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Sample records for central nuclear de zorita-1

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

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

    1967-09-15

    The authors analyse and describe the sites of three Spanish nuclear power stations: the Zorita station (153 M W (e )) with a pressurized water reactor and single containment; the Santa Marfa de Garofia station (380 MW (e)), with a boiling water reactor and containment by steam condensation; and the Vandellos station (480 MW(e)), with a graphite-moderated gas-cooled reactor and integrated design of the EDF-4 type. The first two are located in the interior of the country and the third on the Mediterranean coast. The paper discusses the normal criteria and the safety considerations governing the choice of site, and points out the influence of Spanish orography on the transport of heavy equipment and hence its repercussions on the selection of power station sites. Reference is made to the experience acquired in transporting equipment for the Z-orita plant, and an analysis of the practical difficulties encountered in applying particular safety standards to the sites of stations of different types and designs is included. As the type of reactor and its containment system affect the practical value of applying particular standards which, moreover, have to be adapted to the special features of each country, safety standards for assessing power station sites should be applied in an appropriate and flexible manner. The paper describes the geological and meteorological features of the three sites and summarizes the studies carried out in these fields. It refers particularly to the hydrological studies carried out at Zorita and Santa Maria de Garofia and describes the weather stations set up at both sites, the diffusion experiments with neutcal-buoyancy balloons at Santa Maria de Garofia, and the results of these investigations. (author) [Spanish] Se analizan y describen los emplazamientos de tres centrales nucleares espanolas: la central de Zorita, de 153 MW(e), con reactor de agua a presion y sistema de contencion simple; la central de Santa Maria de Garofia, de 380 MW

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

    DOMINGO QUILICI

    2013-06-01

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

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

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

    2005-07-01

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

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

    Belinchón Vergara, Julio Angel

    2016-01-01

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

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

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

    1963-10-15

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

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

    Torralbo, J. R.

    2016-08-01

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

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

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

    2001-07-01

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

  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

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

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

    2016-08-01

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

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

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

    1963-10-15

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

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

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

    1998-07-01

    Full text: During decontamination works of the fueling machine of Atucha I nuclear power plant (AINPP), a liquid waste with special characteristics was generated, which needed the development of a treatment method. The waste consisted of an emulsion designed for the cleaning of mechanical components and was formed by an organic solvent dispersed in water with aid of an emulsifier additive. After several cleaning operations, the emulsion contained an important quantity of lubricants and radioactive dirt. The treatment had the objective of recycling a toxic waste such as the organic solvent and reducing the volume of the residual mass. Laboratory tests were made tending to the emulsion separation in their components. Ionic force and ionic mobility were modified for join the emulsion micelles and produce their coalescence. Different salts and working temperatures were tried and it was stated that the combination of 1% of Na{sub 2}SO{sub 4} added and 40 degree C temperature were the optimum taking into account the available equipment in AINPP and cost considerations. The process was carried out in batch mode and 3 residual streams were obtained, an aqueous one which was sent to Residual Water System of AINPP, an organic liquid consisting of decontaminated hydrocarbons, useful for other cleaning tasks and finally a solid one, sited in the in-between interface of the other two liquids, consisting of insoluble soaps used as lubricant thickness, containing the principal proportion of radioactivity. As a result of this process we have achieved a volume reduction higher than 90%, the recycling of the organic solvent and concentration of radioactivity in a solid greasy mass with low water solubility. (author) [Spanish] Texto completo: Como resultado de tareas de descontaminacion de la maquina de carga de la central nuclear Atucha I (CNAI) se genero un residuo liquido de caracteristicas especiales, que requirio el desarrollo de un metodo de tratamiento. El residuo consistia en

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

    João Batista Araujo Figueiredo

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

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

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

    2000-07-01

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

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

    Reis Martins Junior, L.L. dos.

    1980-01-01

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

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

    Gonzalez Lopez, A.

    2012-11-01

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

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

    Hacker, P; Kogan, A; Garzon, D

    1991-12-31

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

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

    Ramos Pellejero, J.L.

    2010-07-01

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

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

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

    1996-12-31

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

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

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

    1997-12-31

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

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

    Col Buti, P.; Tapia Fernandez, C.

    2002-07-01

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

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

    Esteban, G.

    2014-10-01

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

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

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

    1988-12-31

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

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

    Viñals Atienza, Òscar

    2008-01-01

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

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

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

    1963-10-15

    .), responsible for maintenance of all mechanical equipment; and (5) Service maintainers: responsible for a wide variety of less skilled tasks requiring lower qualifications. In addition to these general categories a few specialists are required, such as chemists and radiation protection officers. Organization of the NPD staff and training for future nuclear-power needs will be discussed. (author) [French] La centrale nucleaire de demonstration canadienne (NPD), creee par un organisme federal, l'Atomic Energy of Canada Limited, est exploitee par une compagnie provinciale de distribution d'electricite, la Hydro-Electric Power Commission of Ontario, qui pourvoit aussi aux besoins en personnel. Le recrutement et la formation du personnel de la centrale ont ete difficiles du fait que, recemment encore, la plupart des besoins en electricite de l'Ontario pouvaient etre satisfaits par les abondantes ressources hydro-electriques de cette province. La multiplication des centrales thermiques, depuis 1950, a cree une enorme demande de personnel. Pour faire face a cette situation, on a organise la formation de personnel pour les centrales nucleaires de la maniere suivante: a) un groupe initial d'ingenieurs a ete selectionne parmi des specialistes ayant une vaste experience des travaux dans le domaine nucleaire de l 'exploitation des centrales thermiques et de la production d'electricite; b) on a selectionne un autre groupe d'operateurs et d'agents des services d'entretien hautement qualifies; c) ces groupes ont recu une formation systematique comprenant l'exploitation de centrales nucleaires et de centrales thermiques a charbon, un enseignement theorique et pratique et des instructions donnees par les specialistes qui ont concu les plans de NPD ; d) un centre de formation nucleaire a ete cree et charge de la selection et de la formation du personnel supplementaire ainsi que de l 'organisation des examens officiels; il doit s'assurer, d'une maniere generale, de la competence du personnel

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

    NONE

    2012-04-15

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

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

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

    2000-07-01

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

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

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

    1991-12-31

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

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

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

    1992-12-31

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

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

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

    1963-10-15

    predicted performance for the reactor. Further testing of response to load transients is to continue into the Spring of 1963. The Indian Point Station has proved to the satisfaction of our Company the feasibility of a combination nuclear and oil-fired plant to produce competitive power. The United States Atomic Energy Commission has been requested to issue a construction permit for the Company to build another nuclear plant, similar in design, but of 1000 MW capacity, to be located at Ravenswood which is within the corporate limits of the City of New York. Our Company is prepared to finance the venture with its own funds without subsidy of any kind as was the case with our Indian Point Station. (author) [French] La centrale No. 1 d'Indian Point se compose d'un reacteur a eau sous pression de 585 MWt, quatre circuits de refroidissement primaires avec des echangeurs de chaleur horizontaux, deux surchauffeurs au mazout de 500 000 kg/h et un turbogenerateur de 275 000 kW. Le combustible du reacteur est un melange d'oxyde d'uranium completement enrichi en {sup 235}U et d'oxyde de {sup 232}Th. L'installation se trouve au bord de l'Hudson a une quarantaine de kilometres au nord de New York. En raison de la proximite de cette ville, on a prevu des dispositifs de securite intrinseques exceptionnels contre le risque d'un emballement du reacteur et contre les rayonnements qui pourraient en resulter. La construction a ete terminee en mai 1962. Le combustible a ete charge en juin et le reacteur est entre en divergence pour la premiere fois le 2 aout 1962. On a ensuite procede, dans le courant du mois d'aout, a des essais a faible puissance (jusqu'a 5 MWt), a la temperature ambiante et a .des temperatures elevees. Le turbogenerateur aeteintegre pour la premiere fois au reseau de la ''Consolidated Edison'', le 16 septembre 1962. Les essais aux puissances allant jusqu'a 50% de la puissance theorique se sont prolonges jusqu'en novembre et ont ete marques par de frequents arrets automatiques

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

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

    1998-12-31

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

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

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

    2015-07-01

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

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

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

    2015-07-01

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

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

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

    1960-07-01

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

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

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

    2016-07-01

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

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

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

    2006-07-01

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

  16. The First Two Years of Operating Experience of the Kahl Nuclear Power Station; Experience acquise pendant les deux premieres annees de fonctionnement de la centrale nucleaire de Kahl; Opyt pervykh dvukh let ehkspluatatsii atomnoj ehlektrostantsii v Kale; Experiencia adquirida en los primeros cuatro anos de funcionamiento de la central nucleoelectrica de Kahl

    Bruchner, H. J. [Aeg-Kernenergieanlagen, Frankfurt-am-Main (Germany); Weckesser, A. [Versuchs-Atomkraftwerk Kahl Gmbh, Kahl (Germany)

    1963-10-15

    Kahl, being the first European private atomic power station, has been operating at load since June 1961. Kahl is equipped with a boiling-water reactor, operating in an indirect cycle and with natural circulation. Its electrical net capacity is 15 MW, and the power produced until February 1963 amounts to 140 million kWh. In the paper the operating experience, particularly the extensive testing programme such as concerning transient behaviour and gammascanning, will be reviewed. Results about the operating performance of certain plant components such as control-rod-drive system, off-gas system and turbine will be presented. After this testing programme the plant has been operated at base load for some time in order to obtain realistic experience on fuel performance. After completion of the base-load phase of operation a nuclear superheating test loop will be installed and run in the Kahl reactor. (author) [French] La centrale de Kahl, la premiere en Europe dont l'exploitation soit assuree par une entreprise privee, alimente le secteur depuis juin 1961. Elle est equipee d'un reacteur a eau bouillante, en cycle indirect, a circulation naturelle. Avec une puissance electrique nette de 15 MW, elle avait produit, jusqu'a fevrier 1963, 140 millions de kWh. Le memoire rend compte de l'experience acquise concernant le fonctionnement de la centrale, notamment du programme etendu des essais effectues sur son comportement en regime transitoire et sur la detection gamma. Il donne, en particulier, des renseignements sur le fonctionnement de certains elements de la centrale tels que le mecanisme de commande des barres de controle, le dispositif d'echappement des gaz et la turbine. A la suite de ce programme d'essais, on fait fonctionner depuis quelque temps la centrale comme centrale de base afin de rassembler des donnees pratiques sur les performances du combustible. A l'expiration de la periode prevue pour le fonctionnement comme centrale de base, on amenagera, dans le reacteur

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

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

    1992-03-01

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

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

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

    2011-07-01

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

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

    Mostaza, J. M.

    2011-07-01

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

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

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

    2013-09-01

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

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

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

    2011-07-01

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

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

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

    2014-07-01

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

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

    NONE

    2004-04-01

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

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

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

    1965-10-15

    In the Federal Republic of Germany there are nuclear reactors under construction with steam generators inside the reactor pressure-vessel. As a result design repairs of steam- generator tubes are very difficult and cause large shut-down times of the nuclear-power plant. It is known that numerous troubles in operating conventional power plants are results of steam-generator tube damages. Because of the high total costs of these reactors it. is necessary to construct the steam generators especially in such a manner that the load factor of the power plant is as high as possible. The Technischer Ueberwachungs-Verein Rheinland was charged to supervise and to test fabrication and construction of the steam generators to see that this part of the plant was as free of defects as possible. The experience gained during this work is of interest for manufacture and construction of steam generators for nuclear-power plants in general. This paper deals with the efficiency limits of non-destructive testing steam-generator tubes. The following tests performed will be discussed in detail: (a) Automatic ultrasonic testing of the straight tubes in the production facility; (b) Combined ultrasonic and radiographic testing of the bent tubes and tube weldings; (c) Other non-destructive tests. (author) [French] En Allemagne, on construit actuellement des generatrices nucleaires dans lesquelles les bouilleurs sont installes a l'interieur du caisson etanche du reacteur. Il s'ensuit que les reparations des tubes des bouilleurs sont tres difficiles et provoquent de longs arrets des centrales nucleaires. On sait que de nombreuses perturbations du fonctionnement des centrales classiques sont dues a des dommages dans les tubes des bouilleurs. C'est en grande partie en raison du prix de revient eleve de ces reacteurs qu'il est necessaire de construire les bouilleurs notamment de sorte que le facteur d'utilisation de la centrale soit aussi eleve que possible. C'est le ' Technischer Ueberwachungs

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

    Pascual Carballo, N.

    2010-07-01

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

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

    Fernandez-Bolanos, M.

    2008-07-01

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

  7. Nuclear Energy in Central Europe 98, Proceedings

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

    1998-01-01

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

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

    Martin Aparicio, J.; Atanasio, J.

    2011-07-01

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

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

    Suarez, P O

    1991-12-31

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

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

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

    1958-07-01

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

  11. 30 years in the Veracruz state coast landscape: Laguna Verde nuclear power station. 1. ed.; 30 anos de paisaje costero veracruzano: Central Nucleoelectrica Laguan Verde

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

    2008-07-01

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

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

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

    2011-07-01

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

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

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

    1965-09-15

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

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

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

    2006-07-01

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

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

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

    2011-07-01

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

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

    NONE

    2012-04-15

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

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

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

    2012-10-15

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

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

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

    2013-10-15

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

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

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

    2013-07-01

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

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

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

    2006-07-01

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

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

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

    2013-10-15

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

  2. 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

    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.

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

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

    1963-10-15

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

  4. 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

    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)

  5. Nuclear insurance in Central and Eastern Europe

    Warren, G.

    1998-01-01

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

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

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

    2013-10-15

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

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

    Martinez Anton, L.

    2011-07-01

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

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

    Cano, J. C.; Ruiz, S.

    2013-07-01

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

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

    Cosentino, R E

    1988-12-31

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

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

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

    2011-07-01

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

  11. Commissioning Experience from the Agesta Nuclear Power Plant; Experience acquise lors des essais de mise en service de la centrale nucleaire d'Agesta; Opyt po vvedeniyu v ehkspluatatsiyu yadernoj ehnergeticheskoj ustanovki Agesta; Experiencia adquirida con la puesta en marcha de la central nucleoelectrica de Agesta

    Rydell, N. [Aagesta Kraftvarmewerk, Farsta (Sweden)

    1963-10-15

    The Agesta Nuclear Power Plant is a pressurized heavy water reactor of the pressure vessel type, fuelled with natural uranium. It was commissioned with light water from December 1962 to May 1963. Observations of a more general interest were made during this commissioning essentially on the following topics; (a) cleanliness of primary circuit (b) valve operation (c) pressurization of the primary circuit (d) water leakage (e) refuelling machinery (f) containment testing. (author) [French] Il s'agit d'un reacteur a uranium naturel et a eau lourde pressurisee, du type a caisson sous pression. Les essais de mise en service ont ete faits avec de l'eau ordinaire, de decembre 1962 a mai 1963. La mise en service a permis de faire des observations d'interet general sur les sujets suivants: a) non-contamination du circuit primaire; b) fonctionnement des vannes; c) maintien sous pression du circuit primaire; d) fuites d'eau; e) appareils de chargement du combustible; f) essais d'isolement. (author) [Spanish] La central nucleoelectrica de Agesta posee un reactor de agua pesada del tipo de recipiente de presion, con combustible de uranio natural. Se mantuvo en funcionamiento con agua ligera entre diciembre de 1962 y mayo de 1963. Durante esta prueba, se efectuaron observaciones de interes mas general, relacionadas esencialmente con las siguientes cuestiones: a) limpieza del circuito primario; b) funcionamiento de las valvulas; c) presion del circuito primario; d) perdidas de agua; e) dosposiciones de reposicion del Combustible; f) ensayos de confinamiento. (author) [Russian] Yadernaya ehnergeticheskaya ustanovka Agesta predstavlyaet soboj tyazhelovodnyj reaktor pod davleniem, ispol'zuyushchij prirodnyj uran v kachestve topliva. Reaktor byl vveden v ehkspluatatsiyu na obychnoj vode v period s dekabrya 1962 goda po maj 1963 goda. Zamechaniya bolee obshchego kharaktera byli sdelany vo vremya ehkspluatatsii v osnovnom po sledukhshchim temam: a) chistota pervichnogo kontura; b

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

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

    1967-09-15

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

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

    NONE

    2012-12-15

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

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

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

    2011-07-01

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

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

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

    2009-07-01

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

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

    Flach, G.; Bonitz, M.

    1979-12-01

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

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

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

    2013-07-01

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

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

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

    1993-12-15

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

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

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

    1966-02-15

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

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

    Peco, J.

    2015-07-01

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

  1. Central Bureau for Nuclear Measurements

    1991-01-01

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

  2. Centralized vs. de-centralized multinationals and taxes

    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. ...

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

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

    2013-07-01

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

  4. Nuclear Electric's central dose record service

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

    1991-01-01

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

  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

    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. Calculating of radiation doses in rutinary unloads of liquid wastes from Laguna Verde nuclear power plant.; Calculo de las dosis de radiacion debidas a las descargas rutinarias de desechos liquidos de la central nucleoelectrica de Laguna Verde.

    Molina, G

    1986-12-31

    Utilization of nuclear energy to generate electricity is increasingly being used to replace fossil fuels. During operation of nuclear power plants, radioactive materials are produced, a small fraction of which are released to environment as liquid or gaseous effluents. Estimation of radiation doses caused by effluents release has three purposes. During design phase of a nuclear station it is useful to adapt the wastes treatment systems to acceptable limits. During licensing phase, the regulator organism verifies the design of nuclear station effectuating estimation of doses. Finally, during operation, before every unload of radioactive effluents, radiation doses should be evaluated in order to fulfill technical specifications limiting the release of radioactive materials to environment. 1. To perform calculations of individual doses due to liquid radioactive effluents unload in units 1 and 2 of Laguna Verde nuclear power plant (In licensing phase). 2. To perform a parametric study of the effect of unload recirculation over individual dose, since recirculation has two principal effects: thermodynamical effects in nuclear station and radioactivity concentration; the last can affect the fullfilment of dose limits. 3. To perform the calculation of collective doses causes by unloads of liquid effluents within a radius of 80 km of the plant caused by unload of liquid radioactive effluents during normal operation and does not include doses during accident conditions. In Mexico the organism in charge of regulation of peaceful uses of nuclear energy is Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) and for Laguna Verde licensing, the regulations of the country who manufactured the reactor (USA). In Appendix C, units are explained.

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

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

    2013-07-01

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

  8. Central depression of nuclear charge density distribution

    Chu Yanyun; Ren Zhongzhou; Wang Zaijun; Dong Tiekuang

    2010-01-01

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

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

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

    1993-12-15

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

  10. Balance between automation and human actions in nuclear power plant operation. Results of international cooperation; Equilibre entre automatisation et action humaine dans la conduite des centrale nucleaires, resultats de la cooperation internationale

    Sun, B [CEA Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. d' Analyse de Surete; Bastl, W [Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany); Olmstead, R [Atomic Energy of Canada Ltd, Mississauga (Canada); Oudiz, A [Electric Power Research Inst., Palo Alto, CA (United States); Jenkinson, J [Nuclear Electric PLC, Gloucester (United Kingdom); Kossilov, A [International Atomic Energy Agency, Vienna (Austria)

    1990-07-01

    Automation has long been an established feature of power plants. In some applications, the use of automation has been the significant factor which has enabled plant technology to progress to its current state. Societal demands for increased levels of safety have led to greater use of redundancy and diversity and this, in turn, has increased levels of automation. However, possibly the greatest contributory factor in increased automation has resulted from improvements in information technology. Much recent attention has been focused on the concept of inherently safe reactors, which may simplify safety system requirements and information and control system complexity. The allocation of tasks between man and machine may be one of the most critical activity in the design of new nuclear plants and major retro-fits and it therefore warrants a design approach which is commensurate in quality with the high levels of safety and production performance sought from nuclear plants. Facing this climate, in 1989 the International Atomic Energy Agency (IAEA) formed an advisory group from member countries with extensive experience in nuclear power plant automation. The task of this group was to advise on the appropriate balance between manual and automatic actions in plant operation. (author) [French] L'automatisation a longtemps ete une caracteristique bien etablie des centrales nucleaires. Dans certaines applications, l'utilisation de l'automatisation a ete le facteur decisif qui a permis a la technologie des centrales de progresser jusqu'a son etat actuel. Les exigences de l'opinion publique en matiere de securite renforcee ont conduit a l'utilisation d'une plus grande redondance et a une plus grande diversification et ceci, en retour, a encore accru le niveau d'automatisation. Toutefois, il est possible que le facteur preponderant de cet accroissement de l'automatisation soit constitue par les progres effectues dans la technologie de l'information. Plus recemment, l'attention s

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

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

    2015-07-01

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

  12. Problems to be Expected in Disposing of Fission Products from a Possible Nuclear Power Programme; Problemes Eventuels d'Elimination des Produits de Fission dans les Futures Centrales Nucleaires; 0412 0415 0420 041e 042f 0414 ; Problemas que Puede Plantear la Evacuacion de Productos de Fision Resultantes de la Ejecucion de un Programa de Produccion de Energia de Origen Nuclear

    Dickson, G. K. [Cenral Technical Services, Engineering and Development Group, United Kingdom Atomic Energy Authority, Risley (United Kingdom)

    1960-07-01

    typical British nuclear power programme covering the next few decades is examined. The types of reactor to be erected and the types of fuel to be initially used in them are well appreciated but of course the author's conclusions will necessarily become less certain with the passage of time. The chemical processes which must be applied to irradiated fuels will depend on the type of fuel, its burn-up etc., and so will change during the period under review. Consideration is therefore given to the quantities of fission products and heavy isotopes which may be produced, the forms in which they may leave the chemical processing streams and the methods available for handling them safely, either by storage or by disposal. (author) [French] L'auteur examine un programme d'energie nucleaire caracteristique pour la Grande-Bretagne et s'etendant sur les prochaines decennies. Il donne une evaluation fort judicieuse des types de reacteurs dont la construction est envisagee et des genres de combustibles qu'il est question d'y utiliser pendant la periode initiale; toutefois, ses conclusions auront avec le temps de moins en moins de valeur. En effet, le traitement chimique auquel on devra soumettre le combustible irradie depend du genre de ce dernier, de son taux de combustion, etc.; il subira inevitablement des modifications au cours de la periode consideree. L'auteur tient donc compte des quantites de produits fissiles et d'isotopes lourds qu'il sera possible de produire, des formes sous lesquelles ils pourront se presenter a la fin du traitement chimique et des methodes existantes permettant d'assurer leur manipulation sans danger en vue de leur stockage ou de leur elimination. (author) [Spanish] Esta memoria estudia un programa britanico caracteristico de produccion de energia nuclear que cubre las proximas decadas. Se sabe con bastante certeza que tipos de reactores se construiran y el tipo de combustible que se empleara en ellos en un principio, pero estos conocimientos son

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

    Anon.

    2012-03-15

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

  14. Banco Central de Costa Rica

    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

  15. Nuclear Safety in Central and Eastern Europe

    2001-04-01

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

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

    Esparza Martin

    2015-07-01

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

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

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

    2009-07-01

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

  18. 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

    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.

  19. Perspectives for nuclear electricity in Central Africa

    Wa Kalenga, M.

    1977-01-01

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

  20. Perspectives for nuclear electricity in central Africa

    Wa Kalenga, M.

    1977-01-01

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

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

    NONE

    2007-07-01

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

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

    Sarandeses, S.

    2014-07-01

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

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

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

    2012-07-01

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

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

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

    2010-07-01

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

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

    Koelzer, W.

    1993-05-01

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

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

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

    2009-10-15

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

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

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

    2016-09-15

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

  8. 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

    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)

  9. 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

    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)

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

    Rodriguez Silva, M.

    2005-07-01

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

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

    Rodriguez Mendez, M.

    2012-11-01

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

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

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

    1991-07-01

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

  13. 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

    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)

  14. Improvement of the availability of nuclear power station maintenance teleprocessing; Amelioration de la disponibilite des teletraitements de maintenance des centrales nucleaires

    Badellon, D; Bloton, Y; Bres, J P; Cuche, A; Trabaud, C

    1993-11-01

    The Data processing department at the DEPT manages a centralized maintenance application for the nineteen power plants in France. This application performs fourteen million CICS transactions every month, passing through the Electricite de France national teleprocessing network. Operation is split among two IBM 9021 computer partitions located one hundred kilometres apart for backup and security reasons in the two computer centres of the STI (EDF Data Processing Department) and the R and DD (EDF Research and Development Department). The CICS are stopped each night at 10.30 so that the data bases can be backed up onto cassettes and so that the work from the plants can be processed in batches. The plants update the number of bases and extract subsets intended for the plants. From the outset, considerable resources were assigned to this operation: cassette insertion robots, a high-power batch processing scheduling and planning tool optimizing parallel step work, high-power computers: two IBM 3090-40J computers were dedicated to this application as early as 1989. However, the buildup and evolution of this application led to ever greater basic volumes and increasingly voluminous and complex batch processing, leading to reduced transactional availability by pushing back the startup times. To combat this trend, the Data Processing Department at the DEPT, together with the Departments operating the computers, took a number of steps to speed up batch processing and thus improve teleprocessing availability. In particular, on the partition operated by the computer Centre in the Applied Mathematics and Data Processing Service of the Research and Development Department at EDF, a number of studies were conducted, as described in the following text. This description comprises three parts: - report on the studies and steps taken, both from the hardware and the software viewpoint; - an evaluation of their effectiveness and the results obtained; - the new areas for study selected.

  15. La central electronuclear de Garellano (Italia

    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

  16. 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

    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'une des trois filieres suivantes: - filiere uranium

  17. 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

    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

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

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

    2017-09-15

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

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

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

    1996-12-31

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

  20. 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

    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)

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

    Koelzer, W.

    1994-04-01

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

  2. Integration of in-service inspection works in the objectives of nuclear power plants; Integracion de los trabajos de inspeccion en servicio en los objectivos de las centrales nucleares

    Garcia, M.; Lopez, M.A.

    1996-09-01

    The present articles summarizes the objectives of Spanish NPPs and the in-service inspection aspect in these objectives. The Safety maintenance, lifetime of nuclear power plants, reduction of doses and wastes and the participation of main are evaluated.

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

    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)

  4. Central depression of the nuclear charge distribution

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

    1986-01-01

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

  5. Centralized vs. De-centralized Multinationals and Taxes

    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...

  6. Electrical systems at the nuclear power plant of Laguna Verde after the event in Fukushima; Sistemas electricos en la central nucleoelectrica Laguna Verde despues del evento de Fukushima

    Lopez J, J. F., E-mail: jflopez@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose M. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2016-09-15

    During the event at the nuclear power plant of Fukushima Daichii (Japan), the electrical systems were affected both Onsite and Offsite, which were lost for a long time with irreversible consequences. Therefore, the Mexican Regulatory Body known as the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has taken various actions to review the current capacity of the electrical systems at the nuclear power plant of Laguna Verde (NPP-LV) before an event beyond the design bases. The CNSNS made special inspections to the NPP-LV to verify the current capacity of the electrical systems of Ac and Dc; as a result of the inspections, requirements were generated that must be met to demonstrate that has the capacity to deal with events beyond the design bases. In addition, CNSNS has participated in the Ibero-American Forum to deal with resistance testing. Is important to note that prior to the event at the nuclear power plant of Fukushima, the NPP-LV had implemented 1) the project Extended Power Increase in both Units of the NPP-LV, and 2) the Generic Charter 2006-02, both issues are considered contributions in the robustness of electrical systems. But it is also important to mention that the US Nuclear Regulatory Commission will soon issue mitigation strategies for a Station Blackout event, which could involve new actions at nuclear power plants. Based on the aforementioned, the CNSNS concludes that all the actions being taken contribute to the strengthening of the NPP-LV electrical systems, in order to increase their reliability, safety and operation when these are required to deal with events beyond the design bases as the event occurred in Fukushima Daichii and avoid as far as possible, damage in the reactor cores of the NPP-LV. (Author)

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

    NONE

    2003-05-01

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

  8. 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

    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

    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. Simulation of the turbine trip of Unit 1 of the Laguna Verde nuclear power plant using the code Simulate-3K; Simulacion del disparo de turbina de la Unidad 1 de la central nuclear Laguna Verde empleando el codigo Simulate-3K

    Alegria A, A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico); Filio L, C. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, 07738 Ciudad de Mexico (Mexico); Ortiz V, J., E-mail: aalegria@cnsns.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    In order to compare the results obtained from the model developed in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) with the code Simulate-3K (S3K) with respect to those reported by the process computer of the Central (SIIP), the simulation of the turbine trip transient was carried out, caused by the firing of the main generator, the low differential pressure of oil of its seals and the automatic Scram of Unit 1 of the Laguna Verde nuclear power plant, at 87% of power nominal during the operation cycle 16. Since the reactor was brought to a safe stop due to Scram, was enough to simulate 20 seconds to observe the maximum increase in pressure with S3K. In this work, the following parameters are shown and compared: the neutron flux, the thermal power, the pressure in the dome, the flow at the entrance to the core, the steam flow that leaves the vessel and the minimal critical power ratio (MCPR). The neutron flux of the average power range monitors of the nuclear power plant was compared with the S3K detectors model. Finally, the MCPR was calculated with a different correlation to that of the fuel supplier and its deviation from its safety limit was determined. In conclusion, the results obtained show the current state of the model for the simulation of reactivity transients and the opportunity areas to consolidate this tool in support of the process of licensing refueling in the CNSNS. (Author)

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

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

    2005-07-01

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

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

    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)

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

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

    1997-07-01

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

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

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

    2014-07-01

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

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

    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)

  16. Nuclear Power in South-Central Brazil

    Cintra do Prado, L.

    1966-01-01

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

  17. Projeto de pesquisa Energia Nuclear

    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”.

  18. Central Institute of Nuclear Research Rossendorf 25 years old

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

    1981-12-01

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

  19. Mechanical and Radiological Characterization of Different parts of an Irradiation Coolant Channel Tube from Atucha I Nuclear Plant; Caracterizacion Mecanica y Radiologica de Partes de Canales Refrigerantes Irradiados Extraidos del Reactor de la Central Nuclear Atucha I

    Piquin, Ruben [Instituto Balseiro, Universidad Nacional de Cuyo, Centro Atomico Bariloche, Universidad Nacional de Mar del Plata (Argentina)

    2001-07-01

    The widespread replacement of reactor internals has generated a substantial volume of active material. It is essential to work with these components at least in a partial way before the next planned stop, which will take place during the second semester of the year 2002. Due to the fact that the reactor internals pool and the storage pool for irradiated nuclear fuel have limited capacities, it has been proposed to compact an experimental shift of 50 irradiated coolant channels, that are currently placed in storage pools. Basically the processed waste will be put in baskets at the bottom pools.The alternative choice proposes to divide an irradiation coolant channel tube into different parts: stainless steel section, zircaloy-4 section and stainless steel section with hardened zones with cobalt alloys named Estelite-6. The person in charge has already planned the constructive and operative solutions but the mechanical characterization of the different parts of the channel tube is necessary in order to dimension the compaction tool needed for the semi-industrial installation.In the present special report, two well-differentiated actions will be described. The necessary compacted strength of the irradiation coolant channel tube will be estimated for the stainless steel section and the zircaloy-4 section starting from experiment with unirradiated material and considering effects of radiation damage and hydrides on the ductility.These results will be used to design the necessary compacted tools for the semi-industrial installation. The necessary equipment for the radiological characterization of the different material sections already specified will be described and the most important emitting particles of radiation that could be detected will be mentioned. Also the decontamination process to use including the radiological characterization of every stage of the process will be described in order to establish the decontamination factor. Finally the most important

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

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

    1994-07-01

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

  1. Puesto central de defensa pasiva

    R. Evan Kennedy

    2017-06-01

    Full Text Available La ciudad de Portland, Oregón (EE. UU., está terminando la construcción de un centro subterráneo, destinado a la defensa civil del casco urbano, que, en caso de emergencia, tendrá por objeto la dirección y rehabilitación de los servicios que un ataque o desastre local pudieran devastar. El refugio dispondrá de facilidades para poder acomodar al gobierno con sede en la ciudad. Este proyecto, de larga incubación hasta llegar al estado de ejecución, ha previsto la instalación en el refugio de los servicios siguientes: policía, contra incendios, ingeniería, médicos, beneficencia y jefaturas varias. También se han previsto los servicios de prensa y radio.

  2. 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

    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)

  3. The radiological accident of Goiania and the acceptance by the public of new nuclear power plants; El accidente radiologico de Goiania y la aceptacion publica de nuevas centrales nucleares

    Meldonian, N L; Mattos, L A.T. [Grupo de Energia e Ambiente, Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil)

    1998-12-01

    Misunderstandings on the peaceful uses and the safety of nuclear energy have been a leading cause of apprehension in Brazilian public opinion. A lack of knowledge of the characteristics and destination of radioactive wastes and negative media coverage of the use of nuclear energy have aggravated this situation. Believing that applications of nuclear energy are harmful to the population`s welfare and the environment, Brazilian public opinion is opposed to the utilization of nuclear energy, and in particular to the construction of new nuclear power plants. For this reason, the Brazilian nuclear sector should promote a more intensive programme of public discussion, directed not solely at the technical and scientific communities, but also at the Brazilian public at large. Such a campaign would contribute towards a better understanding by Brazilian society of the different uses of nuclear energy and would present arguments in support of the benefits of this form of energy. Moreover, a campaign of this kind would show that negative associations about the use of electricity derived from nuclear power, which are based on the Goiania radiological accident, are not justified. (author) 10 refs, 5 tabs

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

    Stritar, A.; Jencic, I.

    1996-01-01

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

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

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

    1996-07-01

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

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

    Peltzer, P.

    1986-01-01

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

  7. THERMOS, district central heating nuclear reactors

    Patarin, L.

    1981-02-01

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

  8. Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide (Spanish Edition); Diseno del sistema de refrigeracion del reactor y los sistemas asociados en las centrales nucleares. Guia de seguridad

    NONE

    2010-07-15

    This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1982), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1987), which are superseded by this new Safety Guide. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1982 and 1987, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2004, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included.

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

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

    2014-07-01

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

  10. Nuclear energy in central and eastern Europe

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

    2010-01-01

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

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

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

    2017-09-15

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

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

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

    2010-07-01

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

  13. 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

    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)

  14. 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

    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)

  15. 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

    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)

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

    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.

  17. 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

    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)

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

    Smagala, G.

    2002-01-01

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

  19. Jose Cabrera NPP; Central Nuclear Jose Cabrera

    Diez, P.

    2004-07-01

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

  20. 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

    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)

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

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

    1993-07-01

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

  2. 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)

    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.

  3. 30 years of Central Institute for Nuclear Research at Rossendorf

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

    1986-10-01

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

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

    1976-01-01

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

  5. Nuclear spin noise in the central spin model

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

    2018-05-01

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

  6. 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

    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)

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

    Martinez M, E

    1992-05-15

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

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

    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...

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

    2009-06-01

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

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

    Yang Xiaowei

    2014-01-01

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

  11. Los Discursos de Legitimación de la Industria Nuclear Española

    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 Pazayuda 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.

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

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

    1983-01-01

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

  13. Instalaciones de Aire Comprimido (Central compresora

    Enoc Duliep Lescaille

    2011-03-01

    Full Text Available En los últimos cincuenta años, el aire comprimido ha experimentado una incorporación inusitada en la industria ysectores de servicios, debido a su alto poder de adaptación a cualquier sistema de trabajo, ya que sus cualidades lohacen recomendable para ejecutar labores que difícilmente podrían cubrir otras energías que carecen de la flexibilidadque lleva implícito éste. La instalación de aire comprimido consta de dos partes fundamentales: la central de compresióny su correspondiente tratamiento para su posterior aprovechamiento, y las redes de tuberías hacia los diferentes puntosde trabajo donde están ubicados los consumidores o máquinas neumáticas. Es importante conocer cada uno de loselementos que intervienen en el proceso de compresión, para operar la instalación eficientemente y así garantizar unservicio de calidad con el menor costo posible.  In the last fifty years, the compressed air experimented an unusual utilisation in the industry and services sectors, dueto its high capability of adaptation to any work system, since its qualities make it advisable to execute works thatdifficulty could cover other energy lacking its flexibility that takes implicit this. The compressed air installationconsists of two fundamental parts: The compression power station and their corresponding treatment for their lateruse, and the network pipes toward to the different work points where the consumers or pneumatic machines arelocated. It is important to know every participating element of the compression process.

  14. 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

    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)

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

    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.)

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

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

    1996-12-31

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

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

    Stritar, A.; Jencic, I.

    1995-01-01

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

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

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

    2000-07-01

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

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

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

    1995-07-01

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

  20. Administrative Arrangement between the Atomic Control Board of Canada and le Service central de surete des installations nucleaires du Ministere de l'Industrie et de l'Amenagement du Territoire de la Republique francaise for the Exchange of Technical Information and Cooperation in the Regulation of Nuclear Safety

    1991-01-01

    This Arrangement between the Atomic Energy Control Board of Canada (AECB) and the French Central Service for the Safety of Nuclear Installations (SCSIN) entered into force on the date of its signature and will remain in effect for five years. The Arrangement provides for the exchange of information between both agencies on the regulation of nuclear facilities and intervention measures in cases of emergency. This includes information on regulatory procedures for the safety of designated nuclear facilities, notification of important events, such as serious operating incidents, reactor shutdowns ordered by the regulatory authorities, etc. (NEA) [fr

  1. Analysis of the preliminary trajectory of emergency venting of the nuclear power plant of Laguna Verde using RELAP5; Analisis de la trayectoria preliminar del venteo de emergencia de la Central Laguna Verde mediante RELAP5

    Cecenas F, M.; Jimenez S, R.; Ovando C, R. [Instituto Nacional de Electricidad y Energias Limpias, Reforma No. 113, Col. Palmira, 42490 Cuernavaca, Morelos (Mexico); Tijerina S, F.; Tapia M, R. N., E-mail: mcf@iie.org.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, 94271 Veracruz (Mexico)

    2016-09-15

    For a commercial nuclear plant, the availability of a vent line to the atmosphere is an improvement to achieve the prevention and mitigation of the consequences of a severe accident. The importance of this system received greater attention after the Fukushima accident in 2011. Subsequently, in 2012 and 2013, the United States Nuclear Regulatory Commission issued documents stating that the venting must be able to dislodge 1% of the rated thermal power of the core without over pressurizing the primary container. To analyze the venting of the nuclear power plant of Laguna Verde, the line and the primary container are modeled using the thermo-hydraulic code RELAP5, simulating a release of 1% of the nominal licensed power to the container in the form of saturated steam. The vent has no problem to evacuate the energy and manages to keep the container without exceeding its design limit, and the highest percentage of thermal power that can channel the vent to the outside is approximately 3%. A sensitivity analysis increasing the diameter of the line to 14 inches allows increasing in 10% the percentage of power that can be vented to the outside without problem for the containment. (Author)

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

    1984-05-01

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

  3. 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

    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.

  4. Protection and isolation device for pipe maintenance, particularly for pipes of nuclear power plants. Dispositif d'isolement et de protection pour intervention sur tuyauterie, notamment tuyauterie de centrale nucleaire

    Dohlen, G.; Le Marquis, J.C.; Oberlin, C.

    1984-09-28

    The device is aimed to be introduced and deployed inside a pipe, to collect and remove debris (dust or scraps) or foreign bodies, resulting from the work especially maintenance work being carried out. It comprises a central mast, a deformable sealing joint, mating with the interior of the conduit; a number of arms regularly distributed around the mast, which can be folded back against the mast, to permit introduction of the device into the conduit, each arm supporting the joint at one end and being pivoted on a common base at its other end; mechanical compression apparatus, connected to the mast and the base for deploying the apparatus, and flattening the joint against the interior surface of the conduit to which it is mated; and two sheets of material, each supported at its periphery by the joint, at least one of the sheets being suitable for isolating in sealed manner the space volumes which it delimits. The invention applies to maintenance operations for which the pipes have to be maintained under a controlled inert gas atmosphere, such as sodium circuits maintenance of nuclear power plants.

  5. 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

    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)

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

    2003-01-01

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

  7. Centralized operation and monitoring system for nuclear power plants

    Kudo, Mitsuru; Sato, Hideyuki; Murata, Fumio

    1988-01-01

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

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

    2000-01-01

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

  9. The de-escalation of nuclear crises

    Nation, J.E.

    1992-01-01

    Whether and by what means nations can successfully de-escalate nuclear crises - and avoid the disastrous effects of nuclear war - will remain two of the most critical challenges facing humankind. Whatever the future of superpower relations, the United States, the Soviet Union, and other nations will undoubtedly continue to possess and to threaten the use of nuclear weapons. Moreover, the number of nations with nuclear weapons seems likely to increase. This examines how nations in crises might successfully move back from the brink of nuclear war - and how confidence-building measures might help and hinder the de-escalatory process

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

    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.

  11. 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

    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.

  12. Macrophytes control on a stretch of the Ebro River flowing through the Asco Nuclear Power Plant; Control de macrofitos en un tramo del rio Ebro a su paso por la Central Nuclear Asco

    Munte Clua, L.; Fernandez Alentorn, E.; Beltran Grau, A.

    2010-07-01

    The objective of this paper is to evaluate the time evolution of the different macrophytes populations in the stretch of the Ebro River between the town of Flix and the Asco Nuclear Power Plant, and the effects observed by the programmed flood for their control.

  13. Estudio de viabilidad de una central de restaurantes

    Sáez Lanaspa, Idoya

    2015-01-01

    Mediante este estudio de viabilidad hemos analizado un nuevo campo dentro de la gastronomía y veremos su impacto en el mercado. Queremos presentar un nuevo concepto de restaurante, fuera de lo tradicional, de comida rápida basado en el buen gusto, la comida saludable e inspirado en una nueva idea de servicio más común en otros países como Estados Unidos. Instalado en un contenedor reciclado, reformado y adaptado con zona de comedor y cocina visible, creando un ambiente agrad...

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

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

    2008-07-01

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

  15. Una nueva especie de Lepidoblepharis (Sauria, Gekkonidae de la Cordillera Central de Colombia Una nueva especie de Lepidoblepharis (Sauria, Gekkonidae de la Cordillera Central de Colombia

    Ayala Stephen C.

    1986-12-01

    Full Text Available A third Lepidoblepharis is described from temperate elevations in the Colombian Andes. Unlike L. colombianus or L. duolepis, the new species from central Antioquia is a small, moderately short toed species, reaching about 30 mm snout-vent length. Most specimens have prominent rust colored dorsolateral stripes on the tail. Una tercera especie de Lepidoblepharis se describe de zonas templadas de los Andes de Colombia. A diferencia de L. colombianus o L. duolepis, la nueva especie de Antioquia es una especie de menor tamaño que alcanza unos 30 mm de longitud rostro-ano, y los dedos son moderadamente cortos. La mayoría de los ejemplares tiene franjas dorsolaterales muy notorias de color herrumbre en la cola.

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

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

    2000-01-01

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

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

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

    1993-07-01

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

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

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

    2004-07-01

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

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

    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...

  20. 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

    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)

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

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

    2013-07-01

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

  2. Simulation of a hypothetical liquid relief valve failure (open) at Embalse nuclear power plant when a reactor shutdown is considered; Simulacion de la evolucion de la CNE (central nuclear Embalse) en el caso hipotetico de la apertura espuria de una valvula de alivio liquido con disparo del reactor

    Bedrossian, G; Gersberg, S [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

    1997-12-31

    The study of the spurious opening of the liquid relief valves is of great interest in CANDU nuclear power plants because this could lead to a loss of coolant through the degasser-condenser relief valves, and implies an undesirable intermittent opening/closure of them. In fact, there is a specific procedure to follow at Embalse nuclear power plant whenever this abnormal situation occurs. This procedure contains a section where a reactor trip is considered. Really, automatic reactor trip is not accepted to occur. No trip parameters set points are through to be reached (neutronic or process). However, the procedure considers the situation where the reactor does trip. We analyzed the plant behavior when a reactor shutdown is triggered. Our objective was to assess if after this trip, the procedure can lead the plant to a safe situation, preventing high pressures in the degasser-condenser and with the inventory recovered in the storage tank. The case was analyzed with Firebird III, Mod. 1.0 code. Two situations were considered: trip at 40 sec. and trip at 180 sec. after the liquid relief valve failed opened (the latter when the degasser-condenser fills up). Procedure analysis and code simulations showed that following the steps recommended, provided the liquid relief valve can be closed manually, the inventory that enters the degasser-condenser from the heat transport primary system through the failed valve could be recovered in the storage tank, leading the plant to shutdown in safe conditions, and preventing the degasser-condenser relief valves setpoint from being reached. (author). 3 refs., 10 figs.

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

    Myers, L.C.

    1993-11-01

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

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

    Widell, C.-O.

    1978-06-01

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

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

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

    1993-11-01

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

  6. 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

    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)

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

    Matsumoto, Masaru

    1977-01-01

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

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

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

    1999-07-01

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

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

    Gortnar, O.; Stritar, A.

    1999-01-01

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

  10. 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

    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)

  11. 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

    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)

  12. 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

    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)

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

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

    2017-01-01

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

  14. Capital óptimo de Bancos Centrales y criterios de distribución de utilidades

    Luis Fernando Escobar Patiño; Dennise Martin Alarcón

    2005-01-01

    El capital de un banco central tiene varios roles, entre ellos, servir de respaldo para sus acciones de política y absorber posibles pérdidas por las operaciones que realiza o los riesgos que confronta; generar confianza y credibilidad en el público, y contribuir a la independencia financiera y la transparencia de la entidad. En este sentido, el objetivo de este documento es explorar los roles que cumple el capital en los bancos centrales del MERCOSUR y países asociados (en adelante MERCOSUR-...

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

    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.

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

    Gerardo Moreno

    2012-02-01

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

  17. 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

    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.)

  18. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states; 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

    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.)

  19. Riesgos ocupacionales en la central de esterilización

    Martínez de Acosta, Carmen

    2010-01-01

    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...

  20. 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

    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)

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

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

    1988-01-01

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

  2. Problemas centrales del análisis de datos cualitativos

    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

  3. Centralized digital computer control of a research nuclear reactor

    Crawford, K.C.

    1987-01-01

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

  4. Instalaciones de Aire Comprimido (Central compresora)

    Enoc Duliep Lescaille

    2011-01-01

    En los últimos cincuenta años, el aire comprimido ha experimentado una incorporación inusitada en la industria ysectores de servicios, debido a su alto poder de adaptación a cualquier sistema de trabajo, ya que sus cualidades lohacen recomendable para ejecutar labores que difícilmente podrían cubrir otras energías que carecen de la flexibilidadque lleva implícito éste. La instalación de aire comprimido consta de dos partes ...

  5. 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

    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)

  6. 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

    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)

  7. New recommendations of the ICRP and the ALARA program of the Nuclear power plant of Laguna Verde; Nuevas recomendaciones del ICRP y el programa ALARA de la Central Laguna Verde

    Padilla C, I [Comision Federal de Electricidad, Central Laguna Verde (Mexico)

    1991-07-01

    In view of the events happened in it finishes it decade, in the nuclear environment, it is necessary that any he/she practices that it involves exhibition to the radiation, real or potential, be detailed and systematically analyzed by the light of the current knowledge, capitalizing the generated experience. They think about three fundamental aspects in the campaign of radiological cultivation: 1. New methods of evaluation of equivalent dose. 2. Limit of individual dose, base of the change and control implications, and 3. Analysis philosophies and the application of the system of dose limitation. The program ALARA of the Laguna Verde Central from its installation in 1987 observes and it implements actions trending to optimize it practice of situation of potential and planned exhibition with the purpose of fulfilling the commitment settled down in the declaration of political of this program.

  8. Notes on the Start-Up of the Latina Power Station; Notes concernant le demarrage de la centrale nucleaire de Latina; Zapusk ehlektrostantsii Latina; Notas sobre la puesta en marcha de la central electrica de Latina

    Calabria, G.; Gualtieri, G. [AGIP Nucleare, Milano (Italy)

    1963-10-15

    Information is given on the start-up of the first Italian nuclear power plant, the Latin Power Station, designed for an electrical output of 200 MW, incorporating a natural uranium-gas-graphite reactor. After a brief description of the main characteristics of the station, details are given on die performance of the final tests of the plant, on the fuel loading and on the sequence of commissioning operations, measurements and controls subsequent to the criticality attained. The operations for the start-up and connection of the station to the electrical network are treated. The organization problems relevant to the station operation including personnel preparation and qualification, safety measures, are also illustrated. (author) [French] Le memoire donne des renseignements sur le demarrage de la premiere centrale nucleaire italienne, la centrale de Latina, dont la puissance electrique est de 200 MW et qui fonctionne avec un reacteur du type uranium naturel-gaz-graphite. Apres une breve description des caracteristiques essentielles de la centrale, des explications detaillees sont donnees sur les resultats des derniers essais auxquels elle a ete soumise, sur le chargement du combustible et sur la serie des operations de mise en service, des mesures et des verifications auxquelles il a ete procede lorsque l'etat critique a ete atteint. Les operations de demarrage et de raccordement de la centrale au reseau electrique sont etudiees dans le memoire, ainsi que les problemes d'organisation que pose l 'exploitation de la centrale, notamment en ce qui concerne la formation du personnel et les mesures de securite. (author) [Spanish] Se comunican datos sobre la puesta en marcha de la primera central nucleoelectrica italiana, en Latina, proyectada para desarrollar una potencia de 200 MW (e), que se basa en un reactor de uranio natural moderado por grafito u refrigerado por gas. Despues de describir brevemente las caracteristicas de la central, se dan detalles sobre el

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

    Jencic, I.; Glumac, B.

    2001-01-01

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

  10. Espacio central en la arquitectura: las claves de su permanencia

    Bosch Reig, Ignacio; Martínez Boquera, Arturo; Fernández Gómez, Margarita; Bosch Roig, Lluis

    2006-01-01

    En el presente artículo se exponen, de forma resumida, los resultados de la investigación desarrollada sobre el "Espacio Central Arquitectónico", exponiendo los conceptos a los que alude, los orígenes en los que se basa, las geometrías que lo desarrollan, las tres direcciones formales en las que se ha presentado a lo largo de la historia: espacio-volumen, concebido "de fuera a dentro"; espacio-cavidad, concebido "de dentro a fuera"; y espacio-fluido, como síntesis de ambos. Haciendo especial ...

  11. Riesgos ocupacionales en la central de esterilización

    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. Granuloma central de células gigantes Giant cells central granuloma

    Ayelén María Portelles Massó

    2011-03-01

    Full Text Available El granuloma reparativo central de células gigantes es una lesión proliferativa no neoplásica de etiología desconocida. Se presenta un paciente masculino de 40 años de edad, portador de prótesis parcial superior. Fue remitido al Servicio de Cirugía Maxilofacial del Hospital "V. I. Lenin" por presentar aumento de volumen en reborde alveolar superior, de color rojo grisáceo y que provocaba expansión de corticales óseas. Una vez analizados los exámenes clínicos, radiográficos e histopatológicos se diagnosticó un granuloma reparativo central de células gigantes Se realizó exéresis quirúrgica de la lesión y extracción de dientes adyacentes con una evolución satisfactoria sin señales de recidivas luego de tres años del tratamiento. El granuloma reparativo central de células gigantes se presentó como respuesta a un trauma. La correcta interpretación de los datos clínicos, radiográficos e histopatológicos nos permitió llegar al correcto diagnóstico y plan de tratamiento.Giant-cell central reparative granuloma is non neoplastic proliferative lesion of unknown etiology. We report a 40 years old male patient who was admitted at the Maxillofacial Service of the "V. I. Lenin" Hospital. The patient had partial upper prosthesis and was complaining of red-grey volume increase lesion in upper alveolar ridge which led to the expansion of cortical bone. Having analyzed clinical, radiographic and histopathological findings the case was concluded as a giant-cell central reparative granuloma. Surgical exeresis and adjunct tooth extraction were done. After three years of treatment, satisfactory follow up without recurrence is reported.

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    Asie centrale. Asie centrale. Read more about The Alliance to Scale Digital Innovation and Entrepreneurship (Seed Alliance). Langue English. Read more about La transformation économique de l'Inde favorise-t-elle l'autonomisation économique des femmes? Langue French. Read more about Does India's Economic ...

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    Asie centrale. Asie centrale. Read more about Climate Change, Innovation, and Information and Communication Technologies. Langue English. Read more about Programme de formation en actuariat Inde-Canada (Waterloo). Langue French. Read more about Actuarial Sciences Graduate Training Program ...

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    Asie centrale. Asie centrale. Read more about Renforcement de la recherche en sciences sociales en Iraq. Langue French. Read more about Strengthening Social Science Research in Iraq. Langue English. Read more about Genetically Modified Organisms : Public Knowledge, Attitudes and Perceptions (India). Langue ...

  16. Evolution of central banking? De Nederlandsche Bank 1814-1852

    Uittenbogaard, R.A.

    2014-01-01

    Nowadays the role of central bank is unquestioned and nearly ubiquitous. But was this always the case? This thesis analyses how De Nederlandsche Bank (DNB) developed into a central bank during the first four decades of its existence. Its establishment in 1814 was the result of a combination of both

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

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

    2016-07-01

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

  18. Knowledge management for modelling nuclear power plants control in incidental and accidental states; Application de la systemique a la conception d`un modele de conduite en mode degrade d`une centrale nucleaire

    MIllerat, P

    1996-11-01

    A knowledge model uses different techniques of complex systems management. Progress realised in the computer representation of links between different documents allows us to design a software facilitating the comprehension of the model built. This model is a qualitative model of the operators` behaviour in nuclear power plant accidental control. This model concerned three topics closely linked together. The first gives a description of every physical phenomena implied the application of the State-oriented Approach (APE in French) procedures. It`s referred as model of process. The second gives a description of every activities used by the operators` team to manage all thermohydraulic incidents and accidents. It`s a functional model also referred as tasks model. The quality of the method, based on the Systems` Science, capitalized a know-how simply transferable to design a new software on industrial process to support the operators. (author). 10 refs.

  19. 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

    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)

  20. 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

    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)

  1. CENTRAL NUCLEAR ELECTRIC, A FUTURE OF ROMANIAN ENERGY

    Gabriel I. NĂSTASE

    2010-05-01

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

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

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

    1989-01-01

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

  3. Complicaciones mecánicas de los accesos venosos centrales

    Rodrigo Rivas, T.

    2011-01-01

    Las complicaciones mecánicas de los accesos venosos centrales son frecuentes, 2 a 15% y en ocasiones pueden comprometer la vida del paciente. Hay factores que determinan el riesgo de una u otra, que pueden ser modificados o enfrentados de diferente forma para minimizarlo. En esta puesta al día se describen las complicaciones más frecuentes o de mayor gravedad como son: el neumotórax, la embolia aérea, mal-posición del catéter, perforación de grandes venas, punción arterial, arritmias, trom...

  4. Instrumentation of a Charpy-pendulum. Additional data obtained from it and its application to nuclear reactor pressure vessels surveillance programs; Instrumentacion de un pendulo Charpy. Datos adicionales obtenidos a partir de la misma y su aplicacion a programas de vigilancia de centrales nucleares

    Chomik, Enrique P; Dhers, Horacio; Iorio, Antonio F [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Materiales; Ciriani, Dario F [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Combustibles Nucleares

    1999-07-01

    Charpy test gives information about a material dynamic fracture behavior. In a plain Charpy test, this information is the absorbed energy during fracture of the specimen, lateral deformation and the percentage of ductile fracture of the specimen. These parameters can then be used for the determination of the material response to a dynamic applied load, and are used at present to determine the brittle-ductile transition temperature of a material. However, there is a lot of additional information that can be obtained from a Charpy test, which is vital for the case of surveillance programs of nuclear power plants, where it is necessary to get the most available information from the specimens to be tested, because each one of them was irradiated for many years under temperature and neutronic flux conditions similar to that of the internal surface of the reactor pressure vessel, which converts these specimens in unique and very expensive ones. This additional information can be obtained from the curve that determines the evolution of the applied force to the specimen throughout the time involved in its fracture. It was possible to instrument a Charpy pendulum at a fraction of the cost necessary to buy an instrumentation package like the ones available in the market, and since the instrumentation equipment obtained is easy to transport. It has the additional advantage that can be used to instrument any other pendulum replacing only the hammer of the pendulum with a instrumented one for that pendulum. (author)

  5. 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

    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)

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

    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.

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

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

    2008-07-01

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

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

    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.

  9. DINÁMICA NUTRICIONAL EN CINCO PARRONES DE DIFERENTE PRODUCTIVIDAD DEL VALLE CENTRAL REGADO DE CHILE

    Ruiz S., Rafael

    2000-01-01

    Se efectuó un estudio comparativo de aspectos nutricionales del suelo y de la planta en 5 parronales de uva de mesa cv. Thompson Seedless con un historial muy diferente de productividad y vigor, en el valle central de Chile, durante 4 años. Durante este período se efectuaron análisis nutricionales mensuales, que incluyeron además de N, P y K total, fracciones de N de reserva como arginina y aminoácidos totales y carbohidratos de reserva en la parte aérea (sarmientos y brotes) y en raíces. El ...

  10. The Performance of Major Plant Items at Calder Hall; Fonctionnement des elements principaux de la centrale de Calder Hall; Kharakteristika osnovnykh uzlov ustanovki v Kolder-Kholle; Rendimiento de los principales elementos de la central de Calder Hall

    Desbruslais, E. L. [United Kingdom Atomic Energy Authority, Seascale, Cumberland (United Kingdom)

    1963-10-15

    questioned. Statistics have shown that the data-logging equipment is extremely reliable. More standardization of fuel handling equipment is advocated. The use of special flasks and special discharge equipment are time-wasting and should be discouraged. Modifications made to the charge/discharge machines and auxiliary plant are described. Careful handling of fuel during loading is emphasized. Fuel channel television cameras and special grabs have enabled discharge times to be reduced. Only minor faults have been experienced with the compled control-rod mechanisms and associated control equipment. As far as possible plant controls should be centralized and important control centres and items of plant should be protected from accidental damage from external sources. Automatic start-up and parallelling features for the emergency diesel plant are considered unnecessary but the plant could, with advantage, be centralized. (author) [French] Depuis plus de six ans, Calder Hall fonctionne comme centrale de base et a subi des defaillances semblables a celles qu'on peut constater dans les centrales electriques classiques. Toutes ces defaillances se sont produites dans la partie classique de la centrale; aucune n'a ete relevee dans les reacteurs proprements dits. L'experience a montre que du point de vue de la securite du reacteur, il faut traiter comme un tout les reacteurs et les principaux elements de la centrale ainsi que les connections avec le reseau. On n'a constate aucune alteration importante donnant a penser que le caisson du reacteur ou le ralentisseur de graphite limiteront la duree de vie de la centrale. La distribution de la temperature autour des conduites de sortie du gaz est asymetrique, ce qui limite actuellement la puissance du reacteur. Il y aurait eu interet a amenager au debut un plus grand nombre de thermocouples.d'instruments de mesure des efforts et de dispositifs permettant un examen visuel des zones soumises a des contraintes et des temperatures elevees. Les

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

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

    2013-10-01

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

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

    Duran, Felicia Angelica; Waymire, Russell L.

    2013-01-01

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

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

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

    2013-10-15

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

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

    Messner, S.; Strubegger, M.

    1986-12-01

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

  15. Collective phenomena in non-central nuclear collisions

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

    2008-10-20

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

  16. Collective phenomena in non-central nuclear collisions

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

    2008-01-01

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

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

    1979-09-01

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

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

    Vlcek, Tomas; Jirusek, Martin

    2015-01-01

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

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

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

    1982-01-01

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

  20. Current experience with central-station nuclear cogeneration plants

    1981-10-01

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

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

    1992-12-01

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

  2. The relations between de-alerting nuclear force and nuclear strategy

    Li Zhimin

    2001-01-01

    De-alerting nuclear force is a hot-point issue in recent years. The relations between de-alerting and strategy (including nuclear force, target doctrine and use principle et al.), stability, advanced conventional force and NMD of the United States are analyzed, the impact of de-alerting on Chinese nuclear force were discussed and the proposal of de-alerting by stages is presented

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

    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).

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

    Santiago VEGA SOMBRÍA; Juan Carlos GARCÍA FUNES

    2012-01-01

    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 ...

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

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

    2000-01-01

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

  6. Nuclear DNA content variation among central European Koeleria taxa

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

    2006-01-01

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

  7. Complicaciones mecánicas de los accesos venosos centrales

    Dr. T. Rodrigo Rivas

    2011-05-01

    En esta puesta al día se describen las complicaciones más frecuentes o de mayor gravedad como son: el neumotórax, la embolia aérea, mal-posición del catéter, perforación de grandes venas, punción arterial, arritmias, trombosis venosa asociada a catéter venoso central (CVC y oclusión del CVC; algunos elementos de prevención, diagnóstico y tratamiento así como el impacto que puede tener la ultrasonografía rutinaria para instalar un CVC.

  8. Nuclear magnetic resonance imaging of the central nervous system

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

    1989-01-01

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

  9. 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

    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.

  10. Le genre, variable centrale de la violence sociale ?

    Ayral , Sylvie; Raibaud , Yves

    2010-01-01

    Le but de cet article n'est pas de savoir si le genre est une variable centrale de la violence sociale mais comment cette hypothèse (qui induit la possibilité d'un changement social) est réfutée et quelles connaissances sont mobilisées à cet effet. Il s'agit d'identifier les modèles récurrents mis en œuvre par les « membres » (par exemple la communauté scientifique des sciences humaines et sociales) lorsqu'ils.elles examinent le sens de ces modèles par l'observation de « ce que les gens font ...

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

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

    2003-01-01

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

  12. AP1000, a nuclear central of advanced design

    Hernandez M, N.; Viais J, J.

    2005-01-01

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

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

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

    2000-06-15

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

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

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

    2000-06-01

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

  15. Super compacting of drums with dry solid radioactive waste in the nuclear power plant of Laguna Verde;Super compactacion de bidones con desecho radiactivo solido seco en la central nucleo electrica Laguna Verde

    Ramirez G, R.; Lara H, M. A.; Cabrera Ll, M.; Verdalet de la Torre, O., E-mail: marco.lara@cfe.gob.m [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Nautla-Cardel Km. 42.5, Alto Lucero, Veracruz (Mexico)

    2009-10-15

    The nuclear power plant of Laguna Verde located in the Gulf of Mexico, completes in this 2009, nineteen years to produce by nuclear means 4.78% of the electric power that Mexico requires daily. During this time, the Unit 1 has generated more of 88.85 million mega watt-hour and the Unit 2 more of 69.48 million mega watt-hour with an availability average of 83.55%. Derived of their operation cycles, the nuclear power plant has generated (as any other installation of its type) radioactive wastes of low activity that at the moment are temporarily stored in the site. Due to the life cycle of the nuclear power plant, actually has become necessary to begin a project series focused to continue guaranteeing the storage of these wastes, guarantee that is a license requirement for the operation of this nuclear installation before the National Commission of Nuclear Security and Safeguards. The Federal Commission of Electricity beginning a project that allows continue guaranteeing space of sufficient storage for the wastes that the nuclear power plant of Laguna Verde could generate for the rest of its useful life, this project consisted on a process of physical volume reduction of dry solid radioactive wastes denominated super compacting, it has made possible to reduce the volume that these wastes occupy in the temporary storage noted Dry Solid Radioactive Wastes Deposit located inside the site that occupies the nuclear power plant of Laguna Verde. This work presents the super compacting results, as well as a description of the realization of this task until concluding with the super compacting of 5,854 drums with dry solid radioactive waste of low activity. We will enunciate which were the radiological controls that the Department of Radiological Protection of the nuclear power plant of Laguna Verde applied to this work that was realized for first time in Mexico and the nuclear power plant. (Author)

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

    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.

  17. Suministro de alimentos e indicadores ambientales en el Magreb Central

    José Soler

    2013-01-01

    Full Text Available El suministro de alimentos básicos en Argelia, Marruecos y Túnez se basa en una gran proporción en las importaciones desde el exterior, que presentan una balanza comercial agrícola negativa y un flujo de biomasa, energía, proteína y agua virtual hacia el interior del metabolismo de su economía. Aparece también una dualidad entre los sistemas cerealísticos extensivos para consumo interno y los hortofrutícolas intensivos para la exportación. El rendimiento es el factor agronómico que explica la producción de los cereales, aunque la superficie dedicada a su cultivo puede ser también limitante. El uso de insumos y maquinaria es bajo en el Magreb Central, propio de agriculturas con un bajo índice de tecnificación que limitaría el rendimiento, aunque esto se compensa en parte con una elevada productividad de la mano de obra agrícola.

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

    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

  19. LA JUNTA CENTRAL DE HIGIENE DE COLOMBIA, OTRA DE LAS VÍCTIMAS DE LA PANDEMIA DE GRIPA DE 1918-1919.

    Abel Fernando Martínez Martín

    2014-12-01

    Full Text Available Objetivo: El presente artículo, a través de las fuentes primarias, busca establecer el papel del estado y las medidas tomadas ante la aparición de la pandemia de gripa de 1918 en Bogotá. Materiales y métodos: Se consultaron como fuentes primarias los periódicos que circulaban en Bogotá y Colombia durante 1918, los informes oficiales de la Junta Central de Higiene y de la Junta de Socorros y las tesis de medicina de la Universidad Nacional de Colombia. Además de hacer una revisión de las fuentes secundarias sobre el tema. Conclusión: La Higiene Pública, en manos del Estado, se mostró incapaz de hacer frente a la pandemia, siendo la Junta de Socorros, un organismo privado constituido por los notables de la capital, la única institución que realizó acciones efectivas con los afectados. Esta institución aparece recordada y alabada por los medios escritos, en contraposición a la Dirección Nacional y Municipal de Higiene, que fueron fuertemente criticadas por su escasa intervención ante la pandemia y representadas como víctimas en las caricaturas. Palabras Clave: Gripa 1918, Pandemia, Bogotá, Junta de Socorros, Junta Central de Higiene.

  20. The Physical Protection of Nuclear Material and Nuclear Facilities; Proteccion Fisica De Los Materiales Y Las Instalaciones Nucleares

    NONE

    1999-06-15

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers [Spanish] La proteccion fisica contra el robo o la desviacion no autorizada de materiales nucleares y contra el sabotaje de las instalaciones nucleares por parte de individuos o grupos es motivo de preocupacion nacional e internacional desde hace mucho tiempo. Aunque la obligacion de crear y hacer funcionar un sistema completo de proteccion fisica de las instalaciones y materiales nucleares en el territorio de un Estado determinado incumbe exclusivamente al Gobierno de dicho Estado, el que esa obligacion se cumpla o no, y si se cumple, en que medida o hasta que punto, son cosas que no dejan indiferentes a los demas Estados. Por ello, la proteccion fisica se ha convertido en motivo de interes y cooperacion internacional. La necesidad de la cooperacion internacional se hace evidente en los casos en que la eficacia de la proteccion fisica en el territorio de un Estado depende de que otros Estados tomen tambien medidas apropiadas para evitar o hacer fracasar los actos hostiles dirigidos contra instalaciones y

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

    Paulin, Ph.

    2006-01-01

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

  2. Diagnóstico ambiental preliminar de la Central Termoeléctrica de Paipa

    Carlos Magno Martínez Mora

    1990-01-01

    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. Waste management as the central task of nuclear energy policy

    Boehm, H.

    1977-01-01

    A survey article deals with the tasks of the different steps of waste disposal, the amounts of fuel elements and waste obtained and the role of reprocessing in waste management, the intermediate storage of fuel elements and the alternative reprocessing or direct ultimate storage of fuel elements. The present state of the art of large-scale waste management in West Germany, is briefly outlined including responsibilities. (HPH) [de

  4. 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

    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)

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

    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.

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

    1977-10-01

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

  7. Annual report 89. Central Bureau for nuclear measurements

    1990-01-01

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

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

    Agirsoy, L.

    1987-01-01

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

  9. Themes in nuclear law; Temas de Derecho Nuclear

    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.

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

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

    2008-07-01

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

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

    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.

  12. Neutron fluence measurement in nuclear facilities.; Medicion de flujos de neutrones en instalaciones nucleares.

    Camacho L, M E

    1997-12-01

    The objective of present work is to determine the fluence of neutrons in nuclear facilities using two neutron detectors designed and built at Instituto Nacional de Investigaciones Nucleares (ININ), Mexico. The two neutron detectors are of the passive type, based on solid state nuclear tracks detectors (SSNTD). One of the two neutron detectors was used to determine the fluence distribution of the ports at the nuclear research reactor TRIGA Mark III, which belongs to ININ. In these facilities is important to know the neutron fluence distribution characteristic to carried out diverse kind of research activities. The second neutron detector was employed in order to carry out environmental neutron surveillance. The detector has the property to separate the thermal, intermediate and fast components of the neutron fluence. This detector was used to measure the neutron fluence at hundred points around the primary container of the first Mexican Nuclear Power plant `Laguna Verde`. This last detector was also used to determine the neutron fluence in some points of interest, around and inside a low scattering neutron room at the `Centro de Metrologia de Radiaciones Ionizantes` of the ININ, to know the background neutron field produced by the neutron sources used there. The design of the two neutron detector and the results obtained for each of the surveying facilities, are described in this work. (Author).

  13. Central móvil de hormigón asfáltico

    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.

  14. DISPERSION LARVAL Y PATRONES DE CONECTIVIDAD EN PECES LITORALES DE CHILE CENTRAL

    MANZUR, LIDIA ELENA

    2013-01-01

    En estudios de ecología marina, uno de los temas centrales es la conectividad o intercambio de individuos entre poblaciones marinas. Para muchas especies bentónicas con ciclos de vida complejo, este intercambio ocurre en los estadios larvales pelágicos. El pequeño tamaño de las larvas y su comportamiento, la dificultad en realizar seguimientos desde la eclosión de huevos hasta el asentamiento y las condiciones oceanográficas en las cuales se desarrollan estas especies, dificultan el entendimi...

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

    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

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

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

    2015-09-15

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

  17. Organización territorial de los antiguos mayas de Belice Central

    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...... se centran predominantemente sobre cada sitio investigado. Las exploraciones en Belice Central de las cuatro últimas décadas, sin embargo, han sacado a la luz numerosas piezas clave que aportan datos epigráficos, incluyendo “Glifos Emblema”. Vistos en conjunto, los datos arqueológicos y epigráficos...... proporcionan una posición más ventajosa en la determinación de la estructura del paisaje socio-político del Período Clásico del Valle de Belice. Udgivelsesdato: 2008...

  18. Reports by the Parliamentary Office for scientific and technological assessments. Thursday, April 14, 2011. Information on the Fukushima accident by Mr Thomas Houdre, Nuclear plant manager by the Nuclear Safety Authority. Nuclear safety, the role and future of the sector - Presentation of the feasibility study; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 14 avril 2011. Point d'information sur l'accident de Fukushima par M. Thomas Houdre, directeur des centrales nucleaires de l'Autorite de Surete Nucleaire. Securite nucleaire, place de la filiere et son avenir - Presentation de l'etude de faisabilite

    NONE

    2011-04-15

    In a first part, a representative of the ASN describes the situation of the Fukushima Daiichi nuclear power station about one month after the accident. He reports the phenomena which have occurred, gives some explanations, compares this accident with that of Chernobyl. The second part is a discussion about the content and the organization of a parliamentary mission which aims at investigating nuclear safety, and the role and future of the nuclear sector

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

    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.

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

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

    2017-08-01

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

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

    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

  2. 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

    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)

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

    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:…

  4. Renewal of release and sampling authorizations of the Cattenom nuclear power plant. Complementary note on the authorizations demands of radioactive release; Renouvellement des autorisations de rejets et de prelevements de la centrale nucleaire de Cattenom. Note complementaire sur les demandes d'autorisation de rejets radioactifs

    Marignac, Y.; Coeytaux, X

    2003-10-15

    The present note follows the exchanges with the contracting authority, the Cattenom nuclear power plant, during the public hearing stood on the 10. of october 2003 at Cattenom. In the frame of the evaluation of the inquiry file by WISE -Paris, this note constitutes a deepening on the question of authorization demands for the radioactive releases. The elements supplied by E.D.F in the file submitted to the inquiry, and the presentation of these demands and the information complements brought during the meeting of the 10. of october, raise different problems of evaluation and justification relative to the evolution of radioactive release of Cattenom. The note analyses in particular, the increasing of dosimetry impact expected from the progression of real release forecasted by the operator, and the weight linked to the feedback of clad failure problem. It discusses the justification brought by E.D.F. to the standing and even the increasing of liquid tritium release instead of the expected reduction, facing the arguments of the operator to the experience feedback on the park and to the uncertainties on the future progress. (N.C.)

  5. Administrative Arrangement between the Atomic Energy Control Board of Canada and le Service central de surete des installations nucleaires du Ministere de l'industrie et de l'amenagement du territoire de la Republique francaise for the exchange of technical information and cooperation in the regulation of nuclear safety (10 May 1990)

    1990-01-01

    The Arrangement which entered into force on the date of its signature and remains in effect for five years, provides for exchange of information between both agencies on the regulation of nuclear facilities and intervention measures in cases of emergency. This includes information on regulatory procedures for the safety of designated nuclear facilities, notification of important events, such as serious operating incidents, reactor shutdowns ordered by the regulatory authorities, etc. (NEA) [fr

  6. 1989 annual report of the Rossendorf Central Institute of Nuclear Research

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

    1990-01-01

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

  7. Calidad del servicio de atención en la Unidad de Laboratorio de Emergencia y Laboratorio Central, Hospital Público de Lima, 2016

    Castillo Acuña, Marissa Gladys

    2016-01-01

    La Calidad en el Servicio de Atención de acuerdo a Camarasa (2004) “La Calidad de los servicios de atención constituyen el conjunto de prestaciones y atenciones que el cliente espera recibir de la organización que los presta”. (p.13) Objetivo: Comparar el nivel de calidad del servicio de atención en la unidad de Laboratorio de Emergencia con respecto a la unidad de Laboratorio Central en un Hospital Público de Lima 2016. Metodología: Estudio de Nivel descriptivo comparativo, tr...

  8. 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

    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.)

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

    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.

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

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

    1997-12-31

    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.

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

    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 ...

  12. Shippingport Atomic Power Station Operating Experience, Developments and Future Plans; La centrale nucleaire de Shippingport, experience de son fonctionnement et plans pour l'avenir; Shippingportskaya atomnaya ehlektrostantsij, opyt ehkspluatatsii, usovershenstvovaniya i plany na budushchee; Central nucleoelectrica de Shippingport; experiencia adquirida con su explotacton y programa de desarrollo

    Feinroth, H. [Division of Reactor Development, United States Atomic Energy Commission, Washington, DC (United States); Oldham, G. M. [Shippingport Atomic Power Station, Duquesne Light Company, Pittsburgh, PA (United States); Stiefel, J. T. [Bettis Atomic Power.Labora Tory, Westinghouse Electric Corporation, Pittsburgh, PA (United States)

    1963-10-15

    Shippingport. Les resultats fournis par la serie complete des essais realises a Shippingport sont compares avec les calculs; la concordance est satisfaisante. Les auteurs examinent aussi les performances du cceur du reacteur, la stabilite de l'installation et sa reponse aux variations de charge, les performances des cartouches de combustible et des barres de controle, les effets a long terme tels que la corrosion et la radioexposition, le fonctionnement des divers elements constitutifs, etc. Les auteurs examinent le principal objectif des programmes actuel et futur de Shippingport pour le developpement de la technique fondamentale des reacteurs refroidis a l'eau. On prevoit notamment de continuer l'exploitation de la centrale et d'etudier, de fabriquer et d'essayer un deuxieme coeur de reacteur a longue duree de Vie et de grande puissance specifique. Avec une puissance nominale brute de 150 MWe et une duree de vie equivalant a 10 000 h de marche a pleine puissance pour la premiere charge de combustible enrichi, le coeur No. 2 aura cinq fois et demie la production d'energie prevue pour le cceur Ne 1 et deux fois sa puissance specifique. Les auteurs decrivent le coeur No. 2 et indiquent brievement les principaux progres qui ont ete realises a cet egard dans les domaines de la physique des reacteurs, de la metallurgie, du transfert de chaleur, de la circulation du fluide caloporteur et de la fabrication des cartouches de combustible. Ils exposent les plans de decontamination de la centrale nucleaire et les modifications qu'entrafnera l'installation du coeur No. 2 plus puissant. (author) [Spanish] Los autores exponen y analizan los resultados obtenidos en cinco aflos de ensayo y explotacion de la central nucleoelectrica de Shippingport y examinan el programa de actividades en curso y los planes para el futuro. Con ese programa se proyecta perfeccionar la tecnologia basica de los reactores de agua ligera, a fin de contribuir a la reduccion de los costos de la energia nuclear. La

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

    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.

  14. 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

    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

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

    Garde Sesma, Idoia

    2014-01-01

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

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

    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.

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

    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.

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

    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.

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

    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.

  20. Central de producción de calor - Madrid – España

    Laorden Jiménez, J.

    1973-10-01

    Full Text Available The Heat Production Station of the University City Hospital in Madrid is described, after several years operation. The Station is equipped for an output of 13,000,000 kcal/hr, for heating; 1,000,000 kcal/hr, for hospital hot water, and 3,200,000 kcal/hr, for steam at 5 kp/cm2. The different alternatives are presented and the general outline of the solution chosen, as well as a comprehensive list of the materials used.Se describe la Central de Producción de Calor del Hospital Clínico de la Ciudad Universitaria de Madrid, después de algunos años de funcionamiento. La Central está preparada para una producción de 13.000.000 de kcal/h, para calefacción; 1.000.000 de kilocalorías/h, para agua caliente sanitaria, y 3.200.000 kcal/h, para vapor a 5 kp/cm2. Se presentan las diversas alternativas y el esquema general de la solución elegida, así como una extensa relación de ios materiales empleados.

  1. Basílica del Real Monasterio de San Lorenzo de El Escorial. Restauración de las cubiertas y fachadas laterales de la nave central

    Esther de Vega García

    2005-12-01

    Full Text Available Las patologías del plomo empleado en las cubiertas de la nave central de este templo tan significativo constituían un riesgo para la integridad de las pinturas al fresco de sus bóvedas internas. El artículo relata e ilustra con detalle el montaje de la sobrecubierta de protección para la realización de los trabajos sin exponer al monumento, el proceso de sustitución de los emplomados existentes, la reconstrucción de las buhardillas y, por último, la restauración de las fachadas laterales de la iglesia.

  2. Antecedentes geobotánicos de una cuenca andina de Chile Central

    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

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

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

    2015-09-15

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

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

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

    2009-01-01

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

  5. 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

    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

  6. 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

    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)

    1999-12-31

    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.

  7. 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

    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.

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

    Potter, W.C.

    1997-01-01

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

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

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

    2011-05-01

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

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

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

    2008-12-15

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

  11. Autofluorescencia de fondo en pacientes con coriorretinopatía serosa central Fundus autofluorescence in patients with central serous chorioretinopathy

    Eva R Santana Alas

    2010-01-01

    Full Text Available OBJETIVO: Describir las características de la autofluorescencia de fondo en pacientes con coriorretinopatía serosa central y determinar su relación con las alteraciones funcionales y anatómicas de la región macular. MÉTODOS: Estudio descriptivo, transversal en 21 ojos (21 pacientes con coriorretinopatia serosa central en diferentes estadios evolutivos. Se identificó el patrón de autofluorescencia en el área de desprendimiento neurosensorial, se usó el angiógrafo retinal de Heidelberg a 30°. Con la tomografía de coherencia óptica, se midió el grosor macular central y se describieron los cambios anatómicos. A 12 de los pacientes se les realizó angiografía fluoresceínica en el Angiógrafo Retinal de Heidelberg. RESULTADOS: Se encontró hipoautofluorescencia en el 51,90 %, hiperautofluorescencia en el 42,86 %; coexisten ambos en el 4,76 %. No hubo diferencia significativa entre la hiperautofluorescencia y la hipoautofluorescencia en cuanto a agudeza visual mejor corregida (media de 0,43 y 0,49, respectivamente; p= 0,184, ni respecto al grosor macular central (media de 371,3 µm y 388,1 µm, respectivamente; p= 0,867, pero sí entre el tiempo de evolución y el patrón de autofluorescencia, (p= 0, 023. En ojos con hiperautofluorescencia se observó por tomografía de coherencia óptica irregularidad en capas externas y en epitelio pigmentario de la retina. El 83,3 % de los casos que requirieron angiografía fluoresceínica presentaron hiperfluorescencia que coincidió con la hipoautofluorescencia del sitio de fuga. CONCLUSIONES: En la coriorretinopatía serosa central se encuentran diferentes patrones de autofluorescencia, los que reflejan cambios en la retina externa y epitelio pigmentario de la retina. La autofluorescencia puede ayudar a identificar el sitio de difusión focal en el epitelio pigmentario de la retina.OBJECTIVES: To describe the peculiarities of the Fundus Autofluorecense in patiens with Central Serous

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

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

    2013-01-01

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

  13. 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

    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)

    1997-12-31

    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

  14. 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

    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

  15. Seismic evaluation of nuclear installations; Avaliacao sismica de instalacoes nucleares

    Mattar Neto, Miguel [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1997-10-01

    Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs.

  16. Estilos de crianza en familias nucleares con hijos únicos

    Quezada Fernández, Juan Carlos

    2015-01-01

    La Teoría clásica de Diana Baumrind plantea tres estilos de educación familiar, a partir de ella se pretende conocer los estilos educativos de las familias nucleares con un solo hijo, y relacionar estos estilos de crianza con la estructura familiar: jerarquía límites y alianzas. El estudio fue cuantitativo y cualitativo, las variables dependientes fueron los estilos de educación familiar, las variables independientes la estructura familiar. La selección de la muestra se realizó desde la ...

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

    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.

  18. Detection of nuclear radiations; Deteccion de Radiaciones nucleares

    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)

  19. Detection of nuclear radiations; Detectores de radiaciones nucleares

    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.

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

    NONE

    1995-12-01

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

  1. Diagnostic ?tiologique du diab?te insipide central: ? propos de 41 cas

    Chaker, Fatma; Chihaoui, Melika; Yazidi, Meriem; Slimane, Hedia

    2016-01-01

    La survenue d'un syndrome polyuro-polydipsiqueavec des urines hypotoniques n?cessite une strat?gie diagnostique rigoureuse. Le but de cette ?tude ?tait d??tudier les modalit?s de diagnostic du diab?te insipide central. A travers une ?tude r?trospective de 41 cas de diab?te insipide central(DIC) collig?s au service d'Endocrinologie ? l'h?pital de la Rabta de Tunis, allant de l'ann?e 1990 ? l'an 2013, nous avons relev? les circonstances de d?couverte du DIC, les anomalies du bilan ant?-hypophys...

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

    Mirambel Boquera, J.

    2011-07-01

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

  3. 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

    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

  4. 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

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

    1991-12-31

    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

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

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

    1998-01-01

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

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

    Gómez Muñoz, Geovanny Patricio; Méndez Peñaloza, Gino Fabricio

    2011-01-01

    Hoy en día las Centrales de Generación Eléctrica necesitan contar con un eficiente programa de mantenimiento, el cual sea conocido por todo el personal para que se lleve a cabo de la mejor manera. Y si a esto le sumamos la implementación de un programa de mantenimiento asistido por computador, que nos permitirá mejorar la gestión del mantenimiento en la Central. Con el contenido de este proyecto y como resultado es un plan de mantenimiento concreto que permite organizar de manera eficiente...

  7. Formulación de Funciones de Costo de Incertidumbre en Pequeñas Centrales Hidroeléctricas dentro de una Microgrid

    Ferney Sadid Molina Sanchez

    2017-02-01

    Full Text Available El presente artículo propone extender el concepto de costo de incertidumbre en la operación de sistemas de energía que contienen fuentes renovables (solar y eólica a sistemas de potencia con penetración de pequeñas centrales hidroeléctricas (PCHs. La extensión propuesta se logra obtener conociendo la probabilidad de distribución del caudal donde está la PCH. Para ello, se presenta el desarrollo analítico de los costos de incertidumbre en pequeñas centrales hidroeléctricas, obteniendo la probabilidad de potencia inyectada por la central y desarrollando la formulación matemática de los costos por subestimar y sobreestimar la potencia disponible. Adicionalmente, se presenta la validación de la formulación analítica a través de simulaciones de Monte Carlo, comprobando que en los dos casos (costo de incertidumbre con la formula analítica y valor esperado de la simulación de Monte Carlo se llega al mismo costo de incertidumbre. Adicionalmente, se presentan los códigos que calculan el costo esperado mediante la formulación analítica obtenida y el costo esperado mediante el valor medio de los costos de la simulación de Monte Carlo.

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

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

    1997-01-01

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

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

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

    2016-01-22

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

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

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

    2016-01-01

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

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

    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.

  12. 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

    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.

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

    Goetzke, R.E.

    1987-01-01

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

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

    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.

  15. Instituto de Asuntos Nucleares: Science and technology for progress

    Ahumada, J.J.; Zuleta, S.; Lucero, E.; Guzman, O.; Zamora, H.; Briceno de M, C.

    1989-01-01

    On the thirtieth anniversary celebration of the ''Instituto de Asuntos Nucleares'', a historical review of its activities has been made, emphasizing on its politics of development, technological and scientific advances, including the goals and accomplishments attained for the uses and applications of nuclear technology in Colombia. This includes the technical assistance which is being provided by International Organizations. National and international influences are shown for each one of the technical areas: agricultural applications, industrial applications and metallurgy, biochemistry and radiopharmacy, development process, nuclear electronics, solar and non-conventional energies, gamma facility, nuclear physics, hydrology, raw materials, chemistry, health radiophysics, reactor, nuclear documentation and information center and administration

  16. EL TRABAJO INVISIBLE DE MENORES DE BAZURTO. MERCADO CENTRAL DE CARTAGENA DE INDIAS

    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.

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

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

    2013-03-01

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

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

    Zafer, A.

    2006-01-01

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

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

    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

  20. Cuestiones centrales de la actual Filosofía de la imagen

    Roberto Rubio

    2017-12-01

    Full Text Available Desde hace algunas décadas, se desarrolla en el ámbito germano-parlante un proyecto interdisciplinario enfocado en las imágenes. Se trata de la Bildwissenschaft o Ciencia de la imagen. Ella pretende integrar en un marco común el aporte de diversas disciplinas, tales como la historia del arte, la teoría del arte, la filosofía y la psicología, entre otras. El aporte de la filosofía al programa de la Bildwissenschaft ha dado lugar a la así denominada “filosofía de la imagen”. Ella es especialmente sensible a los intentos de renovación paradigmática que afectan de modo más o menos directo a la cuestión de la imagen, tales como el “giro performativo”, el “giro icónico” o el “giro medial”. A continuación, expondré dos cuestiones centrales en la filosofía de la imagen. Presentaré, en primer lugar, la pregunta por el estatuto exhibitorio de las imágenes, y en segundo lugar, la pregunta acerca de la condición medial de las imágenes. Luego de la exposición, ofreceré un análisis crítico de los debates correspondientes a tales cuestiones.

  1. Leptoglossus lonchoides Allen (Heteroptera, Coreidae), causente de la caida de los frutos de Bactris gasipaes (Palmae) en la Amazonia central

    Couturier, Guy; Clement, C.R.; Viana Filho, P.

    1991-01-01

    #Leptoglossus lonchoïdes$ Allen (Heteroptera Coreidae) provoque la chute des fruits de #Bactris gasipaes$ HBK (Palmae) en Amazonie centrale. Les plantations de "pejibaye", #B.gasipaes$, un palmier neotropical domestiqué, souffrent d'importantes chutes de jeunes fruits en Amazonie centrale (Manaus, Amazonas, Brésil), dues en partie, peut-être principalement, à la punaise #L. lonchoïdes$. Dans cet article, on évalue l'importance économique des dégâts et on décrit l'insecte. (Résumé d'auteur)...

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

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

    2013-10-15

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

  3. Instituto de Asuntos Nucleares. Report of Activities 1989

    1989-01-01

    It is a summary of the technical activities carried out by the Instituto de Asuntos Nucleares, Bogota, Colombia, during 1989. It includes activities in topics as: research projects, transfer of technology, scientific information, qualification and training programs, mainly, which were done in areas like: agriculture, industrial applications, medicine, radiation protection, hydrology, nuclear technology development, radiochemistry and physics, among others

  4. Consejo de Seguridad Nuclear: the Spanish safety authority

    Gonzalez, E.

    1993-01-01

    The Spanish Authority in Nuclear Safety and Radiological Protection was created by special law in 1981. The Consejo de Seguridad Nuclear (CNS) was established independent of the Government and reporting direct to Congress. This five-member commission is responsible for assisting the Government and other institutions in safety matters, with the the authority to impose safety conditions on all activities related to radioactive materials, and particularly on the nuclear power plants. (author) 1 fig

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

    González Consuegra, Renata Virginia

    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 ...

  6. International nuclear data centers and the nuclear data center of Instituto de Estudos Avancados

    Corcuera, R.P.; Nair, R.P.K.; Santos, R. dos

    1985-01-01

    The nuclear data centers existent in the world and their areas, of responsability are presented. The efforts made by the Instituto de Estudos Avancados of Centro Tecnico Aeroespacial, in Brazil to create a local nuclear data center are presented. (M.C.K.) [pt

  7. Las flores del desierto. Opciones de vida en pueblos de la región central de Sonora

    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.

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

    Pande, Savita

    1998-01-01

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

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

    Payez Freire, Eva Cristina

    2015-01-01

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

  10. Availability analysis of the nuclear instrumentation of a research reactor; Analise da disponibilidade da instrumentacao nuclear de um reator de pesquisa

    Vianna Filho, Alfredo Marques

    2016-07-01

    The maintenance of systems and equipment is a central question related to Production Engineering. Although systems are not fully reliable, it is often necessary to minimize the failure occurrence likelihood. The failures occurrences can have disastrous consequences during a plane flight or operation of a nuclear power plant. The elaboration of a maintenance plan has as objective the prevention and recovery from system failures, increasing reliability and reducing the cost of unplanned shutdowns. It is also important to consider the issues related to organizations safety, especially those dealing with dangerous technologies. The objective of this thesis is to propose a method for maintenance analysis of a nuclear research reactor, using a socio-technical approach, and focused on existing conditions in Brazil. The research reactor studied belongs to the federal government and it is located in the city of Rio de Janeiro. The specific objective of this thesis is to develop the availability analysis of one of the principal systems of the research reactor, the nuclear instrumentation system. In this analysis, were taken into account not only the technical aspects of the modules related to nuclear instrumentation system, but also the human and organizational factors that could affect the availability of the nuclear instrumentation system. The results showed the influence of these factors on the availability of the nuclear instrumentation system. (author)

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

    Schmid, J.

    1991-04-01

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

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

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

    2010-11-15

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

  13. Validación del Cuestionario de Creencias Centrales de los Trastornos de la Personalidad (CCE-TP) en población colombiana

    Londoño A., Nora Helena; Maestre C., Katherine; Marín M., Carlos Alberto; Schnitter C., Mónica; Castrillón M., Diego; Ferrer B., Alberto; Chaves C., Liliana

    2007-01-01

    Se construyó un cuestionario para evaluar creencias centrales asociadas con los trastornos de la personalidad, fundamentadas en el Modelo de la Terapia Cognitiva. Se realizó el análisis estructural y la validez de contenido de la prueba en población universitaria de la ciudad de Medellín, Colombia. La muestra fue representativa y elegida al azar a través de un procedimiento polietápico. Un número de 809 estudiantes universitarios contestaron el cuestionario de creencias centrales de los trast...

  14. Validación del Cuestionario de Creencias Centrales de los Trastornos de la Personalidad (CCE-TP) en población colombiana

    Nora Helena Londoño A.; Katherine Maestre C.; Mónica Schnitter C.; Diego Castrillón M.; Alberto Ferrer B.; Liliana Chavez C.

    2010-01-01

    Se construyó un cuestionario para evaluar creencias centrales asociadas con los trastornos de la personalidad, fundamentadas en el Modelo de la Terapia Cognitiva. Se realizó el análisis estructural y la validez de contenido de la prueba en población universitaria de la ciudad de Medellín, Colombia. La muestra fue representativa y elegida al azar a través de un procedimiento polietápico. Un número de 809 estudiantes universitarios contestaron el cuestionario de creencias centrales de los trast...

  15. Clima Organizacional y el Desempeño Laboral de los trabajadores de la Gerencia Central de Logística de la Sede Central del Ministerio Público – 2014

    Arévalo Contreras, Niltón César; Arroyo Muñoz, Carol Liliana

    2016-01-01

    La presente investigación tuvo como objetivo general de determinar qué relación existe entre el Clima Organizacional y el Desempeño Laboral de los trabajadores de la Gerencia Central de Logística de la Sede Central del Ministerio Público – 2014, la población fue Constituida por 265 trabajadores del Ministerio Público, como muestra no probabilística por conveniencia se consideró a 114 trabajadores de la población, en los cuales se han empleado la variable: Clima Organizacional ...

  16. Desarrollo nuclear, condicionantes externos y acuerdos nucleares bilaterales: el caso de Argentina y Brasil

    Quintanar, Silvia; Romegialli, Mónica

    2007-01-01

    Argentina y Brasil han sido países pioneros dentro del escenario latinoamericano en la investigación y desarrollo de tecnología nuclear. En el período anterior al advenimiento de las democracias, ambos países sostuvieron posiciones convergentes frente a los acuerdos mundiales, al mismo tiempo que rivalizaban en sus respectivos desarrollos en materia nuclear. Argentina era el país que tenía la vanguardia en el programa desarrollo nuclear. Las democracias reencontradas en Brasil y Argenti...

  17. 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

    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

  18. 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

    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)

    1997-12-31

    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

  19. Calculo Preliminar de la Tasa de Meteorización del Batolito Antioqueño, Cordillera Central, Colombia

    Carolina Garcia; Michel Hermelin

    2004-01-01

    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 d...

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

    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)

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

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

    Sychou, A.

    1997-01-01

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

  3. Algunos aspectos relacionados con los riesgos en una central de esterilización

    Méndez Hernández, Mirla

    2004-01-01

    Se muestran los riesgos que están presente en una central de esterilización y su relación con la bioseguridad. Se identifican los diferentes tipos de riesgo y se hace una descripción de cada uno de ellos. Para obtener la información se utilizó la observación, como fuente primaria y los registros existentes como fuente secundaria. Los riesgos que se pueden presentar en una central de esterilización son de tipo biológico, físico, químico y los condicionados por factores humanos y ambientales. E...

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

    Ventura, M.

    2006-01-01

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

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

    Tomik, L.; Kichev, E.

    2003-01-01

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

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

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

    2002-07-01

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

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

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

    1999-01-01

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

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

    Hendricks, J.R.

    1996-01-01

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

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

    Rodriguez Luis Felipe

    1997-06-01

    Full Text Available

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

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

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

    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.

  11. Diseño del sistema de control y protección de una central hidráulica de 37 MVA

    Feliz Juárez, Javier Fernando

    2013-01-01

    El presente Proyecto Fin de Carrera tiene como objetivo el estudio, diseño y valoración técnica y económica del Sistema de Control y Protección de Grupo de una central hidroeléctrica de 37 MVA. Este Sistema está compuesto por el conjunto de equipos eléctricos, electrónicos y mecánicos encargados del control y protección de los dispositivos e instalaciones existentes en la central y necesarias para el correcto funcionamiento de la unidad Turbina- Generador de la misma. Se han...

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

    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.

  13. Memoir 1985. Instituto Nacional de Investigaciones Nucleares

    1985-01-01

    A brief review of the National Institute of Nuclear Research is given and its activities in 1985 summarized, among which were the Institute's fabrication of nuclear fuel rods, advisory and technical support of the national nucleoelectric program, encouragement of the utilization of nuclear techniques in farming, livestock breeding, industry and health, improving processes in radioisotope production, construction of a metrology building for ionizing radiation measurement, training of manpower for the nucleoelectric industry, for applying nuclear techniques, and the assemblying of a pelletron electron accelerator. (m.r.)

  14. Sede central de una compañía de seguros Oberursel/Ts. - Alemania Federal

    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. Analysis of occupational exposure at nuclear power plants in Western Europe from 1980-1988; Bilan et analyse de l'exposition professionnelle (exploitants et entreprises exterieures) dans les centrales nucleaires des pays de l'europe de l'ouest periode 1980-1988

    Seror, V; Lefaure, C; Benedittini, M

    1989-12-01

    The objective of this study is to establish for the first time the facts concerning professional exposure in nuclear power plants in different European countries. The professionals outside the power plants affected are taken into account as well. Three type of power plants are examined: PWRs, BWRs, and GCRs.

  16. 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

    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.

  17. 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

    Robles Pimentel, Edgar [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Garcia Hernandez, Javier [Comision Federal de Electricidad, Mexico, D. F. (Mexico)

    1998-12-31

    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.

  18. Protocol in NORM industries. Central thermal coal production; Protocolo de actuacion en industrial NORM. Centrales de produccion termica de carbon

    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)

  19. Diseño de una mini central de energía hidroeléctrica en la planta de tratamiento de aguas residuales de la ciudad de Cuenca

    Criollo Cabrera, Xavier Leonardo; Quezada Damián, Cristian Lautaro

    2011-01-01

    Esta tesis busca analizar la factibilidad de la utilización de mini centrales de generación hidroeléctrica, ya que en la actualidad necesitamos fomentar la utilización de energías renovables y limpias que protejan el medio ambiente y que no generen gases de efecto invernadero. En este trabajo planteamos la reutilización de la infraestructura de la planta de tratamiento de aguas residuales de la ciudad de Cuenca para la generación de energía eléctrica, analizando la infraestructura existent...

  20. Competencias informacionales de los estudiantes de la escuela de bibliotecología de la Universidad Central de Venezuela - Information skills of students the school of library science at library science at Universidad Central de Venezuela

    José Jesus López Salazar

    2016-12-01

    Full Text Available El presente trabajo examina las competencias informacionales de los estudiantes de la Escuela de Bibliotecología de la Universidad Central de Venezuela. Para ello se aplicó un cuestionario de 25 presuntas abiertas, cerradas y mixtas a 213 estudiantes cursantes de la asignatura obligatoria Seminario de tesis dictada durante los periodos lectivos 2014-2, 2015-1 y 2015-2 como parte de una evaluación diagnóstico que buscó establecer el conocimiento y las habilidades que deben poseer para iniciar una investigación bibliotecológica. Se utilizaron cuatro parámetros para medir el reconocimiento de la necesidad de conseguir información, localizar información y acceder a ella, establecer estrategias para localizar la información, distinguir entre distintas formas de cubrir la necesidad, comparar y evaluar la información, organizar, aplicar y comunicar la información. Las competencias informacionales de los estudiantes de la Escuela de Bibliotecología hacia la investigación puede ser valorada como moderada o mediana que requiere de estrategias de enseñanza aprendizaje para desarrollar aptitudes para localizar la información, comparar y evaluar la información, organizar, aplicar y comunicar la información de manera ética. Abstract This paper examines the information skills of Central University of Venezuela´s Library Sciences School students. For this reason, a questionnaire of 25 open and closed mixed questions was applied to 213 thesis seminars students during school periods 2014-2, 2015-1 and 2015-2 as part of a diagnostic evaluation that sought to establish the knowledge and skills that should be developed to initiate an investigation in the library science field. Four parameters were used to measure the recognition of the information needs, find the information and access to it, establish the strategies to locate information, distinguish between different ways of meeting the need, compare and evaluate information, organize

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

    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. El valor de la opinión en los noticieros televisivos chilenos de hoy el caso de 24 horas central de TVN

    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.

  3. Importancia, evolución y organización de un Servicio de Esterilización Central

    Rothamel, Alicia

    1986-01-01

    La Central de Esterilización Hospitalaria es el lugar donde se decontaminan, lavan, preparan, acondicionan y esterilizan los materiales de uso en el Hospital. La gran responsabilidad profesional y técnica que caracterizan su rol en el Hospital exigen que el Servicio esté estrictamente organizado, contando con una estructura física, equipamiento, plantel de personal y estructura técnico-administrativa conforme a las Normas de Esterilización en vigencia. La Central de Esterilización en un Hospi...

  4. The radiological safety in the use of nuclear technique -activities developed by Centro de Desenvolvimento da Tecnologia Nuclear - CNEN

    Wakabayashi, T.; Pereira, E.G.; Hirayama, T.

    1991-01-01

    The activities developed by the Centro de Desenvolvimento da Tecnologia Nuclear - CDTN supporting the users of nuclear techniques are described. The methodology used and future plans for the group are shown. (E.G.)

  5. EFECTO DEL USO DE ADITIVOS EN DIETAS DE CODORNICES REPRODUCTORES (Coturnix coturnix japonica) BAJO CONDICIONES DE VERANO EN LA COSTA CENTRAL

    Ciriaco Castañeda, Pedro; Facultad Zootecnia, Dpto. de Produccion Animal de la Universidad Nacional Agraria La Molina (Perú).; Roncal Ñañez, Henry David; Ing. Zootecnista (Perú).

    2016-01-01

    Se evaluaron los efectos de la adición en la dieta de 0.05% del Complejo B, 0.05% de Vitamina C, 0.2% de Bicarbonato de Sodio y 0.05% de Ácido Acetil Salicílico, sobre los parámetros productivos y reproductivos de codornices japonesas en época de verano en la costa central del Perú (Lima), con temperatura ambiental promedio de 25°C. Codornices reproductores (270 hembras y 90 machos) de 48 días de edad, fueron distribuidas en cinco tratamientos (4 con aditivos y una dieta control) con tres rep...

  6. Analgesia e sedacao durante a instalacao do cateter central de insercao periferica em neonatos

    Priscila Costa; Mariana Bueno; Cintia Luiza Oliva; Talita Elci de Castro; Patricia Ponce de Camargo; Amelia Fumiko Kimura

    2013-01-01

    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 25...

  7. Caracterización y propue stas de mejora de los sistemas de producción caprina de la costa central de Perú

    José A. Sarria

    2014-01-01

    Full Text Available Perú tiene un importante sector caprino con rebaños de aptitud cárnica o mixta. Sin embargo, en los valles de la costa central hay una mayor tendencia a la orientación lechera, alimentando a los animales en bas e a rastrojos agrícolas. El objetivo de este estudio fue caracterizar las explotaciones de esta zona, pa ra lo cual se entrevistaron 60 ganaderos y se analizaron 39 variables. Se realizó un análisis multivariante seguid o de un ANOVA entre los cuatro grupos resultantes del mismo; obteniéndose dos dimensiones que explican el 69 .9 % de la varianza. Ocho variables mostraron diferencias significativas: (i educación del ganadero, los niveles primario y secundario predominaron respectivamente en los Grupos 2 y 3, P <0.05; (ii superficie de explotación, menos de 0.50 ha a excepción del Grupo 1, P <0.05; (iii modo de propiedad de la tierra, la propiedad privada fue menor en el Grupo 1, P <0.01; (iv importancia de las cabras, la producción caprina es la principal actividad del ganadero en los Grupos 3 y 4, P <0.001; (v número de caprinos, 97 y 80 respectivamente en los Grupos 1 y 4 y menos en el resto; P <0.001; (vii número de bovinos, 18 y 16 respectivamente en los Grupos 1 y 2, y menos en el resto, P <0.001; y (viii suministro de alimentos en la granja, no existiendo éste en los Grupos 1 y 4, P <0.01. Para tener continuidad y mejora, estos sistemas de producción caprina deberían reorganizarse de forma global, incrementar el tamaño de las explotaciones y tratar de comercializar productos diferen ciados.

  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

    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

  9. ESTRATEGIAS DE MERCADOTECNIA DE LA EMPRESA FAMILIAR CAFÉ EL GOLFO, GUAYABO CENTRAL, SIUNA, 2013

    Isabel del Socorro Masis Suazo

    2016-05-01

    Full Text Available El estudio se realizó en la empresa Familiar Café El Golfo, ubicada en la comunidad Guayabo Central a 53 Kilómetros, sureste del Municipio de Siuna, Región Autónoma de la Costa Caribe Norte (RACCN. Se orientó al análisis de estrategias de mercadotecnia que utilizan, describe lo que implementa la microempresa, identificó las oportunidades de mercado en este negocio y propone acciones estratégicas con relación a los factores que influyen en este campo. Es de carácter descriptivo con un enfoque cualitativo. Las técnicas que se utilizaron fueron: la entrevista individual a propietarios de la microempresa, comerciantes y consumidores. La observación directa, se realizó en el área de producción y almacenamiento del producto. De acuerdo a la información que se obtuvo mediante la aplicación de los instrumentos en contraste con la teoría, se considera, que la microempresa Familiar Café El Golfo hace uso de estrategias de mercadotecnia, pero no en su totalidad. Las propiedades físicas de este producto, prometen excelente oportunidades de mercado; sin embargo, es necesario que la empresa complemente otras estrategias de mercadotecnia a las que implementan por el negocio. Con respecto a las acciones estratégicas propuestas, estas servirán como una herramienta para el aumento de las ventas en la comercialización de su producto. Summary The research was conducted in the family business “Cafe El Golfo”, located in the Guayabo Central community at 53 kilometers southeast of the municipality of Siuna, Autonomous Region of the North Caribbean Coast (RACCN. It was oriented to the analysis of the marketing strategies they employ; it also describes the actions implemented by the microenterprise, it identifies the market opportunities in this business and proposes strategic actions in relation to the factors influencing this field. The study is descriptive with a qualitative approach. The techniques that were used: individual interviews to

  10. Estudio y análisis de instalaciones de centrales termosolares con tecnología CCP

    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

  11. IMPLEMENTACION DE UNA CENTRAL DE COORDINACION COMO MEDIDA DE MEJORA AL SISTEMA DE ATENCION PRIMARIA DE SALUD

    BAZAN GANTZ, OSCAR ANDRES; BAZAN GANTZ, OSCAR ANDRES

    2012-01-01

    La salud pública chilena, es uno de los servicios públicos con mayor utilización, y a la vez, obtiene, por parte de los usuarios, los peores resultados en la medición de percepción de la calidad de la atención.(Subjetiva, 2010) La atención primaria de salud (APS) es la puerta de entrada al sistema, contando con una altísima cobertura (880 centros de atención primaria) y por tanto un gran número de pacientes atendidos (más de 32 millones de consultas médicas al año). Es el eslab...

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

    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.

  13. IPEN (Instituto de Pesquisas Energeticas e Nucleares) - annual report - 1997

    1998-01-01

    The annual activities report of 1997 of IPEN (Instituto de Pesquisas Energeticas e Nucleares) - Brazilian organization - introduces the next main topics: mission; permanent goals; year main achievements - health and bioengineering, industry and materials and environmental aspects, nuclear reactor technology and fuel cycle, radiation protection and nuclear assurance, human resources formation, infrastructure and support, administration innovation; more important projects summary developed in 1997; budgetary data summary; products and services commercialization; year evaluation of 1997; perspectives for 1998; projects and researches financed for resources captivated in fomentation agencies; and clients

  14. BENCHMARKING INTERNO EN UNA CENTRAL DE COMPRAS DE AGENCIAS DE VIAJES

    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.

  15. Central de diluição: uma proposta da comissão de controle de infecção hospitalar

    Vitor Hugo Della Valentina

    1984-03-01

    Full Text Available Relata-se a experiência na organização, implantação e avaliação de uma central de diluição de desindetantes a nível de um hospital geral com mais de seiscentos leitos. A viabilização desta central deve-se à designação de um enfermeiro , em jornada integral de trabalho, dedicado à Comissão de Controle de Infecção Hospitalar. No desenvolvimento do estudo discutem-se as vantagens desta central no que se refere aos pacientes; à equipe multiprofissional com ênfase nas equipes de enfermagem e de limpeza; à redução dos custos e à facilidade de divulgação de informações relativas ao emprego dos desinfetantes. Pelas vantagens abordadas no presente trabalho acredita-se que a inplantação de uma central de diluição deva constituir meta de toda instituição de saúde interessada em reduzir os riscos de exposição a infecções.

  16. Post-Construction Testing of the Elk River, Hallam and Piqua Power Reactor Plants; Essais apres construction des centrales nucleaires d'Elk River, de Hallam et de Piqua; Predehkspluatatsionnoe ispytanie Ehlk-riverskoj, Khehlpemskoj i Pikuaskoj ehnergeticheskikh reaktornykh ustanovok; Ensayos posteriores a la construccion de las centrales nucleoelectricas de Elk River, Hallam y Piqua

    Pursel, C. A. [United States Atomic Energy Commission, Argonne, IL (United States)

    1963-10-15

    numerous, observed or suspected, deficiencies or malfunctions of components which led to additional testing and analyses. In some instances, repair or modification of components was necessary to correct fabrication or engineering errors. Major problem areas are discussed: Elk River Reactor. Discovery of cracks in portions of the reactor vessel surface cladding led to extensive investigations and analyses and required some repairs and vessel modifications. Insufficient steam separation capacity required replacement and modification of some reactor vessel internal hardware. Hallam Nuclear Power Facility. Entrainment of the helium cover gas led to modifications of the secondary sodium loops. Failure of a tube in the intermediate (sodium to sodium) heat exchanger led to analyses to determine the cause of failure followed by removal and repair of the heat exchanger. Piqua Nuclear Power Facility. Chemical cleaning of the piping system damaged several valves which required mere repair or replacement. Leaks in the organic coolant and steam tracing systems caused repeated delays. After completion of the necessary repairs and modifications, the actual performance characteristics of each of the three reactors closely matched design predictions. (author) [French] Les resultats des essais apres construction de trois centrales nucleaires, dans le cadre du programme de demonstration des centrales nucleaires de la Commission de l'energie atomique des Etats-Unis (CEA-EU), permettront peut-etre de faire certaines generalisations concernant cette phase de la construction et de l'exploitation des centrales. Ces trois centrales, le reacteur de puissance d'Elk River (ERR), la centrale nucleaire de Hallam (HNPF), et la centrale nucleaire de Piqua (PNPF), appartiennent a trois filieres differentes: reacteur a eau bouillante a circulation naturelle, reacteur a graphite et a sodium et reacteur ralenti et refroidi par un fluide organique. La periode des essais apres construction a commence a la fin

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

    1977-08-01

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

  18. Aplicaciones industriales de la tecnología nuclear

    Vargas, Celso

    2013-01-01

    Las aplicaciones industriales de la tecnología nuclear son muydiversas a nivel mundial. En Costa Rica se ha comenzado a introducir este tipo de tecnología para evaluar y mejorar diferentes procesos industriales. Estas aplicaciones se clasifican en dos o en tres categorías, según el criterio utilizado. Están los sistemasde control nucleónico, el perfilaje gamma y los radiotrazadores.

  19. Charged particle radioisotope production at Instituto de Engenharia Nuclear - IEN

    Lemos Junior, O.F.

    1992-05-01

    A variable energy isochronous cyclotron (CV-28) was installed in 1974 at the Instituto de Engenharia Nuclear in Rio de Janeiro, with the purpose, among others, of irradiating suitable targets to produce radioisotopes for medical diagnostic studies. This papers is an overview of the work done in the last two decades and reports the present status on the production of iodine-123 and gallium-67. (author)

  20. Aquaculture investigations with nuclear energy techniques; Investigaciones acuicolas con tecnicas de energia nuclear

    Heredia Salazar, Brunilda [Fondo Nacional de Investigaciones Agropecuarias (FONAIAP), (CIAE), Estacion Experimental Guanapito, Guarico (Venezuela)

    1997-07-01

    The culture of aquatic organisms, especially that of fishes under controlled conditions, up to their harvesting, processing, commercialization and consumption, has been pointed out as an activity that produces a lot of benefits, among them: the obtention high proteic valued food, the incorporation to the economy of lands not usefull for agriculture activities, the increment of fishing resources, the recycling of organic matter produced in the units, the regional development, the generation of employment, technologies and foreign currencies. Several research areas are identified that can be developed, using the nuclear technologies, for example in the reproduction, nutrition, diagnose and control of illnesses, environmental monitoring and quality certification of products. In the concerning to the Venezuelan aquaculture, investigations are required that need to use those techniques. For example: 1) Production of autochthonous inductive agents, by means of radioinmunoenssay (RIA), to determine the gonadotropines coming from the hypophysis of fish cultivated with the purpose of gathering the glands in its best moment, to generate the final maturation and spawn in autochthonous species. 2) Genetic improvement of cultivated species through the knowledge of the genetic load of different lines and breeds found in the natural means, and to achieve its maintenance to solve inbreeding problems, in autochthonous species aswell in as in exotic ones, by the use of marking techniques (ADE, RFLA and microsatellite techniques). 3) Nutritional and feeding studies of species under commertial culture, especially on the effect of the aflatoxins in the inputs or the portions, substances that influence in a negative way the aquatic nutrition. In this case, competitive immunoassays of enzymes bounded (ELISA) and radioinmunoessays. 4) Illness diagnose, by means of the ELISA kit, specifically of the more common illness in fishes cultivated in the country. [Spanish] El cultivo de organismos

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

    Getzner, M.

    2003-01-01

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

  2. Microtuberización in vitro de siete accesiones de papa de la colección central colombiana

    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.

  3. Aplicaciones de los registros de resonancia magnética nuclear (nmrl) en la evaluación de yacimientos

    Landi Torres, Richard Paúl

    2008-01-01

    La extraordinaria tecnología de adquisición de registros o perfilaje de resonancia magnética nuclear (RMN) ha estado en continua evolución durante los últimos 10 años. Las compañías petroleras utilizan las mediciones de RMN en una variedad de aplicaciones cada vez más numerosa; por ejemplo, para caracterizar los fluidos de las formaciones durante la evolución de los yacimientos y determinar la producibilidad de la formación. Hoy en día, las mediciones obtenidas con estas herramien...

  4. Afrique occidentale et centraleDe nouveaux défis relevés avec ...

    25 janv. 2011 ... Ainsi, les éleveurs de l'Afrique occidentale et centrale doivent composer avec un certain nombre de changements écologiques et sociaux, tels que la vente de pâturages à des agriculteurs. La privatisation de superficies qui étaient jusque-là réservées à la vaine pâture occasionne souvent des problèmes ...

  5. Calculo Preliminar de la Tasa de Meteorización del Batolito Antioqueño, Cordillera Central, Colombia

    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.

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

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

    1997-12-31

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

  7. Base de datos compraventas de cafetales y haciendas de café realizadas en el Valle Central de Costa Rica (1834-1850.

    Iván Molina Jiménez

    2011-08-01

    Full Text Available propiedades cafetaleras, realizadas en el Valle Central de Costa Rica entre 1834 y 1850, quefueron localizadas en los Protocolos Coloniales. La información está agrupada en dosarchivos: en el primero, “Cafetales”, constan todas las transacciones de terrenos sembradosparcial o totalmente de café, y que carecían de construcciones (excepto alguna galera orancho; en el segundo, “Haciendas”, figuran las de aquellas fincas que, además del cultivo delllamado grano de oro, incluían edificaciones como patios para procesarlo en seco, casas,beneficios y otras por el estilo.

  8. Avances en el estudio de la Adenilato Quinasa Nuclear de Trypanosoma cruzi

    Cámara, María de los Milagros

    2012-01-01

    Trypanosoma cruzi, el agente etiológico del Mal de Chagas es un eucariota inferior en donde el control de la expresión génica recae mayormente en mecanismos postraduccionales. Durante todo su ciclo de vida se observan fluctuaciones en la expresión génica. En la presente tesis se realizó el estudio de una adenilato quinasa nuclear (TcADKn) que se encuentra involucrada en la biogénesis ribosomal. Las adenilato quinasas nucleares han sido descriptas en muy pocos organismos, se las ha asociado al...

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

    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

  10. Verification of practicability of quantitative reliability evaluation method (De-BDA) in nuclear power plants

    Takahashi, Kinshiro; Yukimachi, Takeo.

    1988-01-01

    A variety of methods have been applied to study of reliability analysis in which human factors are included in order to enhance the safety and availability of nuclear power plants. De-BDA (Detailed Block Diagram Analysis) is one of such mehtods developed with the objective of creating a more comprehensive and understandable tool for quantitative analysis of reliability associated with plant operations. The practicability of this method has been verified by applying it to reliability analysis of various phases of plant operation as well as evaluation of enhanced man-machine interface in the central control room. (author)

  11. MORFOMETRÍA COMPARADA DE SEMILLAS DE NICOTIANA (SOLANACEAE E IDENTIFICACIÓN DE SEMILLAS CARBONIZADAS PROVENIENTES DE UN SITIO ARQUEOLÓGICO EN CHILE CENTRAL

    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.

  12. (De)centralization of the global informational ecosystem

    Möller, Johanna; Rimscha, M. Bjørn von

    2017-01-01

    Centralization and decentralization are key concepts in debates that focus on the (anti)democratic character of digital societies. Centralization is understood as the control over communication and data flows, and decentralization as giving it (back) to users. Communication and media research focuses on centralization put forward by dominant digital media platforms, such as Facebook and Google, and governments. Decentralization is investigated regarding its potential in civil society, i.e., h...

  13. Nuevo puente para el oleoducto de Europa Central

    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.

  14. 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

    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

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

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

    2014-10-15

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

  16. Asie centrale | Page 86 | CRDI - Centre de recherches pour le ...

    C'est en Thaïlande que l'on observe la plus forte incidence de cholangiocarcinome, forme mortelle de cancer du foie notamment attribuable à une infection parasitaire par l'opisthorchiase (Opisthorchis viverrini). À certains endroits du nord-est de la Thaïlande, près de 85 % des habitants sont infectés par l'opisthorchiase.

  17. INVENTARIO DE MAMÍFEROS EN UN BOSQUE DE LOS ANDES CENTRALES DE COLOMBIA

    SÁNCHEZ FRANCISCO

    2004-06-01

    Full Text Available 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 trampas Tomahawk, puntos de observación, recorridos, trampasde huellas, rastros y encuestas. Se registraron 42 especies de mamíferospertenecientes a doce órdenes. El inventario de pequeños mamíferos no voladoresy murciélagos es incompleto; se dan sugerencias para complementarlo. Las trampasde huellas, los rastros y las encuestas fueron técnicas más eficientes para registrarmedianos y grandes mamíferos, que la captura con trampas Tomahawk, los recorridosy los puntos de observación. Se hacen observaciones y se dan recomendacionespara implementar las diferentes técnicas en bosques andinos.

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

    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

  19. Fabric of topsoil horizons in aridic soils of Central Asia Fábrica de horizontes superficiales en suelos áridos de Asia Central Tessitura dos horizontes superficiais de solos Arídicos da Ásia Central

    Marina Lebedeva

    2013-11-01

    Full Text Available Two surface microhorizons – vesicular and platy – were found to be typical of the fabric of topsoil horizons in gravely loamy soils located along an arid/continental climatic gradient in the Subboreal zone of Central Asia (from southern Russia to Uzbekistan, Kazakhstan, and Mongolia. Their genesis is related to active vesiculation (for vesicular ?1 microhorizon and cryogenesis (for platy ?2 microhorizon against a background of high clay mobility and/or eolian accumulation of fine material. New mechanisms responsible for the formation of vesicular pores are suggested: (a the leaching of dense complete crystal infillings (moldic voids and (b the development of biogenic capsules typical of iron bacteria that were diagnosed by the microbiological method of fouling Agar-covered glasses under natural conditions. In a series of studied soils, Yermic Regosols are characterized by additional specific microfeatures: (1 iron depletion from the material around the pores and formation of iron concentrations in the intrapedal mass owing to biogenic mobilization of iron with participation of sulfate- and iron-reducing bacteria and (2 the accumulation of organic matter (residues of microbial cells in the vesicular pores.En este trabajo se estudiaron dos microhorizontes superficiales- vesicular y laminar- cuya fábrica se encuentra típicamente en horizontes superficiales de suelos franco gravosos situados a lo largo del gradiente climático árido/continental de la zona Subboreal de Asia Central (desde el sur de Rusia hacia Uzbekistán, Kazakhstán y Mongolia. Su génesis se relaciona con una activa formación de vesículas (para el microhorizonte A1 vesicular y con criogénesis (para el microhorizonte A2 laminar en un medio con elevada movilidad de arcilla y/o acumulación de material fino. Se proponen los siguientes nuevos mecanismos responsables de la formación de los poros vesiculares: a el lavado de rellenos cristalinos densos (poros móldicos; y b el

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

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

    2010-07-15

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

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

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

    2010-01-01

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

  2. Asie centrale | Page 35 | CRDI - Centre de recherches pour le ...

    Langue English. Read more about Soutien aux processus d'élaboration des politiques de réglementation des biotechnologies en Asie du Sud-Est. Langue French. Read more about Innovation en matière de biocarburants sous le signe de l'inclusion en Indonésie. Langue French. Read more about Toward Inclusive Biofuel ...

  3. Policia Preventiva en la Región Central de México y el Modelo Gaditano de Seguridad Interior

    Yañez, Arturo

    2003-01-01

    El argumento central de Arturo Yáñez es que "la policía preventiva no es, jurídicamente, una fuerza pública" debido a que constitucionalmente, funciones de seguridad interior son adjudicadas a la Guardia Nacional (5). Yáñez sostiene que una de las principales causas de esta ambigüedad es la influencia del modelo de seguridad interior previsto en la Constitución de Cadiz (1812) sobre la Constitución Federal mexicana. La confusión conceptual en torno a la función judicial ha provocado que la po...

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

    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)

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

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

    2009-07-01

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

  6. Conhecimento de enfermeiros de Neonatologia acerca do Cateter Venoso Central de Inserção Periférica

    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.

  7. Activities report of Instituto de Pesquisas Energeticas e Nucleares -IPEN - 1993; Relatorio anual de atividades 1993

    NONE

    1994-08-01

    This is an activity report of 1993 year from Instituto de Pesquisas Energeticas Nucleares - IPEN, one brazilian organization that form personnel actuate in radioprotection at the man and environment. Their works in social and environmental applications of nuclear energy, developing of reactors, alternative technologies to energy generation, advanced technologies and infra-structure activities are presented. (C.M.).

  8. Tipos de vegetación del llano de Paletará. Cordillera Central Colombia Tipos de vegetación del llano de Paletará. Cordillera Central Colombia

    Restrepo Carla

    1992-09-01

    Full Text Available We studied the vegetation found in the Llano de Paletará, municipality of Coconuco, department of Cauca, Colombia. Based on the physiognomy and floristic composition of the vegetation we identified 8 paramo vegetation types. These units represent the most extensive azonal paramo vegetation types described up to now for the Cordillera Central. Four of the 8 vegetation types are herbaceous ("frailejonal-pajonal" with Espeletia, "chuscal abierto" with Chusquea,"swamp" with Carex, and "grassland" with Calamagrostis , three are bush tickets (thicket with Hypericum, thicket with Ageratina, and thicket with Diplostephium, and one is a forest of low stature (forest with Escallonia. We analyze some aspects of the ecology and distribution of the vegetation types and evaluate their degree of peril and value of conservation. Se estudiaron los tipos de vegetación del Llano de Paletará, municipio de Coconuco, departamento del Cauca, Colombia. Basados en la fisonomía y composición florística de la vegetación identificamos 8 tipos de vegetación, los cuales representan los tipos de vegetación paramunos de carácter azonal más extensos de la Cordillera Central registrados hasta el momento. De los 8 tipos de vegetación, cuatro son de porte herbáceo (''frailejonalpajonal'' con Espeletia. "chuscal abierto" con Chusquea. "pantano" con Carex y un "pajonal" con Calamagrostis, tres son de porte arbustivo (matorral con Hypericum, matorral con Ageratina y matorral con Diplostephium y uno es de porte arbóreo (bosque con Escallonia. Se analizan algunos aspectos de la ecología y distribución de los tipos de vegetación y se evalúa su grado de amenaza y valor de conservación.

  9. EFECTO ANTIOXIDANTE DE FRUTAS Y HORTALIZAS DE LA ZONA CENTRAL DE CHILE

    Palomo G, Iván; Gutiérrez C, Margarita; Astudillo S, Luis; Rivera S, Carolina; Torres U, Constanza; Guzmán J, Luis; Moore-Carrasco, Rodrigo; Carrasco S, Gilda; Alarcón L, Marcelo

    2009-01-01

    Las especies reactivas del oxígeno (ERO) causan daño celular que se puede expresar como patología, tales como las enfermedades cardiovasculares (ECV) y otras enfermedades crónicas no transmisibles. El organismo humano cuenta con sistemas antioxidantes; algunos provienen de la dieta, especialmente de frutas y hortalizas, otros los genera el mismo organismo de manera endógena. El objetivo de este estudio fue conocer la capacidad antioxidante in vitro de algunas frutas y hortalizas que se consum...

  10. Evaluación de la seguridad alimentaria sostenible en el Magreb Central con indicadores agregados

    José Soler

    2013-01-01

    Full Text Available Se ha desarrollado un indicador agregado mediante la técnica de análisis de componentes principales, que incluye 21 indicadores individuales para 60 países. Los países del Magreb Central no muestran una seguridad alimentaria sostenible de acuerdo a las variables estudiadas y dentro del conjunto de países incluidos en este trabajo. Aunque la producción de alimentos es relativamente sostenible desde el punto de vista ambiental, no lo es en las dimensiones humana y productiva, ya que los cereales se presentan como el mayor aporte energético en la dieta, si bien, por un lado, no cubren los requerimientos óptimos y, por otro, la productividad de su cultivo en el Magreb Central es deficiente, debiéndose cubrir con importaciones externas.

  11. 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

    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

  12. 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

    Saldana, R; Morales, F; Urrutia, M [eds.; Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1997-12-31

    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

  13. Optimizing the distribution of centralizers; Otimizacao da distribuicao de centralizadores

    Fonseca, Carlos Fernando H; Salies, Jacques Braile [PETROBRAS, XX (Brazil). Dept. de Perfuracao. Div. de Revestimento de Cimentacao

    1990-12-31

    There are two procedures for the distribution of centralizers on casing: rules of thumb for vertical wells and the well-know theoretical model developed in API SPEC 10D. This paper presents a new approach for the disposition of centralizers. Casing deflection is modeled more realistically than in the API algorithm, using better boundary conditions. A computer application was developed to integrate information on hole trajectory, casing properties and the performance of centralizers, in order to optimize centralizer spacing. The paper also presents a few comparative examples, and the results obtained are less conservative than those of the API model, thus reducing the number of centralizers to be run in a particular well. (author) 6 refs., 7 figs., 3 tabs.

  14. Optimizing the distribution of centralizers; Otimizacao da distribuicao de centralizadores

    Fonseca, Carlos Fernando H.; Salies, Jacques Braile [PETROBRAS, XX (Brazil). Dept. de Perfuracao. Div. de Revestimento de Cimentacao

    1989-12-31

    There are two procedures for the distribution of centralizers on casing: rules of thumb for vertical wells and the well-know theoretical model developed in API SPEC 10D. This paper presents a new approach for the disposition of centralizers. Casing deflection is modeled more realistically than in the API algorithm, using better boundary conditions. A computer application was developed to integrate information on hole trajectory, casing properties and the performance of centralizers, in order to optimize centralizer spacing. The paper also presents a few comparative examples, and the results obtained are less conservative than those of the API model, thus reducing the number of centralizers to be run in a particular well. (author) 6 refs., 7 figs., 3 tabs.

  15. Neurocitoma central com apresentação incomum por hemorragia intraventricular: relato de caso

    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.

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

    Ossa Vásquez, Karla Andrea

    2008-01-01

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

  17. Integration of the nuclear energy among the production facilities of energy in France; Integration de l'energie nucleaire parmi les moyens de production de l'energie en france

    Ailleret, P [Electricite de France (EDF), 75 - Paris (France). Direction des Etudes et Recherches; Taranger, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The present report gives an overview of the present facilities of energy productions in France and their perspectives. the electric production comes for half about power stations hydraulics and for half of thermal power stations. However due to the increase of the energy consumption, France is particularly interested by the atomic energy that appears to bring a supply in due time to the hydraulics and to limit a development of the thermal power stations to which the natural resources of France in classic fuel would not permit to cope presumably. The integration of the nuclear plants to the other production facilities will make itself gradually according to the evolution of the energy needs. (M.B.) [French] Le present rapport donne un apercu des moyens actuels de productions energetiques en France et de ses perspectives. la production electrique provient pour moitie environ de centrales hydraulique et pour moitie de centrales thermiques. Cependant face a l'augmentation de la consommation energetique, la France est tres particulierement interessee par l'energie atomique qui parait devoir apporter en temps utile la releve a l'hydraulique et limiter un developpement des centrales thermiques auxquels les ressources naturelles de la France en combustible classique ne permettraient vraisemblablement pas de faire face. L'integration des centrales nucleaires aux autres moyens de production se fera graduellment en fonction de l'evolution des besoins energetiques. (M.B.)

  18. Estado del Arte: El Banco Central de Estados Unidos a sus 100 años

    Jane D'Arista

    2013-09-01

    Full Text Available La creencia en la hipótesis de los mercados eficientes y la adopción de requerimientos de capital para los bancos como la mejor herramienta macroprudencial compatible con las fuerzas del mercado, reemplazó el compromiso previo de la Reserva Federal (Fed de emplear la conexión entre las operaciones de mercado abierto y los cambios en los requerimientos de reservas para limitar el crédito. Desde que se cortó esta palanca sobre la oferta crediticia, el banco central ha dependido de las operaciones de mercado abierto para lograr solamente un objetivo: influir sobre la demanda de crédito cambiando la tasa de referencia de corto plazo. La desequilibrada caja de herramientas contribuyó a un sesgo procíclico en los resultados de sus políticas que reflejó y exacerbó el sesgo procíclico del sistema financiero. El fracaso de evaluar y fortalecer sus herramientas monetarias ha socavado la habilidad de la Fed para restaurar el crecimiento económico y evitar otra crisis financiera. La traducción del inglés al español es de Wesley Marshall y Eugenia Correa.

  19. Esquistossomose do sistema nervoso central relato de um caso

    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.

  20. Professional practices: a short introduction of national nuclear activities to university students; Practicas profesionales: breve incursion laboral de alumnos universitarios en las actividades nucleares

    Martin, Hugo R [Comision Nacional de Energia Atomica, Cordoba(Argentina). Regional Centro

    2005-07-01

    This paper is a continuation of precedents annual works presented in AATN Meetings, informing about activities of Institutional Affairs Sector of Central Region delegation of National Atomic Energy Commission (CNEA-RC). Regular activities in Cordoba city, have been carried out during half a century in urban zone of Cordoba City. Activities show a long misunderstanding and confrontations with the provincial and municipal authorities, and with the neighbors and environmentalist antinuclear organizations. The experience indicates that the people demands for the protection of health or environment, and sometimes the claiming for closing some facilities, have been directly related with what people really know about the activities in the site. The common denominator that one observes in the conflicts of the past, is the high degree of ignorance on the part of the citizenship on the activities that are carried out in the place. This is valid for the neighbors, the competent authorities and even for Cordoba's university, scientific and technical qualified community. Starting from the recognition of the responsibility that has the institution of informing the population appropriately on what is carried out in their facilities, the CNEA-RC had developed an institutional process of Professional Practices of university students which is described in this paper. The experience of two years, has shown that results are positive because the university community (teachers, students and researchers) knows now the real status of national nuclear activities. (author) [Spanish] Este trabajo pretende dar continuidad a la informacion que anualmente, a traves de las reuniones de la AATN, se brinda desde la Subgerencia de Asuntos Institucionales de la CNEA, sobre los resultados obtenidos en las actividades que se realizan en Cordoba. Como se ha informado antes, debido al emplazamiento urbano de la Regional Centro de CNEA (CNEA-RC) en un predio compartido con la empresa Dioxitek S.A. que

  1. Parasitosis y Micosis del Sistema Central como Causa de Epilepsia en Adultos

    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...

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

    Cabrera Rioja, Luis Alberto

    2007-01-01

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

  3. Logistica de coleta e transporte de material biologico e organizacao do laboratorio central no ELSA-Brasil

    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.

  4. Las redes de drenaje de los rios Alberche y Guadarrama como indicadores estructurales del Sistema Central Espanol

    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.

  5. Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

    Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    nucleoelectrica de Humboldt Bay (Pacific Gas and Electric Company, Eureka, California), la central nucleoelectrica de Garigliano (Societa Elettronucleare Nazionale, Scauri, Italia), y el reactor de potencia japones para fines de demostracion (Instituto de Investigaciones Nucleares, Tokai Mura, Japon). La puesta en marcha y el funcionamiento inicial de estas centrales confirma las esperanzas despertadas por las centrales de Dresden, Kahl y Vallecitos. Los registros de rendimiento de las centrales de Dresden, Kahl y Vallecitos han puesto claramente de manifiesto la estabilidad y seguridad de los reactores de agua hirviente. Ademas, los niveles de radiacion dentro de la central y en sus alrededores se han mantenido muy por debajo de los limites fijados en los permisos de explotacion. Ha quedado confirmada la sencillez y facilidad de explotacion de los reactores de agua hirviente. La rapidez de la respuesta del reactor con doble ciclo de Dresden a las fluctuaciones de la demanda es excelente. Ninguno de los trabajos de conservacion y reparacion, sea cual fuere su importancia, exige calificaciones especiales ni entrana riesgos de irradiacion excesivos. La inspeccion general y la revision de la turbina de la central de Dresden puso de manifiesto la inexistencia de problemas de conservacion despues de mas de 12 000 h de funcionamiento con el vapor en ciclo directo, a pesar de que la explotacion prosiguio despues de haberse comDtobado algunas fallas en los elementos combustibles. (author) [Russian] K nastoyashchemu vremeni priobreten znachitel'nyj opyt v ehkspluatatsii ehlektrostantsij s kipyashchim reaktorom. K kontsu 1962 goda proizvedeno svyshe 2200 mln.kvt.ch ehlektroehnergii na trekh ehlektrostantsiyakh ehnergosistemy kommunal'nogo obsluzhivaniyagna Drezdenskoj atomnoj ehlektrostantsii, ''Kommonvels Ehdison kompani'', Morris, Illinojs, na atomnoj ehlektrostantsii Valleeitos,''Pasifik gaz ehnd ehlektrik kompani'', Plezanton, Kaliforniya, i na Kal'skoj atomnoj ehlektrostantsii

  6. La enfermedad de Chagas en la zona central de Honduras: conocimientos, creencias y prácticas

    Gustavo Ávila Montes

    1998-03-01

    Full Text Available En el período de noviembre a diciembre de 1991 y en marzo de 1993 se realizó una encuesta en 17 comunidades rurales de la parte central de Honduras. Las comunidades correspondían a dos zonas en las que la enfermedad de Chagas es endémica. En una de las zonas habían tenido lugar actividades de control de la enfermedad. Fueron entrevistados 849 adultos, uno en cada uno de otros tantos hogares familiares. El objetivo de la encuesta fue investigar y comparar en ambas zonas los conocimientos sobre la enfermedad de Chagas y sus mecanismos de transmisión, las prácticas para evitar la presencia de triatómidos en las viviendas, las creencias acerca de los triatómidos y su control, y las fuentes a partir de las cuales la población obtiene información sobre la enfermedad. Se utilizó un cuestionario de 23 preguntas validado y precodificado. Casi 100% de los entrevistados pudieron reconocer el vector y conocían sus hábitos, pero solo 30,1% sabían que el Triatoma es vector transmisor de la enfermedad y apenas 6% pudieron mencionar su relación con una afección cardíaca crónica. El 47,9% de los entrevistados indicó que la responsabilidad de eliminar los triatómidos de la vivienda es personal, aunque 78% consideraron como medida de control la aplicación institucional de insecticidas. El contacto personal entre el funcionario institucional y los miembros de la comunidad fue la principal fuente de información entre los que mencionaron haber oído de la enfermedad de Chagas (41,0%. Los resultados sugieren que al planificar medidas de control se debe incluir el componente de educación sanitaria. Ha de ponerse énfasis en el papel que desempeñan los triatómidos en la transmisión, así como en la importancia de mejorar la vivienda como medida eficaz y sostenible mediante la participación de la comunidad. Este componente deberá ser desarrollado por canales de comunicación interpersonales para obtener un mayor impacto.

  7. Diversidad y aspectos biológicos de abejas silvestres de un ambiente urbano y otro natural de la región central de Santa Fe, Argentina

    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.

  8. Síntesis de zeolitas a partir de cenizas volantes de centrales termoeléctricas de carbón

    Umaña Peña, Juan Carlos

    2002-01-01

    Los sub-productos de combustión del carbón producidos en centrales térmicas, están compuestos generalmente por más de un 70% de material vítreo aluminosilicatado. Esta composición los hace potencialmente utilizables en obras de ingeniería civil o alternativamente como rellenos inertes en minería, así como adsorbentes, inmovilizadores, fuente alternativa en la extracción de Al, Fe, Si, Ge, Ga, V y Ni, y aditivos en suelos.Las cenizas volantes se caracterizan por una distribución granulométrica...

  9. El tarwi o chocho: una de las principales fuentes de proteína vegetal de las comunidades indígenas de los Andes Centrales

    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...

  10. Asie centrale | Page 12 | CRDI - Centre de recherches pour le ...

    8 · 9 · 10 · 11; 12; 13 · 14 · 15 · 16 … suivant › · dernier » · Ce que nous faisons · Financement · Ressources · À propos du CRDI. Savoir. Innovation. Solutions. Carrières · Communiquez avec nous · Plan du site · Droits d'auteur · Éthique de la recherche · Politique de libre accès · Politique de confidentialité · Transparence ...

  11. Asie centrale | Page 73 | CRDI - Centre de recherches pour le ...

    69 · 70 · 71 · 72; 73; 74 · 75 · 76 · 77 … suivant › · dernier » · Ce que nous faisons · Financement · Ressources · À propos du CRDI. Savoir. Innovation. Solutions. Carrières · Communiquez avec nous · Plan du site · Droits d'auteur · Éthique de la recherche · Politique de libre accès · Politique de confidentialité · Transparence ...

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

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

    2010-07-15

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

  13. El contrato de franquicia en el comercio internacional (Tema Central)

    Castellanos Peñafiel, Lorena del Carmen

    2006-01-01

    El artículo destaca el rol trascendente que desempeña el contrato de franquicia en el mundo globalizado de hoy y su proyección jurídica en el comercio internacional. A tal efecto, parte del estudio de temas generales, tales como su origen, concepto, características, elementos y clasificación, para luego examinar, a profundidad, los rasgos que determinan su naturaleza jurídica, su aproximación a otros tipos contractuales y el régimen conflictual aplicable, analiza, así mismo, la incidencia de ...

  14. ÁREA IRRIGADA POR PIVÔ CENTRAL NO MUNICÍPIO DE PINHEIROS, ES

    Rebyson Bissaco Guidinelle

    2017-05-01

    Full Text Available Resumo: Este trabalho teve como objetivo realizar o levantamento da área irrigada com pivô central no município de Pinheiros, Espírito Santo, Brasil. O levantamento da área irrigada por pivô central foi realizado mediante o uso do programa Google EarthTM Pro. Foi feito a sobreposição do arquivo vetorial do município de Pinheiros sobre a imagem de satélite disponível no programa computacional. Em seguida realizou-se a fotointerpretação de todas as áreas irrigadas com pivô central. A escala utilizada foi de 1:1.000. Foram levantados o raio (m, o perímetro (m e a área de cada alvo fotointerpretado. Chegando à uma conclusão que o município de Pinhiros possui 116 áreas irrigadas por pivô central, totalizando uma área de 5624,40 ha.

  15. Lutte contre la maladie de Chagas en Amérique centrale | CRDI ...

    Guatemala,. En Amérique centrale, les insectes qui transmettent la maladie de Chagas sont nombreux. Les équipes de chercheurs mettent la démarche écosanté à l'épreuve dans 15 emplacements différents se trouvant dans les ...

  16. Dolor musculoesquelético en trabajadores de América Central: resultados de la I encuesta Centroamericana de condiciones de trabajo y salud

    Marianela Rojas

    2015-08-01

    Full Text Available OBJETIVO: Examinar la prevalencia de dolor musculoesquelético (DME en los seis países de habla hispana de América Central con un instrumento único, la I Encuesta Centroamericana de Condiciones de Trabajo y Salud, en trabajadores de todos los sectores, manuales y no manuales, y con cobertura o no de la seguridad social como un indicador de formalidad o informalidad. MÉTODOS: Trabajadores encuestados en sus domicilios (n = 12 024. Se calculó la prevalencia ajustada por edad en el último mes de DME en la espalda (alta o cervical, media o dorsal y baja o lumbar o en las articulaciones de los miembros superiores (hombro, codo y muñeca. La prevalencia fue estimada por sexo, ocupación (manual o no, sector económico (agrícola, industrial y servicios y cobertura de la seguridad social. Se utilizaron modelos de regresión Poisson para calcular las razones de prevalencia e intervalos de confianza de 95%, con estratificación por país y localización anatómica. RESULTADOS: Por localizaciones, la prevalencia ajustada por edad de DME cervical-dorsal es la más elevada, en especial en El Salvador (47,8% y Nicaragua (45,9%, y la de DME lumbar la menos frecuente, sobre todo en Panamá (12,8% y Guatemala (14,8%. Tras ajustes adicionales, la prevalencia de DME fue mayor en mujeres y los trabajadores manuales en todas las localizaciones y países. No hubo diferencias de DME respecto a la cobertura de la seguridad social y el sector de actividad económica. CONCLUSIONES: La elevada prevalencia de DME en América Central, independiente del sector de actividad y cobertura o no de la seguridad social, indica que la prevención de los DME debe constituir también una prioridad en salud laboral en países de bajos y medianos ingresos, en especial en mujeres y trabajadores manuales.

  17. Analgesia e sedacao durante a instalacao do cateter central de insercao periferica em neonatos

    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.

  18. Microdureza del esmalte dental en incisivos centrales permanentes de dos genotipos bovinos

    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.

  19. 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?

    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

  20. Nuevas regularidades estructurales de la Cuenca Central (Cuba a partir de la interpretación cualitativa de datos gravimétricos

    Jesús A. Blanco-Moreno

    2007-03-01

    Full Text Available La Cuenca Central es uno de los lugares de mayor interés geológico y económico de la isla por sus importantes yacimientos de petróleo. Durante la exploración se realizaron levantamientos gravimétricos 1:100 000 cuyos datos se interpretaron cualitativamente teniendo en cuenta resultados de otras áreas. Inicialmente se realizaron transformaciones del campo gravimétrico (Continuación Ascendente y cálculos de gradientes horizontales y se representaron en mapas de isolineas y de relieve sombreado. Se establecieron nuevas regularidades estructurales de la cuenca que evidencian el marcado control tectónico de la región. La mayoría de los sistemas de fallas conocidos se relacionan con alineaciones del campo gravimétrico, de igual manera existen zonas alineadas, principalmente de direcciones noroeste-sureste y noreste-suroeste, que no se asocian a estos sistemas, y que pueden constituir zonas de fallas no reportadas. La presencia de grandes zonas anómalas positivas debajo de las secuencias cuaternarias indica la existencia en profundidad de secuencias vulcanógenas-sedimentarias o vulcanógenas depositadas durante la actividad volcánica cretácica. Se define una zona de altos gradientes con dirección noreste-suroeste que sugiere el límite entre las secuencias plegadas y sobrecorridas del paleomargen pasivo y el hemigraben de la Cuenca Central. Las rocas de bajas densidades alcanzan grandes profundidades hacia el extremo noroccidental y central de la región, mientras que al occidente alcanzan grandes profundidades las de altas densidades. Los elementos antes señalados permitirán una mejor planificación de investigaciones geológicas en la región.

  1. Limitación de la conservación de variedades nativas por variedades mejoradas: Estudio de caso de la papa en los Andes centrales del Ecuador

    MSc. María Cecilia Dávila

    2018-04-01

    Full Text Available La conservación de la biodiversidad para la alimentación y la agricultura, es una actividad importante a nivel mundial para asegurar la seguridad alimentaria y nutricional, pero dicha actividad está siendo limitada por varios factores. Este estudio de caso analiza cómo la adopción de variedades mejoradas de papa limita la conservación de la diversidad de las variedades nativas a nivel de granja o chakra en seis comunidades indígenas en los Andes centrales ecuatorianos. Los resultados muestran que la adopción de variedades mejoradas ha desplazado una amplia gama de variedades locales tradicionales de los campos de agricultores que, junto con las condiciones socioeconómicas y ambientales que caracterizaron el sitio de estudio, han socavado la diversidad genética de variedades cultivadas de papa en las fincas. Palabras clave: Conservación en finca, diversidad de papa, variedades mejoradas, variedades nativas.

  2. El tarwi o chocho: una de las principales fuentes de proteína vegetal de las comunidades indígenas de los Andes Centrales

    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.

  3. Sede central de LENOX, New Jersey - EE. UU.

    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.

  4. Extensiones centrales universales de álgebras Hom-Leibniz

    Pacheco Rego, Natália Maria de Bessa

    2014-01-01

    Las álgebras Hom-Leibniz son espacios vectoriales V dotados de un producto corchete [-,-] : V × V → V y de una aplicación α : V --> V satisfaciendo la denominada identidad Hom-Leibniz: [α (x),[y,z

  5. História natural de Tropidurus oreadicus em uma área de cerrado rupestre do Brasil Central

    Meira,Klarissa Teixeira Rocha; Faria,Renato Gomes; Silva,Maria das Dores Mendes; Miranda,Viviane Teixeira de; Zahn-Silva,Welington

    2007-01-01

    Aspectos ecológicos e da biologia reprodutiva de Tropidurus oreadicus foram investigados em uma área de cerrado rupestre do Brasil Central. Foram estudados a morfometria, o uso do microhábitat, o padrão de atividade, a dieta e características da biologia reprodutiva de T. oreadicus em Cocalzinho - GO, de abril a setembro/2003. São animais sexualmente dimórficos, com os machos adultos maiores que as fêmeas. O microhábitat preferencial utilizado pela espécie foi a superfície das rochas (hábito ...

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

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

    2014-10-15

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

  7. História da terra e do homem no Planalto Central, de Paulo Bertran

    Kelerson Semerene Costa

    2012-07-01

    Full Text Available História da terra e do homem no Planalto Central: eco-história do Distrito Federal, de Paulo Bertran. Brasília, Editora da Universidade de Brasília, 3a. edição, 2011. 615 p. Coleção UnB nos 50 anos de Brasília. R$ 65,00 Ilustrado, Índice remissivo, ISBN 978-85-230-1281-6

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

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

    1998-12-31

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

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

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

    1999-12-31

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

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

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

    2006-02-15

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

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

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

    2006-02-01

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

  12. Nuevas regularidades estructurales de la Cuenca Central (Cuba) a partir de la interpretación cualitativa de datos gravimétricos

    Jesús A. Blanco-Moreno; José A. Batista-Rodríguez; Aliuska Peña-Reyna

    2007-01-01

    La Cuenca Central es uno de los lugares de mayor interés geológico y económico de la isla por sus importantes yacimientos de petróleo. Durante la exploración se realizaron levantamientos gravimétricos 1:100 000 cuyos datos se interpretaron cualitativamente teniendo en cuenta resultados de otras áreas. Inicialmente se realizaron transformaciones del campo gravimétrico (Continuación Ascendente y cálculos de gradientes horizontales) y se representaron en mapas de isolineas y de relieve sombreado...

  13. Nuclear study of Melusine; Etude nucleaire de Melusine

    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)

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

    Nakayama, Naoki

    1998-01-01

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

  15. El Central Colombia: inicios de industrialización en el Caribe colombiano

    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.

  16. Efetividade do treinamento auditivo na plasticidade do sistema auditivo central: relato de caso

    Tatiana Rocha Silva

    2014-08-01

    Full Text Available O objetivo do estudo foi descrever, por meio de relato de caso, a efetividade do treinamento auditivo na modificação do sistema auditivo central de uma criança com queixas de alteração de fala e linguagem. Trata-se de um estudo retrospectivo, por meio de relato de caso, de uma criança do gênero masculino de 02 anos e 06 meses com queixas de alteração de fala e/ou linguagem. Na avaliação de potencial evocado auditivo de tronco encefálico observou-se presença de ondas eletrofisiológicas I, III e V com latência absoluta e intervalos interpicos dentro da normalidade na orelha direita e presença de ondas I, III e V com latência absoluta da onda V elevada e intervalos interpicos III-V e I-V elevados na orelha esquerda. O limiar eletrofisiológico foi de 70dBNA à direita e 40dBNA à esquerda. Após a avaliação a criança foi encaminhada para terapia fonoaudiológica baseada no treinamento auditivo informal. Para monitorar a função auditiva, após 06 meses de terapia fonoaudiológica, a criança foi encaminhada para reavaliação auditiva. Na reavaliação auditiva os resultados foram presença de ondas eletrofisiológicas I, III e V com latência absoluta e intervalos interpicos dentro da normalidade em ambas as orelhas com limiares eletrofisiológicos de 20dBNA bilateral. O programa de treinamento auditivo foi eficaz na reabilitação das habilidades auditivas.

  17. 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

    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.

  18. Análisis del estado estructural y administrativo de los campos de juego de los distritos urbanos de Ulloa, San Francisco, Heredia Centro y Mercedes del Cantón Central de la provincia de Heredia

    María Morera Castro

    2010-01-01

    Full Text Available El propósito de esta investigación fue analizar los factores que influirían en el estado estructural y administrativo de los campos de juegos en cuatro distritos urbanos del Cantón Central de la provincia de Heredia. En esta investigación mixta se analizó una muestra del 40% de los cien campos de juego en estudio, por medio de una hoja de evaluación del estado estructural de los aparatos, una entrevista estructurada y la técnica de recopilación pictórica. El estado general de los campos de juego se ve afectado por aspectos como desechos, la falta de basureros, la iluminación, entre otros. Asimismo, la diversidad de aparatos en los campos de juegos es escasa y el daño más frecuente es la herrumbre. El mantenimiento lo brindaba en la mayoría de los casos la propia comunidad o la Municipalidad de Heredia y los planes de mantenimiento eran escasos o nulos. Los campos de juego son actualmente espacios poco seguros que cuentan con peligros como la corrosión de las estructuras, puntas filosas y aparatos dañados. Por lo tanto, requieren una atención inmediata de las autoridades pertinentes y, en su mayoría, no están cumpliendo con el objetivo de su creación.

  19. Central de serviços compartilhados: métricas e resultados de implantação

    Santos, Márcia da Silva

    2009-01-01

    A atenção dispensada aos atrativos das implantações de Centrais de Serviços Compartilhados, também conhecidas como Shared Services, ganha espaço significativo no planejamento estratégico das organizações, principalmente das que possuem várias unidades de negócio. Esta dissertação tem o objetivo de descrever os principais resultados do processo de implantação de uma central de serviços compartilhados, através do uso das métricas determinadas no plano estratégico da corporação e também de ident...

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

    Gortnar, O.; Stritar, A.

    1999-01-01

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