se incrementa; en especial cuando las posturas de diversos países, pero fundamentalmente de EUA, se tornan cada vez más totalitarias. El reloj del juicio final no en vano ha sido recientemente ajustado dos minutos más cerca de una guerra general termonuclear. Since 11.09, it is observable an upsurge on the measures and actions meant for the progress of the so called “war on terrorism”. The concentration of power in the US Executive, the derogation of diverse laws or the suspension of civil rights, are aspects, among others, that indicate that in fact an State of Exception has been established. One that, what's more, it´s trapped in a highly and increasingly destabilizing dynamic of (petrowar in the Middle East which affects not only international

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

    OpenAIRE

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

    2013-01-01

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

  6. Corrales de piedra-pirkas- un patrimonio cultural del paisaje rural de Chile central

    OpenAIRE

    Tomic Jakas, Tonci Stipe

    2016-01-01

    Quisiéramos partir con este soliloquio, quizás el más famoso del drama español; ocurre al final del primer acto, cuando Segismundo piensa en la vida y en su suerte. No es el fatalismo lo que interesa si no que desde el inicio explicitar que se trata de una reflexión que lleva a configurar un visión –algo que anida en la mente-- que su fin central radica es tratar de poner en valor sobre la base de la importancia histórica, cultural y patrimonial de los muros de piedra o pirkas; en particular ...

  7. Measurement of void fractions by nuclear techniques; Medicion de fracciones de vacio por tecnicas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez G, A.; Vazquez G, J.; Diaz H, C.; Salinas R, G.A. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1997-07-01

    In this work it is done a general analysis of those techniques used to determine void fractions and it is chosen a nuclear technique to be used in the heat transfer circuit of the Physics Department of the Basic Sciences Management. The used methods for the determination of void fractions are: radioactive absorption, acoustic techniques, average velocity measurement, electromagnetic flow measurement, optical methods, oscillating absorption, nuclear magnetic resonance, relation between pressure and flow oscillation, infrared absorption methods, sound neutron analysis. For the case of this work it will be treated about the radioactive absorption method which is based in the gamma rays absorption. (Author)

  8. Telmex: el caso de las operadoras de la central San Juan

    Directory of Open Access Journals (Sweden)

    Gerardo Tunal Santiago

    2004-01-01

    Full Text Available El objetivo general de este artículo es analizar el impacto de los procesos de modernización productiva en las identidades ocupacionales de las operadoras de la empresa Teléfonos de México, S.A. de C.V. (Telmex; así como abordar las dimensiones que engloban y describen la identidad ocupacional de dichas trabajadoras para así señalar cuáles son sus niveles de pertenencia en su ocupación laboral, en la empresa, con sus compañeras y con su género. De igual forma veremos cómo la valoración de los cambios técnicos y organizativos se convierten en un factor que modifica dichos niveles. Asimismo, haremos una caracterización del tipo de identidad ocupacional propia de las operadoras de la Central San Juan de Telmex y ante qué problemas o reconfiguraciones simbólicas se presenta esta identidad.

  9. Lucha tras las rejas franquistas. La prisión central de mujeres de Segovia

    Directory of Open Access Journals (Sweden)

    Santiago VEGA SOMBRÍA

    2012-02-01

    Full Text Available Edificio de tipo panóptico inaugurado en 1924 como Reformatorio de Mujeres, posteriormente sería Hospital Asilo Penitenciario para ancianos y enfermos de tuberculosis. Con la guerra civil se vio abarrotado de presos políticos, que ya no abandonarían el edificio durante toda la dictadura. En 1946 se transformó en Prisión Central de Mujeres y, durante sus diez años de existencia, albergó al mayor contingente de luchadoras antifranquistas españolas, que convirtieron esta prisión en un centro de formación política y cultural clandestino. El papel que representó la cárcel de Burgos para los presos políticos lo constituyó Segovia para las políticas. Su impulso organizativo desarrolló y mantuvo redes de solidaridad que llevaron a declarar una huelga de hambre en enero de 1949. Aunque fueron castigadas severamente, con este pulso ante las autoridades represivas, las presas defendieron su dignidad y su identidad como reclusas políticas. Desde finales de los sesenta, el edificio encerró de nuevo a militantes antifranquistas de organizaciones políticas y sindicales.

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

    Science.gov (United States)

    Szewczak, Kamil; Jednoróg, Sławomir; Krajewski, Paweł

    2013-01-01

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

  11. Validación de genotipos de frijol negro en la zona central del Estado de Veracruz, México

    OpenAIRE

    2005-01-01

    Validación de genotipos de frijol negro en la zona central del estado de Veracruz, México. El objetivo del presentetrabajo, fue validar genotipos de frijol con el paquete tecnológico del INIFAP, en parcelas de productores. Durante los ciclosde humedad residual de 1998 a 2001 se establecieron nueveparcelas de validación. Los genotipos utilizados fueron: las lí-neas II-307 y DOR-500 y las variedades Negro Huasteco 81,Negro Cotaxtla 91 y Negro INIFAPy como testigo del productor la variedad Jamap...

  12. Nuevas consideraciones en torno a la Cleopatra del Esquilino de la Central Montemartini de Roma

    Directory of Open Access Journals (Sweden)

    Silvio Strano

    2008-07-01

    Full Text Available Este artículo es un estudio sobre la iconografía de Cleopatra VII Philopator, hoy conocida gracias a las efigies monetarias y a los pocos retratos de bulto redondo llegados hasta nosotros. La atención se centra en la discutida interpretación de la Cleopatra/Venus Esquilina de la Sala Caldaie de la Centrale Montemartini de Roma. Los resultados de esta investigación han permitido demostrar la identificación propuesta de la réplica como imagen divinizada de la última reina tolemaica, aquí representada como Isis-Afrodita. Además, el autor propone una datación diferente de la obra, individúa el probable patrocinio, así como también, el lugar de su originaria localización.This essay is a survey about the iconography of Cleopatra VII Philopator, today well known thanks to the coin images and to the few portraits in full relief handed down to us. Attention is concentrated on the debated interpretation of the Cleopatra/Venus Esquiline found in the Sala Caldaie of the Centrale Montemartini in Rome. The result of this survey has allowed the suggested identification of the replica to be confirmed, as divinized image of the last Tolemaic Queen portrayed here as Isis-Aphrodite. Moreover the author proposes a different dating of the work, identifies the possible commission and also the site of its original positioning.

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

    OpenAIRE

    2014-01-01

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

  14. Kinematics of high-energy nuclear processes; Cinematica de los procesos nucleares de alta energia

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez del Rio, C.

    1972-07-01

    This report is the first draft of one of the chapters of a book being prepared under the title:Topics on Practical Nuclear Physics. It is published as a report because of its immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  15. Kinematics of low-energy nuclear processes; Cinematica de los procesos nucleares de baja energia

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez del Rio, C.

    1972-07-01

    This report is the first draft of one of the chapters of a book being prepared under the title: Topics on Practical Nuclear Physics. It is published as a report because of its immediate educational value and in order to include in its final draft the suggestions of the readers. (Author)

  16. Antecedentes geobotánicos de una cuenca andina de Chile Central

    Directory of Open Access Journals (Sweden)

    Quintanilla Pérez, V.

    2004-12-01

    Full Text Available Like any other mountain ecosystem; the Andes Mountains show an outstanding phytoecological specificity. This is because of the influence of ecological conditions; as well as the presence of special vegetation groups. These groups of plants show a well defined structure and functionality; arising from the adaptation of biological behavior to the regional altitude. Nevertheless; despite the rigourous climatic conditions; plants do have access to water supplies. A latitudinal vegetation distribution is proposed; based on three vegetation belts: montane; subandine and andine. A remarkable similarity can be noticed between the montane plant communities and those corresponding to the central lower valleys. In addition; the influence of geomorphological processes on plant life and its distribution is presented. Finally; a case study in the highlands of the Andes; Santiago de Chile; is discussed.

    [fr] Comme tous les systèmes de montagne du monde; les Andes du Chili Central présentent une identité phytoécologique; qui se manifeste par l'action des conditions écologiques très particulières et par la présence de groupements végétaux qui montrent une individualité par rapport à ces caractères structurels et fonctionels; résultant de l'adaptation des plantes aux effets de l'altitude; avec des conditions climatiques difficiles; mais pourtant avec la possibilité de profiter des reserves du sol en eau. Dans ces montagnes on a établi une zonation en altitude; et on peut distinguer trois étages: montagnard; subandin et andin. Les seuils altimétriques des étages changent selon les versants; mais tous présentent une certaine richesse d'espèces endémiques. Cependant on remarque les ressemblances floristiques de l'étage montagnard avec les vallées centrales du pays. On présente aussi un aperçu des effets de la dynamique agressive des processus géomorphologiques de montagne sur la vie des plantes; avec une étude de cas dans les

  17. Electric generator overhaul of the Ing. Carlos Ramirez Ulloa hydroelectric. Central project conclusions; Rehabilitacion de los generadores de la central hidroelectrica Ing. Carlos Ramirez Ulloa. Conclusiones del proyecto

    Energy Technology Data Exchange (ETDEWEB)

    Campuzano Martinez, Ignacio Roberto; Gonzalez Vazquez, Alejandro Esteban; Robles Pimentel, Edgar Guillermo; Esparza Saucedo, Marcos; Garcia Martinez, Javier; Sanchez Flores, Ernesto; Martinez Romero, Jose Luis [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1998-12-31

    The Hydroelectric Ing. Carlos Ramirez Ulloa Power Central has three 200 MW electric generators. The Central initiated its commercial operation in 1985. The electric generators had design problems that were properly corrected in an overhaul program that was initiated in 1996, with Unit 2 electric generator and completed in 1998 with Unit 1 electric generator. This paper presents the relevant aspects of the experience accumulated in the project. [Espanol] La central hidroelectrica Ing. Carlos Ramirez Ulloa cuenta con tres generadores de 200 MW cada uno. La central inicio su operacion comercial en 1985. Los generadores tenian problemas de diseno que fueron debidamente corregidos en un programa de rehabilitacion que inicio en 1996, con el generador de la unidad 2, y culmino en 1998 con el generador de la unidad 1. En este articulo se presentan los aspectos relevantes de la experiencia acumulada en el proyecto.

  18. Central Bank independence in Latin America La independencia de la Banca Central en América Latina

    Directory of Open Access Journals (Sweden)

    Junguito Bonnet Roberto

    1996-06-01

    Full Text Available This article describes the origin and evolution of the central banks of Argentina, Brazil, Chile, Colombia, Mexico, and Venezuela, and analyzes their respective institutional structures. It also studies the contribution of the central bank to stabilization and the problems for maintaining this independence into the future.Este artículo describe el origen y la evolución de los Bancos Centrales de Argentina, Brasil, Chile, Colombia, México y Venezuela, y analiza sus respectivas estructruras institucionales. También estudia la contribución de la banca central a la estabilización y los problemas para que esta independencia se mantenga en el futuro.

  19. Study of metrologic characteristics in activimeters used in Nuclear Medicine Centers in Colombia; Estudio de caracteristicas metrologicas en activimetros utilizados en centros de Medicina Nuclear de Colombia

    Energy Technology Data Exchange (ETDEWEB)

    Davila, Hernan Olaya; Flores, Guillermo, E-mail: holayadavila@gmail.com [Instituto Colombiano de Geologia y Mineria (INGEOMINAS), Bogota, D.C. (Colombia). Laboratorio de Metrologia de las Radiaciones del Servicio Geologico Colombiano; Cantillo, Juliana I.P., E-mail: julianacantillo5@gmail.com [Universidad Pedagogica y Tecnologica de Colombia, Boyaca (Colombia)

    2013-07-01

    In our country currently there is a legislation that regulated de Nuclear Medicine practice, that establish the criteria about quality assurance in Nuclear Medicine and the justification to imparted to medical exposures. In this work includes some tests to the clinical approval in this type of instruments before to be used. The type of tests are linearity, geometric dependence and the energetic response and moreover to evaluate the total uncertainty during the work the physician using this equipment with radioactive sources. (author)

  20. Benchmarking de la banca central en América Latina, 1990-2010

    Directory of Open Access Journals (Sweden)

    Germán Alarco Tosoni

    2013-01-01

    Full Text Available Se desarrolla un análisis de benchmarking de la eficacia de la banca central en América Latina en 1990-2010. Con tal objetivo se consideran las funciones principales y secundarias de la autoridad monetaria en los países considerados, luego de analizar brevemente la evolución de las prácticas de los banqueros centrales internacionales. Se seleccionan, especifican y ponderan los indicadores pertinentes para evaluar el desempeño de estas instituciones: menor inflación, mayor disponibilidad de crédito al sector privado, menores márgenes de intermediación financiera, menor variabilidad del tipo de cambio real y diversos objetivos para las reservas internacionales. Se establecen funciones objetivo, que se miden con la información oficial disponible. Por último, se establece un ordenamiento de los bancos centrales considerando los indicadores y funciones objetivo seleccionadas.

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

    CERN Document Server

    Helenius, Ilkka; Eskola, Kari J

    2016-01-01

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

  2. TRANSLOCACION NUCLEAR DE LA ISOFORMA HEPATICA DE FRUCTOSA 1,6-BISFOSFATASA

    OpenAIRE

    BERTINAT, ROMINA PAOLA

    2010-01-01

    El hígado cumple una función clave en la homeostasis de la glucosa. Gluconeogénesis es la vía metabólica encargada de la producción endógena de glucosa y es regulada a nivel de 3 enzimas que catalizan reacciones irreversibles, entre ellas fructosa 1,6-bisfosfatasa (FBPasa), cuya actividad es modulada por los inhibidores AMP y f2,6Pz. Glucosa e insulina inducen la concentración nuclear de FBPasa en hepatocitos aislados de rata; sin embargo, FBPasa de hígado de rata poseé 25 residuos extra en s...

  3. Biblioteca de la Universidad Central de San Diego - California (EE. UU.

    Directory of Open Access Journals (Sweden)

    William L. Pereira y Asociados, Arquitectos

    1972-09-01

    Full Text Available This building, which is an original and daring design, consists of five floors and is sphere shaped. It is in the central square of the campus with magnificent views in all directions. It is anticipated that there will be room for 700,000 volumes and about 1,250 students. And in the near future, with easy extensions, these figures will be tripled. The central nucleus and the concrete columns constitute the vertical structure, from which the beams which support the floors extend. The majority of these elements have been left exposed.El edificio, de original y atrevido diseño, consta de cinco plantas y presenta forma esférica, estando emplazado en la plaza central del «campus», con magníficas vistas hacia todas las direcciones. La capacidad prevista es de 700.000 volúmenes, que pueden ser consultados por unos 1.250 estudiantes. En un futuro previsible, y con auxilio de fáciles ampliaciones, pueden llegarse a triplicar las cifras citadas. El núcleo central y los pilares de hormigón constituyen la estructura vertical, desde la que se extienden las vigas que soportan las plantas. La mayor parte de estos elementos se han dejado vistos.

  4. Las encuadernaciones mudéjares toledanas con motivo central de la catedral de Toledo

    Directory of Open Access Journals (Sweden)

    Carpallo Bautista, Antonio

    2012-12-01

    Full Text Available The Capitular Library of Toledo Cathedral has among its collection a group of Mudejar bindings with decorative central motives realized by craftsmen during the 15th century. This work indicates the existence of different workshops that realized orders for the cathedral by means of the study of the decorative structures of the boards and spines, the individual decorative elements used, the construction and decoration of the headbands, the metallic and embroidered clasps, as well as the identifi cation of the heraldic emblems that appear on the fi rst folios of the volumes.

    La Biblioteca Capitular de la Catedral de Toledo dispone entre sus fondos de un grupo de encuadernaciones mudéjares con motivos decorativos centrales realizadas por artesanos durante el siglo XV. Este trabajo nos señala la existencia de diferentes talleres que realizaron encargos para la catedral mediante el estudio de las estructuras decorativas de las tapas y lomos, los elementos decorativos individuales empleados, la construcción y decoración de las cabezadas, los broches metálicos y bordados, así como la identifi cación de los emblemas heráldicos que aparecen en los primeros folios de los volúmenes.

  5. INB 40 OSIRIS and ISIS reactors: complementary safety evaluation in the light of the Fukushima Daiichi nuclear power station accident; INB 40 reacteurs OSIRIS et ISIS evaluation complementaire de la surete au regard de l'accident servenu a la centrale nucleaire de Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This report proposes a complementary safety evaluation of the Osiris and Isis reactors (INB 40) in Saclay, one of the French basic nuclear installations (BNI, in French INB) in the light of the Fukushima accident. This evaluation takes the following risks into account: risks of flooding, earthquake, loss of power supply and loss of cooling, in addition to operational management of accident situations. It presents some characteristics of the installation (brief description, buildings, effluents, control-command, radioprotection), identifies the risks of cliff effect and the main structures and equipment, evaluates the seismic risk (installation sizing, installation conformity, margin evaluation), evaluates the flooding risk (installation sizing, installation conformity, margin evaluation), briefly examines other extreme natural phenomena (extreme events, combination of events, earthquake or flooding with a higher level than that for which the installation is designed, measures to prevent a cliff effect). It analyzes the risk of a loss of power supply and of cooling (loss of external and internal electric sources, loss of the ultimate cooling system). It analyzes the management of severe accidents: crisis management organization, training and exercises, available intervention means, robustness of available means, measures for the protection of the confinement integrity after fuel damage. It discusses the conditions of the use of subcontractors

  6. The Jules Horowitz reactor: complementary safety evaluation in the light of the Fukushima 1 nuclear power station accident; Reacteur Jules Horowitz evaluation complementaire de la surete au regard de l'accident servenu a la centrale nucleaire de Fukushima 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This report proposes a complementary safety evaluation of the Jules Horowitz reactor in Cadarache (INB 172), one of the French basic nuclear installations (BNI, in French INB) in the light of the Fukushima accident. This evaluation takes the following risks into account: risks of flooding, earthquake, loss of power supply and loss of cooling, in addition to operational management of accident situations. It presents the main characteristics of the installation, identifies the risks of a cliff effect and the main structures and equipment, evaluates the seismic risk (installation sizing, installation conformity, margin evaluation), evaluates the flooding risk (installation sizing, installation conformity, margin evaluation), briefly examines other extreme natural phenomena (extreme meteorological conditions related to flooding, earthquake or flooding with a higher level than that for which the installation is designed). It analyzes the risk of a loss of power supply and of cooling (loss of external and internal electric sources, loss of the ultimate cooling system). It analyzes the management of severe accidents: crisis management organization, available intervention means, robustness of available means. It discusses the conditions of the use of subcontractors

  7. The Nuclear and Safety Council and the Nuclear Energy Agency; El Consejo de Seguridad Nuclear y la Agencia de Energia Nuclear. Una estrecha colaboracion

    Energy Technology Data Exchange (ETDEWEB)

    Martinez Ten, C.

    2008-07-01

    On the occasion of the fiftieth anniversary of creation of the Nuclear Energy Agency (NEA), specialised agency within the Organisation for Economic Cooperation and Development (OECD), the President of the Spanish Nuclear Safety Council (CSN), summarizes the activities of the NEA throughout its life up to now. Since it started up, the CSN has worked closely with this international organization, as a reflection of the strong commitment, shared by both institutions, each one in its field, to reach the highest levels in the regulation which contributes decisively to the nuclear safety of the Spanish nuclear power plants. (Author)

  8. Nuclear program of Iran. Towards de-escalation of a nuclear crisis. Advisory letter; Nucleair programma van Iran. Naar de-escalatie van een nucleaire crisis. Briefadvies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-04-15

    The Dutch government, partly at the request of the House of Representatives (Second Chamber), the AIV asked to give an opinion about the position of Iran in the region and the role of the nuclear program of Iran in the geopolitical relations, in view of the most recent developments [Dutch] De Nederlandse regering heeft, mede op verzoek van de Tweede Kamer der Staten-Generaal, de AIV gevraagd advies uit te brengen over de positie van Iran in de regio en de rol van het nucleaire programma van Iran in de geopolitieke verhoudingen hierin, mede gelet op de meest recente ontwikkelingen.

  9. Puberdade precoce central como única manifestação de cisto aracnoide supraselar Central precocious puberty as a sole manifestation of suprasellar arachnoid cyst

    Directory of Open Access Journals (Sweden)

    Adriana Mangue E. Aun

    2011-03-01

    Full Text Available OBJETIVO: Os cistos aracnoides são achados raros. Em 10% dos casos, sua localização é supraselar e ocorrem quase exclusivamente em crianças. Em geral, apresentam manifestações neurológicas e visuais, sendo incomum a puberdade precoce central como sinal clínico de sua presença. DESCRIÇÃO DO CASO: Menina avaliada aos dois anos e sete meses por telarca iniciada com um ano e oito meses e pubarca e axilarca com dois anos, com aumento da velocidade de crescimento (13cm/ano e da idade óssea (sete anos e um mês. Ao exame, apresentou peso de 22,6kg (Z+4,0, estatura de 106cm (Z+3,5 e Tanner de M3P2. Exames realizados: teste de estímulo com GnRH (LH basal 8,3 UI/L, pico aos 30 minutos 94,3 UI/L; FSH basal=10,1 UI/L, pico aos 30 minutos 29,5 UI/L, ressonância nuclear magnética de crânio com cisto aracnoide supraselar e demais testes de função hipofisária normais. Foi iniciado tratamento com análogo de GnRH. Atualmente, aos quatro anos e três meses com estadio puberal M3P2, velocidade de crescimento e desenvolvimento neuropsicomotor normais para a idade. COMENTÁRIOS: A puberdade precoce central pode ser manifestação única de um cisto aracnoide, sendo essenciais o diagnóstico e o tratamento precoces, além de seguimento prolongado, uma vez que outras disfunções hipofisárias podem ocorrer tardiamente.OBJECTIVE: Arachnoid cysts (AC are a rare finding; 10% of them are suprasellar and occur almost exclusively in children. They are frequently associated with neurological and visual manifestations. Central precocious puberty as a sole manifestation is uncommon. CASE DESCRIPTION: Girl evaluated at the age of two years and seven months. She started breast development at the age of one year and eight months, pubic and axillary hair at the age of two years, with growth velocity acceleration (13cm/year and increased bone age (seven years and one month. On exam: weight: 22.6kg (Z+4.0, height: 106cm (Z+3.5 and puberal stage of B3P2. The Gn

  10. Thermal analysis of the heat recuperator of a combined cycle thermoelectric central; Analisis termico del recuperador de calor de una central termoelectrica de ciclo combinado

    Energy Technology Data Exchange (ETDEWEB)

    Romero Paredes, Hernando; Sanchez, I.; Lazcano, L. C.; Ambriz, Juan Jose; Alvarez, M. [Universidad Autonoma Metropolitana-Iztapalapa, Mexico, D. F. (Mexico); Gonzalez, O. [Comision Federal de Electricidad, Tula (Mexico)

    1996-12-31

    The thermoelectric centrals of the combined cycle type (Brayton Cycle and Rankine Cycle) present a series of opportunities to increase the efficiency of the combined cycle or of the generated power. This paper shows the methodology for the performance of energy balances in a heat recuperator (H. R.), typically employed in the combined cycle stations operating in Mexico, for the assessment of the energy harnessing in the different sections conforming a H. R. The effect of the installation of evaporative coolers and/or an absorption cooling system at the gas turbine compressor intake on the steam generation in the heat recuperator, is evaluated. This extra generation of steam is quantified for its potential use in the same absorption refrigeration system. From the assessment, it follows up that the steam generation in the H.R. is inversely proportional to the ambient temperature and that, although the increased amount of steam generated can not be harnessed in total by the steam turbine, the remaining fraction is good enough to cover the heat demand for the operation of the refrigeration system. [Espanol] Las centrales termoelectricas del tipo ciclo combinado (ciclo Brayton y ciclo Rankine) presentan un conjunto de oportunidades para incrementar la eficiencia del ciclo combinado o bien la potencia generada. En el presente trabajo se expone la metodologia para realizar los balances de energia en un recuperador de calor (R.C.) tipicamente utilizado en las Centrales de Ciclo Combinado (CCC) que operan en Mexico, para evaluar el aprovechamiento de la energia en las diferentes secciones que conforman un R.C. Se evalua el efecto que tiene la instalacion de enfriadores evaporativos y/o un sistema de enfriamiento por absorcion en la succion del compresor de la turbina de gas sobre la generacion de vapor en el recuperador de calor. Se cuantifica esta generacion extra de vapor para su posible utilizacion en el mismo sistema de refrigeracion por absorcion. De la evaluacion se

  11. Instantánea de los cánceres de cerebro y del sistema nervioso central

    Science.gov (United States)

    Información sobre las tendencias de incidencia, mortalidad y financiamiento del NCI sobre los cánceres de cerebro y del sistema nervioso central; así como ejemplos de actividades del NCI y adelantos en la investigación de estos tipos de cáncer.

  12. FLUJOS DE PODER Y PODER DE LOS FLUJOS: ANÁLISIS DE UNA FÓRMULA CENTRAL DE MANUEL CASTELLS

    Directory of Open Access Journals (Sweden)

    Esteban Torres

    2015-06-01

    Full Text Available En el presente artículo analizo la principal fórmula del poder de Manuel Castells asociada con su noción de flujo, y una de las piezas centrales de su teoría sociológica del poder a partir de 1986: el vínculo entre flujos del poder y poder de los flujos. Se trata de una forma conceptual no definida por el autor, llamativamente críptica e inasible, a la vez que absolutamente clave para la comprensión de su visión contemporánea del poder y del Estado. El estudio permite descubrir, entre otros aspectos, la relación que finalmente propone el sociólogo español entre economía y política. De tal vínculo se desprende una versión en extremo radical de la tesis del declive irreversible del poder del Estado-nación, aún vigente en la teoría social contemporánea pase a los cambios sociopolíticos registrados en América Latina en los últimos años. 

  13. Plant endemics to Sierra de Gredos (central Spain: taxonomic, distributional, and evolutionary aspects

    Directory of Open Access Journals (Sweden)

    García, Bernardo

    2008-12-01

    Full Text Available Causes related to a low number of endemics to Sierra de Gredos (central Iberian Peninsula are poorly understood. Taxonomic, distributional and genetic aspects of the 12 endemic taxa (species and subspecies are herein discussed. New populations found in the last years provide new chorological reports and taxa to science. As a result, we extend the distribution range of Pseudomisopates rivas-martinezii and describe a new subspecies (Teucrium oxylepis subsp. Gredense. Genetic variation was investigated by sequencing the ITS (Internal Transcribed Sequence region, which is a widespread nuclear DNA region used to detect significant sequence divergence at the species and population levels. At the species level, only eight endemics to this large mountain range (c. 4,800 km2 indicates both limited speciation events coupled with their persistence, despite the high species richness of the flora of Sierra de Gredos (>2,500. According to the levels of ITS sequence divergence, significant isolation processes may have predated the Quaternary in Sierra de Gredos to account for divergence of the monotypic genus Pseudomisopates from its closest relatives (Misopates, Acanthorrhinum. Isolation of the other seven endemic species from their closest relatives has been a more recent process, as revealed by the limited ITS sequence variation obtained in this study. At the population level, no net nucleotide substitutions were observed between distant populations of the endemic species: Antirrhinum grosii, Astragalus devesae, Centaurea avilae, Dianthus gredensis, Echinospartum barnadesii, Pseudomisopates rivas-martinezii, Santolina oblongifolia. In contrast, the three populations of Sedum lagascae displayed a relatively high number (4 of nucleotide substitutions. These results, together with limited morphological differentiation, may reflect insufficient population isolation of seven of the eight endemic species of Sierra de Gredos in the Quaternary. Recurrent population

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-01-31

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

  15. Factores que inciden sobre el tiempo de permanencia de un catéter endovenoso central

    Directory of Open Access Journals (Sweden)

    H. Bello-Villalobos

    Full Text Available Objetivo: Determinar los factores que inciden en el tiempo de permanencia de un catéter endovenoso central. Antecedentes: En el paciente con cáncer existen factores propios del estado de inmunocompromiso por el tumor y los efectos colaterales de su tratamiento que aumentan la probabilidad de infección y consecuentemente reducen el tiempo de uso de un catéter. Sujetos: Se integró una cohorte de 306 pacientes con cáncer, con una edad promedio de 59 ± 14,5 años. Intervenciones: Se definió tiempo cero como el día de colocación del catéter. Diariamente se buscaron signos clínicos de infección por catéter, con toma de hemocultivos simultáneos cada 7 días. El desenlace primario fue infección del catéter y el alternativo fin de tratamiento, obstrucción o fallecimiento del paciente. Se comparó el tiempo de permanencia del catéter infectado vs no infectado y su relación con factores de riesgo potenciales. Resultados: Se colocaron 306 catéteres para un total de 4.043 días/catéter. Se infectaron 25 (8,2%. La sobrevida media global fue de 50 días. Se encontró que a mayor tiempo de permanencia, mayor fue la incidencia de infección. En el análisis de sobrevida ajustado, la presencia de infección a distancia (OR = 4,71, IC95% = 1,7-10,1, p = 0,002 fue el factor que mostró una asociación significativa. Conclusiones: El tiempo de vida útil de un catéter es amplia, limitada por la presencia de infección a distancia como factor de riesgo potencial de infección por catéter.

  16. Generating power stations and optimization energetic of processes; Centrales generadoras y optimacion energetica de procesos

    Energy Technology Data Exchange (ETDEWEB)

    Gutierrez Ramirez, Ranulfo; Fernandez Montiel, Manuel Francisco [Instituto de Investigaciones Electricas, Temixco, Morelos (Mexico)

    1999-07-01

    Some recent experiences of the Management of Thermal Processes of the Instituto de Investigaciones Electricas (IIE) related to the works on generating power stations of electricity, plants of cogeneration and energy saving are presented. [Spanish] Se presentan algunas experiencias recientes de la Gerencia de Procesos Termicos del Instituto de Investigaciones Electricas (IIE) relacionadas con los trabajos sobre centrales generadoras de electricidad, plantas de cogeneracion y ahorro de energia.

  17. Los mamíferos marinos en la costa central de Oaxaca Marine mammals along the central coast of Oaxaca

    Directory of Open Access Journals (Sweden)

    Juan Meraz

    2008-06-01

    Full Text Available Con la finalidad de conocer las especies de mamíferos marinos que se encuentran en la costa central de Oaxaca, se elaboró un listado comentando las características de los registros obtenidos. Se incluyeron las observaciones hechas a lo largo de 30 recorridos por mar, entre junio de 1999 y enero de 2004, realizadas entre las bahías de Huatulco y la playa de La Escobilla. Adicionalmente se incluyeron registros de animales varados, así como observaciones realizadas desde la costa. Se presentan comentarios sobre el registro de 8 especies en la zona, incluyendo las localidades y fechas de los avistamientos. Stenella attenuata es la especie más abundante, y la zona de Zipolite-Isla Roca Blanca la localidad con el mayor número de avistamientos. Dado el crecimiento turístico del lugar, es importante contar con este tipo de registros ya que es poco lo que se sabe sobre estas especies en esta porción de la costa oaxaqueña.With the aim of documenting the species of marine mammals that occur along the central coast of Oaxaca, a list with the characteristics of the records was elaborated based on observations made throughout 30 surveys from Huatulco Bays to La Escobilla beach between June 1999 and January 2004. Additional records from stranded animals are included, as well observations from the coast. Comments on 8 species are presented, including localities and dates of sightings. Stenella attenuata is the most abundant species. Zipolite-Roca Blanca island was the locality with the highest number of sightings. This records are important to promote conservation due growth of tourism in the area, given that Oaxaca coast is poorly known regarding marine mammals.

  18. Analizan partículas calientes del accidente nuclear de Palomares

    OpenAIRE

    2012-01-01

    Investigadores pertenecientes al Centro Nacional de Aceleradores, CNA, (Universidad de Sevilla-Junta de Andalucía-CSIC) en colaboración con la Organización Internacional de la Energía Atómica (IAEA), han llevado a cabo me didas de elementos transuránicos en partículas calientes procedentes de accidentes nucleares tales como el de Thule (Groenlandia) o Palomares (España).

  19. La colección de tesis doctorales de Derecho en la Universidad Central: 1847-1868

    OpenAIRE

    Miguel Alonso, Aurora; Calderón Rehecho, Antonio

    2009-01-01

    Este trabajo presenta el catálogo de tesis defendidas en la Facultad de Derecho de la Universidad Central de Madrid (ahora Universidad Complutense de Madrid) entre los años 1847 a 1868. Inicia la publicación del catálogo de tesis de derecho defendidas en este Facultad durante el siglo XIX. El listado se organiza por fecha de lectura, apellidos y nombre del doctor, e índices de autores y materias. La organización cronológica permitirá al investigador el seguimiento de la evolución de esta cien...

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

    OpenAIRE

    Arista, José

    1989-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

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

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

    Directory of Open Access Journals (Sweden)

    Raupach Michael J

    2010-09-01

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

  3. Direct reading spectrochemical analysis of nuclear graphite; Analisis espectroquimico de lectura directa de grafito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Roca Adell, M.; Becerro Ruiz, E.; Alvarez Gonzalez, F.

    1964-07-01

    A description is given about the application of a direct-reading spectrometer the Quantometer, to the determination of boron. calcium, iron, titanium and vanadium in nuclear grade graphite. for boron the powdered sample is mixed with 1% cupric fluoride and excited in a 10-amperes direct current arc and graphite electrodes with a crater 7 mm wide and 10 mm deep. For the other elements a smaller crater has been used and dilution with a number of matrices has been investigated; the best results are achieved by employing 25% cupric fluoride. The sensitivity limit for boron is 0,15 ppm. (Author) 21 refs.

  4. Chapter 2: selection process for nuclear sites; Capitulo 2: processo de selecao de sitios nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Atala, Drausio Lima

    2009-07-01

    The five criteria of a selection process will be discussed as follows: 1) Structure of the site selection procedure: functional stages required for discrimination from the interest region to installation license. 2) Selection criteria incorporating the nuclear regulatory, environmental and installation project requirements that should be considered in the selection process. 3) Quantification criterion: quantification of relative adequacy of a site related to selection criterion. 4) Weighing factor: weighing factor development reflecting the relative importance of individual criteria incorporating the interest composition among criterion. 5) Public involvement: development of a process integrating information and public enrollment participation.

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

    Science.gov (United States)

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

    2004-01-01

    The Inilchek Glacier, located in the Tien Shan Mountains, central Asia, is unique among mid-latitude glaciers because of its relatively large average annual accumulation. In July 2000, two ice cores of 162 and 167 meters (m) in length were collected from the Inilchek Glacier for (chlorine-36) 36Cl analysis a part of a collaborative international effort to study the environmental changes archived in mid-latitude glaciers worldwide. The average annual precipitation at the collection site was calculated to be 1.6 m. In contrast, the reported average annual accumulations at the high-latitude Dye-3 glacial site, Greenland, the mid-latitude Guliya Ice Cap, China, and the mid-latitude Upper Fremont Glacier, Wyoming, USA, were 0.52, 0.16 and 0.76 m, respectively. The resolution of the 36Cl record in one of the Inilchek ice cores was from 2 to 10 times higher than the resolution of the records at these other sites and could provide an opportunity for detailed study of environmental changes that have occurred over the past 150 years. Despite the differences in accumulation among these various glacial sites, the 36Cl profile and peak concentrations for the Inilchek ice core were remarkably similar in shape and magnitude to those for ice cores from these other sites. The 36Cl peak concentration from 1958, the year during the mid-1900s nuclear-weapons-tests period when 36Cl fallout was largest, was preserved in the Inilchek core at a depth of 90.56 m below the surface of the glacier (74.14-m-depth water equivalent) at a concentration of 7.7 ?? 105 atoms of 36Cl/gram (g) of ice. Peak 36Cl concentrations from Dye-3, Guliya and the Upper Fremont glacial sites were 7.1 ?? 105, 5.4 ?? 105 and 0.7 ?? 105 atoms of 36Cl/g of ice, respectively. Measurements of 36Cl preserved in ice cores improve estimates of historical worldwide atmospheric deposition of this isotope and allow the sources of 36Cl in ground water to be better identified. ?? 2004 Published by Elsevier B.V.

  6. Egresados y tesis 1960-2005, Escuela de Geografía de la Facultad de Humanidades y Educación, Universidad Central de Venezuela

    Directory of Open Access Journals (Sweden)

    José Manuel Guevara

    2005-01-01

    Full Text Available Este trabajo es una contribución al conocimiento de las aportaciones de los egresados de la Escuela de Geografía y tiene un doble propósito: por un lado, presentar los nombres y fecha de graduación de los 1030 egresados de la Escuela de Geografía de la Universidad Central de Venezuela, desde su fundación, las tesis de grado elaboradas por los 923 egresados de la Escuela de Geografía entre 1972 y 2005, y por el otro, destacar la importancia del Trabajo Especial de Grado (TEG como culminación del proceso formativo con el cual los estudiantes dan a luz su primera creación intelectual de significación, bajo la orientación de un tutor. Los nombres de los egresados y su fecha de egreso se cotejó con la obra de la secretaría de la Universidad "Egresados de la Universidad Central de Venezuela, 1725-1995" y continuada de 1996 al 2003; y con los libros de firmas de los actos de graduación que lleva la secretaría de la universidad para garantizar la fidelidad de la información. Como recomendación, se exhorta a las autoridades de la Escuela a que este trabajo se actualice anualmente para lo cual se requiere llevar un libro donde se registren los nombres de tesis y fecha de egreso del estudiante y que tal lista le sea entregada a cada uno de los graduando en el acto de imposición de medallas, tal como era realizado de 1980 a1986 en la Facultad.

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

    OpenAIRE

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

    2013-01-01

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

  8. Heat transfer equipment performance diagnosis of auxiliary systems in electric power stations; Diagnostico de comportamiento de equipo de transferencia de calor de sistemas auxiliares de centrales termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz Esparza Gutierrez, Rogelio [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1990-12-31

    In this article the methodology followed to diagnose the performance of the equipment where heat is transferred from the feed water, condensate and circulation water systems in fossil power plants (FPP). The data collection is made with the unit in normal operation, using local instrumentation without taking the equipment out of service for its installation. The equipment diagnosis is made through the analysis of the collected data in actual operation and the design data; for this purpose a thermal balance of the interested systems is performed to obtain all the conditions an operation data. Later on the performance indicative parameters (PIP) of actual operation and design are calculated and compared one against the other. Such a comparison reveals the performance deterioration and the possible equipment faults. The data obtained and the supplementary information are stored in a data base whose objective is that Comision Federal de Electricidad has on hand a prompt access to them in order to control the performance, compare them among similar units and power stations, and inclusively verify possible recurrent causes of low availability in the referred systems. [Espanol] En este articulo se presenta la metodologia seguida para diagnosticar el comportamiento de equipos en los que se transfiere calor de los sistemas de agua de alimentacion, condensado y circulacion de las centrales termoelectricas (CTE). La toma de datos se realiza con la unidad en operacion normal, utilizando instrumentacion local sin necesidad de sacar de servicio a los equipos para su instalacion, ya que se ocupan los mismos puntos para instrumentos con que cuentan por diseno. El diagnostico de los equipos se realiza mediante el analisis de los datos recopilados, tanto de operacion real como de diseno; para ello, se efectua un balance termico de los sistemas de interes para obtener todas las condiciones y los datos de operacion. Posteriormente, se calculan los parametros indicativos de

  9. Criterios sobre la uniformidad de riego en cultivos protegidos de las provincias centrales

    Directory of Open Access Journals (Sweden)

    Miriel Ajete Gil

    2011-01-01

    Full Text Available El presente trabajo tiene como objetivo evaluar aspectos técnicos en sistemas de riego de las provincias centrales del país pertenecientes al Programa de Cultivos Protegidos del MINAG. A partir de la puesta en explotación de los primeros módulos comienzan a presentarse deficiencias en la uniformidad del riego. En las casas de posturas, en Camagüey se ensayó una solución alternativa utilizando el emisor bailarina con resultados preliminares aceptables, experiencia que se extendió posteriormente a otros módulos. Además se realizaron evaluaciones de uniformidad del riego en cuatro provincias, los resultados ratifican la calidad del riego por goteo con el emisor Twin Drip utilizado en cultivos protegidos, mientras en las casas de posturas con el emisor microjet de 2 x 1400 de 1 mm de producción nacional los resultados fueron ineficientes, y con el emisor "bailarina" fueron aceptables.

  10. Cuidando desde la central de estirilización al cliente interno y externo

    OpenAIRE

    2012-01-01

    A partir del concepto de cuidado, pretendo mostrar la importancia que representa la labor de enfermería en la central de esterilización, lugar desde el cual, en forma muy silenciosa, se realizan acciones que sin discusión alguna garantizan el éxito de los diferentes procedimientos que se realizan por parte del equipo de salud relacionados con la técnica aséptica.La complejidad de la Central de Esterilización es tal, que puede ser comparada con una gran industria, en la cual se encuentran una ...

  11. Evaluacion del componente central y periferico de fatiga muscular en pacientes neuropaticos y miopaticos

    OpenAIRE

    Cohen, L.G.; Marcela E. Panizza; Olga P. Sanz; Schutz,Carlos G.; R. Rey

    1983-01-01

    Utilizando un método de cuantificación del electromiograma, se investigaron parte de los mecanismos centrales y periféricos responsables de la fatiga muscular en enfermos crónicamente denervados y en pacientes con compromiso muscular primitivo. Se observó en los denervados que los mecanismos de fatiga muscular, no difieren mayormente de los observados en el grupo de sujetos sanos, por el contrario, en los miopáticos a más del componente central, existen otros de orden periférico, tales como l...

  12. Empleo de paneles compuestos por subproductos de centrales térmicas en fachadas trasdosadas

    Directory of Open Access Journals (Sweden)

    Alba, M. D.

    2012-06-01

    Full Text Available Two new recycled gypsum boards are proposed which have a better environmental performance due to the fact that they are made of traditional materials and new recycled ones derived from biomass (waste generated during the extraction of olive pomace and the coal combustion produced in power plants. Before using these wastes as raw materials, they have been submitted to chemical analysis and the panels made of them have been tested to prove their mechanical, thermal and fire performance. Subsequently, the new recycled panels have been implemented in a traditional facade solution to verify their functional and thermal feasibility. Finally, the results obtained show that the panels made of biomass ashes have a better mechanical and thermal performance than those made of coal ashes and that they can provide a sustainable alternative to the traditional facade materials due to its lower environmental impact based on the reduction of raw materials consumption and industrial waste. The new materials comply with the specifications of Spanish Technical Building Code in the region evaluated

    Se presentan dos nuevas tipologías de paneles para trasdosado de fachadas, que proporcionan como mejora ambiental la combinación de materiales tradicionales con nuevos materiales reciclados obtenidos de residuos procedentes de la combustión de orujillo y de carbón en centrales térmicas. Con anterioridad a su uso, dichos residuos han sido sometidos a exhaustivos ensayos químicos y los paneles fabricados a partir de los mismos, a ensayos mecánicos, térmicos y de resistencia al fuego que justifican su empleo. Posteriormente, los nuevos paneles hechos a base de materiales reciclados se han implementado como trasdosado de una solución de fachada convencional para verificar su viabilidad funcional y el buen comportamiento aislante del conjunto. Finalmente, de los resultados obtenidos se extrae que los paneles fabricados con cenizas de orujillo tienen un mejor

  13. Criticality calculation of the nuclear material warehouse of the ININ; Calculo de criticidad del almacen del material nuclear del ININ

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, T.; Angeles, A.; Flores C, J., E-mail: teodoro.garcia@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    In this work the conditions of nuclear safety were determined as much in normal conditions as in the accident event of the nuclear fuel warehouse of the reactor TRIGA Mark III of the Instituto Nacional de Investigaciones Nucleares (ININ). The warehouse contains standard fuel elements Leu - 8.5/20, a control rod with follower of standard fuel type Leu - 8.5/20, fuel elements Leu - 30/20, and the reactor fuel Sur-100. To check the subcritical state of the warehouse the effective multiplication factor (keff) was calculated. The keff calculation was carried out with the code MCNPX. (Author)

  14. Desenvolvimento de um espectrômetro nuclear digital de radiação gama.

    OpenAIRE

    Rafael Valadares Leite

    2006-01-01

    O método nuclear gamaespectrométrico vem ganhando espaço em diversas aplicações como fornecer a informação médica em um paciente ou de uma galáxia distante, detectar radioatividade para fins de segurança e medir a concentração de radioelementos em um mineral ou rocha. Esta dissertação apresenta um projeto e implementação de um espectrômetro gama digital conectado a um conjunto detector contendo cristal cintilador de iodeto de sódio dopado com tálio. O hardware é baseado em um dispositivo lógi...

  15. Sero-prevalencia de Mycoplasma gallisepticum y Mycoplasma synoviae en aves de combate del altiplano central en México

    OpenAIRE

    Martín Talavera Rojas; Celedonio Vázquez Vera; Pomposo Fernández Rosas; Agustín Horacio Peña Romero; Edgardo Soriano Vargas; Juan Martin Talavera Gonzalez

    2012-01-01

    El objetivo del presente trabajo fue determinar la prevalencia de Micoplasmosis en aves de combate en el altiplano central Mexicano. El muestreo se realizó en seis Municipios del valle de Toluca durante los meses de diciembre 2010 a mayo 2011, debido a que es la temporada de casteo en México. Se muestrearon 323 aves al azar de 29 criaderos asociados a la Federación Nacional de Criadores de Gallos de Pelea (FNCGP). Las muestras se analizaron con la prueba de aglutinación en placa para detectar...

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

    Directory of Open Access Journals (Sweden)

    Gadó János

    2014-01-01

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

  17. Galaxias espirales de núcleos activos: efecto de las barras en la actividad nuclear

    Science.gov (United States)

    Alonso, S.; Coldwell, G.

    In this work we analyze barred active galactic nuclei galaxies (AGN), in order to study the effect produced by the bars on the central black hole activity. We construct a sample of AGN galaxies with bars, classified by visual inspection, from the seventh release of Sloan Digital Sky Survey (SDSS-DR7). In addition, we construct a non-barred AGN galaxy sample with similar redshift distributions, luminosity and mass in stars than barred AGN galaxies. We present preliminary results of the effect of bars on the central nuclear activity, exploring different properties of barred spiral AGN galaxies, compared to its counterpart in non-barred galaxies. FULL TEXT IN SPANISH

  18. EL TRABAJO INVISIBLE DE MENORES DE BAZURTO. MERCADO CENTRAL DE CARTAGENA DE INDIAS

    Directory of Open Access Journals (Sweden)

    Hortensia Naizarra Rodriguez

    2000-08-01

    Full Text Available A un cuando la motivación principal del trabajo infanto juvenil sigue siendo la ayuda a la familia, hay factores de orden cultural que 10 propician. Para las familias de origen rural el trabajo infantil está relacionado con la imagen del menor como símbolo y unidad económica de producción ya que existe la creencia entre los padres que los niños son veloces, ágiles, tienen mucha destreza y voluntad para cierto tipo de trabajo, y por tanto se convierten en una ayuda; pero tras esta denominada ayuda lo que se observa es una carga de responsabilidades que deterioran física, social y emocionalmente al menor y disminuyen ostensiblemente sus opciones de desarrollo humano.

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

    Science.gov (United States)

    2013-10-01

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

  20. The role of nuclear law in nuclear safety after Fukushima; El rol del derecho nuclear en seguridad nuclear luego de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Cardozo, Diva E. Puig, E-mail: d.puig@adinet.com.uy [International Nuclear Law Association (INLA), Montevideo (Uruguay)

    2013-07-01

    The paper contains the following topics: nuclear law, origin and evolution, role of the legal instruments on nuclear safety, nuclear safety the impact of major nuclear accidents: Chernobyl and Fukushima. The response of the nuclear law post Fukushima. Safety and security. International framework for nuclear safety: nuclear convention joint convention on safety on spent fuel management and on the safety of radioactive waste management. The Fukushima World Conference on Nuclear Safety. Convention on Prompt Notification and Assistance in case of a Nuclear Accident or Radiological Emergency. Plan of Action for Nuclear Safety. IAEA recommendations for the safety transport of radioactive material. International framework for nuclear security. Convention on the Physical Protection of Nuclear Materials. International Convention for the Suppression of Acts Against Nuclear Terrorism. Resolution No. 1540 of the Security Council of United Nations (2004). Measures to strengthen international safety. Code of conduct on the safety research reactor.

  1. Las flores del desierto. Opciones de vida en pueblos de la región central de Sonora

    Directory of Open Access Journals (Sweden)

    Ma. Amalia Gracia

    2014-01-01

    Full Text Available Aunque la búsqueda de las localidades rurales por generar opciones de vida se observa en el esfuerzo de algunos pobladores, en México la política pública se restringe a ofrecer garantías sociales; le deja al mercado la creación de alternativas económicas, que no alcanzan para producir desarrollo local y regional. El presente artículo reflexiona sobre esto, a partir de una iniciativa de trabajo asociativo surgida hace más de seis años en pueblos de la región central del norte de Sonora, y muestra cómo se resuelven temporal y dinámicamente las tensiones entre prácticas de cooperación y reciprocidad y las de intercambio con el mercado utilizando postulados teóricos de distintas disciplinas, retomadas por las propuestas de economía solidaria. El caso ilustra las dificultades, riqueza y potencialidad de iniciativas como ésta, y la importancia del apoyo gubernamental en localidades a las que la baja capacidad económica y la generalización del narcotráfico las vuelve frágiles para contrarrestar procesos profundos de despoblamiento.

  2. Applications of the gas chromatography in the nuclear science and technology; Aplicaciones de la cromatografia de gases a la ciencia y tecnologia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gasco Sanchez, L.

    1972-07-01

    This paper is a review on the applications of the gas chromatography in the nuclear science and technology published up to December 1971. Its contents has been classified under the following heads; I) Radiogaschromatography, II) Isotope separation, III) Preparation of labelled molecules, IV) Nuclear fuel cycle, V) Nuclear reactor technology, VI) Irradiation chemistry, VIl) Separation of me tal compounds in gas phase, VIII) Applications of the gas chromatography carried out at the Junta de Energia Nuclear, Spain. Arapter VIII only includes the investigations carried out from January 1969 to December 1971. Previous investigations in this field has been published elsewhere. (Author)

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

    Directory of Open Access Journals (Sweden)

    Carlos Arriaga Jordán

    1999-01-01

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

  4. Temporary storage in dry of the spent nuclear fuel in the Nuclear Power Plant of Laguna Verde; Almacenamiento temporal en seco del combustible nuclear gastado en la Central Nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, N.; Vargas A, A., E-mail: natividad.hernandez@cfe.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Carretera Veracruz-Medellin Km. 7.5, 94270 Dos Bocas, Veracruz (Mexico)

    2013-10-15

    To guarantee the continuity in the operation of the two nuclear reactors of the nuclear power plant of Laguna Verde (NPP-L V) is an activity of high priority of the Comision Federal de Electricidad (CFE) in Mexico. At the present time, the CFE is working in the storage project in dry of the spent fuel with the purpose of to liberate space of the pools and to have the enlarged capacity of storage of the spent fuel that is discharged of the reactors. This work presents the storage option in dry of the spent fuel, considering that the original capacity of the spent fuel pools of the NPP-L V was of 1242 spaces each one and that in 1991, through a modification of the original design, the storage capacity was increased to 3177 spaces by pool. At present, the cells occupied by unit are of 2165 (68%) for the Unit-I and 1839 (58%) for the Unit-2, however, in 2017 and 2022 the capacity to discharge the complete core will be limited by what is required of a retirement option of spent fuel assemblies to liberate spaces. (author)

  5. La independencia de la banca central en Colombia desde 1923. Aspectos institucionales

    Directory of Open Access Journals (Sweden)

    Mauricio Avella Gómez

    2014-06-01

    Full Text Available Un aspecto invariable de las discusiones sobre banca central es el de su independencia relativa para cumplir con sus funciones tradicionales de estabilización monetaria. En el caso de Colombia, dicha controversia ha hecho parte de las iniciativas de reforma del Banco de la República desde su creación en 1923. Este artículo presenta una perspectiva histórica de las reformas institucionales del Banco con especial referencia al tema de su independencia.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-11-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  8. Análisis estructural del extremo sur de la Precordillera Central Sanjuanina

    Directory of Open Access Journals (Sweden)

    P. Giampaoli

    2003-03-01

    Full Text Available La Precordillera Central de San Juan es una faja plegada y corrida de piel fina que está limitada hacia el este por las estructuras de piel gruesa de la Precordillera Oriental. El objetivo de este estudio es describir e interpretar las estructuras encontradas en el extremo sur de esta faja plegada y corrida. Los pliegues presentes en las lomas de Andapaico son asimétricos, abiertos, de tipo chevron y están genéticamente relacionados a la propagación de una falla. Hacia el norte el pliegue es más cerrado y está fragmentado por fallas. La estructura regional consiste en un abanico imbricado de pliegues por propagación de falla y corrimientos fuera de secuencia relacionados al levantamiento de las estructuras de la Precordillera Oriental. El nivel de despegue principal está localizado cerca del techo de la caliza de la Formación San Juan. La evolución de la deformación se produjo en dos etapas. Primero se desarrolla un abanico imbricado de pliegues por propagación de falla como resultado de la migración hacia el antepaís del frente de corrimientos. Luego el levantamiento de la Precordillera Oriental impide la propagación del frente de corrimiento, lo cual pudo disparar la formación de las estructuras fuera de secuencia de la Precordillera Central. El acortamiento horizontal mínimo calculado es de 4,8 km y la estructura regional muestra una disminución del acortamiento en dirección sur que afecta a estructuras de varios órdenes y estilos de deformación.

  9. Simulation of the steady state of the Laguna Verde Nuclear power station at full power (1931 MWt and 2027 Mwt) with the SCDAPSIM code; Simulacion del estado estacionario de la Central Nucleoelectrica de Laguna Verde a plena potencia (1931 MWt y 2027 MWt) con el codigo SCDAPSIM

    Energy Technology Data Exchange (ETDEWEB)

    Amador G, R.; Nunez C, A.; Mateos, E. del A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico D.F. (Mexico)

    2001-07-01

    This document describes two models developed for the Laguna Verde Nuclear Power Station (LVNPP) using SCDAPSIM computer code. These models represent the LVNPP in normal operation with a nominal power of 1931 MWt and power uprate conditions of 2027 MWt. The steady states obtained by means of these models comply with the criteria established by the ANSI/ANS-3.5-1985 for nuclear power plant simulators. This criteria has been applied to the models of the LVNPP developed by CNSNS in want of some international accepted criteria for ''Best Estimation'' computer codes. These models will be the bases to carry out studies of validation of the own models as well as the analysis of diverse scenarios that evolve to a severe accident. (Author)

  10. Fatores de risco nas alianças em projetos de TI: estudo de casos no Banco Central do Brasil

    Directory of Open Access Journals (Sweden)

    Liana Ribeiro dos Santos

    2014-03-01

    Full Text Available Em resposta às crescentes mudanças e pressões da concorrência, número cada vez maior de empresas tem estabelecido alianças como forma de complementar seus recursos e assegurar suas vantagens competitivas. Embora essas alianças sejam uma boa opção estratégica para as empresas, existem evidências de grande taxa de fracasso. Muitos estudos têm analisado os fatores de sucesso das parcerias, mas poucos têm dado ênfase às dificuldades e à prevenção de riscos. O objetivo neste artigo consiste em apresentar os resultados de uma pesquisa em que se buscou identificar os fatores de risco que dificultam as alianças no caso de projetos de Tecnologia da Informação (TI. Trata-se de uma pesquisa exploratória, focada em cinco projetos estratégicos de TI do Banco Central do Brasil, desenvolvidos em parceria com outras instituições públicas e privadas, a maioria delas nacionais e uma estrangeira. Apesar de os projetos terem tido sucesso, foi possível identificar como principais fatores de risco: falta de planejamento da aliança, falta de negociação entre parceiros, falta de comprometimento dos parceiros e falta de apoio institucional. A pesquisa trouxe lições relevantes para o gerenciamento de projetos que podem beneficiar outras alianças em projetos de TI.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

  12. Use of hafnium in control bars of nuclear reactors; Uso de hafnio en barras de control de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

    Recently the use of hafnium as neutron absorber material in nuclear reactors has been reason of investigation by virtue of that this material has nuclear properties as to the neutrons absorption and structural that can prolong the useful life of the control mechanisms of the nuclear reactors. In this work some of those more significant hafnium properties are presented like nuclear material. Also there are presented calculations carried out with the HELIOS code for fuel cells of uranium oxide and of uranium and plutonium mixed oxides under controlled conditions with conventional bars of boron carbide and also with similar bars to which are substituted the absorbent material by metallic hafnium, the results are presented in this work. (Author)

  13. Cooling system at the compressors air inlet of the gas turbines from the Tula`s combined cycle central; Sistema de enfriamiento en la succion del compresor de las turbinas de gas de la central de ciclo combinado de Tula

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez F, Oscar [Comision Federal de Electricidad, Tula (Mexico); Romero Paredes, Hernando; Vargas, Martin; Gomez, Jose Francisco [Universidad Autonoma Metropolitana-Iztapalapa, Mexico, D. F. (Mexico)

    1996-12-31

    It has been formerly evaluated that it is possible to enhance notably the electric power generation in gas turbine power plants by cooling the air at the compressor inlet. It has been pointed out that provided a source of waste heat is available it can be very attractive the use of absorption refrigeration systems. In this paper the technical and the economical benefits of bringing the air inlet temperature down 8 Celsius degrees of the four gas turbines of the Combined Cycle Central of Tula, in the State of Hidalgo (combined cycle central-Tula) are evaluated. The results show that it is possible to achieve an efficiency enhancement of at least 1%, and that in very warm days up to 48 additional Megawatts can be generated, or about 10% of the installed capacity. The final economic result is very encouraging and an annual economical benefit in the order of 50 million pesos can be obtained and the refrigeration units can be amortized in approximately one year. [Espanol] Se ha evaluado anteriormente que es posible mejorar notablemente la capacidad de generacion electrica en plantas que utilizan turbinas de gas, mediante el enfriamiento del aire de succion del compresor. Se ha senalado que en la medida en que se encuentre disponible una fuente termica de desecho puede ser muy atractivo el uso de sistemas de refrigeracion por absorcion. En el presente trabajo se evaluan los beneficios tecnicos y economicos que puede tener el llevar el aire de succion hasta una temperatura de 8 grados Celsius, de las cuatro unidades de gas de la Central de Ciclo Combinado de Tula, Hidalgo (CCC-Tula). Los resultados muestran que es posible alcanzar un aumento en la eficiencia de al menos 1% y que se pueden generar, en dias muy calurosos, hasta 48 MW extras, equivalente al 10% de la capacidad instalada. El resultado economico final es muy alentador y puede llegar a tenerse un beneficio economico del orden de los 50 millones de pesos anuales y las unidades de refrigeracion podran pagarse en

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

    OpenAIRE

    2013-01-01

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

  15. Protocol in NORM industries. Central thermal coal production; Protocolo de actuacion en industrial NORM. Centrales de produccion termica de carbon

    Energy Technology Data Exchange (ETDEWEB)

    Robles, B.; Mora, J. C.; Corbacho, J. A.; Baeza, A.; Cancio, D.

    2011-07-01

    This protocol arises from the execution of R and D project Study of the radiological impact of coal power plants on their environment, funded by the Nuclear Safety Council. Its main objective was to assess the radiological impact exerted on workers and their environments, the four coal-fired power more currently in Spain: As Pontes (A Coruna), Compostilla II (Leon ),Litoral (Almeria) and Andorra (Teruel). (Author)

  16. Central térmica de Puente Nuevo – España (I

    Directory of Open Access Journals (Sweden)

    Sánchez Conde, Enrique

    1970-03-01

    Full Text Available The Empresa Nacional Eléctrica de Córdoba, S. A. has built near Córdoba the Puente Nuevo power station, to take advantage of the local coal, mined in the district of Peñarroya, Bélmez and Espiel, which is difficult to export. In addition to the construction difficulties which have had to be overcome, the power station is especially significant because it has been fitted with Spanish machinery, including the electrical and steam generators. This design has been followed by the construction of the power station at Almería and two additional power plants at San Juan de Dios, in Palma de Mallorca. All these installations are now in working order.La Empresa Nacional Eléctrica de Córdoba, S. A., ha montado, cerca de esta ciudad, la Central Térmica de Puente Nuevo para aprovechar los carbones de la zona Peñarroya-Bélmez-Espiel, de escasa salida en el mercado. Aparte de las dificultades constructivas que se han resuelto durante su instalación, la Central es interesante, especialmente, por el logrado intento de utilizar en ella la primera maquinaria de fabricación nacional, tanto en lo que se refiere a generadores eléctricos como a los de vapor. Se ha encabezado así el montaje de una serie que ha tenido su continuación en los dos grupos de la ampliación de la Central Térmica de Almería y en los otros dos de la Central de San Juan de Dios, de Palma de Mallorca, todos ellos funcionando en la actualidad.

  17. Neonatal mortality in intensive care units of Central Brazil Mortalidade neonatal em unidades de cuidados intensivos no Brasil Central

    Directory of Open Access Journals (Sweden)

    Claci F Weirich

    2005-10-01

    Full Text Available OBJECTIVE: To identify potential prognostic factors for neonatal mortality among newborns referred to intensive care units. METHODS: A live-birth cohort study was carried out in Goiânia, Central Brazil, from November 1999 to October 2000. Linked birth and infant death certificates were used to ascertain the cohort of live born infants. An additional active surveillance system of neonatal-based mortality was implemented. Exposure variables were collected from birth and death certificates. The outcome was survivors (n=713 and deaths (n=162 in all intensive care units in the study period. Cox's proportional hazards model was applied and a Receiver Operating Characteristic curve was used to compare the performance of statistically significant variables in the multivariable model. Adjusted mortality rates by birth weight and 5-min Apgar score were calculated for each intensive care unit. RESULTS: Low birth weight and 5-min Apgar score remained independently associated to death. Birth weight equal to 2,500g had 0.71 accuracy (95% CI: 0.65-0.77 for predicting neonatal death (sensitivity =72.2%. A wide variation in the mortality rates was found among intensive care units (9.5-48.1% and two of them remained with significant high mortality rates even after adjusting for birth weight and 5-min Apgar score. CONCLUSIONS: This study corroborates birth weight as a sensitive screening variable in surveillance programs for neonatal death and also to target intensive care units with high mortality rates for implementing preventive actions and interventions during the delivery period.OBJETIVO: Identificar fatores prognósticos de mortalidade neonatal em unidades de cuidados intensivos. MÉTODOS: Realizou-se estudo de coorte de nascidos vivos do município de Goiânia, no período de novembro de 1999 a outubro de 2000. Procedeu-se à vinculação das bases de dados das declarações de nascidos vivos e de óbitos, das quais as variáveis de exposição foram extra

  18. Paradox place by nuclear sector discourse line; Lugar de paradoxos pelos caminhos discursivos do setor nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Iona Ponce [Centro Regional de Ciencias Nucleares (CRCN), Recife, PE (Brazil)]. E-mail: iona@cnen.gov.br

    2002-07-01

    This article, taking into consideration the Critical Discourse Analysis and the French Discourse Analysis, examines the relationship between the public image and the acceptance of nuclear energy and the discourse and arguments commonly employed by the nuclear institutions, in Brazil, in favor of a widespread use of nuclear energy by the society. In doing so, the article discusses aspects such as the social memory, intertextuality and image construction and shows that the pro-nuclear arguments and the discourse produced by the institutions of the nuclear sector, in its essence, carries much of the ideas and concepts frequently utilized by the anti-nuclear entities. This fact, instead of providing a positive view, or even a correct understanding of the nuclear area, reinforces the negative image of nuclear energy witch is reflected in its public acceptance by the society. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-07-01

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

  20. Overhaul of the generator of the hydroelectric central station Ingeniero Carlos Ramirez Ulloa; Rehabilitacion del generador de la unidad 2 de la central hidroelectrica ingeniero Carlos Ramirez Ulloa

    Energy Technology Data Exchange (ETDEWEB)

    Robles Pimentel, Edgar [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Garcia Hernandez, Javier [Comision Federal de Electricidad, Mexico, D. F. (Mexico)

    1997-12-31

    In November 1995, the failure of the Unit 2 generator at the hydroelectric central station Ingeniero Carlos Ramirez Ulloa, El Caracol, occurred. The accident forced to carry out its overhaul. Here are presented the technical problems faced during the overhaul of the generator and analyzed the implemented solutions. [Espanol] En noviembre de 1995 ocurrio la falla del generador de la unidad 2 de la central hidroelectrica Ing. Carlos Ramirez Ulloa, El Caracol. El accidente obligo a llevar a cabo su rehabilitacion. Se presentan los problemas tecnicos enfrentados durante la rehabilitacion del generador y se discuten las soluciones implementadas.

  1. Evaluacion del componente central y periferico de fatiga muscular en pacientes neuropaticos y miopaticos

    Directory of Open Access Journals (Sweden)

    L. G. Cohen

    1983-09-01

    Full Text Available Utilizando un método de cuantificación del electromiograma, se investigaron parte de los mecanismos centrales y periféricos responsables de la fatiga muscular en enfermos crónicamente denervados y en pacientes con compromiso muscular primitivo. Se observó en los denervados que los mecanismos de fatiga muscular, no difieren mayormente de los observados en el grupo de sujetos sanos, por el contrario, en los miopáticos a más del componente central, existen otros de orden periférico, tales como la pérdida de unidades motoras funcionantes durante el esfuerzo y el bloqueo temporario de la transmisión neuromuscular, que contribuye al desarrollo de la fatiga.

  2. 77 FR 37936 - Central Vermont Public Service Corporation, Gaz Métro Limited Partnership, Dominion Nuclear...

    Science.gov (United States)

    2012-06-25

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

  3. Communication techniques and nuclear energy; Tecnicas de comunicacion y energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Carpintero Santamaria, N.

    2005-07-01

    The paper presents some thoughts on several factors related to nuclear energy and the way they are presented by the mass media, usually provoking controversy to the Spanish society and thus, undermining public acceptance. Some possibilities for boosting nuclear energy among public opinion are suggested, emphasizing the fact that nuclear power is essential because it is both ecologically and economically sound. (Author)

  4. Management of the process of nuclear transport; Gestion del proceso de transporte nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Requejo, P.

    2015-07-01

    Since 1996 ETSA is the only Spanish logistics operator specialized on servicing the nuclear and radioactive industry. Nowadays ETSA has some technological systems specifically designed for the management of nuclear transports. These tools have been the result of the analysis of multiple factors involved in nuclear shipments, of ETSAs wide experience as a logistics operator and the search for continuous improvement. (Author)

  5. Distribution of nuclear medicine service in Brazil; Distribuicao do servico de medicina nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Ana Carolina Costa da; Duarte, Alessandro; Santos, Bianca Maciel dos [Faculdade Metodo de Sao Paulo (FAMESP), Sao Paulo, SP (Brazil)

    2011-10-26

    The Brazil does not posses a good distribution of nuclear medicine service por all his territory. This paper shows the difference among country regions as far the number of clinics of nuclear medicine as is concerning, and also doctors licensed in the area and radioprotection supervisors, both licensed by the Brazilian Nuclear Energy Commission (CNEN)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-10-15

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

  7. Simulación teórica de las oscilaciones de flujo en centrales de bombeo con chimeneas de equilibrio

    OpenAIRE

    Barrio Perotti, Raúl; Parrondo Gayo, Jorge Luis

    2006-01-01

    El presente trabajo tiene como objeto el estudio del comportamiento transitorio del flujo en centrales de bombeo como consecuencia de la interacción entre las chimeneas de equilibrio y el resto del circuito hidráulico. Este estudio se abordó mediante una modelización del sistema a partir de las ecuaciones de la mecánica de fluidos bajo las hipótesis de flujo unidimensional, incompresible y no estacionario. A continuación se programó un algoritmo que permitió resolver este sistema de...

  8. Comparación de Peso Entre Dos Protocolos de Crianza Artificial de venados cola blanca (Odocoileus virginianus) en el Altiplano Central de México

    OpenAIRE

    Karen Montaño-Suárez

    2014-01-01

    En el altiplano central de México, el aprovechamiento sustentable del venado cola blanca (Odocoileus virginianus) a través de la caza deportiva, ha permitido el desarrollo de nuevas empresas de prestación de servicios cinegéticos. Cuando se habla de los nuevos agronegocios se puede mencionar a los ranchos cinegéticos que son predios rústicos particulares, destinado a la producción ganadera o forestal y que se dedican a la reproducción y aprovechamiento económico de diferentes especies de la f...

  9. Updates of the fire protection system of the Juzbado Nuclear Fuel Fabrication Plant; Actualizaciones del Sistema de Proteccion Contra Incendios de la Fabrica de Combustible Nuclear de Juzbado

    Energy Technology Data Exchange (ETDEWEB)

    Dorado, P.; Palomo, J. J.; Romano, A.

    2015-07-01

    The Juzbado Nuclear Fuel Fabrication Plant fire protection system is one of the most important safety system of the plant. Every year, a large part of the annual investment is employed to improve this system, to update its technology, in order to improve detection and extinction capability to minimize fire risk. Over the last few years, several improvement projects have been carried out that focused on fire detection technology update and on optimization of local detectors integration with a centralized control system, as well as on an advanced public address system, which used clear and unambiguous messages improving personnel response to a plant evacuation. Planned projects and those, which are currently under development, focus on improving passive fire protection means as well as fire protection of key emergency response equipment s such as emergency diesel generators and fire extinguishing bombs. (Author)

  10. Measurement of nuclear cross sections using radioactive beams; Medicion de secciones eficaces nucleares usando haces radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Lizcano, D.; Aguilera, E.F.; Martinez Q, E. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    One of the main applications of the production and use of nuclear radioactive beams is the measurement of nuclear cross sections. In this work is used a {sup 6} He nuclear radioactive beam ({beta} emitting with half life 806.7 ms) for the study of the reaction {sup 6} + {sup 209} Bi which could have several products. This investigation was realized in collaboration with the personnel of the Nuclear Structure laboratory at the University of Notre Dame (U.S.A.) and the National institute of Nuclear Research and CONACyT by Mexico. (Author)

  11. UTILIZAÇÃO DE CATETER VENOSO CENTRAL EM PACIENTES INTERNADOS EM UMA UNIDADE DE TERAPIA INTENSIVA

    OpenAIRE

    2013-01-01

    El objetivo fue describir la utilización del catéter venoso central de corta permanencia en Unidad de Cuidados Intensivos cuanto a la inserción, mantenimiento y remoción, e identificar el perfil de pacientes que recibieron el catéter entre junio y diciembre/2012, en hospital privado de Fortaleza-CE, Brasil. Datos fueron recogidos a través de cuestionario con informaciones contenidas en registros médicos de pacientes y observación. Con respecto al tipo de catéter utilizado y sitio de punción d...

  12. Ampliación con una turbina de vapor de condensación de una central de cogeneración en México

    OpenAIRE

    Bustamante Almazán, Oscar

    2012-01-01

    El presente Proyecto Final de Carrera presenta la Ingeniería Básica de ampliación con una turbina de vapor de condensación de 9 MW de una central de cogeneración con una turbina de gas de 41 MW y turbina de vapor a contrapresión de 2 MW en México. Este Proyecto Final de Carrera tiene por objetivo definir la solución considerada, con suficiente información para que, eventualmente, el propietario pudiera decidir sobre la viabilidad técnica y económica de llevar a cabo el proyecto. En este senti...

  13. La crisis nuclear de Corea del Norte: Sky News o Fox News

    OpenAIRE

    Pablo Rodríguez; Dimitrina Jivkova Semova

    2014-01-01

    En este artículo analizamos, desde la teoría del framing, la información ofre - cida por los dos canales de noticias 24 horas del grupo News Corporation, Sky News y Fox News, con relación a la crisis nuclear de Corea del Norte en el periodo 9 -23 de abril de 2013. Nos centramos en aspectos como la “foxificación”, la presencia de expertos militares en los bloques de noti - cias y los encuadres informativos. En el caso de Sky News, la información se ofrece desde el prisma de los sucesos a nivel...

  14. Sede central de una compañía de seguros Oberursel/Ts. - Alemania Federal

    Directory of Open Access Journals (Sweden)

    Hentrich, Helmut

    1977-02-01

    Full Text Available This building is designed to house the control Centre of an Insurance Company, formed by three chartered companies, in the town of Oberursel, near Frankfurt. The work includes seven floors and two basements, in the shape of a swastika, and is completed with a rectangular annex, with two storeys, intended for the restaurant, cafeteria and an all-purpose room. The main building provides offices of a landscape type, with a total of 1,500 jobs, to be extended to 2,500. The structure is in reinforced concrete, with a modulation between support axes of 10.50 X 10.50 m. The stability of the unit is achieved through a main bracing nucleus, which also acts as a vertical communication axis. The frontage is of curtain wall, with steel framework corridor on all the floors, aluminium carpentry and insulating glazing. These corridors lead to two fire scapes, backing on to the main building on opposite sides. Suitable decoration, together with the specially chosen furniture and the varied series of installations, both generic and specific, for this type of centers, contribute towards achieving the suitable working atmosphere. Furthermore, a group of social, recreative and sports installations, facilitate personal contacts among employees.Este edificio se destina a albergar el Centro de control de una compañía de seguros, integrada por tres sociedades anónimas, en la ciudad de Oberursel, cerca de Frankfurt. La obra se desarrolló en seis plantas y dos sótanos con forma de cruz gamada, y se completa con un anexo rectangular, de dos plantas, dedicado a restaurante, cafetería y sala polivalente. El edificio principal distribuye oficinas de tipo paisajístico con un total de 1.500 puestos de trabajo, ampliables hasta 2.500. La estructura es de hormigón armado, con una modulación entre ejes de soportes de 10,50 x 10,50 m. La estabilidad del conjunto se consigue mediante un núcleo central de arriostramiento, que sirve, además, de eje de

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

    CERN Document Server

    Capella, A

    2001-01-01

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

  16. Paradox place: discourse line of nuclear sector; Lugar de paradoxos: pelos caminhos discursivos do setor nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ponce, Iona

    2002-05-15

    This thesis examines the relationship between the public acceptance and image of nuclear energy and the discourse and arguments commonly employed by the nuclear institutions. In doing so, the Critical Discourse Analysis, the French Discourse Analysis and Pragmatics theories were used to evaluate important variables involved in the construction of the nuclear discourse such as social memory, intertextualilty and image construction. The analysis performed shows that the discourse in favor of the nuclear energy is in fact imbedded by the anti-nuclear discourse. As a consequence, the negative image of the nuclear sector is being reinforced at the same time that its public acceptance becomes more difficult. The core of this analysis consists of two sets of information. The first one is the Internet site of the Brazilian National Nuclear Energy Commission (CNEN). CNEN is the federal nuclear regulatory and research and development agency of Brazil. In this analysis it represents the discourse in favor of nuclear energy. The second set of information used in this thesis is composed by a number of texts displayed in the open literature such as newspapers, magazines and Internet sites, all of them expressing anti-nuclear positions. A careful comparison of both sets shows that the discourse of CNEN, instead of showing new ideas and issues related to nuclear energy, in fact, stays mainly in a reactive position as if it were trying to defend itself from the arguments posed by the anti-nuclear discourse. It was concluded that the discourse of CNEN is constrained within a complex field of non positive expressions, arguments and ideas mostly encountered in the anti-nuclear discourse which brings obvious difficulties to explain the benefits of nuclear energy as a whole. To overcome such situation a more detailed study of the CNEN discourse is suggested. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  18. Nuclear medicine external individual occupational doses in Rio de Janeiro

    Energy Technology Data Exchange (ETDEWEB)

    Mauricio, Claudia L.P.; Lima, Ana Luiza S.; Silva, Herica L.R. da; Santos, Denison Souza [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)], e-mail: claudia@ird.gov.br, e-mail: analuslima@yahoo.com.br, e-mail: herica@ird.gov.br, e-mail: santosd@ird.gov.br; Silva, Claudio Ribeiro da [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao Geral de Ciencia e Tecnologia da Informacao (CGTI)(Brazil)], e-mail: claudio@cnen.gov.br

    2009-07-01

    According to the Brazilian National Database there are about 300 Nuclear Medicine Services (NMS) in Brazil, 44 of them located in the State of Rio de Janeiro (RJ). Individual dose measurements are an important input for the evaluation of occupational exposure in order to demonstrate the effectiveness of radioprotection implementation and to keep individual doses as low as possible. In Brazil, most nuclear medicine (NM) staff is routinely monitored for external dose. The internal committed dose is estimated only in abnormal conditions. This paper makes a statistics analysis of all the RJ NMS annual external occupational doses in year 2005. A study of the evolution of monthly external individual doses higher than 4.00 mSv from 2004 to 2008 is also presented. The number of registered thorax monthly dose higher than 4.0 mSv is increasing, as its value. In this period the highest dose measured reaches 56.9 mSv, in one month, in 2008. About 50% of the annual doses are smaller than the monthly record level of 0.20 mSv. In 2005, around 100 professionals of RJ NMS received annual doses higher than 4.0 mSv, considering only external doses, but no one receives doses higher than 20.0 mSv. Extremities dosimeters are used by about 15% of the staff. In some cases, these doses are more than 10 times higher than the dose in thorax. This study shows the importance to improve radiation protection procedures in NM. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, E. M.

    2014-07-01

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

  20. De-alerting of U.S. nuclear forces: a critical appraisal

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, K C; Barish, F

    1998-08-21

    Since the end of the Cold War, there have been pressures by disarmament advocates to move more quickly to draw down, toward zero, the number of nuclear weapons in U.S. and Russian arsenals. They criticize the process of negotiating arms control agreements as being too slow, and point out that treaty implementation is hampered by the necessity of ratification by the U.S. Senate and Russian Duma. One method of moving more rapidly toward nuclear abolition suggested by some analysts is de-alerting of nuclear-weapon delivery systems. De-alerting is defined as taking steps that increase significantly the time required to launch a given delivery vehicle armed with a nuclear warhead. Although there is little inclination by the U.S. Government to de-alert its nuclear forces at present, some academic literature and press stories continue to advocate such steps. This paper offers a critique of de-alerting proposals together with an assessment of the dangers of accidental, unauthorized, or unintended use of nuclear weapons. It concludes that de-alerting nuclear forces would be extremely de-stabilizing, principally because it would increase the value to an opponent of launching a first strike.

  1. Reflectance measurement in heliostats field of Solar Thermal Central Receivers Systems; Medida de reflectancia en campos de heliostatos de sistemas de Torre Central

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez-Reche, J.; Monterreal, R.

    2004-07-01

    Determination of the mean reflectance of Heliostats field of Solar Thermal Central Receivers Systems takes high relevance, from both the operational point of view and the components evaluation. To calculate the mean reflectance calculation becomes essential to establish a procedure that allows offering its value without measuring all and each one of the facets that constitute the field, since this is a long-time consuming and little operational task. This work presents the results of the statistical reflectance study of the CRS heliostats field of the Plataforma Solar de Almeria. In addition, to validate the results, the obtained average reflectance is introduced in the heliostats field simulation code Fiat{sub L}ux. A comparison between the simulation and real incident solar power measurement was performed. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, Maria B.M.A.

    1996-12-31

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

  3. El valor de la opinión en los noticieros televisivos chilenos de hoy el caso de 24 horas central de TVN

    Directory of Open Access Journals (Sweden)

    Jimena Maiz Sáenz-Villarreal

    2014-12-01

    Full Text Available Con la cultura de masas y como efecto de la búsqueda de consenso propia de la democracia, la opinión, entendida como juicio de valor, se ha incorporado en los noticieros televisivos como medio de legitimación para el líder que la emite y como forma de identificación para el receptor que se sienta representado por ella. Por ello, su intención es generar un acercamiento con el destinatario, tratando de impactar, al mismo tiempo, su inteligencia y sus emociones, para orientarlo en algún sentido a través de opiniones propiamente tales, expresión de sentimientos y apelaciones. El presente trabajo busca demostrar este planteamiento mediante el análisis semiótico del noticiario 24 horas Central de TVN, utilizando para ello el paradigma de Charles Morris.

  4. LA PARTICIPACIÓN DE LOS BANCOS CENTRALES EN LAS CRISIS BANCARIAS DE LA AMÉRICA LATINA. Lecciones de los decenios de los noventa y de 2000

    Directory of Open Access Journals (Sweden)

    Luis I. Jácome H.

    2013-01-01

    Full Text Available En el presente artículo se analiza el papel de los bancos centrales en las crisis bancarias de la América Latina. Se descubre que, salvo por un puñado de casos, cuando las resoluciones bancarias se ejecutaron puntualmente, el dinero del banco central se utilizó a gran escala para contener y gestionar crisis tanto sistémicas como menores. Sin embargo, las aportaciones de dinero a raudales en el sistema financiero tendieron a exacerbar la turbulencia macroeconómica y aumentaron las probabilidades de que ocurrieran crisis cambiarias, sobre todo en los países de mercados emergentes. Si bien con algunas salvedades, las conclusiones del presente artículo son pertinentes y los países en desarrollo deberían verlas como una advertencia contra la expansión excesiva de los balances generales de los bancos centrales para hacer frente a las crisis financieras, tal como lo han hecho recientemente varios países industrializados.

  5. Escenario de Sismo y Tsunami en el Borde Occidental del la Region Central del Peru.

    OpenAIRE

    Tavera, Hernando

    2014-01-01

    En el presente informe se analiza la información publicada sobre la ocurrencia de grandes sismos en el Perú, con el propósito de consolidar el posible escenario sísmico y de tsunami que pueda presentarse en el borde occidental de la región central del Perú y que afectaría a la ciudad de Lima Metropolitana y a la provincia Constitucional del Callao. Se considera como fuentes primarias los trabajos de investigación realizados por Tavera y Bernal (2005) “Distribución espacial de á...

  6. Second Mexican School of Nuclear Physics: Notes; Segunda Escuela Mexicana de Fisica Nuclear: Notas

    Energy Technology Data Exchange (ETDEWEB)

    Aguilera, E.F. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico); Chavez L, E.R. [Instituto de Fisica, UNAM, 04510 Mexico D.F. (Mexico); Hess, P.O. [Instituto de Ciencias Nucleares, UNAM, 04510 Mexico D.F. (Mexico)

    2001-07-01

    The II Mexican School of Nuclear Physics which is directed to those last semesters students of the Physics career or post-graduate was organized by the Nuclear Physics Division of the Mexican Physics Society, carrying out at April 16-27, 2001 in the installations of the Institute of Physics and the Institute of Nuclear Sciences, both in the UNAM, and the National Institute of Nuclear Research (ININ). A first school of a similar level in Nuclear Physics, was carried out in Mexico at 1977 as Latin american School of Physics. This book treats about the following themes: Interactions of radiation with matter, Evaluation of uncertainty in experimental data, Particle accelerators, Notions of radiological protection and dosimetry, Cosmic rays, Basis radiation (environmental), Measurement of excitation functions with thick targets and inverse kinematics, Gamma ray technique for to measure the nuclear fusion, Neutron detection with Bonner spectrometer, Energy losses of alpha particles in nickel. It was held the practice Radiation detectors. (Author)

  7. Nuclear DNA content in Galaxias maculatus (Teleostei: Osmeriformes: Galaxiidae Contenido de ADN nuclear en Galaxias maculatus (Teleostei: Osmeriformes: Galaxiidae

    Directory of Open Access Journals (Sweden)

    Pedro Jara-Seguel

    2008-01-01

    Full Text Available The nuclear DNA content (2C value was determined in the commercial fish Galaxias maculatus (Galaxiidae was determined by microdensitometry of erythrocyte nuclei after Feulgen staining; rainbow trout erythrocytes with a known 2C value were used as a standard. The 2C value of G. maculatus was 2.21 ± 0.12 pg and its C value was equivalent to 1.105 pg (1,082.9 Mbp. This C value is within the range recorded for other osmeriform species (0.62-3.2 pg. The average sperm head diameter of G. maculatus is lower than the average sperm head diameter of rainbow trout (used as a standard, which coincides with the differences observed in the nuclear DNA content of both species. This information increases the genome data available for G. maculatus and might be useful in future programs dealing with its genetic manipulation.El contenido de ADN nuclear (valor 2C fue determinado en el pez comercial Galaxias maculatus (Galaxiidae usando microdensitometría de núcleos de eritrocitos sometidos a tinción de Feulgen, utilizando como estándar eritrocitos de trucha arco iris con un valor 2C conocido. El valor 2C de G. maculatus fue 2,21 ± 0,12 pg y su valor C es equivalente a 1,105 pg (1.082,9 pMb. Este valor C está dentro del rango registrado para otras especies de osmeriformes (0,62-3,2 pg. El diámetro promedio de la cabeza del espermatozoide de G. maculatus es menor al promedio descrito para la trucha arco iris utilizado como estándar, lo que coincide con las diferencias observadas en el contenido de ADN nuclear entre ambas especies. Estos datos contribuyen a ampliar los antecedentes genómicos disponibles para G. maculatus y podrían ser útiles en futuros programas tendientes a su manipulación genética.

  8. Suscetibilidade de Spodoptera Frugiperda a isolados geográficos de um vírus de poliedrose nuclear Spodoptera Frugiperda susceptibility to nuclear polyhedrosis virus geographical isolates

    Directory of Open Access Journals (Sweden)

    Sérgio Arce Gomez

    1999-09-01

    Full Text Available O presente trabalho objetivou verificar a suscetibilidade de larvas de segundo ínstar de Spodoptera frugiperda (Smith, 1797 a sete isolados geográficos de um vírus de poliedrose nuclear (VPN, conduzindo-se sete bioensaios no Laboratório de Patologia de Insetos da Embrapa-Centro Nacional de Pesquisa de Soja, Londrina. Para cada isolado preparou-se dieta artificial contendo 0, 2x10³, 4x10³, 8x10³, 16x10³, 32x10³ e 64x10³ corpos poliédricos de inclusão (CPI/mL. Cada dose foi oferecida às larvas em copos de plástico de 50 mL, sob condições controladas (temperatura: 26±2ºC; umidade relativa: 60±10%; fotófase:14 horas. A análise (Probits realizada sobre o somatório de larvas mortas (contadas, diariamente, do quinto ao décimo quarto dia após a inoculação mostrou, com base na ausência de sobreposição das amplitudes dos intervalos de confiança das concentrações letais médias (CL50, que: o isolado de Sertaneja, PR (5.631 CPI/mL, foi o mais virulento; o da Guatemala (11.520 CPI/mL equivaleu aos de Ponta Grossa, PR (14.184 CPI/mL, Argentina (15.891 CPI/mL e Alabama, EUA (17.558 CPI/mL, mas foi superior aos isolados de Louisiana, EUA (19.325 CPI/mL e Sete Lagoas, MG (25.310 CPI/mL. A variação do tempo letal médio, de 8,3 a 10 dias, não foi significativa em relação aos isolados.In order to verify the Spodoptera frugiperda (Smith,1797 second instar larvae susceptibility to seven nuclear polyhedrosis virus (NPV geographical isolates, seven bioassays were carried out at Embrapa-Centro Nacional de Pesquisa de Soja, Insect Pathology Laboratory, Londrina, Paraná State, Brazil. Artificial diet containing 0 (control, 2x10³, 4x10³, 8x10³, 16x10³, 32x10³, and 64x10³ polyhedral inclusion bodies (PIB/mL was prepared for each virus isolate; each dose was offered, in 50 mL plastic cups to the larvae under controlled conditions (temperature 26±2ºC; relative humidity: 60±10% and photophase: 14 hours. The statistical analysis

  9. Nuclear Safety research in CIEMAT; Quince anos de investigacion en Seguridad Nuclear en el Ciemat

    Energy Technology Data Exchange (ETDEWEB)

    Lopez Jimenez, J.

    2003-07-01

    A review was done on the main activities performed and achievements managed by the Project of Nuclear Safety Research (Department of Nuclear Fission) of Ciemat in the last fifteen years on the areas of: severe accident, advanced reactors and containment analysis. It was emphasised Ciemat's participation in national and international projects, mainly promoted by The Spanish Nuclear Sector, the CSN the OECD, EPRI and the European Union. The experimental and analytical capabilities on reactor nuclear safety set up in Ciemat along this period of time were also described. (Author) 23 refs.

  10. Inventario de mamíferos en un bosque de los andes centrales de colombia

    OpenAIRE

    2012-01-01

    Se usaron técnicas de captura, observación directa y registro indirecto para obtenerun inventario de mamíferos en un bosque andino de Colombia. Se realizaronmuestreos entre octubre de 1998 y abril de 1999 en la Reserva Río Blanco (Manizales,Departamento de Caldas), entre 2200 - 3750 m de altitud. Para capturar pequeñosmamíferos no voladores se usaron trampas Sherman. Para capturar murciélagos seusaron mallas de niebla y colectas manuales. Para registrar medianos y grandesmamíferos se usaron t...

  11. Estudio y análisis de instalaciones de centrales termosolares con tecnología CCP

    OpenAIRE

    MAS SANZ, JAVIER

    2011-01-01

    Trabajo científico técnico. El presente proyecto, trata de realizar el análisis y estudio de las plantas de generación de energía limpia y renovable, basadas en tecnología desarrollada a partir de captadores cilindro parabólicos Mas Sanz, J. (2011). Estudio y análisis de instalaciones de centrales termosolares con tecnología CCP. http://hdl.handle.net/10251/12088. Archivo delegado

  12. Caracterización de un grupo de pacientes con esquizofrenia en el Valle Central de Costa Rica

    Directory of Open Access Journals (Sweden)

    Javier Contreras

    2008-09-01

    Full Text Available Justificación y objetivo: la esquizofrenia es una enfermedad crónica con importantes repercusiones sociales que afecta al 1% de la población mundial. Se describe las características de la esquizofrenia en una muestra de pacientes del Valle Central de Costa Rica. Métodos: estudio descriptivo, transversal en esquizofrénicos diagnosticados a través del proceso de mejor estimado diagnostico según la cuarta edición del Manual Diagnóstico y Estadístico de los Trastornos Mentales (DSMIV. Resultados: de 260 esquizofrénicos, 186 (71.5% son varones y 74 (28.5% mujeres, la edad promedio de entrevista es 38.95 años (Desviación Standard (DS: 11.37, menor en los varones (37.54 años, DS: 10.46 que en las mujeres (42.49 (DS: 12.81, p0.05. El número de hospitalizaciones es en promedio 5.49 (DS: 5.24, (p>0.05, los sujetos solteros presentan tendencia a un mayor número de ingresos (17.25 internamientos. El 49.6% ha sufrido al menos un síndrome depresivo mayor, 7.5% de los varones presenta abuso y el 22.0% dependencia al alcohol; 7.7% de sujetos presenta abuso y el 7.3% dependencia a sustancias (p>0.05. Discusión: Nuestros pacientes presentaron características clínicas y demográficas similares a lo observado en otras poblaciones. Más de la mitad de los individuos tenían antecedente de síntomas afectivos siendo los depresivos los más frecuentes. Los varones solteros constituyeron el grupo con peor pronóstico, mayor desempleo y mayor tendencia a presentar reingresos hospitalarios. Sin embargo, dicho hallazgo podría ser explicado por la organización económica de los hogares y el rol social del varón en nuestra sociedad. Conclusión: los varones y las mujeres EZ del VCCR muestran una misma edad de inicio de enfermedad, el subtipo predominante en ambos grupos es el indiferenciado con el antecedente de síntomas depresivos. Los varones presentan un mayor índice de desempleo, mayor consumo de sustancias lícitas e ilícitas y mayor n

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

    CERN Document Server

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

    2016-01-01

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

  14. Central hormigonera y de clasificación de áridos

    Directory of Open Access Journals (Sweden)

    Hossdorf, Heinz

    1963-11-01

    Full Text Available In order to exploit industrially the aggregates to be found in substantial quantities near the river Aare, Switzerland, a station has been constructed in which the aggregates will be classified. Concrete will then be made at a nearby building, to be sold commercially. It is estimated that there are about 2 million cubic metres of suitable aggregate material available for exploitation. The design of these installations has been prepared in collaboration with the firm which supplied the equipment so that the resulting project fully meets with the functional demands. The building is divided into four independent units, which are closely integrated in their operational use. The main item for the transport of aggregates is a tubular metal bridge, easy to assemble, and to adapt to the varying positions of the quarry face. The total length of this bridge is 120 ms. The main part of the building includes the housing of the installations and two groups of silos. On each side of the silos roadways have been provided to be utilized by the trucks that take the aggregates to their various destinations.Los áridos de una capa potente en las proximidades del río Aare, en Suiza, se ha construido un edificio, de características particulares, destinado a tratar y clasificar dichos áridos y, a la vez, vender el hormigón preparado en una central situada al lado de las instalaciones de clasificación. Los estudios geológicos del banco puesto en explotación, arrojan una reserva aproximada de dos millones de metros cúbicos de áridos sin clasificar. El proyecto de estas instalaciones se ha redactado en colaboración con !a factoría que ha suministrado la maquinaria que ha de tratar los áridos procedentes de la cantera, con lo que se ha conseguido una solución que cubre las exigencias originales a plena satisfacción, que consiste en una subdivisión del edificio en cuatro cuerpos independientes, aunque orgánicamente se hallen enlazados. Él elemento

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

    Energy Technology Data Exchange (ETDEWEB)

    Garcia V, M.A

    2006-07-01

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

  16. Validación de genotipos de frijol negro en la zona central del Estado de Veracruz, México

    Directory of Open Access Journals (Sweden)

    Francisco Javier Ugalde Acosta

    2005-01-01

    Full Text Available Validación de genotipos de frijol negro en la zona central del estado de Veracruz, México. El objetivo del presentetrabajo, fue validar genotipos de frijol con el paquete tecnológico del INIFAP, en parcelas de productores. Durante los ciclosde humedad residual de 1998 a 2001 se establecieron nueveparcelas de validación. Los genotipos utilizados fueron: las lí-neas II-307 y DOR-500 y las variedades Negro Huasteco 81,Negro Cotaxtla 91 y Negro INIFAPy como testigo del productor la variedad Jamapa. En las parcelas se realizaron las laboresde manejo agronómico recomendadas por el INIFAPpara esazona de producción. Cada parcela ocupó una superficie total de3000 m2. Se realizaron análisis de varianza individuales por localidad, considerando como repetición los rendimientos obtenidos por cada genotipo (500 m2 por ciclo de evaluación; también se efectuaron análisis combinado con prueba deseparación de medias (DMS 5% y un análisis económico mediante la Tasa de Retorno Marginal. Los resultados indicaronque las variedades y líneas mejoradas fueron superiores en másdel 100% en rendimiento al testigo. El análisis económicomostró que el mayor beneficio económico se obtuvo al sembrarlas variedades Negro INIFAPy Negro Cotaxtla 91, con utilidades superiores a los US $ 286/ha y una relación beneficio/costo de 1,52 y 1,51, respectivamente.

  17. 19. Brazilian congress on biology and nuclear medicine; 19. Congresso brasileiro de biologia e medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The issue contain 97 abstracts of 19 Brazilian congress on biology and nuclear medicine held in Pernambuco, Brazil, from November 4 to 8, 1998. The subjects addressed are diagnostic and therapy nuclear medicine techniques, especially scintiscanning, SPECT and PET and their uses. The main topics were as follows: cardiology, neuro-psychiatry, oncology, endocrinology, radiopharmacy, infectious diseases, radiobiology and others.

  18. Indicators of Nuclear safety and exploitation in ANAV; Indicadores de Seguridad Nuclear y explotacion en ANAV

    Energy Technology Data Exchange (ETDEWEB)

    Quintana Prieto, M.; Jorda Alcove, M.

    2013-07-01

    The use of indicators by ANAV plants, aims to be a tool to facilitate the assessment of the behaviour of the plants nuclear over a specific time period. The following are and are they explain those related to Nuclear safety and exploitation.

  19. Applied nuclear physics group - activities report. 1977-1997; Grupo de fisica nuclear aplicada - relatorio de atividades. 1977-1997

    Energy Technology Data Exchange (ETDEWEB)

    Appoloni, Carlos Roberto

    1998-06-01

    This report presents the activities conducted by the Applied Nuclear Physics group of the Londrina State University - Applied Nuclear Physics Laboratory - Brazil, from the activities beginning (1977) up to the end of the year 1997.

  20. De novo copy number variations in cloned dogs from the same nuclear donor

    OpenAIRE

    Jung, Seung-Hyun; Yim, Seon-Hee; Oh, Hyun Ju; Park, Jung Eun; Kim, Min Jung; Kim, Geon A; Kim, Tae-Min; Kim, Jin-Soo; Lee, Byeong Chun; Chung, Yeun-Jun

    2013-01-01

    Background Somatic mosaicism of copy number variants (CNVs) in human body organs and de novo CNV event in monozygotic twins suggest that de novo CNVs can occur during mitotic recombination. These de novo CNV events are important for understanding genetic background of evolution and diverse phenotypes. In this study, we explored de novo CNV event in cloned dogs with identical genetic background. Results We analyzed CNVs in seven cloned dogs using the nuclear donor genome as reference by array-...

  1. 3. Mexican school of nuclear physics; 3. Escuela Mexicana de Fisica Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Chavez L, E.R. [Instituto de Fisica, UNAM, 04510 Mexico D.F. (Mexico); Hess, P.O. [Instituto de Ciencias Nucleares, UNAM, 04510 Mexico D.F. (Mexico); Martinez Q, E. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    The III Mexican School of Nuclear Physics which is directed to those post graduate in Sciences and those of last semesters students of the Physics career or some adjacent career was organized by the Nuclear Physics Division of the Mexican Physics Society, carrying out at November 18-29, 2002 in the installations of the Institute of Physics and the Institute of Nuclear Sciences both in the UNAM, and the National Institute of Nuclear Research (ININ). In this as well as the last version its were offered 17 courses, 9 of them including laboratory practices and the rest were of theoretical character only. This book treats about the following themes: Nuclear physics, Electrostatic accelerators, Cyclotrons, Thermonuclear reactions, Surface barrier detectors, Radiation detection, Neutron detection, Bonner sphere spectrometers, Radiation protection, Biological radiation effects, Particle kinematics, Nucleosynthesis, Plastics, Muons, Quadrupoles, Harmonic oscillators, Quantum mechanics among many other matters. (Author)

  2. BENCHMARKING INTERNO EN UNA CENTRAL DE COMPRAS DE AGENCIAS DE VIAJES

    Directory of Open Access Journals (Sweden)

    Isabel Montero Muradas

    2010-01-01

    Full Text Available El sector turístico es uno de los más dinámicos de nuestra economía que necesita poner en marcha nuevas estrategias para mantener sus niveles de participación en el PIB. El objetivo de este trabajo es determinar, mediante un análisis conjunto probabilístico, utilizando el modelo de Rasch, la importancia relativa de los factores determinantes de la oferta turística de una alianza estratégica entre agencias de viajes: Travel Advisors Guild (TAG. En los resultados se destaca el posicionamiento de las agencias integradas en el TAG, así como los desajustes competitivos internos.

  3. Antígeno nuclear de proliferação celular em tumores de adrenal Proliferating cell nuclear antigen in adrenal tumors

    Directory of Open Access Journals (Sweden)

    Rodrigo A.R. Falconi

    2000-01-01

    Full Text Available Fez-se um estudo imunohistoquímico do antígeno nuclear de proliferação celular (PCNA em 26 adenomas e 24 carcinomas de adrenal através da técnica da avidina-biotina-peroxidase. O índice de marcação (IP do PCNA, definido com o número de células marcadas/1000 contadas, foi em média de 77,4± 66,1 (mediana - 63,5 para os adenomas enquanto que para os carcinomas foi 215,8± 56,0 (mediana - 217,5 (p<0,0001. Estabelecendo-se o IP de 100 o marcador (para a discriminação de carcinomas dos adenomas o marcador exibiu sensibilidade, especificidade e valor preditivo positivo seguintes, respectivamente: 100%, 69% e 75%.

  4. Análisis del proceso de descentralización fiscal: el caso de las finanzas públicas del gobierno central de Cundinamarca

    OpenAIRE

    Manuel Bernal Garzón

    2016-01-01

    Este artículo presenta un análisis del proceso de descentralización fiscal en Colombia, a la luz de las finanzas públicas de la administración central del gobierno departamental de Cundinamarca. Se estudia cómo se ha profundizado y perfeccionado el proceso de descentralización mediante unas transferencias automáticas de recursos de la nación a los entes territoriales, de una legislación encaminada a fortalecerlos fiscos locales, y de unos sistemas de créditoy cofinanciación que buscan imprimi...

  5. Nuevo puente para el oleoducto de Europa Central

    Directory of Open Access Journals (Sweden)

    Giuliani, G.

    1971-04-01

    Full Text Available This bridge runs over the Po river, near Pavia, and is 1,370 m long. It is divided into spans of 36 m length each. The horizontal structure of the bridge consists of sets of four continuous girders, running over six spans, and two continuous girders, extending over seven spans. The piles are 14 m high and 1.50 m in diameter, and rest on the extension of the foundation piles. This article describes details of the project and the system of placing the continuous girders.Este puente, construido sobre el río Po, cerca de Pavía, tiene una longitud total de 1.370 m, dividida en tramos de 36 m de longitud, salvados por cuatro vigas continuas, de 6 vanos, y dos vigas continuas, de 7 vanos. Las pilas, de 14 m de altura y 1,50 m de diámetro, se han construido sobre la prolongación de los pilotes de cimientos. El artículo explica las particularidades de la obra y el procedimiento de lanzamiento adoptado.

  6. Calculo Preliminar de la Tasa de Meteorización del Batolito Antioqueño, Cordillera Central, Colombia

    Directory of Open Access Journals (Sweden)

    Carolina Garcia

    2004-12-01

    Full Text Available Este trabajo es una estimación preliminar del tiempo necesario para generar la espesa capa de saprolito que caracteriza el perfil de meteorización actual de un batolito cuarzodiorítico cretácico que aflora en altiplanos de la Cordillera Central de Colombia, entre 5º50' y 7º00' de latitud Norte y 74º50' y 75º35' de longitud Oeste y a alturas entre 750 y 2700 m.Se utilizan datos obtenidos previamente mediante el análisis de la composición química de las aguas superficiales de cuatro cuencas con áreas diferentes, ubicadas sobre el Batolito Antioqueño, al este de Medellín. Los cáculos se hicieron con el método basado en la pérdida de componentes en solución utilizando diferentes valores de solutos. Al utilizar la pérdida de sílice se obtiene un tiempo de meteorización de unos 6 x 10 6 años, comparable con el obtenido mediante la datación de las cenizas volcánicas mas antiguas que recubren la topografía actual y que indican la fecha mínima de configuración de la superficie de erosión.A pesar de resultar de una serie de suposiciones simplificadoras, este resultado es interesante y justifica la realización de determinaciones mas detalladas. Confirma la larga preservación de superficies de erosión antiguas conformadas sobre un saprolito que desde hace varios millones de años no ha sido sometido a una erosión profunda, fenómeno poco común en una zona tectónicamente activa como la estudiada.

  7. Microtuberización in vitro de siete accesiones de papa de la colección central colombiana

    Directory of Open Access Journals (Sweden)

    Rivera ängela Liliana

    2008-09-01

    Full Text Available Se evaluó la producción in vitro de microtubérculos de papa (cuatro accesiones de S. tuberosum ssp andigena y tres de S. phureja de la Colección Central Colombiana. Se emplearon dos protocolos (líquido-líquido y sólido-líquido en un diseño completamente al azar con arreglo factorial. Las variables evaluadas al momento de la cosecha fueron número de microtubérculos con tamaño inferior a 0.5cm, superior a 0.5cm y número total. La producción de microtubérculos estuvo determinada por el genotipo, el protocolo y las diferentes concentraciones de las hormonas Benzilaminopurina (BAP y Cloruro de Cloro Colina (CCC. La producción fue mayor en el protocolo sólido – líquido, y entre concentraciones la de mejor producción de microtubérculos fue C1 (Sales MS 100%, sacarosa 8%, 10mg BAP/ 500mg CCC y oscuridad. Los mejores productores de microtubérculos fueron las accesiones C.C.C. 4318 (Carriza, C.C.C. 4981 (Guata negra y Solanum phureja 50 (sin nombre.

  8. Influence of riverine outputs on sandy beaches of Higuerote, central coast of Venezuela Influencia de aportes fluviales en playas arenosas de Higuerote, costa central de Venezuela

    Directory of Open Access Journals (Sweden)

    Antonio Herrera

    2011-01-01

    Full Text Available The influence of riverine outputs from the Tuy River on the coastal processes of near sandy beaches was assessed by measuring the physical and chemical characteristics of water and sediment samples at eight sites along the north central Venezuelan coast and from the rivers that flow through this región into the sea (Tuy, Capaya, Curiepe during two field surveys. In addition, the behavior of the Tuy River discharge plume was evaluated using remote sensors, and its effect on the population abundance and size structure of the clam Tivela mactroides was determined. Of the three rivers evaluated, the Tuy River had the highest impact on the coastal zone (789.15 ± 190.63 km² in terms of flow rate (246.39 m³ s-1, nutrients (659.61 ± 503.27 g s-1total nitrogen; 52 ± 53.09 g s-1 total phosphorus and sedimentary material (9320.84 ± 9728.15 g s-1. The variables measured (salinity, total nitrogen and phosphorus, pH, turbidity, and total organic carbon showed a spatial gradient along the coast. Tivela mactroides had the highest biomass and density (9126.8 ± 1562 g m-2; 9222.22 ± 1976.72 ind m-2 at the sites farthest from the river mouths and smaller sizes (Para evaluar los aportes del río Tuy sobre los procesos costeros en playas arenosas cercanas, se examinó en dos campañas de muestreo, las características físicas y químicas a nivel de agua y sedimento en ocho estaciones ubicadas a lo largo de la costa centro norte de Venezuela, el cauce de los ríos que allí desembocan (Tuy, Capaya, Curiepe, además del comportamiento de la pluma del río Tuy mediante sensores remotos y su influencia sobre las poblaciones de la almeja Tivela mactroides en cuanto a abundancia y estructura de talla. El río Tuy tuvo mayor predominio sobre la zona costera (789,15 ± 190,63 km , presentó el mayor aporte líquido (246,39 m³ s-1, de nutrientes (659,61 ± 503,27 g s-1 nitrógeno total; 52 ± 53,09 g s-1fósforo total y material sedimentario (9320,84 ± 9728,15 g

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

  10. The convenience of nuclear energy; La conveniencia de la energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lucena, A.

    2007-07-01

    It is unquestionable that the power sources must change, for the same reasons for which the propagandist ones have been appropriated of the nuclear energy: its use is not a sustainable practice and produces the climatic change and other many damages. In this sense, any alternative has to be considered, and, a priori, the nuclear one, that at this moment is very minority in the power system, does not have to be an exception. For that reason it is not necessary to let be critical with anyone of the alternatives that are considered, and this aspect also affects the nuclear energy. (Author)

  11. Subcritical calculation of the nuclear material warehouse;Calculo de subcriticidad del almacen del material nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Garcia M, T.; Mazon R, R., E-mail: teodoro.garcia@inin.gob.m [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2009-07-01

    In this work the subcritical calculation of the nuclear material warehouse of the Reactor TRIGA Mark III labyrinth in the Mexico Nuclear Center is presented. During the adaptation of the nuclear warehouse (vault I), the fuel was temporarily changed to the warehouse (vault II) and it was also carried out the subcritical calculation for this temporary arrangement. The code used for the calculation of the effective multiplication factor, it was the Monte Carlo N-Particle Extended code known as MCNPX, developed by the National Laboratory of Los Alamos, for the particles transport. (Author)

  12. Development for analysis system of rods enrichment of nuclear fuels; Desarrollo de un sistema de analisis de enriquecimiento de barras de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Rojas C, E.L

    1998-11-01

    Nuclear industry is strongly regulated all over the world and quality assurance is important in every nuclear installation or process related with it. Nuclear fuel manufacture is not the exception. ININ was committed to manufacture four nuclear fuel bundles for the CFE nucleo electric station at Laguna Verde, Veracruz, under General Electric specifications and fulfilling all the requirements of this industry. One of the quality control requisites in nuclear fuel manufacture deals with the enrichment of the pellets inside the fuel bundle rods. To achieve the quality demanded in this aspect, the system described in this work was developed. With this system, developed at ININ it is possible to detect enrichment spikes since 0.4 % in a column of pellets with a 95 % confidence interval and to identify enrichment differences greater than 0.2 % e between homogeneous segments, also with a 95 % confidence interval. ININ delivered the four nuclear fuel bundles to CFE and these were introduced in the core of the nuclear reactor of Unit 1 in the fifth cycle. Nowadays they are producing energy and have shown a correct mechanical performance and neutronic behavior. (Author)

  13. MORFOMETRÍA COMPARADA DE SEMILLAS DE NICOTIANA (SOLANACEAE E IDENTIFICACIÓN DE SEMILLAS CARBONIZADAS PROVENIENTES DE UN SITIO ARQUEOLÓGICO EN CHILE CENTRAL

    Directory of Open Access Journals (Sweden)

    M. Teresa Planella

    2012-01-01

    Full Text Available La presencia frecuente de pipas para fumar en sitios arqueológicos del Período Alfarero Temprano deChile central y las evidencias en relación con la costumbre de fumar especies de Nicotiana halladas en sitios prehispánicos de otros lugares de las Américas, muestran la necesidad de contar con una metodología para identificar las especies de este género usadas en Chile. En este trabajo se ha realizado un estudio morfométrico en semillas de especies de Nicotiana que sirve de referencia para comparaciones con semillas de origen arqueológico. La forma y tamaño de la semilla, el patrón de ornamentación dado por las células epidérmicas y la ubicación del hilum resultaron ser caracteres relevantes para identificaciones confiables. Utilizando estos caracteres, se determinaron como N. corymbosa a las semillas recuperadas en el sitio arqueológico Las Morrenas 1, ubicado en Chile central.

  14. Neurocitoma central com apresentação incomum por hemorragia intraventricular: relato de caso

    Directory of Open Access Journals (Sweden)

    Hanel Ricardo Alexandre

    2001-01-01

    Full Text Available O neurocitoma central foi descrito pela primeira vez na literatura em 1982 por Hassoun e colaboradores como tumor bem diferenciado de origem neuronal. O tumor geralmente localiza-se no sistema ventricular, afetando adultos jovens e geralmente cursando com hipertensão intracraniana secundária à hidrocefalia obstrutiva. O diagnóstico diferencial com outros processos intraventriculares como oligodendroglioma é realizado através de métodos imuno-histoquímicos. Raros casos de neurocitoma central associados com hemorragia têm sido descritos na literatura. Descrevemos um caso de neurocitoma central de uma paciente de 35 anos com apresentação atípica. A paciente havia procurado o hospital com quadro súbito de cefaléia, vômitos e rigidez de nuca, sugerindo a presença de hemorragia subaracnóidea. A ressonância magnética demonstrou volumosa massa no ventrículo lateral direito cujos perfis histológico e imuno-histoquímico eram condizentes com neurocitoma central, a ressecção cirúrgica foi realizada com sucesso, embora a paciente tenha evoluído para um quadro de ventriculite no pós-operatório. Salientamos a importância do estabelecimento do neurocitoma central como diagnóstico diferencial de pacientes com hemorragia intraventricular e discutimos as opções de tratamento para este tumor incomum.

  15. Medicina nuclear, tecnología de avanzada

    OpenAIRE

    1999-01-01

    ¿Qué es la medicina nuclear?/ ¿Por qué se llama medicina nuclear?/ ¿Cómo se producen las imágenes?/ ¿Son seguros los estudios?/ ¿Pueden realizarse los estudios en mujeres embarazadas o que están lactando?/ ¿Qué estudios se realizan y para que se utilizan?/ ¿Cuáles son los tratamientos con medicina nuclear?

  16. Nuclear power plants. Site choice; Usinas nucleoeletricas. Escolha de local

    Energy Technology Data Exchange (ETDEWEB)

    Atala, Drausio Lima

    2009-07-01

    This book establishes the standards for selection and development of criteria for evaluation of new nuclear sites in Brazil. The places where the new nuclear power plants will be installed must be adequate for construction and operation of the power plants will be submitted to Brazilian environmental and nuclear legislation of the Union, states and the local governments, besides to accomplish the world good practices of this activity.

  17. Pancreatectomía central: Relato de casos y descripción de la técnica

    OpenAIRE

    APODACA-TORREZ,Franz R.; Saad, Sarhan S; Goldenberg, Alberto [UNIFESP; Triviño,Tarcísio; LOBO,EDSON J

    2010-01-01

    Las técnicas convencionales de resección pancreática para el tratamiento de enfermedades neoplásicas, en la mayoría de las veces implican la extirpación de segmentos extensos del parénquima pancreático, existiendo como eventuales complicaciones a largo plazo, el surgimiento de insuficiencia pancreática endocrina o exocrina. La pancreatectomía central se constituye en una alternativa de resección pancreática, que limita esta resección solamente al sector comprometido, especialmente en las neop...

  18. La colección de tesis doctorales de derecho en la Universidad Central: 1869-1883

    OpenAIRE

    Miguel Alonso, Aurora; Raya Rienda, Alberto

    2010-01-01

    Este trabajo forma parte de un proyecto para dar a conocer las tesis doctorales defendidas en la Universidad Central de Madrid, durante el siglo XIX, en las seis Facultades entonces existentes: Filosofía y Letras, Ciencias, Derecho, Teología, Medicinay Farmacia. En concreto, en esta publicación se recopilan las tesis doctorales presentadas en la Facultad de Derecho, entre los años 1869 y 1883. Con anterioridad hemos publicado el catálogo de la Facultad de Farmacia a lo largo de todo el siglo ...

  19. Dieta e comportamento de forrageamento de Suiriri affinis e S. islerorum (Aves, Tyrannidae) em um cerrado do Brasil central

    OpenAIRE

    Leonardo E. Lopes

    2005-01-01

    Foi estudado o comportamento de forrageamento de Suiriri affinis (suiriri-do-cerrado) e S. islerorum (suiriri-da-chapada), duas espécies de Tyrannidae que ocorrem em sintopia nos cerrados do Brasil central. Durante o ano de 2003 foram registradas 188 observações de forrageamento para S. affinis e 150 para S. islerorum. Foram encontradas diferenças significativas entre as duas espécies em relação à altura e substrato de forrageamento, fitofisionomia utilizada e densidade da folhagem no local d...

  20. Análisis de fluctuaciones en reactores nucleares: modelos no lineales y no markovianos

    OpenAIRE

    1983-01-01

    El análisis de las fluctuaciones en reactores nucleares es hoy día un valioso instrumento de diagnosis y control del reactor sus fundamentos teóricos están enmarcados en la melanica estadística del no equilibrio y en la teoría de procesos estocásticos. Bajo estos supuestos se estudia en primer lugar los fundamentos de una descripción estocástica con ruidos externos e internos. En segundo lugar analizamos modelos de reactores no lineales con efecto de temperatura y ruidos externos. Es...

  1. Análisis de fluctuaciones en reactores nucleares: modelos no lineales y no markovianos

    OpenAIRE

    Rodríguez Díaz, Miguel Ángel

    2011-01-01

    RESUMEN: El análisis de las fluctuaciones en reactores nucleares es hoy día un valioso instrumento de diagnosis y control del reactor. Sus fundamentos teóricos están enmarcados en la mecánica estadística del no equilibrio y en la teoría de procesos estocásticos. Bajo estos supuestos se estudia en primer lugar los fundamentos de una descripción estocástica con ruidos externos e internos. En segundo lugar analizamos modelos de reactores no lineales con efecto de temperatura y ruidos externos. E...

  2. The Laguna Verde Central by it results in maintenance and operation consolidates it position of world class enterprise; La central Laguna Verde por sus resultados en mantenimiento y operacion consolida su posicion de empresa de clase mundial

    Energy Technology Data Exchange (ETDEWEB)

    Rivera C, A. [CFE, Central Laguna Verde, Km. 42.5 Carretera Cardel- Nautla, Veracruz (Mexico)

    2008-07-01

    This work has the objective of showing the results of the Laguna VerdeCentral in the maintenance and the operation that in the short term the generation of electricity in Mexico by nuclear means is a viable option, in virtue of their positioning like Company of World Class, when winning March 25, 2008 the National Prize of Quality with the more high qualification in the history of this prize, same that allows us to be very optimistic in increasing the possibility to that the Nuclear Industry in Mexico grows. The focus of the comparative graphs, with official data of the Comision Federal de Electricidad (CFE), it is so that it is observed that the Laguna Verde Central is above those the other types of generation like they are the Coal power stations, Thermoelectric, Hydroelectric, likewise they can see that we are for up of the Independent Producers of Energy. The information of the electric power generation is presented by reactors nuclear at world level that is growing, in having 31 Generating Units in the construction process that favors the decisions making in the Government federal, likewise contributed data of the increment projected for 2016 in the country of 380,102 GWh that equivalent to 63% of growth, where it exists without place to doubts a good opportunity for the nucleoelectricity. The Investment Works Program of Public Sector (POISE), it shows the information that 6,178 Mwe will be installed settled of a Non-defined Technology in Mexico, information that specifies the opportunity to be a viable option, because the one Plant Factor, the Production of Electric power, and the Variable Cost of Production, the energy generation by nuclear means is the more competitiveness. Finally this work stood out the effort that communitary works are developed to benefit to the society and the environment to be one Viable option not only for their high performance, or competitive for those more low costs, but also to improve the public opinion with the sustainable

  3. Designing a mini subcritical nuclear reactor; Diseno de un mini reactor nuclear subcritico

    Energy Technology Data Exchange (ETDEWEB)

    Escobedo G, C. R.; Vega C, H. R.; Davila H, V. M., E-mail: rafelaescobedo@hotmail.com [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Jardin Juarez 147, Col. Centro, 98000 Zacatecas, Zac. (Mexico)

    2015-10-15

    In this work the design of a mini subcritical nuclear reactor formed by means of light water moderator, uranium as fuel, and isotopic neutron source of {sup 239}PuBe was carried out. The design was done by Monte Carlo methods with the code MCNP5 in which uranium was modeled in an array of concentric holes cylinders of 8.5, 14.5, 20.5, 26.5, 32.5 cm of internal radius and 3 cm of thickness, 36 cm of height. Different models were made from a single fuel cylinder (natural uranium) to five. The neutron source of {sup 239}PuBe was situated in the center of the mini reactor; in each arrangement was used water as moderator. Cross sections libraries Endf/Vi were used and the number of stories was large enough to ensure less uncertainty than 3%. For each case the effective multiplication factor k{sub e}-f{sub f}, the amplification factor and the power was calculated. Outside the mini reactor the ambient dose equivalent H (10) was calculated for different cases. The value of k{sub eff}, the amplification factor and power are directly related to the number of cylinders of uranium as fuel. Although the average energy of the neutrons {sup 239}PuBe is between 4.5 and 5 MeV in the case of the mini reactor for a cylinder, in the neutron spectrum the presence of thermal neutrons does not exist, so that produced fissions are generated with fast neutrons, and in designs of two and three rings the neutron spectra shows the presence of thermal neutrons, however the fissions are being generated with fast neutrons. Finally in the four and five cases the amount of moderator is enough to thermalized the neutrons and thereby produce the fission. The maximum value for k{sub eff} was 0.82; this value is very close to the assembly of Universidad Autonoma de Zacatecas generating a k{sub eff} of 0.86. According to the safety and radiation protection standards for the design of mini reactor of one, two and three cylinders they comply with the established safety, while designs of four and five

  4. Centro Regional de Ciencias Nucleares (a Brazilian regional center for nuclear sciences) - activities report - 1999; Centro Regional de Ciencias Nucleares - relatorio de atividades - 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-01

    The annual activities report of 1999 of nuclear sciences regional center - Brazilian organization - introduces the next main topics: institutional relations; sectorial actions - logistic support and training, laboratory of radiation protection and dosimetry, laboratory of metrology, laboratory of chemical characterization; technical and scientific events; and financial resources and perspectives for 2000.

  5. Foreseeing techniques and control of emissions in thermal power plants. Workshop Latin American. [Selected Papers]; Control y tecnicas de prevision de las emisiones de centrales termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Saldana, R.; Morales, F.; Urrutia, M. [eds.] [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1996-12-31

    This document contains the conference proceedings of the Latin-American Workshop ``Control and Prevision Techniques of Emissions in Power Plants`` carried out in Cuernavaca, Mexico on June 1996, with the participation of representatives of Argentina, Chile, Guatemala, Colombia, Ecuador, Mexico, Nicaragua, Panama and Venezuela, as well as specialists from the European Union. The core issue analyzed in this workshop was the control and the evaluation techniques of polluting emissions in Power Plants [Espanol] Este documento contiene las memorias de conferencia del Taller Latinoamericano ``Control y tecnicas de prevision de las emisiones de centrales termoelectricas`` que se llevo a cabo en Cuernavaca, Mexico en junio de 1996. Participaron representantes de Argentina, Chile, Guatemala, Colombia, Ecuador, Mexico, Nicaragua, Panama y Venezuela, asi como especialistas de la Union Europea. El tema central tratado en este taller fue el control y tecnicas de evaluacion de las emisiones contaminantes en centrales termoelectricas

  6. Digital Systems Security in the nuclear scope; Sistemas Digitales de Seguridad en el ambito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Amado, I.

    2011-07-01

    Overall nuclear power plants and in particular the Spanish, work well, but to modernize and improve the operation of existing Spanish plants, perhaps the natural evolution is to use digital technologies.

  7. Conhecimento de enfermeiros de Neonatologia acerca do Cateter Venoso Central de Inserção Periférica

    Directory of Open Access Journals (Sweden)

    Marcela Patricia Macêdo Belo

    2012-02-01

    Full Text Available O Cateter Central de Inserção Periférica (PICC vem sendo utilizado como acesso venoso seguro para neonatos de risco. Objetivou-se descrever o conhecimento e prática dos enfermeiros das cinco unidades públicas de Terapia Intensiva Neonatal, de Recife-PE, sobre a utilização do PICC. A amostra foi composta por 52 enfermeiros; os dados foram coletados de janeiro a fevereiro de 2010. Nos resultados verificou-se que 64,8% dos enfermeiros não possuíam habilitação para inserção do PICC. Apenas duas unidades utilizavam o PICC rotineiramente. Sobre a indicação desse acesso, houve nível de acerto acima de 70%. Na unidade B apenas 8,3% dos enfermeiros referiram localização inicial adequada da ponta do cateter. Conclui-se que é necessário maior incentivo à capacitação dos enfermeiros para utilização do PICC.

  8. Fire protection system management in nuclear facilities: strengthening factor of integrated management system - a case study; Gestao de sistema de protecao contra incendio em instalacoes nucleares: fator de fortalecimento do sistema de gestao integrada - um estudo de caso

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Joao Regis dos

    2005-07-01

    The present study investigated and analyzed the importance of a system of integrated safety manage, environment and health in a nuclear installation, having as perspective, the fire protection manage. The inquiry was made using a qualitative research involving a case study, where the considered environment was the Reconversion and UO{sub 2} Plant of the Industrias Nucleares do Brasil (INB), located in Resende, Rio de Janeiro and the studied population, the managers and the staff directly involved with the aspects related to the safety of the industrial complex of the related company. The motivation for the research was the search of a bigger interaction of the questions related to the safety, environment and health in the nuclear industry having, as axle of the investigation, the fire protection. As a result, it was observed that in a nuclear installation, although dealing with diversified safety processes, integration is possible and necessary, since there are more reasons for integration than otherwise. (author)

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

    Science.gov (United States)

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

    2012-01-01

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

  10. Trets acústics de les vocals del català central

    Directory of Open Access Journals (Sweden)

    Agnès Rius-Escudé

    2014-11-01

    Full Text Available Presentem una proposta d’investigació basada en l’anàlisi acústica de les vocals i de la seva combinació en català central en parla espontània. Per portar-la a terme, hem utilitzat el Corpus oral de parla espontània (Font-Rotchés, 2006 i Rius-Escudé, en premsa. Els informants són d’ambdós sexes, d’edats compreses entre 18 i 80 anys, de professions diverses i procedents de diferents contrades de la varietat dialectal central, en un context de parla espontània real i genuïna. La metodologia serà experimental, empírica i quantitativa. Ens servirem de l’aplicació d’anàlisi i síntesi de veu praat, i del programa SPSS per comprovar la fiabilitat dels resultats. La finalitat d’aquesta investigació és que pugui esdevenir una aportació en el coneixement de la caracterització acústica de les vocals de la llengua catalana en parla espontània i que pugui facilitar-ne el desenvolupament d’aplicacions didàctiques que afavoreixin l’ensenyament-aprenentatge de la pronúncia del català als nous aprenents d’aquesta llengua en els diversos nivells educatius.

  11. Parasitosis y Micosis del Sistema Central como Causa de Epilepsia en Adultos

    Directory of Open Access Journals (Sweden)

    Alejandro Jiménez Arango

    1987-12-01

    Full Text Available

    Nos corresponde hoy tratar el tema de las micosis y parasitosis del sistema nervioso central en relación con uno de los múltiples síntomas o complejos sindromáticos que pueden ocasionar: la epilepsia, se trata de uno de los síntomas más frecuentes en estas enfermedades y, en general, en las enfermedades encefálicas, y es el resultado de múltiples procesos fisiopatológicos que se producen en el cerebro. Puede la epilepsia ser síntoma de una enfermedad aguda o subaguda, o puede ser una de las secuelas, y a veces la única, de una enfermedad cuyo proceso activo ya ha terminado.

    Con el objeto de buscar cierta coherencia en la presentación del tema, mencionaremos en primer lugar los procesos patológicos, síndromes y lesiones, varios de ellos comunes a muchas micosis y parasitosis, que pueden dar lugar al cuadro epiléptico. En seguida nos referiremos con mayor detalle a cuatro enfermedades o grupos de enfermedades que tienen particular importancia entre nosotros desde el punto de vista clínico y epidemiológico: las micosis, la toxoplasmosis del adulto, el paludismo cerebral y la cisticercosis.

    Como ha sido ampliamente expuesto, las micosis y parasitosis del sistema nervioso central comprenden un gran número de entidades...

  12. Nueva estación central de Varsovia, Polonia

    Directory of Open Access Journals (Sweden)

    Romanowicz, Arseniusz

    1977-10-01

    Full Text Available The inauguration of this station, one of the three long-distance stations in the city, has provided a series of advantages for the Capital, amongst which is the comfortable and fast access of the passengers to the canter of the city and the decongestion of urban transport systems. Regarding its architectonic dimensions, the building satisfactorily fulfills the two main purposes imposed from the very beginning of the planning stage —its integration in the urban surroundings and the street system— and at the same time it constitutes a visible landmark to guide the public and it has also been adapted to the different train, automobile and passenger routes, without interference and minimum runs. Regarding this second point, and thanks to the proper organization of itineraries, in the future the station will be able to hold a considerably larger number of passengers than foreseen in the project estimates without having to increase the number or size of the installations.La realización de esta Estación, una de las tres de larga distancia con las que cuenta la ciudad, ha supuesto una serie de ventajas para la capital, entre las que cabe destacar el cómodo y rápido acceso de los pasajeros al núcleo de la población, y la descongestión de los medios de transporte urbano. En cuanto a su configuración arquitectónica, el edificio cumple satisfactoriamente las dos principales premisas impuestas en los primeros momentos del planteamiento: su integración en el entorno urbano de la ciudad y en el sistema de calles, constituyéndose, al mismo tiempo, en un hito visible de orientación ciudadana; y la adecuación de los distintos tráficos de trenes, automóviles y viajeros, sin interferencias y con recorridos mínimos. Respecto a este segundo punto, y gracias a la correcta organización de las circulaciones, la estación podrá dar cabida en el futuro, sin necesidad de aumentar el número o tamaño de las instalaciones, a un número de viajeros

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

    Energy Technology Data Exchange (ETDEWEB)

    Espanol Villar, J.

    2013-07-01

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

  14. APLICACIÓN DEL ENFOQUE DE PROMOCIÓN DE LA SALUD EN LA REGIÓN CENTRAL DE OCCIDENTE DE COSTA RICA: LOS PRINCIPALES HALLAZGOS

    Directory of Open Access Journals (Sweden)

    MSc. Lidia Isabel Picado Herrera

    2013-08-01

    Full Text Available El enfoque en Promoción de la Salud es un eje técnico-político que busca brindar los medios y las herramientas necesarias a los actores sociales, para que ejerzan un mayor control sobre los determinantes que favorecen la salud. En el caso particular de la Región Central de Occidente de Costa Rica, se han desarrollado una serie de esfuerzos institucionales y comunales para posicionar este paradigma en el abordaje de la salud, en procura de reconstruir una cultura de salud desde una visión positiva. No obstante, se carecen de investigaciones que permitan conocer la situación real de su aplicación, en instituciones públicas, de la región citada. En este marco, surge la inquietud de indagar al respecto, con el propósito no solo de reflejar la realidad, sino también de aportar insumos que contribuyan a fortalecer la toma de decisiones, por parte de las respectivas autoridades de las instituciones objeto de estudio. El proceso de investigación evaluación utilizó un enfoque de estudio cualitativo, que permitió un acercamiento más integrador del objeto de estudio, al aplicar dos métodos de investigación evaluativa: investigación-exploratoria e investigación-acción. El artículo hace un recuento del proceso de investigación evaluativa realizada, donde integra los referentes teóricos-metodológicos utilizados, los principales hallazgos, las conclusiones y algunas recomendaciones generales derivadas de la investigación.

  15. Esquistossomose do sistema nervoso central relato de um caso

    Directory of Open Access Journals (Sweden)

    M. S. Ferreira

    1990-09-01

    Full Text Available O comprometimento do sistema nervoso na esquistossomose mansônica é evento raramente diagnosticado na evolução desta parasitose. Os autores descrevem o caso de uma paciente de 23 anos, natural de São Francisco-MG, que apresentava há duas semanas quadro de ceíaléia, vômitos em jato, febre e sonolência; o exame neurológico mostrava rigidez de nuca, paresia com hipertonia muscular bilateral em membros superiores, perda de motricidade e sensibilidade em membros inferiores. Não se palpava hepato-esplenomegalia. O exame do liqüido cefalorraquidiano (LCR mostrou hipoglicorraquia (28 mg%, hiperproteinorraquia (113 mg% e pleocitose acentuada (949 células/mm3, com predomínio de neutrófilos (70%, além de eosinofilorraquia (9%. A reação de imunofluorescência indireta para esquistossomose, no LCR, realizada em cortes de fígado com granuloma peri-ovular foi reagente (IgG: 1/16; IgM: 1/4. As pesquisas de fungos e b.a.a.r. no LCR, assim como a cultura para b.a.a.r. (após 60 dias e as reações imunológicas para neurocisticercose foram negativas. Uma tomografia computadorizada do cérebro e medula espinhal não evidenciou anormalidades. No exame parasitologico das fezes foi identificada a presença de ovos viáveis de S. mansoni. Instituiu-se tratamento com corticóides e praziquantel (60 mg/kg/dia; 7 dias tendo havido regressão das alterações do LCR, permanecendo entretanto seqüelas neurológicas graves (paraplegia e bexiga neurogênica.

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

    OpenAIRE

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

    2010-01-01

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

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

    Directory of Open Access Journals (Sweden)

    Nei Peixoto

    2002-09-01

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

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

    Institute of Scientific and Technical Information of China (English)

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

    2012-01-01

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

  19. Las redes de drenaje de los rios Alberche y Guadarrama como indicadores estructurales del Sistema Central Espanol

    Directory of Open Access Journals (Sweden)

    Martín Escorza, C.

    2003-08-01

    Full Text Available The network of the Alberche and Guadarrama rivers, obtained by a semicuantitative method, shows that on the granitic and metamorphic rocks of the Spanish Central System exist circular alignments, until now detected by analysis of satellite image. Such alignments are located in the sub-geological system of the Sierra de Guadarrama, and they coexist with to already known rectilinear alignments. In the sub-westem system, Sierra de Gredos, are detected rectilinear alignments. The circular structures of Sierra de Guadarrarna would have a relationship to geological processes still unknown after the Hercynian Orogeny but before of the Oligocene.Utilizando una metodología semicuantitativa, las redes de drenaje de los ríos Alberche y Guadarrama ponen de manifiesto que existen alineaciones circulares sobre las rocas graníticas y metamórficas de la Cordillera Central, cuya presencia hasta ahora se había detectado por análisis de imagen de satélite. Tales alineaciones se sitúan en el subsistema geológico de la Sierra del Guadarrama, en donde coexisten con alineaciones rectas ya conocidas. En el subsistema occidental, la Sierra de Gredos, se detectan alineaciones rectas. Las estructuras circulares de la Sierra de Guadarrama tendrían su origen en relación con procesos geodinámicos todavía desconocidos, ocurridos con posterioridad a la Orogenia Hercínica, pero antes del Oligoceno.

  20. Logistica de coleta e transporte de material biologico e organizacao do laboratorio central no ELSA-Brasil

    Directory of Open Access Journals (Sweden)

    Ligia G Fedeli

    2013-06-01

    Full Text Available O Estudo Longitudinal de Saúde do Adulto (ELSA-Brasil é um estudo de coorte multicêntrico com o objetivo de identificar os fatores de risco associados ao diabetes tipo 2 e à doença cardiovascular na população brasileira. O artigo descreve as estratégias de coleta, processamento, transporte e de controle de qualidade dos exames de sangue e urina no ELSA. O estudo optou pela centralização dos exames em um único laboratório. O processamento das amostras foi realizado nos laboratórios locais, reduzindo o peso do material a ser transportado e diminuindo os custos do transporte para o laboratório central no Hospital da Universidade de São Paulo. O estudo incluiu exames para avaliação de diabetes, resistência à insulina, dislipidemias, alterações eletrolíticas, hormônios tireoidianos, ácido úrico, alterações de enzimas hepáticas, inflamação e hemograma completo. Além desses exames, foram estocados DNA de leucócitos, amostras de urina, plasma e soro. O laboratório central realizou aproximadamente 375.000 exames.

  1. Advecciones de polvo africano sobre la costa central venezolana y sus efectos sobre el desarrollo de la nubosidad

    Directory of Open Access Journals (Sweden)

    Estatio José Gutiérrez Quevedo

    2006-01-01

    Full Text Available Empleando el índice de aerosol, determinado a través de las mediciones del sensor TOMS, se ha realizado un análisis del comportamiento de las magnitudes del parámetro sobre la costa central venezolana en base al período 19972005; los resultados señalaron que se presentaron los máximos valores del índice en los meses de Julio y Agosto correspondientes a la temporada de lluvias. Para este período las masas de aire cargadas de partículas de polvo llegan al Caribe provenientes del desierto del Sahara, como lo demuestra el mapa con la distribución espacial de la mediana del índice para el mes de julio, por el contrarío existe una disminución sustancial en la cantidad de partículas dispersas sobre la troposfera venezolana en la temporada seca en donde las nubes de polvo se desplazan generalmente desde el Sahel. Los productos atmosféricos del sensor MODIS han sido utilizados para determinar la relación entre la concentración de aerosoles y el comportamiento de la nubosidad, presentando ésta una disminución en su desarrollo en presencia de valores altos del índice de aerosol principalmente en los meses de abril y mayo.

  2. LA INFLACIÓN Y EL BANCO CENTRAL: ECONOMÍA DE UN EMISOR INDEPENDIENTE

    Directory of Open Access Journals (Sweden)

    Carlos Esteban Posada P

    2002-06-01

    Full Text Available En este artículo formulo una relación teórica de fundamento microeconómico entre un Banco privado monopólico y la tasa óptima de inflación. La relación propuesta es la base para establecer una condición suficiente para la independencia de la Banca Central. La parte central del artículo lo consti tuye un modelo que expone las condiciones que se requieren para igualar las tasas óptimas, social y privada, de la inflación. A pesar de la sencillez del argumento, se pueden deducir algunas proposiciones de "Economía Constitucional".

  3. The nuclear energy in the seawater desalination; La energia nuclear en la desalacion de agua de mar

    Energy Technology Data Exchange (ETDEWEB)

    Moreno A, J.; Flores E, R.M. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2004-07-01

    In general, the hydric resources of diverse regions of the world are insufficient for to satisfy the necessities of their inhabitants. Among the different technologies that are applied for the desalination of seawater are the distillation processes, the use of membranes and in particular recently in development the use of the nuclear energy (Nuclear Desalination; System to produce drinkable water starting from seawater in a complex integrated in that as much the nuclear reactor as the desalination system are in a common location, the facilities and pertinent services are shared, and the nuclear reactor produces the energy that is used for the desalination process). (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-12-31

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

  5. Microdureza del esmalte dental en incisivos centrales permanentes de dos genotipos bovinos

    Directory of Open Access Journals (Sweden)

    Jorge Cabrera A

    2011-04-01

    Full Text Available Objetivo. Evaluar la microdureza del esmalte dental de novillos criollos de origen patagónico y cruza índica criados en ambientes diferentes. Materiales y métodos. Se utilizaron dientes incisivos centrales derechos de novillos adultos: ocho Criollos Patagónicos (GCP y siete Cruzas Índicas (GCI. Para cada diente se definió una transecta central recorriendo el diente desde el borde externo del esmalte hacia la dentina y se midió la dureza en tres profundidades equidistantes: a 30 μ del borde exterior (P1, a 30 μ previos a la conexión amelodentinaria (P3 y P2 equidistante entre P1 y P3. Las mediciones de microdureza se realizaron con un microdurómetro Shimadzu modelo HMV-2 y se expresaron en unidades Vickers. Para el análisis se utilizó un modelo de regresión aleatoria. Se empleó el criterio de información de Akaike para la elección de la estructura de las matrices asociadas a los efectos aleatorios. Para el análisis estadístico se empleó el procedimiento PROC MIXED de SAS, y un nivel de significación del 5%. Resultados. No se detectó falta de paralelismo entre los grupos (p>0.05, con lo cual se ajustaron rectas de igual pendiente en cada grupo. La dureza media del esmalte disminuyó al aumentar la profundidad de la medición para ambos genotipos. Se observó heterogeneidad en la variabilidad de los grupos. Conclusiones. El GCP presentó mayor dureza pero fue el de mayor variabilidad. Se confirma la disminución de la dureza media con el aumento de la profundidad en el esmalte independientemente del genotipo y el ambiente.

  6. Analgesia e sedacao durante a instalacao do cateter central de insercao periferica em neonatos

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    Priscila Costa

    2013-08-01

    Full Text Available Objetivou-se caracterizar as estratégias de analgesia e sedação em neonatos submetidos à instalação do cateter central de inserção periférica (CCIP e relacioná-las ao número de punções venosas, duração do procedimento e posicionamento da ponta do cateter. Estudo transversal com coleta prospectiva de dados, realizado em uma unidade de cuidados intensivos neonatais de um hospital privado na cidade de São Paulo, no período de 31 de agosto de 2010 a 01 de julho de 2011, em que foram avaliadas 254 inserções do CCIP. A adoção de estratégias analgésicas ou sedativas ocorreu em 88 (34,6% instalações do cateter e não esteve relacionada ao número de punções venosas, duração do procedimento ou posicionamento da ponta do cateter. As estratégias mais frequentes foram a administração endovenosa de midazolam em 47 (18,5% e fentanil em 19 (7,3% inserções do cateter. Recomenda-se maior adoção de estratégias analgésicas antes, durante e após o procedimento.

  7. Earthquake-proof plants; Centrales a prueba de terremotos

    Energy Technology Data Exchange (ETDEWEB)

    Francescutti, P.

    2008-07-01

    In the wake of the damage suffered by the Kashiwazaki-Kariwa nuclear power plant as a result of an earthquake last July, this article looks at the seismic risk affecting the Spanish plants and the safety measures in place to prevent it. (Author)

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

    OpenAIRE

    Ossa Vásquez, Karla Andrea

    2008-01-01

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

  9. A ínsula e o conceito de bloco cerebral central The insula and the central core concept

    Directory of Open Access Journals (Sweden)

    Guilherme Carvalhal Ribas

    2007-03-01

    Full Text Available A caracterização anatômica de regiões encefálicas topograficamente bem definidas é particularmente útil para a prática neurocirúrgica por propiciar melhor compreensão da tridimensionalidade das suas estruturas e das lesões que as acometem, e por incitar uma maior sistematização dos seus acessos cirúrgicos. Neste sentido, se destaca no interior de cada hemisfério cerebral, um verdadeiro bloco único composto externamente pela ínsula, internamente pelos núcleos da base e tálamo, e que abriga no seu interior a cápsula interna. Com uma conformação predominantemente biconvexa e disposto entre a cisterna silviana e as cavidades ventriculares supratentoriais, esse bloco cerebral central morfologicamente se caracteriza como uma cabeça de cada metade do tronco encefálico, encoberta por todo o manto neocortical do seu hemisfério ao qual se une através de verdadeiros istmos constituídos pelos prolongamentos das diferentes partes da cápsula interna. Anteriormente e sob o sulco limitante anterior da ínsula se dispõem as fibras que compõem o ramo anterior da cápsula interna, superiormente e sob o seu sulco limitante superior se dispõem as fibras restantes do ramo anterior e as do joelho e do ramo posterior, entre as quais se destacam em importância funcional as fibras piramidais córtico-espinhais, e sob o sulco limitante inferior da ínsula se dispõem as partes retro e sub-lentiformes da cápsula interna, que englobam as radiações auditiva e visual. Lateralmente o bloco cerebral central tem a ínsula como um verdadeiro escudo externo das principais estruturas cerebrais subcorticais. As escolhas dos acessos microneurocirúrgicos às lesões relacionadas com o bloco cerebral central devem ter como maior preocupação as suas relações topográficas com o tálamo e com as fibras da cápsula interna.The caracterization of well defined and circumscribed brain regions is particularly useful for the neurosurgical practice once

  10. Desafios no estudo de famílias nucleares: etapas iniciais de análise Challengers in nuclear family studies: first steps in data analysis

    Directory of Open Access Journals (Sweden)

    Cláudia Lúcia de Moraes Forjaz

    2011-12-01

    Full Text Available Os estudos em famílias nucleares possibilitam a avaliação da existência de agregação familiar numa dada característica, permitindo avaliar o quanto da variação dessa característica na população pode ser atribuída à variação genética existente entre os sujeitos. Os resultados desses estudos possibilitam a elaboração de estratégias de intervenção mais eficientes e direcionadas, além de serem o ponto de partida para estudos mais complexos de epidemiologia genética, como a identificação de genes responsáveis pela característica em análise. Nas áreas de Ciências do Desporto e Educação Física, alguns estudos têm sido realizados para verificar a existência de agregação familiar e a influência genética em traços relacionados a estados de saúde, atividade e desempenho físicos. Entretanto, esses esforços revelam-se escassos em populações lusófonas e são, praticamente inexistentes, na população brasileira. Dessa forma, o presente artigo teve como propósito abordar, de forma simples e introdutória, aspectos importantes de estudos em famílias nucleares. Para tanto, foram analisadas as duas fases iniciais dos estudos de Epidemiologia Genética, ou seja, a identificação e quantificação da agregação familiar e da heritabilidade. As diferentes etapas de análise foram exemplificadas com dados reais, coletados em famílias nucleares pertencentes a um estudo realizado na cidade de Muzambinho-MG. Espera-se que esse artigo forneça subsídios e estímulo aos pesquisadores iniciantes neste tipo de investigação.Studies with nuclear families allow the identification of familiar aggregation, as well as the estimation of how much of the variability in a characteristic might be attributed to genetic differences among subjects. Results from these studies are starting points for more complex genetic research, including the identification and relevance of candidate genes. In Sport Science, studies have analyzed the

  11. INDIAN POINT. Processus de reconversion d'une centrale nucléaire (NY, USA)

    OpenAIRE

    Di, Capua Davide

    2012-01-01

    Autrefois symbole absolu de la maîtrise de l'homme sur la nature, les centrales nucléaires obsolètes présentent à ce jour un défi non négligeable, à savoir le démantèlement de ces installations ainsi que la requalification territoriale de leurs emprises spatiales. La présence des centrales nucléaires produit un équilibre urbain entre la centrale et son environnement à différentes échelles. Cette relation urbaine s'établit sur plusieurs fronts, premièrement par la contribution du développement...

  12. Factores que inciden sobre el tiempo de permanencia de un catéter endovenoso central Factors that affect the dwell time of a central venous catheter

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    H. Bello-Villalobos

    2006-06-01

    Full Text Available Objetivo: Determinar los factores que inciden en el tiempo de permanencia de un catéter endovenoso central. Antecedentes: En el paciente con cáncer existen factores propios del estado de inmunocompromiso por el tumor y los efectos colaterales de su tratamiento que aumentan la probabilidad de infección y consecuentemente reducen el tiempo de uso de un catéter. Sujetos: Se integró una cohorte de 306 pacientes con cáncer, con una edad promedio de 59 ± 14,5 años. Intervenciones: Se definió tiempo cero como el día de colocación del catéter. Diariamente se buscaron signos clínicos de infección por catéter, con toma de hemocultivos simultáneos cada 7 días. El desenlace primario fue infección del catéter y el alternativo fin de tratamiento, obstrucción o fallecimiento del paciente. Se comparó el tiempo de permanencia del catéter infectado vs no infectado y su relación con factores de riesgo potenciales. Resultados: Se colocaron 306 catéteres para un total de 4.043 días/catéter. Se infectaron 25 (8,2%. La sobrevida media global fue de 50 días. Se encontró que a mayor tiempo de permanencia, mayor fue la incidencia de infección. En el análisis de sobrevida ajustado, la presencia de infección a distancia (OR = 4,71, IC95% = 1,7-10,1, p = 0,002 fue el factor que mostró una asociación significativa. Conclusiones: El tiempo de vida útil de un catéter es amplia, limitada por la presencia de infección a distancia como factor de riesgo potencial de infección por catéter.Objective: To determine the factors that affect the dwell time of a central venous catheter. Background: The own immunodeficiency in cancer patient and the collateral effects of their treatment increase the probability of infection and reduce the time of use of a catheter. Subjects: Incipient cohort of 306 patients with cancer, with an average age of 59 ± 14.5 years. Interventions: Time zero like the day of the placement of the catheter was defined. Daily

  13. El tarwi o chocho: una de las principales fuentes de proteína vegetal de las comunidades indígenas de los Andes Centrales

    OpenAIRE

    PLANCHUELO Ana m.; Fuentes, Esteban P.

    2005-01-01

    El lupino andino (Lupinus mutabilis Sweet) conocido también como tarwi o chocho, es una especie de leguminosa nativa de los Andes Centrales. Su domesticación se remonta a los principios de la cultura Nazca y desde ese entonces hasta la actualidad el cultivo está ampliamente difundido en las laderas montañosas y en los altos valles de Ecuador, Perú y Bolivia. La importancia del lupino para las comunidades andinas prehispánicas quedo documentada en pinturas de cerámicas y en tributos encontrado...

  14. Sede central de LENOX, New Jersey - EE. UU.

    Directory of Open Access Journals (Sweden)

    Hellmuth, George

    1979-10-01

    Full Text Available The main headquarters of the Company, recently built in Lawrence Township, New Jersey, meets every requirement of ecological adaptation, ease of function, optimal and varied natural lighting convenient vertical and horizontal traffic, etc, necessary for a modern administrative and office compound. The layout is based on an octagonal module. The bearing elements are structural metal, the outside walls are prefab concrete and glass shapes, the glazing being insulating tinted glass, partitions are flexible and do not reach the ceiling. Al! this, and the design of vertical cores (lifts-stairways and amenities and services, makes this building an excellent plant, satisfying demands imposed by the owner.

    El edificio rector de la empresa, recientemente construido en Lawrence Township, New Jersey, reúne todas las condiciones de ambientación ecológica, comodidad de funcionamiento, óptima y variada iluminación natural, fáciles comunicaciones verticales y horizontales, etc. que se requieren para un moderno centro administrativo y de oficinas. Se ha utilizado el módulo octogonal, en planta, la estructura metálica como elemento resistente, los cerramientos a base de placas prefabricadas de hormigón y cristal coloreado aislante, divisiones móviles de altura media y núcleos verticales de escaleras, ascensores y servicios, con lo que se ha logrado un resultado excelente, que satisface las exigencias propuestas por la entidad propietaria.

  15. Data mining in the study of nuclear fuel cells; Mineria de datos en el estudio de celdas de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Medina P, J. A. [Universidad Autonoma de Campeche, Av. Agustin Melgar s/n, Col. Buenavista, 24039 San Francisco de Campeche, Campeche (Mexico); Ortiz S, J. J.; Castillo, A.; Montes T, J. L.; Perusquia, R., E-mail: j.angel.mp@hotmail.com [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    In this paper is presented a study of data mining application in the analysis of fuel cells and their performance within a nuclear boiling water reactor. A decision tree was used to fulfill questions of the type If (condition) and Then (conclusion) to classify if the fuel cells will have good performance. The performance is measured by compliance or not of the cold shutdown margin, the rate of linear heat generation and the average heat generation in a plane of the reactor. It is assumed that the fuel cells are simulated in the reactor under a fuel reload and rod control patterns pre designed. 18125 fuel cells were simulated according to a steady-state calculation. The decision tree works on a target variable which is one of the three mentioned before. To analyze this objective, the decision tree works with a set of attribute variables. In this case, the attributes are characteristics of the cell as number of gadolinium rods, rods number with certain uranium enrichment mixed with a concentration of gadolinium, etc. The found model was able to predict the execution or not of the shutdown margin with a precision of around 95%. However, the other two variables showed lower percentages due to few learning cases of the model in which these variables were or were not achieved. Even with this inconvenience, the model is quite reliable and can be used in way coupled in optimization systems of fuel cells. (Author)

  16. Is there redundancy in bioengineering for molluscan assemblages on the rocky shores of central Chile? ¿Existe redundancia en la bioingeniería de los ensambles de moluscos de las costas rocosas de Chile central?

    Directory of Open Access Journals (Sweden)

    BRENDAN P KELAHER

    2007-06-01

    través de sus propias estructuras físicas e incrementan la diversidad local. En costas rocosas existen grandes solapamientos en la composición de las comunidades asociadas a bioingenieros que forman habitats frondosos (algas o mitílidos. Nosotros investigamos la potencial redundancia en la provisión de este tipo de habitat comparando ensambles faunísticos asociados a mantos de Perumytilus purpuratus y frondas de Corallina officinalis var. chilenis, Gelidium chilense y Gastroclonium cylindricum. En tres oportunidades, entre septiembre de 2003 y enero de 2004, muestreamos ensambles de moluscos asociados a cada uno de estos bioingenieros, en alturas de mareas similares en dos áreas rocosas de Chile central. De las 31 especies de moluscos identificados, 30 fueron encontrados en Corallina y 19-22 fueron identificados en los otros habitat. El conjunto de especies asociado a cada bioingeniero se sobrepone ampliamente, demostrando el potencial de redundancia en la provisión de habitat y poca especificidad de habitat. Sin embargo, análisis multivariados y univariados mostraron que los bioingenieros, con excepción de Gastroclonium, contenían un ensamble de moluscos único en al menos uno de los periodos de muestreo, ya sea en la variación en la frecuencia de ocurrencia, riqueza y abundancia total. Estudios recientes han destacado diversos procesos antropogénicos y naturales que influencian directamente la diversidad y composición de especies en bioingenieros de costas rocosas. Se demuestra que para la costa de Chile central la pérdida de cualquier de los bioingenieros analizados no alteraría sustancialmente el conjunto total de especies de moluscos, alojados en ellos. Sin embargo, la pérdida de cualquier bioingeniero, excepto Gastroclonium, resultaría en una disminución local de la biodiversidad debido a que cada uno de los ensambles de moluscos en Perumytilus, Corallina y Gelidium, contiene una estructura comunitaria significativamente diferente, en al menos

  17. Characterization of Patients with Central Nervous System Infections Caracterización de pacientes con infecciones del sistema nervioso central

    Directory of Open Access Journals (Sweden)

    Benigno Figueiras Ramos

    2011-07-01

    agentes causales que las producen. Objetivo: caracterizar a pacientes con infecciones del sistema nervioso central. Métodos: estudio descriptivo de serie de casos realizado en el Hospital “Dr. Gustavo Aldereguía Lima” de Cienfuegos a pacientes con infecciones del sistema nervioso central, desde enero del 2002 al 31 de diciembre del 2006. Se analizaron variables como: edad, sexo, estadía, fecha, manifestaciones clínicas, exámenes utilizados para el diagnóstico, condiciones predisponentes, gérmenes más frecuentes y evolución final. Resultados: la media de edad fue 35,65 años con predominio discreto del sexo femenino y la estadía de 5 días; ocurrieron 22 fallecimientos (6,9 % de letalidad, fundamentalmente por meningoencefelitis bacteriana; la meningoencefalitis linfocitaria fue la más frecuente; el grupo de edad más afectado el de 20 a 29 años. En los meses desde julio hasta octubre tuvo mayor incidencia la meningoencefalitis linfocitaria y de enero a diciembre la bacteriana. Los síntomas y signos más frecuentes fueron: cefalea (92,1 %, fiebre (82,7 %, meningismo (67,6 % y vómitos (37,7 %; el recurso clínico y el estudio del líquido cefalorraquídeo fueron los más empleados para el diagnóstico. Los factores predisponentes fueron neumonía, sinusitis y alcoholismo; el S. pneumoniae resultó el germen aislado con más frecuencia; la E. Coli mostró mayor letalidad. Conclusiones: haber presentado degradación de la conciencia (OR=41,735, lesiones purpúricas (OR=6,641 o padecer de una meningoencefalitis bacteriana (OR=22,958, se asociaron de forma independiente con el riesgo de morir.

  18. Diversidad y aspectos biológicos de abejas silvestres de un ambiente urbano y otro natural de la región central de Santa Fe, Argentina

    Directory of Open Access Journals (Sweden)

    Milagros DALMAZZO

    2010-01-01

    Full Text Available El objetivo del presente trabajo fue relevar el elenco de abejas silvestres en la región central de Santa Fe y comparar la diversidad de especies y aspectos biológicos en dos ambientes de una misma región. Las abejas fueron colectadas en el estrato herbáceo de la Reserva Universitaria “Escuela Granja” de la localidad Esperanza, y en la zona urbana de la localidad Susana, ambas ubicadas dentro de la Provincia Fitogeográfica del Espinal. La colecta se realizó en octubre, noviembre y diciembre de 2004 y en enero, febrero y marzo de 2005, registrando las especies vegetales sobre las que se capturaron. Se colectaron 277 ejemplares en total, de los cuales se identificaron 62 especies (27 géneros en 5 familias. Las curvas de rarefacción indican una tasa de acumulación de especies mayor para la Reserva Ecológica, los índices de diversidad de Shannon son 3,25 para la Reserva Ecológica y 2,64 para la Zona Urbana. Para la comparación de las comunidades en ambos sitios, las abejas fueron clasificadas en tres categorías según la especialización en el uso del recurso floral, sustrato de nidificación y comportamiento social. Se observó una asociación entre los grupos especialistas y de nidificación en el suelo con el ambiente natural, y por otro lado, las especies generalistas y de nidificación en cavidades con el ambiente urbano. No se identificaron diferencias, en cuanto al tipo de comportamiento social de las especies, entre ambos sitios.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  20. Perception of the nuclear energy in Mexico; Percepcion de la energia nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Xolocostli M, J.V.; Alonso V, G.; Gomez T, A.M.; Palacios H, J.C. [ININ, Carretera Mexico-Toluca s/n, La Marqesa, 52750 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: vxm@nuclear.inin.mx

    2007-07-01

    From their beginnings the Nuclear Energy has generated a lot of polemic, since on one hand it was seen as something completely harmful, due to the making of atomic weapons and those effects of the radiation (Hiroshima and Nagasaki). But on the other hand it has been saying that it could be the 'Panacea' of the humanity like an inexhaustible source of energy, this brought that a countless of reactors was built for the electric power production at world level, unfortunately some accidents as that of Chernobyl (Former Soviet Union 1986) as well as the contribution of the media of the fear toward the nuclear energy made that it was formed a barrier of the public opinion toward all that has to do with the nuclear energy, the construction of new power stations one came below and even in some countries the environmentalist organizations achieved their governments to close some power stations. In the last years the concern for the global heating and the climatic change has put in the world calendar the use of the nuclear energy again, by means of the new designs of advanced reactors with more safety measures, more efficient and economic. In several countries the public opinion is looking to the nuclear energy with good eyes, reason by a resurgence is glimpsed from the nuclear energy to great scale, so it is so several countries they have already begun the construction of new advanced reactors ones (Japan, China, Finland) and some included one already has them in operation. In Mexico, it is ignored to certain science which is the real posture of the public opinion with regard to this topic so controversial, reason why it was carried out this study to know the perception of the public in general with regard to this topic, as well as the convenience of enlarging the infrastructure of electric power generation in our country by means of this energy type. (Author)

  1. Methodology of complexity analysis of Emergency Operating Procedures for Nuclear Power Plants; Metodologia de analisis de complejidad de Procedimientos de Operacion de Emergencia de Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Martorell, P.; Martorell, S.; Marton, I.; Pelayo, F.; Mendizabal, R.

    2013-07-01

    The Emergency Operating Procedures (SOPs) set out the stages and contain actions to be executed by an operator to respond to an emergency situation. Methodologies are being developed to assess aspects such as complexity, completeness and vulnerability of these procedures. A methodology is presented in this paper to develop a network topology POE and analysis focused on the same complexity as a fundamental attribute.

  2. Desarrollo de nuevos aceros ferríticos ODS para aplicaciones nucleares

    OpenAIRE

    García Rodríguez, Nerea

    2016-01-01

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

  3. Training in nuclear engineering companies; La formacion en las empresas de ingenieria del ambito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Perezagua, R. L.

    2013-03-01

    The importance of training is growing in all business areas and fields and especially in hi-tech companies like engineering firms. Nuclear projects are highly multidisciplinary and, even in the initial awarding and pre-construction phases, need to be staffed with personnel that is well-prepared and highly-qualified in areas that, in most cases, are not covered by university studies. This article examines the variables that influence the design of specific training for nuclear projects in engineering firms, along with new training technologies (e-learning) and new regulatory aspects (IS-12). (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

  5. Safety assessment of nuclear medicine practice using the Risk Matrix Method; Evaluaciones de seguridad de la practica de medicina nuclear utilizando el metodo de Matrices de Riesgo

    Energy Technology Data Exchange (ETDEWEB)

    Cruz, Dumenigo; Cruz, Yoanis; Soler, Karen, E-mail: cruz@orasen.co.cu [Centro Nacional de Seguridad Nuclear (CNSN), La Habana (Cuba); Guerrero, Mayka, E-mail: mayka@infomed.sld.cu [Centro de investigaciones Medico Quirurgicas (CIMEQ), La Habana (Cuba)

    2013-10-01

    This paper presents the main results from the application of the methodology of Risk Matrices in a hypothetical service / department of the Nuclear medicine that realize metabolic radiotherapy treatment and diagnostic studies with {sup 131}I and {sup 99} m Tc and {sup 18}F. We could identify major equipment failures and human errors that could potentially lead to a accident in practice. For each analyzed initiating events evaluated the frequency of occurrence, identified key existing defenses to avoid the accident and assessed the potential consequences of an accident if this comes to fruition. With this methodology we could identify which accident sequences increased risk and to propose means to reduce the risk in such cases. As a result of this work was developed the 'RMA Nuclear Medicine' computer tools that will apply this methodology in nuclear medicine services that need to do similar risk assessments.

  6. Calibration and intercomparison methods of dose calibrators used in nuclear medicine facilities; Metodos de calibracao e de intercomparacao de calibradores de dose utilizados em servicos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Alessandro Martins da

    1999-07-01

    Dose calibrators are used in most of the nuclear medicine facilities to determine the amount of radioactivity administered to a patient in a particular investigation or therapeutic procedure. It is therefore of vital importance that the equipment used presents good performance and is regular;y calibrated at a authorized laboratory. This occurs of adequate quality assurance procedures are carried out. Such quality control tests should be performed daily, other biannually or yearly, testing, for example, its accuracy and precision, the reproducibility and response linearity. In this work a commercial dose calibrator was calibrated with solution of radionuclides used in nuclear medicine. Simple instrument tests, such as response linearity and the response variation of the source volume increase at a constant source activity concentration, were performed. This instrument can now be used as a working standard for calibration of other dose calibrators/ An intercomparison procedure was proposed as a method of quality control of dose calibrators used in nuclear medicine facilities. (author)

  7. Quality assessment of radiopharmaceuticals in nuclear medicine services at Northeast states, Brazil; Avaliacao da qualidade de radiofarmacos em servicos de medicina nuclear de estados da regiao nordeste

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, Wellington Gomes de

    2012-07-01

    The radiopharmaceuticals are used in the field nuclear medicine services (NMS) as tracer in the diagnoses and treatment of many diseases. Radiopharmaceuticals used in nuclear medicine and usually have a minimum of pharmacological effect. The procedures for labelling Radiopharmaceuticals should be observed in order to minimize risks to patients, employees and individuals from the public, and to be administered in humans, must be sterile and free of pyrogens and possess elements all measures of quality controls required a conventional drug. The 'Agencia Nacional de Vigilancia Sanitaria (ANVISA)' in its 'Resolucao de Diretoria Colegiada' (RDC) No. 38 of June 4{sup th} 2008, decided that the NMS must perform quality control in the generators eluate and radiopharmaceuticals according to recommendations of manufacturers and scientific evidence accepted by ANVISA. Thus, this study proposes to evaluate the quality of the generator {sup 99M}o-{sup 99m}Tc eluate and radiopharmaceuticals labeled with {sup 99m}Tc used in most NMS of some states in the Northeast, in relation to radionuclide, chemical, radiochemical purity and pH and promote the inclusion of procedure for quality control of radiopharmaceuticals in routine NMS. The results show that 90% radionuclidic purity, 98.2% purity chemical and radiochemical purity of 46% and 100% of the eluates are in agreement with international pharmacopoeias; already radiopharmaceuticals showed 82.6% purity and all radiochemical pH values are also in accordance with international pharmacopoeias. Even with so many positive results, staff the majority of MNS was not able to perform the quality control of the eluates and radiopharmaceuticals. Showing the importance of implementing of quality control programs of the eluates and radiopharmaceuticals in nuclear medicine. (author)

  8. La crisis nuclear de Corea del Norte: Sky News o Fox News

    Directory of Open Access Journals (Sweden)

    Pablo Rodríguez

    2014-01-01

    Full Text Available En este artículo analizamos, desde la teoría del framing, la información ofre - cida por los dos canales de noticias 24 horas del grupo News Corporation, Sky News y Fox News, con relación a la crisis nuclear de Corea del Norte en el periodo 9 -23 de abril de 2013. Nos centramos en aspectos como la “foxificación”, la presencia de expertos militares en los bloques de noti - cias y los encuadres informativos. En el caso de Sky News, la información se ofrece desde el prisma de los sucesos a nivel nacional debido al tiempo dedicado a la polémica con el documental del programa “Panorama” de la BBC. El tratamiento de la crisis nuclear en Fox News se traduce en constantes críticas a las políticas militares llevadas a cabo por Corea, la exalta - ción patriótica de los Estados Unidos poniendo el acento sobre el sistema defensivo y todo ello rodeado de una crítica feroz a la Administración Oba - ma por no promover una intervención militar en el conflicto.

  9. APLICACIONES CLÍNICAS DE LAS TÉCNICAS NUCLEARES EN EL ESTUDIO DEL SINCRONISMO VENTRICULAR / Clinical applications of nuclear techniques in the study of ventricular synchronism

    Directory of Open Access Journals (Sweden)

    Amalia Peix González

    2012-07-01

    Full Text Available ResumenTécnicas incruentas como la ecocardiografía, la resonancia magnética nuclear y los estudios de Medicina Nuclear (ventriculografía radioisotópica y gammagrafía de perfusión miocárdica con tomografía de emisión de fotón único, proporcionan información indirecta sobre el sincronismo ventricular cuando se utilizan parámetros de contractilidad mecánica. El análisis de fase de Fourier es un instrumento útil para el empleo de técnicas nucleares con este propósito y se ha aplicado, tanto en la ventriculografía radioisotópica como en la gammagrafía de perfusión. En este trabajo se presenta una revisión en el tiempo de los fundamentos y aplicaciones clínicas de las técnicas nucleares en el estudio del sincronismo ventricular. En la actualidad es la gammagrafía SPECT-gatillada, dentro de las técnicas nucleares, la más utilizada, por la posibilidad que ofrece de evaluar perfusión, función y sincronismo intraventricular en el mismo examen. / AbstractNoninvasive techniques such as echocardiography, nuclear magnetic resonance imaging and nuclear medicine studies (radionuclide ventriculography and myocardial perfusion scintigraphy with single photon emission tomography, provide indirect information about ventricular synchronism when parameters of mechanical contractility are used. The Fourier phase analysis is a useful tool for the use of nuclear techniques for this purpose, and has been applied in both radionuclide ventriculography and perfusion scintigraphy. A review in time of the basics and clinical applications of nuclear techniques in the study of ventricular synchronism is presented in this article. Nowadays, the gated-SPECT scintigraphy is the most common among nuclear techniques because it allows assessing perfusion, function, and intraventricular synchronism in the same test.

  10. El Central Colombia: inicios de industrialización en el Caribe colombiano

    Directory of Open Access Journals (Sweden)

    María Teresa Ripoll de Lemaitre

    1997-05-01

    Full Text Available En el primer decenio del siglo XX, en 1907, los cartageneros serían testigos del establecimiento de dos nuevas industrias creadas con capital enteramente colombiano: la Cartagena Oil Refining Company, primera refinería de petróleo que funcionó en el país, creada por Diego Martínez Camargo e inversionistas cartageneros y sinuanos, y un ingenio azucarero conocido popularmente como el ingenio de Sincerín. En 1910, la Cartagena Oil Refining Co. contaba con un capital que ascendía a 253.000 pesos oro, y una capacidad de refinación de cuatrocientos barriles de crudo diarios. Su producción de queroseno permitió sustituir totalmente las importaciones de este derivado en el país . El ingenio se comenzó a instalar en 1907, distante cincuenta kilómetros de Cartagena, en las inmediaciones de la población de Sincerín, a orillas del canal del dique, y fue llamado el Central Colombia. El capital inicial invertido fue de un millón de pesos oro, y produciría a partir de 1909 azúcar refinado con calidad de exportación, abaratando en una tercera parte los precios del azúcar en el interior del país.

  11. Modelo computacional del circuito motor basado en estudios de Resonancia Magnética Nuclear funcional

    Directory of Open Access Journals (Sweden)

    Karla Batista García-Ramó

    2012-01-01

    Full Text Available Los ganglios basales constituyen una compleja red de núcleos subcorticales implicados en el control motor,en la integración sensorimotora y en los procesos cognitivos. Su funcionamiento e interacción con el resto de las estructurascerebrales permanecen como una gran polémica. Este trabajo tuvo como objetivo modelar la interacción del circuito formado por los ganglios basales, el tálamo y la corteza para la selección de un programa motor, sobre la base del patrón de conectividad funcional obtenido por imágenes de resonancia magnética nuclear funcional. La determinación de los pesos de las conexiones entre las poblaciones neuronales a partir de imágenes de resonancia magnética nuclear funcional, contribuyó a una formulación más realista del modelo; y consecuentemente, a la obtención de resultados comparables con datos experimentales y clínicos, lo que permitió describir la participación de los ganglios basales en la selección de una acción en estado normal y en la enfermedad de Parkinson. La simulación posibilitó demostrar que ante una pérdida de dopamina superior al 40 %, el circuito ganglio basal-tálamo-cortical no es capaz de seleccionar entre dos programas motores y además, reveló la capacidad de adaptación del sistema para compensar el trastorno funcional del circuito motor en la enfermedad de Parkinson de modo coincidente con estudios clínicos y experimentales.

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

    Science.gov (United States)

    Zhang, Fengjiao; Juhlin, Christopher

    2014-02-01

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

  13. Métodos de caracterización de combustible nuclear gastado con vistas a su almacenamiento y transporte

    OpenAIRE

    Canadell Navarro, Francina

    2008-01-01

    El objetivo es proporcionar un esquema general de la caracterización necesaria de los elementos combustibles irradiados que sirva para el diseño de un correcto y óptimo transporte y posterior almacenamiento de dicho combustible. Es evidente que el almacenamiento de todos los elementos combustibles en la propia central es ilógico y poco rentable. Debe encontrarse una solución que permita la evacuación del combustible gastado con una primera fase de almacenamiento intermedio para...

  14. Sazonalidade de Haematobia irritans no Brasil Central The seasonality of Haematobia irritans in central Brazil

    Directory of Open Access Journals (Sweden)

    Ivo Bianchin

    2006-06-01

    Full Text Available A mosca-dos-chifres (Haematobia irritans é um dos principais ectoparasitos de bovinos no Brasil. Estudos epidemiológicos são exigidos devido às dificuldades crescentes do seu controle químico. Por isso, para um melhor conhecimento da dinâmica populacional sazonal desta mosca foram realizadas contagens a cada 14 dias sobre bovinos para corte, entre 7 e 30 meses de idade, durante o período de inverno de 1996 até o verão de 2002. Foi verificada elevação nos níveis populacionais de H. irritans (PHorn fly (Haematobia irritans is one of the most important Brazilian cattle ectoparasites. Epidemiological studies are needed due the increasing difficulty of their chemical control. In order to obtain a better knowledge of their seasonal population dynamics, 14 days interval fly counts were made on 7-30 month old beef cattle, from winter 1996 to summer 2002. Horn fly population levels increase (P<0.05 was observed during the seasons of each infestation period (spring until autumn, mainly in spring and summer, and sometimes in autumn, followed by a significant reduction (P<0.05 in winter, when the relative humidity decreases to less than 60%. A straight (P<0.05 and immediate correlation between the relative humidity and the fly count was found, whilst the most evident effects of temperature and rain fall (P<0.05 were associated with counts done 42-56 days after attainment of the climatic data. The highest parasitism load (average number of flies per animal observed for the genetic groups used were: Aberdeen Angus x Nellore = 173.5 (134-254; ½ Brown Swiss x Nellore = 183.5 (32-540; ¾ Aberdeen Angus x Nellore = 133.0 (18-374, and Valdostana x Nellore = 219.0 (58-620. Torrential rain falls during the initial half of the infestation period (spring until midsummer are common in this region and were considered the main reason for the low to moderate population levels verified at that time, in comparison with those which occurred during the last half

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

    OpenAIRE

    Mario Edgar López-Ramírez; Jorge Alberto Quevedo-Flores

    2014-01-01

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

  16. El tarwi o chocho: una de las principales fuentes de proteína vegetal de las comunidades indígenas de los Andes Centrales

    Directory of Open Access Journals (Sweden)

    Planchuelo, Ana M.

    2005-01-01

    Full Text Available El lupino andino (Lupinus mutabilis Sweet conocido también como tarwi o chocho, es una especie de leguminosa nativa de los Andes Centrales. Su domesticación se remonta a los principios de la cultura Nazca y desde ese entonces hasta la actualidad el cultivo está ampliamente difundido en las laderas montañosas y en los altos valles de Ecuador, Perú y Bolivia. La importancia del lupino para las comunidades andinas prehispánicas quedo documentada en pinturas de cerámicas y en tributos encontrados en tumbas de 100-150 años AC. Diversas técnicas de lavado y de mejoramiento vegetal fueron aplicadas desde la antigüedad para eliminar los alcaloides tóxicos que le confieren el sabor amargo a la planta y los granos. El tarwi, el maíz. los frijoles, los pseudocereales, quinoa y amaranto y la papa junto a otras raíces y tubérculos constituyen la comida básica de muchas culturas andinas. El objetivo de este trabajo fue determinar los componentes nutricionales de los granos del lupino andino para compararlos con los otros constituyentes de la dieta de las comunidades campesinas. Se analizaron por medio de técnicas fitoquímicas distintas variedades de tarwi. Se determinaron los contenidos de proteínas y grasas y los patrones de ácidos grasos. Los resultados muestran que la ingesta de lupinos, que provee un buen balance de proteínas y grasas en combinación con el maíz y los tubérculos, que aportan los hidratos de carbono, forman una dieta balanceada y de alto valor nutricional.

  17. Doctoral education in the nuclear sector; La formacion de doctores en el sector nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Minguez, E.

    2013-03-01

    Doctoral aducation is a major priority for European universities. In the context of the Bologna Process the importance of doctoral education as the third cycle of higher education and the first stage of a young researchers career, and thus in linking the European Higher Education and Research Areas, was first highlighted in the 2003 Berlin Report. The core component of doctoral training is the advancement of knowledge through original research. considering the need for structured doctoral programs and the need for transparent supervision and assessment, we note that the normal workload of the third cycle in most countries would correspond 3-4 years full time. This is spirit of the new Spanish Doctoral Law. Then, universities should ensure that their doctoral programmes promote interdisciplinary training and the development of transferable skills, thus meeting the needs of the wider employment market. We need to achieve and overall increase in the numbers of doctoral candidates taking up research careers as early stage researchers and also increase the employability as a normal way as it is the case of other advance countries. In Spain, universities with doctoral nuclear programmes and the CIEMAT, with the sponsorship of the nuclear sector, a doctoral school in nuclear science and engineering should be created to enhance the research careers of Young students for the future of nuclear activities in Spain. (Author)

  18. Modern concepts of thermodynamic optimization in Mexican thermoelectric stations; Conceptos modernos de optimacion termodinamica en centrales termoelectricas mexicanas

    Energy Technology Data Exchange (ETDEWEB)

    Cervantes-de Gortari, J; Vidal-Santo, A.; Mendez-Lavielle, F.; Bautista-Godinez, O. [Departamento de Termoenergia, from Facultad de Ingenieria UNAM (Mexico)

    2002-03-01

    In this paper, a summary review of the current thermodynamic concepts related to the maximum power generation and minimum entropy production are presented. The results of the analysis are considered in Mexican power stations using conventional cycles and are compared with other power stations around the world. [Spanish] En este trabajo se revisa el analisis de maxima generacion de potencia que implica la minimizacion de la produccion de entropia en centrales generadoras de potencia. De acuerdo con los lineamientos mas recientes publicados en la literatura. Los conceptos y resultados del analisis se aplican a varias centrales mexicanas y se comparan con otras centrales en el mundo.

  19. Modern concepts of thermodynamic optimization in Mexican thermoelectric power stations; Conceptos modernos de optimacion termodinamica en centrales termoelectricas mexicanas

    Energy Technology Data Exchange (ETDEWEB)

    Cervantes de Gortari, J.; Vidal Santo, A.; Mendez Lavielle, F.; Bautista Godinez, O. [Facultad de Ingenieria, UNAM, Mexico, D.F. (Mexico)

    2002-03-01

    In this paper, a summary review of the current thermodynamic concepts to the maximum power generation and minimum entropy production are presented. The results of the analysis are considered in Mexican power stations using conventional cycles and are compared with other power stations around the world. [Spanish] En este trabajo se revisa el analisis de maxima generacion de potencia que implica la minimizacion de la produccion de entropia en centrales generadoras de potencia, de acuerdo con los lineamientos mas recientes publicados en la literatura. Los conceptos y resultados del analisis se aplican a varias centrales mexicanas y se comparan con otras centrales en el mundo.

  20. Arquitectura moderna en la Av. 9 de Octubre (1949-1970). El Banco Central del Ecuador Sucursal Mayor Guayaquil

    OpenAIRE

    Serrano Galarza, Pablo

    2009-01-01

    Arquitectura moderna en la Avenida 9 de Octubre (1949-1970) El Banco Central del Ecuador sucursal Mayor Guayaquil Este trabajo hace un poco de historia de la ciudad de Guayaquil y de cómo se originó la avenida 9 de Octubre. Posteriormente elegimos un marco temporal (1949-1970) en el que escogimos 7 edificios, haciendo un análisis muy general de los mismos, para tomar la resolución de seleccionar un proyecto: el edificio del Banco Central del Ecuador Sucursal Mayor; en donde se estudia a fond...

  1. Integral power evaluation in fossil fuel power plants; Evaluacion energetica integral en unidades de centrales termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Figueroa I, Luis R; Sanchez H, Laura E; Rodriguez M, Jose H [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico); Nebradt G, Jesus [Unidad de Investigacion y Desarrollo de la Subdireccion de Generacion de la Comision Federal de Electricidad, (Mexico)

    2006-07-01

    In this occasion, a methodology is presented that carries out an integral energy evaluation of fossil fuel power plants units (FFPPU) with the purpose of determining the root of the significant decrements of power produced soon after the annual maintenance service. This proposal, besides identifying the origin of the energy efficiency problems, offers information about the contributions of each one of the involved equipment in the total decrement of the unit. With this methodology, the maintenance focuses in the equipment that contributes to the greater energy loss. This document presents such methodology along with its application in a real case, results and necessary remedial actions, demonstrating that its application offers bases for the investment in corrective measures. [Spanish] En esta ocasion se presenta una metodologia que efectua una evaluacion energetica integral de las unidades de centrales termoelectricas (UCT) con el fin de determinar la raiz de los decrementos de potencia significativos producidos luego del servicio anual de mantenimiento. Dicha propuesta, ademas de identificar el origen de los problemas de eficiencia energetica, brinda informacion acerca de las aportaciones de cada uno de los equipos involucrados al decremento total de la unidad. Con esta metodologia, el mantenimiento se enfoca a los equipos que contribuyen a la mayor perdida de potencia. Este documento exhibe tal metodologia junto con su aplicacion en un caso real, resultados y las acciones correctivas necesarias, demostrando que su aplicacion ofrece bases para una inversion futura en medidas correctivas.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-04-01

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

  3. Controle microbiológico de drogas vegetais comercializadas na região central do Rio Grande do Sul

    OpenAIRE

    Gindri,A. L.; L. V. Laporta; M. R. Santos

    2012-01-01

    O objetivo deste trabalho foi analisar a qualidade microbiológica de 40 amostras de matérias-primas de fitoterápicos coletadas de farmácias de manipulação da região central Rio Grande do Sul. Foram realizados os testes de contagem de microrganismos viáveis e pesquisa e identificação de patógenos, ambos de acordo com a Farmacopéia Brasileira. Os resultados obtidos mostraram que há presença de microrganismos nas amostras, entretanto, em nenhuma delas, o valor de UFC g-1 ultrapassou o limite est...

  4. Analysis of the problems of induced draft fans in a carbo-electric power station; Analisis de la problematica de ventiladores de tiro inducido de una central carboelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Diaz Sanchez, Valentin de Jesus; Vital Flores, Francisco [LAPEM, Comision Federal de Electricidad (Mexico)

    2007-11-15

    The induced draft fans of the 350 MW units of a Thermo-electric power plant presented problems consisting of the failure of the capacity of gases extraction, together with the presence of cracks in the blades; this condition was observed since the stage of putting into service. Consequently, losses have been originated in the availability in two units, as well as, losses due to the manufacture of new impellers, which also originated that, in some cases, that the measures of the impellers, locally manufactured, differed from the originals, resulting in differences in the unit's efficiency. [Spanish] Los ventiladores tiro inducido de las unidades de 350 MW de una Central Termoelectrica presentaban una problematica consistente en la falla de capacidad de extraccion de gases, aunado a la presencia de fracturas en las aspas de los impulsores, esta condicion se observo desde la etapa de puesta en servicio. En consecuencia se han ocasionado perdidas de disponibilidad en dos unidades, asi como tambien, perdidas debido a la fabricacion de nuevos impulsores, lo que tambien origino que, en algunos casos, las medidas de los impulsores, fabricados localmente, diferian de los originales, dando como resultado diferencias en la eficiencia de las unidades.

  5. Influence of nuclear de-excitation on observables relevant for space exploration

    CERN Document Server

    Mancusi, Davide; Cugnon, Joseph; David, Jean-Christophe; Leray, Sylvie

    2010-01-01

    The composition of the space radiation environment inside spacecrafts is modified by the interaction with shielding material, with equipment and even with the astronauts' bodies. Accurate quantitative estimates of the effects of nuclear reactions are necessary, for example, for dose estimation and prediction of single-event-upset rates. To this end, it is necessary to construct predictive models for nuclear reactions, which usually consist of an intranuclear-cascade or quantum-molecular-dynamics stage, followed by a nuclear-de-excitation stage. While it is generally acknowledged that it is necessary to accurately simulate the first reaction stage, transport-code users often neglect or underestimate the importance of the choice of the de-excitation code. The purpose of this work is to prove that the de-excitation model is in fact a non-negligible source of uncertainty for the prediction of several observables of crucial importance for space applications. For some particular observables, the systematic uncertai...

  6. Proposta de método de inspeção de radioproteção aplicada em instalações de medicina nuclear