WorldWideScience

Sample records for nucleares del codigo

  1. Validation of a new library of nuclear constants of the WIMS code; Validacion de una nueva biblioteca de constantes nucleares del Codigo WIMS

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    Aguilar H, F [Departamento de Experimentacion, Gerencia del Reactor, ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1991-10-15

    The objective of the present work is to reproduce the experimental results of the thermal reference problems (benchmarks) TRX-1, TRX-2 and BAPL-1 to BAPL-3 with the WIMS code. It was proceeded in two stages, the first one consisted on using the original library of the code, while in the second one, a library that only contains the present elements in the benchmarks: H{sup 1}, O{sup 16}, Al{sup 27}, U{sup 235} and U{sup 238} was generated. To generate the present nuclear data in the WIMS library, it was used the ENDF/B-IV database and the Data processing system of Nuclear Data NJOY, the library was generated using the FIXER code. (Author)

  2. Determination of the costs of the nuclear desalination using the DEEP code from IAEA; Determinacion de los costos de la desalacion nuclear utilizando el codigo DEEP del OIEA

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

    2005-07-01

    The desalination of seawater is being an important solution to satisfy the demands of drinking water to population's centers that have hydric resources very limited, like it is the case of some Arab countries and arid regions of the planet, in where they have settled desalination plants that use as energy source to those fossil fuels or nuclear energy plants. Taking into account that the desalination of seawater is a process that consumes a lot of thermal and/or electric energy, it is necessary to quantify the costs of the supply and that of the desalination plant for different options and technologies, looking for this way the but appropriate for the specific conditions of the region where it has planned the desalination of seawater. In this report the three technologies but promising for the desalination are described and by means of the DEEP code the costs of production of water and energy are evaluated, using as thermal source different types of power nuclear reactors. It was obtained according to DEEP that the costs of the electricity generation for the considered reactors are around 40 USD/MWh. With these costs of electric power generation and using the DEEP code is obtained that the costs of production of drinking water are around 1 USD/m{sup 3}. (Author)

  3. Determination of the physical parameters of the nuclear subcritical assembly Chicago 9000 of the IPN using the Serpent code; Determinacion de los parametros fisicos del conjunto subcritico nuclear Chicago 9000 del IPN usando el codigo SERPENT

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    Arriaga R, L.; Del Valle G, E. [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); Gomez T, A. M., E-mail: guten_tag_04@hotmail.com [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    For the Serpent code was developed the three-dimensional model corresponding to the nuclear subcritical assembly (S A) Chicago 9000 of the Escuela Superior de Fisica y Matematicas del Instituto Politecnico Nacional (ESFM-IPN). The model includes: a) the core, formed by 312 aluminum pipes that contain 5 nuclear fuel rods (natural uranium in metallic form), b) the multi-perforated plates where they penetrate the inferior part of each pipe to be able to remain in vertical form, c) water, acting as moderator and reflector, and d) the recipient lodging to the core. The pipes arrangement is hexagonal although the transversal section of the recipient that lodges to the core is circular. The entrance file for the Serpent code was generated with the data provided by the manual of the S A use about the composition and density of the fuel rods and others obtained in direct form of the rods, as the interior and external diameter, mass and height. Of the obtained physical parameters, those more approached to that reported in the manual of the subcritical assembly are the effective multiplication factor and the reproduction factor η. The differences can be because the description of the fuel rods provided by the manual of the S A use do not correspond those that are physically in the S A core. This difference consists on the presence of a circular central channel of 1.245 diameter centimeters in each fuel rod. The fuel rods reported in the mentioned manual do not have that channel. Although the obtained results are encouraging, we want to continue improving the model to incorporate in this the detectors, defined this way by the Serpent code, which could determine the existent neutrons flux in diverse points of interest like the axial or radial aligned points and to compare these with those that are obtained in an experimental way when a generating neutrons source (Pu-Be) is introduced. Added to this effort the cross sections for each unitary cell will be determined, so that

  4. Human population doses: Comparative analysis of CREAM code results with currently computer codes of Nuclear Regulatory Authority; Dosis en la poblacion: comparacion de los resultados del codigo CREAM con resultados de modelos vigentes en la ARN

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    Alonso Jimenez, Maria Teresa; Curti, Adriana [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)]. E-mail: mtalonso@sede.arn.gov.ar; acurti@sede.arn.gov.ar

    2001-07-01

    The Nuclear Regulatory Authority is performing an analysis with PC CREAM, developed at the NRPB, for updating computer programs and models used for calculating the transfer of radionuclides through the environment. For CREAM dose assessment verification for local scenarios, this paper presents a comparison of population doses assessed with the computer codes used nowadays and with CREAM, for unitary releases of main radionuclides in nuclear power plant discharges. The results of atmospheric dispersion processes and the transfer of radionuclides through the environment for local scenarios are analysed. The programs used are PLUME for atmospheric dispersion, FARMLAND for the transfer of radionuclides into foodstuffs following atmospheric deposition in the terrestrial environment and ASSESSOR for individual and collective dose assessments.This paper presents the general assumptions made for dose assessments. The results show some differences between doses due to differences in models, in the complexity level of the same models, or in parameters. (author)

  5. 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

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    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)

  6. SISTEMAS DETECTORES DE INTRUSOS Y ANALISIS DE FUNCIONAMIENTO DEL PROYECTO DE CODIGO ABIERTO SNORT

    Directory of Open Access Journals (Sweden)

    Jairo Alberto Rojas

    2011-11-01

    Full Text Available En este artículo se presenta el análisis de funcionamiento del SNORT, herramienta de software libre para la detección de intrusiones en red, así como una detallada explicación de la creación de reglas y algunas pruebas realizadas, obteniendo capturas de los paquetes de red por medio del software con una regla existente y otra creada. Lo anterior siguiendo un desarrollo en el cual se trata una breve introducción a los tipos conocidos de ataques informáticos e intrusiones, así como una descripción de la clasificación de los tipos de sistemas detectores de intrusos (IDS, centrándonos en el tipo orientado a red.

  7. Development of a dynamical model of a nuclear processes simulator for analysis and training in classroom based in the RELAP/SCDAP codes; Desarrollo del modulo dinamico del simulador de procesos nucleares para analisis y entrenamiento en aula basado en los codigos RELAP/SCDAP

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    Salazar C, J.H.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [UNAM, Fac. de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, DEPFI Campus Morelos, Cuernavaca (Mexico)]. e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    The present work illustrates the application of the concept of a simulator for analysis, design, instruction and training in a classroom environment associated to a nuclear power station. Emphasis is made on the methodology used to incorporate the best estimate codes RELAP/SCDAP to a prototype under development at the Nuclear Reactor Engineering Analysis Laboratory (NREAL). This methodology is based on a modular structure where multiple processes can be executed in an independent way and where the generated information is stored in shared memory segments and distributed by means of communication routines developed in the C programming language. The utility of the system is demonstrated using highly interactive graphics (mimic diagrams, pictorials and tendency graphs) for the simultaneous dynamic visualization of the most significant variables of a typical transient event (feed water controller failure in a BWR). A fundamental part of the system is its advanced graphic interface. This interface, of the type of direct manipulation, reproduces instruments and controls whose functionality is similar to those found in the current replica simulator for the Laguna Verde Nuclear Power Station. Finally the evaluation process is described. The general behavior of the main variables for the selected transitory event is interpreted, corroborating that they follow the same tendency that those reported for a BWR. The obtained results allow to conclude that the developed system works satisfactorily and that the use of al 1 x 1 real time visualization tools offers important advantages regarding other traditional methods of analysis. (Author)

  8. 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

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    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)

  9. 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

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    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)

  10. 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

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    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)

  11. Simulation of the steady state of the Laguna Verde Nuclear power station at full power (1931 MWt and 2027 Mwt) with the SCDAPSIM code; Simulacion del estado estacionario de la Central Nucleoelectrica de Laguna Verde a plena potencia (1931 MWt y 2027 MWt) con el codigo SCDAPSIM

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    Amador G, R.; Nunez C, A.; Mateos, E. del A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico D.F. (Mexico)

    2001-07-01

    This document describes two models developed for the Laguna Verde Nuclear Power Station (LVNPP) using SCDAPSIM computer code. These models represent the LVNPP in normal operation with a nominal power of 1931 MWt and power uprate conditions of 2027 MWt. The steady states obtained by means of these models comply with the criteria established by the ANSI/ANS-3.5-1985 for nuclear power plant simulators. This criteria has been applied to the models of the LVNPP developed by CNSNS in want of some international accepted criteria for ''Best Estimation'' computer codes. These models will be the bases to carry out studies of validation of the own models as well as the analysis of diverse scenarios that evolve to a severe accident. (Author)

  12. Simulation of the turbine discharge transient with the code Trace; Simulacion del transitorio disparo de turbina con el codigo TRACE

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    Mejia S, D. M.; Filio L, C., E-mail: dulcemaria.mejia@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2014-10-15

    In this paper the results of the simulation of the turbine discharge transient are shown, occurred in Unit 1 of nuclear power plant of Laguna Verde (NPP-L V), carried out with the model of this unit for the best estimate code Trace. The results obtained by the code Trace are compared with those obtained from the Process Information Integral System (PIIS) of the NPP-L V. The reactor pressure, level behavior in the down-comer, steam flow and flow rate through the recirculation circuits are compared. The results of the simulation for the operation power of 2027 MWt, show concordance with the system PIIS. (Author)

  13. Code of Practice on the International Transboundary Movement of Radioactive Waste; Codigo De Practica Sobre Movimientos Internacionales Transfronterizos De Desechos Radiactivos

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    NONE

    1990-11-14

    On 21 September 1990, the General Conference, by resolution GC(XXXIV)/RES/530, adopted a Code of Practice on the International Transboundary Movement of Radioactive Waste and requested the Director General - inter alia - to take all necessary steps to ensure wide dissemination of the Code of Practice at both the national and the international level. The Code of Practice was elaborated by a Group of Experts established pursuant to resolution GC(XXXII)/RES/490 adopted by the General Conference in 1988. The text of the Code of Practice is reproduced herewith for the information of all Member States [Spanish] El 21 de septiembre de 1990, la Conferencia General, en su resolueion GC(XXXIV)/RES/53O, aprobo un Codigo de Practica sobre movimientos internacionales transfronterizos de desechos radiactivos y pidio al Director General, entre otras cosas, que tomase todas las medidas necesarias para lograr una amplia difusion del Codigo de Practica en los planos nacional e internacional. El Codigo de Practica lo elaboro un Grupo de Expertos establecido en cumplimiento de la resolucion GC(XXXII)/RES/49O aprobada por la Conferencia General en 1988. En el presente documento se reproduce el texto del Codigo de Practica para informacion de todos los Estados Miembros.

  14. MCNP and other nuclear codes output graphical representation using python scripts; Representacion grafica de outputs de MCNP y codigos nucleares mediante el uso de scripts en python

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    Cadenas Mendicoa, A. M.

    2016-08-01

    Due to the lack of graphical representation capability of same nuclear codes like MCNP of GOTHIC, widely used in the industry, the following article describes the development of an interface to use a graphical representation open source (Paraview) with the outputs generated by the nuclear codes. Moreover, this article aims at describing the advantage of this type of visualization programs for the modeling and decision making in the calculation. (Author)

  15. Aztheca Code; Codigo Aztheca

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    Quezada G, S.; Espinosa P, G. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, San Rafael Atlixco No. 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico); Centeno P, J.; Sanchez M, H., E-mail: sequga@gmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, Circuito Exterior s/n, 04510 Ciudad de Mexico (Mexico)

    2017-09-15

    This paper presents the Aztheca code, which is formed by the mathematical models of neutron kinetics, power generation, heat transfer, core thermo-hydraulics, recirculation systems, dynamic pressure and level models and control system. The Aztheca code is validated with plant data, as well as with predictions from the manufacturer when the reactor operates in a stationary state. On the other hand, to demonstrate that the model is applicable during a transient, an event occurred in a nuclear power plant with a BWR reactor is selected. The plant data are compared with the results obtained with RELAP-5 and the Aztheca model. The results show that both RELAP-5 and the Aztheca code have the ability to adequately predict the behavior of the reactor. (Author)

  16. Development of neutron own codes for the simulation of PWR reactor core; Desarrollo de codigos neutronicos propios para la simulacion del nucleo de reactores PWR

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    Ahnert, C.; Cabellos, O.; Garcia-Herranz, N.; Cuervo, D.; Herrero, J. J.; Jimenez, J.; Ochoa, R.

    2011-07-01

    The core physic simulation is enough complex to need computers and ad-hoc software, and its evolution is to best-estimate methodologies, in order to improve availability and safety margins in the power plant operation. the Nuclear Engineering Department (UPM) has developed the SEANAP System in use in several power plants in Spain, with simulation in 3D and at the pin level detail, of the nominal and actual core burnup, with the on-line surveillance, and operational maneuvers optimization. (Author) 8 refs.

  17. Modeling of High pressure core spray system (HPCS) with TRAC-BF1 code.; Modelacion del HPCS con el codigo TRAC-BF1.

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    Angel M, E Del

    1994-12-31

    In this work we present a model of the HPCS system of Laguna Verde Nuclear Power Plant (CNLV) which consist of a condensate storage tank (TAC) a vertical surge pipe (TOS), implemented by the Comision Federal de Electricidad (CFE), and the suppression pool (PSP), as well as the associated piping and valves for the HPCS pump suction, to study the system under transient state conditions. The analysis results show that the implemented surge pipe, allows a normal HPCS pump start without automatic inadvertented transfer of the HPCS pump suction from the condensate storage tank to the suppression pool. We briefly mention some problems found during the stimulation and their solution, further we point out some deficiencies of the code for this type of studies. The present model can be used to stimulate other transients with only minor modifications of it. (Author).

  18. Validation of the AZTRAN 1.1 code with problems Benchmark of LWR reactors; Validacion del codigo AZTRAN 1.1 con problemas Benchmark de reactores LWR

    Energy Technology Data Exchange (ETDEWEB)

    Vallejo Q, J. A.; Bastida O, G. E.; Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico); Xolocostli M, J. V.; Gomez T, A. M., E-mail: amhed.jvq@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    The AZTRAN module is a computational program that is part of the AZTLAN platform (Mexican modeling platform for the analysis and design of nuclear reactors) and that solves the neutron transport equation in 3-dimensional using the discrete ordinates method S{sub N}, steady state and Cartesian geometry. As part of the activities of Working Group 4 (users group) of the AZTLAN project, this work validates the AZTRAN code using the 2002 Yamamoto Benchmark for LWR reactors. For comparison, the commercial code CASMO-4 and the free code Serpent-2 are used; in addition, the results are compared with the data obtained from an article of the PHYSOR 2002 conference. The Benchmark consists of a fuel pin, two UO{sub 2} cells and two other of MOX cells; there is a problem of each cell for each type of reactor PWR and BWR. Although the AZTRAN code is at an early stage of development, the results obtained are encouraging and close to those reported with other internationally accepted codes and methodologies. (Author)

  19. Analysis of the three dimensional core kinetics NESTLE code coupling with the advanced thermo-hydraulic code systems, RELAP5/SCDAPSIM and its application to the Laguna Verde Central reactor; Analisis para el acoplamiento del codigo NESTLE para la cinetica tridimensional del nucleo al codigo avanzado de sistemas termo-hidraulicos, RELAP5/SCDAPSIM y su aplicacion al reactor de la CNLV

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    Salazar C, J H; Nunez C, A [CNSNS, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D.F. (Mexico); Chavez M, C [UNAM, Facultad de Ingenieria, DEPFI Campus Morelos (Mexico)

    2004-07-01

    The objective of the written present is to propose a methodology for the joining of the codes RELAP5/SCDAPSIM and NESTLE. The development of this joining will be carried out inside a doctoral program of Engineering in Energy with nuclear profile of the Ability of Engineering of the UNAM together with the National Commission of Nuclear Security and Safeguards (CNSNS). The general purpose of this type of developments, is to have tools that are implemented by multiple programs or codes such a that systems or models of the three-dimensional kinetics of the core can be simulated and those of the dynamics of the reactor (water heater-hydraulics). In the past, by limitations for the calculation of the complete answer of both systems, the developed models they were carried out for separate, putting a lot of emphasis in one but neglecting the other one. These methodologies, calls of better estimate, will be good to the nuclear industry to evaluate, with more high grades of detail, the designs of the nuclear power plant (for modifications to those already existent or for new concepts in the designs of advanced reactors), besides analysing events (transitory and have an accident), among other applications. The coupled system was applied to design studies and investigation of the Laguna Verde Nuclear power plant (CNLV). (Author)

  20. Development and evaluation of the NSSS model with four steam lines for the LVNP using the SCDAPSIM code; Desarrollo y evaluacion del modelo del NSSS con cuatro lineas de vapor para la CNLV utilizando el codigo SCDAPSIM

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    Salazar C, J.H.; Nunez C, A.; Camargo C, R. [CNSNS, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)

    2005-07-01

    The present work shows the pattern of the NSSS considering the four main vapor lines as well as their evaluation. The pattern was developed by the National Commission of Nuclear Security and Safeguards (CNSNS) and it has as main objective to account with a model of the Laguna Verde Nuclear power plant (CNLV) for the simulation and analysis of transitory events where are involved some of main vapor lines, or some relief valves and safety (SRV's). The model was evaluated with data of the CNLV. In 1996 the Federal Commission of Electricity (CFE) request to the CNSNS permission to operate the Unit 2 until the first recharge, having the main vapor line 'B' isolated and operating with a level of power corresponding to a flow of total vapor of 85% of the nominal one (of 1931 MWt). The obtained values were compared with the obtained registrations of the CNLV in order to evaluate the model. Those results show relative errors inferior to 3% among the CNLV reported value and the one calculated by the SCDAPSIM code. (Author)

  1. Generation of nuclear constants of the TRIGA reactor with the Leopard code; Generacion de constantes nucleares del reactor TRIGA con el codigo Leopard

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    Aguilar H, F; Perusquia del C, R [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1983-09-15

    The reactor core was divided in 12 regions, this was made in function of the composition and temperature and its are: 1) central thimble, 2) B ring, 3) C ring, 4) D ring, 5) E ring, 6) F ring, 7) G ring, 8) superior caps of fuel elements (E.C. s) standard, 9) inferior caps of E.C.'s standard, 10) superior and inferior reflector of the core, 11) lateral reflector and 12) superior and inferior caps of the E.C.'s graphite. Likewise the constants of the followers' of fuel cell, of the empty follower and of the conduits of the gamma camera were obtained. For the obtaining of the enter data of the LEOPARD the dimensions and the composition of the different regions are required, this is consigned in the IT/E21-83 report. (Author)

  2. Comparison and validation of the results of the AZNHEX v.1.0 code with the MCNP code simulating the core of a fast reactor cooled with sodium; Comparacion y validacion de los resultados del codigo AZNHEX v.1.0 con el codigo MCNP simulando el nucleo de un reactor rapido refrigerado con sodio

    Energy Technology Data Exchange (ETDEWEB)

    Galicia A, J.; Francois L, J. L.; Bastida O, G. E. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico); Esquivel E, J., E-mail: blink19871@hotmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    The development of the AZTLAN platform for the analysis and design of nuclear reactors is led by Instituto Nacional de Investigaciones Nucleares (ININ) and divided into four working groups, which have well-defined activities to achieve significant progress in this project individually and jointly. Within these working groups is the users group, whose main task is to use the codes that make up the AZTLAN platform to provide feedback to the developers, and in this way to make the final versions of the codes are efficient and at the same time reliable and easy to understand. In this paper we present the results provided by the AZNHEX v.1.0 code when simulating the core of a fast reactor cooled with sodium at steady state. The validation of these results is a fundamental part of the platform development and responsibility of the users group, so in this research the results obtained with AZNHEX are compared and analyzed with those provided by the Monte Carlo code MCNP-5, software worldwide used and recognized. A description of the methodology used with MCNP-5 is also presented for the calculation of the interest variables and the difference that is obtained with respect to the calculated with AZNHEX. (Author)

  3. OECD/NEA International Benchmark exercises: Validation of CFD codes applied nuclear industry; OECD/NEA internatiion Benchmark exercices: La validacion de los codigos CFD aplicados a la industria nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Pena-Monferrer, C.; Miquel veyrat, A.; Munoz-Cobo, J. L.; Chiva Vicent, S.

    2016-08-01

    In the recent years, due, among others, the slowing down of the nuclear industry, investment in the development and validation of CFD codes, applied specifically to the problems of the nuclear industry has been seriously hampered. Thus the International Benchmark Exercise (IBE) sponsored by the OECD/NEA have been fundamental to analyze the use of CFD codes in the nuclear industry, because although these codes are mature in many fields, still exist doubts about them in critical aspects of thermohydraulic calculations, even in single-phase scenarios. The Polytechnic University of Valencia (UPV) and the Universitat Jaume I (UJI), sponsored by the Nuclear Safety Council (CSN), have actively participated in all benchmark's proposed by NEA, as in the expert meetings,. In this paper, a summary of participation in the various IBE will be held, describing the benchmark itself, the CFD model created for it, and the main conclusions. (Author)

  4. Qualification and application of nuclear reactor accident analysis code with the capability of internal assessment of uncertainty; Qualificacao e aplicacao de codigo de acidentes de reatores nucleares com capacidade interna de avaliacao de incerteza

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Ronaldo Celem

    2001-10-15

    This thesis presents an independent qualification of the CIAU code ('Code with the capability of - Internal Assessment of Uncertainty') which is part of the internal uncertainty evaluation process with a thermal hydraulic system code on a realistic basis. This is done by combining the uncertainty methodology UMAE ('Uncertainty Methodology based on Accuracy Extrapolation') with the RELAP5/Mod3.2 code. This allows associating uncertainty band estimates with the results obtained by the realistic calculation of the code, meeting licensing requirements of safety analysis. The independent qualification is supported by simulations with RELAP5/Mod3.2 related to accident condition tests of LOBI experimental facility and to an event which has occurred in Angra 1 nuclear power plant, by comparison with measured results and by establishing uncertainty bands on safety parameter calculated time trends. These bands have indeed enveloped the measured trends. Results from this independent qualification of CIAU have allowed to ascertain the adequate application of a systematic realistic code procedure to analyse accidents with uncertainties incorporated in the results, although there is an evident need of extending the uncertainty data base. It has been verified that use of the code with this internal assessment of uncertainty is feasible in the design and license stages of a NPP. (author)

  5. Analysis of an accident type sbloca in reactor contention AP1000 with 8.0 Gothic code; Analisis de un accidente tipo Sbloca en la contencion del reactor AP1000 con el codigo Gothic 8.0

    Energy Technology Data Exchange (ETDEWEB)

    Goni, Z.; Jimenez Varas, G.; Fernandez, K.; Queral, C.; Montero, J.

    2016-08-01

    The analysis is based on the simulation of a Small Break Loss-of-Coolant-Accident in the AP1000 nuclear reactor using a Gothic 8.0 tri dimensional model created in the Science and Technology Group of Nuclear Fision Advanced Systems of the UPM. The SBLOCA has been simulated with TRACE 5.0 code. The main purpose of this work is the study of the thermo-hydraulic behaviour of the AP1000 containment during a SBLOCA. The transients simulated reveal close results to the realistic behaviour in case of an accident with similar characteristics. The pressure and temperature evolution enables the identification of the accident phases from the RCS point of view. Compared to the licensing calculations included in the AP1000 Safety Analysis, it has been proved that the average pressure and temperature evolution is similar, yet lower than the licensing calculations. However, the temperature and inventory distribution are significantly heterogeneous. (Author)

  6. Adaptation and implementation of the TRACE code for transient analysis in designs lead cooled fast reactors; Adaptacion y aplicacion del codigo TRACE para el analisis de transitorios en disenos de reactores rapidos refrigerados por plomo

    Energy Technology Data Exchange (ETDEWEB)

    Lazaro, A.; Ammirabile, L.; Martorell, S.

    2015-07-01

    Lead-Cooled Fast Reactor (LFR) has been identified as one of promising future reactor concepts in the technology road map of the Generation IVC International Forum (GIF)as well as in the Deployment Strategy of the European Sustainable Nuclear Industrial Initiative (ESNII), both aiming at improved sustainability, enhanced safety, economic competitiveness, and proliferation resistance. This new nuclear reactor concept requires the development of computational tools to be applied in design and safety assessments to confirm improved inherent and passive safety features of this design. One approach to this issue is to modify the current computational codes developed for the simulation of Light Water Reactors towards their applicability for the new designs. This paper reports on the performed modifications of the TRACE system code to make it applicable to LFR safety assessments. The capabilities of the modified code are demonstrated on series of benchmark exercises performed versus other safety analysis codes. (Author)

  7. Development of a model of a NSSS of the PWR reactor with thermo-hydraulic code GOTHIC; Desarrollo de un modelo del NSSS de un reactor PWR con el codigo termo-hidraulico GOTHIC

    Energy Technology Data Exchange (ETDEWEB)

    Gomez Garcia-Torano, I.; Jimenez, G.

    2013-07-01

    The Thermo-hydraulic code GOTHIC is often used in the nuclear industry for licensing transient analysis inside containment of generation II (PWR, BWR) plants as Gen III and III + (AP1000, ESBWR, APWR). After entering the mass and energy released to the containment, previously calculated by other codes (basis, TRACE), GOTHIC allows to calculate in detail the evolution of basic parameters in the containment.

  8. Methodology for solving the equation of transport ordered discrete TORT code in the reactor IPEN/MB-01; Metodologia para resolver la ecuacion del transporte con el codigo de Ordenadas Discretas TORT en el reactor IPEN/MB-01

    Energy Technology Data Exchange (ETDEWEB)

    Bernal, A.; Abarca, A.; Barrachina, T.; Miro, R.; Verdu, G.

    2013-07-01

    The resolution of the neutron transport equation in steady state in pool-type nuclear reactors, is normally achieved through 2 different numerical methods: Monte Carlo (stochastic) and discrete ordinates (deterministic). The discrete ordinates method solves the neutron transport equation for a set of specific addresses, obtaining a set of equations and solutions for each direction, where the solution for each direction is the angular flux. With the aim of treating energy dependence, used energy multigroup approximation, thus obtaining a set of equations that depends on the number of energy groups considered.

  9. Verification of the AZNHEX code v.1.4 with MCNP6 for different reference cases; Verificacion del codigo AZNHEX v.1.4 con MCNP6 para diferentes casos de referencia

    Energy Technology Data Exchange (ETDEWEB)

    Galicia A, J.; Francois L, J. L.; Bastida O, G. E. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, Circuito Exterior s/n, 04510 Ciudad de Mexico (Mexico); Del Valle G, E., E-mail: jgaliciaa87@gmail.com [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, 07738 Ciudad de Mexico (Mexico)

    2017-09-15

    The codes that make up the AZTLAN platform (AZTHECA, AZTRAN, AZKIND and AZNHEX) are currently in the testing phase simulating a variety of nuclear reactor assemblies and cores to compare and validate the results obtained for a particular case, with codes globally used in the nuclear area such as CASMO, Serpent and MCNP. The objective of this work is to continue improving the future versions of the codes of the AZTLAN platform so that accurate and reliable results can be obtained for the user. To test the current version of the AZNHEX code, 3 cases were taken into account, the first being the simulation of a VVER-440 reactor assembly; for the second case, the assembly of a fast reactor cooled with helium was simulated and for the third case it was decided to take up the case of the core of a fast reactor cooled with sodium, this because the previous versions of AZNHEX did not show adequate results and, in addition, they presented a considerable amount of limitations. The comparison and validation of the results (neutron multiplication factor, radial power, radial flow, axial power) for these three cases were made using the code MCNP6. The results obtained show that this version of AZNHEX produces values of the neutron multiplication factor and the neutron and power flow distributions very close to those of MCNP6. (Author)

  10. Development and validation of a model TRIGA Mark III reactor with code MCNP5; Desarrollo y validacion de un modelo del reactor Triga Mark III con el codigo MCNP5

    Energy Technology Data Exchange (ETDEWEB)

    Galicia A, J.; Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico); Aguilar H, F., E-mail: blink19871@hotmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    The main purpose of this paper is to obtain a model of the reactor core TRIGA Mark III that accurately represents the real operating conditions to 1 M Wth, using the Monte Carlo code MCNP5. To provide a more detailed analysis, different models of the reactor core were realized by simulating the control rods extracted and inserted in conditions in cold (293 K) also including an analysis for shutdown margin, so that satisfied the Operation Technical Specifications. The position they must have the control rods to reach a power equal to 1 M Wth, were obtained from practice entitled Operation in Manual Mode performed at Instituto Nacional de Investigaciones Nucleares (ININ). Later, the behavior of the K{sub eff} was analyzed considering different temperatures in the fuel elements, achieving calculate subsequently the values that best represent the actual reactor operation. Finally, the calculations in the developed model for to obtain the distribution of average flow of thermal, epithermal and fast neutrons in the six new experimental facilities are presented. (Author)

  11. Generation of initial geometries for the simulation of the physical system in the DualPHYsics code; Generacion de geometrias iniciales para la simulacion del sistema fisico en el codigo DualSPHysics

    Energy Technology Data Exchange (ETDEWEB)

    Segura Q, E.

    2013-07-01

    In the diverse research areas of the Instituto Nacional de Investigaciones Nucleares (ININ) are different activities related to science and technology, one of great interest is the study and treatment of the collection and storage of radioactive waste. Therefore at ININ the draft on the simulation of the pollutants diffusion in the soil through a porous medium (third stage) has this problem inherent aspects, hence a need for such a situation is to generate the initial geometry of the physical system For the realization of the simulation method is implemented smoothed particle hydrodynamics (SPH). This method runs in DualSPHysics code, which has great versatility and ability to simulate phenomena of any physical system where hydrodynamic aspects combine. In order to simulate a physical system DualSPHysics code, you need to preset the initial geometry of the system of interest, then this is included in the input file of the code. The simulation sets the initial geometry through regular geometric bodies positioned at different points in space. This was done through a programming language (Fortran, C + +, Java, etc..). This methodology will provide the basis to simulate more complex geometries future positions and form. (Author)

  12. Performance of the primary containment of a BWR during a severe accident whit the code RELAP/SCDAPSIM; Comportamiento del contenedor primario de un reactor BWR durante un accidente severo con el codigo RELAP/SCDAPSIM

    Energy Technology Data Exchange (ETDEWEB)

    Castillo G, F.

    2015-07-01

    In this thesis work, it was developed a model of the vacuum breaker valves and down comers for a BWR Mark II primary containment for the code RELAP/SCDAPSIM Mod. 3.4. This code was used to simulate a Station Blackout (Sbo) that evolves to a severe accident scenario. To accomplish this task, the vacuum breaker valves and down comers were included in a simplified model of the primary containment that includes both wet well and dry well, which was coupled with a model of the Nuclear Steam Supply System (NSSS), in order to study the behavior of the primary containment during the evolution of the accident scenario. In the analysis of the results of the simulation, the behavior of the wet well and dry well during the event was particularly monitored, by analyzing the evolution of temperature and pressure profiles in such volumes, this to determine the impact of the inclusion of the breaker vacuum valves and down comers. The results show that the effect of this extension of the model is that more conservative results are obtained, i.e., higher pressures are reached in both wet well and dry well than when it is used a containment model that does not include neither the vacuum valves nor the down comers. The most relevant results obtained show that the Rcic alone is able to keep the core fully covered, but even in such a case, it evaporates about 15% of the initial inventory of liquid water in the Pressure Suppression Pool (Psp). When the Rcic operation is lost, 20% more of the liquid water inventory in the Psp is further reduced within four to twelve hours (approximately), time at which the simulation crashed. Besides, there is a significant increase of pressure in the containment. As the accident evolves, the pressure in the containment continues increasing, but there is still considerable margin to reach the design pressure of the containment. At the end of the simulation, the results show a gauge pressure value of 224,550 Pa in the Psp and 187,482 Pa in the wet well

  13. Structural integrity assessment of a pressure container component. Design and service code implementation. Case studies; Evaluacion de la integridad estructural de un componente contenedor de presion. Aplicacion de los codigos para el disenio y servicio. Estudio de casos

    Energy Technology Data Exchange (ETDEWEB)

    Sanzi, H C [Universidad Tecnologica Nacional, Buenos Aires (Argentina)

    2006-07-01

    In the present work, the most important results of the local stresses occurred in the cracked pipes with a axial through-wall crack (outer), produced during operation of a Petrochemical Plant, using finite elements method, are presented. As requested, the component has been verified based 3D FE plastic analysis, under the postulated failure loading, assuring with this method a high degree of accuracy in the results. Codes used by Design and Service, as ASME Section VIII Div. 2 and API 579, have been used in the analysis. (author) [Spanish] La correcta evaluacion de la integridad estructural de componentes contenedores de presion y canierias requiere del conocimiento y la participacion de especialistas en 'Stress Analysis' y materiales e inspectores. En la actualidad, las tecnicas avanzadas de analisis, que incluyen un detallado 'Stress Analysis', a partir de la utilizacion del metodo de elementos finitos y la mecanica de Fractura, junto con el conocimiento del comportamiento de los materiales y la capacidad para detectar fisuras o discontinuidades - tales como los ensayos no destructivos y la emision acustica - permiten garantizar la seguridad de los componentes a lo largo de su vida util. En este camino los codigos de aplicacion, tanto en el disenio como en el servicio, son utilizados para llevar a cabo un estudio de integridad. En este trabajo se presenta un procedimiento de calculo para evaluar la integridad estructural de un componte contenedor de presion que posee una falla superficial no pasante, en donde se aplica el Codigo API 579, utilizando el metodo de elementos finitos y la mecanica de fractura. (autor)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  15. RECEPTORES NUCLEARES: DEL NÚCLEO AL CITOPLASMA

    Directory of Open Access Journals (Sweden)

    Bibiana Ortega-Domínguez

    2015-01-01

    Full Text Available Los receptores nucleares (RNs constituyen una familia de factores transcripcionales activados por ligando que regulan la expresión de un gran número de genes de forma dependiente del tipo y contexto celular. La localización subcelular de los RNs es altamente dinámica y repercute sobre sus funciones como factores transcripcionales. En presencia de su ligando específico, los RNs se acumulan en el núcleo para modular la expresión de sus genes blanco. Por ende, la salida desde el núcleo a citoplasma de los RNs disminuye su acumulación nuclear y abate su actividad transcripcional. Por lo tanto, la exportación nuclear constituye un importante mecanismo de regulación de la actividad de los RNs. A pesar de su importancia, el proceso de exportación nuclear de los RNs no ha sido completamente explorado, sin embargo, los estudios que se tienen hasta ahora sugieren la participación de las proteínas CRM–1 y la Calreticulina (CRT como mediadoras de este proceso. En esta revisión se destaca la exportación nuclear como un mecanismo regulador de las funciones de los RNs y se discuten las características estructurales y funcionales de las exportinas CRM–1 y CRT.

  16. Validation of finite element code DELFIN by means of the zero power experiences at the nuclear power plant of Atucha I; Convalidacion del codigo DELFIN por medio de las experiencias a potencia cero de la central nuclear Atucha I

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-31

    Code DELFIN, developed in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and currents among elements and a more realistic representation of the hexagonal lattice of the reactor. It can be used for fuel management calculation, Xenon oscillation and spatial kinetics. Using the HUEMUL code for cell calculation (which uses a generalized two dimensional collision probability theory and has the WIMS library incorporated in a data base), the zero power experiences performed in 1974 were calculated. (author). 8 refs., 9 figs., 3 tabs.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

  19. Review: Personal Effects of Divorce in Relation to Children / Recension: Efectos personales del divorcio respecto de los hijos

    Directory of Open Access Journals (Sweden)

    Teresa Duplá Marín

    2013-05-01

    Full Text Available Review: Carmen López‐Rendo Rodríguez, Personal Effects of Divorce in Relation to Children, from Classical Rome to the Spanish Civil Code, RIDROM (online 9, 2012, pp. 249–270. Recension: Carmen López‐Rendo Rodríguez, Efectos personales del divorcio respecto de los hijos, De Roma al Codigo civil español, RIDROM (online 9, 2012, Pág. 249–270.

  20. Proposals for an effective application of the continuous improvement at the ININ according to the IAEA 50-C/SG-Q new code; Propuestas para una aplicacion efectiva del proceso de mejora continua en el ININ, de acuerdo al nuevo codigo 50-C/SG-Q del OIEA

    Energy Technology Data Exchange (ETDEWEB)

    Cardenas A, B.M.; Olivares O, L.A. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1997-07-01

    This work contains the requirements of continuous improvement contained in the IAEA new code {sup Q}uality assurance for safety in nuclear power plants and other nuclear installations, code 50-C/SG-Q. Assuming that it was the base for to elaborate the review No. 5 of the Quality assurance plan at ININ, it was done an analysis to give proposals for the application of continuous improvement in effective way. The relevant points which must be taken in account at the continuous improvement process are: Direction responsibility, involucring of all personnel, process planning, education and training, elaboration of improvement projects, investigation of processes which can be improved, continuation of the improvement process and its evaluation. With the implantation of an effective continuous improvement system it will be obtained to get a better quality and a more efficient safety. (Author)

  1. Model of the containment building of Almaraz NPP and the system of recombiners PARs, with the GOTHIC code, for the study of the diffusion of combustible gases; Modelo del edificio de contencion de C.N. Almaraz y del sistema de recombinadores PARs, con el codigo GOTHIC, para el estudio de la difusion de gases combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Gonzalez, M.; Huelamo, E.; Mazrtinez, M.; Perez, J. R.

    2014-07-01

    This paper presents the analysis of distribution of gases within the containment building carried out a simulation model with the code Thermo hydraulic GOTHIC, which has been evaluated based on passive autocatalytic recombiners gas control system. The model considers scenarios of severe accident with specific conditions that produce the most hydrogen generation rates. Intended to verify the effectiveness of the control system of gas expected to be installed in the Almaraz Nuclear power plant so that the number and location of recombiners equipment meets its function of preventing the formation of explosive atmospheres which impairs the integrity of the containment, reducing and limiting the concentration of combustible gases during the postulated accident. (Author)

  2. Modelization of the initiator success of the accident of Fukushima Daiichi in the NPP of ZION by the code MAAP-5; Modelizacion del suceso iniciador del accidente de Fukushima Daiichi en la C.N. de ZION mediante el codigo MAAP-5

    Energy Technology Data Exchange (ETDEWEB)

    Kevin Fernandez, M.; Jimenez, G.; Batteira, P.

    2013-07-01

    The main objective of the project is the modeling of the accident with a code new in the industry, MAAP5, and in a different nuclear plant, as well as various parameters sensitivity analysis to assess their influence on the evolution of the accident. The paper presents the analysis of the evolution of the simulated accident, as well as the evaluation of different sensitivity analyses performed on different parameters influence on the evolution: pre-accident conditions, actions of operator, etc. Operator actions, not referred to in the emergency procedures, which could influence the behavior of the reactor vessel during severe accident progression were analyzed.

  3. Fuel management inside the reactor. Impact of the substitution of the basic libraries of the Eclipse and Record codes of the FMS system of fuel management; Administracion de combustible dentro del reactor. Impacto de la sustitucion de las bibliotecas basicas de los codigos Eclipse y Record del sistema FMS de administracion de combustible

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G.; Hernandez L, H. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1992-12-15

    The present work is given to know the repercussions in the obtained results by the ECLIPSE-RECORD system of the package of fuel management FMS of SCANDPOWER, with the use of the libraries of effective sections of neutrons, for both codes, generated starting from the ENDF-B/IV database. Inside of the Institute it doesn't have any version of the ECLIPSE code it which drove us to make use of the versions of the THERMOS and GADPOL codes. The obtained results with the libraries generated were compared against those that are obtained making use of the libraries that it possesses the code, generated starting from the ENDF-B/III database, and the data that General Electric Co. reports for the cells that were used for this work. The calculations with the THERMOS-GADPOL-RECORD system, installed in 830 CDC machine of the Institute, its were carried out following the calculation sequence that it is continued during the generation of nuclear databases proposed by CFE only for the series 1 and 2. The obtained results are reported in the Appendixes B and C as well as some of the enter files for the codes used in the Appendix D, which are specified for those installed versions. (Author)

  4. Fuel management inside the reactor. Impact of the substitution of the basic libraries of the Eclipse and Record codes of the FMS system of fuel management; Administracion de combustible dentro del reactor. Impacto de la sustitucion de las bibliotecas basicas de los codigos Eclipse y Record del sistema FMS de administracion de combustible

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G; Hernandez L, H [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1992-12-15

    The present work is given to know the repercussions in the obtained results by the ECLIPSE-RECORD system of the package of fuel management FMS of SCANDPOWER, with the use of the libraries of effective sections of neutrons, for both codes, generated starting from the ENDF-B/IV database. Inside of the Institute it doesn't have any version of the ECLIPSE code it which drove us to make use of the versions of the THERMOS and GADPOL codes. The obtained results with the libraries generated were compared against those that are obtained making use of the libraries that it possesses the code, generated starting from the ENDF-B/III database, and the data that General Electric Co. reports for the cells that were used for this work. The calculations with the THERMOS-GADPOL-RECORD system, installed in 830 CDC machine of the Institute, its were carried out following the calculation sequence that it is continued during the generation of nuclear databases proposed by CFE only for the series 1 and 2. The obtained results are reported in the Appendixes B and C as well as some of the enter files for the codes used in the Appendix D, which are specified for those installed versions. (Author)

  5. Involvement of Union Fenosa skills in the thermohydraulic area of the Jose Cabrera NPP PSA. Applications of the RELAPS5/MOD2 Code; Implicacion de las capacidades de union fenosa dentro del area de termohidraulica en el APS de la C.N. Jose Cabrera. Aplicaciones del codigo RELAP5/MOD2

    Energy Technology Data Exchange (ETDEWEB)

    Martin, L; Saenz Tejada, P [Empresarios Agrupados, A.I.E., Madrid (Spain)

    1993-12-15

    When performing a level 1 Probabilistic Safety Analysis (PSA) on a standard power plant, in order to model plant response to the potential occurrence of the various initiating events postulated in a PSA, reference documentation applicable to the type of plant in question is frequently consulted. Because of the specific design characteristics of the Jose Cabrera NPP, most of the reference documentation for the W-PWR-type power plants is not applicable to this plant. To fill in these gaps in the documentation and to construct the most realistic model of plant behaviour possible, assistance was sought from Union Fenosa by way of infrastructure, capabilities and thermohydraulic experience of the Nuclear Engineering and Fuel Group, and especially the use of calculations performed with the RELAP5/ MOD2 code. This paper will provide an overview of the general assistance rendered to the PSA by the technical experts in thermohydraulics, the calculations performed with RELAP5/MOD2 and the influence all of this has had on the development, quality and results of the Jose Cabrera NPP level 1 PSA Project. (author)

  6. Fuel management inside the reactor. Report of generation of the nuclear bank for the fuel of the initial load of the Laguna Verde U-1 reactor with the FMS codes; Administracion de combustible dentro del reactor. Reporte de generacion del banco nuclear para el combustible de la carga inicial del reactor de Laguna Verde U-1 con los codigos del FMS

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico); Torres A, C. [CFE, Veracruz (Mexico)

    1991-06-15

    In this work in a general way the form in that it was generated the database of the initial fuel load of the Laguna Verde Unit 1 reactor is described. The initial load is formed with fuel of the GE6 type. The obtained results during the formation of the database in as much as to the behavior of the different cell parameters regarding the one burnt of the fuel and the variation of vacuums in the coolant channel its are compared very favorably with those reported by the General Electric fuel supplier and reported in the design documents of the same one. (Author)

  7. ASME power test code ptc 4.1 for steam generators; Codigo de pruebas de potencia ASME ptc 4.1 para generadores de vapor

    Energy Technology Data Exchange (ETDEWEB)

    Plauchu Alcantara, Jorge Alberto [Plauchu Consultores, Morelia, Michoacan (Mexico)

    2001-07-01

    lo anterior al dedicar a este uso de la energia proyectos importantes, algunos de ellos con apoyo de la USAID. La medicion del aprovechamiento energetico o de la eficiencia de generadores de vapor (o calderas) se realiza aplicando algun procedimiento convenido por las partes y el de mayor aceptacion y conocimiento en Mexico e internacionalmente es el Codigo de Pruebas de Potencia ASME PTC 4.1 para Generadores de Vapor. El proposito y formalidad en la determinacion de eficiencia y capacidad de generacion de vapor, comportamiento, regimen termico base o cumplimiento de garantias, cambia radicalmente las exigencias de apego estricto al PTC 4.1 Esta definicion determinara la importancia del metodo de prueba seleccionado, las desviaciones y excepciones convenidas, la influencia de la precision y los errores de medicion, la consideracion de equipo auxiliar, etc. Una interpretacion o aplicacion incorrecta de Codigo de Pruebas ha conducido y conducira a resultados y decisiones no confiables.

  8. Modeling of the vapor cycle of Laguna Verde with the PEPSE code to conditions of thermal power licensed at present (2027 MWt); Modelado del ciclo de vapor de Laguna Verde con el codigo PEPSE a condiciones de potencia termica actualmente licenciada (2027 MWt)

    Energy Technology Data Exchange (ETDEWEB)

    Castaneda G, M. A.; Maya G, F.; Medel C, J. E.; Cardenas J, J. B.; Cruz B, H. J.; Mercado V, J. J., E-mail: miguel.castaneda01@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Veracruz (Mexico)

    2011-11-15

    By means of the use of the performance evaluation of power system efficiencies (PEPSE) code was modeled the vapor cycle of the nuclear power station of Laguna Verde to reproduce the nuclear plant behavior to conditions of thermal power, licensed at present (2027 MWt); with the purpose of having a base line before the implementation of the project of extended power increase. The model of the gauged vapor cycle to reproduce the nuclear plant conditions makes use of the PEPSE model, design case of the vapor cycle of nuclear power station of Laguna Verde, which has as main components of the model the great equipment of the vapor cycle of Laguna Verde. The design case model makes use of information about the design requirements of each equipment for theoretically calculating the electric power of exit, besides thermodynamic conditions of the vapor cycle in different points. Starting from the design model and making use of data of the vapor cycle measured in the nuclear plant; the adjustment factors were calculated for the different equipment s of the vapor cycle, to reproduce with the PEPSE model the real vapor cycle of Laguna Verde. Once characterized the model of the vapor cycle of Laguna Verde, we can realize different sensibility studies to determine the effects macros to the vapor cycle by the variation of certain key parameters. (Author)

  9. South Pacific Nuclear Free Zone Treaty; Tratado Sobre La Zona Desnuclearizada Del Pacifico Sur

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-02-15

    On 6 August 1985 the South Pacific Forum, a body comprising the independent and self-governing countries of the South Pacific (Australia, the Cook Islands, Fiji, Kiribati, Nauru, New Zealand, Niue, Papua New Guinea, the Solomon Islands, Tonga, Tuvalu, Vanuatu and Western Samoa), endorsed the text of the South Pacific Nuclear Free Zone Treaty and opened it for signature [Spanish] El 6 de agosto de 1985 el Foro del Pacifico Sur, organo compuesto por los paises independientes y autonomos del Pacifico Sur (Australia, Fiji, Islas Cook, Islas Salomon, Kiribati, Nauru, Niue, Nueva Zelandia, Papua Nueva Guinea, Samoa Occidental, Tonga, Tuvalu, y Vanuatu), aprobo el texto del Tratado sobre la Zona Desnuclearizada del Pacifico-Sur y lo abrio a la firma.

  10. Knowledge management in the Argentine Nuclear Regulatory Authority; La gestion del conocimiento en la Autoridad Regulatoria Nuclear Argentina

    Energy Technology Data Exchange (ETDEWEB)

    Chahab, Martin [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)

    2006-07-01

    In 2006, the Argentine Nuclear Regulatory Authority has initiated a regulatory knowledge management process to face the loss of knowledge resulting from retiring experts, the generation gap, and the existing need to train new human resources. A number of projects have been started together with the technical assistance of the National Public Administration Institute to preserve knowledge and render it explicit for the coming generations. These projects include 'The History of the Expert's Learning Process' in which the majority of the most critical experts have been interviewed so far. The results of this project help envision a training structure and prospective projects. An Internet Site has also been created on the Intranet in order to render knowledge explicit and facilitate the tools for knowledge management initiatives. Furthermore, ARN's knowledge map project has also been started. (author) [Spanish] La Autoridad Regulatoria Nuclear (ARN), es un Organismo Autarquico de la Administracion Publica Nacional de la Republica Argentina. La puesta en marcha de la gestion del conocimiento en este Organismo responde a la necesidad de no perder los conocimientos de la institucion en el marco del problema del retiro de un numero importante de expertos y de la falta de transmision de sus conocimientos a la nueva generacion. Esta actividad se pone en marcha a traves de programas especificos como entrevistas a expertos retirados y en actividad, la confeccion de un mapa del conocimiento, la identificacion de los conocimientos tacitos y explicitos para su transmision intergeneracional, entre otros, e implica supeditar la estructura tradicional y los procedimientos ya establecidos a los resultados de la misma para cumplir con la mision y vision institucional. Se presentan los objetivos y las caracteristicas del Plan Estrategico de la Institucion, los resultados hasta ahora alcanzados y los desafios a afrontar. (autor)

  11. Management of the process of nuclear transport; Gestion del proceso de transporte nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Requejo, P.

    2015-07-01

    Since 1996 ETSA is the only Spanish logistics operator specialized on servicing the nuclear and radioactive industry. Nowadays ETSA has some technological systems specifically designed for the management of nuclear transports. These tools have been the result of the analysis of multiple factors involved in nuclear shipments, of ETSAs wide experience as a logistics operator and the search for continuous improvement. (Author)

  12. Core reactor simulation of the Central Laguna Verde (CLV) reactor in stationary state and an example of the application in the recharge options analysis of cycle 3; Simulacion del nucleo del reactor de la Central Laguna Verde (CLV) en estado estacionario y ejemplo de aplicacion en el analisis de alternativas de recarga del ciclo 3

    Energy Technology Data Exchange (ETDEWEB)

    Ocampo Mansilla, Hector; Francois Lacouture, Juan Luis; Blanco Lara, Jesus; Cortes Campos, Carlos Cristobal; Esquivias Montoya, Jesus; Esquivel Torres, Jose Luis; Martin del Campo Marquez, Cecilia [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico); Sanchez Herrera, Luciano; Torres Alvarez, Carlos [Comision Federal de Electricidad (CFE), Mexico, D. F. (Mexico)

    1991-12-31

    The results are presented of a study requested by Comision Federal de Electricidad (CFE) for the analysis of Cycle 3, of Unit No. 1 of the Laguna Verde Nuclear Power Station (CLNV) and determine the burning effect impact, carried out with the starting tests and the operation of Cycles 1 and 2 on base of the cycle extension known as coastdown. The calculations were realized with the Code Package FMS for fuel managing, using the Code PRESTO-B that analyzes the reactor in detailed form in three dimensions an in stationary state. In the study the schemes of fraction of recharge proposed by General Electric (GE) were analyzed with the effect of cycle extension. The initial design value of 100 assemblies for Cycle 3, GE proposes to increase such fraction from 112 to 120 assemblies. This impacts the cost of the second recharge and the purpose of this investigation is to analyze options with higher fuel enrichment in U-235 to minimize the number of assemblies in this recharge. The analyses effected show that the designs proposed by GE do not fulfill the required energy proposed for the cycle, even using in the recharge only fuel with 3.03% of enrichment. It is proposed, likewise, the fuel enrichment up to 3.25% to satisfy the energy demand with a minimum of assemblies. [Espanol] Se presentan los resultados de un estudio solicitado por la Comision Federal de Electricidad (CFE) para analizar el ciclo 3, de la unidad 1 de la Central Laguna Verde (CLV), y determinar el impacto del efecto de quemado llevado a cabo con las pruebas de arranque y por la operacion de los ciclos 1 y 2 con base en la tecnica de alargamiento del ciclo conocida como coastdown1. Los calculos se realizaron con el paquete de codigos FMS para la administracion de combustible, usando el codigo PRESTO-B que analiza el reactor en forma detallada en tres dimensiones y en estado estacionario. Se analizaron en el estudio los esquemas de fraccion de recarga propuesta por la General Electric (GE) con el efecto de

  13. Core reactor simulation of the Central Laguna Verde (CLV) reactor in stationary state and an example of the application in the recharge options analysis of cycle 3; Simulacion del nucleo del reactor de la Central Laguna Verde (CLV) en estado estacionario y ejemplo de aplicacion en el analisis de alternativas de recarga del ciclo 3

    Energy Technology Data Exchange (ETDEWEB)

    Ocampo Mansilla, Hector; Francois Lacouture, Juan Luis; Blanco Lara, Jesus; Cortes Campos, Carlos Cristobal; Esquivias Montoya, Jesus; Esquivel Torres, Jose Luis; Martin del Campo Marquez, Cecilia [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico); Sanchez Herrera, Luciano; Torres Alvarez, Carlos [Comision Federal de Electricidad (CFE), Mexico, D. F. (Mexico)

    1992-12-31

    The results are presented of a study requested by Comision Federal de Electricidad (CFE) for the analysis of Cycle 3, of Unit No. 1 of the Laguna Verde Nuclear Power Station (CLNV) and determine the burning effect impact, carried out with the starting tests and the operation of Cycles 1 and 2 on base of the cycle extension known as coastdown. The calculations were realized with the Code Package FMS for fuel managing, using the Code PRESTO-B that analyzes the reactor in detailed form in three dimensions an in stationary state. In the study the schemes of fraction of recharge proposed by General Electric (GE) were analyzed with the effect of cycle extension. The initial design value of 100 assemblies for Cycle 3, GE proposes to increase such fraction from 112 to 120 assemblies. This impacts the cost of the second recharge and the purpose of this investigation is to analyze options with higher fuel enrichment in U-235 to minimize the number of assemblies in this recharge. The analyses effected show that the designs proposed by GE do not fulfill the required energy proposed for the cycle, even using in the recharge only fuel with 3.03% of enrichment. It is proposed, likewise, the fuel enrichment up to 3.25% to satisfy the energy demand with a minimum of assemblies. [Espanol] Se presentan los resultados de un estudio solicitado por la Comision Federal de Electricidad (CFE) para analizar el ciclo 3, de la unidad 1 de la Central Laguna Verde (CLV), y determinar el impacto del efecto de quemado llevado a cabo con las pruebas de arranque y por la operacion de los ciclos 1 y 2 con base en la tecnica de alargamiento del ciclo conocida como coastdown1. Los calculos se realizaron con el paquete de codigos FMS para la administracion de combustible, usando el codigo PRESTO-B que analiza el reactor en forma detallada en tres dimensiones y en estado estacionario. Se analizaron en el estudio los esquemas de fraccion de recarga propuesta por la General Electric (GE) con el efecto de

  14. Propuesta de un nuevo Codigo de etica para los servidores publicos del Estado de Nuevo Leon

    Directory of Open Access Journals (Sweden)

    Jimenez, E.

    2007-07-01

    Full Text Available The global society of the XXI century has a crisis of values. The only important thing is the money. This is serious and dramatic when this crisis is presented in the public service because it interests to the whole society that needs a program of values that it serves from foundation to government's action. This program of values is a Code of Ethics in the public Administration that here intends.

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

    Energy Technology Data Exchange (ETDEWEB)

    Saragoni, G. R.

    2012-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

  17. 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)

    Energy Technology Data Exchange (ETDEWEB)

    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)

  18. Nuclear technology and knowledge management in radioprotection; Tecnologia nuclear y gestion del conocimiento en Radioproteccion

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, A.

    2007-07-01

    The cycle of life of nuclear power plant expands along seven well defined phases lasting about a century and therefore employing three successive generations. Each one of such phases is in need of specific knowledge on radiation protection matters. The nuclear moratorium introduced in Spain in 1983 suspended all those activities related to site selection, design and construction of new units and their commissioning. As it does not seem to be prudent to renounce to nuclear energy on a permanent basis, nuclear utilities, engineering and service companies, academic, research and state organizations agencies should establish programmes to recuperate the radiological knowledge and experience, among other subjects, acquired in the interrupted activities. Likewise, those responsible for the operation of nuclear power plants and the follow up activities should also establish knowledge management activities on radiation protection and other subject matters in line with the IAEA recommendations. (Author) 19 refs.

  19. Maintenance and improvement of thermal hydraulic system codes using results of OCDE experiments (PKL, Rosa, Atlas) and application to Spanish Nuclear power plants. Camp-Spain project; Mejora y mantenimiento de codigos termohidraulicos de sistema de base a resultados de los experimentos OECD (PKL, ROSA y ATLAS) y su aplicacion a plantas espanolas, proyecto Camp-Espana

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, M.; Perez, J.; Martorell, S.; Carlos, S.; Villanueva, J. F.; Sanchez, F.; Queral, C.; Rebollo, M. J.; Rivas-Lewicky, J.; Verdu, G.; Gallardo, S.; Miro, R.; Querol, A.; Munoz-Cobo, J. L.; Escriva, A.; Berna, C.; Reventos, F.; Freixa, J.; Martinez, V.

    2016-08-01

    CSN involvement in different international NEA experimental TH programmes has outlined the scope for a new period of CAMP-Espana activities, currently focused on the: -Analysis, simulation and investigation of specific safety aspects of PKL3/OECD and ATLAS/OECD experiments. -Analysis of applicability and/or extension of the results in these projects to the safety, operation or availability of the Spanish nuclear power plants. Both objective are carried out by simulating experiments and plant application with the last available versions of NRC TH codes (RELAP5 or TRACE). A CAMP in kind contribution (NUREG/IA) is aimed as final result of both types of analyses. Five different national research groups (from Technical Universities of Madrid, Valencia and Cataluna) ate carrying out the development of these activities. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-15

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

  1. Training in nuclear engineering companies; La formacion en las empresas de ingenieria del ambito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Perezagua, R. L.

    2013-03-01

    The importance of training is growing in all business areas and fields and especially in hi-tech companies like engineering firms. Nuclear projects are highly multidisciplinary and, even in the initial awarding and pre-construction phases, need to be staffed with personnel that is well-prepared and highly-qualified in areas that, in most cases, are not covered by university studies. This article examines the variables that influence the design of specific training for nuclear projects in engineering firms, along with new training technologies (e-learning) and new regulatory aspects (IS-12). (Author)

  2. The role of nuclear law in nuclear safety after Fukushima; El rol del derecho nuclear en seguridad nuclear luego de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Cardozo, Diva E. Puig, E-mail: d.puig@adinet.com.uy [International Nuclear Law Association (INLA), Montevideo (Uruguay)

    2013-07-01

    The paper contains the following topics: nuclear law, origin and evolution, role of the legal instruments on nuclear safety, nuclear safety the impact of major nuclear accidents: Chernobyl and Fukushima. The response of the nuclear law post Fukushima. Safety and security. International framework for nuclear safety: nuclear convention joint convention on safety on spent fuel management and on the safety of radioactive waste management. The Fukushima World Conference on Nuclear Safety. Convention on Prompt Notification and Assistance in case of a Nuclear Accident or Radiological Emergency. Plan of Action for Nuclear Safety. IAEA recommendations for the safety transport of radioactive material. International framework for nuclear security. Convention on the Physical Protection of Nuclear Materials. International Convention for the Suppression of Acts Against Nuclear Terrorism. Resolution No. 1540 of the Security Council of United Nations (2004). Measures to strengthen international safety. Code of conduct on the safety research reactor.

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

    Directory of Open Access Journals (Sweden)

    Lilia Fernández Sánchez

    2015-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-03-01

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

  5. Digital transformation and nuclear knowledge management; Transformacion digital y gestion del conocimiento nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz M, F. J., E-mail: fjruiz@tecnatom.es [Grupo Tecnatom, Av. Montes de Oca, 1, 28703 San Sebastian de los Reyes, Madrid (Spain)

    2017-09-15

    The digital transformations that shape and condition the context in which we move are based on an apparent dichotomy between autonomy and collaboration. From this base and taking advantage of hyper connectivity phenomena, the consequences for the knowledge management in its broadest sense, and its involvement in concepts such as smart planet, are analyzed. This concept determines the evolution of organizations towards intelligent (smart) and opens conceptions that influence, in turn, a redesign of teaching-learning processes in the framework of organizations in accordance with these demands. The future bet of Tecnatom is to respond to the challenges that this situation poses in the nuclear and technological sector. (Author)

  6. Los problemas del desarme nuclear en la postguerra fría: Las naciones unidas y la conferencia de desarme en la década del noventa

    Directory of Open Access Journals (Sweden)

    Ana Tejo Carrasco

    2011-04-01

    Full Text Available En este artículo se analiza el desarrollo del desarme nuclear y los pensamientos a favor de su realización definitivo en los noventas. El desarme estuvo bajo la dirección de las Naciones Unidas a través de la Conferencia de Desarme, el cual intentó la eliminación paulatina de las armas nucleares, problema heredado de la Guerra Fría. Este programa no tuvo grandes avances por el desarrollo de la política nuclear de las potencias, lo que ocasionó críticas al funcionamiento  de la organización y la constante presión de la opinión pública por el continuo peligro de estas armas que se acentúa cada década. Palabras claves: Conferencia de Desarme (CD, Desarme Nuclear, política nuclear.      ___________________________Abstract:This article analyzes the development of nuclear disarmament and arguments in favor of a definitive one during the nineties. The disarmament process was carried out by the UN through the Conference of Disarmament (DC who attempted to slowly eliminate nuclear weapons, a Cold War inherited problem. The development of nuclear policies by powerful countries made the schedule of the DC failed which criticizes the way this organization works and the constant pressure from public opinion for the danger these weapons represent, a danger that accentuates each decade.Keywords: Conference of Disarmament (DC, Nuclear Disarmament, nuclear policies.

  7. Nuclear Astrophysics at ELI-NP: the ELISSA prototype tested at Laboratori Nazionali del Sud

    Science.gov (United States)

    Guardo, Giovanni Luca; Anzalone, Antonello; Balabanski, Dimiter; Chesnevskaya, Svetlana; Crucillá, Walter; Filipescu, Dan; Gulino, Marisa; La Cognata, Marco; Lattuada, Dario; Matei, Catalin; Pizzone, Rosario Gianluca; Rapisarda, Giuseppe; Romano, Stefano; Spitaleri, Claudio; Taffara, Alessandra; Tumino, Aurora; Xu, Yi

    2018-01-01

    The Extreme Light Infrastructure-Nuclear Physics (ELI-NP) facility, under construction in Magurele near Bucharest in Romania, will provide high-intensity and high-resolution gamma ray beams that can be used to address hotly debated problems in nuclear astrophysics, such as the accurate measurements of the cross sections of the 24Mg(γ,α)20Ne reaction, that is fundamental to determine the effective rate of 28Si destruction right before the core collapse and the subsequent supernova explosion. For this purpose, a silicon strip detector array (named ELISSA, acronym for Extreme Light Infrastructure Silicon Strip Array) will be realized in a common effort by ELI-NP and Laboratori Nazionali del Sud (INFN-LNS), in order to measure excitation functions and angular distributions over a wide energy and angular range. A prototype of ELISSA was built and tested at INFN-LNS in Catania (Italy) with the support of ELI-NP. In this occasion, we have carried out experiments with alpha sources and with a 11 MeV 7Li beam. Thanks to our approach, the first results of those tests show up a very good energy resolution (better than 1%) and very good position resolution, of the order of 1 mm. Moreover, a threshold of 150 keV can be easily achieved with no cooling.

  8. Evolution of the Radio-sterilized Tissues Bank of the Instituto Nacional de Investigaciones Nucleares; Evolucion del Banco de Tejidos Radioesterilizados del Instituto Nacional de Investigaciones Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Martinez P, M. E.; Reyes F, M. L.; Luna Z, D., E-mail: esther.martinez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    The Radio-sterilized Tissues Bank (RTB) of the Instituto Nacional de Investigaciones Nucleares (ININ) was established in 1997, as national project supported by the IAEA, who provided equipment, training and expert missions. In July of 1999, the Secretaria de Salud (Mexico) granted the sanitary license to the RTB. The first radio-sterilized tissue was the amnion. Later on, the process of frozen and lyophilized pig skin was development. Both tissue types are used as biological dressings in patient with burns, ulcers or on injuries difficult to heal, the amnion is also used for the damage treatment in the ocular surface. In 2003, the ININ improved the facilities of the RTB and in August of that same year the certification of the Quality Administration System was obtained under the standard ISO 9001:2000, at the present time ISO 9001:2008. The support of the IAEA granted to Mexico was of 1997-2004 and 2009-2012, by means of regional and inter regional projects where was obtained equipment and training mainly, for personal of the ININ and other institutions. With the last project supported by the IAEA, two very important documents were generated for the tissues bank of Argentina, Brazil, Colombia, Costa Rica, Cuba, Ecuador, El Salvador, Mexico, Peru, Uruguay and Venezuela, strengthening the interaction among these countries. To offer more radio-sterilized tissues to the medical community, in June of 2007 the RTB signed and agreement with the Secretaria de Salud of the Mexico State by means of the Centro Estatal de Transplantes del Estado de Mexico, for the process of muscle-skeletal tissue, skin and amnion. At present, besides amnion and pig skin, in the RTB there is in existence powdered and chips bone; concluding the validation stage the human skin process is. As a social function of the ININ, the RTB has contributed to the health improvement of patients of more than 50 hospital institutions, mainly those that assist to patient of low resources in different cities of

  9. Divergencia genética en poblaciones peruanas detectada a partir de las frecuencias haplotípicas del mtDNA y del gen nuclear MBL

    Directory of Open Access Journals (Sweden)

    Jesús H. Córdova

    2011-01-01

    Full Text Available Objetivos: Avanzar en el conocimiento del origen de las poblaciones peruanas estudiadas en un contexto filogeográfico. Diseño: Estudio genético poblacional. Instituciones: Laboratorio de Genética Humana, Facultad de Ciencias Biológicas, Universidad Nacional Mayor de San Marcos, e Instituto de Genética y Biología Molecular, Facultad de Medicina, Universidad San Martín de Porras, Lima, Perú. Participantes: Siete poblaciones peruanas. Metodología: Análisis comparativo de los resultados a partir del estudio del mtDNA y el gen nuclear MBL de siete poblaciones peruanas, procesados de manera separada y luego combinados, utilizando el programa PHYLYP 3.65, para obtener valores FST de diferenciación genética y la construcción de árboles de distancias por aplicación del algorritmo UPGMA y el análisis subsecuente de los agrupamientos (clusters generados. Principales medidas de resultados: Árboles genéticos generados. Resultados: De manera separada, los árboles generados para cada marcador genético tuvieron topologías propias y diferentes entre sí. Procesados de manera combinada, el árbol resultante demostró que los mayores valores de diferenciación genética se hallaron en las Islas del Lago Titicaca (Puno, Perú conocidas -Taquile, Amantani y Anapia-, que fue calificada como muy alta, porque mostró valores de FST de 0.3113, 0.2949 y 0.3348 respecto de las poblaciones estudiadas, tanto fuera del Departamento de Puno -como Chachapoyas, Pucallpa y Chiclayo, respectivamente-, así como a la de los Uro del mismo Puno y del mismo Lago Titicaca (0.2837. Fuera de Puno, el par de poblaciones Chachapoyas-Pucallpa fue el menos divergente, al alcanzar entre ellas un valor de FST de 0.0108, calificándosele de pequeña. Conclusiones: El árbol obtenido del procesamiento de los marcadores vía una matriz combinada demostró que las poblaciones que habitan las islas de Taquile, Amantani y Anapia, divergen notablemente de las restantes cuatro

  10. Análisis de los intereses geoestratégicos de China y Estados Unidos en Corea del Sur tras el programa nuclear de Corea del Norte

    OpenAIRE

    Ramírez Ruiz, Vanessa

    2012-01-01

    La península coreana ha sido desde la Guerra Fría y a la actualidad una zona convulsionada por intereses políticos, económicos e ideológicos. Ese panorama obliga un análisis sobre la configuración y los cambios que se han dado entre las potencias actuales, China y Estados Unidos, desde la existencia de un programa nuclear norcoreano que afecta a Corea del Sur y la definición de los intereses de Beijin y Washington.

  11. Efectos del procedimiento de extraccion en la organizacion estructural y composicion quimica de la matriz nuclear en plantas.

    OpenAIRE

    Cerezuela Rosique, María Angeles

    1991-01-01

    La matriz nuclear es una estructura núcleoesquel&ica ampliamente estudiada en sistemas animales, pero apenas existen trabajos que aborden el tema en sistemas vegetales, que poseen diferencias acusadas en la organización del citoesqueleto respecto a las células animales. Para profundizar en el conocimiento sobre el nucleoesqueleto y la matriz nuclear de plantas, hemos realizado un análisis de su organización ultraestructural, composición pohpeptídica y localización de ácidos ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  13. Uranium Determination in Samples from Decommissioning of Nuclear facilities Related to the First Stage of Nuclear Fuel Cycle; Determinacion de Uranio en Muestras Procedentes del Desmantelamiento de Instalaciones de la Primera Parte del Cielo del Combustible Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez, A; Correa, E; Navarro, N; Sancho, C [Ciemat, Madrid (Spain); Angeles, A

    2000-07-01

    An adequate workplace monitoring must be carried out during the decommissioning activities, to ensure the protection of workers involved in these tasks. In addition, a large amount of waste materials are generated during the decommissioning of nuclear facilities. Clearance levels are established by regulatory authorities and are normally quite low. The determination of those activity concentration levels become more difficult when it is necessary to quantify alpha emitters such as uranium, especially when complex matrices are involved. Several methods for uranium determination in samples obtained during the decommissioning of a facility related to the first stage of the nuclear fuel cycle are presented in this work. Measurements were carried out by laboratory techniques. In situ gamma spectrometry was also used to perform measurements on site. A comparison among the different techniques was also done by analysing the results obtained in some practical applications. (Author)

  14. Status of the nuclear sector in Spain Situación del sector nuclear en España

    Directory of Open Access Journals (Sweden)

    Antonio González Jiménez

    2010-12-01

    Full Text Available Spain began to show interest in nuclear energy in the late 1940’s. In 1964 the Nuclear Energy Law was approved, and in 1972 the Nuclear and Radioactive Sites Regulation was developed. Safety and regulation activities were entrusted to the Nuclear Safety Council (Consejo de Seguridad Nuclear created in 1980, and the research and management of radioactive waste to the National Radioactive Waste Company (Empresa Nacional de Residuos Radiactivos, created in 1985. The structure of Spain’s nuclear industry began to be created in the 1960’s, as a consequence of the decision to build the nuclear power plants of José Cabrera, Santa María de Garoña and Vandellós I. In the next stage, during the 1970’s, the Almaraz, Ascó and Cofrentes Nuclear Power Plants were built. During the third stage, in the 1980’s, the Vandellós II and Trillo I Nuclear Power Plants were built. Nowadays, the expert and efficient Spanish nuclear industry is a guarantee that nuclear technology is maintained in Spain, and not only to support the operating plants but also a reactivated international nuclear market. Spain has the necessary infrastructure, the technical capacity, the financial resources and the companies’ willpower in a common effort to provide Spaniards with reliable, cheap and sustainable electric energy that respects the environment and guarantees security for citizens. Nuclear energy is, definitively, a key component today and in the future.España comenzó a interesarse por la energía nuclear a finales de los años cuarenta. En el año 1964 se aprobó la Ley de Energía Nuclear, y en el año 1972 se desarrolló el Reglamento de Instalaciones Nucleares y Radiactivas. Las actividades de seguridad y regulación se encomendaron al Consejo de Seguridad Nuclear, creado en 1980, y la investigación y gestión de los residuos radiactivos a la Empresa Nacional de Residuos Radiactivos (ENRESA, creada en 1985. La estructura industrial nuclear en España comenz

  15. The need of the Nuclear Civil Liability Insurance; La necesidad del Seguro de Responsabilidad Civil Nuclear (SRCN)

    Energy Technology Data Exchange (ETDEWEB)

    Gomez del Campo, J.

    2011-07-01

    Nuclear Liability Insurance (NLI), emerged as a safety mechanism and product to respond to a great risk. because of the compulsory nature of international and national regulations, it has become a compulsory contract. Nuclear risk coverage pools are founded as groups of insurers and reinsures, without legal entity, which cooperate and pool their resources to deal with these great risks. In spain Atomic Pool has been renamed ESPANUCLEAR, administered by and Economic Interest Grouping called Nuclear risk Insurers. (Author)

  16. Dynamics of TRIGA-3 Salazar Reactor.; Dinamica del Reactor TRIGA Mark III del Centro Nuclear de Mexico.

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo S, L F

    1991-12-31

    The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author).

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

    Energy Technology Data Exchange (ETDEWEB)

    Mostaza, J. M.

    2011-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Peco, J.

    2015-07-01

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

  19. APLICACIONES CLÍNICAS DE LAS TÉCNICAS NUCLEARES EN EL ESTUDIO DEL SINCRONISMO VENTRICULAR / Clinical applications of nuclear techniques in the study of ventricular synchronism

    Directory of Open Access Journals (Sweden)

    Amalia Peix González

    2012-07-01

    Full Text Available ResumenTécnicas incruentas como la ecocardiografía, la resonancia magnética nuclear y los estudios de Medicina Nuclear (ventriculografía radioisotópica y gammagrafía de perfusión miocárdica con tomografía de emisión de fotón único, proporcionan información indirecta sobre el sincronismo ventricular cuando se utilizan parámetros de contractilidad mecánica. El análisis de fase de Fourier es un instrumento útil para el empleo de técnicas nucleares con este propósito y se ha aplicado, tanto en la ventriculografía radioisotópica como en la gammagrafía de perfusión. En este trabajo se presenta una revisión en el tiempo de los fundamentos y aplicaciones clínicas de las técnicas nucleares en el estudio del sincronismo ventricular. En la actualidad es la gammagrafía SPECT-gatillada, dentro de las técnicas nucleares, la más utilizada, por la posibilidad que ofrece de evaluar perfusión, función y sincronismo intraventricular en el mismo examen. / AbstractNoninvasive techniques such as echocardiography, nuclear magnetic resonance imaging and nuclear medicine studies (radionuclide ventriculography and myocardial perfusion scintigraphy with single photon emission tomography, provide indirect information about ventricular synchronism when parameters of mechanical contractility are used. The Fourier phase analysis is a useful tool for the use of nuclear techniques for this purpose, and has been applied in both radionuclide ventriculography and perfusion scintigraphy. A review in time of the basics and clinical applications of nuclear techniques in the study of ventricular synchronism is presented in this article. Nowadays, the gated-SPECT scintigraphy is the most common among nuclear techniques because it allows assessing perfusion, function, and intraventricular synchronism in the same test.

  20. Management of the nuclear knowledge and educational strategies in universities; Gestion del conocimiento nuclear y estrategias educativas en universidades

    Energy Technology Data Exchange (ETDEWEB)

    Martin del Campo M, C., E-mail: cecilia.martin.del.campo@gmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac No. 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico)

    2012-10-15

    An introduction is made to the topic of management of the nuclear knowledge and recommendations are presented for its implementation as a curricular subject in the universities and institutions that have post-graduate programs in the engineering and/or nuclear sciences area. The necessity of incorporating a wide variety of tools and innovative techniques of teaching (for example, simulators, didactic games in computer, e-learning) that assure that the learning will be given in an efficient and lasting way is projected. Some strategies are listed to attract the best students toward the academic programs in nuclear engineering or related. Given the great multidisciplinary of the personnel of a nuclear power station, and the other facilities of the fuel cycle, the importance is pointed out of providing the nuclear foundations to all the workers and directive with different formation to the nuclear area, in an attractive way so that they obtain and assimilate the nuclear foundations that will allow him to work efficiently and with all security. Finally, also an analysis is presented about the advantages that represent the education nets that integrate people or institutions in the national, regional or international ambit, which have been created to initiative of the IAEA, having as objective to share ideas, information, study programs, courses, software and resources in general that support the formation of human resources of very high quality, required by the nuclear facilities and the research centers on advanced technologies, as well as to implement programs of nuclear development to short, medium and long period in our country. (Author)

  1. Library of neutron cross sections of the Thermos code; Biblioteca de secciones eficaces de neutrones del codigo Thermos

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G; Hernandez L, H [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1991-10-15

    The present work is the complement of the IT.SN/DFR-017 report in which the structure and the generation of the library of the Thermos code is described. In this report the comparison among the values of the cross sections that has the current library of the Thermos code and those generated by means of the ENDF-B/NJOY it is shown. (Author)

  2. Advances of the Radio sterilized Tissue Bank of the National Institute of Nuclear Research; Avances del Banco de Tejidos Radioesterilizados del Instituto Nacional de Investigaciones Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Reyes F, M. L.; Martinez P, M. E.; Luna Z, D.; Lavalley E, M. C., E-mail: lourdes.reyes@inin.gob.m [ININ, Gerencia de Aplicaciones Nucleares en la Salud, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-07-01

    In view of the necessity of finding alternative sources of biological tissues provision for surgical interventions, the Instituto Nacional de Investigaciones Nucleares (ININ) received the IAEA support from 1997 to 1998, for the establishment of a tissue bank, using the gamma radiation like sterilizing agent. The IAEA support consisted on basic equipment, the personnel's training by means of scientific visits and training in other banks, besides experts missions. As a result of this great support, the Radio sterilized Tissue Bank was established in the ININ, attributed to the Office of Nuclear Applications to the Health. The bank obtained its license in July 7, 1999, granted by the Health Secretary in Mexico. The advances that have been obtained from their creation to the date are presented, with respect to the activities that are carried out in this Tissue Bank. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-15

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

  4. Actualization of the Tandem-E N Accelerator of the Nuclear Centre of Mexico; Actualizacion del Acelerador Tandem-EN del Centro Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Villasenor S, P.; Aguilera R, E.; Aspiazu F, J.; Fernandez A, J.; Fernandez B, M.; Garcia R, B.; Lopez M, J.; Martinez Q, E.; Mendez G, B.; Moreno B, E.; Murillo O, G.; Policroniades R, R.; Ramirez T, J.; Reynoso V, R.; Varela G, A.; Vega C, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2004-07-01

    In this work, the activities are described carried out to change the tubes accelerators and original resistances of the accelerator Tandem-E N of the Nuclear Center, for tubes DOWLISH and resistances again design, both donated ones for ORNL. This way same, the problem is described that imply this changes, and like it was solved by the personnel of the laboratory, without having to appeal to external services, what there is redounded in a considerable increment in the costs. In form preliminary the improvements are described observed after the rehabilitation of the Accelerator. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    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.

  7. Modelo computacional del circuito motor basado en estudios de Resonancia Magnética Nuclear funcional

    OpenAIRE

    Karla Batista García-Ramó; Rafael Rodríguez-Rojas; Maylén Carballo-Barreda

    2012-01-01

    Los ganglios basales constituyen una compleja red de núcleos subcorticales implicados en el control motor,en la integración sensorimotora y en los procesos cognitivos. Su funcionamiento e interacción con el resto de las estructurascerebrales permanecen como una gran polémica. Este trabajo tuvo como objetivo modelar la interacción del circuito formado por los ganglios basales, el tálamo y la corteza para la selección de un programa motor, sobre la base del patrón de conectividad funcional ob...

  8. 3D CAD model of the subcritical nuclear reactor of IPN; Modelo CAD 3D del reactor nuclear subcritico del IPN

    Energy Technology Data Exchange (ETDEWEB)

    Pahuamba V, F. de J.; Delfin L, A.; Gomez T, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Ibarra R, G.; Del Valle G, E.; Sanchez R, A., E-mail: narehc@hotmail.com [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN, Edif. 9, Unidad Profesional Adolfo Lopez Mateos, San Pedro Zacatenco, 07738 Ciudad de Mexico (Mexico)

    2016-09-15

    The three-dimensional (3D) CAD model of the subcritical reactor Chicago model 9000 of Instituto Politecnico Nacional (IPN) allows obtaining a 3D view with the dimensions of each of its components, such as: natural uranium cylindrical rods, fuel elements, hexagonal reactor core arrangement, cylindrical stainless steel tank containing the core, fuel element support grids and reactor water cleaning system. As a starting point for the development of the model, the Chicago model 9000 subcritical reactor manual provided by the manufacturer was used, the measurement and verification of the components to adapt the geometric, physical and mechanical characteristics was carried out and materials standards were used to obtain a design that allows to elaborate a new manual according to the specifications. In addition, the 3D models of the building of the Advanced Physics Laboratory, neutron generator, cobalt source and the corridors connecting to the subcritical reactor facility were developed, allowing an animated ride, developed by computer-aided design software. The manual provided by the company Nuclear Chicago, dates from the year 1959 and presents diverse deviations in the design and dimensions of the reactor components. The model developed; in addition to supporting the development of the new manual represents a learning tool to visualize the reactor components. (Author)

  9. Vision of the Training Department of the National Institute of Nuclear Research; Vision del Departamento de Capacitacion del Instituto Nacional de Investigaciones Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Dominguez A, C. E. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2008-12-15

    The availability of skilled personnel is an essential element of the national infrastructure, to ensure the safety and security through the strong principles of management and good technology, quality assurance, training and qualification of new personnel, thorough safety evaluations and building on lessons of experience and research. In the national case the General Regulation of Radiation Safety requires that the Radiation Safety Responsible (RSR) must be experienced in issues of radiation safety of the facility in which employed. As experience has been found by chance that some people who have attended courses offered by the National Institute of Nuclear Research and have not achieved a result approval, obtain approval at the respective courses offered by other entities, which may have a potential dilemma (not at all cases since then), in the sense that the aspiration to become experts in the safety basic standards, can be addressed only after ensuring that there is an acceptance at the level of the course and evaluation ways of the present courses to RSR. Viewed another way, one can consider the formation of RSR experience in planning for better training of experts in the safety basic standards. It happens that the courses offered to RSR some of them do not cover the requirements of time, content and practices established in the regulations. The Mexican Society of Radiological Safety can affect as a partner to improve the courses quality. (Author)

  10. Nuclear plants in the expansion of the Mexican electrical system;Plantas nucleares en la expansion del sistema electrico mexicano

    Energy Technology Data Exchange (ETDEWEB)

    Estrada S, G. J.; Martin del Campo M, C., E-mail: gestradas@yahoo.co [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2009-10-15

    In this work the results of four studies appear that were realized to analyze plans of long term expansion of Mexican electrical system of generation for the study period 2005-2025. The objective is to identify between the two third generation reactors with greater maturity at present which is it is that it can be integrated better in the expansion of the Mexican electrical system of generation. It was analyzed which of the four cases represents the best expansion plan in terms of two only parameters that are: 1) total cost of generation and, 2) the diversity of generated energy in all the period. In all studies candidates three different units of combined cycle were considered (802, 583 and 291 MW), a turbo gas unit of 267 MW, units of 700 MW with coal base and integrated de sulphur, geo thermo electrical units of 26.95 MW and two different types of nuclear units. In both first studies the Advanced Boiling Water Reactor (A BWR) for the nuclear units is considered, considering that is technology with more maturity of all the third generation reactors. In the following two studies were considered the European Pressurized Reactor (EPR), also of third generation, that uses in essence technology more spread to world-wide level. For this task was used the uni nodal planning model WASP-IV, developed by the IAEA to find the expansion configuration with less generation cost for each study. Considering the present situation of the generation system, the capacity additions begin starting from the year 2012 for the four studies. It is not considered the installation of nuclear plants before 2016 considering that its planning period takes 3 years, and the construction period requires at least of 5 years. In order to evaluate the diversity of each study it was used the Stirling Index or of Shannon-Weiner. In order to classify the studies in cost terms and diversity it was used like decision tool the Savage criterion, called also of minimal repentance. With this data, taking

  11. Neutron analysis of the fuel of high temperature nuclear reactors; Analisis neutronico del combustible de reactores nucleares de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Bastida O, G. E.; Francois L, J. L., E-mail: gbo729@yahoo.com.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2014-10-15

    In this work a neutron analysis of the fuel of some high temperature nuclear reactors is presented, studying its main features, besides some alternatives of compound fuel by uranium and plutonium, and of coolant: sodium and helium. For this study was necessary the use of a code able to carry out a reliable calculation of the main parameters of the fuel. The use of the Monte Carlo method was convenient to simulate the neutrons transport in the reactor core, which is the base of the Serpent code, with which the calculations will be made for the analysis. (Author)

  12. Situación del sector nuclear en España

    Directory of Open Access Journals (Sweden)

    Antonio González Jiménez

    2010-12-01

    Full Text Available España comenzó a interesarse por la energía nuclear a finales de los años cuarenta. En el año 1964 se aprobó la Ley de Energía Nuclear, y en el año 1972 se desarrolló el Reglamento de Instalaciones Nucleares y Radiactivas. Las actividades de seguridad y regulación se encomendaron al Consejo de Seguridad Nuclear, creado en 1980, y la investigación y gestión de los residuos radiactivos a la Empresa Nacional de Residuos Radiactivos (ENRESA, creada en 1985. La estructura industrial nuclear en España comenzó a desarrollarse en los años sesenta, como consecuencia de la decisión de construir las centrales nucleares de José Cabrera, Santa María de Garoña y Vandellós I. En la siguiente etapa, en la década de los años setenta, se construyeron las centrales de Almaraz, Ascó y Cofrentes. Durante la tercera etapa, en la década de los años ochenta, se construyeron las centrales de Vandellós II y Trillo I.Actualmente, la industria nuclear española, experta y eficaz, es garantía de que la tecnología nuclear se conserva en España no solo para apoyar a las centrales nucleares en operación, sino para atender un mercado nuclear reactivado a nivel internacional. España dispone de la infraestructura necesaria, la capacidad técnica, los recursos financieros y la voluntad de las empresas en el empeño común de proporcionar a los españoles una energía eléctrica fiable, barata y sostenible, con respeto al medio ambiente y seguridad para los ciudadanos. La energía nuclear es, en definitiva, una pieza clave hoy y lo será en el futuro.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

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

    Directory of Open Access Journals (Sweden)

    Antonio Torres-Valle

    2012-05-01

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

  16. Entramado organizativo del movimiento feminista en el País Vasco

    Directory of Open Access Journals (Sweden)

    JOSÉ MANUEL FERNÁNDEZ SOBRADO

    1997-01-01

    Full Text Available mas alla de ciertos reduccionismos, parece evidente que los movimientos sociales actuales no son unicamente ideas, codigos culturales, estructuras cognoscitivas, sino tambien organizacion, accion organizada. partiendo de esta premisa, estas paginas que presentamos a continuacion ponen el acento en la dimension organizacional de estos movimientos. la estructura y el entramado organizativo de los movimientos sociales, sus modos de organizacion no son un a priori, algo que preexiste a la accion, sino el resultado de un proceso de construccion social. en este proceso intervienen los propios actores (sus fines, estrategias, ambitos de accion junto con factores del contexto sociopolitico donde surgen los movimientos sociales. el articulo que presentamos aporta, en su primer apartado, algunas claves teoricas y analiticas para el estudio de la organizacion como resultado. en el segundo apartado se exponen los datos mas significativos de una primera investigacion sobre la estructura organizativa del movimiento feminista en el conjunto del estado español, con especial atencion al movimiento feminista del pais vasco.

  17. Improving performance of high risk organizations Spanish nuclear sector from the analysis of organizational culture factors; Mejora del desempeno de las organizaciones de alto riesgo del sector nuclear espanol a partir del analisis de los factores de cultura organizativa

    Energy Technology Data Exchange (ETDEWEB)

    La Salabarnada, E.; German, S.; Silla, I.; Navajas, J.

    2012-07-01

    This paper presents the research project funded by UNESA and conducted by the CISOT-CIEMAT that aims to contribute to improving the operating performance of the Spanish nuclear power plants. This paper aims to identify the factors and key organizational processes to improve efficiency, in order to advance knowledge about the influence of organizational culture on the safety of high reliability organizations.

  18. Analizan partículas calientes del accidente nuclear de Palomares

    OpenAIRE

    León Dueñas, Sergio David

    2012-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    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).

  1. Fire risk assessment method under the technical building code; Metodo de evaluacion del reisgo de incendio en el marco del Codigo Tecnico de la Edificacion

    Energy Technology Data Exchange (ETDEWEB)

    Perez-Martin, J. C.; Diaz-Diaz, R.; Santos-Garcia, R.

    2010-07-01

    The high complexity of measuring and comparing the risk level of performance based design allowed by the Spain Building Code (CTE) and the lack of Spanish legislation on the matter makes a fire risk evaluation tool highly useful guiding the project's and the control authority over the feasibility of these complicated projects. A fire Risk Evaluation Method within the frame of the Spanish Building Code (MEREDICTE) has been developed trying to balance input sources, simplicity and clearness in its use. The number of parameters implied guarantees sound, exhaustive and reliable outputs. MEREDICTE is made of 73 parameters: 31 calculate potential risk and 42 obtain protection level. In an orientative way, MEREDICTE's parameters triple those of the most referred and extended evaluation method: the Gretener Method. The article shows the MEREDICTE technique and foundations, the methodology used in its investigation and development, its most significant innovation and its possible applications. Regarding the protection level, its formulation and applications re referred to the Windsor buildings of Madrid comparing the results obtained on the building as it was devastated by the fire of February 2005 and whether it fulfilled the Spanish building code conditions. (Author) 8 refs.

  2. ITER safety studies: starting the quality plan code AINA; Estudios de seguridad de ITER: Puesta en marcha del plan de calidad del Codigo AINA

    Energy Technology Data Exchange (ETDEWEB)

    Dies, J.; Rivas, J. C.; Bargallo, E.

    2010-07-01

    This contribution discusses the implementation of the Quality Plan AINA Code 2.0. The work has affected areas such as the life cycle model, the software reliability plan, the design of the equipment or software tools to use, and has finally produced a new code.

  3. La retención del conocimiento tácito de los expertos en el sector nuclear: una visión general

    Directory of Open Access Journals (Sweden)

    ÓSCAR RODRÍGUEZ RUIZ

    2007-01-01

    Full Text Available La industria nuclear ha realizado una significativa labor de investigación analítica en el área de reactores en los últimos cincuenta años. Buena parte del conocimiento obtenido tiene carácter tácito, por lo que existe el riesgo de que se pierda a medida que las organizaciones se reestructuren, las prioridades cambien y los trabajadores más experimentados se retiren. Este artículo pretende ofrecer una visión general de las distintas estrategias de retención del conocimiento experto en el sector de la energía atómica. Con esta finalidad realiza una revisión de diferentes iniciativas de difusión del conocimiento tácito desde una perspectiva socio-cognitiva.

  4. Nuclear raw materials prospection mission 1965 report to the Government of the Republic Oriental del Uruguay

    Energy Technology Data Exchange (ETDEWEB)

    Cameron, J

    1966-07-01

    A preliminary reconnaissance survey of Uruguay for nuclear raw materials has been completed. Over 7.700 kilometers have been surveyed by car borne scintillometer and 112 radioactive anomalies have been discovered. Favourable areas with high incidence of anomalies and indications of uranium occurrences have been de-limited in the Minas- Aigua, Valentines-Treinta y Tres, Las Canas, Minas de Corrales and Melo areas. A possibly important indication of uranium at Paso de Las Piedras, Department of Durazno, has also 'been discovered by other means.The area investigated only comprises 0.83 of the total area of Uruguay and the high incidence of anomalies discovered and the other indications of uranium within this area are favourable and encouraging factors for further work,.

  5. Nuclear raw materials prospection mission 1965 report to the Government of the Republic Oriental del Uruguay

    International Nuclear Information System (INIS)

    Cameron, J.

    1966-01-01

    A preliminary reconnaissance survey of Uruguay for nuclear raw materials has been completed. Over 7.700 kilometers have been surveyed by car borne scintillometer and 112 radioactive anomalies have been discovered. Favourable areas with high incidence of anomalies and indications of uranium occurrences have been de-limited in the Minas- Aigua, Valentines-Treinta y Tres, Las Canas, Minas de Corrales and Melo areas. A possibly important indication of uranium at Paso de Las Piedras, Department of Durazno, has also 'been discovered by other means.The area investigated only comprises 0.83 of the total area of Uruguay and the high incidence of anomalies discovered and the other indications of uranium within this area are favourable and encouraging factors for further work,

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-15

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

  7. Las quiebras de la identidad: La doble faz del espacio público

    Directory of Open Access Journals (Sweden)

    GABRIEL GATTI CASAL DE REY

    1997-01-01

    Full Text Available en el pais vasco, tanto las coordenadas que orientan los discursos sobre la identidad colectiva como los escenarios en los que estos discursos se producen y reelaboran han pasado y pasan, tras el proceso de institucionalizacion politica, por una seria redefinicion. la emergencia de estas nuevas formas de construir identidad hace necesaria la reelaboracion del modelo teorico-metodologico que la sociologia ha aplicado a su estudio. dos momentos estructuran nuestro recorrido: 1 identificar los postulados que soportan este modelo (la socializacion entendida como continuidad, los espacios de interaccion entendidos como lugares antropologicos, la identidad entendida como actualizacion de un codigo que preexiste al sujeto ; 2 edificar una optica alternativa, que encuentra en la imagen de la ruptura su centro orientador (la ruptura de los trayectos de socializacion, la crisis que esconde el acceso a los espacios publicos, las quiebras de la identidad. estos desarrollos se apoyan en el estudio de un caso de especial relevancia sociologica: la gestion que de su entrada a uno de estos escenarios institucionales -el de la universidad del pais vasco en sus ramas de euskera- hacen sujetos socializados en el posfranquismo.

  8. Master on Nuclear Engineering and Applications (MINA): instrument of knowledge management in the nuclear sector; Master en Ingenieria Nuclear y Aplicaciones (MINA): instrumento de gestion del conocimiento en el sector nuclear espanol

    Energy Technology Data Exchange (ETDEWEB)

    Herranz, L. E.; Garcia Cuesta, J. C.; Falcon, S.; Casas, J. A.

    2013-03-01

    Knowledge Management in nuclear industry is indispensable to ensure excellence in performance and safety of nuclear installations. The Master on Nuclear Engineering and Applications (MINA) is a Spanish education venture which foundations and evolution have meant and adaptation to the European Education system and to the domestic and international changes occurred in the nuclear environment. This paper summarizes the most relevant aspects of such transformation, its motivation and the final outcome. Finally, it discusses the potential benefit of a closer collaboration among the existing national education ventures in the frame of Nuclear Engineering. (Author)

  9. Optimization of enrichment distributions in nuclear fuel assemblies loaded with Uranium and Plutonium via a modified linear programming technique

    Energy Technology Data Exchange (ETDEWEB)

    Cuevas Vivas, Gabriel Francisco

    1999-12-01

    number of enrichments is accomplished with this methodology. [Spanish] Se ha desarrollado y probado una metodologia para optimizar las distribuciones de enriquecimiento de ensambles de combustible nuclear en Reactores de Agua Ligera (LWR). La tecnica de optimizacion empleada es el metodo revisado simplex de programacion linear y el desempeno del ensamble de combustible se evalua con un codigo de transporte de neutrones que tambien se utiliza en el calculo de los coeficientes de susceptibilidad. El procedimiento de optimizacion de la distribucion del enriquecimiento empieza desde una distribucion de enriquecimiento de un solo-valor (plano) hasta que se logra una meta factor pico de la maxima potencia local. La distribucion optima de barras para el enriquecimiento, con 1.00 para el factor de pico de maxima potencia local y teniendo cada barra su propio enriquecimiento, se calcula en una etapa intermedia del analisis. Posteriormente, las mejores ubicaciones y valores para un reducido numero de enriquecimiento de barras, se obtiene como una funcion del factor pico de la maxima potencia local, mediante la aplicacion de la sensibilidad al cambio de tecnicas. Finalmente, se lleva a cabo un proceso de barajar que asigna enriquecimiento individual entre los grupos de enriquecimiento de barras. La potencia relativa de distribucion de barras de potencia se modifica entonces ligeramente y se redefine el agrupamiento de barras hasta que se logra una configuracion optima. Para verificar la precision de la disposicion de barras.

  10. The public perception of the nuclear energy in Eastern Europe: past and present; La percepcion publica de la energia nuclear en Europa del Este: pasado y presente

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez, A.; Jimenez, G.

    2010-07-01

    In Eastern Europe, people associate nuclear energy to the idea of progress, and prestige of the nuclear industry is very high. This article sets the use of nuclear technology to produce energy in a historical context that is particular to these countries. Results of interviews and surveys are analyzed in order to provide an insight on the level of acceptance among population. (Author)

  11. Workshop on radiation protection of patient. Workshop on radiation protection of worker in nuclear medicine and biomedicine; Taller sobre proteccion radiologica del paciente. Taller sobre proteccion radiologica del trabajador en medicina nuclear y biomedicina

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    In these workshops, information on the following subjects was presented: biological and prenatal effects of ionizing radiation, excretion of radiopharmaceuticals in human breast milk, fetal doses assessment, final disposal of radioactive waste in medical applications, regulatory functions for installations in nuclear medicine, workers doses in nuclear medicine and biomedicine, radioprotection of their nuclear installations, programs of quality assurance, etc.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

  13. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

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

  14. Papers of the First Annual Congress of the Mexican Nuclear Society, C.A.; Memorias del Primer Congreso Anual de la Sociedad Nuclear Mexicana A.C.

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-11-01

    The fulfillment of the First Annual Congress of the Sociedad Nuclear Mexicana is the culmination of a longing for a long time expected for every one of the professionals in the different branches of the nuclear field; to have a forum for the discussion and communication of the achievements of the different institutions in any way involved with nuclear sciences. The reply attained on behalf of community (51 papers) is an indicative of the interest of our members in the event, we are not doubtful that in its consolidation, will be an important forum for the exchange of ideas and the approach among the members of the nuclear community. (Author).

  15. Transactions of the Second Annual Congress of the Sociedad Nuclear Mexicana A.C.; Memorias del Segundo Congreso Anual de la Sociedad Nuclear Mexicana A.C.

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-11-01

    With no doubt, 1991 has been a good year for Nuclear Energy in Mexico. The record imposed by Laguna Verde Nuclear Power Plant, the first in his type in the world, operating without interruption in its first operating cycle, represents a splendid incentive for we all the nuclear workers. This fact is reflected in the percentage of papers presented in this congress, dealing with several aspects of Laguna Verde Central. This achievement should serve as an impulse for the development of other areas of application of nuclear energy in the country and at the same time be a reflection of the participation of the members of our society with good quality papers. In this Second Congress of Sociedad Nuclear Mexicana A.C., around thirty papers were presented in the technical sessions, in areas as: fuel management, radiation protection, reactor physics, transients analysis, nuclear materials and others. A special section is dedicated to present the experiences of the first fuel reload of Unit 1 in Laguna Verde Nuclear Power Plant,as well as different plenary meetings dedicated to subjects of general interest as advanced reactors, waste disposal and others. It is the wish of all the members of Sociedad Nuclear Mexicana A.C., that this annual meetings will be enriched with the enthusiastic participation of the scholars of nuclear field and that they represent the forum that we all need for the exchange of knowledge and experiences. (Author).

  16. Proposal of a monitoring program of occupational exposure by incorporation of radioactive material for nuclear medicine services in the Caja Costarricense del Seguro Social

    International Nuclear Information System (INIS)

    Badilla Segura, Mirta

    2013-01-01

    A monitoring program of the occupational exposure by incorporation of radioactive material is proposed. Nuclear medicine services of the Caja Costarricense del Seguro Social (CCSS) are evaluated. The monitoring program is based on the provisions of the International Atomic Energy Agency and of study of nuclear medicine services of the CCSS. Radionuclides are determined for monitoring of the occupational exposure, according to the radioactive material that is worked in nuclear medicine services of the CCSS. The appropriate and alternative techniques are established for the monitoring of the occupational exposure by incorporation of radioactive material, depending on the type of radionuclide that is worked in nuclear medicine services. The worker occupationally exposed (TOE) should be subject of monitoring and how often should be realized the monitoring of the occupational exposure. The monitoring of the radiation by radioactive material must be applied to personnel working in radiopharmacies and the worker has carried out therapeutic procedures for handling of significant amounts of 13 1 I. The calculation of the committed effective dose is proposed by incorporation of radioactive material with the TOE [es

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  18. Importance of Promocat in nuclear emergency management in ANAV; Impacto del Promocat en la gestion de emergencias en ANAV

    Energy Technology Data Exchange (ETDEWEB)

    Gil Cortiella, R.; Torres Gurdel, C.

    2016-08-01

    The nuclear power plant emergency management tool PROMOCAT, has been developed for supporting and facilitating the nuclear emergency management in the Spanish NPPs of Asco and Vandellos II. PROMOCAT is a computerized tool that comprises all the activities made by the Technical Support Centre (TSC) and Offsite facilities. In order to ease the management and decision-making during a nuclear emergency. In addition, the drill mode helps to improve and strengthen emergency personnel training. (Author)

  19. Research and service capabilities of the National Nuclear Forensic Research Laboratory; Capacidades de investigacion y servicio del Laboratorio Nacional de Investigacion en Forense Nuclear, Lanafonu

    Energy Technology Data Exchange (ETDEWEB)

    Romero G, E. T.; Hernandez M, H.; Flores C, J.; Paredes G, L. C., E-mail: elizabeth.romero@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    According to the recommendations of the International Atomic Energy Agency, Mexico is taking steps to combat illicit trafficking in nuclear material. The creation of a National Nuclear Forensic Research Laboratory (Lanafonu, acronym in Spanish) has been assigned to the Instituto Nacional de Investigaciones Nucleares (ININ, Mexico) in 2014. The objectives of this Laboratory are: to combat illicit trafficking in nuclear materials, to optimize scientific processes and techniques used to analyze nuclear materials (orphans or radioactive sources), environmental and potential biological sources as a result of the handling, transport and final storage. At present, the Lanafonu facilities are focused on the optimization of emergency and routine protocols for measuring radioisotopes in environmental and biological samples using inductive coupling mass spectrometer with magnetic sector. The main activities are: i) optimization of the methods for measuring the isotopes of Pu by alpha-spectrometry, Icp-SFMS and AMS (accelerator mass spectrometry), ii) development or radiochemical methods for routine situations and nuclear emergencies, iii) participation in the scientific technical commission on nuclear forensic science, iv) participation in international intercomparison exercises to optimize and validate methods, and v) consolidation of Lanafonu in Mexico and the IAEA. (Author)

  20. Análisis de las sanciones internacionales en el marco del tratado de no proliferación nuclear. Estudio de caso: energía atómica en Irán (2006-2015)

    OpenAIRE

    Góngora Celedón, Juan Camilo

    2016-01-01

    El presente trabajo de Grado tiene como propósito examinar la incidencia de las sancionesinternacionales en el marco del régimen de no proliferación nuclear en el caso de Irán durante el periodo 2006-2015, teniendo en cuenta factores históricos de años anteriores. Se analiza y explica cómo las sanciones internacionales pueden ser una medida persuasiva por violar ciertos artículos del Tratado de no Proliferación Nuclear. Finalmente identifica y analiza los tipos de sanciones económicas, finan...

  1. Physical aspects of quality assurance in nuclear medicine and radiotherapy, regulatory approach of the National Nuclear Safety Center; Aspectos fisicos de garantia de calidad en medicina nuclear y radioterapia. Enfoque regulatorio del centro Nacional de Seguridad Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez C, D.; Fuente P, A. de la; Quevedo G, J.R.; Lopez F, Y. [CNSN, Calle 28 No. 504 e/5 y 7, Ave. Miramar, La Habana (Cuba); Varela C, C. [CCEEM, Calle 4 No. 455 e/19 y 21, Ave. Vedado, La Habana (Cuba)]. e-mail: cruz@orasen.co.cu

    2006-07-01

    The physical aspects of the quality guarantee in Nuclear Medicine and Radiotherapy its are of cardinal importance to guarantee the quality of the diagnoses and treatments that are carried out to the patients in this type of services. The OIEA, the OMS and other scientific and professional organizations have contributed significantly to the elaboration of recommendations, Protocols, etc. applicable in the quality control programs and safety of the Nuclear Medicine and Radiotherapy departments. In spite of the great effort developed in this sense the Installation of the programs of quality control and safety of the Nuclear Medicine and Radiotherapy departments can fail if the same ones are not based in three decisive elements that are: the existence of national regulations, the existence of the infrastructure required for it and the existence of enough qualified personnel to develop this programs. The present work shows the regulatory focus that on this topic, it has followed the National Center of Nuclear Safety of Cuba (CNSN). The same left of strengthen all the existent Synergies in the different organizations of the country and it went in two fundamental directions: installation of the regulatory requirements that govern this activity and the Authorization of a Cuban Entity, specialized in carrying out audits to the quality control and safety programs of the Nuclear Medicine and Radiotherapy departments. After 4 work years in this direction, the results confirm the validity of the experience developed by the CNSN, at the moment all the services of Nuclear Medicine and Radiotherapy of Cuba possess quality control and safety programs, these programs are annually Auditing by an Authorized entity by the CNSN and the Inspectors of the Regulatory Authority, control, during the inspections, the one execution of the established requirements in the national regulations. The work developed so far can serve, modestly, of reference to others countries of Latin America that

  2. 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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  3. Papers of the Third Annual Congress of the Mexican Nuclear Society, C.A.; Memorias del Tercer Congreso Anual de la Sociedad Nuclear Mexicana, A.C.

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-11-01

    Once again the Sociedad Nuclear Mexicana fulfill its annual Congress being this time the installations of the Instituto de Investigaciones Electricas the place for the event with a collection of forty documents in the following areas: modelling of nuclear systems, expert systems, dosimetry, experimentation and fuel cycle among others. This significant number of papers is a sample of the great interest of the nuclear community in the participation in this forum presenting its more recent works. The participants belongs to the main institutions in the country dedicated to the technological development of the nuclear area in its different branches. Our best wishes are that this event allows not only the exchange of ideas and the knowledge of the type of works that other colleagues are developing, but also to present the opportunity to live together in a pleasant environment where the main ingredient be the surmounting spirit. We welcome all the participants to the Third Congress of our Society. (Author).

  4. Proceedings of the 6. Argentine congress on radiation protection and nuclear safety; Actas del 6. congreso argentino de proteccion radiologica y seguridad nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    The 6th Argentine Congress on Radiation Protection and Nuclear Safety was organized by the Radioprotection Argentine Society, in Buenos Aires, between the 22 and 24 of september of 1998. In this event, were presented almost 66 papers in the following sessions, about these subjects: 1.- Safety in nuclear installations. 2.- Control of nuclear material and physical protection of nuclear installations. 3.- Programs of quality assurance. 4.- Training, technical information and public information. 5.- Physical dosimetry. 6.- Physical dosimetry and occupational radiation protection. 7.- Exposure of the natural radiation. 8.- Environmental radiological safety. 9.- Biological effects of the ionizing radiations and biological dosimetry. 10.- Radiological protection of the medical practice and the radiological emergencies. 11.- Radioactive wastes management. 12.- Transport of radioactive materials

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

    Energy Technology Data Exchange (ETDEWEB)

    Esparza Martin

    2015-07-01

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

  6. Administrative Reorganization, Modification And Enlargement The Personal Plant And The Functions Manual Of The Documentation Center And Nuclear Information Of The Institute Of Nuclear Matters; Reorganizacion administrativa, Modificacion y Amipliacion de la planta de personal y del Manual de Funciones del Centro de Documentacion e Informacion Nuclear del Instituto de Asuntos Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    De Escobar, Cecilia

    1991-07-01

    This document is a project of administrative reorganization, modification and amplification of the personal plant and the functions manual of of the Center of Documentation and Nuclear Information of the IAN. The methodology used to develop this work was constituted by an analysis of the statutes and objectives of the institution. A study of the objectives that the CDIN of the flowchart of the IAN should complete. Interview with the Boss of the CDIN to define necessities as soon as administrative organization, modification of the plant of personal and of the manual of functions of the Center, interview the officials of the Documentation Center, tending efficiently to gather information on the current conditions of work and their proposals for the benefit of the more services. Surveys of the Center users to diagnose like they are come lending the services and their recommendations for the improvement of the same ones.

  7. Modelling of the RA-1 reactor using a Monte Carlo code; Modelado del reactor RA-1 utilizando un codigo Monte Carlo

    Energy Technology Data Exchange (ETDEWEB)

    Quinteiro, Guillermo F; Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Reactores y Centrales Nucleares

    2000-07-01

    It was carried out for the first time, a model of the Argentine RA-1 reactor using the MCNP Monte Carlo code. This model was validated using data for experimental neutron and gamma measurements at different energy ranges and locations. In addition, the resulting fluxes were compared with the data obtained using a 3D diffusion code. (author)

  8. Calculation of the CAREM reactor with the HUEMUL-PUMA-THERMIT chain of codes; Calculo del reactor CAREM con la cadena de codigos HUEMUL-PUMA-THERMIT

    Energy Technology Data Exchange (ETDEWEB)

    Notari, Carla; Grant, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina)

    2000-07-01

    The purpose of the work was the evaluation of the the CAREM 25 reactor core, using a chain of codes (HUEMUL-PUMA-THERMIT) different to the one used in the original design (CONDOR-CITVAP-THERMIT). First, we performed a partial validation of the our codes in lattices similar to CAREM and reproduced a benchmark for simulation of gadolinium burnup. The results were considered satisfactory for this stage of the project. Then, we calculated the core along the normal operating equilibrium cycle and in hot and cold shut-down conditions. The main outcome of our evaluation confirms the general behaviour of the reference calculations except in one important point referring to the cold shut down. In this condition, the failure of one single rod of bank number 13 of the shut down system, leaves the core in a supercritical state at the beginning of the cycle and this anomaly persists during almost a third of the overall cycle. A new design of the core is proposed with minor modifications of the reference one, without introducing new types of fuel elements and keeping the same fuel management scheme. This new core fulfills all the design requirements. (author)

  9. Test and validation of the iterative code for the neutrons spectrometry and dosimetry: NSDUAZ; Prueba y validacion del codigo iterativo para la espectrometria y dosimetria de neutrones: NSDUAZ

    Energy Technology Data Exchange (ETDEWEB)

    Reyes H, A.; Ortiz R, J. M.; Reyes A, A.; Castaneda M, R.; Solis S, L. O.; Vega C, H. R., E-mail: alfredo_reyesh@hotmail.com [Universidad Autonoma de Zacatecas, Unidad Academica de Ingenieria Electrica, Av. Lopez Velarde 801, Col. Centro, 98000 Zacatecas (Mexico)

    2014-08-15

    In this work was realized the test and validation of an iterative code for neutronic spectrometry known as Neutron Spectrometry and Dosimetry of the Universidad Autonoma de Zacatecas (NSDUAZ). This code was designed in a user graph interface, friendly and intuitive in the environment programming of LabVIEW using the iterative algorithm known as SPUNIT. The main characteristics of the program are: the automatic selection of the initial spectrum starting from the neutrons spectra catalog compiled by the International Atomic Energy Agency, the possibility to generate a report in HTML format that shows in graph and numeric way the neutrons flowing and calculates the ambient dose equivalent with base to this. To prove the designed code, the count rates of a spectrometer system of Bonner spheres were used with a detector of {sup 6}LiI(Eu) with 7 polyethylene spheres with diameter of 0, 2, 3, 5, 8, 10 and 12. The count rates measured with two neutron sources: {sup 252}Cf and {sup 239}PuBe were used to validate the code, the obtained results were compared against those obtained using the BUNKIUT code. We find that the reconstructed spectra present an error that is inside the limit reported in the literature that oscillates around 15%. Therefore, it was concluded that the designed code presents similar results to those techniques used at the present time. (Author)

  10. Obtaining of primary rays of spectrum X codes Penelope and MCNP5; Obtencion del espectro primario de Rayos X con los codigos Penelope y MCNP5

    Energy Technology Data Exchange (ETDEWEB)

    Pozuelo, F.; Querol, A.; Gallardo, S.; Rodenas, J.; Verdu, G.

    2012-07-01

    In this case, used codes PENELOPE MCNP5, based on the Monte Carlo method for x-ray spectrum taking into account the characteristics of the x-ray tube. In order to achieve a greater fit of simulated by the theoretical spectrum. It carried out a sensitivity analysis of the parameters available in both codes. The obtaining of the simulated spectrum could lead to an improvement in quality control of the x-ray tube to incorporate it as a method complementary to techniques.

  11. Analysis of the burnup of the control rods with the COREMASTER-Presto code; Analisis del quemado de barras de control con el codigo COREMASTER-PRESTO

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez, J.L.; Alonso, G.; Perusquia, R.; Montes, J.L.; Hernandez, H. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: jlhm@nuclear.inin-mx

    2003-07-01

    An evaluation of the capacity of the COREMASTER-Presto code, to evaluate generically the burnt of the control bars in the Laguna Verde reactors plant (CLV) is made. It was found that the code only reports burnt values of the control rods in MWD/TM, in spite of having with a second order polynomial model, for the conversion to remainder of the Boron-10 (B-10). It was observed that said model is adequate only for burnt smaller to 45,000 MWD/TM. To evaluate the burnt of the control rods it was reproduced the balance cycle of 18 months for the CLV, executing Cm-Presto during 13 consecutive cycles. First without rod burnt, taking this as the base case. Later on, cases with 1, 2 and up to 13 cycles with rod burnt were generated. When comparing results it was observed that the control rods pattern it loses reactivity lineally with the burnt one. By each 10 G Wd/T of burnt of the nucleus it is decreased the reactivity of the pattern rods {approx} 1 pcm in hot condition and of {approx} 20 pcm in cold condition. When burning three cycles those rods more burnt reached the 13,900 MWD/TM, equivalent to 36% of B-10 reduction, near value to 34% proposed by aging in the one lost study of B-10. It was observed that Cm-Presto it doesn't burn the superior node of the control rods when these are completely extracted. A one big lost of B-10, of the order of 50%, it represents only a decrease of 11% of the reactivity value of the rod. One can affirm that even when it is strongly decreased the content of B-10, the rod is continue considering as a black absorber, that is to say, thermal neutron that enters in the neutron rod that is absorbed. (Author)

  12. Application of a Monte Carlo Penelope code at diverse dosimetric problems in radiotherapy; Aplicacion del codigo Monte Carlo Penelope a diversos problemas dosimetricos en radioterapia

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.A.; Fernandez V, J.M.; Salvat, F. [Servicio de Oncologia Radioterapica. Hospital Clinico de Barcelona. Villarroel 170 08036 Barcelona (Spain)

    1998-12-31

    In the present communication it is presented the results of the simulation utilizing the Penelope code (Penetration and Energy loss of Positrons and Electrons) in several applications of radiotherapy which can be the radioactive sources simulation: {sup 192} Ir, {sup 125} I, {sup 106} Ru or the electron beams simulation of a linear accelerator Siemens KDS. The simulations presented in this communication have been on computers of type Pentium PC of 100 throughout 300 MHz, and the times of execution were from some hours until several days depending of the complexity of the problem. It is concluded that Penelope is a very useful tool for the Monte Carlo calculations due to its great ability and its relative handling facilities. (Author)

  13. Verification of Serpent code for the fuel analysis of a PBMR; Verificacion del codigo SERPENT para el analisis de combustible para un PBMR

    Energy Technology Data Exchange (ETDEWEB)

    Bastida O, G. E.; Francois L, J. L., E-mail: gbo729@yahoo.com.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2015-09-15

    In this paper the models and simulations with the Monte Carlo code Serpent are presented, as well as the obtained results of the different analyzed cases in order to verify the suitability or reliability of the use of this code to ensure favorable results in the realization of a neutronic analysis of fuel for a Pebble Bed Modular Reactor (PBMR). Comparisons were made with the results reported in a report by the OECD/Nea relative to a high temperature reactor of spheres bed with plutonium reactor grade as fuel. The results show that the use of Serpent is appropriate, as these results are comparable with those reported in the report. (Author)

  14. Nuclear Medicine Imaging

    Science.gov (United States)

    ... necesita saber acerca de... Estudios de Imagen de Medicina Nuclear Un procedimiento de medicina nuclear se describe algunas veces como unos rayos- ... través del cuerpo del paciente. Los procedimientos de medicina nuclear utilizan pequeñas cantidades de mate- riales radiactivos, ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-09-15

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

  16. L'uso pacifico dell'energia nucleare da Ginevra 1955 ad oggi : il caso italiano : atti del convegno

    CERN Document Server

    2007-01-01

    Energia e sviluppo (le fonti energetiche) ; l'Italia e l'opzione nucleare ; stato a prospettive delle tecnologie nucleari ; reattori nucleari di nuova generazione ; tecniche nucleari in biologia, medicina biochimica, agraria e beni culturali ; sicurezza e ambiente.

  17. Use of bioindicators in the environmental radiological surveillance of Mexican Nuclear Center; Utilizacion de biondicadores en la vigilancia radiologica ambiental del Centro Nuclear de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Gaso P, M.I.; Segovia, N.; Herrera, T.; Perez S, E.; Cervantes, M.L.; Quintero, E.; Palacios, J.; Acosta, E. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico); Herrera, T. [UNAM Instituto Biologia, 04510 Ciudad Univ., Mexico D.F. (Mexico)

    1998-07-01

    Cs-137 and K-40 concentrations were determined in soil samples and wild eatable mushrooms at the forest ecosystem of Mexican Nuclear Center and its surrounding area. The evaluation was carried out with a low bottom gamma spectroscopy system including a high-purity Ge detector (HPGe). The local species that showed greater soil-mushroom transference factor, for Cs-137, were Clavariadelphus truncatus, Cortinarius caerulescenc, Gomphus floccosus and Lyophyllum decastes. The Cs-137 levels obtained in the mushroom samples of Nuclear Center, were in general slightly lower than those of adjacent places, which indicates that this Center is not polluting the atmosphere with such radionuclide. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Martin Aparicio, J.; Atanasio, J.

    2011-07-01

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

  19. The renewable and nuclear energies in the basquet of energy supply; Las energias nuclear y renovables en La cesta del suministro energetico

    Energy Technology Data Exchange (ETDEWEB)

    Martinez Corcoles, F.

    2008-07-01

    The share of nuclear and renewable sources in the energy portfolio yields great benefits to all stake holders and that both sources are not exclusive each other but offer multiple complementary features and synergy's, therefore both technologies should be part of the present and future energy mix. This portfolio should be enough and reliable all the time, guarantee the security of supply, protect the environment and give competitive prices. All these features are to a great extent met by nuclear and renewable technologies and therefore they should play an important role on world and national energy supply. (Author)

  20. Instruction of the CSN on the requirements of the system of management of the nuclear power plants; Instruccion del CSN sobre los requisitos del sistema de gestion de las instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Cid, R.; Santo, A. de; Gil Montes, B.; Toca, A.

    2008-07-01

    The Western European Nations Regulatory Authorities (WENRA) performed a nuclear safety requirements harmonization task, as a result of this work and its implementation, the Spanish Nuclear Safety Counsel (CSN) has the commitment to issue its own Regulation Safety Instructions) to identify the WENRA to level nuclear safety requirements, and to incorporate it in the Spanish regulatory pyramid. However, the Spain nuclear installations meet these requirements through the original criteria to fulfill the regulation of the country that supply the NSSS design, these requirements are not incorporated in our regulation. One of the issues, identified by WENRA, is the implementation of the management system requirements in accord with the IAEA GS-R-3 The Management System for Facilities and Activities. As these regards, the CSN has developed a Safety Instruction, basically endorsing the IAEA GS-R-3. The Safety Instruction is actually in a phase of external comments and should be issued by june 2008. This paper describes the bases for the Safety Instruction, summarises the requirements that would meet the management system for nuclear installations and the activities to perform for its implementations. (Author)

  1. La nascita del programma nucleare iraniano. Washington e Teheran tra alleanza e reciproci sospetti 1956-1979

    OpenAIRE

    Passino, Carlo

    2013-01-01

    The purpose of this dissertation is to investigate and understand the role of the Shah of Iran, and his close relationships with the United States, in the development of the Iranian nuclear program before the Revolution of 1979. The period covered goes from the assignment of Mohammed Reza Pahlavi as Shah of Iran in 1946 to the 1979 when finally Iran and United States found an agreement about mutual nuclear cooperation. The first part of this study examines the situation when Mohammed Reza...

  2. Pre-processing of input files for the AZTRAN code; Pre procesamiento de archivos de entrada para el codigo AZTRAN

    Energy Technology Data Exchange (ETDEWEB)

    Vargas E, S. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Ibarra, G., E-mail: samuel.vargas@inin.gob.mx [IPN, Av. Instituto Politecnico Nacional s/n, 07738 Ciudad de Mexico (Mexico)

    2017-09-15

    The AZTRAN code began to be developed in the Nuclear Engineering Department of the Escuela Superior de Fisica y Matematicas (ESFM) of the Instituto Politecnico Nacional (IPN) with the purpose of numerically solving various models arising from the physics and engineering of nuclear reactors. The code is still under development and is part of the AZTLAN platform: Development of a Mexican platform for the analysis and design of nuclear reactors. Due to the complexity to generate an input file for the code, a script based on D language is developed, with the purpose of making its elaboration easier, based on a new input file format which includes specific cards, which have been divided into two blocks, mandatory cards and optional cards, including a pre-processing of the input file to identify possible errors within it, as well as an image generator for the specific problem based on the python interpreter. (Author)

  3. Analysis of the documents about the core envelopment of nuclear reactor at the Laguna Verde U-1 power plant; Analisis de documentos de los materiales de la envolvente del nucleo del reactor nuclear de la CLV U-1

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-07-01

    The degradation of internal components at BWR type reactors is an important subject to consider in the performance availability of the power plant. The Wuergassen nuclear reactor license was confiscated due to the presence of cracking in the core envelopment. In consequence it is necessary carrying out a detailed study with the purpose to avoid these problems in the future. This report presents a review and analysis of documents and technical information referring to the core envelopment of a BWR/5/6 and the Laguna Verde Unit 1 nuclear reactor in Mexico. In this document are presented design data, documents about fabrication processes, and manufacturing of core envelopment. (Author)

  4. The International Nuclear Event Scale (INES) user's manual. 2001 edition; La escala internacional de sucesos nucleares (INES) manual del usuario. Edicion de 2001

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-12-01

    The International Nuclear Event Scale (INES) was introduced in March 1990 jointly by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). Its primary purpose is to facilitate communication and understanding between the nuclear community, the media and the public on the safety significance of events occurring at nuclear installations. The scale was refined in 1992 in the light of experience gained and extended to be applicable to any event associated with radioactive material and/or radiation, including the transport of radioactive materials.This edition of the INES User's Manual incorporates experience gained from applying the 1992 version of the scale and the document entitled 'Clarification of Issues Raised'. As such, it replaces those earlier publications. It does not amend the technical basis of the INES rating procedure but is expected to facilitate the task of those who are required to rate the safety significance of events using the INES scale. The INES communication network currently receives and disseminates event information to the INES National Officers of 60 Member States on special Event Rating Forms which represent official information on the events, including the rating. The INES communication process has led each participating country to set up an internal network which ensures that all events are promptly communicated and rated whenever they have to be reported outside or inside the country. The IAEA provides training services on the use of INES on request.

  5. Evaluation of the degradation of the service water system in nuclear plants; Evaluacion de la degradacion del sistema de agua de servicio en plantas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Salaices A, E. [IIE, Av. Reforma 113, Col. Palmira, Cuernavaca, Morelos (Mexico)

    2003-07-01

    The service water system, the circulation water system, the cooling water system and the protection against fires system so much in nuclear plants as in fossils plants they are being degraded by a wide variety of mechanisms. These mechanisms include microbiologically influenced corrosion, cavitation, erosion-corrosion, erosion by solid particles, corrosion in cracks, stings, general corrosion, galvanic corrosion, sedimentation and obstructions and incrustations in the heat exchangers. In the last years were developed predictive models for the more common degradation forms and were installed in a new application of the CHECWORKS{sup TM} code called Cooling Water Application (CWA). This application of the code provides a new technology that so much nuclear facilities as fossil ones can use to modelling specific systems and to carry out corrosion predictions in each one of its components. Presently work the results of the employment of the CHECWORKS CWA code are described to carry out predictions of 12 different corrosion mechanisms that affect to the service water system of a nuclear plant, as well as the recommendations and options that the plant can to consider to reduce indexes of damages. This work can be used for to optimize inspections to the service water system and it gives the bases for similar changes in other nuclear plants. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  7. Temporary storage in dry of the spent nuclear fuel in the Nuclear Power Plant of Laguna Verde; Almacenamiento temporal en seco del combustible nuclear gastado en la Central Nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, N.; Vargas A, A., E-mail: natividad.hernandez@cfe.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Carretera Veracruz-Medellin Km. 7.5, 94270 Dos Bocas, Veracruz (Mexico)

    2013-10-15

    To guarantee the continuity in the operation of the two nuclear reactors of the nuclear power plant of Laguna Verde (NPP-L V) is an activity of high priority of the Comision Federal de Electricidad (CFE) in Mexico. At the present time, the CFE is working in the storage project in dry of the spent fuel with the purpose of to liberate space of the pools and to have the enlarged capacity of storage of the spent fuel that is discharged of the reactors. This work presents the storage option in dry of the spent fuel, considering that the original capacity of the spent fuel pools of the NPP-L V was of 1242 spaces each one and that in 1991, through a modification of the original design, the storage capacity was increased to 3177 spaces by pool. At present, the cells occupied by unit are of 2165 (68%) for the Unit-I and 1839 (58%) for the Unit-2, however, in 2017 and 2022 the capacity to discharge the complete core will be limited by what is required of a retirement option of spent fuel assemblies to liberate spaces. (author)

  8. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

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

  9. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  10. Impact analysis of modifying the composition of the nuclear fuel of a BWR with beryllium oxide; Analisis del impacto de modificar la composicion del combustible nuclear de un BWR con oxido de berilio

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo V, J. M.; Morales S, J. B., E-mail: euqrop@hotmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2013-10-15

    The beryllium oxide (Be O) presents excellent physical properties, especially its high thermal conductivity that contrasts clearly with that of the uranium dioxide (UO{sub 2}) used at the present as fuel in a great number of nuclear plants. The present work models a nuclear reactor cooled by light water in boiling with two external recirculation loops (BWR/5) using the code for the transitory analysis and postulated accidents Trac-B F1, implementing a UO{sub 2} mixture and different fractions of Be O, with the objective of improving the thermal conductivity of the fuel. The numeric results and the realized analyses indicate that when adding a fraction in volume of 10% the central temperature decreases in 30.4% in stationary state, while during the large break loss of coolant accident the peak cladding temperature diminishes in 7%. Although the real interaction of the mixture has not been determined experimentally, the obtained results are promising. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Silva, M.

    2005-07-01

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

  13. Immobilization of ion exchange radioactive resins of the TRIGA Mark III nuclear reactor; Inmovilizacion de resinas de intercambio ionico radiactivas del reactor nuclear Triga Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Garcia M, H.; Emeterio H, M.; Canizal S, C. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, C.P. 11801 Mexico D.F. (Mexico)

    2000-07-01

    This work has the objective to develop the process and to define the agglutinating material which allows the immobilization of the ion exchange radioactive resins coming from the TRIGA Mark III nuclear reactor contaminated with Ba-133, Co-60, Cs-137, Eu-152, and Mn-54 through the behavior analysis of different immobilization agents such as: bitumens, cement and polyester resin. According to the International Standardization the archetype samples were observed with the following tests: determination of free liquid, leaching, charge resistance, biodegradation, irradiation, thermal cycle, burned resistance. Generally all the tests were satisfactorily achieved, for each agent. Therefore, the polyester resin could be considered as the main immobilizing. (Author)

  14. The prisoner's dilemma in the production of nuclear hydrogen; El dilema del prisionero en la produccion de hidrogeno nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Mendoza, A.; Francois, J. L.; Martin del Campo, C., E-mail: iqalexmdz@yahoo.com.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2011-11-15

    The human beings take to daily decisions, so much at individual as social level, that affect their quality of life in more or minor measure and modify the conditions of their environment. Decisions like to use the car or the public transportation or government policies to adopt and energy development plan that includes technologies like the production of nuclear hydrogen, present a grade of global influence, not only affect or benefit at the person or government that it carries out them, but also present consequences in the individuals and resources of the environment. The hydrogen production using nuclear energy as supply of thermal energy is in itself decision matter; from investing or not in their investigation until fomenting laws and policies that impel their development and incorporation to the industrial panorama. The countries and institutes that opt to impel this technology have the possibility to obtain economic and environmental benefits in contrast with those that do not make it, these last only benefited of the first ones in the environmental aspect. High cost for the technological transfer and economic sanctions sustained in environmental arguments toward those -non cooperators- would be a possible consequence of the cooperators action in the search of a Nash balance. The Prisoner's dilemma exemplifies and increases the comprehension of this type of problems to search for better conditions in the system that improve the situation of all the participants, in this case: governments and institutions. (Author)

  15. 3D analysis of Navier-Stokes in steady state of the behavior of the flow in the Inter stage 1 of a gas turbine Frame 7; Analisis de navier-stokes tridimensional en estado estable del comportamiento del flujo en la inter etapa 1 de una turbina de gas frame 7

    Energy Technology Data Exchange (ETDEWEB)

    Henandez Rosete, Alejandro; Mazur C, Zdzislaw [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2007-11-15

    The results of the simulation by CFD (Computacional Fluid Dynamics) realized to the first stage of a gas turbine GE Frame 7 are presented. The analysis includes the 3D modeling of the flow channel in the nozzle and the movable blade to know the velocities distributions, temperatures and pressures of the main hot gas flow that are developed in the Inter stage. The results are influenced by the imposed border conditions in the properties of the main flow, the rotation of the movable blade, as well as the simulation of cooling air injection in the nozzle. The present study focuses in the validation of the model of the meshes of the ensemble nozzle-blade, for later realize an analysis of conjugated heat transfer in a model with ceramic lining type heat barrier (THB) in the movable blade. The analysis is realized in a CFD commercial code oriented to turbo-machinery using the equations of unstable flows 3D of Navier Stokes. [Spanish] Se presentan los resultados de la simulacion por CFD (Computacional Fluid Dynamics) realizada a la primera etapa de una turbina de gas GE Frame 7. El analisis incluye la modelacion tridimensional del canal de flujo en la tobera y el alabe movil para conocer las distribuciones de las velocidades, temperaturas y presiones del flujo principal de gases calientes que se desarrollan en la inter etapa. Los resultados son influenciados por las condiciones de frontera impuestos en las propiedades del flujo principal, la rotacion del alabe movil, asi como la simulacion de inyeccion de aire de enfriamiento en la tobera. El presente estudio se enfoca en la validacion del modelo de la malla del conjunto tobera-alabe, para posteriormente realizar un analisis de transferencia de calor conjugada en un modelo con recubrimiento ceramico tipo barrera termica (TBC) en el alabe movil. El analisis es realizado en un codigo de CFD comercial orientado a turbomaquinaria utilizando las ecuaciones de flujos inestables 3D de Navier Stokes.

  16. Analysis of the anisotropy effects with the AZTRAN code; Analisis de los efectos de la anisotropia con el codigo AZTRAN

    Energy Technology Data Exchange (ETDEWEB)

    Xolocostli, V.; Vargas, S.; Gomez, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle, E., E-mail: vicente.xolocostli@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, 07738 Ciudad de Mexico (Mexico)

    2017-09-15

    Among the improvements that are made for the deterministic codes with which nuclear reactors are analyzed, is the implementation of the dispersion anisotropic dispersion section, which can obtain better results. With the current computing technology is possible to carry out these implementations, since the computation time is no longer a considerable problem as in the past. In this paper we analyze some effects of anisotropy in the AZTRAN code, a code that solves the Boltzmann transport equation in one, two and three dimensions at steady state, using the multigroup technique, the nodal method RTN-0 and ordered discrete, which is part of the AZTLAN platform for analysis of nuclear reactors, which is currently under development. The implementation of the anisotropy in the AZTRAN code is one of the latest improvements that have been made to the code, leading to different tests and analyzes regarding the anisotropic dispersion, some as a test with homogeneous fuel assemblies. In the case presented here, the benchmark problem of a fuel assembly type BWR is analyzed, which is part of the Benchmark problem suite for reactor physics study of LWR next generation fuels, proposed by the Committee on Reactor Physics organized by the Japan Atomic Energy Research Institute (JAERI). In this problem the behavior of the infinite multiplication factor (k{sub inf}) is analyzed, as well as the behavior of using odd and even anisotropy approximation with respect to the symmetry in the radial power of the assembly. (Author)

  17. Improvement of the obtention process of phosphorus-32 of the ININ through the application of nuclear analytical techniques; Perfeccionamiento del proceso de obtencion de fosforo-32 del ININ, mediante la aplicacion de tecnicas analiticas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zepeda R, C P [UMSNH, Facultad de Ingenieria Quimica, Morelia, Michoacan (Mexico)

    2007-07-01

    The phosphorus-32, is radioisotope emitting pure {beta}{sup -}, of maximum energy 1.71 MeV with an average life of 14.28 days, and that has application in the industry, agriculture, medicine and biology. The {sup 32} P, produced by means of two nuclear reactions {sup 32} S(n,p){sup 32} P and {sup 31} P (n,{gamma}){sup 32} P; by the facility of handling of sulfur, his low cost and its fast acquisition in the market. I selected the reaction {sup 32} S(n,p){sup 32} P. To produce {sup 32} P it is necessary to prepare and to characterize the target (S-{alpha}) that is obtained from the purification of the raw material, make the mathematical calculations of irradiation, irradiation of the target in the nuclear reactor TRIGA Mark III, radiochemical separation of {sup 32} P of {sup 32} S by a dry distillation method and an hydrolysis of {sup 32} P with diluted HCl obtaining H{sub 3}{sup 32}PO{sub 4} and finally quality control. In the order to make the radiochemistry separation it was necessary to make previous modifications to the process guarantee the quality of product ({sup 32} P), and security of the operator. (Author)

  18. Circuits design of action logics of the protection system of nuclear reactor IAN-R1 of Colombia; Diseno de los circuitos de la logica de actuacion del sistema de proteccion del reactor nuclear IAN-R1 de Colombia

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez M, J. L.; Rivero G, T.; Sainz M, E., E-mail: joseluis.gonzalez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    Due to the obsolescence of the instrumentation and control system of the nuclear research reactor IAN-R1, the Institute of Geology and Mining of Colombia, IngeoMinas, launched an international convoking for renewal it which was won by the Instituto Nacional de Investigaciones Nucleares (ININ). Within systems to design, the reactor protection system is described as important for safety, because this carried out, among others two primary functions: 1) ensuring the reactor shutdown safely, and 2) controlling the interlocks to protect against operational errors if defined conditions have not been met. To fulfill these functions, the various subsystems related to the safety report the state in which they are using binary signals and are connected to the inputs of two redundant logic wiring circuits called action logics (Al) that are part of the reactor protection system. These Al also serve as logical interface to indicate at all times the status of subsystems, both the operator and other systems. In the event that any of the subsystems indicates a state of insecurity in the reactor, the Al generate signals off (or scram) of the reactor, maintaining the interlock until the operator sends a reset signal. In this paper the design, implementation, verification and testing of circuits that make up the Al 1 and 2 of IAN-R1 reactor is described, considering the fulfillment of the requirements that the different international standards imposed on this type of design. (Author)

  19. License considerations of the temporary storage in dry of the nuclear spent fuel of light water reactors; Consideraciones de licenciamiento del almacenamiento temporal en seco del combustible gastado nuclear de reactores de agua ligera

    Energy Technology Data Exchange (ETDEWEB)

    Bazan L, A.; Vargas A, A.; Cardenas J, J. B., E-mail: ariadna.bazan@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 spent fuel of the nuclear power plants of light water is usually stored in cells or frames inside steel coating pools. The water of the spent fuel pool has a double function: it serves as shielding or barrier for the radiation that emits the spent fuel and, on the other hand, to cool it in accordance with its decay in the time. The administration policies of the spent fuel vary of some countries to other, resulting common to all the cases this initial stage of cooling in the pools, after its irradiation in the reactor. When is not possible to increase more this capacity, usually, technologies of temporary storage in dry of the spent fuel in independent facilities are used. The storage in dry of the spent fuel differs of the storage in the fuel pools making use of gas instead of water as coolant and using metal or concrete instead of the water like barrier against the radiation. The storage industry in dry offers a great variety of technologies, which should be certified by the respective nuclear regulator entity before its use. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  1. Updates of the fire protection system of the Juzbado Nuclear Fuel Fabrication Plant; Actualizaciones del Sistema de Proteccion Contra Incendios de la Fabrica de Combustible Nuclear de Juzbado

    Energy Technology Data Exchange (ETDEWEB)

    Dorado, P.; Palomo, J. J.; Romano, A.

    2015-07-01

    The Juzbado Nuclear Fuel Fabrication Plant fire protection system is one of the most important safety system of the plant. Every year, a large part of the annual investment is employed to improve this system, to update its technology, in order to improve detection and extinction capability to minimize fire risk. Over the last few years, several improvement projects have been carried out that focused on fire detection technology update and on optimization of local detectors integration with a centralized control system, as well as on an advanced public address system, which used clear and unambiguous messages improving personnel response to a plant evacuation. Planned projects and those, which are currently under development, focus on improving passive fire protection means as well as fire protection of key emergency response equipment s such as emergency diesel generators and fire extinguishing bombs. (Author)

  2. Neutrons characterization of the nuclear reactor Ian-R1 of Colombia; Caracterizacion de los neutrones del reactor nuclear IAN-R1 de Colombia

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez P, L. X.; Martinez O, S. A. [Universidad Pedagogica y Tecnologica de Colombia, Grupo de Fisica Nuclear Aplicada y Simulacion, Carretera Central del Norte Km. 1, Via Paipa, 150003 Tunja, Boyaca (Colombia); Vega C, H. R., E-mail: s.agustin.martinez@uptc.edu.co [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico)

    2014-08-15

    By means of Monte Carlo methods, with the code MCNPX, the neutron characteristics of the research nuclear reactor Ian-R1 of Colombia, in power off but with the neutrons source in their start position, have been valued. The neutrons spectra, the total flow and their average power were calculated in the irradiation spaces inside the graphite reflector, as well as in the cells with air. Also the spectra, the total flow and the absorbed dose were calculated in several places distributed along the radial shaft inside the water moderator. The neutrons total flow was also considered to the long of the axial shaft. The characteristics of the neutrons spectra vary depending on their position regarding the source and the material that surrounds to the cell where the calculation was made. (Author)

  3. Evaluation of the recycling costs, as a disposal form of the spent nuclear fuel; Evaluacion de los costos del reciclado como una forma de disposicion del combustible nuclear gastado

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

    At the moment there are 2 BWR reactors operating in the Nuclear Power station of Laguna Verde in Mexico. At the end of the programmed life of the reactors (40 years) its will have completed 26 operation cycles, with will have 6712 spent fuel assemblies will be in the pools of the power station. Up to now, the decision on the destination of the high level wastes (spent nuclear fuel) it has not been determined in Mexico, the same as in other countries, adopting a politics of 'to wait to see that it happens in the world', in this respect, in the world two practical alternatives exist, one is to store the fuel in repositories designed for that end, another is reprocess the fuel to recycle the plutonium contained in it, both solutions have their particular technical and economic problematic. In this work it is evaluated from the economic point of view the feasibility of having the spent fuel, using the one recycled fuel, for that which thinks about a consistent scenario of a BWR reactor in which the fuel discharged in each operation cycle is reprocessed and its are built fuel assemblies of the MOX type to replace partly to the conventional fuel. This scenario shows an alternative to the indefinite storage of the high level radioactive waste. The found results when comparing from the economic point of view both options, show that the one recycled, even with the current costs of the uranium it is of the order of 7% more expensive that the option of storing the fuel in repositories constructed for that purpose. However the volumes of spent fuel decrease in 66%. (Author)

  4. Immobilization of Ion Exchange radioactive resins of the TRIGA Mark III Nuclear Reactor; Inmovilizacion de resinas de intercambio ionico radiactivas del reactor nuclear TRIGA Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Martinez, H

    1999-07-01

    In the last decades many countries in the world have taken interest in the use, availability, and final disposal of dangerous wastes in the environment, within these, those dangerous wastes that contain radioactive material. That is why studies have been made on materials used as immobilization agent of radioactive waste that may guarantee its storage for long periods of time under drastic conditions of humidity, temperature change and biodegradation. In mexico, the development of different applications of radioactive material in the industry, medicine and investigation, have generated radioactive waste, sealed and open sources, whose require a special technological development for its management and final disposal. The present work has as a finality to develop the process and define the agglutinating material, bitumen, cement and polyester resin that permits immobilization of resins of Ionic Exchange contaminated by Barium 153, Cesium 137, Europium 152, Cobalt 60 and Manganese 54 generated from the nuclear reactor TRIGA Mark III. Ionic interchange contaminated resin must be immobilized and is analysed under different established tests by the Mexican Official Standard NOM-019-NUCL-1995 {sup L}ow level radioactive wastes package requirements for its near-surface final disposal. Immobilization of ionic interchange contaminated resins must count with the International Standards applicable in this process; in these standards, the following test must be taken in prototype examples: Free-standing water, leachability, compressive strength, biodegradation, radiation stability, thermal stability and burning rate. (Author)

  5. Dose measurement received by the exposed occupationally personnel of the nuclear medicine department of the INCan; Medicion de dosis recibida por el personal ocupacionalmente expuesto del departamento de medicina nuclear del INCan

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez U, N. A.

    2011-07-01

    Personal dose equivalent (PDE) values were determined for occupational exposed workers (OEW) at the Nuclear Medicine Department (NMD) of Instituto Nacional de Cancerologia (INCan), Mexico, using TLD-100 thermoluminescent dosemeters. OEW at NMD, INCan make use of radiopharmaceuticals for diagnosis and treatment of diseases. Radionuclides associated to a pharmaceutical compound used at this Department are {sup 131}I, {sup 18}F, {sup 67}Ga, {sup 99m}Tc, {sup 111}In and {sup 201}Tl with main gamma emission energies between 93 and 511 keV. Dosemeter calibration was performed at the metrology department of Instituto Nacional de Investigaciones Nucleares, Mexico. Every occupational worker used dark containers with three dosemeters which were replaced monthly for a total of 5 periods. Additionally, control dosemeters were also placed at a site free of radioactive sources in order to determine the background radiation. Results were adjusted to find PDE/day and estimating annual PDE values in the range between 2 mSv (background) and a maximum of 9 mSv. Two of the 16 members of the OEW receive high estimated annual doses (6-9 mSv), other 5 receive annual doses between 3 and 5 mSv, other 3 between 2.5 and 3 mSv, and the rest receive dose values consistent with background radiation. These values are dependent on their daily activities and it is clear that the maximum doses are received by those OEW who perform nursing duties and receive radiopharmaceuticals for daily use. All obtained values are well within the established annual OEW dose limit stated in the General Regulation of Radiological Protection, Mexico (50 mSv) as well as within the lower limit recommended by the International Commission on Radiation Protection, report no. 60 (20 mSv). Additionally, consistence was found between measured monthly values and those reported by the firm that performs the monthly service. These results verify the adequate compliance of the NMD at INCan, Mexico with the standards given by

  6. Implementation of the kinetics in the transport code AZTRAN; Implementacion de la cinetica en el codigo de transporte AZTRAN

    Energy Technology Data Exchange (ETDEWEB)

    Duran G, J. A.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, San Pedro Zacatenco, 07738 Ciudad de Mexico (Mexico); Gomez T, A. M., E-mail: redfield1290@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    This paper shows the implementation of the time dependence in the three-dimensional transport code AZTRAN (AZtlan TRANsport), which belongs to the AZTLAN platform, for the analysis of nuclear reactors (currently under development). The AZTRAN code with this implementation is able to numerically solve the time-dependent transport equation in XYZ geometry, for several energy groups, using the discrete ordinate method S{sub n} for the discretization of the angular variable, the nodal method RTN-0 for spatial discretization and method 0 for discretization in time. Initially, the code only solved the neutrons transport equation in steady state, so the implementation of the temporal part was made integrating the neutrons transport equation with respect to time and balance equations corresponding to the concentrations of delayed neutron precursors, for which method 0 was applied. After having directly implemented code kinetics, the improved quasi-static method was implemented, which is a tool for reducing computation time, where the angular flow is factored by the product of two functions called shape function and amplitude function, where the first is calculated for long time steps, called macro-steps and the second is resolved for small time steps called micro-steps. In the new version of AZTRAN several Benchmark problems that were taken from the literature were simulated, the problems used are of two and three dimensions which allowed corroborating the accuracy and stability of the code, showing in general in the reference tests a good behavior. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  8. ESTRUCTURA TRIDIMENSIONAL DEL a-CICLOPROPIL- (p-METOXIFENIL-5-PIRIMIDINMETANOL (ANCIMIDOL UTILIZANDO EL MÉTODO DE RESONANCIA MAGNÉTICA NUCLEAR

    Directory of Open Access Journals (Sweden)

    O. Ospina

    2005-12-01

    Full Text Available El Ancimidol, α-ciclopropil-(p-metoxifenil-5-pirimidinmetanol, (C15H16N2O2 es un regulador de crecimiento vegetal sintético, que hace parte del grupo de compuestos heterocíclicos que contienen nitrógeno que inhiben la síntesis de las giberelinas. La estructura de esta molécula se determinó por resonancia magnética nuclear, partiendo de una solución en cloroformo deuterado (CDCl3, utilizando un espectrómetro de 500MHz (campo de 11.7Teslas. Se tomaron espectros unidimensionales RMN 1H, RMN 13C, pruebas DEPT 45, 90 y 135 y espectros bidimensionales HMBC y HMQC. En la estructura obtenida para el Ancimidol, se observaron tres ciclos como son la pirimidina, el metoxifenilo y el ciclopropilo, identi-ficados por la asignación de los átomos de hidrógeno y de carbono y por las relaciones de conectividad dadas por los espectros bidimensionales HMBC y HMQC.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-10-15

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

  10. Evaluación y estandarización del análisis por activación neutrónica según el método del k-sub cero en el reactor nuclear RP-10: Estudio preliminar empleando irradiaciones cortas

    OpenAIRE

    Montoya Rossi, Eduardo Haroldo

    1995-01-01

    Se ha estandarizado una posición de irradiación del reactor nuclear RP-10 para el uso del análisis por activación neutrónica según el método del k sub cero, empleando la convención de Högdahl y se ha evaluado el comportamiento de dicho método respecto a la exactitud y precisión de los resultados obtenidos en el análisis multielemental cuantitativo de diversos materiales certificados de referencia. Para comprobar que el método analítico se encuentra totalmente bajo control estadístico, se ha e...

  11. Evaluation of Computational Fluids Dynamics (CFD) code Open FOAM in the study of the pressurized thermal stress of PWR reactors. Comparison with the commercial code Ansys-CFX; Evaluacion del codigo de Dinamica de Fluidos Computacional (CFD) Open FOAM en el estudio del estres termico presurizado de los reactores PWR. Comparacion con el codigo comercial Ansys-CFX

    Energy Technology Data Exchange (ETDEWEB)

    Martinez, M.; Barrachina, T.; Miro, R.; Verdu Martin, G.; Chiva, S.

    2012-07-01

    In this work is proposed to evaluate the potential of the OpenFOAM code for the simulation of typical fluid flows in reactors PWR, in particular for the study of pressurized thermal stress. Test T1-1 has been simulated , within the OECD ROSA project, with the objective of evaluating the performance of the code OpenFOAM and models of turbulence that has implemented to capture the effect of the thrust forces in the case study.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-12-31

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

  13. Preparation of mandatory documentation before the start up of the RA-0 `zero power` nuclear reactor at Cordoba National University; Preparacion de la documentacion mandatoria para la puesta en marcha del reactor nuclear RA-0 en la Universidad Nacional de Cordoba

    Energy Technology Data Exchange (ETDEWEB)

    Martin, H R; Keil, W M; Pezzi, N

    1992-12-31

    Before the start up of the RA-0 `zero power` nuclear reactor installed at Cordoba National University, it was necessary to send to the Regulatory Authority the mandatory documentation which is required in the licensing process. With the previous papers existing for the operation in the first years of the `70, a work program for the future operational training personnel was elaborated. Based on the Authority`s applicable rules and the recommendations and with particular criteria originated in the working university conditions, the SAFETY report of RA-0 nuclear reactor was prepared. This paper describes the principal contents, items and documents involved in the safety report. (Author). [Espanol] Con motivo de la nueva puesta en servicio del REACTOR NUCLEAR RA-0 fue necesario elaborar la documentacion mandatoria requerida por la Autoridad Regulatoria Nacional. Siguiendo los lineamientos de las normas y recomendaciones vigentes e incluyendo criterios propios en lo que debia ser el contenido final de dicha documentacion, fue preparado lo que se ha denominado el INFORME DE SEGURIDAD DEL REACTOR NUCLEAR RA-0. Este documento que se describe en este trabajo, si bien contiene las habituales descripciones de todos los Informes de Seguridad, incluye otros aspectos que no siendo requeridos expresamente en el mismo, han dado una mayor coherencia a la conformacion de todos los aspectos que interrelacionan las areas de seguridad fisica, radiologica, nuclear y de control de materiales nucleares bajo salvaguardias. (Autor).

  14. Peces del Noroeste del Ecuador

    OpenAIRE

    Barriga, Ramiro

    1994-01-01

    La ictiofauna del occidente del Ecuador es poco conocida. Los peces del noroccidente son diferentes a los del suroccidente del Ecuador. 34 familias y 82 especies fueron colectadas que equivale al 11 % de las especies de peces continentales registradas en el Ecuador. Icteogeográficamente se sabe que la costa ecuatoriana posee dos provincias: la del Pacifico Norte y la del Guayas, se determinó que el límite de las dos provincias es el río Santiago ya que las especies del mencionado río so...

  15. Co-operation Agreement. The Text of the Agreement of 25 May 1998 between the International Atomic Energy Agency and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials; Acuerdo de Cooperacion. Texto del Acuerdo de 25 de Mayo de 1998 entre el Organismo Internacional de Energia Atomica y la Agencia Brasileno-Argentina de Contabilidad y Control de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-30

    The text of the Co-operation Agreement between the International Atomic Energy Agency and the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials is reproduced herein for the information of all Members. The Agreement entered into force on 25 May 1998, pursuant to Article 8 [Spanish] El texto del Acuerdo de Cooperacion entre el Organismo Internacional de Energia Atomica y la Agencia Brasileno-Argentina de Contabilidad y Control de Materiales Nucleares se reproduce en el presente documento para informacion de todos los Miembros. El Acuerdo entro en vigor el 25 de mayo de 1998 en conformidad con lo dispuesto en el articulo 8.

  16. The Text of the Agreement between Belgium, Denmark, the Federal Republic of Germany, Ireland, Italy, Luxembourg, The Netherlands, the European Atomic Energy Community and the Agency in Connection with the Treaty on the Non-Proliferation of Nuclear Weapons; Texto del Acuerdo Concertado Entre Belgica, Dinamarca, La Republica Federal De Alemania, Irlanda, Italia, Luxemburgo, Los Paises Bajos, La Comunidad Europea De Energia Ato Mica Y El Organismo En Relacion Con El Tratado Sobre La No Proliferacion De Las Armas Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-09-14

    The text of the Agreement, and of the Protocol thereto, between Belgium, Denmark, the Federal Republic of Germany, Ireland, Italy, Luxembourg, The Netherlands, the European Atomic Energy Community and the Agency in implementation of Article III (1) and (4) of the Treaty on the Non-Proliferation of Nuclear Weapons (reproduced in document INFCIRC/140) is reproduced in this document for the information of all Members [Spanish] Para informacion de todos los Estados Miembros, en el presente documento se transcribe el texto del Acuerdo concertado entre Belgica, Dinamarca, la Republica Federal de Alemania, Irlanda, Italia, Luxemburgo, los Paises Bajos, la Comunidad Europea de Energia Atomica y el Organismo en ejecucion de lo dispuesto en los parrafos 1 y 4 del articulo III del Tratado sobre la no proliferacion de las armas nucleares, asi como el del Protocolo que acompana a dicho Acuerdo.

  17. Pertinencia de la gammagrafía de tiroides en un servicio de medicina nuclear de referencia del oriente colombiano / Pertinence of Thyroid Scan in a Nuclear Medicine Department in Eastern Colombia / Relevância da cintilografia da tireóide em um centro de referência de medicina nuclear no leste colombiano

    Directory of Open Access Journals (Sweden)

    Liset Sánchez-Ordúz, MD.

    2015-03-01

    Full Text Available Introducción: La gammagrafía de tiroides es un examen frecuentemente empleado en el estudio de la enfermedad tiroidea. Se recomienda su realización en el paciente con tirotoxicosis, nódulo tiroideo con citología indeterminada y en la búsqueda de tiroides ectópica. Objetivo: Determinar la pertinencia de la solicitud de la gammagrafía tiroidea en un servicio de medicina nuclear de referencia del oriente colombiano. Metodología: Estudio observacional, corte transversal retrospectivo tipo descriptivo. Se evaluaron las gammagrafías de tiroides realizadas en la unidad de medicina nuclear de la clínica Carlos Ardila Lulle durante 3 meses consecutivos que en la hoja de solicitud incluyeran todas las variables de interés. Se registró la indicación del estudio, formación académica del médico que solicitaba el examen, sexo del paciente, presencia concomitante de TSH con su valor respectivo y el consumo de levotiroxina previo al examen. Adicionalmente se registró el resultado gammagráfico. Resultados: 277 gammagrafías fueron analizadas, 244 (88% eran mujeres. EL 67% no estaban correctamente indicadas y de estas el 32% de los pacientes estaban recibiendo suplencia hormonal, la cual fue suspendida 25 días antes de la realización del examen. Los médicos generales y médicos especialistas no endocrinólogos tienen la probabilidad de 9.08 veces y 9.37 veces respectivamente de no indicar adecuadamente la gammagrafía tiroidea respecto a los médicos endocrinólogos. Conclusiones: Dos de cada 3 gammagrafías tiroideas que se realizaron en un servicio de medicina nuclear de referencia del oriente colombiano no están adecuadamente indicadas, teniendo esto un impacto en la salud pública. [Sánchez-Orduz L, Wandurraga-Sánchez EA, García RE, Camacho PA. Pertinencia de la gammagrafía de tiroides en un servicio de medicina nuclear de referencia del oriente colombiano. MedUNAB 2015; 17(3: xx-xx]. Introduction: Thyroid scan is a test frequently

  18. Translation of the model plant of the CN code TRAC-BF1 Cofrentes of a SNAP-TRACE; Traduccion del modelo de planta de CN Cofrentes del codigo TRAC-BF1 a SNAP-TRACE

    Energy Technology Data Exchange (ETDEWEB)

    Escriva, A.; Munuz-Cobo, J. L.; Concejal, A.; Melara, J.; Albendea, M.

    2012-07-01

    It aims to develop a three-dimensional model of the CN Cofrentes whose consistent results Compared with those in current use programs (TRAC-BFl, RETRAN) validated with data of the plant. This comparison should be done globally and that you can not carry a compensation of errors. To check the correct translation of the results obtained have been compared with TRACE and the programs currently in use and the relevant adjustments have been made, taking into account that both the correlations and models are different codes. During the completion of this work we have detected several errors that must be corrected in future versions of these tools.

  19. Optimization of the Penelope code in F language for the simulation of the X-ray spectrum in radiodiagnosis; Optimizacion del codigo PENELOPE en lenguage F para la simulacion del espectro de rayos X en radiodiagnostico

    Energy Technology Data Exchange (ETDEWEB)

    Ballon P, C. I.; Quispe V, N. Y.; Vega R, J. L. J., E-mail: cballon@scifreelancer.com [Universidad Nacional de San Agustin de Arequipa, Av. Independencia s/n, 04000 Arequipa (Peru)

    2017-10-15

    The computational simulation to obtain the X-ray spectrum in the range of radio-diagnosis, allows a study and advance knowledge of the transport process of X-rays in the interaction with matter using the Monte Carlo method. With the obtaining of the X-ray spectra we can know the dose that the patient receives when he undergoes a radiographic study or CT, improving the quality of the obtained image. The objective of the present work was to implement and optimize the open source Penelope (Monte Carlo code for the simulation of the transport of electrons and photons in the matter) 2008 version programming extra code in functional language F, managing to double the processing speed, thus reducing the simulation time spent and errors when optimizing the software initially programmed in Fortran 77. The results were compared with those of Penelope, obtaining a good concordance. We also simulated the obtaining of a Pdd curve (depth dose profile) for a Theratron Equinox cobalt-60 teletherapy device, also validating the software implemented for high energies. (Author)

  20. Estatus de parámetros oxidativos y del gen p53 en sangre de niños en edad escolar de zonas afectadas por el accidente nuclear de Chernobyl.

    OpenAIRE

    García Mora, Mª Carmen

    2004-01-01

    RESUMEN Tras el accidente nuclear de Chernobyl producido el 26 de abril de 1986 se liberaron muchos radioisótopos, produciendo la contaminación del medio ambiente, con la consiguiente implicación sobre la salud de las personas afectadas. La irradiación produce su efecto sobre el material biológico de manera directa, como consecuencia inmediata de la ionización inducida por la irradiación y de manera indirecta, que al interaccionar sobre cualquier estructura celular, esencialmente el agua t...

  1. Simulación del efecto producido por una catarata nuclear sobre la calidad óptica de un ojo sano

    OpenAIRE

    Martínez Moro, Marta

    2014-01-01

    En Oftalmología, se conoce como catarata a la opacificación parcial o total del cristalino. El cristalino es una de las partes del ojo que normalmente es transparente y que actúa como una lente en una cámara, enfocando la luz a medida que ésta pasa hasta la parte posterior del ojo. Entre sus características, se encuentra la capacidad de modificar su curvatura y espesor mediante el proceso de acomodación para enfocar objetos cercanos y lejanos y verlos con mayor claridad. El cristalino está...

  2. Simulación con el código MCNP del reactor nuclear RP-10 en su configuración #14, BOC

    OpenAIRE

    Lázaro, Gerardo; Parreño, Fernando

    2001-01-01

    Se presenta los resultados de exceso de reactividad del núcleo del reactor RP-10 en su configuración 14. Este exceso de reactividad ha sido calculado con MCNP4B con un modelo que describe en detalle las características de los elementos combustibles normales y de control, así como de cada elemento que constituye la configuración de trabajo #14. Este modelo fue previamente utilizado en el reactor RP-0 y ha sido aplicado en la configuración de arranque para el cálculo del exceso de reactividad y...

  3. Public opinion about nuclear energy is in a change process: we have moved from opposition to the consideration; La opinion publica sobre la energia nuclear esta en proceso de cambio: hemos pasado del rechazo a la consideracion

    Energy Technology Data Exchange (ETDEWEB)

    Nunez, P.

    2012-07-01

    The nuclear sector in Spain is making huge affords towards improving public acceptance. the common trend is rigorous and professional diffusion and information regarding nuclear issues. The goal, besides informing on the excellent results and impeccable performance of nuclear power plants, is for effective communication to offer society information on current activities. (Author)

  4. Communication Received from the Permanent Mission of Brazil regarding Certain Member States' Guidelines for the Export of Nuclear Material, Equipment and Technology; Comunicacion recibida de la Mision Permanente del Brasil relativa a las directrices de ciertos Estados Miembros para la exportacion de materiales, equipos y tecnologia nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-16

    The Agency has received a Note Verbale from the Permanent Mission of Brazil, dated 22 March 2007, in which it requests that the Agency circulate to all Member States a letter of 12 December 2006 from the Chairman of the Nuclear Suppliers Group, Ambassador Jose Artur Denot Medeiros, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, providing further information on those Governments' Guidelines for Nuclear Transfers [Spanish] El Organismo ha recibido una nota verbal de la Mision Permanente del Brasil, de fecha 22 de marzo de 2007, en la que le solicita que distribuya a todos los Estados Miembros una carta de 12 de diciembre de 2006 enviada al Director General por el Presidente del Grupo de Suministradores Nucleares, el Embajador Jose Artur Denot Medeiros, en nombre de los Gobiernos de Alemania, Argentina, Australia, Austria, Belarus, Belgica, Brasil, Bulgaria, Canada, Croacia, China, Chipre, Dinamarca, Eslovaquia, Eslovenia, Espana, Estados Unidos de America, Estonia, Federacion de Rusia, Finlandia, Francia, Grecia, Hungria, Irlanda, Italia, Japon, Kazajstan, Letonia, Lituania, Luxemburgo, Malta, Noruega, Nueva Zelandia, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Republica Checa, Republica de Corea, Rumania, Sudafrica, Suecia, Suiza, Turquia y Ucrania, por la que se proporciona mas informacion sobre las Directrices de esos Gobiernos para las transferencias nucleares.

  5. Radiation protection requirements necessary for the introduction of the Ga-68 in a Nuclear Medicine Service; Requisitos de protección radiológica necesarios para la introducción del Ga-68 en un Servicio de Medicina Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Campayo, G.; Ibáñez-Roselló, B.; Reinado, D.; Verdú, G.

    2016-07-01

    The new diagnostic technique that use Ga-68 entail a radiation safety review in nuclear medicine service. It will be evaluate the exposure risk of the workers, who actually are exposed to dose associated to labeled radiopharmaceuticals with F-18, and are estimated the risks due to radiopharmaceuticals with Ga-68. A barrier check-up is made in the current location and an increase of dose rate is estimated with the introduction of Ga-68. Two studies have been done, exposure risk and barrier check-up, in a particular installation. The results obtained conclude that the introduction of Ga-68 in a nuclear medicine service is possible taking into account the minimal modifications in the installation. However, the related modifications have to be studied for each different installation. [Spanish] Las nuevas técnicas diagnósticas que hacen uso del Ga-68 implica la revisión de aspectos de protección radiológica en un servicio de medicina nuclear. Se evalúa el riesgo de exposición de los trabajadores, que en la actualidad están expuestos a los riesgos asociados a los radiofármacos marcados con F-18, y se estiman los debidos a radiofármacos con Ga-68. Se realiza una verificación de barreras en la situación actual y se estima el aumento de la tasa de dosis con la introducción del Ga-68. Se han aplicado ambos estudios, de riesgo de exposición y de verificación de barreras, a una instalación concreta. Los resultados obtenidos concluyen que la introducción del Ga-68 en un servicio de medicina nuclear es posible teniendo en cuenta unas modificaciones mínimas de la instalación. No obstante, las modificaciones aplicables deben ser estudiadas para cada instalación concreta.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-06-22

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

  7. Communications Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Materials, Software and Related Technology; Comunicaciones recibidas de diversos Estados Miembros relativas a las directrices para las transferencias de equipos, materiales y programas informaticos (software) de doble uso del ambito nuclear y tecnologia relacionada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-11

    The Director General of the International Atomic Energy Agency has received Notes Verbales, dated 1 December 2005, from the Resident Representatives to the Agency of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, Croatia, Czech Republic, Estonia, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Latvia, Lithuania, Luxembourg, Malta, the Netherlands, New Zealand, Poland, Portugal, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, relating to transfers of nuclear-related dual-use equipment, materials, software and related technology [Spanish] El Director General del Organismo Internacional de Energia Atomica ha recibido Notas verbales de fecha 1 de diciembre de 2005 de los Representantes Permanentes ante el Organismo de Alemania, Argentina, Australia, Austria, Belarus, Belgica, Brasil, Bulgaria, Canada, Croacia, Eslovenia, Espana, Estados Unidos de America, Estonia, Finlandia, Francia, Grecia, Hungria, Irlanda, Italia, Japon, Letonia, Lituania, Luxemburgo, Malta, Nueva Zelandia, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Republica Checa, Republica de Corea, Sudafrica, Suecia, Suiza, Turquia y Ucrania relativas a las transferencias de equipos, materiales y programas informaticos de doble uso del ambito nuclear y tecnologia relacionada.

  8. Hydrocortisone fails to abolish NF-κB1 protein nuclear translocation in deletion allele carriers of the NFKB1 promoter polymorphism (-94ins/delATTG and is associated with increased 30-day mortality in septic shock.

    Directory of Open Access Journals (Sweden)

    Simon T Schäfer

    Full Text Available BACKGROUND: Previous investigations and meta-analyses on the effect of glucocorticoids on mortality in septic shock revealed mixed results. This heterogeneity might be evoked by genetic variations. Such candidate is a promoter polymorphism (-94ins/delATTG of the gene encoding the ubiquitous transcription-factor nuclear-factor-κB (NF-κB which binds to recognition elements in the promoter of several genes encoding for the innate immune-system. In turn, hydrocortisone inhibits NF-κB nuclear translocation and thus transcription of key immune-response regulators. Accordingly, we tested the hypotheses that hydrocortisone has a NFKB1 genotype dependent effect on 1 NF-κB1 nuclear translocation evoked by lipopolysaccharide (LPS in monocytes in vitro, and 2 mortality in septic shock. METHODS: Monocytes of volunteers with the homozygous insertion (II; n = 5 or deletion (DD; n = 6 NFKB1 genotype were incubated with 10 µgml-1 LPS ± hydrocortisone (10-5M, and NF-κB1 nuclear translocation was assessed (immunofluorescence. Furthermore, we analyzed 30-day-mortality in 160 patients with septic shock stratified for both genotype and hydrocortisone therapy. RESULTS: Hydrocortisone inhibited LPS induced nuclear translocation of NF-κB1 in II (25%±11;p = 0.0001 but not in DD genotypes (51%±15;p = n.s.. Onehundredandfour of 160 patients with septic shock received hydrocortisone, at the discretion of the intensivist. NFKB1 deletion allele carriers (ID/DD receiving hydrocortisone had a much greater 30-day-mortality (57.6% than II genotypes (24.4%; HR:3.18, 95%-CI:1.61-6.28;p = 0.001. In contrast, 30-day mortality was 22.2% in ID/DD and 25.0% in II genotypes without hydrocortisone therapy. Results were similar when using propensity score matching to account for possible bias in the intensivists' decision to administer hydrocortisone. CONCLUSION: Hydrocortisone fails to inhibit LPS induced nuclear NF-κB1 translocation in deletion allele

  9. Hydrocortisone Fails to Abolish NF-κB1 Protein Nuclear Translocation in Deletion Allele Carriers of the NFKB1 Promoter Polymorphism (-94ins/delATTG) and Is Associated with Increased 30-Day Mortality in Septic Shock

    Science.gov (United States)

    Schäfer, Simon T.; Gessner, Sophia; Scherag, André; Rump, Katharina; Frey, Ulrich H.; Siffert, Winfried; Westendorf, Astrid M.; Steinmann, Jörg; Peters, Jürgen; Adamzik, Michael

    2014-01-01

    Background Previous investigations and meta-analyses on the effect of glucocorticoids on mortality in septic shock revealed mixed results. This heterogeneity might be evoked by genetic variations. Such candidate is a promoter polymorphism (-94ins/delATTG) of the gene encoding the ubiquitous transcription-factor nuclear-factor-κB (NF-κB) which binds to recognition elements in the promoter of several genes encoding for the innate immune-system. In turn, hydrocortisone inhibits NF-κB nuclear translocation and thus transcription of key immune-response regulators. Accordingly, we tested the hypotheses that hydrocortisone has a NFKB1 genotype dependent effect on 1) NF-κB1 nuclear translocation evoked by lipopolysaccharide (LPS) in monocytes in vitro, and 2) mortality in septic shock. Methods Monocytes of volunteers with the homozygous insertion (II; n = 5) or deletion (DD; n = 6) NFKB1 genotype were incubated with 10 µgml-1 LPS ± hydrocortisone (10-5M), and NF-κB1 nuclear translocation was assessed (immunofluorescence). Furthermore, we analyzed 30-day-mortality in 160 patients with septic shock stratified for both genotype and hydrocortisone therapy. Results Hydrocortisone inhibited LPS induced nuclear translocation of NF-κB1 in II (25%±11;p = 0.0001) but not in DD genotypes (51%±15;p = n.s.). Onehundredandfour of 160 patients with septic shock received hydrocortisone, at the discretion of the intensivist. NFKB1 deletion allele carriers (ID/DD) receiving hydrocortisone had a much greater 30-day-mortality (57.6%) than II genotypes (24.4%; HR:3.18, 95%-CI:1.61-6.28;p = 0.001). In contrast, 30-day mortality was 22.2% in ID/DD and 25.0% in II genotypes without hydrocortisone therapy. Results were similar when using propensity score matching to account for possible bias in the intensivists' decision to administer hydrocortisone. Conclusion Hydrocortisone fails to inhibit LPS induced nuclear NF-κB1 translocation in deletion allele carriers of the

  10. Objective and Essential Elements of a State's Nuclear Security Regime. Nuclear Security Fundamentals (Spanish Edition); Objetivo y elementos esenciales del régimen de seguridad física nuclear de un Estado. Nociones fundamentales de seguridad física nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-10-15

    The possibility that nuclear material or other radioactive material could be used for criminal purposes or intentionally used in an unauthorized manner cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to respond effectively to nuclear security events. States have agreed to strengthen existing instruments and have established new international legal instruments to enhance nuclear security worldwide. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear material or other radioactive material is used or transported. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its Nuclear Security Series, the IAEA aims to assist States in implementing and sustaining such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises: Nuclear Security Fundamentals, which include the objeurity Fundamentals, which include the objective and essential elements of a State's nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance. Each State carries the full responsibility for nuclear security. Specifically, each State has the responsibility to provide for the security of nuclear material and other radioactive material and their associated facilities and activities; to ensure the security of such material in use, storage, or in transport; to combat illicit

  11. Communication of 2 June 2009 received from the Permanent Mission of the United Kingdom regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material; Comunicacion de fecha 2 de junio de 2009 recibida de la Mision Permanente del Reino Unido en relacion con la exportacion de materiales nucleares y de determinadas categorias de equipo y otros materiales

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-31

    The Director General has received a note ver bale from the Permanent Mission of the United Kingdom, dated 2 June 2009, in which it requests that the Agency circulate to all Member States a letter of 28 May 2009 from the Chairman of the Zangger Committee, Mr. Pavel Klucky, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, China, Croatia, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Kazakhstan, the Republic of Korea, Luxemburg, the Netherlands, Norway, Poland, Portugal, Romania, the Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom and the United States of America, concerning a number of corrections to the communication regarding the export of nuclear material and of certain categories of equipment and other material published in INFCIRC/209/Rev.2 [Spanish] El Director General ha recibido una nota verbal de la Mision Permanente del Reino Unido, de fecha 2 de junio de 2009, en la que se pide que el Organismo distribuya a todos los Estados Miembros una carta de fecha 28 de mayo de 2009 del Presidente del Comite Zangger, Sr. Pavel Klucky, en nombre de los Gobiernos de Alemania, Argentina, Australia, Austria, Belgica, Bulgaria, Canada, China, Corea (Republica de), Croacia, Dinamarca, Eslovaquia, Eslovenia, Espana, Estados Unidos de America, Federacion de Rusia, Finlandia, Francia, Grecia, Hungria, Irlanda, Italia, Japon, Kazajstan, Luxemburgo, Noruega, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Rumania, Sudafrica, Suecia, Suiza, Turquia y Ucrania, en relacion con varias correcciones hechas a la comunicacion referente a la exportacion de materiales nucleares y de determinadas categorias de equipo y otros materiales publicadas en el documento INFCIRC/209/Rev.2.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1974-12-17

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

  13. Knowledge Management Seminar on Nuclear Sector at UPM, an initiative of the IAEA; Seminario de Gestion del Conocimiento en el Sector Nuclear en la UPM, una iniciativa de la IAEA

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, G.; Minguez, E.; Sbaffoni, M.

    2012-07-01

    Nuclear technology, developed over fifty years of knowledge, comprises many disciplines such as mechanical engineering, nuclear physics, automation, etc. During the operational experience of current reactors has developed a great knowledge that needs to be managed properly so present and future generations can enjoy this technology.

  14. Decree 212/80 11/4/80 Nuclear politic of the Uruguay eastern Republic; Decreto 212/80 11/4/80 Politica Nuclear de la Republica Oriental del Uruguay

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-07-01

    The ordinance 212 of the year 1980 incorporate the science and nuclear technology to the activities techniques scientific and industrials to contribute by means of their application to reach the objectives of economic and social development . It is also included general objective of the political nuclear, lines to reach this objective.

  15. TL dosimetry in the new Tandetron ion accelerator site of the National Institute of Nuclear Research (ININ); Dosimetria TL en el area del nuevo acelerador de iones Tandetron del ININ

    Energy Technology Data Exchange (ETDEWEB)

    Valdovinos A, M.; Gonzalez M, P.R. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    The National Institute of Nuclear Research (ININ) acquired a positive ions accelerator type Tandetron 2 MV of the dutch company High Voltage Engineering, Europe B.V., which was finished its installation this year (2000) in an already existing building in the Dr. Nabor Carrillo Flores Nuclear Centre, where it was prepared for the following purposes: the accelerator will be used to realize research through X-ray emission induced by charged particles, Rutherford backscattering analysis, nuclear reaction analysis, gamma ray emission induced by charged particles, resonant dispersion analysis, elastic backward detection analysis and by particle canalization analysis. The accelerator consists of an injection system with two ion sources, ion accelerator tank with voltage in terminal at 2 MV, recovery and recirculation system of charge interchange gas, iman selector analyzer system and with high energy focussing, control system through computer and management and recovery of isolator gas system. For the realization of operation tests of this accelerator, it was had the license authorizing by the National Commission of Nuclear Safety and Safeguards (CNSNS). During the test stage Tl dosemeters were arranged in the Tandetron accelerator area, and also in direction to the beam outlet. In this work, are presented the obtained results of the measurement of radiation levels, as in the area as in the beam outlet. (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

    Directory of Open Access Journals (Sweden)

    Sophie Prunier-Poulmaire

    2011-12-01

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

  17. Uncertainty analysis for results of thermal hydraulic codes of best-estimate-type; Analisis de incertidumbre para resultados de codigos termohidraulicos de mejor estimacion

    Energy Technology Data Exchange (ETDEWEB)

    Alva N, J.

    2010-07-01

    In this thesis, some fundamental knowledge is presented about uncertainty analysis and about diverse methodologies applied in the study of nuclear power plant transient event analysis, particularly related to thermal hydraulics phenomena. These concepts and methodologies mentioned in this work come from a wide bibliographical research in the nuclear power subject. Methodologies for uncertainty analysis have been developed by quite diverse institutions, and they have been widely used worldwide for application to results from best-estimate-type computer codes in nuclear reactor thermal hydraulics and safety analysis. Also, the main uncertainty sources, types of uncertainties, and aspects related to best estimate modeling and methods are introduced. Once the main bases of uncertainty analysis have been set, and some of the known methodologies have been introduced, it is presented in detail the CSAU methodology, which will be applied in the analyses. The main objective of this thesis is to compare the results of an uncertainty and sensibility analysis by using the Response Surface Technique to the application of W ilks formula, apply through a loss coolant experiment and an event of rise in a BWR. Both techniques are options in the part of uncertainty and sensibility analysis of the CSAU methodology, which was developed for the analysis of transients and accidents at nuclear power plants, and it is the base of most of the methodologies used in licensing of nuclear power plants practically everywhere. Finally, the results of applying both techniques are compared and discussed. (Author)

  18. Communication Received from Certain Member States Regarding Guidelines for Transfers of Nuclear-related Dual-use Equipment, Material, Software and Related Technology; Comunicacion recibida de algunos Estados Miembros relativa a las directrices para las transferencias de equipos, materiales y programas informaticos de doble uso del ambito nuclear y tecnologia afin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-12

    The Agency has received a Note Verbale from the Permanent Mission of Hungary, dated 14 June 2010, in which it requests that the Agency circulate to all Member States a letter of 7 May 2010 from the Chairman of the Nuclear Suppliers Group, Ambassador Ms. Gyorgyi Martin Zanathy, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belarus, Belgium, Brazil, Bulgaria, Canada, China, Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Kazakhstan, Republic of Korea, Latvia, Lithuania, Luxemburg, Malta, Netherlands, New Zealand, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America,1 providing further information on those Governments' Guidelines for Nuclear Transfers [Spanish] El Organismo ha recibido una nota verbal de la Mision Permanente de Hungria, de fecha 14 de junio de 2010, en la que le solicita que distribuya a todos los Estados Miembros una carta de 7 de mayo de 2010 enviada al Director General por la Presidenta del Grupo de Suministradores Nucleares, la Sra. Embajadora Gyorgyi Martin Zanathy, en nombre de los Gobiernos de Alemania, Argentina, Australia, Austria, Belarus, Belgica, Brasil, Bulgaria, Canada, China, Chipre, Croacia, Dinamarca, Eslovaquia, Eslovenia, Espana, Estados Unidos de America, Estonia, Federacion de Rusia, Finlandia, Francia, Grecia, Hungria, Irlanda, Islandia, Italia, Japon, Kazajstan, Letonia, Lituania, Luxemburgo, Malta, Noruega, Nueva Zelandia, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Republica Checa, Republica de Corea, Rumania, Sudafrica, Suecia, Suiza, Turquia y Ucrania,1 por la que se proporciona mas informacion sobre las Directrices de esos Gobiernos para las transferencias nucleares.

  19. Nuclear fuel activity with minor actinides after their useful life in a BWR; Actividad del combustible nuclear con actinidos menores despues de su vida util en un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Martinez C, E.; Ramirez S, J. R.; Alonso V, G., E-mail: eduardo.martinez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    Nuclear fuel used in nuclear power reactors has a life cycle, in which it provides energy, at the end of this cycle is withdrawn from the reactor core. This used fuel is known as spent nuclear fuel, a strong problem with this fuel is that when the fuel was irradiated in a nuclear reactor it leaves with an activity of approximately 1.229 x 10{sup 15} Bq. The aim of the transmutation of actinides from spent nuclear fuel is to reduce the activity of high level waste that must be stored in geological repositories and the lifetime of high level waste; these two achievements would reduce the number of necessary repositories, as well as the duration of storage. The present work is aimed at evaluating the activity of a nuclear fuel in which radioactive actinides could be recycled to remove most of the radioactive material, first establishing a reference of actinides production in the standard nuclear fuel of uranium at end of its burning in a BWR, and a fuel rod design containing 6% of actinides in an uranium matrix from the enrichment tails is proposed, then 4 standard uranium fuel rods are replaced by 4 actinide bars to evaluate the production and transmutation of the same, finally the reduction of actinide activity in the fuel is evaluated. (Author)

  20. Precision and accuracy control of dose calibrator: CAPINTEC CRC 12 in laboratory for radiopharmacy of Nuclear Medicine Institute of Sucre, Bolivia; Control de precision y exactitud del calibrador de dosis: CAPINTEC CRC 12 del Laboratorio de Radiofarmacia del Instituto de Medicina Nuclear Sucre

    Energy Technology Data Exchange (ETDEWEB)

    Huanca Sardinas, E; Castro Sacci, O; Torrez Cabero, M; Vasquez Ibanez, M.R; Zambrana Zelada, AJ., E-mail: nuclear_sre@entelnet.bo, E-mail: ehuancasardinas@hotmail.com, E-mail: marcetorrez@hotmail.com, E-mail: maritavas@yahoo.es, E-mail: alfzambrana@gmail.com [Universidad Mayor Real y Pontifica de San Francisco Xavier de Chuquisaca, Sucre (Bolivia, Plurinational State of). Radiofarmacia - Instituto de Medicina Nuclear de Sucre. Hospital Santa Barbara

    2013-11-01

    The dose calibrator is one of the indispensable tools in radiopharmacy laboratories of a nuclear medicine department also is mandated to provide accurate readings. A very high doses produce unnecessary radiation exposure to the patient or a very low dose, prolong the acquisition time of the studies affecting the quality of the image. In the present work we did a retrospective analysis of the results of quality checks performed at precision accuracy of the Gauge CRC12 CAPINTEC dose calibrator over a period of 16 years, using sealed certified sources with low power, medium and high: Ba{sup 133} , Cs{sup 137} , Co{sup 60} and Co{sup 57}. The results showed that the lowest standard deviation value was 0.17 for Ba133, relative to Co{sup 57} of 2.97 in the control of accuracy. Accuracy over control values were also lower standard deviation for Ba{sup 133} 1.00, relative to Co{sup 57} 10.06. Being stated that the CRC12 CAPINTEC activimeter reliability is acceptable during the reporting period and under the conditions indicated. Therefore, we continue to make these quality control procedures and the professional must feel confident that the measurements obtained with it are reliable.

  1. Development of containers sealing system like part of surveillance program of the vessel in nuclear power plants; Desarrollo del sistema de sellado de contenedores como parte del programa de vigilancia de la vasija en nucleoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Romero C, J.; Hernandez C, R.; Fernandez T, F.; Rocamontes A, M.; Perez R, N. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: jesus.romero@inin.gob.mx

    2009-10-15

    The owners of nuclear power plants should be demonstrate that the embrittlement effects by neutronic radiation do not commit the structural integrity from the pressure vessel of nuclear reactors, during conditions of routine operation and below postulate accident. For this reason, there are surveillance programs of vessels of nuclear power plants, in which are present surveillance capsules. A surveillance capsule is compound by the support, six containers for test tubes and dosimeters. The containers for test tubes are of two types: rectangular container for test tubes, Charpy V and Cylindrical Container for tension test tubes. These test tubes are subject to a same or bigger neutronic flow to that of vessel, being representative of vessel mechanical conditions. The test tubes are rehearsed to watch over the increase of embrittlement that presents the vessel. This work describes the development of welding system to seal the containers for test tubes, these should be filled with helium of ultra high purity, to a pressure of an atmosphere. In this system the welding process Gas Tungsten Arc Welding is used, a hermetic camera that allows to place the containers with three grades of freedom, a vacuum subsystem and pressure, high technology equipment's like: power source with integrated computer, arc starter of high frequency, helium flow controller, among others. Finally, the advances in the inspection system for the qualification of sealing system are mentioned, system that should measure the internal pressure of containers and the helium purity inside these. (Author)

  2. Calculation of the neutron flux and fluence in the covering of the nucleus and the vessel of a BWR; Calculo del flujo neutronico y fluencia en la envolvente del nucleo y la vasija de un reactor nuclear BWR

    Energy Technology Data Exchange (ETDEWEB)

    Martinez C, E.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, U. P. Adolfo Lopez Mateos, Col. Lindavista, 07738 Mexico D. F. (Mexico); Longoria G, L. C., E-mail: evalle@esfm.ipn.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2011-11-15

    One of the main objectives related with the safety in any nuclear power plant, including the nuclear power plant of Laguna Verde, is to guarantee the structural integrity of the pressure vessel of the reactor. To identify and quantifying the damage caused be neutron irradiation in the vessel of any nuclear reactor, is necessary to know as much the neutron flux as the fluence that it has been receiving during their time of operation life, since the observables damages by means of tests mechanics are products of micro-structural effects, induced by neutron irradiation, therefore, is important the study and prediction of the neutron flux to have a better knowledge of the damage that are receiving these materials. In our calculation the code DORT was used, which solves the transport equation in discreet coordinates and in two dimensions (x-y, r-{theta} and r-z), in accord to the regulator guide, it requires to make and approach of the neutron flux in three dimensions by means of the Synthesis Method. Whit this method is possible to achieve a representation of the flux in 3D combining or synthesizing the calculated fluxes by DORT code in r-{theta}, r-z and r. In this work the application of the Synthesis Method is presented, according to the Regulator Guide 1.190, to determine the fluxes 3D in the interns of a BWR using three different space meshes. (Author)

  3. Code for the steam tables for pure water in visual basic 6.0.; Un codigo para las tablas de vapor para agua pura en visual basic 6.0

    Energy Technology Data Exchange (ETDEWEB)

    Verma, Mahendra P. [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2002-07-01

    The thermodynamic data of the water are of extreme importance in all of the branches of science and technology; the facilitate the understanding of the natural Earth processes. Nevertheless, for the electrical industry the water plays a very important role during the generation of electrical energy process. Different heat sources such as coal, oil, natural gas, nuclear fuel or the geothermal heat boil the water that forms the steam used to move the turbines. Consequently, the steam tables (the thermodynamic water data) are vital to model thermal and mass transference and physical-chemical processes during the generation of electrical energy. [Spanish] Los datos termodinamicos del agua son de suma importancia en todas las ramas de la ciencia y tecnologia, ellos facilitan el entendimiento de los procesos naturales de la Tierra. Sin embargo, para la industria electrica el agua juega un papel muy importante durante el proceso de generacion de energia electrica. Diferentes fuentes de calor tales como carbon, aceite, gas natural, combustible nuclear o el calor geotermico calientan el agua que forma el vapor utilizado para mover las turbinas. Luego entonces, las tablas de vapor (los datos termodinamicos de agua) son vitales para modelar transferencia termica y de masa y procesos fisico-quimico durante la generacion energia electrica.

  4. Status report about the works for the start up of the RA-0 `zero power` nuclear reactor at the Cordoba National University; Estado actual de avance de las tareas para la nueva puesta en marcha del reactor nuclear RA-0 en la Universidad Nacional de Cordoba

    Energy Technology Data Exchange (ETDEWEB)

    Martin, H R; Carballido, C; Oliveras, T

    1992-12-31

    After two years of works at the Cordoba National University for the new start-up of the RA-0 `zero power` nuclear reactor, the results obtained are herein presented. Starting with practically null infrastructure at the beginning, specially in human resources and instrumentation of the reactor, the objectives can be considered satisfactory. The training in work of the future operational staff, the design and the construction of the instrumentation and the fitting of the installations are the principal items described in this paper. An special attention is devoted to the insertion of this type of installation in the university organization, usually not prepared for the quality and control activities, which is necessarily considered in these type of works. (Author). [Espanol] Luego de aproximadamente dos anos de trabajo para la nueva puesta en marcha del REACTOR NUCLEAR RA-0, se han alcanzado los resultados presentados en este trabajo. Partiendo de una infraestructura practicamente inexistente en cuanto a recursos humanos y estado de las instalaciones, los avances logrados son significativos. Comenzando por la capacitacion y el entrenamiento del futuro personal de operacion y pasando por la adecuacion de los equipos y componentes, hasta la confeccion de la documentacion mandatoria, se muestran los aspectos mas destacables de los trabajos realizados. Una atencion especial se dedica a la insercion de una instalacion de este tipo en el ambito universitario, el cual por sus particulares caracteristicas, ha debido ser tenido en cuenta permanentemente para la futura operacion de las instalaciones. (Autor).

  5. Calculation of dose due to exposure internal in the services of nuclear medicine of Peru; Calculo de dosis debida a la exposicion interna en los servicios de medicina nuclear del Peru

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, S.; Zapata, L.; Cardenas, A.; Velasquez, M.

    2013-07-01

    The objective of this work is to improve the radiation protection of workers occupationally exposed to open source of nuclear medicine services and train those responsible for radiation protection of such installations to carry a comprehensive record of doses. (Author)

  6. Nuclear minerals prospect ion activity report Period 1985-1987-Uranium prospect ion in Uranium; Informe sobre las actividades del Programa de prospeccion de minerales nucleares Periodo 1985 - 1987 Prospeccion de Uranio en el Uruguay

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-07-01

    In framework of Mineral Inventory and Nuclear minerals program in the article has been carried out the following aims: strategic level, synthesis and results reached, evaluation conclusions and trends.

  7. Development of a graphic interface for the Ramona-3B code; Desarrollo de una interfaz grafica para el codigo Ramona-3B

    Energy Technology Data Exchange (ETDEWEB)

    Maldonado D, D.; Santos O, M.A. [Laboratorio de Analisis de Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, Jiutepec, Morelos (Mexico)]. e-mail: chalismx@hotmail.com

    2003-07-01

    In this work a graphic interface that interprets the data of the Ramona-3B code is presented. The Ramona-3B code it is a computer program, that it uses text files as input and its generate output also of this type. The quantity of generated information is so big that always it is necessary to process this information with graphic tools to be able to analyze the results of the simulations of nuclear centrals with boiling water reactors. When having a modern tool that it translates text in graphics in an automatic way and that it is of great versatility, one can obtain a graphic interface that facilitates the interpretation of how a BWR nuclear plant behaves. To achieve this tool the key it has been a program that it reads chains of previously indicated characters that keeps the data in a file for later to manipulate them in the creation of the graphic interface. It is used a software of easy access that resists the processing of a great one quantity of data and that later its have been able to graph. Another important function of this interface it is allowing the modification of the input file for Ramona using graphic unfolding and helps in it lines without necessarily to go to the file with input data. For the design of graphic interface it was decided first to show the more representative variables of a BWR type nuclear plant. It is used Mat lab as platform on several options, as PHP, Lab view or C{sup '}. The obtained graphs allow monitoring the plant and to have the control of selected variables. For the graphic interface only is necessary to indicate it the variable to simulate for to be able to interpret graphically the behavior of the BWR type nuclear plant. This tool is of great utility for the teaching of students that they are interested in this type of nuclear topics. (Author)

  8. PCRELAP5: data calculation program for RELAP 5 code; PCRELAP5: programa de calculo dos dados de entrada para o codigo RELAP5

    Energy Technology Data Exchange (ETDEWEB)

    Silvestre, Larissa Jacome Barros

    2016-07-01

    Nuclear accidents in the world led to the establishment of rigorous criteria and requirements for nuclear power plant operations by the international regulatory bodies. By using specific computer programs, simulations of various accidents and transients likely to occur at any nuclear power plant are required for certifying and licensing a nuclear power plant. Based on this scenario, some sophisticated computational tools have been used such as the Reactor Excursion and Leak Analysis Program (RELAP5), which is the most widely used code for the thermo-hydraulic analysis of accidents and transients in nuclear reactors in Brazil and worldwide. A major difficulty in the simulation by using RELAP5 code is the amount of information required for the simulation of thermal-hydraulic accidents or transients. The preparation of the input data requires a great number of mathematical operations to calculate the geometry of the components. Thus, for those calculations performance and preparation of RELAP5 input data, a friendly mathematical preprocessor was designed. The Visual Basic for Application (VBA) for Microsoft Excel demonstrated to be an effective tool to perform a number of tasks in the development of the program. In order to meet the needs of RELAP5 users, the RELAP5 Calculation Program (Programa de Calculo do RELAP5 - PCRELAP5) was designed. The components of the code were codified; all entry cards including the optional cards of each one have been programmed. In addition, an English version for PCRELAP5 was provided. Furthermore, a friendly design was developed in order to minimize the time of preparation of input data and errors committed by users. In this work, the final version of this preprocessor was successfully applied for Safety Injection System (SIS) of Angra 2. (author)

  9. IAEA Capacity Building in Nuclear Techniques for Environmental Sustainability; Asistencia del OIE A en la creacion de capacidad para el empleo de tecnicas nucleares en aras de la sostenibilidad ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Dixit, Aabha [International Atomic Energy Agency, Division of Public Information, Vienna (Austria)

    2013-09-15

    The IAEA helps Member States use nuclear technology for a broad range of applications: from generating electricity to increasing food production, from fighting cancer to managing freshwater resources and protecting coastal areas and the ocean. Assistance provided through IAEA capacity building projects addresses specific national and regional problems. Expertise in the application of nuclear technology and knowledge of good practices are transferred via training activities, information exchange, coordinated research projects and the technical cooperation programme.

  10. Communication of 10 January 2008 received from the Permanent Mission of the United Kingdom regarding the Export of Nuclear Material and of Certain Categories of Equipment and Other Material; Comunicacion de fecha 10 de enero de 2008 recibida de la Mision Permanente del Reino Unido en relacion con la exportacion de materiales nucleares y de determinadas categorias de equipo y otros materiales

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-02-26

    The Director General has received a note ver bale from the Permanent Mission of the United Kingdom, dated 10 January 2008, in which it requests that the Agency circulate to all Member States a letter of 12 December 2006 from the Chairman of the Zangger Committee, Mr. Pavel Klucky, to the Director General, on behalf of the Governments of Argentina, Australia, Austria, Belgium, Bulgaria, Canada, China, Croatia, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Republic of Korea, Luxemburg, the Netherlands, Norway, Poland, Portugal, Romania, Russian Federation, Slovakia, Slovenia, South Africa, Spain, Sweden, Switzerland, Turkey, Ukraine, the United Kingdom of Great Britain and Northern Ireland and the United States of America, concerning the export of nuclear material and of certain categories of equipment and other material [Spanish] El Director General ha recibido una nota verbal de la Mision Permanente del Reino Unido, de fecha 10 de enero de 2008, en la que se pide que el Organismo distribuya a todos los Estados Miembros una carta de fecha 12 de diciembre de 2006, relativa a la exportacion de materiales nucleares y de determinadas categorias de equipo y otros materiales, dirigida por el Presidente del Comite Zangger, Sr. Pavel Klucky, en nombre de los Gobiernos de Alemania, Argentina, Australia, Austria, Belgica, Bulgaria, Canada, China, Croacia, Dinamarca, Eslovaquia, Eslovenia, Espana, Estados Unidos de America, Federacion de Rusia, Finlandia, Francia, Grecia, Hungria, Irlanda, Italia, Japon, Luxemburgo, Noruega, Paises Bajos, Polonia, Portugal, Reino Unido de Gran Bretana e Irlanda del Norte, Republica Checa, Republica de Corea, Rumania, Sudafrica, Suecia, Suiza, Turquia y Ucrania.

  11. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  12. Potencial del Agua del suelo

    Directory of Open Access Journals (Sweden)

    Bustamante Heliodoro

    1986-12-01

    Full Text Available La energía potencial del agua presenta diferencias de un punto del suelo a otro; esas diferencias son las que originan el movimiento del agua de acuerdo a la tendencia universal de la materia en el sentido de moverse de donde la energía potencial es mayor a donde dicha energía es menor. En el suelo el agua en consecuencia se mueve hacia donde su energía decrece hasta lograr su estado de equilibrio. Se desprende entonces que la cantidad de energía potencial absoluta contenida en el agua, no es importante por sí misma, sino por su relación con la energía en diferentes lugares dentro del suelo. El concepto Potencial de agua del suelo es un criterio para esta energía.

  13. Mathematic preprocessor for RELAP5 code using Microsoft Excel; Pre-processador matematico para o codigo RELAP5 utilizando o Microsoft Excel

    Energy Technology Data Exchange (ETDEWEB)

    Paladino, Patricia Andrea

    2006-07-01

    Computational program are used for thermal hydraulic analysis of accidents and transients conditions in nuclear power plants. The RELAP5 code has been developed to simulate accidents and transients conditions, performing a best estimate analysis, in Pressurized Water Reactors (PWR) and auxiliary systems. The RELAP5 code, which has been used as a toll for licensing nuclear facilities in Brazil, is the objective of the study performed in this work. The main problem in using the RELAP5 code is the huge amount of information necessary to model the nuclear reactor and thus to simulate thermal-hydraulic accidents. Moreover, the RELAP5 code input data requires a large amount of mathematical operations to calculate the geometry of the plant components. Therefore, in order to make easier the data input for the RELAP5 code a friendly preprocessor has been developed. The preprocessor accepts basic information about the geometry of the plant components and performs all the calculations needed for the RELAP5 input. This preprocessor has been developed based on the MS-Excel software. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  15. Contributions of the National Institute of Nuclear Research to the advance of Science and Technology in Mexico. Commemorative edition 2010; Contribuciones del Instituto Nacional de Investigaciones Nucleares al avance de la ciencia y la tecnologia en Mexico. Edicion conmemorativa 2010

    Energy Technology Data Exchange (ETDEWEB)

    Duque M, G.; Jimenez R, M.; Monroy G, F.; Romero H, S.; Serment G, J. (ed.) [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-07-01

    From the second decade of the X X century the applications of the nuclear energy have been important part of the scientific and technological patrimony in Mexico. Records exist with regard to the use of the radioisotopes and the radiations in our country in that time, and in a formal way until the year of 1950, in a process that culminates with the creation of the Comision Nacional de Energia Nuclear (CNEN. January 1, 1956). In January 12, 1972 were published the Organic Law that created to the Instituto Nacional de Energia Nuclear, being responsible for the works that the CNEN developed. The current Instituto Nacional de Investigaciones Nucleares (ININ) was constituted starting from the Regulation Law of the constitutional Article 27 in nuclear matter of January 26, 1979, abrogated and substituted by the Law in force of February 4, 1985. In this lapse they were undertaken multitude of projects with results and diverse achievements. From their creation, the mission of the ININ and the previous institutions has been to realize research in science and nuclear technology, to promote their peaceful uses and to diffuse the achieved advances, always searching for to link them to the economic, social, scientific and technological development of the country. In this occasion with the purpose of participating in the commemoration of the bicentennial of the independence and centennial of the Mexican revolution in our country, the ININ decided to publish this work, directed to a wide public, with the intention of providing a vision the most complete and appropriate possible of the activities in research and technology that it is carries out at the moment. This work also seeks to be a diffusion instrument of the tasks that they are carried out in the institute, in diverse subjects as: the basic research, the nuclear applications in the health, the agriculture and the industry, the studies on the contamination and the environment; the dosimetry; the radiological protection; as

  16. 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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  17. Utilización de la energía nuclear: la percepción del riesgo radiológico del público. Experiencia desde el sector sanitario

    Directory of Open Access Journals (Sweden)

    Leopoldo Arranz y Carrillo de Albornoz

    2010-12-01

    Full Text Available Los riesgos radiológicos están, seguramente por el hecho que las bombas de Hiroshima y Nagasaki sigan formando parte de las pesadillas colectivas de la humanidad, siempre con la espada de Damocles de un posible uso de las armas nucleares, el paradigma de la subjetividad. Y su percepción negativa por parte de los ciudadanos se ha convertido en un momento de creciente interés para los responsables de la gestión y el manejo de cualquiera de las aplicaciones de las radiaciones ionizantes. En este trabajo se expone la opinión de expertos en comunicación cuando se habla de riesgos radiológicos, basándose algunos en su experiencia en el sector sanitario, y lo que se puede hacer para que esa percepción negativa pueda llegar a modificarse.

  18. Analysis of results of AZTRAN and AZKIND codes for a BWR; Analisis de resultados de los codigos AZTRAN y AZKIND para un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Bastida O, G. E.; Vallejo Q, J. A.; Galicia A, J.; Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Xolocostli M, J. V.; Rodriguez H, A.; Gomez T, A. M., E-mail: gbo729@yahoo.com.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    This paper presents an analysis of results obtained from simulations performed with the neutron transport code AZTRAN and the kinetic code of neutron diffusion AZKIND, based on comparisons with models corresponding to a typical BWR, in order to verify the behavior and reliability of the values obtained with said code for its current development. For this, simulations of different geometries were made using validated nuclear codes, such as CASMO, MCNP5 and Serpent. The results obtained are considered adequate since they are comparable with those obtained and reported with other codes, based mainly on the neutron multiplication factor and the power distribution of the same. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  20. 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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  1. Meetings of all the contracting parties of agreements on Nuclear Safety of the IAEA; Las reuniones de todas las partes contratantes de los convenios sobre seguridad nuclear del OIEA

    Energy Technology Data Exchange (ETDEWEB)

    Ripoll Carulla, S.

    2003-07-01

    One of the most original aspects at the Convention on Nuclear Safety was the incorporation of the mechanism for Meetings with Contracting States into Chapter III. This mechanism has become one of the most characteristic elements at the convention, which is usually defined as a motivational convention, due in large part to the actual existence of these meetings. (Author)

  2. Il rischio tecnologico vantaggi e svantaggi del progresso scientifico

    CERN Document Server

    Lewis, H W

    1995-01-01

    I rischi della vita ; misurare il rischio ; la percezione del rischio ; la politica del rischio ; la valutazione del rischio ; la gestione del rischio ; il valore della vita ; qual è il livello "sufficiente" di sicurezza? ; incertezza, causalità, rilevabilità ; le delusioni della cautela ; sostanze chimiche tossiche ; sostanze chimiche cancerogene ; sicurezza sulle autostrade ; trasporto aereo ; radiazioni ionizzanti ; conbustibili fossili ; l'inverno nucleare ; radiazioni non ionizzanti ; quanto basta di statistica e di teoria delle probabilità ; epilogo : cosa significa tutto questo?.

  3. Thermodynamic study of residual heat from a high temperature nuclear reactor to analyze its viability in cogeneration processes; Estudio termodinamico del calor residual de un reactor nuclear de alta temperatura para analizar su viabilidad en procesos de cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

    Santillan R, A.; Valle H, J.; Escalante, J. A., E-mail: santillanaura@gmail.com [Universidad Politecnica Metropolitana de Hidalgo, Boulevard acceso a Tolcayuca 1009, Ex-Hacienda San Javier, 43860 Tolcayuca, Hidalgo (Mexico)

    2015-09-15

    In this paper the thermodynamic study of a nuclear power plant of high temperature at gas turbine (GTHTR300) is presented for estimating the exploitable waste heat in a process of desalination of seawater. One of the most studied and viable sustainable energy for the production of electricity, without the emission of greenhouse gases, is the nuclear energy. The fourth generation nuclear power plants have greater advantages than those currently installed plants; these advantages have to do with security, increased efficiencies and feasibility to be coupled to electrical cogeneration processes. In this paper the thermodynamic study of a nuclear power plant type GTHTR300 is realized, which is selected by greater efficiencies and have optimal conditions for use in electrical cogeneration processes due to high operating temperatures, which are between 700 and 950 degrees Celsius. The aim of the study is to determine the heat losses and the work done at each stage of the system, determining where they are the greatest losses and analyzing in that processes can be taken advantage. Based on the study was appointed that most of the energy losses are in form of heat in the coolers and usually this is emitted into the atmosphere without being used. From the results a process of desalination of seawater as electrical cogeneration process is proposed. This paper contains a brief description of the operation of the nuclear power plant, focusing on operation conditions and thermodynamic characteristics for the implementation of electrical cogeneration process, a thermodynamic analysis based on mass and energy balance was developed. The results allow quantifying the losses of thermal energy and determining the optimal section for coupling of the reactor with the desalination process, seeking to have a great overall efficiency. (Author)

  4. Analysis of the dead layer of a detector of germanium with code ultrapure Monte Carlo SWORD-GEANT; Analisis del dead layer de un detector de germanio ultrapuro con el codigo de Monte Carlo SWORDS-GEANT

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo, S.; Querol, A.; Ortiz, J.; Rodenas, J.; Verdu, G.

    2014-07-01

    In this paper the use of Monte Carlo code SWORD-GEANT is proposed to simulate an ultra pure germanium detector High Purity Germanium detector (HPGe) detector ORTEC specifically GMX40P4, coaxial geometry. (Author)

  5. Optimization of analysis best-estimate of a fuel element BWR with Code STAR-CCM+; Optimizacion del analisis best-estimate de un elemento combustible BWR con el codigo STAR-CCM+

    Energy Technology Data Exchange (ETDEWEB)

    Morgado Canada, E.; Concejal Barmejo, A.; Jimenez Varas, G.; Solar Martinez, A.

    2014-07-01

    The objective of the project is the evaluation of the code STAR-CCM +, as well as the establishment of guidelines and standardized procedures for the discretization of the area of study and the selection of physical models suitable for the simulation of BWR fuel. For this purpose several of BFBT experiments have simulated [1] provide a data base for the development of experiments for measuring distribution of fractions of holes to changes in power in order to find the most appropriate models for the simulation of the problem. (Author)

  6. Modelization Post-test experiment IFA-650.10 HALDEN with FRAP series codes; Modelizacion post-test del experimento HALDEN IFA-650.10 con los codigos de la serie FRAP

    Energy Technology Data Exchange (ETDEWEB)

    Vallejo, I.; Herranz, L. E.

    2013-07-01

    There is a need to review the criteria for security relating to LOCA accidents , including the effect of different materials of pod, as well as conditions of high burned as fuel. In this work is modeled with code FRAPTRAN-1.4 the IFA-650.10 experiment executed in the experimental reactor HALDEN. It is an approximation to the thermo-hydraulic rod-refrigerant and the results are compared with experimental measurements. The thermal behavior shows good agreement with the experimental measures; mechanical parameters are observed light quality deviations in pod and very good quantitative agreement in the maximum elongation; the diameter calculated at the end of the simulation above - predicts the post-irradiation values and oxide presents a good deal.

  7. Generation of the library of neutron cross sections for the Record code of the Fuel Management System (FMS); Generacion de la biblioteca de secciones eficaces de neutrones para el codigo Record del Sistema de Administracion de Combustible (FMS)

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G; Hernandez L, H [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1991-11-15

    On the basis of the library structure of the RECORD code a method to generate the neutron cross sections by means of the ENDF-B/IV database and the NJOY code has been developed. The obtained cross sections are compared with those of the current library which was processed using the ENDF-B/III version. (Author)

  8. Calculation of absorbed doses in sphere volumes around the Mammosite using the Monte Carlo simulation code MCNPX; Calculo de dosis absorbida en volumenes esfericos alrededor del Mammosite utilizando el codigo de simulacion Monte Carlo MCNPX

    Energy Technology Data Exchange (ETDEWEB)

    Rojas C, E. L. [ININ, Carretera Mexico-Toluca s/n, Ocoyoacac 52750, Estado de Mexico (Mexico)

    2008-07-01

    The objective of this study is to investigate the changes observed in the absorbed doses in mammary gland tissue when irradiated with a equipment of high dose rate known as Mammosite and introducing material resources contrary to the tissue that constitutes the mammary gland. The modeling study is performed with the code MCNPX, 2005 version, the equipment and the mammary gland and calculating the absorbed doses in tissue when introduced small volumes of air or calcium in the system. (Author)

  9. Adaptation and implementation of the TRACE code for transient analysis on designs of cooled lead fast reactors; Adaptacion y aplicacion del codigo TRACE para el analisis de transitorios en disenos de reactores rapidos refrigerados por plomo

    Energy Technology Data Exchange (ETDEWEB)

    Lazaro, A.; Ammirabile, L.; Martorell, S.

    2014-07-01

    The article describes the changes implemented in the TRACE code to include thermodynamic tables of liquid lead drawn from experimental results. He then explains the process for developing a thermohydraulic model for the prototype ALFRED and analysis of a selection of representative transient conducted within the framework of international research projects. The study demonstrates the applicability of TRACE code to simulate designs of cooled lead fast reactors and exposes the high safety margins are there in this technology to accommodate the most severe transients identified in their security study. (Author)

  10. Design of the core of a breed/burn fast reactor with the deterministic code KANEXT; Diseno del nucleo de un reactor rapido de cria/quemado con el codigo deterministico KANEXT

    Energy Technology Data Exchange (ETDEWEB)

    Lopez S, R. C.; Francois L, J. L., E-mail: rcarlos.lope@gmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2014-10-15

    The breeding fast reactors are interesting because they generate more plutonium than they consume, however, the fuel has to be reprocessed for the generated plutonium is used in another reactor. In a breed/burn reactor (BBR) the plutonium is generated and used -in situ- inside the same reactor, reducing this way costs and the proliferation possibility. In this work, the core of a BBR was designed; cooled by sodium that consists of 210 active assemblies and 7 spaces for control rods, each assembly consists of 169 pines. The design differs from other BBR it includes a blanket in the reactor center. The above-mentioned was to take advantage of the fact by geometry that the population of fast and epithermal neutrons will be high in the area, due to the fissions in adjacent fissile areas. Favorable results were obtained, although not definitive with exchange scheme of spent fuel. Efforts should be made in the future to homogenize the power generation within the reactor and replace the spent assemblies more efficiently. (Author)

  11. Spectrum reconstruction with X rays and flat panel wedge PMMA by Monte Carlo codes and Penelope MCNPS; Reconstruccion del esptro de rayos X con flat panel y cuna de PMMa mediante los codigos de monte Carlo Penelope y MCNP5

    Energy Technology Data Exchange (ETDEWEB)

    Pozuelo, F.; Querol, A.; Juste, B.; Gallardo, S.; Rodenas, J.; Verdu, G.

    2012-07-01

    Obtaining the primary spectrum of X-rays to determine the quality of a photon beam produced by an X-ray tube, since the dosimetric characteristics of a radiation beam to have a direct relation to the primary X-ray spectrum. In this work are studied, the depth dose curves obtained in the energy range of diagnostic radiology, between 40 and 130 keV.

  12. del alcoholismo

    Directory of Open Access Journals (Sweden)

    Rodrigo Arias Duque

    2005-01-01

    Full Text Available Desde el punto de vista farmacológico, es importante comprender qué es el alcohol y cómo actúa en el organismo. No existe una causa simple, sino una interacción complicada de factores neuroquímicos, fisiológicos, psicológicos y sociales que originan y desarrollan esta grave enfermedad fármaco-dependiente. La acción psicofisiológica y farmacodinámica del alcohol es fundamentalmente depresiva, por la reducción de la transmisión sináptica en el sistema nervioso humano. Es un hecho conocido que el consumo excesivo de alcohol causa una disfunción aguda y crónica del cerebro, produciendo trastornos en el sistema nervioso central, presentando alteraciones en la memoria y en las funciones intelectuales como cálculo, comprensión y aprendizaje. A nivel hepático tiene lugar, en su mayoría, el metabolismo del alcohol, produciéndose un hígado graso alcohólico, aumentando el tamaño, terminando en necrosis e inflamación grave del hígado; esto se llama hepatitis alcohólica, y si se sigue consumiendo alcohol se desarrollará la cirrosis. El alcohol también ha estado relacionado con alteraciones del miocardio; se ha constatado en animales de experimentación sanos que tanto la velocidad de contracción del músculo cardiaco y su máxima tensión disminuyen en presencia del alcohol, como consecuencia, la fuerza de cada contracción y el aumento de presión en el ventrículo izquierdo son menores, perdiendo eficacia el corazón como bomba.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  14. Quality control for the equipment of Nuclear medicine: experience of the H.U. de la Princesa; Control de calidad del equipamiento en Medicina Nuclear. Experiencia enel H.U. de la Princesa

    Energy Technology Data Exchange (ETDEWEB)

    Espana, M.L.; Gracia, A.; Prieto, C.; Lopez F, P. [Servicio de ProteccionRadiologica. Hospital Universitario de la Princesa C/ Diego de Leon 62, 28006Madrid (Spain)

    1998-12-31

    The quality control of the equipment used in a nuclear medicine service is a fundamental aspect in the Quality Assurance Program that in the present time is starting in our hospital. the objective of this work is to present the internal protocol used, its problematic associated with its starting, and the results obtained in the quality control as of the gamma camera as of the activimeter. In addition to the equipment own to the nuclear medicine service it has been used a Cs-137 source and puppets for several purposes. The results obtained demonstrated the stability of the controlled parameters which has led us to a restating of the established periodicities in our internal protocol, over all for some constancy tests. (Author)

  15. Phosphated in aluminium 6061-T651 used in the pool of the TRIGA Mark III nuclear reactor; Fosfatado en aluminio 6061-T651 utilizado en la tina del reactor nuclear TRIGA Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F.; Espinosa L, J.; Pena B, A.; Perez F, C.; Sanchez C, M.; Vite T, M.; Vite T, J. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2001-07-01

    We characterized a phosphated coating used a substrate in aluminium 6061-T651, which is used in the container of the TRIGA Mark III nuclear reactor. Characterization was made using MEB and X-ray diffraction techniques. Coating application has the function to prevent the corrosion. Coating was probed to test adhesion in accordance with the Standard ASTM D-4541, and the corrosion process using a salt spray (fog) camera, in accordance with the Standard ASTM B-117, so as we could phosphate the welding cord. These experiences were obtained using a Deep cell. Results obtained are going to phosphate 'in situ' using a mobile device which was patented for the National Institute of Nuclear Research (ININ) in the Mexican Institute of Intellectual Property (INPI). (Author)

  16. Optimization of corrective and preventive maintenance on computers in Radiology, Nuclear Medicine and Radiotherapy; Optimizacion del mantenimiento correctivo y preventivo en los equipos de Radiodiagnostico, Medicina Nuclear Y Radioterapia

    Energy Technology Data Exchange (ETDEWEB)

    Carrascosa Fernandez, C. B.; Gil Agudo, A.; Rodriguez Exodo, J. M.; Torres Donaire, J.; Zapata jimenez, J. C.; Arjona Gutierrez, J.

    2011-07-01

    One of the functions of a Service of Radio physics and Radiation Protection is the quality control of equipment emitting ionizing radiation and detectors for clinical use and verification to incidents and actions of the commercial house that could affect the dose or the quality image. The following is the procedure used in our hospital to track incidents that cause teams in Radiology (DR), Nuclear Medicine (MN) and Radiation Oncology (ONRT) in collaboration with the Electro medicine Service (EM .).

  17. Establishment of the Auditing National Service of quality to the instrumentation of Nuclear medicine in Cuba; Establecimiento del Servicio Nacional de Auditorias de calidad a la instrumentacion de medicina nuclear en Cuba

    Energy Technology Data Exchange (ETDEWEB)

    Varela C, C; Diaz B, M [Centro de Control Estatal de Equipos Medicos (CCEEM), Calle 4 No. 455 (altos) e/ 19 y 21 Vedado, Ciudad Habana (Cuba); Lopez B, G M [CPHR, Calle 20 No. 4113 e/ 41 y 47, Playa, Ciudad Habana (Cuba); Torres A, L A; Coca P, M A [Centro de Investigaciones Clinicas, Calle 34 No. 4501, e/ 45 y 47, Roto Kohly, Playa, Ciudad Habana (Cuba)

    2006-07-01

    Next to the vertiginous development of the technology in the Nuclear Medicine field, the possibility of early diagnosis of pathological processes without anatomical alterations, as well as its application with therapeutic purposes in the cancer treatment has grown. To assure a diagnosis and adapted therapy, it is vital to establish quality guarantee programs to the instrumentation. The State Medical Equipment Control Center (CCEEM), as regulator organ attributed to the Public Health Ministry of Cuba, it has licensed the Service of Quality Audits to the Nuclear medicine services, fulfilling all the technical and legal requirements to such effect. As base of these, the National Protocol for the Quality Control of the Instrumentation in Nuclear Medicine has been implemented, put out in vigour 2 national regulations, and an inter-institutional and multidisciplinary auditor equipment has been licensed. The different followed steps, as well as the realization of the first quality audits, its show not only a better execution of the tests and bigger professionalism of the involved specialists, but an increment in the taking of conscience to apply adequately the quality concepts for achieving a better service to the patient. On the other hand, the necessity of incorporating the clinical aspects to the audits, fomenting an integral harmonized advance of the quality guarantee programs is evidenced. (Author)

  18. Development of the user interface for visualization of the auxiliary systems of the TRIGA Mark III nuclear reactor; Desarrollo de la interface de usuario para la visualizacion de los sistemas auxiliares del reactor nuclear Triga Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Merced D, J. E.

    2016-07-01

    The Instituto Nacional de Investigaciones Nucleares (ININ) has a nuclear research reactor type swimming pool with movable core cooled and moderate with light water. The nominal maximum power of the reactor is 1 MW in steady-state operation and can be pulsed at a maximum power of 2,000 MW for approximately 10 milliseconds. This reactor is mainly used to study the effects of radiation on various materials and substances. In 2001 the new control console of the nuclear reactor was installed which was based on two digital computers, one computer controls the bar management mechanisms and the other the systems to the reactor operator. In 2004, the control computer was replaced and the software was updated. Within the modernization and/or updating of the TRIGA Mark III reactor of ININ, is intended (theme of this work) to develop the user interface for the visualization of the auxiliary systems, through a Man-Machine Interface module for the renewal process of the control console. The man-machine interface system to be developed will have communication with the programmable logic controllers that will be constantly monitored and controlled to obtain real-time variables of the reactor behavior. (Author)

  19. Caracterización cualitativa de poliaminas libres en endurecedores de resinas epoxídicas del tipo etilenaminas por espectroscopia de resonancia magnética nuclear Qualitative characterization of free polyamines in ethyleneamines epoxide hardeners by nuclear magnetic resonance spectroscopy

    Directory of Open Access Journals (Sweden)

    Filiberto González Garcia

    2008-03-01

    Full Text Available La caracterización cualitativa de dos agentes de curado comerciales de resinas epoxídicas del tipo etilenaminas comercializados por la ACROS (U.S.A. fue realizada usando la espectroscopia de resonancia magnética nuclear de carbono-13. Los productos comerciales corresponden a la trietilentetramina (TETA y a la tetraetilenpentamina (TEPA. El producto TETA presentó cuatro compuestos diferentes. El compuesto mayoritario correspondió a la trietilentetramina en una concentración de 60% molar que corresponde a una etilenamina de estructura linear. Los otros tres compuestos, uno de ellos mostró estructura ramificada, y los otros dos compuestos presentaron estructuras cíclicas del tipo piperazina. El producto TEPA mostró cinco compuestos con estructuras semejantes a las encontradas en el producto TETA. El compuesto mayoritario correspondió a la tetraetilenpentamina en una concentración aproximada de 55% molar. Los resultados encontrados en este trabajo están de acuerdo con la composición cualitativa de los productos semejantes comercializados por la Compañía Química Dow, productos DEH 24 y DEH 26, respectivamente.The qualitative characterization of two commercial ethyneamines epoxide hardeners marketed by ACROS (U.S.A. was carried out by using carbon-13 nuclear magnetic resonance spectroscopy. The products were triethylenetetramine (TETA and tetraethylenepentamine (TEPA. TETA had four components, the most importante one being triethylenetetramine, an ethyleneamine of lineal structure, in a concentration of 60 mol%. Another component had ramified structure, while the other two exhibited recurrent structures of the piperazina type. TEPA had five components with similar structures. The major component was tetraethylenepentamine in an approximate concentration of 55 mol%. These results agree with the composition of similar products marketed by Dow Chemical Company, namely DEH 24 and DEH 26, respectively.

  20. Qualification of the WIMS lattice code, for the design, operation and accident analysis of nuclear reactors; Calificacion del programa WIMS de calculo neutronico para diseno, seguimiento de operacion y analisis de accidentes de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lerner, A M [Ente Nacional Regulador Nuclear, Buenos Aires (Argentina)

    1997-12-31

    A basic problem in nuclear reactor physics in that of the description of the neutron population behaviour in the multiplicative medium of a nuclear fuel. Due to the magnitude of the physical problem involved and the present degree of technological evolution regarding computing resources, of increasing complexity and possibilities, the calculation programs or codes have turned to be a basic auxiliary tool in reactor physics. In order to analyze the global problem, several aspects should be taken into consideration. The first aspect to be considered is that of the availability of the necessary nuclear data. The second one is the existence of a variety of methods and models to perform the calculations. The final phase for this kind of analysis is the qualification of the computing programs to be used, i.e. the verification of the validity domain of its nuclear data and the models involved. The last one is an essential phase, and in order to carry it on great variety of calculations are required, that will check the different aspects contained in the code. We here analyze the most important physical processes that take place in a nuclear reactor cell, and we consider the qualification of the lattice code WIMS, that calculates the neutronic parameters associated with such processes. Particular emphasis has been put in the application to natural uranium fuelled reactor, heavy water cooled and moderated, as the Argentinean power reactors now in operation. A wide set of experiments has been chosen: a.-Fresh fuel in zero-power experimental facilities and power reactors; b.-Irradiated fuel in both types of facilities; c.-Benchmark (prototype) experiments with loss of coolant. From the whole analysis it was concluded that for the research reactors, as well as for the heavy water moderated power reactors presently operating in our country, or those that could operate in a near future, the lattice code WIMS is reliable and produces results within the experimental values and

  1. Atucha I nuclear power plant: repair works in QK02W01 moderator system heat exchanger; Central nuclar Atucha I. Intervencion al intercambiador nro2 del moderador

    Energy Technology Data Exchange (ETDEWEB)

    Olivieri, Luis E; Zanni, Pablo A [Nucleoelectrica Argentina SA (NASA), Lima (Argentina). Central Nuclear Atucha 1

    2000-07-01

    Atucha I nuclear power plant moderator system operates with highly radioactive heavy water, a pressure of 115 Bar and temperatures of about 200 C degrees. In March 2000, an increasing leakage of heavy water to the conventional thermal circuit was detected, conducting the plant to a shut down. The development of a number of actions and measures were taken, in order to plug this leakage. The leakage was found in a heat exchanger, which is located in a place of difficult access, with a high radiological yield and which, according to design, it was not considered to be mechanically repaired. It is a U bend tubes heat exchanger, weighting about 20 tons, and with a heavy water flow of 800 tons/h on the primary circuit, and 950 tons/h of ordinary water on the secondary side. Foreseeing this event, it had been designed and constructed special equipment and procedures, by means of a contract, with the Company INVAP SA. Repair works were carried out within a period of eighty-six (86) days, from which, forty five days were used to repair the component itself. A considerable amount of time was used to prepare simulators and the training of personnel. Due to the high radiological yield and the strict care of radiological standards, it was necessary the participation of 300 persons, integrating a collective dose of 4,86 Sv-m. It was necessary the construction of platforms and auxiliary stairs so as to make the work place accessible, as well as lifting and movement devices for heavy components, since this area does not have such kind of facilities. Welding and cutting machines remote controlled as well as manipulators which operated in front of the exchanger tube sheet were used. The aim was the reduction of dose values as much as possible. Special shielding were developed and in some cases it was necessary the adoption of drastic measures such as the cutting of bolts or pipes. The failure was detected and the tube was plugged. Also were plugged those tubes with wall thickness

  2. Neutronic / thermal-hydraulic coupling with the code system Trace / Parcs; Acoplamiento neutronico / termohidraulico con el sistema de codigos TRACE / PARCS

    Energy Technology Data Exchange (ETDEWEB)

    Mejia S, D. M. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico); Del Valle G, E., E-mail: dulcemaria.mejia@cnsns.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Col. Lindavista, 07738 Ciudad de Mexico (Mexico)

    2015-09-15

    The developed models for Parcs and Trace codes corresponding for the cycle 15 of the Unit 1 of the Laguna Verde nuclear power plant are described. The first focused to the neutronic simulation and the second to thermal hydraulics. The model developed for Parcs consists of a core of 444 fuel assemblies wrapped in a radial reflective layer and two layers, a superior and another inferior, of axial reflector. The core consists of 27 total axial planes. The model for Trace includes the vessel and its internal components as well as various safety systems. The coupling between the two codes is through two maps that allow its intercommunication. Both codes are used in coupled form performing a dynamic simulation that allows obtaining acceptably a stable state from which is carried out the closure of all the main steam isolation valves (MSIVs) followed by the performance of safety relief valves (SRVs) and ECCS. The results for the power and reactivities introduced by the moderator density, the fuel temperature and total temperature are shown. Data are also provided like: the behavior of the pressure in the steam dome, the water level in the downcomer, the flow through the MSIVs and SRVs. The results are explained for the power, the pressure in the steam dome and the water level in the downcomer which show agreement with the actions of the MSIVs, SRVs and ECCS. (Author)

  3. Culturas del Mundo

    DEFF Research Database (Denmark)

    Benwell, Ann Fenger; Costa, Alberto; Waehle, Espen

    2006-01-01

    ’Culturas del mundo. Colecciones del Museo Nacional de Dinamarca’ with Ann Fenger Benwell in Culturas del Mundo. Colecciones del Museo Nacional de Dinamarca, ed. Silvia Sauquet, Fundación "la Caixa", Barcelona 2006, pp. 31-39......’Culturas del mundo. Colecciones del Museo Nacional de Dinamarca’ with Ann Fenger Benwell in Culturas del Mundo. Colecciones del Museo Nacional de Dinamarca, ed. Silvia Sauquet, Fundación "la Caixa", Barcelona 2006, pp. 31-39...

  4. Implementation of the quality management system in the regulatory body (Peruvian Institute for Nuclear Energy, Lima, Peru); Implementacion del sistema de gestion de calidad en el organo regulador

    Energy Technology Data Exchange (ETDEWEB)

    Medina Gironzini, E., E-mail: medina@ipen.gob.pe [Instituto Peruano de Energia Nuclear (IPEN), Lima (Peru)

    2013-07-01

    One of the functions of the Peruvian Institute of Nuclear Energy (IPEN), Lima, Peru is the control of sources of ionizing radiation. For this, they have the Oficina Tecnica de la Autoridad Nacional (OTAN) which has the necessary infrastructure to issue technical standards, conducting inspections, issuing authorizations and punish according to the existing legislation. OTAN has decided to address this issue and is taking into account the IAEA recommendations, especially the Safety Requirements GS-R-3: Management System facilities and activities and offering advice on the establishment and improvement of integrated management systems, including safety requirements that are not in the ISO 9001 standard and are also considered the requirements of technological safety, security, quality, economic, environmental and health. The working plan is detailed and the activities that are carried out after the scientific visit to a regulator organ, which has experience in the execution of a Quality Management System, consequence of a work initiated for more than four decades ago.

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

    Energy Technology Data Exchange (ETDEWEB)

    Sarandeses, S.

    2014-07-01

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

  6. Application of the SPA in the design of a hydrogen producer plant coupled to a nuclear reactor; Aplicacion del APS en el diseno de una planta productora de hidrogeno acoplada a un reactor nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz S, T.; Nelson, P. F.; Francois, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac No. 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico); Cruz G, M. J., E-mail: truizsmx@yahoo.com.mx [UNAM, Facultad de Quimica, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2013-10-15

    At the present time, one of the processes that is broadly investigated and that, theoretically demonstrates to be one of the most efficient for the hydrogen production, is the thermal-chemistry cycle Sulfur-Iodine (S-I) coupled to a nuclear reactor of very high temperature (VHTR). Because this chemical process of hydrogen production requires of a great inventory of toxic materials (sulphide compounds, hydriodic acid and iodine), is necessary the design of emergency systems with the purpose of protecting the facilities and the equipment s, the environment, as well as the near population. Given the impact of an accidental liberation of the process materials, as well as the proximity with the nuclear plant, is necessary that these emergency systems are the most reliable possible. This way, the results of the consequences analysis are utilized for the optimal localization of the gas sensors that activate the emergency systems, and the flows of the substances that are used for the leakage control. For all this, the use of the Safety Probabilistic Analysis methodology, as well as some standards of the nuclear industry, can be applied to the chemical installation to determine the fault sequences that can take to final states of not controlled leakage. This way, the use of methodologies of Event Tree Analysis and Fault Trees show in their results the components that but contribute in fault of such systems. In this work, is presented the evaluation of the joined models of event and fault trees and like with the obtained results, some proposals to increase the safety of the facilities are exposed. Also, the results of the evaluations of these proposals, and their impact of the probability of the not controlled fault sequences in a plant that is still in design stage are showed. (Author)

  7. Literature study regarding fire protection in nuclear power plants. Part I: Fire rated separations; Litteraturstudie angaaende brandskydd i kaernkraftverk. Del I: Brandteknisk separation

    Energy Technology Data Exchange (ETDEWEB)

    Isaksson, S [Swedish Testing and Research Inst., Boraas (Sweden)

    1995-06-01

    This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Conventional building codes can not give guidance on where to make fire rated separations in order to separate redundant trains of safety systems. The separation must originate in functional demands from the authorities on what functions are essential during and after a fire, and under what circumstances these functions shall be retained, i.e. the number of independent faults and initiating events. As a basic demand it is suggested to rate the strength of separations according to conventional building code, based on fire load. The whole separating construction shall have the same fire rating, including the ventilation system. Deviations from the basic demand can de done in case it can be proven that it is possible to compensate some or all of the fire rating with other measures. There is a general lack of statistical information regarding the reliability of fire separating constructions such as walls, fire doors, penetration seals and fire dampers. The amount of cables penetrating a seal is in many cases much higher in real installations than what has been tested for type approval. It would therefore be valuable to perform a furnace test with a more representative amount of cables passing through a penetration seal. Tests have shown that the 20 foot horizontal separation distance stipulated by NRC is not a guarantee against fire damage. Spatial separations based on general requirements shall not be allowed, but considered from case to case based on actual circumstances. For fire protection by isolation or coatings, it is of great importance to choose the method of protection carefully, to be compatible with the material it shall be applied on, and the environment and types of fire that may occur. 48 refs, 2 figs, 5 tabs.

  8. Nuclear techniques (PIXE and RBS) applied to analysis of pre hispanic metals of the Templo Mayor at Tenochtitlan; Tecnicas nucleares (PIXE y RBS) aplicadas al analisis de metales prehispanicos del Templo Mayor de Tenochtitlan

    Energy Technology Data Exchange (ETDEWEB)

    Mendez U, I.; Tenorio, D.; Galvan, J.L. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    This work has the objective of determining by means of the utilization of nuclear techniques (PIXE and RBS) the composition and the alloy type of diverse aztec ornaments corresponding to Post classic period, they were manufactured principally with copper and gold such as bells, beads and disks; all they belonging at 9 oblations of Templo Mayor of Tenochtitlan. It is presented here briefly the historical and archaeological antecedents of the devices as well as the analytical methods for conclude with the results obtained. (Author)

  9. Development of the main processes of the quality management system in the Centro Nacional de Seguridad Nuclear from Cuba; Desarrollo de los principales procesos del sistema de gestion de la calidad en el Centro Nacional de Seguridad Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Marrero Garcia, M.; Sarabia Molina, I.I., E-mail: marielam@orasen.co.cu [Centro Nacional de Seguridad Nuclear, Oficina de Regulacion Ambiental y Seguridad Nuclear, La Habana (Cuba)

    2013-07-01

    The quality management system of the Centro Nacional de Seguridad Nuclear - CNSN from Cuba is based on the ISO 9001 of 2008, whose key element is the management of the identified processes. The methods used were the diagnosis of the Organization according the expert criteria. It were established the following basic rules: 'to say what you do, do what you say and to be able to demonstrate it'. In the present work, the processes identified are presented, experience in implementing them and the prospects of integration with the model proposed by the IAEA for effective management systems.

  10. Qualitative characterization of free polyamines in ethyleneamines epoxide hardeners by nuclear magnetic resonance spectroscopy; Caracterizacion cualitativa de poliaminas libres en endurecedores de resinas epoxidicas del tipo etilenaminas por espectroscopia de resonancia magnetica nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Garcia, Filiberto [Universidade Federal de Itajuba (UNIFEI), MG (Brazil); Miguez, Eduardo; Tavares, Maria Ines B. [Universidade Federal do Rio de Janeiro (UFRJ/IMA), RJ (Brazil). Inst. de Macromoleculas Professora Eloisa Mano

    2008-01-15

    The qualitative characterization of two commercial ethyneamines epoxide hardeners marketed by ACROS (U.S.A.) was carried out by using carbon-13 nuclear magnetic resonance spectroscopy. The products were triethylenetetramine (TETA) and tetraethylenepentamine (TEPA). TETA had four components, the most important one being triethylenetetramine, an ethyleneamine of lineal structure, in a concentration of 60 mol%. Another component had ramified structure, while the other two exhibited recurrent structures of the piperazina type. TEPA had five components with similar structures. The major component was tetraethylenepentamine in an approximate concentration of 55 mol%. These results agree with the composition of similar products marketed by Dow Chemical Company, namely DEH 24 and DEH 26, respectively. (author)

  11. Advances of the Surgery of the Breast Cancer with help of the Nuclear Medicine; Avances de la cirugia del cancer de mama con la colaboracion de la medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Sierra Garcia, A.; Gomez Embuena, D. A.

    2009-07-01

    The incorporation of the nuclear medicine to the surgical current practice In the treatment of the cancer of breast, by means of the application of radioactive isotopes, have supposed a great achievement not only in the surgical and predicted results but also in the surgical skills more effective and less aggressive. The systematic research of the marking and extirpation of Sentinel Lymph Node is avoiding in the early cancer the linfadenectomy axilar. The application of the ROLL and SNOLL skills is being determinant in the extirpation with trustworthy margins of the non-palpable lesions cancer, with big safety instead harpoons that we used before. (Author) 6 refs.

  12. Individual monitoring of internal exposure of {sup 131}I of workers from the nuclear medicine service FUESMEN, Argentina; Monitoraje individual debido a exposicion interna por {sup 131I} de los trabajadores del servicio de medicina nuclear de FUESMEN

    Energy Technology Data Exchange (ETDEWEB)

    Arenas, G.; Acosta, N.; Venier, V.; Bedoya Toboo, C. [Comision Nacional de Energia Atomica (FUESMEN/CNEA), Buenos Aires (Argentina). Fundacion Escuela de Medicina Nuclear

    2013-07-01

    It is presented the FUESMEN experience in routine monitoring of thyroid internal doses due to inhalation of {sup 131}I in workers of the Nuclear Medicine Service in normal operation or accidental exposure. It is used a surface contamination monitor, type Geiger Mueller, calibrated with a acrylic phantom based on specifications of the simulator of thyroid of ICRU 48 with {sup 131}I reference activity. Through the obtained measurements is achieved to validate the use of Portable Monitor to carry out preliminary exploration on the monitoring scenarios of incidental situations.

  13. APMO: UN PROGRAMA COMPUTACIONAL PARA EL ESTUDIO DE EFECTOS CUÁNTICOS NUCLEARES MEDIANTE LA TEORÍA DEL ORBITAL MOLECULAR ELECTRÓNICO Y NO ELECTRÓNICO.

    Directory of Open Access Journals (Sweden)

    Sergio González

    2009-04-01

    Full Text Available Con el fin de estudiar teóricamente fenómenos en donde los núcleos atómicos presentan comportamiento cuántico, hemos desarrollado el paquete computacional APMO (Any-Particle Molecular Orbital. Este implementa el método de orbitales moleculares nucleares y electrónicos (OMNE a un nivel de teoría Hartree-Fock (HF, en el que tanto núcleos como electrones se representan como funciones de onda.Para comprobar la correcta implementación del método, se realizaron  cálculos de estructura electrónica regular y núcleo-electrónica de las moléculas H2 y LiH. Las componentes de energía calculadas siguen las  tendencias y están en el mismo orden de magnitud de cálculos similares reportados en la literatura.A diferencia de otros paquetes que implementan el método OMNE, el nuestro fué diseñado para estudiar sistemas con cualquier número de especies cuánticas. 

  14. Implementation of a quality control program of the equipment of the nuclear medicine services in Chile; Implementacion de un programa de control de calidad del equipamiento de los servicios de medicina nuclear de Chile

    Energy Technology Data Exchange (ETDEWEB)

    Astudillo, R.; Diaz, G.; Ferreira, A.; Garcia, M.; Hermosilla, A.; Pacheco, F.; Vasquez, M. [Universidad de la Frontera, Departamento de Ciencias Fisicas, Av. Francisco Salazar 1145, Temuco 4811230, Araucania (Chile); Coca, M., E-mail: ferreira.sdgr@gmail.com [MedScan Concepcion, Paicavi 270, Concepcion (Chile)

    2014-08-15

    Now days in Chile there are more of 43 Nuclear Medicine centers; most of them have gamma cameras in order to study physiological process in diagnostic and treatment of patients pathologies. This requires having the equipment in optimal operating condition and it is ensured with quality control programs that are based on a series of tests relating to protocols, such as TECDOC-602 y AAPM No.6. Planar test often applied in gamma cameras including: spatial resolution, spatial linearity, sensitivity and uniformity. SPECT tests consider: tomography uniformity, rotation center tomography resolution and total performance. The tests in dose calibrator are: background measurement, accuracy, precision, linearity and reproducibility. The tests above require the use of radioactive sources and specific simulators patterns or phantom based on international standards such as The National Electrical Manufacturers Association (Nema), International Atomic Energy Agency (IAEA) and The American Association of Medical Physics (AAPM). In this work we carried out several tests of quality control in a Nuclear Medicine Center of Temuco and we propose to implement the applied methodology in others similar Chilean centers. (author)

  15. Developments of STR project in the scope of teleoperation handling robotic for the operation in Spanish nuclear facilities; Desarrollos del proyecto SRT en el area de manipulacion robotica teleoperada para la operacion de las instalaciones nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Bielza, M [ENDESA (Spain); Gomez Santamaria, J [IBERDROLA (Spain); Izquierdo, J A [C.N. COFRENTES (Spain); Martinez, S [C.N. ASCO (Spain); Linares, F [ENSA (Spain); Avello, A [CEIT (Spain); Gago, M J [IBRINCO (Spain)

    1998-12-01

    The main objective of the Teleoperated Robotic Systems project (SRT) is the development of teleoperated robotic systems for use in the inspection, surveillance and maintenance operations in nuclear and radioactive installations. These systems make possible the reduction of the individual and collective doses of the workers that undertake these operations, as well as an increase of plant availability as it is possible to carry out specific tasks of inspection and surveillance in high radiation dose areas without having to reduce the power of the installation. This project started in 1995, deciding to priorize the inspection equipment in a first phase. When this work were advanced, the development of the manipulation activities was carried out to being consider the nuclear installations needs. As a result of this work, the manipulation requirements were elaborated in order to prepare the beginning technical specifications to design the equipment s. These developments are based on a fixed manipulator which is located closed to the equipment that we want to repair, and an arm manipulator which moves by caterpillars, it is easier to control than others; and the navigation system which allows the robot self-locating in the complex area. In this paper the conclusions about the manipulation requirements are described, as well as the state of the manipulation prototype. (Author)

  16. The Impact of Organizational Factors on Safety. The Perspective of Experts from the Spanish Nuclear Sector; El Impacto de los Factores Organizativos en la Seguridad. La Vision de los Expertos del Sector Nuclear Espanol

    Energy Technology Data Exchange (ETDEWEB)

    German, S.; Silla, I.; Navajas, J.

    2014-07-01

    Previous research supports the importance of organizational factors on safety in high reliability organizations. This study aims to determine the impact of those factors in the Spanish nuclear sector. Particularly, this study focuses on examining the role of performance indicators, organizational culture, organizational factors, and organizational context. With that purpose, an electronic survey addressed to experts from the Spanish nuclear sector was carried out. Results showed that performance indicators are well-known among industry experts and are perceived as useful for improving performance. Behavioural norms that influence safety and some relevant factors that promote problem identification were identified. Additionally, findings suggested that organizational context must be taken into account to better understand the role of organizational culture. Moreover, industry experts pointed out organizational factors to be improved: organizational communication processes within the organization, positive reinforcement, and field supervisors practices. Finally, findings supported the influence of organizational context on safety. It is noteworthy the role of the social impact of international events (e.g., Chernobyl...), the relationship with the regulator and the legislative and governmental framework. (Author)

  17. Characterization and adjustment of the neutron radiography facility of the RP-10 nuclear reactor; Caracterizacion y puesta a punto de la facilidad de neutrografia del reactor nuclear RP-10

    Energy Technology Data Exchange (ETDEWEB)

    Ravello R, Y R

    2001-07-01

    The main aim of this work was to characterize and adjust the neutron radiography facility of the RP-10 nuclear reactor, and therefore be able to offer with this technique services to the industry and research centers in general. This technique will be complemented with others such as x-rays and gamma radiography. First, the shielding capacity of the facility was analyzed, proving that it complies with the radiological safety requirements established by the radiological safety code. Then gamma filtration tests were conducted in order to implement the direct method for image formation, optical density curves were built according to the thickness of the gamma filter, the type of film and the type of irradiation. Also, the indirect method for image formation was implemented for two types of converters: indium and dysprosium. Growth curves for optical density were also made according to contact time between converter-film, for different types of films. The resolution of the facility was also analyzed using two methods: Klasens (1946) and Harms (1986). Harms method came closer to the resolution of the human eye when compared to the Klasens method. Finally, the application fields of neutron radiography are presented, including those conducted at the neutron radiography facility of the RP-10 nuclear reactor. With this work, the RP-10 neutron radiography facility is ready to offer inspection and research services.

  18. Parameter calculation tool for the application of radiological dose projection codes; Herramienta de calculo de parametros para la aplicacion de codigos de proyeccion de dosis radiologicas

    Energy Technology Data Exchange (ETDEWEB)

    Galindo G, I. F.; Vergara del C, J. A.; Galvan A, S. J. [Instituto Nacional de Electricidad y Energias Limpias, Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico); Tijerina S, F., E-mail: francisco.tijerina@cfe.gob.mx [CFE, Central Nucleoelectrica Laguna Verde, Carretera Federal Cardel-Nautla Km 42.5, 91476 Municipio Alto Lucero, Veracruz (Mexico)

    2016-09-15

    The use of specialized codes to estimate the radiation dose projection to an emergency postulated event at a nuclear power plant requires that certain plant data be available according to the event being simulated. The calculation of the possible radiological release is the critical activity to carry out the emergency actions. However, not all of the plant data required are obtained directly from the plant but need to be calculated. In this paper we present a computational tool that calculates the plant data required to use the radiological dose estimation codes. The tool provides the required information when there is a gas emergency venting event in the primary containment atmosphere, whether well or dry well and also calculates the time in which the spent fuel pool would be discovered in the event of a leak of water on some of the walls or floor of the pool. The tool developed has mathematical models for the processes involved such as: compressible flow in pipes considering area change and for constant area, taking into account the effects of friction and for the case of the spent fuel pool hydraulic models to calculate the time in which a container is emptied. The models implemented in the tool are validated with data from the literature for simulated cases. The results with the tool are very similar to those of reference. This tool will also be very supportive so that in postulated emergency cases can use the radiological dose estimation codes to adequately and efficiently determine the actions to be taken in a way that affects as little as possible. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-09-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  1. Development of a remote monitoring system, through monitoring of key safety parameters for a nuclear research reactor; Desarrollo de un sistema de vigilancia remota, por medio del monitoreo de parametros claves de seguridad, para un reactor nuclear de investigacion

    Energy Technology Data Exchange (ETDEWEB)

    Urcia, Agustin; Arrieta, Rolando [Direccion de Produccion, Instituto Peruano de Energia Nuclear, Lima (Peru); Baltuano, Oscar; Chan, Renzo [Direccion de Investigacion y Desarrollo, Instituto Peruano de Energia Nuclear, Lima (Peru); Tincopa, Jean Pierre [Facultad de Ingenieria Electrica y Electronica, Universidad Nacional del Callao, Callao (Peru); Urquizo, Rafael [Facultad de Ingenieria Electronica, Universidad Tecnologica del Peru, Lima (Peru); Rosas, Bernick [Facultad de Ingenieria Electronica, Universidad Nacional de Ingenieria, Lima (Peru)

    2014-07-01

    This paper presents the detailed development, installation and commissioning of water level sensors and exposure rate range in the 11 meters level (mouth of tank) of the RP-10 nuclear reactor used to continuously monitor these values and use them as security for the periods of no presence of operating personnel (overlooking situation) with the reactor in shutdown state. The levels of these parameters are packaged and transmitted to a controller in the control room of reactor for display and activation of alarm levels. Additionally, the design of these warning signs is shown in conjunction with the fire alarm in the building of reactor and auxiliary laboratories to be transmitted to the physical security facility, located at a distance of 500 meters. (authors).

  2. Analysis of a Multi-Venturi filter for the venting of the primary container of a nuclear reactor; Analisis de un filtro multiventuri para el venteo del contenedor primario de un reactor nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Reyes G, A. A.; Sainz M, E.; Ortiz V, J., E-mail: alejandroantonioreyess@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    Since the Chernobyl nuclear accident, European nuclear power plants have opted to install filters in the containment vent pipes, whose function is to help mitigate the consequences of a severe accident, by means of the controlled depressurization of the containment passively through of a containment filtering vent system. These systems are designed to relieve the internal pressure of containment by deliberately opening pressure relief devices, either a valve or rupture disk during a severe accident and being channeled to the filtering unit. In this work, the hydraulic response of a liquid gas washing filtration system is evaluated, since this information is necessary to estimate the effect of the increase of the containment pressure on the venting capacity of the vent pipes. Through CFD simulation, using the programs with open source license CaeLinux-2014 and OpenFoam, the hydrodynamic characteristics of the Multi-Venturi system were obtained for the washing of the gases coming from the containment, which could be included in the general model of the vent pipe. Representative models of the venturi tubes of each concentric sector that are part of the washing system were generated and by parametric calculations the average mass expense established by each venturi was estimated, according to its dimensions and depth to which is located inside the tank. In the same way, the pressure and mass expense required to activate each concentric sector was calculated according to the pressure and mass load from the containment, in order to estimate the maximum expenditure that is established through the filter. The velocity profiles and the characteristic pressure at which each sector operates were also calculated, as well as the local and global discharge pressure drop. (Author)

  3. Nuclear law - Nuclear safety

    International Nuclear Information System (INIS)

    Pontier, Jean-Marie; Roux, Emmanuel; Leger, Marc; Deguergue, Maryse; Vallar, Christian; Pissaloux, Jean-Luc; Bernie-Boissard, Catherine; Thireau, Veronique; Takahashi, Nobuyuki; Spencer, Mary; Zhang, Li; Park, Kyun Sung; Artus, J.C.

    2012-01-01

    This book contains the contributions presented during a one-day seminar. The authors propose a framework for a legal approach to nuclear safety, a discussion of the 2009/71/EURATOM directive which establishes a European framework for nuclear safety in nuclear installations, a comment on nuclear safety and environmental governance, a discussion of the relationship between citizenship and nuclear, some thoughts about the Nuclear Safety Authority, an overview of the situation regarding the safety in nuclear waste burying, a comment on the Nome law with respect to electricity price and nuclear safety, a comment on the legal consequences of the Fukushima accident on nuclear safety in the Japanese law, a presentation of the USA nuclear regulation, an overview of nuclear safety in China, and a discussion of nuclear safety in the medical sector

  4. CAC-RA1 1958-1998. The first years of the Constituyentes Atomic Center (CAC). History of the first Argentine nuclear reactor (RA-1); CAC-RA-1 1958-1998. Los primeros anios del CAC. Historia del primer reactor nuclear argentino (RA-1)

    Energy Technology Data Exchange (ETDEWEB)

    Forlerer, Elena; Palacios, Tulio A [comps.

    1998-07-01

    After giving the milestones of the development of the Constituyentes Atomic Center since 1957, the history of the construction of the first nuclear reactor (RA-1) in Argentina, including the local fabrication of its fuel elements, is surveyed. The RA-1 reached criticality on January 17, 1958. The booklet commemorates the 40th year of the reactor operation.

  5. Evaluation of the aptitude for the service of the pool of the TRIGA Mark III reactor of the National Institute of Nuclear Research of Mexico; Evaluacion de la aptitud para el servicio de la piscina del reactor TRIGA Mark III del Instituto Nacional de Investigaciones Nucleares de Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Merino C, J.; Gachuz M, M.; Diaz S, A.; Arganis J, C.; Gonzalez R, C.; Nava G, T.; Medina R, M.J. [Departamento de Sintesis y Caracterizacion de Materiales del ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2001-07-01

    This work describes the evaluation of the structural integrity of the pool of the TRIGA Mark III reactor of the National Institute of Nuclear Research of Mexico, which was realized in July 2001, as an element to determine those actions for preventive and corrective maintenance which owner must do it for a safety and efficient operation of the component in the next years. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-10-15

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

  8. 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

    Energy Technology Data Exchange (ETDEWEB)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

  10. 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

    Energy Technology Data Exchange (ETDEWEB)

    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

  11. Il dono del racconto

    DEFF Research Database (Denmark)

    Polito, Paola

    1998-01-01

    L'articolo indaga a vari livelli strutturali del romanzo "Il coraggio del pettirosso" (rete metaforica, dialogismo diegetico, dialogismo come fenomeno di voce, strategie discorsive messe in atto dalla voce narrante, stile colloquiale) la complessa realizzazione testuale del genere narrativo...

  12. Relationship of the vibrational frequency of the nuclear pair Mo-Cl with it electronegativity, force constant and bond length in the structural conformation of molybden dichloride; Relacion de la frecuencia vibracional del par nuclear Mo-Cl con su electronegatividad, constante de fuerza y distancia de enlace en la conformacion estructural del dicloruro de molibdeno

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez S, A.; Martinez Q, E

    1990-08-15

    The structural elucidation of the cluster hexamerico (MO{sub 6}C1{sub 8}) {sup 4+}, it has been characterized for but of twenty-five years like a conformation octahedrica of simple metallic connections. However, the determination has not been attempted of some physical characteristics of this conformation by means of measures espectroscopicas. We present the electronegatividad measures now, constant of force and it distances of connection of the nuclear couple Mo-Cl, using only their frequency vibracional taken directly of the infrared spectra. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-10-15

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

  14. Guidance and considerations for the implementation of INFCIRC/225/Rev.4, the physical protection of nuclear material and nuclear facilities; Orientaciones y sugerencias para la aplicacion del documento INFCIRC/225/Rev.4, proteccion fisica de los materiales y las instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-01

    This publication is intended to provide guidance and considerations for a State's competent authority to better understand and prescribe appropriate requirements, consistent with INFCIRC/225/Rev.4 for the protection of nuclear material and nuclear facilities which are compatible with accepted international practice. This report, together with a more detailed report, Handbook on the Physical Protection of Nuclear Material and Facilities, which addresses to the licensee or designer of physical protection systems who has specific implementation and compliance responsibilities, should be used in conjunction to each other to provide better and comprehensive guidance on physical protection.

  15. Nuclear Medicine

    Science.gov (United States)

    ... Parents/Teachers Resource Links for Students Glossary Nuclear Medicine What is nuclear medicine? What are radioactive tracers? ... funded researchers advancing nuclear medicine? What is nuclear medicine? Nuclear medicine is a medical specialty that uses ...

  16. del cambio

    Directory of Open Access Journals (Sweden)

    Alejandro Canales

    2006-01-01

    Full Text Available El artículo analiza las propuestas y los compromisos en materia de cobertura y de financiamiento en el periodo 2000-2006. En particular, revisa las modificaciones y los ajustes de los tres principales documentos en los que se expresaron las iniciativas: el de la Asociación Nacional de Universidades e Instituciones de Educación Superior, el del equipo de la transición y el programa sectorial. Los resultados muestran que las cifras de atención a la demanda educativa e inversión quedaron lejos de las metas autoimpuestas por el gobierno federal y que será necesario realizar mayores esfuerzos para atender tales desafíos.

  17. Nuclear safety. Seguranca nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Aveline, A [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Inst. de Fisica

    1981-01-01

    What is nuclear safety Is there any technical way to reduce risks Is it possible to put them at reasonable levels Are there competitiveness and economic reliability to employ the nuclear energy by means of safety technics Looking for answers to these questions the author describes the sources of potential risks to nuclear reactors and tries to apply the answers to the Brazilian Nuclear Programme. (author).

  18. Use of nuclear energy: the perception of public risk from radiation. Experience from health sector Utilización de la energía nuclear: la percepción del riesgo radiológico del público. Experiencia desde el sector sanitario

    Directory of Open Access Journals (Sweden)

    Leopoldo Arranz y Carrillo de Albornoz

    2010-12-01

    Full Text Available Radiological risks are, probably by the fact that Hiroshima and Nagasaki bombs still are a part of the collective nightmares of the humankind, always with the sword of Damocles of a possible use of nuclear weapons, the paradigm of subjectivity. And their negative perception by the citizens has turned into a growing interest for people responsible of the management of any of the applications of the ionizing radiations. In this work the opinion of communication experts, some based on their experience in the health care system, with regard to radiological risks and what can be done in order to modify such negative perception are set out.Los riesgos radiológicos están, seguramente por el hecho que las bombas de Hiroshima y Nagasaki sigan formando parte de las pesadillas colectivas de la humanidad, siempre con la espada de Damocles de un posible uso de las armas nucleares, el paradigma de la subjetividad. Y su percepción negativa por parte de los ciudadanos se ha convertido en un momento de creciente interés para los responsables de la gestión y el manejo de cualquiera de las aplicaciones de las radiaciones ionizantes. En este trabajo se expone la opinión de expertos en comunicación cuando se habla de riesgos radiológicos, basándose algunos en su experiencia en el sector sanitario, y lo que se puede hacer para que esa percepción negativa pueda llegar a modificarse.

  19. Invisible nuclear; converting nuclear

    International Nuclear Information System (INIS)

    Park, Jongmoon

    1993-03-01

    This book consists of 14 chapters which are CNN era and big science, from East and West to North and South, illusory nuclear strategy, UN and nuclear arms reduction, management of armaments, advent of petroleum period, the track of nuclear power generation, view of energy, internationalization of environment, the war over water in the Middle East, influence of radiation and an isotope technology transfer and transfer armament into civilian industry, the end of nuclear period and the nuclear Nonproliferation, national scientific and technological power and political organ and executive organ.

  20. La superaci??n del modelo del ??ngel del hogar:

    OpenAIRE

    Hurtado Mu??oz, M??nica

    2012-01-01

    La Tesis Doctoral titulada "La superaci??n del modelo del "??ngel del hogar". Recuperaci??n de la escritora Leonor Canalejas y Fustegueras (1869-1945)" aborda, en primer lugar, un an??lisis sociol??gico de las circunstancias que rodearon a la mujer espa??ola en el cambio de siglo en el ??mbito social y educativo, en un intento de esclarecer las caracter??sticas propias del contexto en el que la mujer accede a la intelectualidad en general y a la literatura en particular. Esta parte concluye q...

  1. Estudio sobre la aplicación del análisis por activación en reactores nucleares a la determinación multielemental rutinaria en rocas silicatadas

    OpenAIRE

    Espinosa, Ricardo; Cohen, Marcos

    1985-01-01

    Se investigan comparativamente las posibilidades del análisis por activación, con neutrones predominantemente térmicos (AANT) y epitérmicos (AANE), para le determinación multielemental no destructiva de muestras geológicas silicatadas. Se describe el método empleado para el análisis de 23 elementos de materiales de referencia del U.S.G.S. y granitos argentinos, aplicable a la determinación rutinaria.

  2. Composition and concentration of soluble and particulate matter in the coolant of the reactor primary cooling system of the Embalse nuclear power plant; Composicion y concentracion del material soluble y particulado en el refrigerante del SPTC de la central nuclear Embalse

    Energy Technology Data Exchange (ETDEWEB)

    Chocron, Mauricio; Garcia Rodenas, Luis; La Gamma, Ana M; Villegas, Marina [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Quimica; Fernandez, Alberto N; Allemandi, Walter; Manera, Raul; Rosales, Hugo [Nucleoelectrica Argentina SA (NASA), Embalse (Argentina). Central Nuclear Embalse

    2000-07-01

    Nuclear power plants type PWR and PHWR (pressurized water reactor and pressurized heavy water reactor) have three coolant circuits which only exchange energy among them. The primary circuit, whose coolant extracts the reactor energy, the secondary circuit or water-steam cycle and the tertiary circuit which could be lake, river or sea water. The chemistry of the primary and secondary coolants is carefully controlled with the aim of minimizing the corrosion of structural materials. However, very low rates of corrosion are inevitable and one of the consequences of the corrosion processes is the presence of soluble and particulate matter in the coolant from where several problems associated with mass transfer arisen. In this way radioactive nuclides are transported out of the core to the steam generators, hydraulic resistance increases and heat transfer capability degrades. In the present paper some alternative techniques are proposed for the quantification of both, the particulate and soluble matter present in the coolant and their correspondent composition. Some results are also included and discussed. (author)

  3. Advanced Nuclear Magnetic Resonance

    OpenAIRE

    Alonso, Diego A.

    2014-01-01

    Transparencias en inglés de la asignatura "Resonancia Magnética Nuclear Avanzada" (Advanced Nuclear Magnetic Resonance) (36643) que se imparte en el Máster de Química Médica como asignatura optativa de 3 créditos ECTS. En esta asignatura se completa el estudio iniciado en la asignatura de quinto curso de la licenciatura en Química "Determinación estructural" (7448) y en la del Grado de Química de tercer curso "Determinación estructural de los compuestos orgánicos" (26030) en lo referente a té...

  4. Notas del Consejo Editorial

    Directory of Open Access Journals (Sweden)

    Fernando Serpa Florez

    1990-08-01

    Full Text Available

    Merecida Distinción
    Complacidos registrados la señalada distinción de que fue objeto en Hiroshima, Japón, durante la celebración del IX Congreso Mundial de la Organización Internacional a Médicos para la Prevención de la Guerra Nuclear (lPPNW el Académico Honorario Alberto Cárdenas Escovar quien recibió el Premio Albert Schweitzer, en reconocimiento a la meritoria labor que ha cumplido en el campo internacional de la medicina.

    Fernando Serpa Flórez

    Breves de la Academia
    En el número anterior de nuestra revista, por involuntaria omisión no se incluyeron dos señalados acontecimientos, que nos apresuramos a subsanar en la presente edición. Se trata del ingreso a la Corporación de dos distinguidos y muy apreciados Miembros de nuestro Instituto, el Académico correspondiente Joaquín Silva, Profesor de Cirugía y eminente maestro de numerosas generaciones médicas, quien disertó en forma erudita y ponderada sobre el tema “Los albores de la Medicina y Cirugía”. Así mismo tomó posesión como Miembro de Número el actual Presidente del Capítulo de los Santanderes de la Academia Nacional de Medicina, ex-decano de la Escuela de Medicina de la Universidad Industrial de Santander y notable escritor y psiquiátra doctor Roberto Serpa Flórez, quien presentó su libro sobre medicina y enfermedades tropicales en Colombia en la primera mitad de este siglo que, en forma interesante y amena, desarrolló alrededor de la biografía de su padre, el también Académico de Número profesor Roberto Serpa Novoa.

  5. [Nuclear theory

    International Nuclear Information System (INIS)

    Haxton, W.

    1990-01-01

    This report discusses research in nuclear physics. Topics covered in this paper are: symmetry principles; nuclear astrophysics; nuclear structure; quark-gluon plasma; quantum chromodynamics; symmetry breaking; nuclear deformation; and cold fusion

  6. Nuclear topics

    International Nuclear Information System (INIS)

    Lukner, C.

    1982-07-01

    The pamphlet touches on all aspects of nuclear energy, from the world energy demands and consumption, the energy program of the Federal Government, nuclear power plants in the world, nuclear fusion, nuclear liability up to the nuclear fuel cycle and the shutdown of nuclear power plants. (HSCH) [de

  7. Nuclear power and nuclear weapons

    International Nuclear Information System (INIS)

    Vaughen, V.C.A.

    1983-01-01

    The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described

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

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez R, J T

    1992-06-15

    In this work the implementation of a modification of the Varskin code for calculation of absorbed dose by contamination in skin imparted by external radiation fields generated by beta emitting is presented. The necessary data for the execution of the code are: isotope, dose depth, isotope activity, geometry type, source radio and time of integration of the isotope, being able to execute combinations of up to five radionuclides. This program it was implemented in Fortran 5 by means of the FFSKIN source program and the executable one in binary language BFFSKIN being the maximum execution time of 5 minutes. (Author)

  9. Acerca del moho

    Science.gov (United States)

    El moho forma parte del medio ambiente natural. Afuera del hogar, el moho juega un papel en la naturaleza al desintegrar materias organicas tales como las hojas que se han caido o los arboles muertos. El moho puede crecer adentro del hogar cuando las espor

  10. Del bit al qubit

    OpenAIRE

    Torras Font, Josep

    2011-01-01

    Aquest document pretén donar una visió del desenvolupament dels computadors electrònics i dels components que els han fet possibles. Dintre de les opcions de futur en computació, també intenta donar una visió de les bases en que es fonamenta la computació quàntica.

  11. Nuclear rights - nuclear wrongs

    Energy Technology Data Exchange (ETDEWEB)

    Paul, E.F.; Miller, F.D.; Paul, J.; Ahrens, J.

    1986-01-01

    This book contains 11 selections. The titles are: Three Ways to Kill Innocent Bystanders: Some Conundrums Concerning the Morality of War; The International Defense of Liberty; Two Concepts of Deterrence; Nuclear Deterrence and Arms Control; Ethical Issues for the 1980s; The Moral Status of Nuclear Deterrent Threats; Optimal Deterrence; Morality and Paradoxical Deterrence; Immoral Risks: A Deontological Critique of Nuclear Deterrence; No War Without Dictatorship, No Peace Without Democracy: Foreign Policy as Domestic Politics; Marxism-Leninism and its Strategic Implications for the United States; Tocqueveille War.

  12. Nuclear moments

    CERN Document Server

    Kopferman, H; Massey, H S W

    1958-01-01

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

  13. An Appraisal of Analytical Methods for Plutonium and their Applications to the Analysis of Nuclear Materials; Evaluation des Methodes Analytiques de Dosage du Plutonium et de Leur Application a l'Analyse des Matieres Nucleaires; Otsenka analiticheskikh metodov opredeleniya plutoniya i ikh primenenie dlya analiza yadernykh materialov; Metodos Analiticos de Determinacion del Plutonio y su Empleo en el Analisis de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Milner, G. W.C.; Phillips, G. [Atomic Energy Research Establishment, Harwell, Berks. (United Kingdom)

    1966-02-15

    respectifs de la dissolution dans des melanges d'acides mineraux courants et de la dissolution faisant appel a des procedes de fusion, avec des exemples a l'appui. Les auteurs decrivent aussi les procedes utilises et les resultats obtenus, pour l'analyse des alliages Pu-U, Pu-Ce-Co et Pu-U-Mo, des oxydes et carbures de Pu-U, et des cermets de carbure de Pu-U contenant Fe, Mo et Cr. Ces matieres sont l'aboutissement de recherches metallurgiques destinees a mettre au point des combustibles nucleaires. (author) [Spanish] Para determinar el contenido de plutonio de los materiales nucleares existen diversos metodos. Si se trata de cantidades del orden del miligramo se pueden emplear la espectrofotometria diferencial por el color del Pu (III), la gravimetria basada en el PuO2{sub ,} si recuento gamma y metodos de oxidorreduccion como las valoraciones potenciometricas o amperimetricas y la culombiometria de potencial controlado. Si se trata de microgramos son preferibles el recuento alfa, la dilucion isotopica o las tecnicas polarograficas. Teniendo en cuenta que unos metodos son mas adecuados que otros para ciertos tipos de muestra, el analista tiene que resolver un dificil problema de seleccion a fin de obtener ios mejores resultados posibles. Los autores exponen las ventajas y las limitaciones puestas de manifiesto por los anos de experiencia en la A.E.R.E. y formulan observaciones acerca de la exactitud y la precision de los metodos, su sensibilidad y otras cuestiones de especial interes. Como algunos de esos metodos exigen la separacion previa del plutonio, los autores estudian el empleo de las tecnicas de intercambio anionico y de cromatografia en fase inversa, y en particular su conveniencia para el analisis de muestras radiactivas. Examinan los muchos problemas que han surgido al analizar por estos metodos, aleaciones, productos ceramicos y cermets de plutonio en diversos sistemas que contenian uranio, torio, hierro, cromo, molibdeno, cerio y cobalto. La memoria trata

  14. Algunas aclaraciones acerca del conocimiento del singular.

    Directory of Open Access Journals (Sweden)

    Carlos Llano Cifuentes

    2013-11-01

    Full Text Available Llano tries to explain the main purpose of El Conocimiento del Singular, showing how the individuals about which the book is concerned are basically human individuals: people as decision makers.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

  16. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2005-01-01

    This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

  17. Monte Carlo simulation of the dose distribution around the {sup 125}I model 6711 seed as function of radius of the silver cylinder using the Penelope code; Simulacion por el Metodo de Monte Carlo de la distribucion de dosis alrededor de la semilla de {sup 125}I modelo 6711 en funcion del radio del cilindro de plata usando el codigo Penelope

    Energy Technology Data Exchange (ETDEWEB)

    Nerio, U. [Universidad de Cordoba, Monteria (Colombia); Instituto Nacional de Cancerologia, Bogota (Colombia); Chica, L. [Universidad Nacional de Colombia, Bogota (Colombia); Paul, A. [Universite de la Mediterranee, Marseille (France)

    2004-07-01

    The Monte Carlo method is applied to find the dose rates distribution in tissue around {sup 125} I seeds model 6711 as a function of the silver cylinder radius, R{sub sc} (0.017, 0.021, 0.025, 0.029 and 0.033) cm are used as radius values. It is found here that the dose rate at any point within the tissue decreases as R{sub sc} increases. The relative difference of dose rate that produced by the standard R{sub sc} seed, is less than 5%, for seeds with Rsc between 0.017 and 0.033 cm. (author)

  18. Simulation of the fault transitory of the feedwater controller in a Boiling water reactor with the Ramona-3B code; Simulacion del transitorio de falla del controlador de agua de alimentacion en un reactor de agua en ebullicion con el codigo RAMONA-3B

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, J.L.; Ortiz V, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2005-07-01

    The obtained results when carrying out the simulation of the fault transitory of the feedwater controller (FCAA) with the Ramona-3B code, happened in the Unit 2 of the Laguna Verde power plant (CNLV), in September of the year 2000 are presented. The transitory originates as consequence of the controller's fault of speed of a turbo pump of feedwater. The work includes a short description of the event, the suppositions considered for the simulation and the obtained results. Also, a discussion of the impact of the transitory event is presented on aspects of reactor safety. Although the carried out simulation is limited by the capacities of the code and for the lack of available information, it was found that even in a conservative situation, the power was incremented only in 12% above the nominal value, while that the thermal limit determined by the minimum reason of the critical power, MCPR, always stayed above the limit values of operation and safety. (Author)

  19. User manual of Visual Balan V. 1.0 Interactive code for water balances and refueling estimation; Manual del usuario del programa Visual Balan V. 1.0. Codigo interactivo para la realizacion de balances hidrologicos y la estimacion de la recarga

    Energy Technology Data Exchange (ETDEWEB)

    Samper, J.; Huguer, L.; Ares, J.; Garcia, M. A. [Universidad de La Coruna (Spain)

    1999-07-01

    This document contains the Users Manual of Visual Balan V1.0, an updated version of Visual Balan V0.0 (Samper et al., 1997). Visual Balan V1.0 performs daily water balances in the soil, the unsaturated zone and the aquifer in a user-friendly environment which facilitates both the input data process and the postprocessing of results. The main inputs of the balance are rainfall and irrigation while the outputs are surface runoff, evapotranspiration, interception, inter flow and groundwater flow. The code evaluates all these components in a sequential manner by starting with rainfall and irrigation, which must be provided by the user, and continuing with interception, surface runoff, evapotranspiration, and potential recharge (water flux crossing the bottom of the soil). This potential recharge is the input to the unsaturated zone where water can flow horizontally as subsurface flow (inter flow) or vertically as percolation into the aquifer. (Author)

  20. Method to generate the first design of the reload pattern to be used with the Presto-B code in the simulation of the CNLV U-1 reactor; Metodo para generar el primer diseno del patron de recarga a ser utilizado con el codigo Presto-B, en la simulacion del reactor de la CNLV U-1

    Energy Technology Data Exchange (ETDEWEB)

    Montes T, J.L.; Cortes C, C.C. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1992-08-15

    This guide is applied for the reload pattern's formation for mirror symmetry of a core room and in accordance with the Control Cell core technique (of the english Control Cell Core - CCC) for the PRESTO-B code. (Author)

  1. Psicodrama del duelo.

    OpenAIRE

    José Antonio Espina Barrio; Marisol Filgueira Bouza

    1997-01-01

    La pérdida de rituales agrava y alarga la reacción del duelo. Se define el Psicodrama Antropológico y su intervención en el proceso del duelo. El Psicodrama Focal del Duelo es una psicoterapia breve centrada en el proceso de Duelo. Se comentan varios casos y resultados. Se concluye con un programa sencillo para el duelo en Atención Primaria.

  2. Fractura triple del complejo suspensorio del hombro

    Directory of Open Access Journals (Sweden)

    Eraclio Delgado Rifá

    2015-06-01

    Full Text Available El complejo suspensorio del hombro es una estructura sumamente importante, compuesta por un anillo de huesos y tejidos blandos. Las lesiones aisladas de este complejo anatómico son frecuentes y no afectan su estabilidad. La interrupción doble conduce a la inestabilidad de esta estructura y usualmente requiere tratamiento quirúrgico. La triple interrupción, por su parte, es sumamente rara y es encontrada en casos de trauma de alta energía a menudo en asociación con otras lesiones. Se presenta una triple lesión del complejo suspensorio del hombro en un paciente de 46 años de edad, con una fractura de la glenoides, del acromion tipo III de Kuhn y de la coracoides tipo II de Ogawa. En este caso, la fractura del acromion fue tratada con fijación percutánea con alambres de Kirschner, por tener asociado lesiones de partes blandas que contraindicaron la reducción abierta. La fractura de la glenoides y de la apófisis coracoides fueron tratadas conservadoramente. Después de 6 meses de evolución, el paciente tuvo un resultado funcional aceptable, con una abducción de 90 grados, los 30 grados de rotación externa y 70 de rotación interna, además asintomático y consolidación de todas las fracturas. A pesar de ser catalogada de una lesión grave del cinturón escapular y estar asociada a otras lesiones se obtuvo un resultado satisfactorio al final del tratamiento.

  3. Vigencia del Darwinismo

    OpenAIRE

    Lessa, Enrique P

    2009-01-01

    En este ensayo se presenta una revisión histórica del signifcado y legado del darwinismo, con énfasis en el último siglo. La principal conclusión es que la visión darwiniana de la evolución, con las modifcaciones requeridas para dar cuenta de los grandes desarrollos de la disciplina, se ha impuesto y mantiene vigencia en nuestros días. En particular, el papel del azar, la evolución como proceso de “descendencia con modifcación” a lo largo de diversas ramas del árbol de la vida, el pensamiento...

  4. Nuclear science

    International Nuclear Information System (INIS)

    1989-01-01

    This fact sheet answers specific questions about the Department of Energy's possible acquisition and conversion of a partially completed commercial nuclear power plant to a nuclear materials production facility. The nuclear power plant is the Washington Nuclear Plant number sign 1 owned by the Washington Public Power Supply System and is located on DOE's Hanford Reservation near Richland, Washington

  5. Nuclear science

    International Nuclear Information System (INIS)

    1989-04-01

    This report answers questions about the Department of Energy's possible acquisition and conversion of a partially completed commercial nuclear power plant to a nuclear materials production facility. The nuclear power plant is the Washington Nuclear Plant No.1 owned by the Washington Public Power Supply System and is located on DOE's Hanford Reservation near Richland, Washington

  6. Nuclear medicine

    International Nuclear Information System (INIS)

    Lentle, B.C.

    1986-01-01

    Several growth areas for nuclear medicine were defined. Among them were: cardiac nuclear medicine, neuro-psychiatric nuclear medicine, and cancer diagnosis through direct tumor imaging. A powerful new tool, Positron Emission Tomography (PET) was lauded as the impetus for new developments in nuclear medicine. The political environment (funding, degree of autonomy) was discussed, as were the economic and scientific environments

  7. Nuclear option

    Energy Technology Data Exchange (ETDEWEB)

    Kemm, K R

    1978-05-01

    The global outlook is that nuclear reactors are here to stay and South Africa has already entered the nuclear power stakes. This article discusses the rocketing oil prices, and the alternatives that can be used in power generation, the good safety record of the nuclear industry and the effect that South Africa's first nuclear power station should have on the environment.

  8. Nuclear resisters

    International Nuclear Information System (INIS)

    1981-01-01

    The booklet contains six papers by different authors, under the headings: dangers along the nuclear fuel cycle; the nuclear profiteers; the nuclear state is a police state; a non-disposable future (renewable energy sources, energy conservation); nuclear weapons - out of control; man made madness. (U.K.)

  9. Nuclear links

    International Nuclear Information System (INIS)

    1981-01-01

    The subject is dealt with in sections: introduction; energy and the third world; world energy consumption 1978; oil -the energy dilemma; nuclear chains - introduction; uranium; Namibia; enrichment and reprocessing; countries with enrichment and reprocessing facilities; waste; conclusion; why take the nuclear option; third world countries with nuclear reactors; the arms connection; government spending and human resources 1977 (by countries); nuclear power - the final solution; the fascists; world bank; campaigns; community action in Plogoff; Australian labour movement; NUM against nuclear power; Scottish campaign; students against nuclear energy; anti-nuclear campaign; partizans; 3W1 disarmament and development; campaign ATOM; CANUC; 3W1; SANE. (U.K.)

  10. Identificación de biotipos de Spodoptera frugiperda (Lepidoptera: Noctuidae) en los departamentos de Córdoba, Meta, Tolima y Valle del Cauca mediante el gen mitocondrial Citocromo Oxidasa I (COI) y la región nuclear FR

    OpenAIRE

    Cano Calle, Daniela

    2015-01-01

    Resumen: Spodoptera frugiperda (J. E. Smith, 1797) es un insecto plaga del maíz, arroz, algodón, sorgo y pastizales. Presenta dos formas biológicas (biotipos o razas) (maíz y arroz) que son idénticas morfológicamente, pero que difieren en varios aspectos tales como su composición genética, su aislamiento reproductivo y su tolerancia a insecticidas y controladores biológicos. En este trabajo se realizó la identificación molecular de estos biotipos a partir de larvas recolectadas en cultivos de...

  11. Modernization of the feedwater heaters control level of the Almaraz I Nuclear Power Plant by OVATION system; Modernizacion del control de nivel de los calentadores de agua de alimentacion de C.N. Almaraz I mediante el sistema OVATION

    Energy Technology Data Exchange (ETDEWEB)

    Madronal Rodriguez, E.; Cabrero Munoz, J. E.

    2010-07-01

    As a result of the process of technological renovation of the heaters system and the power increase project, Almaraz Nuclear Power Plant has made several design changes in the feedwater heaters system. Within these changes, the old heaters control loops are replaced because the new power will increase the heaters drainage caudal. This modernization is carried out using the OVATION control system.

  12. La luz del origen del universo

    Directory of Open Access Journals (Sweden)

    Casas, Alberto

    2015-10-01

    Full Text Available Penzias and Wilson discovered the cosmic microwave background, a luminous echo of the Big Bang, in 1965. The amount of information encoded in this relic of the early universe is truly extraordinary. At present, the most precise data about the origin and structure of the universe comes from the study of this primordial light, the full potential of which has yet to be explored.En 1965 se descubrió el fondo de radiación de microondas, un eco luminoso de la Gran Explosión (Big Bang. La cantidad de información contenida en esta reliquia del universo primitivo es verdaderamente extraordinaria. En la actualidad los datos más precisos sobre el origen y estructura del universo provienen del estudio de esta luz primigenia, que aún no ha sido explorada en todo su potencial.

  13. Detección de mutacarcinógenos en aguas del Río Pantanillo y efecto genotóxico de esta agua en el DNA nuclear y mitocondrial de células eucarióticas

    Directory of Open Access Journals (Sweden)

    Margarita Zuleta

    2000-02-01

    Full Text Available

    Las aguas negras procedentes de domicilios, hospitales, fábricas, estaciones de gasolina, etc, están cargadas de gran variedad de mutacarcinógenos, como el benzopireno y el antraceno que se forman durante la combustión y pirólisis del material orgánico y se agrupan como hidrocarburos policíclicos aromáticos (HPA, además de las nitrosaminas y aminas heterocíclicas que se generan por la descomposición térmica de alimentos ricos en proteínas y creatina, como la carne asada y frita.  Estos mutágenos también se encuentran en las cenizas, el vapor del aceite de fritos y en la orina y las heces de personas que consumen alimentos fritos y asados (Felton y Knize 1990; Zuleta et al, sin publicar. Las aguas negras del Retiro son tratadas en una planta de lodos activados y luego son vertidas en el río Pantanillo, el cual es el principal afluente de la represa La Fe. Ésta surte la planta de tratamiento de aguas la Ayurá, que distribuye agua potable a más de 2.000.000 de personas. Con el fin de conocer el tipo de mutágenos que pueden llegar al río Pantanillo y si la planta de tratamiento a base de lodos activados es eficiente en su retención, identificamos los mutágenos contenidos en las aguas negras antes y después de pasar por la planta. Además evaluamos su mutagenicidad, genotoxicidad y la inhibición de la síntesis del DNA.

    Hasta el presente hemos obtenido los siguientes resultados:

    ·         

  14. U Y 105 standard use of non sealed radioactive sources in nuclear medicine: approve for Industry energy and Mining Ministry 28/6/2002 Resolution; Norma UY 105 uso de fuentes radiactivas no selladas en Medicina Nuclear: Aprobada por Resolucion del Ministro de Industria Energia y Mineria de 28/6/2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-06-28

    Establish minimal requirements radiological safety for use non sealed radioactive sources in nuclear medicine.The present standard is used in operation or nuclear medicine practices using non sealed radioactive sources with diagnostic and therapeutic purposes in vivo and in vitro.

  15. IAEA Technical co-operation. A partner in development. Nuclear science serving people; La cooperation technique de l`AIEA. Un partenariat pour le developpement. La science nucleaire au service de l`humanite; La cooperacion tecnica del OIEA. Un socio para el desarrollo. La ciencia nuclear al servicio de la gente; Tekhnicheskoe sotrudnichestvo magateh. Partner v tselyakh razvitiya. Yadernaya nauka na sluzhbe chelovechestva

    Energy Technology Data Exchange (ETDEWEB)

    Kinley, D; Perez Vargaz, J

    1998-12-31

    This issue contains descriptions of IAEA technical cooperation programs in a variety of disciplines and locations. It includes articles on the eradication of Tsetse flies in Africa, biofertilizers for agriculture, new strains of rice, water resource management, pollution control for a sustainable environment, nuclear medicine, and ensuring nuclear reactor safety

  16. Archivo del Duelo

    OpenAIRE

    Ferrera, Tamara

    2010-01-01

    Photos taken from the Archive of Mourning following the March 11 terrorist attacks El Archivo del Duelo. Creación de un archivo etnográfico de los Atentados del 11 de marzo en Madrid. Ministerio de Educación y Ciencia HUM2005-03490.

  17. Displasias del seno

    Directory of Open Access Journals (Sweden)

    Ernesto Andrade Valderrama

    1971-04-01

    Full Text Available En general, las Displasias no se presentan antes de la iniciación del estímulo Gonadal y tienden a desaparecer con el climaterio. Se definen entonces como las afecciones benignas del Seno, de origen endocrino.

  18. El mito del zombi en la actualidad: desmembramiento sacrificial colectivo

    Directory of Open Access Journals (Sweden)

    Carcavilla Puey, Lorenzo

    2013-12-01

    Full Text Available For several decades the zombie myth maintained the same symbolic structure as literature and cinematography regarding the perverse use of animal magnetism and hypnosis, the genealogy from which it descends. In the last third of twentieth century the myth underwent a profound transformation, which nevertheless represented a continuation of its previous unconscious meaning. The analysis of the new archetypal elements that it included, closely related to a nuclear aspect of the spirit of twentieth century art, enables us to develop an interpretive approach to a mythical framework and its underlying psychological process currently running through the collective psyche: respectively, the initiation death and the solvent and disintegrative dynamic of the soul. It will be based in the analytical psychology theoretical framework and we will use the historical-comparative method.El mito del zombi conservó durante varias décadas la misma estructura simbólica que la literatura y cinematografía acerca del uso perverso del magnetismo animal y la hipnosis, su genealogía. En el último tercio del siglo XX el mito sufre una profunda transformación que, no obstante, supone la continuación de su anterior sentido inconsciente. El análisis de los nuevos elementos arquetípicos que va a incorporar, estrechamente relacionados con un aspecto nuclear del espíritu del arte del siglo XX, nos va a permitir realizar una aproximación interpretativa a cierto entramado mítico y su proceso psicológico subyacente que atraviesa actualmente la psique colectiva: la muerte iniciática y la dinámica disolvente y desintegradora del alma, respectivamente. Nos basaremos para ello en el marco teórico de la psicología analítica y haremos uso del método histórico-comparativo.

  19. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part I; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del I

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  20. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part II; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del II

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  1. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part III; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del III

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

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

    Energy Technology Data Exchange (ETDEWEB)

    Bru, A

    1975-07-01

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

  3. Nuclear Power

    International Nuclear Information System (INIS)

    Douglas-Hamilton, J.; Home Robertson, J.; Beith, A.J.

    1987-01-01

    In this debate the Government's policy on nuclear power is discussed. Government policy is that nuclear power is the safest and cleanest way of generating electricity and is cheap. Other political parties who do not endorse a nuclear energy policy are considered not to be acting in the people's best interests. The debate ranged over the risks from nuclear power, the UK safety record, safety regulations, and the environmental effects of nuclear power. The Torness nuclear power plant was mentioned specifically. The energy policy of the opposition parties is strongly criticised. The debate lasted just over an hour and is reported verbatim. (UK)

  4. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  5. Experiences in the implementation of the Coaching project in the nuclear power plant of Laguna Verde (NPP-L V); Experiencias en la implementacion del proyecto Coaching en la Central Nucleoelectrica Laguna Verde (CNLV)

    Energy Technology Data Exchange (ETDEWEB)

    Mendez M, H. I., E-mail: hugo.mendez01@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Departamento del Centro de Entrenamiento, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

    2012-10-15

    This document has the purpose of to share acquired experiences during the implementation of the Coaching project focused the training of supervisors and directive personnel of the nuclear power plant of Laguna Verde (NPP-L V). Derived of the improvement areas identified by the supervisor organization of the nuclear power stations WANO (World Association Nuclear of Operators) and of the auto-evaluations realized by the expert personnel of the same power station that based on external experiences carried out through the Benchmarking (comparison with other power stations) they have reflected the necessity to activate a training process in Coaching with a practical focus toward the directive and supervisor personnel in the power station. By means of the observation of the personnel's acting so much in the control rooms like in different areas, three focus areas have been identified for the training in Coaching, these are the personnel's motivation, the organizational communication so much in vertical form as horizontal and the perception of confidence lack among directive, supervisors, operators and technicians. The plan focused in the abilities training of Coaching with practical sense was development, supported with an evaluation of 360 grades as tool of competitions development through a computer application e-Coaching. The use of application and Coaching following techniques facilitated the conformation of the practical focus, same that are of continuous use starting from the training of the supervisor and directive personnel. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-01

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

  7. LINK codes TRAC-BF1/PARCSv2.7 in LINUX without external communication interface; Acoplamiento de los codigos TRAC-BF1/PARCSv2.7 en Linux sin interfaz externa de comunicacion

    Energy Technology Data Exchange (ETDEWEB)

    Barrachina, T.; Garcia-Fenoll, M.; Abarca, A.; Miro, R.; Verdu, G.; Concejal, A.; Solar, A.

    2014-07-01

    The TRAC-BF1 code is still widely used by the nuclear industry for safety analysis. The plant models developed using this code are highly validated, so it is advisable to continue improving this code before migrating to another completely different code. The coupling with the NRC neutronic code PARCSv2.7 increases the simulation capabilities in transients in which the power distribution plays an important role. In this paper, the procedure for the coupling of TRAC-BF1 and PARCSv2.7 codes without PVM and in Linux is presented. (Author)

  8. Incorporation of the variation in conductivity with burnup in the stability of code predictive LAPUR; Incroporacion de la variacion de la conductividad con el quemado en el codigo de estabilidad predictivo LAPUR

    Energy Technology Data Exchange (ETDEWEB)

    Escriba, A.; Munoz-cobo, J. L.; Merino, R.; Melara, J.; Albendea, M.

    2013-07-01

    In the field of nuclear safety, the analysis of the stability of boiling water reactors is one of the biggest challenges for researchers. LAPUR code that allows to obtain the parameters of stability of the plant (Decay rate and frequency), being one of the programs used by IBERDROLA can be used for these calculations. With the collaboration of the research group TIN of the Polytechnic University of Valencia, a model of loss of conductivity of uranium has joined with the burned LAPUR. This update allows you to play the phenomenon in a more realistic way. This improvement has been validated and verified contrasting results with reference values.

  9. Lateral hydraulic forces calculation on PWR fuel assemblies with computational fluid dynamics codes; Calculo de fuerzas laterales hidraulicas en elementos combustibles tipo PWR con codigos de dinamica de fluidos coputacional

    Energy Technology Data Exchange (ETDEWEB)

    Corpa Masa, R.; Jimenez Varas, G.; Moreno Garcia, B.

    2016-08-01

    To be able to simulate the behavior of nuclear fuel under operating conditions, it is required to include all the representative loads, including the lateral hydraulic forces which were not included traditionally because of the difficulty of calculating them in a reliable way. Thanks to the advance in CFD codes, now it is possible to assess them. This study calculates the local lateral hydraulic forces, caused by the contraction and expansion of the flow due to the bow of the surrounding fuel assemblies, on of fuel assembly under typical operating conditions from a three loop Westinghouse PWR reactor. (Author)

  10. Analysis of the behavior of the flow of refrigerant through the bottom head and the impact of the removal of holes in the side panel of the MAEF-2012 with the code CFD STAR-CCM+; Analisis del comportamiento del flujo de refrigerante a traves del cabezal inferior y el impacto de la supresion de los taladros en el faldon lateral del MAEF-2012 con el codigo CFD STAR-CCM+

    Energy Technology Data Exchange (ETDEWEB)

    Barrera, J.; Corpa, R.

    2013-07-01

    The scope of this work consists in the study of different pairs of lower headers with a dynamical code detail like the STAR-CCM + v8, to identify and study the consequences of changes in the distribution of flow and variation in the pressure drop of fluid passing through them, as well as check the absence of impact from the point of view of safety.

  11. La crisi del diritto del lavoro

    Directory of Open Access Journals (Sweden)

    Alessandro Garilli

    2012-01-01

    Full Text Available Riassunto - L’Autore ripercorre in chiave critica l’evoluzione delle politiche legislative in materia di lavoro, alla luce dell’attuale fase di crisi economico finanziaria. Nell’esaminare i principali interventi normativi attuati da inizio secolo, l’Autore mette in evidenza le scelte di metodo e gli elementi di continuità che accomunano i vari provvedimenti, individuandoli nell’affannosa ricerca del punto di equilibrio tra flessibilità e garantismo. La riflessione si chiude con alcuni interrogativi sulle ultime linee di riforma del mercato del lavoro e con l’auspicio che, anche al cospetto delle imprescindibili ragioni dell’economia, il diritto del lavoro possa continuare a svolgere il proprio tradizionale ruolo di disciplina di tutela della persona.   Abstract - The author analyzes, with a critically oriented approach, the development of the employment law, in the light of the current economic and financial crisis. In examining the main regulatory measures implemented since the beginning of the century, the author highlights the methodological choices and the elements of continuity that unite the various measures, focusing them in a hard research of a point of balance between flexibility and security. The discussion concludes with some questions about the last lines of the reform of the labor market and with the hope that, even in the face of compelling reasons of economy, labor law can continue to play its traditional role of governing the protection of person.

  12. OBJETIVO DEL DESARROLLO DEL MILENIO 7

    Directory of Open Access Journals (Sweden)

    Margarita M. Pérez O.

    2013-10-01

    Full Text Available Los Objetivos de Desarrollo del Milenio, también conocidos como los Objetivos del Milenio, constituyeron las metas finales que aprobaron los dirigentes mundiales, 189 jefes de estado y de gobierno en la Cumbre del Milenio de las Naciones Unidas celebrada en Nueva York en el año 2000, en la cual los Estados miembros de la organización reafirmaron su compromiso de luchar por un mundo en el que el desarrollo sostenible y la eliminación de la pobreza tuvieran máxima prioridad1 . En la cumbre se definió la Declaración del Milenio, la cual detalla los objetivos, principios, valores, metas y acciones para erradicar la pobreza Mundial hacia el año 2015, todos ellos ratificados con alto interés y acción estratégica de carácter global, como marco para la medición de los progresos en materia de desarrollo.

  13. Elementos del sistema electoral del Congreso Mexicano

    Directory of Open Access Journals (Sweden)

    Aldo Medina García

    2013-08-01

    Full Text Available El presente artículo es un estudio de los componentes del sistema electoral, diseñado por el legislador mexicano para integrar al parlamento federal. Estudio desarrollado a sabiendas de la importancia que reviste el sistema electoral como un medio que permite a los ciudadanos convertir su voto expresado en las urnas en escaños a favor de determinado candidato o partido. En dicho análisis tomamos en cuenta la evolución constitucional del sistema electoral mexicano, la participación de las fuerzas minoritarias en la integración del Senado y de la Cámara de Diputados, la división que se hace del territorio en circunscripciones electorales, la barrera electoral que se fija a los partidos políticos para acceder a la representación en el Parlamento, la fórmula de asignación que se aplica a la votación obtenida, para finalmente concluir que el sistema electoral mexicano es esencialmente mayoritario aun cuando se vista de proporcional.

  14. Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2; Actas del 3. Congreso Regional sobre Seguridad Radiologica y Nuclear. Proteccion Radiologica en America Latina y el Caribe. Vol. 1,2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    Two volumes contain more than 183 complete papers presented during the Third Regional Meeting on Radiological Protection and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin american specialist talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation.

  15. JPRS Report, Nuclear Developments

    National Research Council Canada - National Science Library

    1991-01-01

    Partial Contents: Medium Range Missiles, Rocket Engine, Nuclear Submarine, Nuclear Reactor, Nuclear Inspection, Nuclear Weapons, Transfer Technology, Scud, Safety, Nuclear Power, Chernobyl Trial, ,CHemical Weapons...

  16. Simulation of the flow obstruction of a jet pump in a BWR reactor with the code RELAP/SCDAPSIM; Simulacion de la obstruccion de flujo de una bomba jet en un reactor BWR con el codigo RELAP/SCDAPSIM

    Energy Technology Data Exchange (ETDEWEB)

    Cardenas V, J.; Filio L, C., E-mail: jaime.cardenas@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

    This work simulates the flow obstruction of a jet pump in one of the recirculation loops of a nuclear power plant with a reactor of type BWR at 100% of operating power, in order to analyze the behavior of the total flow of the refrigerant passing through the reactor core, the total flow in each recirculation loop of the reactor, together with the 10 jet pumps of each loop. The behavior of the power and the reactivity insertion due to the change of the refrigerant flow pattern is also analyzed. The simulation was carried out using the RELAP/SCDAPSIM version 3.5 code, using a reactor model with 10 jet pumps in each recirculation loop and a core consisting of 6 radial zones and 25 axial zones. The scenario postulates the flow obstruction in a jet pump in a recirculation loop A when the reactor operates at 100% rated power, causing a change in the total flow of refrigerant in the reactor core, leading to a decrease in power. Once the reactor conditions are established to its new power, the operator tries to recover the nominal power using the flow control valve of the recirculation loop A, opening stepwise as a strategy to safely recover the reactor power. In this analysis is assumed that the intention of the nuclear plant operator is to maintain the operation of the reactor during the established cycle. (Author)

  17. Solution to the transport equation with anisotropic dispersion in a BWR type assembly using the AZTRAN code; Solucion de la ecuacion de transporte con dispersion anisotropica en un ensamble tipo BWR usando el codigo AZTRAN

    Energy Technology Data Exchange (ETDEWEB)

    Chepe P, M. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, San Rafael Atlixco No. 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico); Xolocostli M, J. V.; Gomez T, A. M. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E., E-mail: liaison.web@gmail.com [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Col. San Pedro Zacatenco, 07730 Ciudad de Mexico (Mexico)

    2016-09-15

    Due to the current computing power, the deterministic codes for analyzing nuclear reactors that have been used for several years are becoming more relevant, since much more precise solution techniques can be used; the last century would have been very difficult, since memory and processor capacities were very limited or had high prices on the components. In this work we analyze the effect of the anisotropic dispersion of the effective dispersion section, compared to the isotropic dispersion. The anisotropy implementation was carried out in the AZTRAN transport code, which is part of the AZTLAN platform for nuclear reactors analysis (in development). The AZTRAN code solves the Boltzmann transport equation in one, two and three dimensions at steady state, using the multi-group technique for energy discretization, the RTN-0 nodal method in spatial discretization and for angular discretization the discrete ordinates without considering anisotropy originally. The effect of the anisotropy dispersion on the effective multiplication factor and the axial and radial power on a fuel assembly BWR type are analyzed. (Author)

  18. The use of best estimate codes to improve the simulation in real time; El uso de codigos best estimate y de entornos disenados para mejorar su productividad en simulacion en tiempo real

    Energy Technology Data Exchange (ETDEWEB)

    Rivero, N.; Esteban, J. A.; Lenhardt, G.

    2007-07-01

    Best estimate codes are assumed to be the technology solution providing the most realistic and accurate response. Best estimate technology provides a complementary solution to the conservative simulation technology usually applied to determine plant safety margins and perform security related studies. Tecnatom in the early 90's, within the MAS project, pioneered the initiative to implement best estimate code in its training simulators. Result of this project was the implementation of the first six-equations thermal hydraulic code worldwide (TRAC{sub R}T), running in a training environment. To meet real time and other specific training requirements, it was necessary to overcome important difficulties. Tecnatom has just adapted the Global Nuclear Fuel core Design code: PANAC 11, and is about to complete the General Electric TRACG04 thermal hydraulic code adaptation. This technology features a unique solution for nuclear plants aiming at providing the highest fidelity in simulation, enabling to consider the simulator as a multipurpose: engineering and training, simulation platform. Besides, a visual environment designed to optimize the models life cycle, covering both pre and post-processing activities, is in its late development phase. (Author)

  19. Nuclear forensics

    International Nuclear Information System (INIS)

    Venugopal, V.

    2010-01-01

    Nuclear forensics is the analysis of nuclear materials recovered from either the capture of unused materials, or from the radioactive debris following a nuclear explosion and can contribute significantly to the identification of the sources of the materials and the industrial processes used to obtain them. In the case of an explosion, nuclear forensics can also reconstruct key features of the nuclear device. Nuclear forensic analysis works best in conjunction with other law enforcement, radiological protection dosimetry, traditional forensics, and intelligence work to provide the basis for attributing the materials and/or nuclear device to its originators. Nuclear forensics is a piece of the overall attribution process, not a stand-alone activity

  20. Nuclear power

    International Nuclear Information System (INIS)

    1987-01-01

    ''Nuclear Power'' describes how a reactor works and examines the different designs including Magnox, AGR, RBMK and PWR. It charts the growth of nuclear generation in the world and its contributions to world energy resources. (author)

  1. Nuclear Scans

    Science.gov (United States)

    Nuclear scans use radioactive substances to see structures and functions inside your body. They use a special ... images. Most scans take 20 to 45 minutes. Nuclear scans can help doctors diagnose many conditions, including ...

  2. Application of CSN Safety Guide on the content and criteria for the development of waste management plans at nuclear facilities; Aplicacion de la Guia de Seguridad del CSN sobre el contenido y criterio para la elaboracion de los planes de gestion de residuos en las instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez Alonso, M. A.; Simon Cirujano, M. I.

    2011-07-01

    The guide was developed with the joint participation and consensus of representatives of all Spanish companies who hold nuclear facilities and was implemented through a pilot project in the CN Jose Cabrera.

  3. Determination of Kr-85 in environmental samples and gaseous effluents from nuclear industries using the standard method; Aplicacion del metodo de concentracion separacion y medida radiactiva por centelleo liquido de Kr-85 en muestras ambientales y en efluentes gaseosos de la industria nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Heras, M c; Perez, M M

    1983-07-01

    The determination of the Kr-85 activity in environmental samples and gaseous effluents from Spanish Nuclear Power Stations is described. The method employed has been published elsewhere. The determinations has been carried out in environmental samples token at JEN Laboratories (Madrid) and the Nuclear Power Stations, Jose Cabrera (Zorita), Garona and Vandellos. Also samples of gaseous effluents of the three plants has been analyzed. Values of the Kr-85 environmental background activity in the Almaraz Nuclear Power Stations, has been determined, before the beginning of its nuclear activity. In this paper the sampling equipment used is described and the values found of Kr-85 activity in all the samples in given. (Author) 29 refs.

  4. Castillo del Real. Olocau

    OpenAIRE

    AUÑÓN VALLEJO, JONATAN

    2012-01-01

    El objetivo que se quiere alcanzar con este proyecto es el de realizar un estudio lo más cercano posible del Catillo del Real, de manera que se pueda conocer su origen, su evolución a lo largo de la historia, así como las diferentes técnicas y sistemas constructivos utilizados en su construcción. Auñón Vallejo, J. (2011). Castillo del Real. Olocau. http://hdl.handle.net/10251/14244. Archivo delegado

  5. La Representabilidad del Genocidio

    OpenAIRE

    Cardona González, Lorena

    2012-01-01

    El presente artículo intenta hacer una aproximación histórica y analítica al fenómeno del Genocidio, sus implicaciones sociales y culturales que dieron como resultado la reformulación analítica y conceptual de hechos que hasta entonces superaban el conocimiento y la moral humana. De este modo, se hace un trayecto histórico de la paulatina aparición del asesinato masivo como practica de Estado, enmarcado en las experiencias del genocidio armenio y el alemán. A su vez, se hace una mirada sobre ...

  6. Significado presente del CSIC

    OpenAIRE

    Garrido Gallardo, Miguel Angel

    2000-01-01

    Not available

    Este artículo, elaborado en 1999, ofrece una panorámica de la realidad del Consejo Superior de Investigaciones Científicas en la actualidad. Repasa su organización, su volumen de publicaciones, sus indicadores de productividad, su capacidad de obtener recursos y, en suma, su lugar en el conjunto del sistema español de Ciencia y Tecnología, considerado en sí mismo y en relación con la Universidad. Como conclusión del repaso de datos, se afirma que, aunque la fó...

  7. Tratamiento del pie equino

    OpenAIRE

    Robles, Fernanda

    2012-01-01

    El pie equino varo es una patología frecuente en los pacientes con Encefalopatía crónica no evolutiva (ECNE).Se observó que existe una mayor frecuencia en el sexo masculino. Se realizó un estudio descriptivo, comparativo y secundario, durante el periodo de septiembre del 2006 a septiembre del 2011, con un total de 125 pacientes con Ecne, de los cuales se encontraron 101 con pie equino varo congénito. Objetivo: observar los resultados obtenidos en la rehabilitación del pie equino, en niños de ...

  8. Del Pasadismo al Futurismo

    OpenAIRE

    Agudo-Martínez, M. J.

    2003-01-01

    Uno de los habituales prejuicios a la hora de abordar el análisis del movimiento futurista, al igual que sucede con el constructivismo, es la consideración del contexto político en el que se desarrollaron ambas vanguardias. Sin embargo, y dejando a un lado un enfoque del arte con finalidad política de signo diverso, habría que insistir en el hecho de que posiblemente sean tanto el futurismo italiano como el constructivismo ruso, los movimientos que con mayor entusiasmo se manifestaron, en un ...

  9. Nuclear energy

    International Nuclear Information System (INIS)

    Kuhn, W.

    1986-01-01

    This loose-leaf collection is made up of five didactically prepared units covering the following subjects: basic knowledge on nuclear energy, nuclear energy in relation to energy economy, site issues, environmental compatibility of nuclear energy, and nuclear energy in the focus of political and social action. To this was added a comprehensive collection of material: specific scientific background material, a multitude of tables, diagrams, charts etc. for copying, as well as 44 transparent charts, mostly in four colours. (orig./HP) [de

  10. Nuclear structure

    International Nuclear Information System (INIS)

    Eastham, D.A.; Joy, T.

    1986-01-01

    The paper on 'nuclear structure' is the Appendix to the Daresbury (United Kingdom) Annual Report 1985/86, and contains the research work carried out at the Nuclear Structure Facility, Daresbury, within that period. During the year a total of 74 experiments were scheduled covering the main areas of activity including: nuclear collective motion, nuclei far from stability, and nuclear collisions. The Appendix contains brief reports on these experiments and associated theory. (U.K.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Flores S, V. H.

    2011-07-01

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

  12. Nuclear terrorism

    International Nuclear Information System (INIS)

    2002-01-01

    Recent reports of alleged terrorist plans to build a 'dirty bomb' have heightened longstanding concerns about nuclear terrorism. This briefing outlines possible forms of attack, such as: detonation of a nuclear weapon; attacks involving radioactive materials; attacks on nuclear facilities. Legislation addressing these risks and the UK's strategy for coping with them are also considered

  13. Nuclear power

    International Nuclear Information System (INIS)

    d'Easum, Lille.

    1976-03-01

    An environmentalist's criticism of nuclear energy is given, on a layman's level. Such subjects as conflict of interest in controlling bodies, low-level radiation, reactor safety, liability insurance, thermal pollution, economics, heavy water production, export of nuclear technology, and the history of the anti-nuclear movement are discussed in a sensationalistic tone. (E.C.B.)

  14. Nuclear alerts

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    Anti-nuclear demonstrations against the deployment of new US missiles were held in Nato Europe. As no agreement has yet been reached at the US-Soviet Intermediate Nuclear Forces talks in Geneva, the deployment of nuclear missiles in Europe has started

  15. Nuclear questions

    International Nuclear Information System (INIS)

    Berg, Eugene

    2012-01-01

    Civilian and military nuclear questions fill a multitude of publications these days, especially after the Japanese tsunami and the Fukushima disaster. The author analyses some of them and highlights the links between civil and military nuclear industries, the realities of the nuclear cycle and related industrial questions before concluding on the controversial issue of weapons and their proliferation potential

  16. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The paper on nuclear decommissioning was presented by Dr H. Lawton to a meeting of the British Nuclear Energy Society and Institution of Nuclear Engineers, 1986. The decommissioning work currently being undertaken on the Windscale advanced gas cooled reactor (WAGR) is briefly described, along with projects in other countries, development work associated with the WAGR operation and costs. (U.K.)

  17. Nuclear electronics

    International Nuclear Information System (INIS)

    Friese, T.

    1981-09-01

    A short survey is given on nuclear radiation detectors and nuclear electronics. It is written for newcomers and those, who are not very familiar with this technique. Some additional information is given on typical failures in nuclear measurement systems. (orig.) [de

  18. Economic Aspects of Air and Gas Cleaning for Nuclear Energy Processes; Aspects Economiques de l'Epuration de l'Air et des Gaz au Cours des Operations Nucleaires; 042d 041a 041e 041d 041e 0414 0; Aspectos Economicos de la Depuracion del Aire y de los Gases en los Procesos de Obtencion de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Silverman, Leslie [Harvard School of Public Health, Boston, MA (United States)

    1960-07-01

    los que ciertos materiales nucleares no radiactivos dan origen a efluentes toxicos o nocivos que deben tambien ser evacuados sin incurrir en gastos excesivos. El autor describe con cierto detalle los factores que influyen en el precio de costo y en los gastos de funcionamiento de los equipos de depuracion de gases, asi como los diferentes sistemas utilizados en los Estados Unidos. Naturalmente, los problemas que plantean los efluentes gaseosos han sido abordados y resueltos mediante varios tipos de dispositivos, pero el rendimiento de estos ha podido medirse en terminos comparables. Por lo tanto, resulta posible evaluar los aspectos economicos relacionados con el consumo de energia, coste de los materiales adsorbentes, necesidades de espacio, problemas de corrosion y otras caracteristicas de funcionamiento de los aparatos. En virtud de un contrato concertado con el Laboratorio de Depuracion del Aire de la Universidad de Harvard, la Comision de Energia Atomica de los Estados Unidos ha iniciado un programa de evaluacion en cuya ejecucion cooperan diversos laboratorios y contratistas de la Comision. En la memoria se enumeran los factores basicos que se han de tener en cuenta para definir y analizar los costos y se presentan algunos resultados preliminares. Asimismo, se describen otros estudios de caracter economico llevados a cabo en los Estados Unidos sobre el empleo de determinados procesos o instalaciones. (author) [Russian] V nastojashhem doklade privodjatsja osnovnye trebovanija po kontrolju za gazovymi i zhidkimi obrazovanijami; jeti trebovanija kasajutsja problem proizvodstva ishodnyh produktov, razdelenija izotopov, proizvodstva toplivnyh jelementov, regeneracii gorjuchego i jekspluatacii reaktorov. Imejutsja takzhe sluchai, kogda neradioaktivnye jadernye materialy, obladajushhie toksichnost'ju ili neznachitel'nym zhidkostnym obrazovaniem (k nim, naprimer, otnosjatsja proizvodstvo berillija i cirkonija), predstavljajut interes, i na nih takzhe dolzhen

  19. Analysis of the accident at Fukushima Daiichi nuclear power plant in an A BWR reactor; Analisis del accidente de la planta nucleoelectrica de Fukushima Daiichi en un reactor tipo ABWR

    Energy Technology Data Exchange (ETDEWEB)

    Escorcia O, D. [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico); Salazar S, E., E-mail: daniel.escorcia.ortiz@gmail.com [UNAM, Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (Mexico)

    2016-09-15

    The present work aims to recreate the accident occurred at the Fukushima Daiichi nuclear power plant in Japan on March 11, 2011, making use of an academic simulator of forced circulation of the A BWR reactor provided by the IAEA to know the scope of this simulator. The simulator was developed and distributed by the IAEA for academic purposes and contains the characteristics and general elements of this reactor to be able to simulate transients and failures of different types, allowing also to observe the general behavior of the reactor, as well as several phenomena and present systems in the same. Is an educational tool of great value, but it does not have a scope that allows the training of plant operators. To recreate the conditions of the Fukushima accident in the simulator, we first have to know what events led to this accident, as well as the actions taken by operators and managers to reduce the consequences of this accident; and the sequence of events that occurred during the course of the accident. Differences in the nuclear power plant behavior are observed and interpreted throughout the simulation, since the Fukushima plant technology and the simulator technology are not the same, although they have several elements in common. The Fukushima plant had an event that by far exceeded the design basis, which triggered in an accident that occurred in the first place by a total loss of power supply, followed by the loss of cooling systems, causing a level too high in temperature, melting the core and damaging the containment accordingly, allowing the escape of hydrogen and radioactive material. As a result of the simulation, was determined that the scope of the IAEA academic simulator reaches the entrance of the emergency equipment, so is able to simulate almost all the events occurred at the time of the earthquake and the arrival of the tsunami in the nuclear power plant of Fukushima Daiichi. However, due to its characteristics, is not able to simulate later

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

    OpenAIRE

    Avella Moreno, Eliseo

    2011-01-01

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

  1. Study of the characteristic response of the pressure control system for the design parameters of the new turbine control system, MARK VI, in Cofrentes Nuclear Power Plant; Resultados del estudio de la respuesta caracteristica del sistema de control de presion para el Proyecto OCP-4300 Nuevo Sistema de Control de Turbina MARK VI en la C.N. Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Palomo anaya, M. J.; Ruiz Bueno, G.; Mora, J. A.; Vaquer, J. I.; Bucho, L.; Lopez, B.

    2010-07-01

    This paper presents the results of the study of the characteristic response of the ancient Pressure and Turbine Control System for the OCP-4300 Project in the Cofrentes Nuclear Power Plant, made by Titania Servicios Tecnologicos in collaboration with the Institute for Industrial, Radiophysical and Environmental Safety. This work was done as one of the preliminary work necessary for replacing the old control system by Mark VI.

  2. Determination of the detection efficiency of a HPGe detector by means of the MCNP 4A simulation code; Determinacion de la eficiencia de deteccion de un detector HPGe mediante el codigo de simulacion MCNP 4A

    Energy Technology Data Exchange (ETDEWEB)

    Leal, B. [Centro Regional de Estudios Nucleares, A.P. 579C, 98068 Zacatecas (Mexico)

    2004-07-01

    In the majority of the laboratories, the calibration in efficiency of the detector is carried out by means of the standard sources measurement of gamma photons that have a determined activity, or for matrices that contain a variety of radionuclides that can embrace the energy range of interest. Given the experimental importance that has the determination from the curves of efficiency to the effects of establishing the quantitative results, is appealed to the simulation of the response function of the detector used in the Regional Center of Nuclear Studies inside the energy range of 80 keV to 1400 keV varying the density of the matrix, by means of the application of the Monte Carlo code MCNP-4A. The adjustment obtained shows an acceptance grade in the range of 100 to 600 keV, with a smaller percentage discrepancy to 5%. (Author)

  3. Introduction to the simulation with MCNP Monte Carlo code and its applications in Medical Physics; Introduccion a la simulacion con el codigo de Monte Carlo MCNP y sus aplicaciones en Fisica Medica

    Energy Technology Data Exchange (ETDEWEB)

    Parreno Z, F.; Paucar J, R.; Picon C, C. [Instituto Peruano de Energia Nuclear, Av. Canada 1470, San Borja, Lima 41 (Peru)

    1998-12-31

    The simulation by Monte Carlo is tool which Medical Physics counts with it for the development of its research, the interest by this tool is growing, as we may observe in the main scientific journals for the years 1995-1997 where more than 27 % of the papers treat over Monte Carlo and/or its applications in the radiation transport.In the Peruvian Institute of Nuclear Energy we are implementing and making use of the MCNP4 and EGS4 codes. In this work are presented the general features of the Monte Carlo method and its more useful applications in Medical Physics. Likewise, it is made a simulation of the calculation of isodose curves in an interstitial treatment with Ir-192 wires in a mammary gland carcinoma. (Author)

  4. MCTP, a code for the thermo-mechanical analysis of a fuel rod of BWR type reactors (Neutron part); MCTP, un codigo para el analisis termo-mecanico de una barra combustible de reactores tipo BWR (Parte Neutronica)

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez L, H; Ortiz V, J [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    In the National Institute of Nuclear Research of Mexico a code for the thermo-mechanical analysis of the fuel rods of the BWR type reactors of the Nucleo electric Central of Laguna Verde is developed. The code solves the diffusion equation in cylindrical coordinates with several energy groups. The code, likewise, calculates the temperature distribution and power distribution in those fuel rods. The code is denominated Multi groups With Temperatures and Power (MCTP). In the code, the energy with which the fission neutrons are emitted it is divided in six groups. They are also considered the produced perturbations by the changes in the temperatures of the materials that constitute the fuel rods, the content of fission products, the uranium consumption and in its case the gadolinium, as well as the plutonium production. In this work there are present preliminary results obtained with the code, using data of operation of the Nucleo electric Central of Laguna Verde. (Author)

  5. Criticality calculations of a generic fuel container for fuel assemblies PWR, by means of the code MCNP; Calculos de criticidad de un contenedor de combustible generico para ensambles combustibles PWR, mediante el codigo MCNP

    Energy Technology Data Exchange (ETDEWEB)

    Vargas E, S.; Esquivel E, J.; Ramirez S, J. R., E-mail: samuel.vargas@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    The purpose of the concept of burned consideration (Burn-up credit) is determining the capacity of the calculation codes, as well as of the nuclear data associates to predict the isotopic composition and the corresponding neutrons effective multiplication factor in a generic container of spent fuel during some time of relevant storage. The present work has as objective determining this capacity of the calculation code MCNP in the prediction of the neutrons effective multiplication factor for a fuel assemblies arrangement type PWR inside a container of generic storage. The calculations are divided in two parts, the first, in the decay calculations with specified nuclide concentrations by the reference for a pressure water reactor (PWR) with enriched fuel to 4.5% and a discharge burned of 50 GW d/Mtu. The second, in criticality calculations with isotopic compositions dependent of the time for actinides and important fission products, taking 30 time steps, for two actinide groups and fission products. (Author)

  6. Preferencias del Turista

    Directory of Open Access Journals (Sweden)

    Jose Luis Leiva Olivencia

    2015-01-01

    Full Text Available Actualmente existen aplicaciones orientadas al turismo basadas en realidad aumentada, pero no integran técnicas de recomendación. Este articulo describe RAMCAT (Realidad Aumentada Móvil Contextual Aplicada al Turismo un modelo de guía turística, que recomienda puntos de interés, teniendo en cuenta factores como preferencias personales y atributos contextuales. Se presentan los componentes teóricos de la arquitectura propuesta, así como sus características, destacando la integración de diferentes sistemas de recomendación, que permiten añadir nuevos motores en el futuro. El articulo se centra en describir sus funcionalidades y el modulo correspondiente al sistema de recomendación basado en el perfil del turista. Otra característica importante del sistema propuesto es la retroalimentación del mismo mediante calificaciones del turista y su trazabilidad.

  7. Carta del Editor

    Directory of Open Access Journals (Sweden)

    Luis Eladio Proaño

    2015-01-01

    Full Text Available La millonaria contratación del futbolista David Beckham, un fenómeno del mercado, ha provocado cuestionamientos a los que se busca respuesta. Es tema de análisis el por qué el betseller "Harry Potter" ha causado tanta conmoción en la opinión pública. Respecto al periodista cibernético, se señalan los contornos del presente y atisban las posibilidades del futuro de esta nueva profesión. El tratamiento de los mitos de la prensa, los temores de la Ley mordaza venezolana y la brutalidad de los video juegos e Internet son temas de enorme interés. Se comenta las pocas veces que la prensa reflexiona sobre la comunicación corporal y la anorexia.

  8. Los muertos del Floreanismo

    Directory of Open Access Journals (Sweden)

    Enrique Ayala Mora

    2008-06-01

    Full Text Available El artículo analiza el crimen político durante las primeras décadas de vida de la República del Ecuador. Específicamente centra su estudio en el período dominado por la figura de Juan José Flores, primer presidente del Ecuador. La inestabilidad política, la precariedad de las alianzas entre las élites regionales, la crisis económica generada por las guerras de Independencia, las conspiraciones y la violencia que caracterizaron al período de surgimiento de las repúblicas andinas hicieron del crimen político un “vicio de nacimiento”. El asesinato del general Antonio José de Sucre, la muerte de los miembros de la sociedad El Quiteño Libre, el homicidio de Juan Otamendi, entre otros, hicieron patente esta característica.

  9. Niveles del aprendizaje organizacional

    OpenAIRE

    Garzón Castrillón, Manuel Alfonso

    2005-01-01

    En la propuesta de modelo de aprendizaje organizacional (AO), la segunda variable se denomina niveles del aprendizaje organizacional ; los niveles de aprendizaje que contemplamos para nuestra investigación son: individual, de equipo, organizacional e interorganizacional.

  10. La escritura del Yo

    Directory of Open Access Journals (Sweden)

    Patricio Landaeta Mardones

    2013-11-01

    Full Text Available Si la creación de una imagen fidedigna del mundo fue la condición de la conquista cognitiva y económica de la tierra, las imágenes mediáticas circulan hoy en día a la manera de un montaje que organiza los sujetos como elementos de un territorio. En esta presentación abordaremos el cruce entre estos dos hechos, entre la escritura del mundo y la de los sujetos, a partir de la idea de Fabulación para mostrar otra escritura del mundo y del yo, leyendo textos e imágenes de la Primera buena Corónica y Buen Gobierno de Felipe Guaman Poma de Ayala.

  11. Nuclear energy

    International Nuclear Information System (INIS)

    2007-01-01

    This digest document was written by members of the union of associations of ex-members and retired people of the Areva group (UARGA). It gives a comprehensive overview of the nuclear industry world, starting from radioactivity and its applications, and going on with the fuel cycle (front-end, back-end, fuel reprocessing, transports), the nuclear reactors (PWR, BWR, Candu, HTR, generation 4 systems), the effluents from nuclear facilities, the nuclear wastes (processing, disposal), and the management and safety of nuclear activities. (J.S.)

  12. Nuclear orientation and nuclear structure

    International Nuclear Information System (INIS)

    Krane, K.S.

    1988-01-01

    The present generation of on-line nuclear orientation facilities promises to revolutionize the gathering of nuclear structure information, especially for the hitherto poorly known and understood nuclei far from stability. Following a brief review of the technological developments that have facilitated these experiments, the nuclear spectroscopic information that can be obtained is summarized. Applications to understanding nuclear structure are reviewed, and challenges for future studies are discussed. (orig.)

  13. Consideraciones alrededor del Libro del Almismo, el Libro del Pensar.

    Directory of Open Access Journals (Sweden)

    MartaLucía Tamayo Fernandez

    1999-12-01

    Full Text Available

    La doctora MarthaLucía Tamayo comparte muchas inquietudes alrededor del Libro del Almismo, el Libro del Pensar; de dónde salió ese nombre; de juntar en medicina y en genética a tres escritores como lo son Jorge Luis Borges, Macedonio Fernández y Julio Cortázar. Su conferencia dice así:

    El término almismo fue ideado por Macedonio Fernández porque defendía mucho el ensimismamiento y el pensamiento hacia el interior, mirar hacia adentro; cada uno somos un “sí mismo” que nos hace diferentes aunque al mismo tiempo podemos ser iguales. Todos tenemos esa parte interior que la medicina debe trabajar y que no puede olvidar.

    “El Libro del Almismo, el libro del pensar” nos lleva a replantear y a repensar un poco la medicina que queremos, una medicina vuelta a pensar.

    Quiero contarles la historia de cómo se llegó a este libro y por qué y para qué se sigue trabajando en estos temas: Después de mi internado y de un trabajo un poco triste de rural, volví al Instituto de Genética y a la Universidad Javeriana en donde encontré al doctor Bernal y un espacio que estaba buscando para esa medicina diferente que quería, con un grupo de personas que me permitía no sólo ver la medicina sino ver muchas otras cosas más; había espacio para la literatura, para Mafalda, para hablar de niños, de locos, había incluso tiempo para hablar de medicina dentro del golf, de carros antiguos y de todo eso fui aprendiendo.

    Eso era lo que estaba buscando. Una medicina que diera espacios diferentes, que fuera más humanizada. Rápidamente me ubiqué y me quedé! No me arrepiento en lo absoluto de haberme quedado porque fue, ha sido y sigue siendo, una experiencia enriquecedora, de muchas vivencias importantes. Sabía exactamente dónde estaba y sabía que había que seguir rápido y había que trabajar muchos aspectos de esa medicina que estábamos buscando y de esa genética especial.

    Rápidamente empezamos a trabajar

  14. Actualidad del relativismo cultural

    OpenAIRE

    Sánchez Durá, Nicolás

    2013-01-01

    Este ensayo tiene tres propósitos. En primer lugar, propone examinar las relaciones entre etnocentrismo y relativismo. El etnocentrismo puede tomar tres formas distintas: a saber, la de una universalidad impostada, la del exotismo y la de un particularismo narcisista exacerbado. El relativismo cultural es una postura que asume la inconmensurabilidad de los conceptos y valores que deben ser considerados como válidos dentro de las imágenes del mundo definidas. En segundo lugar, se argumenta que...

  15. Nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The committee concludes that the nature of the proliferation problem is such that even stopping nuclear power completely could not stop proliferation completely. Countries can acquire nuclear weapons by means independent of commercial nuclear power. It is reasonable to suppose if a country is strongly motivated to acquire nuclear weapons, it will have them by 2010, or soon thereafter, no matter how nuclear power is managed in the meantime. Unilateral and international diplomatic measures to reduce the motivations that lead to proliferation should be high on the foreign policy agenda of the United States. A mimimum antiproliferation prescription for the management of nuclear power is to try to raise the political barriers against proliferation through misuse of nuclear power by strengthening the Non-Proliferation Treaty, and to seek to raise the technological barriers by placing fuel-cycle operations involving weapons-usable material under international control. Any such measures should be considered tactics to slow the spread of nuclear weapons and thus earn time for the exercise of statesmanship. The committee concludes the following about technical factors that should be considered in formulating nuclear policy: (1) rate of growth of electricity use is a primary factor; (2) growth of conventional nuclear power will be limited by producibility of domestic uranium sources; (3) greater contribution of nuclear power beyond 400 GWe past the year 2000 can only be supported by advanced reactor systems; and (4) several different breeder reactors could serve in principle as candidates for an indefinitely sustainable source of energy

  16. Nuclear physics

    International Nuclear Information System (INIS)

    Kamal, Anwar

    2014-01-01

    Explains the concepts in detail and in depth. Provides step-by-step derivations. Contains numerous tables and diagrams. Supports learning and teaching with numerous worked examples, questions and problems with answers. Sketches also the historical development of the subject. This textbook explains the experimental basics, effects and theory of nuclear physics. It supports learning and teaching with numerous worked examples, questions and problems with answers. Numerous tables and diagrams help to better understand the explanations. A better feeling to the subject of the book is given with sketches about the historical development of nuclear physics. The main topics of this book include the phenomena associated with passage of charged particles and radiation through matter which are related to nuclear resonance fluorescence and the Moessbauer effect., Gamov's theory of alpha decay, Fermi theory of beta decay, electron capture and gamma decay. The discussion of general properties of nuclei covers nuclear sizes and nuclear force, nuclear spin, magnetic dipole moment and electric quadrupole moment. Nuclear instability against various modes of decay and Yukawa theory are explained. Nuclear models such as Fermi Gas Model, Shell Model, Liquid Drop Model, Collective Model and Optical Model are outlined to explain various experimental facts related to nuclear structure. Heavy ion reactions, including nuclear fusion, are explained. Nuclear fission and fusion power production is treated elaborately.

  17. Nuclear chemistry

    International Nuclear Information System (INIS)

    Vertes, A.; Kiss, I.

    1987-01-01

    This book is an introduction to the application of nuclear science in modern chemistry. The first group of chapters discuss the basic phenomena and concepts of nuclear physics with emphasis on their relation to chemical problems, including the main properties and the composition of atomic nuclei, nuclear reactions, radioactive decay and interactions of radiation with matter. These chapters provide the basis for understanding the following chapters which encompass the wide scope of nuclear chemistry. The methods of the investigation of chemical structure based on the interaction of nuclear radiation with matter including positronium chemistry and other exotic atoms is elaborated in particular detail. Separate chapters are devoted to the use of radioactive tracers, the chemical consequences of nuclear processes (i.e. hot atom chemistry), radiation chemistry, isotope effects and their applications, and the operation of nuclear reactors

  18. Nuclear chemistry

    International Nuclear Information System (INIS)

    Vertes, A.; Kiss, I.

    1987-01-01

    This book is an introduction to the application of nuclear science in modern chemistry. The first group of chapters discuss the basic phenomena and concepts of nuclear physics with emphasis on their relation to chemical problems, including the main properties and the composition of atomic nuclei, nuclear reactions, radioactive decay and interactions of radiation with matter. These chapters provide the basis for understanding the following chapters which encompass the wide scope of nuclear chemistry. The methods of the investigation of chemical structure based on the interaction of nuclear radiation with matter including positronium chemistry and other exotic atoms is elaborated in particular detail. Separate chapters are devoted to the use of radioactive tracers, the chemical consequences of nuclear processes (i.e. hot atom chemistry), radiation chemistry, isotope effects and their applications, and the operation of nuclear reactors. (Auth.)

  19. Nuclear forensics

    International Nuclear Information System (INIS)

    Karadeniz, O.; Guenalp, G.

    2010-01-01

    This review discusses the methodology of nuclear forensics and illicit trafficking of nuclear materials. Nuclear forensics is relatively new scientific branch whose aim it is to read out material inherent from nuclear material. Nuclear forensics investigations have to be considered as part of a comprehensive set of measures for detection,interception, categorization and characterization of illicitly trafficking nuclear material. Prevention, detection and response are the main elements in combating illicit trafficking. Forensics is a key element in the response process. Forensic science is defined as the application of a broad spectrum of sciences to answer questions of interest to the legal system. Besides, in this study we will explain age determination of nuclear materials.

  20. Nuclear fuels

    International Nuclear Information System (INIS)

    Gangwani, Saloni; Chakrabortty, Sumita

    2011-01-01

    Nuclear fuel is a material that can be consumed to derive nuclear energy, by analogy to chemical fuel that is burned for energy. Nuclear fuels are the most dense sources of energy available. Nuclear fuel in a nuclear fuel cycle can refer to the fuel itself, or to physical objects (for example bundles composed of fuel rods) composed of the fuel material, mixed with structural, neutron moderating, or neutron reflecting materials. Long-lived radioactive waste from the back end of the fuel cycle is especially relevant when designing a complete waste management plan for SNF. When looking at long-term radioactive decay, the actinides in the SNF have a significant influence due to their characteristically long half-lives. Depending on what a nuclear reactor is fueled with, the actinide composition in the SNF will be different. The following paper will also include the uses. advancements, advantages, disadvantages, various processes and behavior of nuclear fuels

  1. Nuclear networking.

    Science.gov (United States)

    Xie, Wei; Burke, Brian

    2017-07-04

    Nuclear lamins are intermediate filament proteins that represent important structural components of metazoan nuclear envelopes (NEs). By combining proteomics and superresolution microscopy, we recently reported that both A- and B-type nuclear lamins form spatially distinct filament networks at the nuclear periphery of mouse fibroblasts. In particular, A-type lamins exhibit differential association with nuclear pore complexes (NPCs). Our studies reveal that the nuclear lamina network in mammalian somatic cells is less ordered and more complex than that of amphibian oocytes, the only other system in which the lamina has been visualized at high resolution. In addition, the NPC component Tpr likely links NPCs to the A-type lamin network, an association that appears to be regulated by C-terminal modification of various A-type lamin isoforms. Many questions remain, however, concerning the structure and assembly of lamin filaments, as well as with their mode of association with other nuclear components such as peripheral chromatin.

  2. el Valle del Cauca

    Directory of Open Access Journals (Sweden)

    Carlos Humberto Ortiz

    2007-01-01

    Full Text Available Este artículo se enfoca en la identi- ficación de aquellos factores estructurales que explican la pérdida de dinamismo económico de largo plazo en Colombia y, en particular, en el Valle del Cauca. Se examina la competitividad del Valle en relación con Colombia y con el resto del mundo. Se cuestiona la insistencia en una estrategia exportadora como dinamizadora del desarrollo económico. Se identifica que una gran parte de la población está excluida de los beneficios del desarrollo económico. Para construir un modelo de desarrollo que incluya a esta población se recomienda recuperar la senda de la industrialización, invertir en el capital humano (educación de alta calidad, salud, salubridad y nutrición, e invertir en infraestructura. La participación del Estado en estas inversiones sociales es necesaria para disminuir la desigualdad y aumentar el crecimiento económico.

  3. Espectroscopia del Cometa Halley

    Science.gov (United States)

    Naranjo, O.; Fuenmayor, F.; Ferrin, L.; Bulka, P.; Mendoza, C.

    1987-05-01

    Se reportan observaciones espectroscópicas del cometa Halley. Los espectros fueron tomados usando el espectrógrafo del telescopio reflector de 1 metro del Observatorio Nacional de Venezuela. Se utilizó óptica azul, con una red de difracción de 600 lineas/min, obteniéndose una dispersión de 74.2 A/mm y una resolución de 2.5 A, en el rango espectral de 3500 a 6500 A. Seis placas fueron tomadas con emulsión IIa-O y dos con IIa-D. Los tiempos de exposición fueron entre 10 y 150 minutos. El cometa se encontraba entre 0.70 y 1.04 UA del Sol, y entre 1.28 y 0.73 UA de la Tierra. Las emisiones más prominentes en el espectro, son las del CN, C2, y C3. Otras emisiones detectadas corresponden a CH, NH2 y Na. Los espectros muestran un fuerte continuo, indicando un contenido significativo de polvo. Se detectó mayor intensidad del contínuo, en la dirección anti solar, lo cual es evidencia de la cola de polvo.

  4. Inventario nacional del uso actual del agua

    OpenAIRE

    Oficina Nacional de Evaluación de Recursos Naturales

    1984-01-01

    Establece como se emplea el agua en el Perú, teniendo en cuenta el tipo de uso, consuntivo y no consuntivo, discriminando según sea el destino: agrícola, pecuario, poblacional,industrial, minero, energético y pesquero, así como su localización geográfica; ello con la finalidad de que sirva de información básica para la planificación del desarrollo.

  5. Pérdida de empleo en el sector minero de la Comarca del Bierzo: estrategias familiares

    OpenAIRE

    Gago Fernández, Inés

    2016-01-01

    El tema de estudio de este trabajo fin de máster es analizar la dinámica de la familia nuclear en el contexto actual de crisis económica y social existente en nuestro país, en la repercusión del desempleo en la familia nuclear. El documento final que

  6. Design of a costing system and valuation for the production of radiopharmaceutical FDG and the provision of radiology service with PET-CT to Caja Costarricense del Seguro Social, for the Centro de Investigacion en Ciencias Atomicas, Nucleares y Moleculares of the Universidad de Costa Rica

    International Nuclear Information System (INIS)

    Gonzalez Cabezas, Gabriel; Jarquin Arguedas, Daniela; Salas Solorzano, Bonnie; Solano Morales, Josue; Zuniga Soto, Karol

    2013-01-01

    The cost of the radiopharmaceutical FDG and of the service of diagnostic studies with PET-CT technology are determined through the design of a costing system. The aim has been to provide to the Centro de Investigacion en Ciencias Atomicas, Nucleares y Moleculares (Cicanum), an appropriate decision making as to definition of sale prices in the CCSS-Cicanum Project. This project has arisen of the partnership between the Cicanum and Caja Costarricense del Seguro Social (CCSS), in order to satisfy the needs in the area of oncology; specifically, the acquisition of PET-CT technology. Diagnostic studies can be performed with this technology to detect and measure the evolution of different types of cancer. Additionally, the realization of these studies have required the acquisition of a cyclotron for the production of the radiopharmaceutical called FDG by Cicanum. The theoretical and conceptual aspects relating to atomic, nuclear and molecular sciences are defined, as well as the contribution of the Universidad de Costa Rica for research in these areas and perspectives of costing systems. The administrative-accounting area of Cicanum is described and diagnosed, as well as of the CCSS-Cicanum Project, to know its scope, management and allocation of costs. The situation diagnosed in the administrative-accounting area of Cicanum and the CCSS-Cicanum Project are analyzed, through the tool Swotr (strengths, opportunities, weaknesses, threats and risks). A costing system is elaborated for Cicanum, based on work orders. The system has been developed in a series of electronic work sheets that have allowed to obtain costs associated with the production of the radiopharmaceutical FDG and the rendering of diagnostic services with PET-CT technology to the CCSS, as well as the definition of sales price. As a complement to the above, a master budget is done, which provides a financial vision of the project in its first ten years of operation [es

  7. Gerencia del cuidado-gerencia del servicio

    Directory of Open Access Journals (Sweden)

    Marta Palmet Jiménez

    2016-01-01

    Full Text Available La gerencia de este siglo debe estar plenamente identificada con la administración para planear, organizar, decidir y obtener resultados definidos, evaluados y alcanzados a través de las personas. Para poder gerenciar el cuidado se debe saber administrar. El objetivo de enfermería es cuidar; el objetivo de la gerencia es la conducción de la producción de bienes o servicios en las organizaciones. La gerencia del cuidado implica: motivación, creatividad, responsabilidad y ética por parte del cuidador y de quien cuida, claridad de actitud frente al ser y al qué hacer por parte del cuidador. Se puede concluir que la gerencia (administración, el cuidado (producto de calidad, el servicio (valor intangible, querer servir son un trinomio que deben ir de la mano de manera integrada para el logro de los objetivos propuestos por la organización de salud y de enfermería.

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

    International Nuclear Information System (INIS)

    Acero, M.

    1995-01-01

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

  9. Simulation of a reactor FBR with hexagonal-Z geometry using the code PARCS 3.1; Simulacion de un reactor FBR con geometria hexagonal-Z usando el codigo PARCS 3.1

    Energy Technology Data Exchange (ETDEWEB)

    Reyes F, M. C.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U.P. Adolfo Lopez Mateos, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Filio L, C., E-mail: rf.melisa@gmail.com [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    The nuclear reactor core type FBR (Fast Breeder Reactor) was modeled in three dimensions of hexagonal-Z geometry using the code PARCS (Purdue Advanced Reactor Core Simulator) version 3.1 developed by Purdue University researchers. To carry out the modeling of the mentioned reactor was taken the corresponding information to one of the described benchmarks in the document NEACRP-L-330 (3-D Neutron Transport Benchmarks, 1991); fundamentally the corresponding to the geometric data and the cross sections. Being a quick reactor of breeding, known as the Knk-II, for which are considered 4 energy groups without dispersions up. The reactor core is formed by prismatic elements of hexagonal transversal cut where part of them only corresponds to nuclear fuel assemblies. This has four reflector rings and 6 identical control elements that together with the active part of the core is configured with 8 different types of elements.With the extracted information of the mentioned document the entrance file was prepared for PARCS 3.1 only considering a sixth part of the core due to the symmetry that presents their configuration. The NEACRP-L-330 shows a wide range of results reported by those who collaborated in its elaboration using different solution techniques that go from the Monte Carlo method to the approaches S{sub 2} and P{sub 1}. Of all the results were selected those obtained with the code HEXNOD, to which were carried out a comparison of the effective multiplication factor, being smaller differences to the 300 pcm, for three different scenarios: a) with the control bars extracted totally, b) with the semi-inserted control bars and c) with the control bars inserted completely and two different axial meshes, a thick mesh with 14 slices and another fine with 38, that which implies that the results can be considered very similar among if same. Radial maps and axial profiles are included, as much of the power as of the neutrons flow. (Author)

  10. Nuclear blackmail and nuclear balance

    International Nuclear Information System (INIS)

    Betts, R.K.

    1987-01-01

    This book raises pointed questions about nuclear saber rattling. More than a dozen cases since the bombing of Hiroshima and Magasaki in which some sort of nuclear threat was used as a sparring technique in tense confrontations are cited. Each incident is described and analyzed. Two theories offered to explain America's use of nuclear threats, the balance of interest theory and the balance of power theory, are contrasted throughout the book. This book helps to fill the gap in the understanding of nuclear weapons and their uses, while pointing out that nuclear bravado could lead to an unintended unleashing of these weapons

  11. El cambio en la política exterior de Estados Unidos que permitió el desarrollo del uso pacífico de energía nuclear en Argentina

    OpenAIRE

    Contursi Reynoso, Adrián

    2017-01-01

    Las bombas atómicas arrojadas sobre Japón no significan sólo el fin de la Segunda Guerra Mundial en 1945. También es el punto de partida para el creciente interés de los países periféricos para obtener dicha tecnología, aunque no desde un enfoque bélico sino como oportunidad de desarrollo. El presente trabajo explora el cambio de la política de cooperación estadounidense en referencia a los conocimientos sobre la energía nuclear y cómo fue la relación de Argentina con Esta...

  12. 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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  13. Determinantes del ingreso y del gasto corriente de los hogares

    OpenAIRE

    Muñoz C., Manuel

    2004-01-01

    Este ensayo de investigación empírica analiza los determinantes del ingreso y del gasto en los hogares colombianos. Utilizando un modelo del ciclo de vida con datos de la encuesta de hogares de 1994 y 1995, muestra que el comportamiento del ingreso está afectado principalmente por las características demográficas del hogar y los rasgos socio ocupacionales de sus miembros. El comportamiento del gasto está determinado ante todo por el ingreso y, en menor medida, por las características sociales...

  14. Las fluctuaciones del nivel del mar durante el Cuaternario

    OpenAIRE

    Pousa, Jorge Lorenzo; Isla, Federico Ignacio; Schnack, Enrique Jorge

    2002-01-01

    Los cambios del nivel del mar han ejercido una fuerte influencia en la evolución del planeta y en la historia de la humanidad. En una escala de tiempo geológico, las variaciones de los niveles oceánicos han dejado un registro ampliamente distribuido en la forma de depósitos sedimentarios. El descenso del nivel del mar durante la Ultima Glaciación, que alcanzó unos 120 metros hace 18.000 años, permitió la emergencia del estrecho de Bering y la migración humana desde Eurasia hacia América. Se e...

  15. Nuclear energy and nuclear weapons

    International Nuclear Information System (INIS)

    Robertson, J.A.L.

    1983-06-01

    We all want to prevent the use of nuclear weapons. The issue before us is how best to achieve this objective; more specifically, whether the peaceful applications of nuclear energy help or hinder, and to what extent. Many of us in the nuclear industry are working on these applications from a conviction that without peaceful nuclear energy the risk of nuclear war would be appreciably greater. Others, however, hold the opposite view. In discussing the subject, a necessary step in allaying fears is understanding some facts, and indeed facing up to some unpalatable facts. When the facts are assessed, and a balance struck, the conclusion is that peaceful nuclear energy is much more part of the solution to preventing nuclear war than it is part of the problem

  16. Calculations of hydrogen transport for the simulation of a Sbo in the NPP-L V using the code CFD GASFLOW; Calculos de transporte de hidrogeno para la simulacion de un SBO en la CNLV usando el codigo CFD GASFLOW

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A. M.; Xolocostli M, V. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Lopez M, R.; Filio L, C.; Mugica R, C. A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico); Royl, P., E-mail: armando.gomez@inin.gob.mx [Karlsruhe Institute of Technology, Consultor, Hermann-von-Helmholtz-Platz, D-76344 Eggenstein -Leopoldshafen, Karlsruhe (Germany)

    2013-10-15

    The scenario of electric power total loss in the nuclear power plant of Laguna Verde (NPP-L V) has been analyzed using the code MELCOR previously, until reaching fault conditions of the primary container. A mitigation measure to avoid the loss of the primary contention is the realization of a venting toward the secondary contention (reactor building), however this measure bears the potential explosions occurrence risk when the hydrogen accumulated in the primary container with the oxygen of the reactor building atmosphere reacting. In this work a scenario has been supposed that considers the mentioned venting when the pressure of 4.5 kg/cm{sup 2} is reached in the primary container. The information for the hydrogen like an entrance fact is obtained of the MELCOR results and the hydrogen transport in both contentions is analyzed with the code CFD GASFLOW that allows predicting the detailed distribution of the hydrogen volumetric concentration and the possible detonation of flammability conditions in the reactor building. The results show that the venting will produce detonation conditions in the venting level (level 33) and flammability in the level of the recharge floor. The methodology here described constitutes the base of a detailed calculation system of this type of phenomena that can use to make safety evaluations in the NPP-L V on scenarios that include gases transport. (Author)

  17. La imagen del pase.

    Directory of Open Access Journals (Sweden)

    Hernando Bernal.

    1999-11-01

    Full Text Available A partir de un texto del poeta Octavio Paz llamado «La imagen», se busca proseguir la equivalencia entre las imágenes de la poesía y la función que ellas tienen para el poeta, y el fantasma fundamental y su función para el analizante que está en el momento del pase. Se parte de la idea de que la poesía busca entrar en el ser así como el psicoanálisis tiene como finalidad apuntar al corazón del ser del sujeto. Se hace entonces una distinción del concepto de «ser» para el psicoanálisis, haciendo alusión también al discurso de la filosofía. Esclarecido el sentido de lo que es el «ser» para el psicoanálisis, se aborda de lleno – entre otras cosas, relacionadas con la experiencia del pase específicamente- la equivalencia entre la definición que hace Octavio Paz de «La Imagen» y el momento del pase en el análisis de un sujeto, imagen que, al igual que el mito para la filosofía, las leyes para la ciencia y el matema para el psicoanálisis, se constituyen en los instrumentos con los que cada una de estas disciplinas horadan en lo real.

  18. Nuclear materials

    International Nuclear Information System (INIS)

    1996-01-01

    In 1998, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) performed 38 inspections, 25 of them were performed in co-operation with IAEA inspectors. There is no fresh nuclear fuel at Bohunice A-1 NPP at present. Fresh fuel of Bohunice V-1 and V-2 NPPs is inspected in the fresh fuel storage.There are 327 fresh fuel assemblies in Mochovce NPP fresh fuel storage. In addition to that, are also 71 small users of nuclear materials in Slovakia. In most cases they use: covers made of depleted uranium for non-destructive works, detection of level in production plants, covers for therapeutical sources at medical facilities. In. 1995, NRA SR issued 4 new licences for nuclear material withdrawal. In the next part manipulation with nuclear materials, spent fuel stores and illegal trafficking in nuclear materials are reported

  19. Nuclear Law

    International Nuclear Information System (INIS)

    Wiesbauer, Bruno

    1978-01-01

    This book is the first attempt of a comprehensive compilation of national Austrian Nuclear Law (Nuclear Liability Act; Radiation protection Act, Radiation Protection Ordinance, Security Control Act, Act on the uses of Nuclear Energy - Zwentendorf Nuclear Power Plant) and the most important international agreements to which Austria is a party. Furthermore, the book contains the most important Nuclear Liability Conventions to which Austria is not yet a party, but which are applicable in neighbouring; the Paris Convention served as a model for the national Nuclear Liability Act and may be used for its interpretation. The author has translated a number of international instruments into German, such as the Expose des Motifs of the Paris Convention. (NEA) [fr

  20. Nuclear nonproliferation

    International Nuclear Information System (INIS)

    Neubert, M.

    1992-01-01

    The following motion was put before the United Kingdom House of Commons on 3rd February 1992 and agreed; that this House, recognising the potential dangers of the rapidly changing world order, welcomes the recent proposals for substantial reductions in nuclear weaponry, the growing support for the non-proliferation treaty and progress in the implementation of the United Nations Security Council Resolutions concerning the dismantling of Iraqi nuclear, chemical and biological capabilities; urges the Government to play their full part in helping the relevant authorities in the Commonwealth of Independent States to dismantle their nuclear devices, to safeguard their nuclear components and to discourage the proliferation of nuclear expertise; and believes it is of the first importance that Britain retains an effective and credible minimum nuclear deterrent as security in a world where there remain many sources of instability. The record of arguments for and against the motion in the debate is presented. (author)

  1. Nuclear energy

    International Nuclear Information System (INIS)

    Panait, A.

    1994-01-01

    This is a general report presenting the section VII entitled Nuclear Power of the National Conference on Energy (CNE '94) held in Neptun, Romania, on 13-16 June 1994. The problems addressed were those relating to electric power produced by nuclear power plant, to heat secondary generation, to quality assurance, to safety, etc. A special attention was paid to the commissioning of the first Romanian nuclear power unit, the Cernavoda-1 reactor of CANDU type. The communications were grouped in four subsections. These were: 1. Quality assurance, nuclear safety, and environmental protection; 2. Nuclear power plant, commissioning, and operation; 3. Nuclear power plant inspection, maintenance, and repairs, heavy water technology; 4. Public opinion education. There were 22 reports, altogether

  2. Nuclear power

    International Nuclear Information System (INIS)

    King, P.

    1990-01-01

    Written from the basis of neutrality, neither for nor against nuclear power this book considers whether there are special features of nuclear power which mean that its development should be either promoted or restrained by the State. The author makes it dear that there are no easy answers to the questions raised by the intervention of nuclear power but calls for openness in the nuclear decision making process. First, the need for energy is considered; most people agree that energy is the power to progress. Then the historicalzed background to the current position of nuclear power is given. Further chapters consider the fuel cycle, environmental impacts including carbon dioxide emission and the greenhouse effect, the costs, safety and risks and waste disposal. No conclusion either for or against nuclear power is made. The various shades of opinion are outlined and the arguments presented so that readers can come to their own conclusions. (UK)

  3. Nuclear power

    International Nuclear Information System (INIS)

    Porter, Arthur.

    1980-01-01

    This chapter of the final report of the Royal Commission on Electric Power Planning in Ontario updates its interim report on nuclear power in Ontario (1978) in the light of the Three Mile Island accident and presents the commission's general conclusions and recommendations relating to nuclear power. The risks of nuclear power, reactor safety with special reference to Three Mile Island and incidents at the Bruce generating station, the environmental effects of uranium mining and milling, waste management, nuclear power economics, uranium supplies, socio-political issues, and the regulation of nuclear power are discussed. Specific recommendations are made concerning the organization and public control of Ontario Hydro, but the commission concluded that nuclear power is acceptable in Ontario as long as satisfactory progress is made in the disposal of uranium mill tailings and spent fuel wastes. (LL)

  4. Nuclear astrophysics

    International Nuclear Information System (INIS)

    Haxton, W.C.

    1992-01-01

    The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized

  5. Nuclear physics

    International Nuclear Information System (INIS)

    Patel, S.B.

    1991-01-01

    This book is a simple and direct introduction to the tools of modern nuclear physics, both experimental and mathematical. Emphasizes physical intuition and illuminating analogies, rather than formal mathematics. Topics covered include particle accelerators, radioactive series, types of nuclear reactions, detection of the neutrino, nuclear isomerism, binding energy of nuclei, fission chain reactions, and predictions of the shell model. Each chapter contains problems and illustrative examples. Pre-requisites are calculus and elementary vector analysis

  6. Nuclear energy

    International Nuclear Information System (INIS)

    Hesketh, Ross.

    1985-01-01

    The subject is treated under the headings: nuclear energy -what is it; fusion (principles; practice); fission (principles); reactor types and systems (fast (neutron) reactors as breeders; fast reactors; thermal reactors; graphite-moderated thermal reactors; the CANDU reactor; light water reactors - the BWR and the PWR); the nuclear fuel cycle (waste storage; fuel element manufacture; enrichment processes; uranium mining); safety and risk assessment; the nuclear power industry and the economy (regulating authorities; economics; advantages and disadvantages). (U.K.)

  7. Uncertainty and sensitivity analysis in the scenario simulation with RELAP/SCDAP and MELCOR codes; Analisis de incertidumbre y sensibilidad en la simulacion de escenarios con los codigos RELAP/SCDAP y MELCOR

    Energy Technology Data Exchange (ETDEWEB)

    Garcia J, T.; Cardenas V, J., E-mail: tonatiuh.garcia@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2015-09-15

    A methodology was implemented for analysis of uncertainty in simulations of scenarios with RELAP/SCDAP V- 3.4 bi-7 and MELCOR V-2.1 codes, same that are used to perform safety analysis in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). The uncertainty analysis methodology chosen is a probabilistic method of type Propagation of uncertainty of the input parameters to the departure parameters. Therefore, it began with the selection of the input parameters considered uncertain and are considered of high importance in the scenario for its direct effect on the output interest variable. These parameters were randomly sampled according to intervals of variation or probability distribution functions assigned by expert judgment to generate a set of input files that were run through the simulation code to propagate the uncertainty to the output parameters. Then, through the use or ordered statistical and formula Wilks, was determined that the minimum number of executions required to obtain the uncertainty bands that include a population of 95% at a confidence level of 95% in the results is 93, is important to mention that in this method that number of executions does not depend on the number of selected input parameters. In the implementation routines in Fortran 90 that allowed automate the process to make the uncertainty analysis in transients for RELAP/SCDAP code were generated. In the case of MELCOR code for severe accident analysis, automation was carried out through complement Dakota Uncertainty incorporated into the Snap platform. To test the practical application of this methodology, two analyzes were performed: the first with the simulation of closing transient of the main steam isolation valves using the RELAP/SCDAP code obtaining the uncertainty band of the dome pressure of the vessel; while in the second analysis, the accident simulation of the power total loss (Sbo) was carried out with the Macarol code obtaining the uncertainty band for the

  8. A review on the separation and measurement of 85{sup K}r from the gaseous effluents and environment of nuclear facilities; Revision bibliografica de las tecnicas de separacion y medida del 85{sup K}r en la atmosfera y efluentes gaseosos de la Industria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Perez Garcia, M. M.

    1981-07-01

    This paper intends to give a general view, based on bibliographic references, on the different techniques used In recent years for the control of 85{sup K}r. It includes sampling, concentration, separation and radioactive measurement, as well as its application to Environmental and Nuclear Establishments Sites Surveys. (Author) 54 refs.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  10. Calls for proposals for Indirect IDT Action within the specific (Euratom) Research and Training Programme on Nuclear Energy (2002-2006); Convocatorias de propuestas de accion indirecta de IDT dentro del progrma especifico (Euratom) de investigacion y formacion sobre energia nuclear (2002-2006)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    The official diary of the European Union C 273 of 14 November, 2003, published the Calls for Indirect IDT Action for the Euratom Research and Training Programme on Nuclear Energy. The complete text of these Calls are reproduced in page 29. (Author)

  11. Fuel management inside the reactor. Project AZ-101 (ININ). Report of the generation of the nuclear bank 'L1PG3826' of the assemblies GE5 and GE9B 'collapsed' of the CNLV for the FCS-II program of the FMS system; Administracion de combustible dentro del reactor. Proyecto AZ-101 (ININ). Reporte de generacion del banco nuclear 'L1PG3826' de los ensambles GE5 y GE9B 'colapsados' de la CNLV para el programa FCS-II del FMS

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G.; Torres A, C

    1991-06-15

    In order to be able to carry out studies but next to the operation of the reactor of the CNLV with the program FCS-II of the package of codes for the fuel management FMS, it was generated a 'collapsed' nuclear bank integrating the generated information with RECORD of each one of those assemblies of the initial load and of the first recharge. To generate the bank, the different ones RECORD 'cells' that compose each assemble were 'collapsed' to an alone one, representing this, to the one complete assemble in what refers to the fuel bars distribution and enrichments. The one collapsed of each assemble it is made averaging the content of UO{sub 2} and Gd{sub 2}O{sub 3} in each fuel bar by the volumetric fraction occupied by each axial section of the fuel bar where the content of UO{sub 2} and Gd{sub 2}O{sub 3} were constant, by this way the x-y fuel bars arrangement is conserved but a representative fuel cell of all the assemble is obtained. Of the five different assemblies that will be load in the reactor of the CNLV (3 of the initial load and 2 of the first recharge), only 4 were collapsed; the remaining one to be totally formed by natural uranium it was not necessary to collapse. From the collapsing process new enrichment values in U-235 and in content of Gd{sub 2}O{sub 3} for each fuel bar, for what according to the generation procedure of nuclear information it was generated the required information by RECORD for each fuel bar with Gd{sub 2}O{sub 3} with the ECLIPSE code. Once generated this information it was proceeded to generate the homogenized nuclear information, with RECORD, for the whole cell. According to the requirements of nuclear information of FCS-II, the nuclear Information generated with RECORD only was of the defined type as series 1 in the procedure of generation of nuclear banks '6F3/1/CN029/90/P1'; that which means that only it was generated nuclear information as function of the burnup of the fuel and of

  12. del Estado Aragua

    Directory of Open Access Journals (Sweden)

    Joselys Cintia Zerpa

    2008-01-01

    Full Text Available Diagnostica la situación actual de los bienes que conforman al patrimonio histórico-cultural del Municipio Zamora, Estado Aragua, Venezuela. La Investigación es descriptiva y de campo, comprendió la elaboración de un inventario de los bienes inmuebles, festividades religiosas y manifestaciones artesanales del municipio. Se estudiaron la condición física y uso actual de estos bienes y los planes y proyectos existentes. Analizó el marco normativo que los rige. Se obtuvo la opinión de los representantes de organismos públicos relacionados con la actividad turística del Municipio, de los visitantes, cronistas e historiadores. Aportes: La mayoría de los bienes se encuentran en buen estado de conservación, Las manifestaciones culturales, festividades y la artesanía se desarrollan periódicamente pero no son aprovechadas turísticamente, Se determinó que existe un marco normativo para tales bienes y No existen propuestas actuales referentes a estos bienes. Se reflejó el interés de los sectores institucional y privado para la incorporación de estos bienes a la oferta turística del Municipio y del Estado

  13. APOSTILLAS ACERCA DEL POSTRABAJO

    Directory of Open Access Journals (Sweden)

    Arturo Torrecilla

    2000-01-01

    Full Text Available El más reciente debate en torno al postrabajo transforma la herencia de los dos ciclos que le precedieron desde los años setenta. El primero se correspondía con la crítica de la división social y técnica de labores informada por una filosofía de la alienación o bien por una rectificación de la arquitectónica marxista pero salvaguardando la promesa laborista del buen trabajo. El segundo ciclo hacía eco del rechazo a las cadenas de montaje fordistas y se abría al horizonte de la abolición del trabajo salarial, manteniendo sin embargo el abolengo del sujeto unitario de la historia. La presente escena asume una densidad mayor, producto del encuentro entre las nuevas tecnologías informacionales, las discusiones en el ámbito de la sociología y la antropología, de la tecnología y la ciencia, junto al dueto que inaugura el posmodernismo.

  14. Apostillas acerca del postrabajo

    Directory of Open Access Journals (Sweden)

    Arturo Torrecilla

    2000-04-01

    Full Text Available El más reciente debate en torno al postrabajo transforma la herencia de los dos ciclos que le precedieron desde los años setenta. El primero se correspondía con la crítica de la división social y técnica de labores informada por una filosofía de la alienación o bien por una rectificación de la arquitectónica marxista pero salvaguardando la promesa laborista del buen trabajo. El segundo ciclo hacía eco del rechazo a las cadenas de montaje fordistas y se abría al horizonte de la abolición del trabajo salarial, manteniendo sin embargo el abolengo del sujeto unitario de la historia. La presente escena asume una densidad mayor, producto del encuentro entre las nuevas tecnologías informacionales, las discusiones en el ámbito de la sociología y la antropología, de la tecnología y la ciencia, junto al dueto que inaugura el posmodernismo.

  15. La universidad del futuro

    Directory of Open Access Journals (Sweden)

    FERNANDO SANCÉN CONTRERAS

    2013-01-01

    Full Text Available El trabajo señala la necesidad de reconstruir la Universidad, dado el dinamismo que muestra la ciencia y la sociedad, pues trae consigo cambios sustanciales en la visión del mundo y en el aumento del poder del hombre sobre la naturaleza. Se analizan los supuestos epistemológicos de la universidad tradicional y se propone una nueva explicación del conocimiento humano, enfatizando el conocimiento científico. Postula una docencia fundada en las propiedades de la ciencia, cuyo método inductivo basado en los paradigmas vigentes: analítico, crítico, pragmático, ofrece una herramienta para la docencia, la investigación y la difusión de la cultura. Se propone una educación centrada en el sujeto que se hace a sí mismo (etopoiética y que insiste en el proceso de auto-creación del individuo y de la sociedad.

  16. Significado presente del CSIC

    Directory of Open Access Journals (Sweden)

    Garrido Gallardo, Miguel Angel

    2000-05-01

    Full Text Available Not available

    Este artículo, elaborado en 1999, ofrece una panorámica de la realidad del Consejo Superior de Investigaciones Científicas en la actualidad. Repasa su organización, su volumen de publicaciones, sus indicadores de productividad, su capacidad de obtener recursos y, en suma, su lugar en el conjunto del sistema español de Ciencia y Tecnología, considerado en sí mismo y en relación con la Universidad. Como conclusión del repaso de datos, se afirma que, aunque la fórmula del CSIC, como organismo nacional e interdisciplinario, no es la única posible, la organización del Estado de las Autonomías, así como la evaluación de los datos con que se cuenta, la hacen vivamente recomendable. No hay, pues, sino que seguir con su desarrollo.

  17. Dalt del tren

    Directory of Open Access Journals (Sweden)

    Jaume Subirana

    2001-11-01

    Full Text Available Ens consta que la saviesa popular hi toca més del que a aquest temps d’enquestes, telèfons mòbils i targetes de crèdit li ve de gust admetre, per això em fa gràcia, en veure la pausada però continuada intrusió de la cultura catalana a Internet, recordar les cançons de quan era petit: “Dalt del tren, tots anem-hi dalt del tren, hi ha lloc per tota la gent”, dèiem, i “El tren pinxo de Banyoles és el més bonic que hi ha, ple de llaunes i cassoles i barrets de capellà”. I resulta que per una vegada a la vida hem pujat, efectivament, dalt del tren que passava per l’estació de Catalunya i en cinc anys hem passat de gairebé res a prou pàgines amb un contingut, a més, apreciable i, sobretot, a un petit teixit de persones i institucions que han entès la importància de la revolució comunicativa que Internet representa i que hi teixeixen i projecten webs amb el convenciment dels conversos.

  18. Las carreras del futuro

    Directory of Open Access Journals (Sweden)

    Luis Piscoya Hermoza

    2011-07-01

    Full Text Available La primera década del siglo XXI ha estado signada por un énfasis en los estudiosde prospectiva, los mismos que, a partir de procesos de complejizacióny articulación de la sociedad planetaria como son la digitalización, el progresivodeterioro del medio ambiente, la necesidad del cambio de la matriz energéticay la globalización del mercado, han ensayado hipótesis para identificar lastendencias que se fortalecerán y profundizarán durante las próximas décadas.Desde el punto de vista metodológico, existen muchas maneras de clasificarlaspara conceptualizarlas y entenderlas mejor. Sin embargo, considerando lanaturaleza de esta edición nos proponemos enfocar directamente aquellas queestán estrechamente ligadas a la formación universitaria.Naturalmente, no pensamos que estamos ante tendencias inevitables en lamedida que epistemológicamente la creencia en leyes históricas deterministases insostenible y la práctica social nos muestra que la construcción del futuroes nuestra responsabilidad y siempre rebasa las mejores previsiones.

  19. Nuclear Asia

    National Research Council Canada - National Science Library

    Ferguson, Joseph; Tarleton, Gael

    2004-01-01

    .... This event was an opportunity for policy makers, security analysts, nuclear scientists and engineers, regional experts, and military planners to share perspectives and identify those issues requiring...

  20. Nuclear cardiology

    International Nuclear Information System (INIS)

    Fish, M.B.

    2002-01-01

    Recent advances in nuclear medicine instrumentation and software, including myocardial perfusion imaging, offer increased accuracy in the detection, diagnosis and prognosis of coronary artery disease. (orig.)

  1. Nuclear medicine

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The area of nuclear medicine, the development of artificially produced radioactive isotopes for medical applications, is relatively recent. Among the subjects covered in a lengthy discussion are the following: history of development; impact of nuclear medicine; understanding the most effective use of radioisotopes; most significant uses of nuclear medicine radioimmunoassays; description of equipment designed for use in the field of nuclear medicine (counters, scanning system, display systems, gamma camera); description of radioisotopes used and their purposes; quality control. Numerous historical photographs are included. 52 refs

  2. Nuclear Law

    International Nuclear Information System (INIS)

    Pascal, Maurice.

    1979-01-01

    This book on nuclear law is the first of a series of analytical studies to be published by the French Energy Commission (CEA) concerning all the various nuclear activities. It describes national and international legislation applicable in France covering the following main sectors: the licensing procedure for nuclear installations, the law of the sea and nuclear law, the legal system governing radioisotopes, the transport of radioactive materials, third party liability and insurance and radiation protection. In each chapter, the overall analysis is supplemented by the relevant regulatory texts and by organisation charts in annex. (NEA) [fr

  3. Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1989-01-01

    This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  4. Nuclear power

    International Nuclear Information System (INIS)

    Bupp, I.C.

    1991-01-01

    Is a nuclear power renaissance likely to occur in the United States? This paper investigates the many driving forces that will determine the answer to that question. This analysis reveals some frequently overlooked truths about the current state of nuclear technology: An examination of the issues also produces some noteworthy insights concerning government regulations and related technologies. Public opinion will play a major role in the unfolding story of the nuclear power renaissance. Some observers are betting that psychological, sociological, and political considerations will hod sway over public attitudes. Others wager that economic and technical concerns will prevail. The implications for the nuclear power renaissance are striking

  5. Componente Cultura del Agua del PMGRH: plan de trabajo

    OpenAIRE

    Autoridad Nacional del Agua; Proyecto de Modernización de la Gestión de Recursos Hídricos

    2012-01-01

    Describe el plan de trabajo del Componente Cultura del Agua del Proyecto de Modernización de la Gestión de Recursos Hídricos (PMGRH) en relacion a dos aspectos estructurales del proyecto: 1. Mejora de la capacidad de la Gestión Integrada de Recursos Hídricos (GIRH) a nivel nacional y 2. Fortalecimiento de las capacidades de GIRH en las cuencas.

  6. En busca del concepto de gerencia del cuidado

    Directory of Open Access Journals (Sweden)

    Ligia Teresa Mora-Delgado

    2005-12-01

    Full Text Available Este articulo, presenta los conceptos de gerencia del cuidado de enfermería, desarrollado por las enfermeras profesionales que laboran en le Empresa social del estado Hospital Universitario Erasmo Meoz de las Ciudad de Cúcuta, desde su desempeño en la asistencia, administración y docencia. Se pretende además precisar los elementos gerenciales, sociales, humanísticos y éticos que deben hacer parte del concepto de gerencia del cuidado.

  7. LA PERSISTENCIA DEL SUBALTERNO

    Directory of Open Access Journals (Sweden)

    John Beverley

    2002-01-01

    Full Text Available Este trabajo es el texto literal de una ponencia presentada en un panel sobre los estudios culturales latinoamericanos en el congreso de LASA en 2001 en Washington DC. Representa la posición desarrollada en el trabajo colectivo del llamado Grupo de Estudios Subalternos Latinoamericano, desde nuestra fundación en 1992 hasta la disolución del grupo en 2001, que sirve como pretexto introductorio para la ponencia. Los otros participantes en el panel eran Walter Mignolo, representando los estudios poscoloniales, Néstor García Canclini y John Kraniauskas, representando los estudios culturales, y Nelly Richard representando la llamada crítica cultural. El trabajo dialoga y debate con cada una de estas posiciones respectivamente desde el punto de vista específico de los estudios subalternos. Concluye con un llamado a una crítica del saber académico en sí.

  8. Acalasia. Controversias del tratamiento

    OpenAIRE

    Restrepo P, Antonio J; Rey T, Mario H; Garzón O, Martín A; Farfán Q, Yesid A; Molano V, Juan C; Marulanda, Juan C; Lizarazo, Jorge I

    2007-01-01

    La acalasia es un desorden motor del esófago caracterizado por pérdida de la peristalsis esofágica con falta en la relajación o relajación incompleta del esfínter esofágico inferior (EEI) (1). La causa exacta de este trastorno es desconocida. Los síntomas más comunes son disfagia, regurgitación, pérdida de peso y dolor torácico (2). La manometría esofágica es el principal método diagnóstico, mostrando aperistalsis del cuerpo esofágico con aumento de la presión, falta de relajación o relajació...

  9. Procedimiento Del Triple Fin

    Directory of Open Access Journals (Sweden)

    Oscar L. Bellido Aguilera

    2008-01-01

    Full Text Available Presenta un procedimiento novedoso basado en un método dialéctico - sistémico - integrador, que facilita la precisión de los fines u objetivos más generales de un proceso de desarrollo comunitario o de otros procesos de cambio deseados (un proyecto sociocultural, una investigación social, un proceso de mejoramiento organizacional, etc.. Su importancia radica en que los fines, según Marx, son una guía que rige como una ley la actuación del hombre y determinarlos es parte esencial del planeamiento del cambio. Se trata de un asunto aparentemente simple, sin embargo, en la práctica es mucho más problemático de lo que comúnmente se cree.

  10. Evaluation and standardization of neutron activation analysis according to the K{sub 0} method in the RP-10 reactor; Evaluacion y estandarizacion del analisis por activacion neutronica segun el metodo del K{sub 0} en el reactor nuclear RP-10

    Energy Technology Data Exchange (ETDEWEB)

    Montoya R, E

    1995-06-01

    It has been characterized and standardized an irradiation of the RP-10 Research Nuclear Reactor for use of the K{sub 0} method of neutron activation analysis using the Hoegdahl convention; also it has been evaluate the behaviour of such method in regard to the accuracy and precision of the results obtained in the quantitative multi elemental analysis of several certified materials of reference. In order to prove that the analytical method is totally under statistical control, it has been used the Heydorn method. It has been verified that the method is exact, precise and reliable to determine the aluminium, antimuonium, arsenic, bromine, calcium, chloride, copper, magnesium, manganese, sodium, titanium, vanadium, zinc and other elements. Also, they are discussed, in regard to the use of K{sub 0} constants, the different formalisms employed to calculate the integral of the reaction rate by nucleus in the activation. (author). 58 refs., 18 tabs., 6 figs.

  11. ¿Comprendemos realmente el significado del ALCA?

    OpenAIRE

    Orlando Zelaya Martínez; Luis Murillo Orozco

    2004-01-01

    Después de finalizada la segunda guerra mundial, Estados Unidos se convierte en el gendarme del mundo tanto en lo económico como en lo político, razón por cual decide no únicamente convertirse en el banquero del mundo, sino en su salvador ante el potencial peligro que representaba el comunismo como sistema. De esta forma crea un nuevo tipo de guerra de intensidad en el enfrentamiento directo, pero trasladando tal circunstancia al campo de la amenaza nuclear. Nos estamos refiriendo a la "Guerr...

  12. Nuclear stress test

    Science.gov (United States)

    ... Persantine stress test; Thallium stress test; Stress test - nuclear; Adenosine stress test; Regadenoson stress test; CAD - nuclear stress; Coronary artery disease - nuclear stress; Angina - nuclear ...

  13. Efecto del silicio y plaguicidas en la fertilidad del suelo y rendimiento del arroz

    OpenAIRE

    Furcal-Beriguete, Parménides; Herrera-Barrantes, Alejandra

    2013-01-01

    Efecto del silicio y plaguicidas en la fertilidad del suelo y rendimiento del arroz. El objetivo de este trabajo fue evaluar el efecto del silicio en la fertilidad del suelo, la incidencia de enfermedades y plagas insectiles, el rendimiento y la calidad de granos del cultivo de arroz. El estudio se realizó en La Vega, Florencia, San Carlos, Costa Rica entre mayo y octubre en los años 2010 y 2011, en el mismo lote con la variedad CR 4477. Se establecieron cinco tratamientos: silicio al suelo, ...

  14. Storia del pensiero matematico

    CERN Document Server

    Kline, Morris

    1999-01-01

    Costruita con l'intento di presentare le idee oltre ai protagonisti della matematica, questa storia ha il duplice pregio dell'esaustività e della chiarezza. Essa prevede infatti vari livelli di lettura: lo specialista vi trova una messe di dati, fonti e spunti di ricerca, mentre lo studente ha a disposizione un formidabile strumento di consultazione e sintesi. L'arco temporale coperto è vasto: dalla Mesopotamia a Euclide, da Fibonacci all'invenzione del calcolo infinitesimale, da Gauss a Poincare, con un'appendice dedicata agli sviluppi piu recenti scritta appositamente per la prima edizione italiana del 1991, nei «Manuali» Einaudi.

  15. La escritura del quechua

    OpenAIRE

    Authier, Martine du

    2015-01-01

    La mayor fantasía ha acompañado siempre la transcripción del quechua. El primer intento de sistematización fue el sistema de la Paz, en 1953. Sin embargo, no existe en el comercio un diccionario satisfactorio en lo que se refiere al quechua del Cusco y, prácticamente, nada se edita en quechua, fuera de algunos trabajos antropológicos bilingües. Bajo la égida de la UNESCO, la Academia Peruana de la Lengua Quechua, que tiene su sede en el Cusco, ha colaborado en un diccionario de doce de los tr...

  16. El lenguaje del cerebro

    Directory of Open Access Journals (Sweden)

    Antonio Ibáñez Molina

    2011-04-01

    Full Text Available La introducción de nuevas técnicas de análisis de ritmos EEG en estudio de la comprensión del lenguaje permite explorar esta habilidad humana desde una perspectiva de integración de grupos de redes neuronales. Los ritmos de disparo neuronal que generan estos grupos pueden conectarse por sincronía formando unidades funcionales transitorias distribuidas en diversas áreas del cerebro. En esta revisión comentamos algunos de estos ritmos y su relación con el lenguaje.

  17. Plasticidad del sistema nervioso

    Directory of Open Access Journals (Sweden)

    L. M. Garcia-Segura

    1976-06-01

    Full Text Available En este trabajo se revisan los conocimientos más recientes sobre el fenómeno de la plasticidad del sistéma nervioso, tanto a nivel morfológico como a nivel fisiológico y molecular. Se estudian los cambios morfólogicos y fisiológicos de las neuronas frente a la experiencia. Tambien se considera la adaptación molecular del sistéma nervioso a la información que recibe como la base de todo tipo de plasticidad.

  18. Las causas del desempleo

    OpenAIRE

    García Balbás, Salomé

    2014-01-01

    En este documento vamos a tratar de dar respuesta a la siguiente pregunta: ¿cuáles son las causas del desempleo? Para ello realizaremos un repaso de las principales teorías económicas del desempleo llegando a la conclusión de que existe una causa fundamental que lo genera: la rigidez de los salarios a la baja. Consideramos el desempleo como la existencia de un exceso de oferta en el mercado de trabajo y haremos alusión, únicamente, a la existencia de desempleo involuntario. La exposición de l...

  19. Nuclear physics for nuclear fusion

    International Nuclear Information System (INIS)

    Li Xingzhong; Liu Bin; Wei Qingming; Ren Xianzhe

    2004-01-01

    The D-T fusion cross-section is calculated using quantum mechanics with the model of square nuclear potential well and Coulomb potential barrier. The agreement between ENDF data and the theoretically calculated results is well in the range of 0.2-280 keV. It shows that the application of Breit-Wigner formula is not suitable for the case of the light nuclei fusion reaction. When this model is applied to the nuclear reaction between the charged particles confined in a lattice, it explains the 'abnormal phenomena'. It implies a prospect of nuclear fusion energy without strong nuclear radiations

  20. Inventario del Archivo del conde de Bornos

    Directory of Open Access Journals (Sweden)

    Pedro Antonio Porras Arboledas

    1995-01-01

    Full Text Available Mi primer contacto con esta Casa se remonta a algunos años atrás, cuando me Mamó la atención un documento muy interesante, publicado a comienzos del presente siglo por el ilustre erudito ubetense don Alfredo Cazaban, por el que los Reyes Católicos hacían merced a su secretario y jefe de la artillería real durante la Guerra contra Granada, Francisco Ramírez de Madrid, personaje madrileño de origen cántabro, de una heredad en término de Jaén —el cortijo de Bornos— por sus grandes esfuerzos en la conquista de las plazas, hasta el momento inexpugnables, de Cambil y Alhabar. Posteriormente, al realizar un estudio sobre el régimen señorial en el Reino de Jaén, intenté localizar los archivos de las diferentes casas nobiliarias asentadas en esta provincia, gracias a lo cual pude saber que la documentación del Condado de Bornos se hallaba en Madrid, bien en la Biblioteca Nacional o en el Archivo Histórico, ya que el actual Conde, el Excmo. Sr. Don Ignacio Ramírez de Haro, así me lo comunicó en marzo de 1983.

  1. Nuclear installations

    International Nuclear Information System (INIS)

    2001-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  2. Nuclear safety

    International Nuclear Information System (INIS)

    1991-02-01

    This book reviews the accomplishments, operations, and problems faced by the defense Nuclear Facilities Safety Board. Specifically, it discusses the recommendations that the Safety Board made to improve safety and health conditions at the Department of Energy's defense nuclear facilities, problems the Safety Board has encountered in hiring technical staff, and management problems that could affect the Safety Board's independence and credibility

  3. Nuclear violence

    International Nuclear Information System (INIS)

    Mullen, R.K.

    1987-01-01

    A great deal of attention has been paid in the past decade or so to the characteristics of terrorists and their apparent goals and objectives, capabilities, and evolving strategy and tactics with respect to nuclear terrorism. In contrast, little has been said about the procedural aspects of nuclear terrorism, and even less about the way in which such endeavors can fail. This latter omission is important because it bears directly on the ability to evaluate credibly the potential for nuclear terrorism. Here, the author addresses the requirements inherent in acquiring a nuclear explosive capability by three routes: separation of plutonium from irradiated light or heavy water reactor (LWR or HWR) fuel, processing, or use of separated fissile material, and theft of a nuclear weapon. In addition, he deals with other potential acts of nuclear terrorism: sabotage of power reactors, uranium enrichment facilities and spent nuclear fuel in transport, and dispersal of radioactive materials, in particular, plutonium. He specifically does not look at the design or production of a nuclear weapon. Finally, the discussion here assumes that the terrorist is subnational; that is, a nation is not involved. Also, the discussion of subnational participation does not address the possibility of collusion with insiders

  4. Nuclear installations

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  5. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2003-01-01

    This chapter discuss on nuclear power and its advantages. The concept of nucleus fission, fusion, electric generation are discussed in this chapter. Nuclear power has big potential to become alternative energy to substitute current conventional energy from coal, oil and gas

  6. Nuclear energy

    International Nuclear Information System (INIS)

    1978-01-01

    This brochure is intended as a contribution to a better and more general understanding of one of the most urgent problems of present society. Emphasis is laid on three issues that are always raised in the nuclear debate: 1) Fuel cycle, 2) environmental effects of nuclear power plants, 3) waste disposal problems. (GL) [de

  7. Nuclear pollution

    International Nuclear Information System (INIS)

    Ramade, Francois

    1979-01-01

    In this chapter devoted to nuclear pollution the following topics were studied: fundamentals of radiobiology (ecological importance of the various radioisotopes, biological effects of ionizing radiations); ecological effects of radioactive fallout (contamination of atmosphere, terrestrial ecosystems, oceans). The electronuclear industry and its environmental impact. PWR type reactors, fuel reprocessing plants, contamination of trophic chains by radionuclides released in the environment from nuclear installations [fr

  8. Nuclear lifetimes

    International Nuclear Information System (INIS)

    Caraca, J.M.G.

    1976-01-01

    The importance of the results obtained in experiments of measurement of lifetimes for a detailed knowledge of nuclear structure is referred. Direct methods of measurement of nuclear lifetimes are described, namely, electronic methods, recoil-distance method, doppler shift atenuation method and blocking-method. A brief reference is made to indirect methods for measurement of life-times

  9. Nuclear facts

    International Nuclear Information System (INIS)

    1982-01-01

    The subject is discussed as follows: the case for using nuclear energy (Britain's energy needs; energy policy); safety; transport of spent fuel; radiation (natural radioactivity); environment (land use of nuclear power plants; storage and disposal of radioactive wastes). (U.K.)

  10. Nuclear measurements

    International Nuclear Information System (INIS)

    Schenkel, R.

    2005-01-01

    Nuclear measurements play a fundamental role in the development of nuclear technology and the assurance of its peaceful use. They are also required in many non-power nuclear applications such as in nuclear medicine, agriculture, environmental protection, etc. This presentation will show examples of most recent advances in measurement methodology or technology in the areas described below. The Generation IV International Forum has selected six innovative reactor systems as candidates for a next generation of sustainable, economic and safe nuclear energy systems. The choice of the best options relies heavily on the availability of accurate nuclear data that can only be obtained, in an international effort, using highly specialised facilities. Significant efforts are being directed towards the partitioning and transmutation of highly active nuclear waste. Different concepts involving fast reactors or accelerator-driven systems are being studied in view of their transmutation capabilities. State of the art equipment has been developed to assess basic properties of nuclear fuel at very high burn-up; some fine examples of this work will be shown. Physical and chemical methods play a crucial role in the detection and identification of radioisotopes used in various stages of the nuclear fuel cycle. Radiation measurement techniques are used, for example, to monitor the quantities of uranium, plutonium and other actinide elements in fuel enrichment and reprocessing facilities. Another field of application of physical and chemical methods is the characterisation of nuclear material seized from illicit trafficking. Seized material has to be analysed in order to obtain clues on its origin and intended use and to prevent diversion of nuclear material from the same source in the future. A recent highlight in basic physics relates to nuclear fission and transmutation with high intensity lasers. Ultra-fast high intensity lasers can produce high energy (tens of MeV) photons through

  11. Nuclear rockets

    International Nuclear Information System (INIS)

    Sarram, M.

    1972-01-01

    Nuclear energy has found many applications in space projects. This article deals with these applications. The first application is the use of nuclear energy for the production of electricity in space and the second main application is the use of nuclear energy for propulsion purposes in space flight. The main objective is to develop a 75000 pound thrust flight engine call NERVA by heating liquid hydrogen, in a nuclear reactor, from 420F to 4000 0 F. The paper describes in detail the salient features of the NERVA rocket as well as its comparison with the conventional chemical rockets. It is shown that a nuclear rocket using liquid hydrogen as medium is at least 85% more efficient as compared with the chemical rockets such as those used for the APOLLO moon flight

  12. Nuclear rockets

    Energy Technology Data Exchange (ETDEWEB)

    Sarram, M [Teheran Univ. (Iran). Inst. of Nuclear Science and Technology

    1972-02-01

    Nuclear energy has found many applications in space projects. This article deals with these applications. The first application is the use of nuclear energy for the production of electricity in space and the second main application is the use of nuclear energy for propulsion purposes in space flight. The main objective is to develop a 75000 pound thrust flight engine called NERVA by heating liquid hydrogen in a nuclear reactor. The paper describes in detail the salient features of the NERVA rocket as well as its comparison with the conventional chemical rockets. It is shown that a nuclear rocket using liquid hydrogen as medium is at least 85% more efficient as compared with the chemical rockets such as those used for the APOLLO moon flight.

  13. Nuclear haematology

    International Nuclear Information System (INIS)

    Masjhur, J.S.

    1992-01-01

    Nuclear techniques have been applied to study diagnose and treat various haematological disorders for more than five decades. Two scientists are regarded as pioneers in this field, i.e. John Lawrence who in 1938 used 32 P to treat chronic myeloid leukaemia and George Hevessy who used 32 P labelled erythrocytes to measure blood volume in 1939. At present, many nuclear medicine procedures are available for diagnosis and therapy of a variety of haematological disorders. Although nuclear techniques are somewhat complex, they give direct and quantitative assessment of the kinetics of blood elements as compared to other non-isotopic haematological tests. Basically, equipment required for nuclear haematology is very simple such as well scintillation counters to measure radioactivity in blood samples. More sophisticated equipment like rectilinear scanner or gamma camera is required when imaging is necessary. An overview of the basic principles and clinical applications of nuclear haematology is given

  14. Nuclear forensics

    International Nuclear Information System (INIS)

    Venugopal, V.

    2010-01-01

    Increasing threat by terrorists for a possible nuclear attack is particularly alarming in recent years. The likelihood of such an event is highly uncertain but cannot be ruled out. The consequence of such an event would be highly disastrous and the implications could be far-reaching both socially and politically. It is feared that significant amount of nuclear weapons materials may be kept under poor security. Therefore, there is a greater demand with utmost priority to curb nuclear terrorism by adapting proper security measures. One of the most important measures is to stop illicit trafficking of nuclear materials which are the source of building nuclear explosive devices. According to the IAEA illicit trafficking database (ITDB) report, a total number of 252 incidents were reported in 2006, of which 150 occurred in 2006 and the remaining 102 had taken place prior to that year, mainly in 2005

  15. Nuclear Safety

    International Nuclear Information System (INIS)

    1978-09-01

    In this short paper it has only been possible to deal in a rather general way with the standards of safety used in the UK nuclear industry. The record of the industry extending over at least twenty years is impressive and, indeed, unique. No other industry has been so painstaking in protection of its workers and in its avoidance of damage to the environment. Headings are: introduction; how a nuclear power station works; radiation and its effects (including reference to ICRP, the UK National Radiological Protection Board, and safety standards); typical radiation doses (natural radiation, therapy, nuclear power programme and other sources); safety of nuclear reactors - design; key questions (matters of concern which arise in the public mind); safety of operators; safety of people in the vicinity of a nuclear power station; safety of the general public; safety bodies. (U.K.)

  16. Nuclear proliferation

    International Nuclear Information System (INIS)

    Stencel, S.

    1978-01-01

    The terms and reactions to President Carter's nuclear policy, culminating in the 1978 Nuclear Non-Proliferation Act, are reviewed and analyzed. The new law increases restrictions on nuclear exports, encourages continued use of light water reactors in preference to plutonium-fueled reactors, and emphasizes technical solutions to proliferation problems. Critics of the law point out that it will hurt U.S. trade unfairly, that other countries do not have as many fuel options as the U.S. has, and that nuclear sales have as many political and economic as technical solutions. Compromise areas include new international safety guidelines, the possibility of an international nuclear fuel bank, and a willingness to consider each case on its merits. 21 references

  17. Nuclear privatization

    International Nuclear Information System (INIS)

    Jeffs, E.

    1995-01-01

    The United Kingdom government announced in May 1995 plans to privatize the country's two nuclear generating companies, Nuclear Electric and Scottish Nuclear. Under the plan, the two companies will become operating divisions of a unified holding company, to be called British Electric, with headquarters in Scotland. Britain's nuclear plants were left out of the initial privatization in 1989 because the government believed the financial community would be unwilling to accept the open-ended liability of decommissioning the original nine stations based on the Magnox gas-cooled reactor. Six years later, the government has found a way around this by retaining these power stations in state ownership, leaving the new nuclear company with the eight Advanced Gas-cooled Reactor (AGR) stations and the recently completed Sizewell B PWR stations. The operating Magnox stations are to be transferred to BNFL, which operates two Magnox stations of their own at Calder Hall and Chapelcross

  18. Nuclear haematology

    Energy Technology Data Exchange (ETDEWEB)

    Masjhur, J S

    1993-12-31

    Nuclear techniques have been applied to study diagnose and treat various haematological disorders for more than five decades. Two scientists are regarded as pioneers in this field, i.e. John Lawrence who in 1938 used {sup 32}P to treat chronic myeloid leukaemia and George Hevessy who used {sup 32}P labelled erythrocytes to measure blood volume in 1939. At present, many nuclear medicine procedures are available for diagnosis and therapy of a variety of haematological disorders. Although nuclear techniques are somewhat complex, they give direct and quantitative assessment of the kinetics of blood elements as compared to other non-isotopic haematological tests. Basically, equipment required for nuclear haematology is very simple such as well scintillation counters to measure radioactivity in blood samples. More sophisticated equipment like rectilinear scanner or gamma camera is required when imaging is necessary. An overview of the basic principles and clinical applications of nuclear haematology is given

  19. Competencia Desarrollo del Pensamiento Creativo

    OpenAIRE

    Rodríguez, Eric; Miceli, Francisco; Tiburcio, Georgina; Gómez, Orlando

    2012-01-01

    1. ¿Qué significa la competencia Desarrollo del Pensamiento Creativo? 2. ¿Por qué es relevante que adquiera la competencia Desarrollo del Pensamiento Creativo en mi formación? 3. ¿Cómo aprendo la competencia Desarrollo del Pensamiento Creativo? 4. ¿Cómo aplico la competencia Desarrollo del Pensamiento Creativo? 5. ¿Cómo puedo autoevaluar mi competencia (con miras a un constante crecimiento)?

  20. Upgrade in the CNSNS of the determination process about the importance for the impact evaluation to the safety of defaults or violations in the national nuclear facilities; Actualizacion en la CNSNS del proceso de determinacion de la importancia para la evaluacion de impacto a la seguridad de incumplimientos o violaciones en las instalaciones nucleares mexicanas

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

    Inside the process of Impact Evaluation to the Safety of the Direccion General Adjunta de Seguridad Nuclear of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the Significance Determination Process (SDP) is used, developed by the United States Nuclear Regulatory Commission (US NRC), to evaluate the violations or defaults to the regulatory framework and to determine its importance to the risk by means of a fixed color: Green (Very low impact to the safety), White (Low impact to moderate to the safety), Yellow (Substantial impact to the safety) or Red (High impact to the safety). All this inside the seven safety foundations of the Reactor Oversight Process: Initiator Events, Mitigation Systems, Integrity of the Barriers, Preparation for Emergencies, Occupational Radiological Safety, Radiological Safety of the Public and Physical Safety. At present the US NRC has developed a new version of the SDP, which presents changes in its structure and the opportunity of carrying out informed evaluations in risk, with more detail about the violations or defaults that happen in different areas. The CNSNS carries out the adaptation of this last version of the SDP in order to have an updated tool for the violations and defaults characterization to the regulatory framework happened in the nuclear power plant of Laguna Verde. In this article is mentioned the legal framework that confers the CNSNS the attributions to impose urgency measures and administrative sanctions to its licensees, also is established the definition of the different colors that the SDP contemplates in function of the increased risk (ΔCdf), a description of the SDP objectives and the elements that conform it is presented, in the same way some examples to illustrate its application are raised. Finally, the steps to continue for their implementation are mentioned. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

  3. Ruptura del projecte parental i disposició dels preembrions

    OpenAIRE

    Farnós Amorós, Esther

    2010-01-01

    La tesi doctoral "Ruptura del projecte parental i disposició dels preembrions" analitza els efectes del consentiment a les tècniques de reproducció assistida prestat en el marc d'un projecte parental. La tesi ofereix una resposta als conflictes que enfronten exesposos o exconvivents en relació al destí dels preembrions sobrants d'un cicle de fecundació "in vitro" iniciat durant la relació. Aquests conflictes constitueixen un grup de casos al voltant del qual no hi ha solucions legislatives qu...

  4. La equinoterapia en las distintas alteraciones del desarrollo del menor.

    OpenAIRE

    Chamorro González, Mireya

    2015-01-01

    La equinoterapia consiste en la utilización del caballo como un método terapéutico para rehabilitar a personas con discapacidad. Esta terapia es considerada una gran alternativa para aumentar el autoestima de los que sufren algún tipo de discapacidad, también a través de esta terapia se mejora y fortalece el estado emocional, así del mismo modo ayuda a mejorar la manera de desenvolverse en su entorno social. Esta terapia se realiza a través de la trasmisión del calor corporal del caballo, del...

  5. Gestión del riesgo del cambio (segunda parte)

    OpenAIRE

    Zorrilla Salgador, Juan Pablo

    2004-01-01

    Segunda parte del artículo acerca del uso de futuros sobre el tipo de cambio. Esta continuación abarca estrategias, definiciones, metodología y explicaciones sobre todo lo relacionado con el Ratio de cobertura de los futuros y la aparición del riesgo base.Segunda parte del artículo acerca del uso de futuros sobre el tipo de cambio. Esta continuación abarca estrategias, definiciones, metodología y explicaciones sobre todo lo relacionado con el Ratio de cobertura de los futuros y la aparición d...

  6. Nuclear questions

    Energy Technology Data Exchange (ETDEWEB)

    Durrani, M. [Physics World (United Kingdom)

    2006-01-01

    The future of nuclear power has returned to centre stage. Freezing weather on both sides of the Atlantic and last month's climate-change talks in Montreal have helped to put energy and the future of nuclear power right back on the political agenda. The issue is particularly pressing for those countries where existing nuclear stations are reaching the end of their lives. In the UK, prime minister Tony Blair has commissioned a review of energy, with a view to deciding later this year whether to build new nuclear power plants. The review comes just four years after the Labour government published a White Paper on energy that said the country should keep the nuclear option open but did not follow this up with any concrete action. In Germany, new chancellor and former physicist Angela Merkel is a fan of nuclear energy and had said she would extend the lifetime of its nuclear plants beyond 2020, when they are due to close. However, that commitment has had to be abandoned, at least for the time being, following negotiations with her left-wing coalition partners. The arguments in favour of nuclear power will be familiar to all physicists - it emits almost no carbon dioxide and can play a vital role in maintaining a diverse energy supply. To over-rely on imported supplies of oil and gas can leave a nation hostage to fortune. The arguments against are equally easy to list - the public is scared of nuclear power, it generates dangerous waste with potentially huge clean-up costs, and it is not necessarily cheap. Nuclear plants could also be a target for terrorist attacks. Given political will, many of these problems can be resolved, or at least tackled. China certainly sees the benefits of nuclear power, as does Finland, which is building a new 1600 MW station - the world's most powerful - that is set to open in 2009. Physicists, of course, are essential to such developments. They play a vital role in ensuring the safety of such plants and developing new types of

  7. del's Proof

    Indian Academy of Sciences (India)

    Home; Journals; Resonance – Journal of Science Education; Volume 12; Issue 5. Gödel's Proof - Incompleteness Theorems. S M Srivastava. General Article Volume 12 Issue 5 May 2007 pp 71-84. Fulltext. Click here to view fulltext PDF. Permanent link: https://www.ias.ac.in/article/fulltext/reso/012/05/0071-0084. Keywords.

  8. Marketing Mix del Software.

    Directory of Open Access Journals (Sweden)

    Yudith del Carmen Rodríguez Pérez

    2006-03-01

    Por ello, en este trabajo se define el concepto de producto software, se caracteriza al mismo y se exponen sus atributos de calidad. Además, se aborda la mezcla de marketing del software necesaria y diferente a la de otros productos para que este triunfe en el mercado.

  9. Gerencia del servicio

    OpenAIRE

    Nancy Peña Acosta

    1992-01-01

    Estamos en la era de la pirámide invertida donde el cliente es primero por lo que es fundamental incentivar la calidad desde abajo; hacer que el trabajador defina su misión, sienta que es parte de la compañía para que la satisfacción del negocio realizado sea de todos.

  10. El Juego del Juego

    OpenAIRE

    Carvalho, Nazaré Cristina

    2012-01-01

    DUVIGNAUD, Jean. El Juego del Juego. Santafé de Bogotá, Colômbia: Fondo de Cultura Econômica, 1997.The game gameDUVIGNAUD, Jean. The Game Game. Santafé de Bogotá, Colombia: Fondo de Cultura Econômica, 1997

  11. El helor del cuerpo

    OpenAIRE

    Sánchez-Biosca, Vicente

    1992-01-01

    Ensayo sobre las formas clásicas y modernas de la metamorfosis. En esta figura mitológica se advierte de manera privilegiada la entrada del imaginario científico, biológico y genético en el dominio de las construcciones literarias y cinematográficas.

  12. Carta del Editor

    Directory of Open Access Journals (Sweden)

    Luis Eladio Proaño

    2014-12-01

    Full Text Available La publicación se centra en temas como: Procesos electorales en México e Italia, se analizan los procesos comunicacionales y sus efectos; las infiltraciones de las agencias de seguridad en la actividad periodística en Europa; la radio y la televisión pública en los EE.UU. Para conocer cómo la prensa enfrenta los problemas críticos entre países, esta el caso de Uruguay y Argentina (discrepancia por la planta de procesamiento de papel y la contaminación del Río de La Plata. Otro artículo refiere la difícil relación entre los medios de comunicación y el gobierno de Chávez en Venezuela. Se aborda el caso brasileño para entender el crecimiento de los Observatorios de Medios; otro sobre el crecimiento del "periodismo confidencial" en la web y la prensa gratuita. Se estudia el impacto de la telenovela "pasión de gavilanes". Para quienes interese la penetración del Internet está: "Usos y competencias del weblog en las corporaciones" más otro sobre la lucha sorda que mantienen los gigantes de la autopista de la información Google y Yahoo.

  13. Punctualizaciones del CERN

    CERN Multimedia

    2002-01-01

    "Viene de la pagina anterior. Puntualizaciones del CERN. La valoracion que me merece la aprobacion en el Consejo de Ministros el 24 de mayo de un acuerdo de colaboracion entre el MCYT y el CERN para el proyecto de neutrinos al Gran Sasso es positiva" (1 page).

  14. A caccia del bosone di Higgs magneti, governi, scienziati e particelle nell'impresa scientifica del secolo

    CERN Document Server

    Maiani, Luciano

    2013-01-01

    Nel luglio 2012 veniva confermata sperimentalmente, presso i laboratori del CERN di Ginevra, l'esistenza del "bosone di Higgs", la più piccola di tutte le particelle subatomiche fino ad ora scoperte, teorizzata da Peter Higgs fin dal lontano 1964 e divulgata al mondo come "la particella di Dio". Una scoperta che costituisce un fondamentale passo avanti nella fisica delle particelle e nella conferma del modello standard dell'universo, in direzione di quella Teoria del Tutto, la teoria unificata delle forze, che la fisica insegue da decenni. Per giungere alla prima conferma sperimentale sono stati necessari quasi 50 anni di ricerche teoriche e la costruzione della macchina più grande del mondo, l'LHC, Large Hadron Collider, un anello lungo 27 chilometri situato a 100 metri di profondità nel territorio di Ginevra. Una sfida sul cui successo, all'inizio, pochi avrebbero scommesso e che si accompagna alla storia stessa del CERN, il Consiglio Europeo per la Ricerca Nucleare di cui Luciano Maiani è stato diretto...

  15. Software del sistema osteomioarticular

    Directory of Open Access Journals (Sweden)

    Dianelys León Medina

    2015-06-01

    Full Text Available Introducción: la aplicación en la enseñanza de las Tecnologías de la Informática y las Comunicaciones, es una de las líneas que ha trazado el sistema de salud cubano en estudiantes de las ciencias médicas. La anatomía es una de las ciencias que integra la disciplina de Morfofisiología y para facilitar su comprensión resulta necesario el empleo de recursos y estrategias, entre los que puede figurar un software educativo. Objetivo: diseñar un software sobre la anatomía del sistema osteomioarticular de cabeza y cuello para los estudiantes de primer año de la carrera de Estomatología de Pinar del Río. Material y método: se realizó un estudio cualitativo. Para obtener los resultados se utilizó el método materialista dialéctico. Para la dialéctica del desarrollo del proceso estudiado se utilizaron los métodos teóricos, empíricos, el estudio profundo del tema, tipo de plataforma a utilizar y criterios de los especialistas. Para su procesamiento se utilizaron técnicas estadísticas descriptivas e inferenciales no paramétricas. Resultados: debido a la necesidad de fortalecer en los estudiantes las habilidades en la utilización de las tecnologías de la informática y las comunicaciones, se elaboró el software de la anatomía del sistema osteomioarticular de cabeza y cuello "Aprendiendo anatomía" mediante imágenes, videos y textos. Conclusiones: el software constituye un aporte al proceso enseñanza aprendizaje, el cual facilita el trabajo independiente y autopreparación mediante la interactividad con el contenido, retroalimentación y evaluación utilizando medios de enseñanza modernos, lo cual tributa al modo de actuación del futuro egresado.

  16. Historia deldel = History of Padel

    Directory of Open Access Journals (Sweden)

    Bernardino Javier Sánchez-Alcaraz Martínez

    2013-10-01

    Full Text Available El presente trabajo resume la historia del deporte deldel. Existen dos versiones sobre el origen deldel. La primera versión relaciona los antecedentes deldel con los de otros deportes de raqueta como el tenis o el bádminton, siendo su origen común el jeu de la paume francés. Posteriormente, surgen variantes en Estados Unidos como el Paddle Tennis y el Platform Tennis, siendo versiones reducidas del tenis, pero con elementos muy comunes al pádel actual. La segunda versión, aprobada por la Federación Internacional de Pádel, afirma que este deporte nació en México, en 1969, a través del empresario Enrique Corcuera.--------------------------------------------------------------------This research summarizes the history of paddle sport. There are two versions about the origin of paddle. The first version relates the history of paddle with other racket sports like tennis or badminton, and its common origin of the Jeu de Paume French. Later, in in the United States, appear two sports called Paddle Tennis and Platform Tennis, which are reduced versions of tennis sport, but these have lot of common characteristics with paddle. The second version, approved by the International Padel Federation, said the sport was born in Mexico in 1969, through the businessman Enrique Corcuera.

  17. Determinantes del ingreso y del gasto corriente de los hogares

    Directory of Open Access Journals (Sweden)

    Muñoz C., Manuel

    2004-06-01

    Full Text Available Este ensayo de investigación empírica analiza los determinantes del ingreso y del gasto en los hogares colombianos. Utilizando un modelo del ciclo de vida con datos de la encuesta de hogares de 1994 y 1995, muestra que el comportamiento del ingreso está afectado principalmente por las características demográficas del hogar y los rasgos socio ocupacionales de sus miembros. El comportamiento del gasto está determinado ante todo por el ingreso y, en menor medida, por las características sociales del hogar y el gasto de otros hogares con características similares. También examina la influencia de la incertidumbre acerca de los ingresos en el gasto de los hogares para comprobar si estos actúan con motivos de precaución.

  18. Nuclear energy

    International Nuclear Information System (INIS)

    Rippon, S.

    1984-01-01

    Do we need nuclear energy. Is it safe. What are the risks. Will it lead to proliferation. The questions are endless, the answers often confused. In the vigorous debates that surround the siting and operation of nuclear power plants, it is all too easy to lose sight of the central issues amid the mass of arguments and counter-arguments put forward. And there remains the doubt, who do we believe. This book presents the facts, simply, straightforwardly, and comprehensibly. It describes the different types of nuclear reactor, how they work, how energy is produced and transformed into usable power, how nuclear waste is handled, what safeguards are built in to prevent accident, contamination and misuse. More important, it does this in the context of the real world, examining the benefits as well as the dangers of a nuclear power programme, quantifying the risks, and providing an authoritative account of the nuclear industry worldwide. Technically complex and politically controversial, the contribution of nuclear energy to our future energy requirements is a crucial topic of our time. (author)

  19. Estudio del CH interestelar

    Science.gov (United States)

    Olano, C.; Lemarchand, G.; Sanz, A. J.; Bava, J. A.

    El objetivo principal de este proyecto consiste en el estudio de la distribución y abundancia del CH en nubes interestelares a través de la observación de las líneas hiperfinas del CH en 3,3 GHz. El CH es una molécula de amplia distribución en el espacio interestelar y una de las pocas especies que han sido observadas tanto con técnicas de radio como ópticas. Desde el punto de vista tecnológico se ha desarrollado un cabezal de receptor que permitirá la realización de observaciones polarimétricas en la frecuencia de 3,3 GHz, con una temperatura del sistema de 60 K y un ancho de banda de 140 MHz, y que será instalado en el foco primario de la antena parabólica del IAR. El cabezal del receptor es capaz de detectar señales polarizadas, separando las componentes de polarización circular derecha e izquierda. Para tal fin el cabezal consta de dos ramas receptoras que amplificarán la señal y la trasladarán a una frecuencia más baja (frecuencia intermedia), permitiendo de esa forma un mejor transporte de la señal a la sala de control para su posterior procesamiento. El receptor además de tener características polarimétricas, podrá ser usado en el continuo y en la línea, utilizando las ventajas observacionales y de procesamiento de señal que actualmente posee el IAR.

  20. Nuclear Hostages

    International Nuclear Information System (INIS)

    Cooper, C.L.

    1978-01-01

    The global spread of nuclear reactors for the production of energy seems inevitable. Nuclear power plants will be supplied--if not by the United States, then by one of several other exporters. But other aspects of this development are less certain. One is the relationship between proliferation of nuclear energy plants and that of nuclear weapons. Another is the actual constraint that such vulnerable potential targets as nuclear power plants would have on would-be aggressors. In the last analysis, this would depend on the rationality of a nation's leadership. What can be said for the concept of nuclear power plants as potential hostages is that by installing a reactor on its territory, a country increases its vulnerability to grave, possibly unacceptable damage in the event of war. As a result, that nation's leaders might be inclined to raise the threshold of their sensitivity to provocation by neighbors and to restrain their own inclinations toward aggression. Admittedly this is a frail substitute for robust international agreements, but in the present order of things it is not a trivial consideration. Many incidents once regarded by the great powers as easi belli have more recently been either resolved by diplomacy or ignored altogether. The idea must not be pressed too far. The export of a nuclear power plant to a Third World country cannot be advocated simply as a means to constrain its own military adventurism. Aside from the promise of a vast increase in energy supply for developing nations, nuclear powered generating stations could actually improve relations among countries. The risk of widespread radioactive contamination by nuclear power plants hit by even conventional bombs could introduce a positive new element into the military calculations of powers outside the NATO-Warsaw Pact arena. As they balance military and diplomatic solutions to local conflicts, moderation rather than bellicosity might become the better part of valor

  1. Nuclear medicine

    International Nuclear Information System (INIS)

    Kand, Purushottam

    2012-01-01

    Nuclear medicine is a specialized area of radiology that uses very small amounts of radioactive materials to examine organ function and structure. Nuclear medicine is older than CT, ultrasound and MRI. It was first used in patients over 60-70 years ago. Today it is an established medical specialty and offers procedures that are essential in many medical specialities like nephrology, pediatrics, cardiology, psychiatry, endocrinology and oncology. Nuclear medicine refers to medicine (a pharmaceutical) that is attached to a small quantity of radioactive material (a radioisotope). This combination is called a radiopharmaceutical. There are many radiopharmaceuticals like DTPA, DMSA, HIDA, MIBI and MDP available to study different parts of the body like kidneys, heart and bones etc. Nuclear medicine uses radiation coming from inside a patient's body where as conventional radiology exposes patients to radiation from outside the body. Thus nuclear imaging study is a physiological imaging, whereas diagnostic radiology is anatomical imaging. It combines many different disciplines like chemistry, physics mathematics, computer technology, and medicine. It helps in diagnosis and to treat abnormalities very early in the progression of a disease. The information provides a quick and accurate diagnosis of wide range of conditions and diseases in a person of any age. These tests are painless and most scans expose patients to only minimal and safe amounts of radiation. The amount of radiation received from a nuclear medicine procedure is comparable to, or often many times less than, that of a diagnostic X-ray. Nuclear medicine provides an effective means of examining whether some tissues/organs are functioning properly. Therapy using nuclear medicine in an effective, safe and relatively inexpensive way of controlling and in some cases eliminating, conditions such as overactive thyroid, thyroid cancer and arthritis. Nuclear medicine imaging is unique because it provides doctors with

  2. Nuclear inheritance

    International Nuclear Information System (INIS)

    Delpech, Therese

    1997-01-01

    Since the end of the East-West confronting, the nuclear weapon issue has been focused in an international debate with obvious repercussions in Europe, because it is the European continent which indicated first the significance of nuclear deterrence. This debate refers first upon the past, as the German unification allowed capturing numerous documents of Warsaw treaty which revealed the intentions and the plans of Soviet Union during the cold war, and secondly concerns the future, since the role of nuclear weapons must be re-thought in a new context. This is the subject of this book, which refers also to the problem of the nuclear proliferation in the world and evolution of different countries in a political and regional context. The extension of the non-proliferation treaty for an undefined duration, in May 1995, is a incontestable victory because this treaty rules the renouncement to nuclear weapons of 185 countries. However, it does not solve most sensible problems like the Iraq case, for which a specific inspection regime has been instituted, or the case of Iran, which is suspected to acquire the bomb, although no clear evidence has been provided up to now. This is also the case of Israel, India and Pakistan which allege plainly their willingness of keeping open, from security reasons, their nuclear option. The content is displayed in five chapters: 1. Introduction; 2. The role of the nuclear weapons after the cold war; 3. The nuclear proliferation at crossroads; 4. Undefined extension of the NPT, a striking but fragile victory; 5. Conclusions. An appendix containing the text of the Nuclear Weapon Non-Proliferation Treaty and a chronology are added

  3. La pluridimensionalidad del rol del docente hospitalario

    Directory of Open Access Journals (Sweden)

    Marian Serradas Fonseca

    2015-07-01

    Full Text Available Este trabajo es el fruto de la observación y la investigación en la trayectoria personal y profesional de la autora dedicada a la educación de niños y niñas en situación de enfermedad u hospitalización. El objetivo de este ensayo es intentar definir de manera específica, el papel, tareas y competencias que el profesional del ámbito educativo tiene en la atención educativa hospitalaria; haciendo especial énfasis en la importancia de la formación de este profesional abogándose por una preparación que permita brindar una atención educativa de calidad a los niños y niñas en situación de enfermedad u hospitalizados.

  4. Nuclear energy

    International Nuclear Information System (INIS)

    Hladky, S.

    1985-01-01

    This booklet appeared in a series on technical history. It tries to communicate some of the scientific, technical and social stresses, which have been connected with the application of nuclear energy since its discovery. The individual sections are concerned with the following subjects: the search for the 'smallest particles'; the atomic nucleus; nuclear fission; the 'Manhattan Project'; the time after this - from the euphoria of the 1950's via disillusionment and change of opinion to the state of nuclear energy at the start of the 1980's. The booklet contains many details and is generously illustrated. (HSCH) [de

  5. Nuclear transport

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    During january and february 2003, a unique event concerning nuclear transport was reported and rated 1 on the INES scale. This event concerns the absence of a maintenance operation on a shipping cask. This shipping cask was used for several years for nuclear transport inside La-hague site before being re-assigned to transport on public thoroughfare. The re-assignment of the cask should have been preceded and conditioned by a maintenance operation whose purpose is to check the efficiency of its radiation shield. During this period 2 on-site inspections concerning the transport of nuclear materials were performed. (A.C.)

  6. Nuclear energy

    International Nuclear Information System (INIS)

    Luxo, Armand.

    1977-01-01

    The reasons and conditions of utilizing nuclear power in developing countries are examined jointly with the present status and future uses already evaluated by some organizations. Some consequences are deduced in the human, financial scientific and technological fields, with provisional suggestions for preparing the nuclear industry development in these countries. As a conclusion trends are given to show how the industrialized countries having gained a long scientific and technological experience in nuclear energy can afford their assistance in this field, to developing countries [fr

  7. Nuclear questions

    International Nuclear Information System (INIS)

    Hohlfeld, W.

    1977-01-01

    This brochure 'nuclear problems' deals with the attitude of the protestant church in the region around the northern Elbe towards further quantitative economic growth, esp. nuclear energy, with the following essays: preaching the Gospel in an environment in danger: the Christian occident and the problems of the third world, facing the problems of exhausted supplies, the role of the prophet, problem of environment - a problem of theology, the political dimension, against ATW, signal Brokdorf, strange effects (defense of the church from unqualified teachings by non-professionals), Christian liberty, church and nuclear energy, violence and robes. (HP) [de

  8. Rotterdam Nuclear

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    In 1965 Rotterdam Nuclear received an order for the design, supply of materials, manufacture, testing, inspection and preparation for shipment of one 450MW Boiling Water Reactor pressure vessel. This was one of the first orders for a reactor pressure vessel, ever obtained by a European Manufacturer. The Company has since supplied 19 reactor pressure vessels for nuclear power stations, having a total weight of about 10,000,000kg. The nuclear power stations in which these are installed represent an electrical output of about 15,000MW and they are located in seven different countries (USA, Spain, Switzerland, Argentina, Sweden, Germany and the Netherlands). (Auth.)

  9. Nuclear law

    International Nuclear Information System (INIS)

    Bringuier, P.

    2009-01-01

    The object of this report is to present the evolution of the nuclear law during the period from 2006 to 2008, period that was characterized in France by a real rewriting from the implementation of a control authority. The prescriptive backing of nuclear activities has been deeply changed by numerous texts. In this first part are presented: (1) the institutional aspects, (2) openness and public information, (7) radioactive wastes and (9) liability and insurance. In a next publication will be treated: (3) safety and radiation protection; (4) nuclear matter, inspection, physical protection; (5) transports; (6) trade, non-proliferation; (8) radiological accidents. (N.C.)

  10. Nuclear fuel

    International Nuclear Information System (INIS)

    D Hondt, P.

    1998-01-01

    The research and development programme on nuclear fuel at the Belgian Nuclear Research Centre SCK/CEN is described. The objective of this programme is to enhance the quantitative prediction of the operational limits of nuclear fuel and to assess the behaviour of fuel under incidental and accidental conditions. Progress is described in different domains including the modelling of fission gas release in LWR fuel, thermal conductivity, basic physical phenomena, post-irradiation examination for fuel performance assessment, and conceptual studies of incidental and accidental fuel experiments

  11. Nuclear energy

    International Nuclear Information System (INIS)

    Wethe, Per Ivar

    2009-01-01

    Today we know two forms of nuclear energy: fission and fusion. Fission is the decomposition of heavy nuclei, while fusion is the melting together of light nuclei. Both processes create a large surplus of energy. Technologically, we can currently only use fission to produce energy in today's nuclear power plants, but there is intense research worldwide in order to realize a controlled fusion process. In a practical context, today's nuclear energy is a sustained source of energy since the resource base is virtually unlimited. When fusion technology is realized, the resource supply will be a marginal problem. (AG)

  12. Nuclear electronics

    International Nuclear Information System (INIS)

    Lucero B, E.

    1989-01-01

    The rapid technical development of Colombia over the past years, resulted among others, a considerable increase in the number of measuring instrumentation and testing laboratories, scientific research and metrology centers, in industry, agriculture, public health, education on the nuclear field, etc. IAN is a well organized institution with qualified management, trained staff and reasonably equipped laboratories to carry out tasks as: Metrology, standardization, quality control and maintenance and repair of nuclear instruments. The government of Colombia has adopted a policy to establish and operate through the country maintenance and repair facilities for nuclear instrumentation. This policy is reflected in the organization of electronic laboratories in Bogota-IAN

  13. ¿Comprendemos realmente el significado del ALCA?

    Directory of Open Access Journals (Sweden)

    Orlando Zelaya Martínez

    2004-06-01

    Full Text Available Después de finalizada la segunda guerra mundial, Estados Unidos se convierte en el gendarme del mundo tanto en lo económico como en lo político, razón por cual decide no únicamente convertirse en el banquero del mundo, sino en su salvador ante el potencial peligro que representaba el comunismo como sistema. De esta forma crea un nuevo tipo de guerra de intensidad en el enfrentamiento directo, pero trasladando tal circunstancia al campo de la amenaza nuclear. Nos estamos refiriendo a la "Guerra Fría": el incentivo para que las dos nuevas potencias militares del mundo desarrollen una infraestructura de industria pesada bélica.

  14. The Fragmentation of Heavy Nuclei by 13.8 GeV/c Protons as a Contribution to the Study of the Interaction Mechanism and Nuclear Structure; Fragmentacion de nucleos pesados por protones de 13'8 GeV/c, como contribucion al estudio del mecanismo de interaccion y estructura nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gil Perez, D.

    1967-07-01

    We present here an global study of the interaction between high- energy particles and heavy nuclei, an interaction which holds obvious interest in relation to the problems of nuclear fragmentation and which, up lo now has only been studied piecemeal. We have used three stacks of photographic emulsions which were irradiated by 13.8 GeV/c protons, 17 GeV/c negative pions and 24 GeV/c protons. All three irradiations took place in a 180 K.G. magnetic field using CERN beams. (Author) 20 refs.

  15. The Fragmentation of Heavy Nuclei by 13.8 GeV/c Protons as a Contribution to the Study of the Interaction Mechanism and Nuclear Structure; Fragmentacion de nucleos pesados por protones de 13'8 GeV/c, como contribucion al estudio del mecanismo de interaccion y estructura nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Gil Perez, D

    1967-07-01

    We present here an global study of the interaction between high- energy particles and heavy nuclei, an interaction which holds obvious interest in relation to the problems of nuclear fragmentation and which, up lo now has only been studied piecemeal. We have used three stacks of photographic emulsions which were irradiated by 13.8 GeV/c protons, 17 GeV/c negative pions and 24 GeV/c protons. All three irradiations took place in a 180 K.G. magnetic field using CERN beams. (Author) 20 refs.

  16. Nuclear wastes

    International Nuclear Information System (INIS)

    2002-01-01

    This scientific document presents an introduction to the nuclear wastes problems, the separation process and the transmutation, the political and technical aspects of the storage, the radioprotection standards and the biological effects. (A.L.B.)

  17. Nuclear Disarmament.

    Science.gov (United States)

    Johnson, Christopher

    1982-01-01

    Material about nuclear disarmament and the arms race should be included in secondary school curricula. Teachers can present this technical, controversial, and frightening material in a balanced and comprehensible way. Resources for instructional materials are listed. (PP)

  18. Nuclear analysis

    International Nuclear Information System (INIS)

    1988-01-01

    Basic studies in nuclear analytical techniques include the examination of underlying assumptions and the development and extention of techniques involving the use of ion beams for elemental and mass analysis. 1 ref., 1 tab

  19. Nuclear reaction

    CERN Multimedia

    Penwarden, C

    2001-01-01

    At the European Research Organization for Nuclear Research, Nobel laureates delve into the mysteries of particle physics. But when they invited artists from across the continent to visit their site in Geneva, they wanted a new kind of experiment.

  20. [Nuclear theory

    International Nuclear Information System (INIS)

    1989-06-01

    This report discusses concepts in nuclear theory such as: neutrino nucleosynthesis; double beta decay; neutrino oscillations; chiral symmetry breaking; T invariance; quark propagator; cold fusion; and other related topics