WorldWideScience

Sample records for nucleares del codigo

  1. Ponencia 40. Aniversario del Codigo de Comercio: pasado, presente y futuro de la regulacion del contrato de seguro en el Codigo de Comercio Colombiano de 1.971

    National Research Council Canada - National Science Library

    Ordonez Ordonez, Andres E; Jaramillo, Carlos Ignacio; Barrera, Carlos Dario

    2012-01-01

    En el presente articulo los autores realizan un analisis del pasado, presente y futuro del derecho de seguros, teniendo como punto de partida la expedicion del Codigo de Comercio de 1971 y su conjunto...

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  4. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  5. Responsabilidad por productos defectuosos: del codigo civil al estatuto de proteccion al consumidor

    National Research Council Canada - National Science Library

    Plata Lopez, Luis Carlos

    2006-01-01

    ...; proteccion que tiene que ver con el saneamiento por vicios ocultos consagrado desde el Codigo Civil, pasando por la presuncion de garantia de funcionamiento, consagrada en el Codigo de Comercio...

  6. 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

    Energy Technology Data Exchange (ETDEWEB)

    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

  7. Application of simulation codes in the optimization of the design of fire protection at nuclear power plants; Aplicacion de codigos de simulacion en la optimizacion del diseno de la proteccion contra incendios en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Amezcua, V.

    2011-07-01

    The evolution of fire protection codes and standards has permitted the use of fire simulation tools for design and optimization of fire protection solution, as an alternative to the traditional deterministic approach. This alternative results in a more flexible design, suiting the solution to the real conditions and risks. In this context, Empresarios Agrupados (EEAA) is carrying out a project jointly with the CSN (the Spanish Nuclear Safety Council), in the area of fire modelling and simulation, aimed for developing a method for the reliable application of the fire simulation models to nuclear power plants scenarios. (Author)

  8. Validation of WIMS-SNAP code systems for calculations in TRIGA-MARK II type reactors; Validacion del sistema de codigos WIMS-SNAP para calculos en reactores nucleares tipo TRIGA-MARK II

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez Valle, S.; Lopez Aldama, D. [Centro de Investigaciones Nucleares, Tecnologicas y Ambientales, La Habana (Cuba). E-mail: svalle@ctn.isctn.edu.cu

    2000-07-01

    The following paper contributes to validate the Nuclear Engineering Department methods to carry out calculations in TRIGA reactors solving a Benchmark. The benchmark is analyzed with the WIMS-D/4-SNAP/3D code system and using the cross section library WIMS-TRIGA. A brief description of the DSN method is presented used in WIMS/d{sup 4} code and also the SNAP-3d code is shortly explained. The results are presented and compared with the experimental values. In other hand the possible error sources are analyzed. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

  10. Analysis of the second part of the fuel cycle of nuclear spanish park using module TR{sub E}VOL of EVOLCODE2; Simulacion del ciclo de combustible del parque nuclear espanol con el codigo TR{sub E}VOL.

    Energy Technology Data Exchange (ETDEWEB)

    Merino Rodriguez, I.; Alvarez-Velarde, F.; Martin-Fuertes, F.

    2011-07-01

    This paper describes the application of the code TR{sub E}VOL an associated fuel cycle Spanish nuclear park, with the objective of estimating the mass of nuclear fuel manufactured by reactor and the mass generated of irradiated fuel.

  11. Un codigo urgente para la arquitectura y la vivienda en Bogota

    National Research Council Canada - National Science Library

    Anzellini Fajardo, Stefano

    2010-01-01

    .... A continuacion se exponen los temas de discusion en cuanto a, por un lado, cual es la pertinencia y la funcion de un codigo "sostenible", como se inserta en el proceso de produccion del entorno...

  12. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  13. Report of generation of the nuclear bank Presto-Hot for the CAORSO 3.26 fuel with the FMS codes; Reporte de generacion del banco nuclear Presto-Hot para el combustible CAORSO 3.26 con los codigos del FMS

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1991-03-15

    In this work it is described in a general way the form in that it was generated the database of the CAORSO 3.26 fuel for to analyze their use in a future reload for Laguna Verde. The formation of the bank was carries out with the ECLIPSE 86-2D, RECORD 89-1A and POLGEN 88-1B codes of the FMS package installed in the VAX system of the offices of the National Commission of Nuclear Safety and Safeguards in Mexico City. The formed bank is denominated 'L1PG9105'. All this one carries out following the '6F3/I/CN029/90/P1' procedure. The generated database contains the enough information in terms of constant in two dependent groups of burnt and instantaneous holes, for the different arrangements of bars present in the one assemble as well as those coefficients that take into account the presence of the control bar, the variation in the fuel temperature and the effect of the 'historical' holes. All this is included in it that one knows as SUPER option of the bank for PRESTO with those options PRCOEF and POLRAM. Also, in the Annex G of this report, the M-FACTOR, the Xenon coefficients and the burnt parameters of the control bar for PRESTO its are by separate provided. They are also presented charts and comparative graphic of the obtained results in the BURNT cell series for three percentages of holes in the moderator, 0%, 40% and 70%, for each one of the five cells identified in the one assemble. (Author)

  14. Report of generation of the nuclear bank Presto-Hot for the CAORSO 3.29 fuel with the FMS codes; Reporte de generacion del banco nuclear Presto-Hot para el combustible CAORSO 3.29 con los codigos del FMS

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1992-10-15

    Prior to the CAORSO 3.26 fuel data bank had been generated whose active longitude was of 144 inches, longitude that not this in agreement with the used assemblies in the unit 1 of Laguna Verde, of 150 inches of active longitude. When realizing this difference, it was speak with the personnel of the CAORSO plant to verify if there was some error in the sent information. The CAORSO personnel, when verifying it, point out that they sent us information of another fuel and that the appropriate one for our plant is that of the CAORSO 3.29 fuel, that which made necessary the generation of this bank. In this work in a general way the form in that was generated the data bank of the CAORSO 3.29 fuel to analyze their use in a future reload for Laguna Verde is described. The formation of the bank was carried out with the ECLIPSE 86-2D, RECORD 89-1A and POLGEN 88-1B of the FMS package installed in the VAX system of the offices of the National Commission of Nuclear Safety and Safeguards in Mexico D.F and in the Electric Investigations Institute in Cuernavaca, Morelos. The formed bank is denominated 'L1PG9110' and was carried out following the '6F3/I/CN029/90/P1' procedure. The generated data bank contains the enough information in terms of constant in two groups of burnt dependent and instantaneous vacuums, for the different arrangements of fuel bars present in the assemble, as well as those coefficients that take into account the presence of the control bar, the variation in the fuel temperature and the effect of the 'historical' vacuums. All this is included in that is known as SUPER option of the bank for PRESTO with the options PRCOEF and POLRAM. Also, in the Annex G of this report, is provided by separate the M-FACTOR, the Xenon coefficients and the burnt parameters of the control bar for PRESTO. Its are also presented charts and comparative graphic of the obtained results in the BURNT series of the cell for three vacuum percentages in the

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

  16. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  19. Codigos eticos: construcclon colectiva del caracter organizacional, EI caso de la Universidad Nacional de Colombia, sede Manizales

    Directory of Open Access Journals (Sweden)

    Maria del Pilar Rodriguez c.

    2004-12-01

    Full Text Available El presente artículo parte de una discusión teórica sobre la ética y la ética empresarial, para apoyar la posición de los autores en cuanto a que los códigos éticos contribuyen a la construcción colectiva del carácter organizacional. Seguidamente, propone una metodología participativa, diseñada en investigaciones previas por miembros del grupo de investigación en Ética Empresarial y Empresariado Social - ETHOS, para elaborar códigos éticos en empresas. A continuación, la ejemplifica mediante el caso de la Universidad Nacional de Colombia Sede Manizales, donde se está implementando un programa integral de desarrollo ético.

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  1. Application of thermal-hydraulic codes in the nuclear sector; Aplicaciones de los codigos termo-hidraulicos en el sector nuclear espanol

    Energy Technology Data Exchange (ETDEWEB)

    Queral, C.; Coriso, M.; Garcia Sedano, P. J.; Ruiz, J. A.; Posada, J. M.; Jimenez Varas, G.; Sol, I.; Herranz, L. E.

    2011-07-01

    Use of thermal-hydraulic codes is extended all over many different aspects of nuclear engineering. This article groups and briefly describes the main features of some of the well known codes as an introduction to their recent applications in the Spain nuclear sector. the broad range and quality of applications highlight the maturity achieved both in industry and research organizations and universities within the Spanish nuclear sector. (Author)

  2. EL JUICIO DE APARIENCIA DE BUEN DERECHO FRENTE A LA IMPARCIALIDAD DEL JUEZ QUE DECRETA MEDIDAS CAUTELARES INNOMINADAS CONFORME EL CODIGO GENERAL DEL PROCESO EN COLOMBIA

    OpenAIRE

    Laguado Serrano, Cristian Eduardo; Vargas Buitrago, Jordan Aquiles

    2015-01-01

    La presente tesis denominada “El juicio de apariencia de buen derecho frente a la imparcialidad del juez que decreta medidas cautelares innominadas conforme el código general del proceso en Colombia”, plantea que a través la reforma del código de procedimiento civil buscando lograr un código general del proceso, al implementar las denominadas medidas cautelares innominadas se establecieron una serie de requisitos que a simple vista son claros y precisos; no obstante, al llevar ...

  3. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  4. Simulation of a nuclear densimeter using the Monte Carlo MCNP-4C code; Simulacao de um densimetro nuclear utilizando o codigo Monte Carlo MCNP-4C

    Energy Technology Data Exchange (ETDEWEB)

    Penna, Rodrigo [UNI-BH, Belo Horizonte, MG (Brazil). Dept. de Ciencias Biologicas, Ambientais e da Saude (DCBAS/DCET); Silva, Clemente Jose Gusmao Carneiro da [Universidade Estadual de Santa Cruz, UESC, Ilheus, BA (Brazil); Gomes, Paulo Mauricio Costa [Universidade FUMEC, Belo Horizonte, MG (Brazil)

    2008-07-01

    Viability of building a nuclear wood densimeter based on low energy photons Compton scattering was done using Monte Carlo code (MCNP- 4C). It is simulated a collimated 60 keV beam of gamma rays emitted by {sup 241}Am source reaching wood blocks. Backscattered radiation by these blocks was calculated. Photons scattered were correlated with blocks of different wood densities. Results showed a linear relationship on wood density and scattered photons, therefore the viability of this wood densimeter. (author)

  5. Efectos del entorno de actividad nuclear

    OpenAIRE

    Sabater, J.; Verdes-Montenegro, L.; Leon, S.; Sulentic, J.; Lisenfeld, Ute; Verley, S.

    2010-01-01

    Presentamos un estudio de la relaci??n entre los efectos del entorno y el fen??meno de la actividad nuclear en general y la actividad nuclear de tipo radio (presencia de un chorro) en particular, en una muestra de galaxias aisladas.

  6. DINÁMICA DEL COMPLEJO DEL PORO NUCLEAR

    Directory of Open Access Journals (Sweden)

    TD GEYDAN

    2010-01-01

    Full Text Available El complejo del poro nuclear (CPN es un conjunto supra-molecular compuesto de múltiples copias de 30 familias de proteínas diferentes, siendo 456 nucleoporinas (Nups en total, que atraviesan la envoltura nuclear de todos los organismos pertenecientes al dominio Eukaria. El CPN es la compuerta del núcleo; por lo tanto, todas las macromo- léculas deben atravesarla para transitar del núcleo al citoplasma y viceversa. Durante los últimos años, se han propuesto varios modelos para explicar la regulación y el transporte de macromoléculas a través del CPN. En esta nota se describe la estructura, los meca- nismos y procesos involucrados durante el transporte a través del CPN, y cómo estos procesos son regulados por interacciones macromoleculares altamente dinámicas.

  7. SPARC-90 code improvement to simulate vapour generator breakages; Mejora del codigo SPARC90 para simular roturas en el generado de vapor

    Energy Technology Data Exchange (ETDEWEB)

    Escriva Castells, A.

    2010-07-01

    The Thermohydraulic and Nuclear Engineering Group of the UPV; together with the CIEMAT; is developing improvements in the decontamination factor calculation in order to introduce them in SPARC90 code (Suppression Pool Aerosol Removal Code). This code calculates the capture of aerosols in pools, which is especially important in case of accident.

  8. 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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  9. 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)

  10. DINÁMICA DEL COMPLEJO DEL PORO NUCLEAR DINAMICS OF NUCLEAR PORE COMPLEX

    Directory of Open Access Journals (Sweden)

    TD GEYDAN

    Full Text Available El complejo del poro nuclear (CPN es un conjunto supra-molecular compuesto de múltiples copias de 30 familias de proteínas diferentes, siendo 456 nucleoporinas (Nups en total que atraviesan la envoltura nuclear de todos los organismos pertenecientes al dominio Eukaria. El CPN es la compuerta del núcleo por lo tanto, todas las macromoléculas deben atravesarla para transitar del núcleo al citoplasma y viceversa. Durante los últimos años, se han propuesto varios modelos para explicar la regulación y el transporte de macromoléculas a través del CPN. En este escrito se describe la estructura, los mecanismos y procesos involucrados durante el transporte a través del CPN, y cómo estos procesos son regulados por interacciones macromoleculares altamente dinámicas.The nuclear pore complex (NPC is a large supramolecular assemble made up of multiple copies of about 30 different families proteins, so in total 456 nucleoporines (Nups span the nuclear envelope of all Eukariotic organisms. The NPC is considered the gate through which all macromolecules must pass in order to achieve nucleo-cytoplasmic transport. The aim of this review is to describe the structure, mechanisms and processes involved during the transportation of molecules and how of these processes are regulated by highly dynamic macromolecular interactions with molecules of the NPC which have been described during the past years.

  11. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)]. E-mail: hsalazar22@prodigy.net.mx

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  13. 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)

  14. 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)

  15. Development of an interface between MCNP and ORIGEN codes for calculations of fuel evolution in nuclear systems. Initial project; Desenvolvimento de uma interface entre os codigos MCNP e ORIGEN para calculos de evolucao de combustiveis em sistemas nucleares. Projeto inicial

    Energy Technology Data Exchange (ETDEWEB)

    Campolina, Daniel de Almeida Magalhaes

    2009-07-01

    In Many situations of nuclear system study, it is necessary to know the detailed particle flux in a geometry. Deterministic 1-D and 2-D methods aren't suitable to represent some strong 3-D behavior configurations, for example in cores where the neutron flux varies considerably in the space and Monte Carlo analysis are necessary. The majority of Monte Carlo transport calculation codes, performs time static simulations, in terms of fuel isotopic composition. This work is a initial project to incorporate depletion capability to the MCNP code, by means of a connection with ORIGEN2.1 burnup code. The method to develop the program proposed followed the methodology of other programs used to the same purpose. Essentially, MCNP data library are used to generate one group microscopic cross sections that override default ORIGEN libraries. To verify the actual implemented part, comparisons which MCNPX (version 2.6.0) results were made. The neutron flux and criticality value of core agree. The neutron flux and criticality value of the core agree, especially in beginning of burnup when the influence of fission products are not very considerable. The small difference encountered was probably caused by the difference in the number of isotopes considered in the transport models (89 MCNPX x 25 GB). Next step of this work is to adapt MCNP version 4C to work with a memory higher than its standard value (4MB), in order to allow a greater number of isotopes in the transport model. (author)

  16. 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

    Energy Technology Data Exchange (ETDEWEB)

    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)

  17. 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)

  18. Elementos relevantes del proyecto de una central nuclear

    Directory of Open Access Journals (Sweden)

    Díaz-Llanos Ros, Miguel

    1990-02-01

    Full Text Available Several topics were selected on the characteristics of Nuclear Power Plant design. The licensing process of USA and Germany (FRG are compared. An introduction to the Quality Assurance Programme as an essential item in the nuclear field is presented. The integration of computer applications as part of the engineering approach to design is explained and comments are made on four computer developments.

    Se presentan varios aspectos elegidos dentro de los característicos del proyecto de una central nuclear. Se comparan los procesos de licencia en EE.UU. y en Alemania (RFA. Se introduce el programa de Garantía de Calidad como proceso esencial en este tipo de instalaciones. Finalmente, se expone la integración de aplicaciones mecanizadas del proyecto, y se comentan cuatro áreas de desarrollo informático.

  19. Simulation of an operation cycle of nuclear power plant of Laguna Verde with code TACHY and computation package CMS; Simulacion de un ciclo de operacion de la CNLV con el codigo TACHY y el paquete de computo CMS

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, J. A.; Del Valle, E.; Vargas, S.; Xolocostli, J. V. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: joseangel.gonzalez@inin.gob.mx

    2009-10-15

    In this work the code TACHY is used, to simulate an operation cycle of the nuclear power plant of Laguna Verde. The code TACHY was designed originally to analyze recharge patterns of Hindu plants type BWR, that have near 800 assemblies, that is almost double the reactor of nuclear power plant of Laguna Verde. For this reason it was necessary to modify the code to be able to apply it to nuclear power plant of Laguna Verde. The values were modified like: operation power, entrance subcooling, flow through the nucleus, assemblies number in nucleus and dimensions of nucleus. In this work is take like base the cycle 9 of Unit 2 of nuclear power plant of Laguna Verde. This cycle is simulated with code TACHY and with code SIMULATE-3 that is part of computation package Core Management System, with the purpose of comparing the results. The results that are compared with the two codes, for the complete nucleus are: the burnt average of nucleus, the cycle longitude, the effective factor of neutrons multiplication, the pick of radial relative power; and for each assembly: the burnt and the relative power. Of the results obtained with TACHY we can conclude that we have a computation tool that allows to analyze a great number of recharge patterns in a reasonable time. (Author)

  20. 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)

  1. 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)

  2. 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.

  3. 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.

  4. Subcritical calculation of the nuclear material warehouse;Calculo de subcriticidad del almacen del material nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Garcia M, T.; Mazon R, R., E-mail: teodoro.garcia@inin.gob.m [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2009-07-01

    In this work the subcritical calculation of the nuclear material warehouse of the Reactor TRIGA Mark III labyrinth in the Mexico Nuclear Center is presented. During the adaptation of the nuclear warehouse (vault I), the fuel was temporarily changed to the warehouse (vault II) and it was also carried out the subcritical calculation for this temporary arrangement. The code used for the calculation of the effective multiplication factor, it was the Monte Carlo N-Particle Extended code known as MCNPX, developed by the National Laboratory of Los Alamos, for the particles transport. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  6. 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)

  7. 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)

  8. 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

  9. 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)

  10. El codigo digital. Del estatuto de la arquitectura contemporanea

    National Research Council Canada - National Science Library

    Trachana, Angelique

    2013-01-01

    En este trabajo se pretende estudiar las relaciones e influencias que se establecen entre la concepcion de la arquitectura contemporanea y las tecnologias de la informacion y la comunicacion senalando...

  11. Use of gadolinium burnable absorbers in VVER Type Reactors. Validation of WIMS-D/4 code; Empleo del gadolinio como absorbente quemable en los reactores nucleares VVER. Validacion del codigo WIMS-D/4

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez Cardona, Caridad M.; Guerra Valdes, Ramiro; Lopez Aldama, Daniel [Centro de Tecnologia Nuclear, La Habana (Cuba)

    1996-07-01

    Burnable absorbers are not used in current operating WWERs, but in order to optimize the fuel cycle and enhance operational safety, one should also introduce gadolinium or a similar burnable absorber in these reactors. For this purpose adequate tools for properly calculating local effects in hexagonal geometries should be developed and validated. The present gives main results in validating the WIMS-D/4 lattice code for Gd burnable absorber bearing WWER lattices. To validate the code experimental and calculational benchmarks proposed in a IAEA Coordinated Research Program were solved. A code system for the optimization of the Gd axial distribution in a WWER reactor was developed and it also presented here. (author)

  12. INFLUENCIA DOS MODELOS DE TENSOES RESIDUAIS PRESCRITOS EM CODIGOS NORMATIVOS NO COMPORTAMENTO DE PERFIS I

    OpenAIRE

    Lemes, Igor José Mendes; Silva, Jessica Lorrany; Batelo, Everton A Pimentel; Silveira, Ricardo Azoubel da Mota

    2017-01-01

    Resumo. O resfriamento nao uniforme de perfis metalicos durante o processo de fabricação gera um estado de tensoes residuais na secao transversal. Codigos normativos descrevem a distribuicao dessas tensoes de formas diferentes. Este trabalho visa investigar numericamente a influencia desses modelos no comportamento de secoes transversais de aco I isoladas e mistas atraves das curvas: rigidez `a flexao-momento fletor, relacao momento-curvatura e curvas de interacao (in´ıcio de plastificacao e ...

  13. Historical aspects of the nuclear right development; Aspectos historicos en el desenvolviminento del derecho nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Puig, Diva E. [Universidad de la Republica, Montevideo (Uruguay). Facultad de Derecho

    1999-04-01

    This paper analyses the historical aspects of the nuclear right development. It makes the evolution of the fundamental principles of nuclear right, in special, the civil responsibility for nuclear damages. (author)

  14. Los inicios del programa nuclear colombiano 1955-1965. Diplomacia y ayuda internacional en la formación de una comunidad científica del Tercer Mundo durante la era del desarrollo

    Directory of Open Access Journals (Sweden)

    Juan Andrés León Gómez

    2009-09-01

    Full Text Available Este trabajo de grado elaborado entre 2002 y 2003 reconstruye los primeros años del programa nuclear colombiano. Está basado en fuentes primarias del extinto Instituto de Asuntos Nucleares y del Archivo General de la Nación, analizadas desde el punto de vista de los estudios sociales de la ciencia.

  15. Participation in benchmark MATIS-H of NEA/OCDE: uses CFD codes applied to nuclear safety. Study of the spacer grids in the fuel elements; Participacion en el Benchmark Matis-H de la NEA/OCDE: usos de codigos CFD aplicados a seguridad nuclear. Estudio de las rejillas espaciadoras en los elementos combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Pena-Monferrer, C.; Chiva, S.; Munoz-cobo, J. L.; Vela, E.

    2012-07-01

    This paper develops participation in benchmark MATIS-H, promoted by the NEA / OECD-KAERI, involving the study of turbulent flow in a rod beam with spacers in an experimental installation. Its aim is the analysis of hydraulic behavior of turbulent flow in the subchannels of the fuel elements, essential for the improvement of safety margins in normal and transient operations and to maximize the use of nuclear energy through an optimal design of grids.

  16. 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)

  17. La crisis nuclear de Corea del Norte: Sky News o Fox News

    OpenAIRE

    Pablo Rodríguez; Dimitrina Jivkova Semova

    2014-01-01

    En este artículo analizamos, desde la teoría del framing, la información ofre - cida por los dos canales de noticias 24 horas del grupo News Corporation, Sky News y Fox News, con relación a la crisis nuclear de Corea del Norte en el periodo 9 -23 de abril de 2013. Nos centramos en aspectos como la “foxificación”, la presencia de expertos militares en los bloques de noti - cias y los encuadres informativos. En el caso de Sky News, la información se ofrece desde el prisma de los sucesos a nivel...

  18. 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)

  19. LA CAUSAL DE PROLONGACIÓN DEL PROCESO ESTABLECIDA EN LA LEY N° 30076 Y SU INCIDENCIA EN EL PLAZO RAZONABLE DE LA MEDIDA DE PRISIÓN PREVENTIVA: SU CONSTITUCIONALIDAD. MÓDULO PENAL DE CAMANÁ, 2014

    OpenAIRE

    DE ROMAÑA VELARDE, HUGO

    2016-01-01

    LA CAUSAL DE PROLONGACIÓN DEL PROCESO ESTABLECIDA EN LA LEY N° 30076 INTRODUCCION AL CODIGO PROCESAL PENAL DE 2004 MEDIDAS DE COERCION PROCESAL MODELOS DE COERCION PROCESAL CARACTERISTICAS DE LAS MEDIDAS DE COERCION PROCESAL LA PRISION PREVENTIVA PRESUPUESTOS DE LA PRISION PREVENTIVA QUE EL IMPUTADO, EN RAZÓN A SUS ANTECEDENTES Y OTRAS CIRCUNSTANCIAS DEL CASO PARTICULAR, PERMITA COREGIR RAZONABLEMENTE QUE TRATARÁ DE OBSTACULIZAR LA AVERIGUACION DE LA VERDAD (PELIGRO DE OBSTACULIZACION)...

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

    Directory of Open Access Journals (Sweden)

    Teresa Dupla Marin

    2013-05-01

    Full Text Available Recension: Carmen López‐Rendo Rodríguez, Efectos personales del divorcio respecto de los hijos, De Roma al Codigo civil español, RIDROM (online 9, 2012, Pág. 249–270Review: 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

  1. 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)

  2. 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)

  3. 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)

  4. 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.

  5. 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.

  6. 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)

  7. 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)

  8. La política nuclear espanyola: el caos del reactor nuclear Argos

    OpenAIRE

    Barca i Salom, Francesc Xavier

    2000-01-01

    L’11 de juny de 1962 s’inaugurava a l’Escola Tècnica Superior d’Enginyeria Industrial de Barcelona un reactor nuclear experimental, que era batejat amb el nom mític d’Argos. Tota la premsa barcelonina se’n feu ressò i el presentava com el primer reactor construït íntegrament a Espanya per la Junta d’Energia Nuclear. La idea de dotar l’Escola d’un reactor nuclear havia nascut, però, set anys abans, precisament en el mateix moment de la creació de la Càtedra Ferran Tallada d’enginyeria...

  9. 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)

  10. Advantage of nuclear knowledge for the new technologies; Aprovechamiento del conocimiento nuclear a las nuevas tecnologias

    Energy Technology Data Exchange (ETDEWEB)

    Legaz, R.

    2002-07-01

    Gathered experiences by several companies related with the nuclear sector, have let us to face up with reliability and optimism, the challenge to undertake other energy experiences with new technologies. As a result of this combined strategy, we have succeeded to keep up the existence and companies development that compete and stand out from a more divers and globalized energetic world. (Author)

  11. La crisis nuclear de Corea del Norte: Sky News o Fox News

    Directory of Open Access Journals (Sweden)

    Pablo Rodríguez

    2014-01-01

    Full Text Available En este artículo analizamos, desde la teoría del framing, la información ofre - cida por los dos canales de noticias 24 horas del grupo News Corporation, Sky News y Fox News, con relación a la crisis nuclear de Corea del Norte en el periodo 9 -23 de abril de 2013. Nos centramos en aspectos como la “foxificación”, la presencia de expertos militares en los bloques de noti - cias y los encuadres informativos. En el caso de Sky News, la información se ofrece desde el prisma de los sucesos a nivel nacional debido al tiempo dedicado a la polémica con el documental del programa “Panorama” de la BBC. El tratamiento de la crisis nuclear en Fox News se traduce en constantes críticas a las políticas militares llevadas a cabo por Corea, la exalta - ción patriótica de los Estados Unidos poniendo el acento sobre el sistema defensivo y todo ello rodeado de una crítica feroz a la Administración Oba - ma por no promover una intervención militar en el conflicto.

  12. Nuclear fission, the energy of the future; La fision nuclear como energia del futuro

    Energy Technology Data Exchange (ETDEWEB)

    Martinez-Val, J. M.; Fernandez, J. A.; Leon, P. T.

    2002-07-01

    The design of new-generation nuclear power stations incorporates approaches and control systems which significantly reduce risk and waste generation, while enhancing an installation's performance. This article reviews current programs involving the world's advanced reactors,and other future systems such as rapid reproduction reactors, or those operating in sub-critical conditions as energy amplifier. (Author) 12 refs.

  13. 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)

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

    Directory of Open Access Journals (Sweden)

    Karla Batista García-Ramó

    2012-01-01

    Full Text Available Los ganglios basales constituyen una compleja red de núcleos subcorticales implicados en el control motor,en la integración sensorimotora y en los procesos cognitivos. Su funcionamiento e interacción con el resto de las estructurascerebrales permanecen como una gran polémica. Este trabajo tuvo como objetivo modelar la interacción del circuito formado por los ganglios basales, el tálamo y la corteza para la selección de un programa motor, sobre la base del patrón de conectividad funcional obtenido por imágenes de resonancia magnética nuclear funcional. La determinación de los pesos de las conexiones entre las poblaciones neuronales a partir de imágenes de resonancia magnética nuclear funcional, contribuyó a una formulación más realista del modelo; y consecuentemente, a la obtención de resultados comparables con datos experimentales y clínicos, lo que permitió describir la participación de los ganglios basales en la selección de una acción en estado normal y en la enfermedad de Parkinson. La simulación posibilitó demostrar que ante una pérdida de dopamina superior al 40 %, el circuito ganglio basal-tálamo-cortical no es capaz de seleccionar entre dos programas motores y además, reveló la capacidad de adaptación del sistema para compensar el trastorno funcional del circuito motor en la enfermedad de Parkinson de modo coincidente con estudios clínicos y experimentales.

  15. 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.

  16. 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)

  17. Evaluation of the thermal-mechanical performance of fuel rods of a BWR during a power ramp using the FUELSIM code; Evaluacion del desempeno termomecanico de barras de combustible de un reactor BWR durante una rampa de potencia utilizando el codigo FUELSIM

    Energy Technology Data Exchange (ETDEWEB)

    Pantoja C, R.

    2010-07-01

    To avoid the risk to environment due to release of radioactive material, because of occurrence of an accident, it is the priority of the design and performance of the diverse systems of safety of a commercial nuclear power plant. The safety of nuclear power plants requires, therefore, monitoring those parameters having some direct or indirect effect on safety. The thermal limits are values set for those parameters considered having most impact on the safe operation of a nuclear power reactor. Some thermal limits monitoring requires the thermal-mechanical analysis of the rods containing the nuclear fuel. The fuel rod thermal-mechanical behavior under irradiation is a complex process in which there exists a great deal of interrelated physical and chemical phenomena, so that the fuel rod performance analysis in the core of a nuclear power reactor is generally accomplished by using computer codes, which integrate several of the phenomena that are expected to occur during the lifetime of the fuel rod in the core. The main application of the thermal-mechanical analysis codes is the prediction of occurrence of conditions and/or phenomena that could lead to the deterioration or even mechanical failure of the fuel rod cladding, as, for example, the pellet-cladding interaction. In the operation of a nuclear power reactor, fuel preconditioning operations refer to the operational procedures employed to reduce the fuel rod failure probability due to fuel-cladding interaction, specially during reactor startup. Preconditioning simulations are therefore necessary to determine in advance limit values for the power that can be generated in a fuel rod, and thus avoiding any rod damage. In this work, a first analysis of the thermal-mechanical performance of typical fuel rods used in nuclear reactors of the type BWR 5/6, as those two nuclear reactors in Laguna Verde, Veracruz, is performed. This study includes two types of fuel rods: one from a fuel assembly design with an array 8 x 8

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

  19. Simulation of a transient with loss of primary coolant due to a small rupture in Angra 2 nuclear power plant with RELAP5/MOD3.2.2G code; Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na usina de Angra 2 com o codigo RELAP5/MOD3.2.2G

    Energy Technology Data Exchange (ETDEWEB)

    Sabundjian, Gaiane; Andrade, Delvonei Alves de [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    2002-07-01

    This paper presents a nodalization for Angra 2 Nuclear Power Plant, as well as the results obtained for a Small Break Loss of Coolant Accident (SBLOCA), simulated with RELAP5/MOD3.2G code. This accident consists in a small break (380 m{sup 2}) in the line of the Emergency Core Coolant System (ECCS) in loop 20 of Angra 2. Results are not as expected, however they are satisfactory regarding the nodalization used. (author)

  20. Codigo civil de 1852: lo nacional y lo importado

    Directory of Open Access Journals (Sweden)

    César Luna Victoria León

    1988-12-01

    Full Text Available Contra lo que sugiere el título, no se trata de investigar las "fuentes" del Código Civil de 1852 ni de determinar el origen de las diversas instituciones jurídicas que recogió. Algo de esto se desarrolla, pero no será lo más relevante. La intención es otra. He querido ubicarme en el proceso de formación del Código para conocer con qué grado de eficacia el codificador logra incorporar o adaptar las ideas liberales prevalecientes en las tendencias codificadoras del siglo XIX (lo importado para establecer normas que regulen situaciones nacionales (lo nacional.

  1. Parametric study of different perturbations applied to the reactor of the NPP Ringhals-1with the coupled codes RELAP5/PARCSv2.7; Estudio parametrico de diferentes perturbaciones aplicadas al reactor de la Central Nuclear de Ringhals 1 con los codigos acoplados RELAP5/PARCSv2.7

    Energy Technology Data Exchange (ETDEWEB)

    Abarca, A.; Barrachina, T.; Miro, R.; Ginestar, D.; Verdu, G.

    2011-07-01

    It has been implemented in the attached code a new method of inducing instabilities in NPP with BWR reactor, through disturbances in the moderator density based on the shape and amplitude of the power modes. This method has been tested and verified with the simulations presented here. The results of the simulations under the conditions of the Record 9' of Ringhals-1 nuclear power plant with the coupled codes show that the type of stability depends on the perturbed mode and amplitudes of these disturbances, that is, the stability of the reactor not only depends on the conditions thermohydraulics previous to the swing, but also the disturbance that starts the swing.

  2. 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)

  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. 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)

  5. 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.

  6. 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

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

    OpenAIRE

    2012-01-01

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

  8. 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

  9. 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

  10. 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)

  11. EFECTO IN VITRO DE LA UNCARIA TOMENTOSA, DEL MTA Y DEL HIDROXIDO DE CALCIO EN LA VIABILIDAD CELULAR, MORFOLOGIA NUCLEAR Y INTEGRIDAD DEL ADN EN PULPA DENTAL DE PIEZAS DENTARIAS EXTRAIDAS, CLINICA ODONTOLOGICA PARTICULAR. AREQUIPA, 2011

    OpenAIRE

    LÓPEZ HUAMÁN, GIOVANNI

    2013-01-01

    UNCARIA TOMENTOSA ANTECEDENTES HISTÓRICOS CLASIFICACIÓN BOTÁNICA COMPOSICIÓN QUÍMICA PROPIEDADES FARMACOLÓGICAS TOXICIDAD Y CONTRAINDICACIONES EFECTOS MTA HIDRÓXIDO DE CALCIO COMPLEJO DENTINO PULPAR RECUBRIMIENTO PULPAR DIRECTO VIABILIDAD CELULAR MORFOLOGÍA NUCLEAR ESTRUCTURA DEL ADN

  12. EFECTO IN VITRO DE LA UNCARIA TOMENTOSA, DEL MTA Y DEL HIDROXIDO DE CALCIO EN LA VIABILIDAD CELULAR, MORFOLOGIA NUCLEAR Y INTEGRIDAD DEL ADN EN PULPA DENTAL DE PIEZAS DENTARIAS EXTRAIDAS, CLINICA ODONTOLOGICA PARTICULAR. AREQUIPA, 2011

    OpenAIRE

    LÓPEZ HUAMÁN, GIOVANNI

    2013-01-01

    UNCARIA TOMENTOSA ANTECEDENTES HISTÓRICOS CLASIFICACIÓN BOTÁNICA COMPOSICIÓN QUÍMICA PROPIEDADES FARMACOLÓGICAS TOXICIDAD Y CONTRAINDICACIONES EFECTOS MTA HIDRÓXIDO DE CALCIO COMPLEJO DENTINO PULPAR RECUBRIMIENTO PULPAR DIRECTO VIABILIDAD CELULAR MORFOLOGÍA NUCLEAR ESTRUCTURA DEL ADN

  13. VARIABILIDAD DEL GEN NUCLEAR G3PDH EN JATROPHA CURCAS L.

    Directory of Open Access Journals (Sweden)

    Sonia Castro Guzmán

    2015-11-01

    Full Text Available Jatrophacurcas L.es una especie nativa de América tropical; en nuestro país se ha venido utilizando principalmente como medicinal y alimenticia desde la época prehispánica. Actualmente el aceite extraído de sus semillas ha adquirido importancia internacional ya que puede ser transformado a biodiesel. El conocimiento que existe sobre la variabilidad genética de la especie es escaso. Un gen utilizado con éxito para el estudio de patrones de variación y origen de la yuca (ManihotesculentaL. y del caco (Theobromacacao L. es el gen nuclearG3pdh(Gliceraldehído3 fosfato deshidrogenasa involucrado en la fotosíntesis. Con base en ello, en este trabajo se exploró la variabilidad del gen G3pdh en individuos deJ. curcasprovenientes de 15 poblaciones de los estados de Veracruz, Campeche, Yucatán y Quintana Roo. Para obtener el gen G3pdh completo de alrededor de 1000 pares de bases, se amplificó utilizando losprimersdiseñados porStrandet al. (1997 y los dosprimersinternos reverse diseñados porOlsenySchaal(1999 para obtener segmentos más cortos, de 600 y 800 pares de bases aproximadamente. Por primera vez se amplificaron aproximadamente 500pby los resultados demuestran que el gen G3pdh es útil para analizar la variabilidad deJ. curcas, y con un importante potencial para evaluar la distribución y evolución de sus poblaciones en México, conocer las relaciones ancestro descendiente a nivel poblacional y explicar las causas de la distribución de los distintoshaplotipos.

  14. 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)

  15. 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)

  16. 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.

  17. 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)

  18. Nuclear energy in the operation of the spanish electric system; La energia nuclear en la operacion del sistema electrico espanol

    Energy Technology Data Exchange (ETDEWEB)

    Atienza, L.

    2008-07-01

    Nuclear energy plays a basic role in electricity production in Spain. Its high availability rate, the predictability of its fuel recharges, its high operational reliability, its geographical location, the stability of its costs, with its fuel having low weight in the cost structure, the security of supply that the possibility of storing its fuel on-site in the power plant gives and the absence of CO{sub 2} emissions are some of the advantages nuclear energy presents. Its stiffness for demand variations, its sudden disconnections, which are infrequent but with high impact on System Operation, the social perception and nuclear waste management must also be weighted up. (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. Unconstitucionality of the articles 7, [section] 1 and 8 of criminal code for breach of the principle of ne bis in idem/Da insconstitucionalidade dos artigos 7, [section] 1 e 8 do codigo penal por violacao ao principio ne bis in idem

    National Research Council Canada - National Science Library

    de Oliveira, Marcus Vinicius Xavier

    2012-01-01

    ...] 1 e 8 do Codigo Penal brasileiro face ao principio ne bis in idem, cuja positivacao no ordenamento juridico brasileiro decorreu da incorporacao do Pacto Internacional de Direitos Civis e Politicos/66...

  1. 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)

  2. R&D in Ciemat Nuclear Fission Department; I+D en el departamento de Fision Nuclear del Ciemat

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, J. L.; Diaz Arocas, P.; Gomez Briceno, D.; Gonzalez de la Huebra Gordo, A.; Gonzalez Romero, E.; Herranz Puebla, L. E.; Sola Farre, R. [Ciemat. Madrid (Spain)

    2000-07-01

    The technologically developed countries count on nuclear fission as a durable energy resource to produce electricity, facing the future by establishing research programmes to enhace the safety and extend the lifetime of the current power plants and to achieve the adequate management of radioactive waste. At the same time, the progress in the development of a new generation of reactors based in innovative safety concepts. The Nuclear fission Department has the ultimate objetive of providing technical support to the Spanish nuclear reactors through applied research and development focused on improving the safety and performance of the operating power plants, and cooperating in the activities related to radioactive waste. In this context, the Departament has been organised in four R&D project covering the areas of Safety, Materials, Radioactive. (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. Regularity of the wear control of radioactive sources from the nuclear measurers; Regularidad del control del desgaste de fuentes radioactivas de los medidores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira L, M. [Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN-SP, Av. Prof. Lineu Prestes 2242 - Cidade Universitaria -CEP(ZC) 05508-900, tel: (005511) 3816-9215, Sao Paulo, (Brazil)]. e-mail: mflima@ipen.br

    2006-07-01

    The control of radioactive sources in Brazil is regulated by the CNEN (National Comissao of Nuclear Energy). The Laboratory of Descontaminacao of the IPEN (Institute of Energy Y Nuclear Investigations) it offers to the companies that work with nuclear measurers, essays for control of the source wear according to the ISO 9978/1992 through the smear tests Y of leakage. The analyses are taken in alpha Y beta detectors of low bottom radiation with annual detection limits around 1 Bq. Certificates of the accepted analyses by the CNEN for sources that already passed its time of validity assured by the makers, but its continue operational are emitted. The smear test is repeated the whole year, while the leakage test repeats to every two years. A balance of the last two years of the activities of the laboratory shows the regularity of the clients Y the growth of companies specialized in radioprotection with official of radioprotection, credited by the regulatory authority that its act as intermediaries in the process, contacting the clients, gathering the samples next to the proprietors of sources Y hiring our services. Overalls, proves that the inspection activities by part of the regulatory authority are fulfil. In 2004, 192 sources were analyzed by the smear method Y 86 sources by leakage. In 2005, 232 sources were analyzed by the smear method Y 60 sources by leakage. All the leakage tests was made in sources of Americium of oneself Y only client that brings the sources so that they dismantle them to him in the Sources production laboratory of the IPEN. By the quantity Y age of the sources that were analyzed in those two years, it is proven that the number of sources without use conditions (total activity measured by the two added methods smaller than 180Bq) it doesn't arrive to 2%. (Author)

  5. 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)

  6. 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

  7. Spanish nuclear industry experience in the evaluation of suppliers; Experiencias del sector nuclear espanol en la evaluacion de suministradores

    Energy Technology Data Exchange (ETDEWEB)

    Ramos Pellejero, J. L.; Martinez, J. A.; Gomez, R.; Pablos, C. de; Herrero, J.

    2012-07-01

    The paper aims to present the experiences identified by the Evaluation Panel Suppliers in fulfilling its role of supplier evaluation of goods and services {sup s}afety related{sup .} It belongs to UNESA and its main objective the evaluation of the quality system of the supplier against the basic rules applicable. With it you get two main benefits: - standardize evaluation criteria share experiences between suppliers and better management of own resources. - market access to all Spanish nuclear fleet by a single evaluation. From the experience gained, it can be concluded that there is a population of highly technically qualified suppliers to meet equipment requirements.

  8. 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)

  9. IMPLEMENTACIÓN DEL MÉTODO DEL GRADIENTE ANALÍTICO DE LA ENERGÍA EN LA TEORÍA DEL ORBITAL MOLECULAR NUCLEAR Y ELECTRÓNICO.

    Directory of Open Access Journals (Sweden)

    Andrés Reyes

    2009-06-01

    Full Text Available Con el fin optimizar las geometrías promedio de sistemas moleculares utilizando la teoría del orbital molecular nuclear y electrónico (OMNE, se dedujo la expresión para el cálculo del gradiente analítico de la energía a nivel de teoría Hartree-Fock, para cualquier tipo de especie cuántica. La implementación computacional se realizó dentro del paquete APMO (Any-Particle Molecular Orbital y con el fin de comprobar la correcta implementación del método se calcularon las moléculas modelo H2, HF y H2O, por medio de métodos numéricos y analíticos.  El uso de derivadas analíticas dentro del formalismo OMNE permitirá  el cálculo más eficiente de la estructura núcleo-electrónica de sistemas moleculares con el paquete APMO. 

  10. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

  12. Comparison of the results obtained in the design of shallow foundations when applying the eurocode 7 and the Spanish standards; Comparacion del dimensionamiento de cimentaciones superficiales aplicando el Eurocodigo 7 y las normativas espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Prieto Rodriguez, A.; Varela Nieto, J. M.; Magdaleno Mas, F.; Diaz Balteiro, L.; Saiz de Omenaca Gonzalez, J. A.; Saiz de Omena Gonzalez, J.; Lazaro Benito, F.; Macias Palomo, A.

    2008-07-01

    It has been done the comparison of the results obtained in the design of shallow foundations when the Eurocode 7 and different geotechnical Spanish Standards are applied (R.O.M. 05-94). Guia de cimentaciones para Obras de Carretera y Documento Basico SE-C del Codigo Tecnico de la Edificacion). Several designs have been done with different types of soils, characterized by their strength parameters, and with different shapes of foundations. the comparison of the results makes it possible to quantify the differences that exist between the European and the Spanish Standards. (Author) 8 refs.

  13. Cine y educación. El uso didáctico del cine en la Facultad de Ciencias de la Educación de la Universidad de Málaga

    OpenAIRE

    Rojano Vera, Raúl

    2015-01-01

    Vivimos en una iconosfera. Un pequeño grupo de profesionales de la imagen elaboran para toda la población innumerables documentos que se devoran sin disponer del necesario dominio de los códigos lingüísticos que le son propios. De ahí que seamos fácilmente manipulados. De ahí también que tengamos escasos criterios de discernimiento sobre lo que sobre lo que es de calidad y lo que es bazofia cinematográfica. Y, por supuesto, la incapacidad general para elaborar documentos en los codigos lingüí...

  14. 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.

  15. 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)

  16. 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)

  17. 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.

  18. 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...

  19. 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)

  20. 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

  1. 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)

  2. Analizan partículas calientes del accidente nuclear de Palomares

    OpenAIRE

    2012-01-01

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

  3. Identificación de nuevos genes diana del receptor nuclear FXR

    OpenAIRE

    Pedraz Cuesta, Elena

    2012-01-01

    [spa] Las sales biliares son cruciales para la solubilización y absorción en el intestino de las grasas y las vitaminas liposolubles procedentes de la dieta. Estas sales biliares son sintetizadas a partir de colesterol en los hepatocitos, lo que representa la mayor vía de eliminación de colesterol del cuerpo. Además de este importante papel fisiológico, las sales biliares también actúan como moléculas de señalización endocrina que afectan a múltiples órganos. Para ejercer estos efectos, los á...

  4. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Cerezo, L. M.

    2001-07-01

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

  6. 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).

  7. 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)

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

    OpenAIRE

    2013-01-01

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

  9. V meeting on results of Research Plan of Nuclear Safety Conseil; V Jornadas sobre Resultados del Plan de Investigacion del CSN

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This book presents the papers presented at the meeting on results of Research Plan of CSN (Nuclear Safety Conseil). The main sessions were : 1.- Nuclear Safety. 2.- Radiation protection and Radioactive wastes. 3.- Riskpercom.

  10. 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)

  11. Nuclear Astrophysics

    Science.gov (United States)

    Drago, Alessandro

    2005-04-01

    The activity of the Italian nuclear physicists community in the field of Nuclear Astrophysics is reported. The researches here described have been performed within the project "Fisica teorica del nucleo e dei sistemi a multi corpi", supported by the Ministero dell'Istruzione, dell'Università e della Ricerca.

  12. 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

  13. Safety of spanish nuclear park. Analysis of the fundamental principles of security of nuclear facilities and activities; Seguridad del parque nuclear espanol. Analisis de los principios fundamentales de ls seguridad de las instalaciones y actividades nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    The aim of this study is to analyze the fundamental principles underlying the safety of nuclear installations and activities, which defined the International Atomic Energy Agency (IAEA). These principles determine the roles of government and responsibilities of the holders of power, explain how to achieve security and nuclear energy to justify the society, present and future and the environment from the risks of ionizing radiation, both and explain natural and man must be managed as waste that occur or have occurred in the past. (Author)

  14. Efectos personales del divorcio respecto de los hijos. De Roma al Codigo civil español

    OpenAIRE

    López-Rendo Rodríguez, Carmen

    2012-01-01

    Este trabajo examina la regulación de la guarda y custodia de los hijos en casos de divorcio desde Roma hasta la actualidad. ¿Quién decide sobre ella? ¿Existían criterios para dicha atribución? ¿Cuáles eran los criterios utilizados? Se analiza la materia en derecho romano, en donde se observa que hasta los emperadores Diocleciano y Maximiano, la regla general atribuía la patria potestad y la guarda y custodia al padre, salvo que existieran justas causas que hicieran oportuno y necesario atrib...

  15. 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)

  16. Epidemiological study of the effects of nuclear and fuel cycle facilities on the health of the neighbouring populations; Estudio epidemiologico del efecto de las instalaciones nucleares y del ciclo sobre la salud de las poblaciones vecinas

    Energy Technology Data Exchange (ETDEWEB)

    Bernal, A.; Lentijo, J. C.; Lopez-Abente, G.; Pollan, M.; Ramos, M. R.; Rodriguez, M.; Tello, O.; Urbano, I.

    2010-07-01

    The Carlos III Health Institute and the Nuclear Safety Council, signed an agreement for the performance of an epidemiological study to investigate the possible effects of exposure to ionising radiations on the health of populations living in the vicinity of nuclear and radioactive facilities involved in the nuclear fuel cycle. (Author)

  17. Participation of CIEMAT in 26th annual meeting of the Spanish Nuclear Safety; Participacion del CIEMAT en la 26 reunion anual de la Sociedad Nuclear Espanola

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The book assembles the paper of researches of CIEMAT during the 26th annual meeting of Spanish Nuclear society. The paper were presented during the following sessions: 1. Maintenance and in-service inspection 2. Radioactive wastes 3. Environment 4. R and D management 5. Nuclear Safety 6. Lifetime.

  18. Participation of CIEMAT in 27th annual meeting of the Spanish Nuclear Safety; Participacion del CIEMAT en la 27 Reunion Anual de la Sociedad Nuclear Espanola

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The book assembles the paper of researches of CIEMAT during the 27th annual meeting of Spanish Nuclear society. The paper were presented during the following sessions: 1. Maintenance and in-service inspection 2. Radioactive wastes. 3. Environment 4. R and D management 5. Nuclear Safety. 6. Lifetime. (Author)

  19. 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.

  20. Nabor Carrillo and the configuration of the Mexican nuclear project 1946-1963; Nabor Carrillo y la configuracion del proyecto nuclear mexicano 1946-1963

    Energy Technology Data Exchange (ETDEWEB)

    Esqueda B, E

    2007-07-01

    This thesis is expressed in the following proposals: 1. That the Doctor Nabor Carrillo Flores was the responsible one of promoting in the UNAM a program in nuclear physics, for that which established a work team under the direction of the Doctor Fernando Alba Andrade. 2. That the Doctor Nabor Carrillo Flores assumed, with the help of other scientists, to the investigation and the technical formation in experimental nuclear physics, like one first stage of the nuclear program of which was promoter. 3. That the Doctor Nabor Carrillo Flores, together with other scientists, intellectuals and politicians believed firmly in the possibilities of impelling the industry, the agriculture and the medicine through the handling of the nuclear energy. In that same sense the objectives are: 1. To rake the structural and of the situation, ideological and material, internal elements external v. general and particular, national and foreigners that drove to the Doctor Nabor Carrillo Flores to promote the nuclear training. 2. To observe the clarity of vision expressed by the Doctor Nabor Carrillo Flores regarding developing the science and the technical training simultaneously with the purpose of preparing nuclear specialists. 3. To understand the way in that the areas of application of the nuclear energy and the impact of the nuclear physics were determined in other disciplines. (Author)

  1. 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)

  2. Nuclear security towards the adequate answers to the new challenge of nuclear and radiological terrorism; Seguridad nuclear hacia las respuestas adecuadas al nuevo reto del terrorismo nuclear y radiologico

    Energy Technology Data Exchange (ETDEWEB)

    Puig, D.E. [Pza. Cagancha 1387 / 404, Montevideo (Uruguay)]. e-mail: d.puig@adinet.com.uy

    2006-07-01

    The globalization phenomenon and the process of regional integration have generated new and defiant characteristics in the criminal activation, the one that has acquired growing trans national dimension. After September 11, 2001 it should to have bigger international initiative to reinforce the safety of materials and facilities in the entire world and to apply the international recommendations for to assure that all the nuclear materials of not used bombs are registered and secure of sabotage. Thousands of radioactive sources exist in the world. Possibility that the terrorists use radioactive sources as attack instruments since its are more easily available and its are more easy too to obtain in comparison with the uranium or plutonium classified for weapons. Dirty bomb. Effects of the Radiations. The Goiania accident. 'Orphans' sources Illicit traffic of radioactive material. Security. Measures of Physical Protection. Security of the radioactive sources. Role of the IAEA and other international organisms and regional CAN-MERCOSUR. Nuclear security and Legal frame. International and national instruments against the nuclear and radiological terrorism. Study from a proposal to Pan-American level to make in front of the problem. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Cicero, R.; Corchon, F.

    2011-07-01

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

  4. 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)

  5. The role of the Nuclear Safety Council in relation to the Fukushima accident; El papel del Consejo de Seguridad Nuclear en relacion con el accidente de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Casado, B.

    2011-07-01

    On March 11th last, in the wake of the earthquake and subsequent tsunami that devastated the East coast of Japan, damage was sustained by the reactors of the Fukushima nuclear power plant. During this process, the CSN, as the organisation solely responsible for nuclear safety and radiological protection in Spain, has played a key role in managing communications, with a view to providing society with reliable and accurate information on the accident. (Author)

  6. Optimization of the fuel use in the nuclear power plant of Laguna Verde; Optimizacion del uso de combustible en la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz S, J. J.; Castillo M, J. A.; Perusquia del Cueto, R., E-mail: juanjose.ortiz@inin.gob.m [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-07-01

    The fuel management in a nuclear power reactor for the electricity production has a main objective the efficient use of the nuclear fuel during the reactor operation, without to neglect the related with the security and to achieve the economic profitability in turn. The efficient use of the fuel implies to extract the maximum electric power of the uranium that the reactor security is guaranteed and provide economic benefits for the owner company of the nuclear reactor. In Mexico, the Federal Commission of Electricity have two boiling water reactors in the nuclear power plant of Laguna Verde (Veracruz, Mexico). In this nuclear power plant the operation of a nuclear reactor is carried out by means of operation cycles that have 18 months of duration at the moment. At the end of each cycle, the reactor stops to carry out the fuel recharge phase. The fuel assemblies can be removed or relocated in each cycle. Approximately a fourth part of the fuel assemblies are replaced by fresh fuels. This means that each fuel assemble remains, on the average, 4 cycles in the reactor or the order of six years. Therefore, the fuel management has for object to design the configuration of fuel load and form of reactor operation, so that the safety aspects are satisfied and that the expectations of electric generation are reached for each operation cycle of the useful life of the reactor. (Author)

  7. Closing the sky. The total dismantling of the Jose Cabrera nuclear power plant demonstrates maturity in the nuclear sector; Cerrando el Cielo. El desmantelamiento total de la central nuclear Jose Cabrera demustra la madurez del sector nuclear espanol

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez, A.

    2015-07-01

    This article aims to put the situation of the decommissioning of nuclear power plants in the world into perspective as an already consolidated activity and with an important future of industrial activity. The decommissioning project that Enresa is currently performing in the old Jose Cabrera plant is being explained in detail, by providing data of the newest and most relevant technical aspects as well as the lessons learned to be reusable in other decommissioning projects. The previous background, the project planning, the activities performed and those still to be done as well as their timing are being explained in detail. (Author)

  8. 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)

  9. La filosofia del entendimiento, de Andres Bello, factum revolucionario

    National Research Council Canada - National Science Library

    Cuartas R., Juan Manuel

    2009-01-01

    ...; organizo en Chile la "instruccion publica", fue Rector de la nueva Universidad de Chile, redacto el Codigo civil chileno, oriento la politica exterior, y el Tratado de derecho internacional, llevo...

  10. 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)

  11. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Martin Aparicio, J.; Atanasio, J.

    2011-07-01

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

  13. Sensitivity analysis codes fire simulation; Analisis de sensibilidad en codigos de simulacion contra incendios

    Energy Technology Data Exchange (ETDEWEB)

    Cordero Garcia, S.; Peco Espinosa, J.

    2010-07-01

    The fire simulation and analytical validation procedures have been gaining importance in the context of safety analysis and probabilistic deterministic Fire at Nuclear Power Plants. Meanwhile, the fire simulation codes have been accepted as valuable tools for risk analysis in fire protection. To evaluate the quality and predictability of the codes used in fire protection, they are validated with different experiments. This work is performed to find the dependency of the FDS output parameters against a certain input.

  14. Ramona cold nuclear bank of the Siemens 9x9-IX fuel; Banco nuclear Ramona Cold del combustible Siemens 9x9-1X

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1994-01-15

    With the purpose of making the transitory analyses of the Laguna Verde Nuclear Power station when Siemens fuel of the type 9x9-IX is used, proposed for the cycle 2 of the Unit 2, the data bank in cold condition for the Ramona code has been generated. (Author)

  15. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Pelayo, F.; Mendizabal, R.

    2005-07-01

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

  17. "Gato encerrado" o "confidencialidad comercial": el problema del secreto en la venta de un reactor nuclear "Gato encerrado" or "confidencialidad comercial": a secret problem regards the sale of a nuclear reactor

    Directory of Open Access Journals (Sweden)

    Ana Spivak L' Hoste

    2006-12-01

    Full Text Available En este artículo se propone abordar uno de los aspectos medulares de la disputa pública que surge a partir de la venta de un reactor nuclear diseñado por una empresa argentina a Australia en el año 2000. Se trata del problema del secreto que atraviesa, para quienes están involucrados en la misma y desde dos perspectivas claramente diferentes, la operación comercial. A través del análisis de las categorías locales que hacen a la configuración del problema del secreto, gato encerrado y secreto comercial, se pretende explorar algunas de las dimensiones sociales, históricas y simbólicas que se articulan en las narrativas que dan vida a esta disputa. Asimismo, se pretende dar cuenta, por ese medio, de qué manera el proceso de construcción de significados es también un proceso de construcción de colectivos sociales (Hecht 1996. Finalmente, se concluirá con una breve reflexión sobre la relevancia analítica y conceptual de la etnografía en el campo de los estudios sociales de la ciencia y la tecnología y, más específicamente, en el ámbito de las disputas públicas que, como ésta, involucran el desarrollo, la producción y el conocimiento científico y tecnológico.This paper deals with one of the many aspects of a science and technology dispute regarding the sale of a nuclear reactor designed by an Argentinean company, INVAP, to Australia in 2000. The analysis is mainly centered on one of the most relevant axis of the conflict: the problem of the secret that passes through a commercial operation. The objective of the article is, on the one hand, to explore some of the social, historical and symbolic dimensions related to the narratives that shaped the dispute through an analysis of the local categories that articulate the secret's problem ("gato encerrado" and "secreto comercial" and to show through this analysis how the process of constructing meanings is also a process of constructing social collectives (Hecht 1996. On the

  18. Acotaciones a las églogas de Juan del Encina

    Directory of Open Access Journals (Sweden)

    Ana Cecilia Prenz

    2002-12-01

    Full Text Available Desde un punta de vista semiológico, el objeto teórico del arte teatral reside en la individualización de su funcionamiento como fenómeno de significación y de comunicación. Ya en 1963 R. Barthes hablaba del teatro como "una especie de máquina cibernética" que emite mensajes simultáneamente y que, por lo tanto, "constituye un objeto semiológico privilegiado". Resulta clara, pues, que, cuando hablamos de teatro, nos estamos refiriendo a un objeto sincrético y multidimensional en el que participan un conjunto de lenguajes heterogéneos, que se modifican cada vez, y cuyo funcionamiento no puede ser explicado sabre la base de un código único, sino en relacion con la pluralidad de codigos que lo conforman. Si bien, el propósito de nuestro trabajo no es estrictamente semiológico, no podemos perder de vista los aspectos arriba mencionados.

  19. Nuclear Structure

    Science.gov (United States)

    Gargano, Angela

    2003-04-01

    An account of recent studies in the field of theoretical nuclear structure is reported. These studies concern essentially research activities performed under the Italian project "Fisica Teorica del Nucleo e dei Sistemi a Molti Corpi". Special attention is addressed to results obtained during the last two years as regards the development of new many-body techniques as well as the interpretation of new experimental aspects of nuclear structure.

  20. Nuclear emergency planning in Spain. The PLABEN review project; Planificacion de emergencias radiologicas en Espana. Revision del Plan Basico de Eergencia Nuclear (PLABEN)

    Energy Technology Data Exchange (ETDEWEB)

    Lentijo Lentijo, J. C.; Vila Pena, M. [Consejo de Seguridad Nuclear. Madrid (Spain)

    2002-07-01

    The international rules and recommendations for nuclear emergency planning and the Spanish experience gained in the management of event with radiological risk have noticed that is necessary to review the planning radiological bases for emergencies in nuclear power plants and to define the planning radiological bases for radiological emergencies that could happen in radioactive facilities or in activities out of the regulatory framework. The paper focuses on CSN actions concerning the Plaben review project related to define the new radiological principles taking into account the current international recommendations for interventions, make a proposal about the organisation and operation of the provincial radiological action group and the national support level for radiological emergency response. (Author) 7 refs.

  1. Study of the neutronic activation of the stainless steel in a nuclear reactor; Estudios de la activacion neutronica del acero inoxidable en un reactor nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lazaro Roche, I.; Rodenas Diago, J.; Marques, J. G.

    2013-07-01

    During operation of a nuclear reactor, various components can be activated by neutron reactions. The activity thus generated produces a dose that is a potential risk to workers and environment. Was simulated using the MCNP and CINDER'90 such activation codes on a piece of steel and the values obtained compared with experimental measurements. The equivalence of both methods is verified to calculate neutron activation and evolution of the dose rate with the cooling time.

  2. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-10-15

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

  4. 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.

  5. Presencia del padre y calidad de la interaccion madre-hijo: un estudio comparativo en familias chilenas nucleares y monoparentales

    National Research Council Canada - National Science Library

    Santelices Alvarez, Maria Pia; Olhaberry, Marcia

    2013-01-01

    .... Considerando este antecedente, se realizo un analisis comparativo de la calidad de la interaccion madre-hijo en diadas pertenecientes a familias chilenas nucleares y monoparentales de bajos ingresos...

  6. 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)

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

    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

  8. 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)

  9. 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)

  10. 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)

  11. Environmental dose in the Nuclear Medicine Department of the National Institute of Cancer;Dosis ambiental en el Departamento de Medicina Nuclear del Instituto Nacional de Cancerologia

    Energy Technology Data Exchange (ETDEWEB)

    Torres U, C. L.; Avila A, O. L. [ININ, Carretera Mexico-Toluca s/n, Ocoyoacac 52750, Estado de Mexico (Mexico); Medina V, L. A.; Buenfil B, A. E.; Brandan S, M. E. [UNAM, Instituto de Fisica, Circuito Exterior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Trujillo Z, F. E. [Instituto Nacional de Cancerologia, Av. San Fernando No. 22, Col. Seccion XVI, 14080 Mexico D. F. (Mexico); Gamboa de Buen, I. [UNAM, Instituto de Ciencias Nucleares, Circuito Exterior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2009-07-01

    The dosimeters TLD-100 and TLD-900 were used to know the levels of environmental dose in areas of the Nuclear Medicine Department of the National Institute of Cancer. The dosimeters calibration was carried out in the Metrology Department of the National Institute of Nuclear Research. The radioisotopes used in the studied areas are {sup 131}I, {sup 18}F, {sup 67}Ga, {sup 99m}Tc, {sup 111}In, {sup 201}Tl and {sup 137}Cs with gamma energies between 93 and 662 KeV. Dosimeters were placed during five months in the diagnostic, injection, waiting and PET rooms as well as hot room, waste room, enclosed corridors to patient rooms treated with {sup 131}I and {sup 137}Cs and witness dosimeters to know the bottom. The values found vary between 0.3 and 70 major times that those of bottom. The maximum doses were measured in the waste room and in the enclosed corridor to the patient rooms with cervical uterine cancer treated with {sup 137}Cs. (Author)

  12. 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)

  13. 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)

  14. 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)

  15. Experimental study of the burned of nuclear fuel by the gamma spectroscopy method; Estudio experimental del quemado de combustible nuclear por el metodo de espectrometria gamma

    Energy Technology Data Exchange (ETDEWEB)

    Amador V, P.

    2009-07-01

    Accurate information on nuclear fuel burnup is of vital importance in reactor operation, fuel management and fuel-characteristics studies. Conventionally fuel management of the TRIGA III Reactor from the National Institute of Nuclear Research (ININ) is done through the thermal balance method (management) of the power generated during reactor operation, since it is known that with 1.24 grams of {sup 235}U is possible to generate a power or 1 MW per day during the reactor operation. On the other hand, it is possible to calculate the operation time in days during a power of 1 MW with the help of the data registered in logs. With the information just mentioned one can calculate the quantity of {sup 235}U consumed in the fuel during a complete period of irradiation. In order to compare and prove that the burnup values, calculated through the thermal balance method, are correct, the ININ implemented, for the first time, the gamma-ray spectroscopy method as an experimental technique to calculate the burnup of several fuel elements. Gamma-ray spectroscopy is a nondestructive method, so that the integrity of the fuel element is not affected which is of great importance. Since there is a direct relation between the activity of {sup 137}Cs contained in the fuel elements and a series of constants which are unique for the radioisotope and for the high resolution system, the problem just simplifies in measuring the {sup 137}Cs activities. Furthermore the {sup 137}Cs concentration equation was developed theoretically and I wrote a computer program (AMAVAL) in Fortran. The task of this program is to calculate the concentrations and the activity through the use of the equation just mentioned and the history of each fuel element. The purpose of this is to compare and validate the experimental activities with the theoretical ones for each fuel element. (Author)

  16. 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)

  17. Usos y abusos del sistema penal. Su uso como forma de emancipacion femenina: un estudio de caso del delito de trata de personas en Colombia

    National Research Council Canada - National Science Library

    Abadia, Gloria

    2012-01-01

    ... se encontraba descrito simplemente como una especie de proxenetismo, para luego ser modificada su ubicacion sistematica en el Codigo Penal dentro de los delitos que pretenden proteger la autonomia personal y la libertad individual...

  18. 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.

  19. 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.

  20. The spanish electric system operation. The contribution of nuclear generation; La operacion del sistema electrico espanol. Contribucion de la generacion nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Duvison, M. R.; Torre, M. de la

    2009-07-01

    Operation of an electric system encloses the collection of activities which extend from affective generation dispatch to issuing instruction for network manoeuvring along with international exchange scheduling. Based on the market mechanisms that apply to energy transactions, these tasks guarantee the security of supply end consumers, which is the final goal of the System Operators actions. In Spain this function is executed by Red Electrica de Espana (REE) since 1985, after being constituted as the first Transmission and System Operator (TSO) in the world. Additionally the variations to Law 54/1997 introduced by law 17/2007 also assign REE the function of sole transmission owner in the Spanish electric system. In order to achieve the aforementioned goal, nuclear energy plays in Spain a fundamental role in electric generation thanks to its high availability rate, the predictability of its fuel recharges, its high operational reliability, its geographical location, the stability of its costs and the security of supply given by the possibility of on-site fuel storage in the power plant. (Author)

  1. 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)

  2. 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)

  3. 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)

  4. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  6. 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)

  7. 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)

  8. 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

  9. Primera fase de la evaluación de cupones de corrosión en los cementerios de elementos combustibles (fisurados, fallados y tanque principal) en el reactor RP-10 del Centro Nuclear RACSO

    OpenAIRE

    Babiche, Iván; León, Constantino; Revilla, Angel

    2005-01-01

    Se presenta las actividades desarrolladas por el grupo de trabajo de corrosión relacionadas a la inmersión, monitoreo y remoción de dos racks de corrosión en su primera fase, después de un año de exposición en los cementerios de elementos combustibles fisurados, fallados y tanque principal del reactor nuclear RP-10. Para esto se evaluó la importancia de la química del agua, los sedimentos y otros contaminantes en el deterioro de los cupones de acero inoxidable 304 y de los aluminios AA1050 y ...

  10. 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

  11. Participation of CIEMAT in the 29 Annual meeting of the Spanish Nuclear Society. Zaragoza 1,2 y 3 October 2003; Participacion del CIEMAT en la 29 Reunion Anual de la Sociedad Nuclear Espanola

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    The book assembles the paper of researches of CIEMAT during the 29th annual meeting of Spanish Nuclear Society. The paper were presented during the following sessions : 1. Nuclear fuel. 2. R and D materials. 3.Operation and maintenance. Lifetime. 4.- R and D and T participation and transmutation.5. Environment. 6. Radioactive wastes and dismantling. 7. Nuclear safety. 8. Nuclear law.

  12. VARIACIÓN DE LA REGIÓN RIBOSÓMICA NUCLEAR EN CRATAEGUS L. DEL CENTRO Y SUR DE MÉXICO

    Directory of Open Access Journals (Sweden)

    Carlos Alberto N\\u00FA\\u00F1ez-Col\\u00EDn

    2011-01-01

    Full Text Available Este estudio fue realizado en la Universidad Autónoma Chapingo y concluido en octubre de 2008 y tuvo como objetivo determinar las relaciones genéticas entre especie s de Crataegus del centro y sur de México. La variación en las secuencias de la región ribosómica nuclear fue baja en todas las accesiones de germoplasma de Crataegus mexicanos, y el filograma sólo mostró separación de las especie s usadas como controles positivos, pero no mostró una clara separación de grupos de especie s. Si n embargo, todas las accesiones tuvie ron un mismo patrón de sustitución de nucleótidos y muy bajos valores en la distancia de composición de nucleótidos; por lo que las especie s mexicanas de Crataegus mostraron alta relación genética, pero falta evidencia para concluir que son variantes de una misma especie taxonómica. C nelsoni y C. stipulosa pueden ser una fuente de genes para C. mexicana porque ambas especie s, originarias de Chiapas, tie nen la más estrecha relación con esta especie , que es la que presenta las mejores características agronómicas.

  13. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-12-31

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

  15. 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)

  16. 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)

  17. 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)

  18. Quality control of the new Monte Carlo code Multi plan for Cyberknife planner; Control de calidad del nuevo codigo Monte Carlo de planificador multiplan para Cyberknife

    Energy Technology Data Exchange (ETDEWEB)

    Fayos Ferrer, F.; Antolin Sanmartin, E.; Simon de Blas, R.; Palazon Cano, I.; Bertomeu Padin, T.; Gutierrez Sarraga, J.; Rey Portoles, G.

    2011-07-01

    This paper is subjected to various tests including Monte Carlo dosimetric the code in the latest versions of Multi plan Accuracy planner. They compare their results and Ray-Tracing Algorithm (RT), present from the earliest versions, with the experimental results obtained by photographic dosimetry and ionization chamber measurements.

  19. 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.

  20. Iterative code for the reconstruction of the neutrons spectrum using the Bonner spheres; Codigo iterativo para la reconstruccion del espectro de neutrones usando las esferas Bonner

    Energy Technology Data Exchange (ETDEWEB)

    Reyes H, A.; Ortiz R, J. M.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Ingenieria Electrica, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico)

    2012-10-15

    The neutrons are the particles more difficult of detecting for their intrinsic nature. The absence of the neutrons charge makes that an interaction exists with the matter in a different way. The term radiation spectrometry can use to describe the measurement of the intensity of a radiation field with regard to the energy. The intensity distribution with relationship to the energy is commonly known as spectrum. A method to know the neutrons spectrum in the radiation fields to those that people are exposed is the use of the known system as spectrometry system of Bonner spheres, being the more used for the purposes of the radiological protection. The current interest in the electrons spectrometry has stimulated the development of several procedures to carry out the reconstruction of the spectra. During the last decades new codes have been developed such as BUNKIUT, Bums, Fruit, UMG, etc., however, these methods still present several inconveniences as the complexity in their use, the necessity of an expert user and a very near initial spectrum to the spectrum that is wanted to obtain. To solve the mentioned problems it was development the program NSDUAZ (Neutron Spectrometry and Dosimetry from Autonomous University of Zacatecas). The objective of the present work is to prove and to validate the code before mentioned making an analysis of likeness and differences and of advantages and disadvantages with relationship to the codes used at the present time. (Author)

  1. 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)

  2. 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)

  3. Desarrollo y validación de una nueva técnica de ensayo no destructivo basada en el potencial termoeléctrico para el conocimiento del envejecimiento de los aceros de vasija de reactores nucleares

    OpenAIRE

    Acosta Iborra, Beatriz

    2001-01-01

    La vasija de presión del reactor (RPV) en los reactores de agua ligera (LWR) es un componente clave para la operación segura de una central nuclear. La vasija de presión forma parte de la contención del reactor y su vida delimita, en gran medida, la vida de la planta. En los materiales de la PRV el efecto más importante de deterioro por la radiación es la disminución de la ductilidad de los aspectos que la forma. Los métodos tradicionales para determinar el comportamiento mecánico de la RPV s...

  4. Una mirada desde la retórica aristotélica y la nueva retórica sobre el debate por la venta del reactor nuclear a Australia por parte de la empresa argentina INVAP

    OpenAIRE

    Fazio,María Eugenia

    2008-01-01

    En el presente trabajo se analizan dos discursos publicados en la Redes (Revista de estudios sobre ciencia y tecnología), con ocasión de la organización de un dossier dedicado al debate sobre la venta de un reactor nuclear a Australia por parte de la empresa argentina INVAP. Tomando como marco teórico la teoría clásica de la argumentación y la nueva retórica, se realiza una indagación en los textos centrada en la organización de las partes del discurso (dispositio), los hechos y las ver...

  5. 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.

  6. Nuclear and radiological safety in the substitution process of the fuel HEU to LEU 30/20 in the Reactor TRIGA Mark III of the ININ; Seguridad nuclear y radiologica en el proceso de sustitucion del combustible HEU a LEU 30/20 en el Reactor TRIGA Mark III del Instituto Nacional de Investigaciones Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez G, J., E-mail: jaime.hernandez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2012-10-15

    Inside the safety initiative in the international ambit, with the purpose of reducing the risks associated with the use of high enrichment nuclear fuels (HEU) for different proposes to the peaceful uses of the nuclear energy, Mexico contributes by means of the substitution of the high enrichment fuel HEU for low enrichment fuel LEU 30/20 in the TRIGA Mark III Reactor, belonging to Instituto Nacional de Investigaciones Nucleares (ININ). The conversion process was carried out by means of the following activities: analysis of the proposed core, reception and inspection of the fuel LEU 30/20, the discharge of the fuels of the mixed reactor core, shipment of the fuels HEU fresh and irradiated to the origin country, reload activities with the fuels LEU 30/20 and parameters measurement of the core operation. In order to maintaining the personnel's integrity and infrastructure associated to the Reactor, during the whole process the measurements of nuclear and radiological safety were controlled to detail, in execution with the license requirements of the installation. This work describes the covering activities and radiological inspections more relevant, as well as the measurements of radiological control implemented with base in the estimate of the equivalent dose of the substitution process. (Author)

  7. 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)

  8. Nuclear Medicine

    Science.gov (United States)

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

  9. 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.

  10. 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)

  11. Alteraciones en los lípidos nucleares hepáticos debidas a la activación in situ del tetracloruro de carbono a radicales libresAlterations in hepatic nuclear lipids due to in situ carbon tetrachloride activation to free radicals.

    OpenAIRE

    Fanelli,Silvia Laura

    1996-01-01

    Se evidenció que a partir de la activación nuclear hepática del tetracloruro de carbono (CCl4) se forman radicales libres triclorometilo (*CCl3). Los radicales *CC13 y los CCl3O2* derivados de la reacción de los primeros con el oxígeno, promueven reacciones de adición y de abstracción de H desde los lípidos nucleares. Las reacciones de adición son más intensas con los *CCl3 ; mientras que las de abstracción de H son promovidas más fuertemente por los CCl302*. Los *CCl3 se adicionan preferente...

  12. CARACTERIZACIÓN AGROMORFOLOGICA Y CONTENIDO EN ADN NUCLEAR EN ACCESIONES DE CUATRO ESPECIES DE MEDICAGOS ANUALES DEL NORTE DE ESPAÑA

    OpenAIRE

    Oliveira Prendes, J. A.; Afif Khouri, E.

    2012-01-01

    Dieciséis accesiones anuales y autógamas de cuatro especies del género Medicago procedentes del norte de España se caracterizaron durante dos años (2008 y 2009) en un diseño por bloques aleatorizados completos con tres repeticiones de 10 plantas por accesión (en total 30 plantas por accesión). El cv Santiago de Medicago polymorpha y la accesión 3710 de Medicago arábica se incluyeron como testigos en el estudio. Todas las accesiones y los testigos se evaluaron mediante nueve caracteres agromor...

  13. CARACTERIZACIÓN AGROMORFOLOGICA Y CONTENIDO EN ADN NUCLEAR EN ACCESIONES DE CUATRO ESPECIES DE MEDICAGOS ANUALES DEL NORTE DE ESPAÑA

    OpenAIRE

    Oliveira Prendes, J. A.; AFIF KHOURI, E.

    2012-01-01

    Dieciséis accesiones anuales y autógamas de cuatro especies del género Medicago procedentes del norte de España se caracterizaron durante dos años (2008 y 2009) en un diseño por bloques aleatorizados completos con tres repeticiones de 10 plantas por accesión (en total 30 plantas por accesión). El cv Santiago de Medicago polymorpha y la accesión 3710 de Medicago arábica se incluyeron como testigos en el estudio. Todas las accesiones y los testigos se evaluaron mediante nueve caracteres agromor...

  14. 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.

  15. 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.

  16. 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

  17. 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)

  18. 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)

  19. 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.

  20. 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)

  1. 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

  2. Nuclear Confidence

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

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

  3. 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)

  4. Determination of internal pressure and the backfill gas composition of nuclear fuel rods; Determinacion de la presion interna y la composicion del gas de llenado de barras de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Garcia C, M.A.; Cota S, G.; Merlo S, L.; Fernandez T, F. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1997-07-01

    An important consideration in the nuclear fuel manufacturing is the measurement of the helium atmosphere pressure and its composition analysis inside the nuclear fuel rod. In this work it is presented a system used to measure the internal pressure and to determine the backfill gas composition of fuel rods. The system is composed of an expansion chamber provided of a seals system to assure that when rod is drilled, the gas stays contained inside the expansion chamber. The system is connected to a pressure measurement digital system: Baratron MKS 310-AHS-1000. Range 1000 mm Hg from which the pressure readings are taken when this is stabilized in all the system. After a gas sample is sent toward a Perkin Elmer gas chromatograph, model 8410 with thermal conductivity detector to get the corresponding chromatogram and doing the necessary calculations for obtaining the backfill gas composition of the rod in matter. (Author)

  5. Evaluation of Zinc element from the information existing in the BROND-2.2 nuclear data base; Evaluacion del elemento Zinc desde la informacion incluida en la base de datos nucleares BROND-2.2

    Energy Technology Data Exchange (ETDEWEB)

    Leszczynski, Francisco [Comision Nacional de Energia Atomica, San Carlos de Bariloche (Argentina). Centro Atomico Bariloche; Panini, Gian C. [ENEA, Bologna (Italy)

    1997-12-01

    In the last years Zinc is becoming an interesting material widely used as component in nuclear machines. Nevertheless, data for preparing nuclear data libraries are not presently fully available than the following evaluations: CENDL-2: natural zinc with neutron diffusion data, no gamma-ray production; JEF-2.2: one isotope only, Zn-64, including neutron diffusion data, no gamma-ray production; BROND-2.2: two evaluation groups: natural zinc with neutron diffusion data and no gamma-ray production data. In order to produce group libraries with all necessary data, i.e. neutron diffusion and damage data including kerma and gamma-ray production, it is necessary to re-evaluate the element (or all the isotopes). The procedure and results of the element evaluation are described. (author). 4 refs., 2 tabs.

  6. 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 .).

  7. Exposure of the limbs during practice nuclear medicine diagnostics and therapy. Project result Oramed; Exposicion de las extremidades durante practicas de medicina nuclear de diagnostico y terapia. Resultados del proyecto oramed

    Energy Technology Data Exchange (ETDEWEB)

    Carnicer, A.; Ginjaume, M.; Ortega, X.; Babchler, S.; Donadille, L.; Donadille, L.; Ferrari, P.; Fulop, M.; Gualdrini, G.; Krim, S.; Mariotti, F.; Rimples, A.; Ruiz, N.; Sans Merce, M.; Vanhavers, F.

    2011-07-01

    This paper presents the main results of the project ORAMED (Optimization of Radiation Protection of medical staff) . One of the working groups (WP4) was devoted to the study and improvement of the doses received in the hand for the implementation of operating procedures in nuclear medicine departments. The objectives of the working group responded to the need to expand the knowledge and improvements in this field, since in previous work had identified practices that could potentially high doses exceed the dose limits.

  8. 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)]. e-mail: consuelo.varela@infomed.sld.cu

    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)

  9. 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.

  10. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Folguera, M.; Corral, A.

    2014-04-01

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

  12. Nuclear safeguards; Salvaguardias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zurron, O.

    2015-07-01

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

  13. 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)

  14. 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)

  15. 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.

  16. 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)

  17. 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.

  18. 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.

  19. Advances in seismic safety of operating nuclear power plants: IAEA Project Results Seismic-EBP; Avances en la seguridad sismica de centrales nucleares en operacion: Resultados del proyecto OIEA Seismic-EBP

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez juan, A.; Sanchez Cabanero, J. G.; Moreno gonzalez, A.

    2010-07-01

    Records of strong earthquakes occurred in the proximity of facilities in operation have shown that there may be greater than the expected acceleration, the seismic danger that the light of the actual experience can exceed the design basis, and that the aging installations and modifications over its operating life significantly influence seismic response capacity. All this confirms that the earthquake is the external event with the greatest impact on the safety of nuclear installations and the largest contributor (even more than 70%) to the core damage frequency of central probabilistic safety analyzes.

  20. 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)

  1. EFECTO DE PMA SOBRE UNA VARIANTE NUCLEAR DE CATEPSINA L Y LA ACTIVACION DEL FACTOR DE TRANSCRIPCION CDP/CUX EN CELULAS CACO-2

    OpenAIRE

    HERMOSILLA AGUAYO, VIVIANA ESTEFANIA

    2012-01-01

    El estudio de los mecanismos moleculares subyacentes al desarrollo del cáncer comprende el uso de compuestos capaces de actuar como promotores tumorales, los que favorecen la proliferación de células incompletamente transformadas. Dentro de ellos, uno de los más ampliamente utilizados es forbol 12-miristato 13-acetato o PMA. Los efectores a nivel celular de este compuesto corresponden a una familia de serina-treonina quinasas, conocidas como "Proteína quinasa C" o PKC, que partici...

  2. Análisis termohidráulico de la refrigeración del combustible nuclear mediante dinámica de fluidos computacional

    OpenAIRE

    Vicente Sánchez, Pablo

    2016-01-01

    La refrigeración en el núcleo de los reactores de agua en ebullición se rige por la fenomenología propia de los flujos bifásicos. En ella se incluyen cambios de fase y regímenes de flujo muy diversos, que afectan a la interacción entre el refrigerante y las varillas de combustible y, en consecuencia, al rendimiento del reactor. Por ello entender en detalle el flujo en ebullición que caracteriza a estos reactores es de gran importancia a la hora de optimizar su diseño y prever su comportamient...

  3. 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)

  4. 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)

  5. Decommissioning process of the experimental nuclear reactor ARGOS, sited at the Technical School of Industrial Engineering in Barcelona; Proceso de desmantelamiento del reactor nuclear experimental Argos de la Universidad Politecnica de Catalunya

    Energy Technology Data Exchange (ETDEWEB)

    Ortega Aramburu, X.; Duch Guillen, M. A.

    2005-07-01

    The experimental nuclear reactor ARGOS, sited at the Technical School of Industrial Engineering in Barcelona, was an experimental reactor used for training purposes, from 1963 to 1977. Due to economic and administrative circumstances this facility was closed down at the end of this period and the fuel remained the fuel inside the reactor core. In 1994 the fuel was removed. The administrative licence was finally agreed with the authorities in 1998 after a long delay. The decommissioning operations began in 2001. The University dismantled, temporarily stored, checked and classified about 1200 components with a total weight of 154.4 t. The material which was declassified from the radiation protection point of view was approximately 99.9% of all the material. After presenting the final documents to the appropriate authorities the formal closing declaration was agreed in December 2003. After this date the site could be used for any purpose and it was the first case of the decommissioning of a nuclear reactor in Spain. Recently the ARGOS building have been finally demolished. (Author)

  6. Nuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Sang, David (Bishop Luffa Comprehensive School, Chichester (UK))

    1990-01-01

    Nuclear Physics covers the aspects of radioactivity and nuclear physics dealt with in the syllabuses of all the A-level examination boards; in particular, it provides detailed coverage of the Joint Matriculation Board option in nuclear physics. It deals with the discovery of the atomic nucleus, the physics of nuclear processes, and nuclear technology. (author).

  7. Nuclear ventriculography

    Science.gov (United States)

    ... ventriculography (RNV); Multiple gate acquisition scan (MUGA); Nuclear cardiology; Cardiomyopathy - nuclear ventriculography ... 56. Udelson JE, Dilsizian V, Bonow RO. Nuclear cardiology. In: Bonow RO, Mann DL, Zipes DP, Libby ...

  8. Nuclear Medicine.

    Science.gov (United States)

    Badawi, Ramsey D.

    2001-01-01

    Describes the use of nuclear medicine techniques in diagnosis and therapy. Describes instrumentation in diagnostic nuclear medicine and predicts future trends in nuclear medicine imaging technology. (Author/MM)

  9. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-07-01

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

  11. LA NULIDAD PROCESAL COMO TECNICA PROTECTORA DE LOS DERECHOS Y GARANTIAS DE LAS PARTES EN EL CODIGO DE PROCEDIMIENTO CIVIL CHILENO

    OpenAIRE

    CARRASCO POBLETE, JAIME ANDRES

    2012-01-01

    La nulidad constituye una institución clásica y fundamental del Derecho. Ella está presente tanto en la teoría general del Derecho como en las diferentes ramas del mismo. En lo que respecta al Derecho procesal, el estudio de la nulidad es complejo y a lo largo de los años no ha perdido actualidad, abordándose desde diversas perspectivas. Las clásicas elaboraciones teóricas que han surgido en nuestra doctrina aparentemente no presentan inconvenientes, pero cuando se analiza...

  12. LA NULIDAD PROCESAL COMO TECNICA PROTECTORA DE LOS DERECHOS Y GARANTIAS DE LAS PARTES EN EL CODIGO DE PROCEDIMIENTO CIVIL CHILENO

    OpenAIRE

    CARRASCO POBLETE, JAIME ANDRES

    2012-01-01

    La nulidad constituye una institución clásica y fundamental del Derecho. Ella está presente tanto en la teoría general del Derecho como en las diferentes ramas del mismo. En lo que respecta al Derecho procesal, el estudio de la nulidad es complejo y a lo largo de los años no ha perdido actualidad, abordándose desde diversas perspectivas. Las clásicas elaboraciones teóricas que han surgido en nuestra doctrina aparentemente no presentan inconvenientes, pero cuando se analiza...

  13. Nuclear Theory - Nuclear Power

    Science.gov (United States)

    Svenne, J. P.; Canton, L.; Kozier, K. S.

    2008-01-01

    The results from modern nuclear theory are accurate and reliable enough to be used for practical applications, in particular for scattering that involves few-nucleon systems of importance to nuclear power. Using well-established nucleon-nucleon (NN) interactions that fit well the NN scattering data, and the AGS form of the three-body theory, we have performed precise calculations of low-energy neutron-deuteron (n+d) scattering. We show that three-nucleon force effects that have impact on the low-energy vector analyzing powers have no practical effects on the angular distribution of the n+d cross-section. There appear to be problems for this scattering in the evaluated nuclear data file (ENDF) libraries, at the incident neutron energies less than 3.2 MeV. Supporting experimental data in this energy region are rather old (>25 years), sparse and often inconsistent. Our three-body results at low energies, 50 keV to 10.0 MeV, are compared to the ENDF/B-VII.0 and JENDL (Japanese Evaluated Nuclear Data Library) -3.3 evaluated angular distributions. The impact of these results on the calculated reactivity for various critical systems involving heavy water is shown.

  14. 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.

  15. Aging of reactor vessels in LWR type reactors; Envejecimiento de la vasija y de los internos del nuclear de los reactores tipo LWR

    Energy Technology Data Exchange (ETDEWEB)

    Gomez Briceno, D.; Lapena, J.; Serrano, M.

    2004-07-01

    Most of the degradation mechanisms of nuclear components were not included on the design so they have to be treated a posteriori, and that imply a loss of capacity. In this paper the state of the art on the reactor pressure vessel neutron embrittlement and on the irradiation assisted stress corrosion cracking that affects internal components, are explained. Special attention is devoted on the influence of the neutron fluence on IASCC process, on the material alterations promoted by irradiation and their consequences on the susceptibility to this phenomenon. Regarding the reactor pressure vessel degradation, this paper discuss the application of the Master Curve on the structural integrity evaluation of the vessel. Other aspects related to further developments are also mentioned and the importance of a good materials ageing management on the operation of the plant is pointed out. (Author) 12 refs.

  16. 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)

  17. La responsabilidad civil derivada de los daños ocasionados al derecho al honor, a la intimidad personal y familiar y a la propia imágen

    OpenAIRE

    Rovira-Sueiro, María E.

    2011-01-01

    [Resumen] SE ANALIZA LA RESPONSABILIDAD CIVIL EN EL AMBITO ESPECIFICO DE LOS DERECHOS AL HONOR, INTIMIDAD E IMAGEN COMPARANDOLA CON EL REGIMEN COMUN DE RESPONSABILIDAD CIVIL CONTENIDO EN EL ARTICULO 1902 DEL CODIGO CIVIL.

  18. Comunicacion electoral universitaria a traves de la web 2.0

    National Research Council Canada - National Science Library

    Vazquez-Gestal, Montserrat; Fernandez-Souto, Ana Belen; Perez-Seoane, Jesus

    2012-01-01

    .... Esto desencadeno una ferrea batalla 2.0 en la que los dos aspirantes a rector utilizaron los codigos propios del medio para desarrollar controvertidas campanas virales, extender todo tipo de rumores y mantener un pulso en la red inedito...

  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. 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)

  1. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

  3. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Kee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    International cooperation in nuclear industries requires nuclear control as prerequisites. The concept of nuclear control is based on the Treaty on the Non-proliferation of Nuclear Weapon (NPT). The International Atomic Energy Agency (IAEA) plays central role in implementing nuclear control. Nuclear control consists of nuclear safeguards, physical protection, and export/import control. Each member state of NPT is subject to the IAEA`s safeguards by concluding safeguards agreements with the IAEA. IAEA recommends member states to implement physical protection on nuclear materials by `The Physical Protection of Nuclear Material` and `The Convention on the Physical Protection of Nuclear Material` of IAEA. Export/Import Control is to deter development of nuclear weapons by controlling international trade on nuclear materials, nuclear equipments and technology. Current status of domestic and foreign nuclear control implementation including recent induction of national inspection system in Korea is described and functions of recently set-up Technology Center for Nuclear Control (TCNC) under the Korea Atomic Energy Research Institute (KAERI) are also explained. 6 tabs., 11 refs. (Author).

  4. 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. 

  5. 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)

  6. 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)

  7. 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)

  8. 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 ...

  9. Nuclear Chemistry.

    Science.gov (United States)

    Chemical and Engineering News, 1979

    1979-01-01

    Provides a brief review of the latest developments in nuclear chemistry. Nuclear research today is directed toward increased activity in radiopharmaceuticals and formation of new isotopes by high-energy, heavy-ion collisions. (Author/BB)

  10. Nuclear weapons, nuclear effects, nuclear war

    Energy Technology Data Exchange (ETDEWEB)

    Bing, G.F.

    1991-08-20

    This paper provides a brief and mostly non-technical description of the militarily important features of nuclear weapons, of the physical phenomena associated with individual explosions, and of the expected or possible results of the use of many weapons in a nuclear war. Most emphasis is on the effects of so-called ``strategic exchanges.``

  11. Nuclear Ambitions

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    China will begin to build the world’s first third-generation nuclear power plant at the Sanmen Nuclear Power Project in Sanmen City, coastal Zhejiang Province, in March 2009, accord-ing to the State Nuclear Power Technology Corp.

  12. Nuclear structure

    CERN Document Server

    Nazarewicz, W

    1999-01-01

    Current developments in nuclear structure are discussed from a theoretical perspective. The studies of the nuclear many-body system provide us with invaluable information about the nature of the nuclear interaction, nucleonic correlations at various energy-distance scales, and the modes of the nucleonic matter.

  13. 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.

  14. Use of codes thermohydraulic Best -estimate to simulate systems of the Bop; Utilizacion de codigos termohidraulicos Best-Estimate para simular sistemas de BOP

    Energy Technology Data Exchange (ETDEWEB)

    Esteban Benavides, J. a.; Ruiz Martin, J. A.; Rey Alonso, P.

    2012-07-01

    This work develops in the context the continuous improvement of simulation, designed, developed and employed by Tecnatom this technology is primarily focused in the field of the training of operators in the control room of various industrial processes (nuclear, thermal, solar thermal, electrical distribution, etc.). The goal is to have the most advanced technology as a vehicle to provide the highest quality.

  15. Nuclear spectroscopy

    CERN Document Server

    Ajzenberg-Selove, Fay

    1960-01-01

    Nuclear Spectroscopy, Part B focuses on the ways in which experimental data may be analyzed to furnish information about nuclear parameters and nuclear models in terms of which the data are interpreted.This book discusses the elastic and inelastic potential scattering amplitudes, role of beta decay in nuclear physics, and general selection rules for electromagnetic transitions. The nuclear shell model, fundamental coupling procedure, vibrational spectra, and empirical determination of the complex potential are also covered. This publication is suitable for graduate students preparing for exper

  16. 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)

  17. 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)

  18. 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)

  19. 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)

  20. Simulation of a SGTR severe PWR-W with the MELCOR code; Simulacion de un SGTR severo en un PWR-W con el codigo MELCOR

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, A. J.; Israelsson, C.; Jimenez, G.

    2013-07-01

    The type SGTR accident is a case of loss of coolant accident small features which make it necessary to differentiate and evolution of classical studies LOCA sequence type. To simulate this type of accident has chosen the MELCOR code, which aims to study the progression of severe accidents in LWR plants. It has been developed by Sandia National Laboratories for the United States Nuclear Regulatory Commission.

  1. 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)

  2. 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.

  3. Nuclear Fission

    Science.gov (United States)

    Denschlag, J. O.

    This chapter first gives a survey on the history of the discovery of nuclear fission. It briefly presents the liquid-drop and shell models and their application to the fission process. The most important quantities accessible to experimental determination such as mass yields, nuclear charge distribution, prompt neutron emission, kinetic energy distribution, ternary fragment yields, angular distributions, and properties of fission isomers are presented as well as the instrumentation and techniques used for their measurement. The contribution concentrates on the fundamental aspects of nuclear fission. The practical aspects of nuclear fission are discussed in http://dx.doi.org/10.1007/978-1-4419-0720-2_57 of Vol. 6.

  4. 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.

  5. Edificios del reactor nuclear experimental. Madrid

    Directory of Open Access Journals (Sweden)

    de Cabanyes, Cayetano

    1959-03-01

    Full Text Available La antigua división entre edificios industriales y edificios arquitectónicos está siendo felizmente superada en España, y los campos específicos de la Arquitectura y de la Ingeniería tienden a mezclarse y a ser tratados conjuntamente por ambas técnicas. Sólo beneficios cabe esperar de este trabajo combinado, y el reconocimiento de que el todo orgánico de un gran edificio no se podrá nunca reducir a una de sus partes (arquitectura, estructura, instalaciones, puede ser la base para una mejor productividad nacional en este campo de la edificación.

  6. Improved in Parallel Version of the thermalhydraulic code Subchannel COBRA-TF; Mejoras en la Version Paralela d el Codigo Termohidraulico de Subcanal COBRA-TF

    Energy Technology Data Exchange (ETDEWEB)

    Ramos, E.; Abarca, A.; Roman, J. E.; Miro, R.

    2014-07-01

    Analysis on nuclear safety at the level rod of fuel requires the execution of coupled code neutronic-thermalhydraulic that allow the simulation of large physical domains in a reasonable amount of time. To do this it is essential the use of numerous processors (or cores) that work together to obtain the solution to a only problem using available memory and computational power in a cluster. This document sets out improvements in coupled code, which are centered in the part of memory optimization and parallelism, in addition the PVM (Parallel Virtual Machine) and MPI technology has combined to enable the use of the attached code CTF/PARCSV2.7. (Author)

  7. 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)

  8. 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 ...

  9. 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

  10. 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?.

  11. Thermomechanical analysis of fuel rods during transitory events using the RAMONA and FETMA codes; Analisis termomecanico de barras combustibles durante eventos transitorios usando los codigos RAMONA y FETMA

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez L, H. [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: hector.hernandez@inin.gob.mx

    2009-10-15

    In National Institute of Nuclear Research, the fuel management system (FMS) has been used by long time to simulate the BWR operation in stationary state, as well as during a transitory event. To evaluate the thermomechanical behavior of a fuel element was created and interface between the FMS codes and the fuel element thermo mechanical analysis (FETMA) code properly developed and implemented. In this work, the results of thermomechanical behavior of fuel rods that compose the hot channel during the simulation of a transitory event of a BWR are shown. The transitory events considered in this work are a load rejection and failure in controller of feed water, which are events more important that can to occur in a BWR. The results show that during the developed conditions by both transitory events some failure is not presented in fuel rods. Also, that the transitory event of load rejection is more claimant in security terms that of controller failure of feed water. (Author)

  12. Generation of cross-sections and reference solutions using the code Serpent; Generacion de secciones eficaces y soluciones de referencia usando el codigo SERPENT

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A. M.; Delfin L, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E., E-mail: armando.gomez@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico)

    2012-10-15

    Serpent is a code that solves the neutron transport equations using the Monte Carlo method that besides generating reference solutions in stationary state for complex geometry problems, has been specially designed for physical applications of cells, what includes the generation of homogenized cross-sections for several energy groups. In this work a calculation methodology is described using the code Serpent to generate the necessary cross-sections to carry out calculations with the code TNXY, developed in 1993 in the Nuclear Engineering Department of the Instituto Politecnico Nacional (Mexico) by means of an interface programmed in Octave. The computation program TNXY solves the neutron transport equations for several energy groups in stationary state and geometry X Y using the Discreet Ordinates method (S{sub N}). To verify and to validate the methodology the results of TNXY were compared with those calculated by Serpent giving minor differences to 0.55% in the value of the multiplication factor. (Author)

  13. Nuclear Physics

    CERN Document Server

    Savage, Martin J

    2016-01-01

    Lattice QCD is making good progress toward calculating the structure and properties of light nuclei and the forces between nucleons. These calculations will ultimately refine the nuclear forces, particularly in the three- and four-nucleon sector and the short-distance interactions of nucleons with electroweak currents, and allow for a reduction of uncertainties in nuclear many-body calculations of nuclei and their reactions. After highlighting their importance, particularly to the Nuclear Physics and High-Energy Physics experimental programs, I discuss the progress that has been made toward achieving these goals and the challenges that remain.

  14. 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)

  15. 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.

  16. 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)

  17. Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    White, Morgan C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-23

    PowerPoint presentation targeted for educational use. Nuclear data comes from a variety of sources and in many flavors. Understanding where the data you use comes from and what flavor it is can be essential to understand and interpret your results. This talk will discuss the nuclear data pipeline with particular emphasis on providing links to additional resources that can be used to explore the issues you will encounter.

  18. Nuclear astrophysics

    Energy Technology Data Exchange (ETDEWEB)

    Arnould, M. [Institut d' Astronomie et d' Astrophysique, Universite Libre de Bruxelles, Bruxelles (Belgium); Takahashi, K. [Max-Planck-Institut fuer Astrophysik, Garching (Germany)

    1999-03-01

    Nuclear astrophysics is that branch of astrophysics which helps understanding of the Universe, or at least some of its many faces, through the knowledge of the microcosm of the atomic nucleus. It attempts to find as many nuclear physics imprints as possible in the macrocosm, and to decipher what those messages are telling us about the varied constituent objects in the Universe at present and in the past. In the last decades much advance has been made in nuclear astrophysics thanks to the sometimes spectacular progress made in the modelling of the structure and evolution of the stars, in the quality and diversity of the astronomical observations, as well as in the experimental and theoretical understanding of the atomic nucleus and of its spontaneous or induced transformations. Developments in other subfields of physics and chemistry have also contributed to that advance. Notwithstanding the accomplishment, many long-standing problems remain to be solved, and the theoretical understanding of a large variety of observational facts needs to be put on safer grounds. In addition, new questions are continuously emerging, and new facts endangering old ideas. This review shows that astrophysics has been, and still is, highly demanding to nuclear physics in both its experimental and theoretical components. On top of the fact that large varieties of nuclei have to be dealt with, these nuclei are immersed in highly unusual environments which may have a significant impact on their static properties, the diversity of their transmutation modes, and on the probabilities of these modes. In order to have a chance of solving some of the problems nuclear astrophysics is facing, the astrophysicists and nuclear physicists are obviously bound to put their competence in common, and have sometimes to benefit from the help of other fields of physics, like particle physics, plasma physics or solid-state physics. Given the highly varied and complex aspects, we pick here some specific nuclear

  19. Nuclear astrophysics

    Science.gov (United States)

    Arnould, M.; Takahashi, K.

    1999-03-01

    Nuclear astrophysics is that branch of astrophysics which helps understanding of the Universe, or at least some of its many faces, through the knowledge of the microcosm of the atomic nucleus. It attempts to find as many nuclear physics imprints as possible in the macrocosm, and to decipher what those messages are telling us about the varied constituent objects in the Universe at present and in the past. In the last decades much advance has been made in nuclear astrophysics thanks to the sometimes spectacular progress made in the modelling of the structure and evolution of the stars, in the quality and diversity of the astronomical observations, as well as in the experimental and theoretical understanding of the atomic nucleus and of its spontaneous or induced transformations. Developments in other subfields of physics and chemistry have also contributed to that advance. Notwithstanding the accomplishment, many long-standing problems remain to be solved, and the theoretical understanding of a large variety of observational facts needs to be put on safer grounds. In addition, new questions are continuously emerging, and new facts endangering old ideas. This review shows that astrophysics has been, and still is, highly demanding to nuclear physics in both its experimental and theoretical components. On top of the fact that large varieties of nuclei have to be dealt with, these nuclei are immersed in highly unusual environments which may have a significant impact on their static properties, the diversity of their transmutation modes, and on the probabilities of these modes. In order to have a chance of solving some of the problems nuclear astrophysics is facing, the astrophysicists and nuclear physicists are obviously bound to put their competence in common, and have sometimes to benefit from the help of other fields of physics, like particle physics, plasma physics or solid-state physics. Given the highly varied and complex aspects, we pick here some specific nuclear

  20. Nuclear Nonproliferation

    Energy Technology Data Exchange (ETDEWEB)

    Atkins-Duffin, C E

    2008-12-10

    With an explosion equivalent of about 20kT of TNT, the Trinity test was the first demonstration of a nuclear weapon. Conducted on July 16, 1945 in Alamogordo, NM this site is now a Registered National Historic Landmark. The concept and applicability of nuclear power was demonstrated on December 20, 1951 with the Experimental Breeder Reactor Number One (EBR-1) lit four light bulbs. This reactor is now a Registered National Historic Landmark, located near Arco, ID. From that moment forward it had been clearly demonstrated that nuclear energy has both peaceful and military applications and that the civilian and military fuel cycles can overlap. For the more than fifty years since the Atoms for Peace program, a key objective of nuclear policy has been to enable the wider peaceful use of nuclear energy while preventing the spread of nuclear weapons. Volumes have been written on the impact of these two actions on the world by advocates and critics; pundits and practioners; politicians and technologists. The nations of the world have woven together a delicate balance of treaties, agreements, frameworks and handshakes that are representative of the timeframe in which they were constructed and how they have evolved in time. Collectively these vehicles attempt to keep political will, nuclear materials and technology in check. This paper captures only the briefest abstract of the more significant aspects on the Nonproliferation Regime. Of particular relevance to this discussion is the special nonproliferation sensitivity associated with the uranium isotope separation and spent fuel reprocessing aspects of the nuclear fuel cycle.

  1. El atributo de la soberanía: en el origen y desarrollo del Derecho Internacional clásico y contemporáneo y en el actual sistema adecuado a la tecnología nuclear

    Directory of Open Access Journals (Sweden)

    Heber Arbuet Vignali

    2015-10-01

    Full Text Available El atributo de la soberanía de los Estados en sus significado jurídico internacional, está intimamente vinculado al origen, la estructura, el desarrollo y la evolución del Derecho Internacional Público. Para comprender cabalmente un sistema jurídico tan pecualiar como éste, resulta imprescindible considerar que sus sujetos originarios, principales y para algunos los únicos, son Estados soberanos (...Contenido: Nuestra visión del tema. Aparición del derecho internacional y la nueva idea desoberanía. Distintos alcances de la expresión soberanía. Características del atributode la soberanía. Soberanía y poderes. Algunas conclusiones

  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. 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)

  4. Using MCNPX and GEANT code to study the energy response of dual energy detectors; Utilizacion del codigo MCNP y GEANT para el estudio de la respuesta energetica de detectores de energia dual

    Energy Technology Data Exchange (ETDEWEB)

    Juste, B.; Moreda, D.; Miro, R.; Verdu, G.

    2011-07-01

    The use of radiation detectors Dual energy (dual energy) is a powerful tool for identification of materials subjected to X-ray analysis. Given a photon spectrum emitted by an X-ray tube, at low energies, the absorption of radiation depends mainly on the effective atomic number and thickness of the material. In contrast, higher energy levels, above 100 kilovolts, the energy absorbed depends, above all, the material density.

  5. Generation of neutron cross sections library for the Thermos code of the Fuel management System (FMS); Generacion de la biblioteca de secciones eficaces de neutrones para el codigo Thermos del sistema de administracion de combustible (FMS)

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G.; Viais J, J. [ININ, Gcia. Sistemas Nucleares, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1990-10-15

    There is developed a method to generate the library of neutron cross sections for the Thermos code by means of the database ENDF-B/IV and the NJOY code. The obtained results are compared with the version previous of the library of neutron cross sections which was processed using the version ENDF-B/III. (Author)

  6. Using the MCNPX code for the calculation of matrix response in a system of shperes bonner; Uso del codigo MCNPX para el calculo de matrices respuesta en un sistema de esferas bonner

    Energy Technology Data Exchange (ETDEWEB)

    Guerrero Araque, J. E.; Mendez Villafane, R.

    2013-07-01

    This work intends to heavily describe simulation steps used in code MCNPX for calculation for Neutron response of a BSS with passive or active detector. Has it been calculated with MCNPX the matrix response of a system of Bonner spheres, with passive or active detector, which described in detail the steps to be followed by the code are part of the solution. (Author)

  7. Analysis of ROSA 1.1 test with TRACE code: ECSS water injection under natural circulation conditions; Analisis con el codigo TRACE del test ROSA 1.1: Inyeccion de agua ECCS bajo condiciones de circulacion natural

    Energy Technology Data Exchange (ETDEWEB)

    Julibe, A. J.; Munoz-Coba, J. L.; Escriva, A.; Romero, A.

    2010-07-01

    This paper is based on modelling the ROSA 1.1 test by TRACE code. The ROSA 1.1 test presents several natural flow phases in biphasic conditions and this was the cause of this work. Therefore, the aim of this paper is verify the TRACE code ability to simulate such flows using standard components and modules.

  8. Study of Aerosols capture process in pool for injections Gaseous Jets at High Speeds: Enhancements SPARC90; Estudio de los Procesos de Captura de Aerosoles en Piscina para Inyecciones de Jets Gaseosos a Altas Velocidades: Mejoras del Codigo SPAR90

    Energy Technology Data Exchange (ETDEWEB)

    Berna, C.; Escriva, A.; Munoz-Cobo, J. L.; Herranz, L. E.

    2012-07-01

    Code The different expressions found in the literature have been analyzed in a modified version of the code SPARC90, those considered most appropriate. are compared in terms of decontamination factors, the results obtained using the original and modified (SPARC90-Jet) for SGTR accident conditions SPARC code.

  9. Adequacy of the SPARC9O code for the simulation of the capture of aerosols by break in steam generator; Adecuacion del codigo sparc90 para la simulacion de la captura de aerosoles por rotura en el generador de vapor

    Energy Technology Data Exchange (ETDEWEB)

    Escriva, A.; Munoz-Cobo, J. L.; Berna, C.; Herranz, L. E.

    2011-07-01

    The SPARC9O (Suppression Pool Aerosol Removal Code)is intended to perform the calculation in terms of discharge of aerosols in swimming pools, is for this reason that it is working to achieve an analytical model that suits the conditions of discharge in a steam generator the code.

  10. 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.

  11. 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.

  12. 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)

  13. 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)

  14. 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)

  15. 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)

  16. 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)

  17. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small ... of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical ...

  18. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... News Physician Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging ... the limitations of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch ...

  19. General Nuclear Medicine

    Science.gov (United States)

    ... Physician Resources Professions Site Index A-Z General Nuclear Medicine Nuclear medicine imaging uses small amounts of ... limitations of General Nuclear Medicine? What is General Nuclear Medicine? Nuclear medicine is a branch of medical ...

  20. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small ... of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical ...

  1. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Physician Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses ... limitations of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of ...

  2. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small amounts ... Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical imaging ...

  3. Children's (Pediatric) Nuclear Medicine

    Science.gov (United States)

    ... Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small amounts ... Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical imaging ...

  4. 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.

  5. 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)

  6. Nuclear scales

    Energy Technology Data Exchange (ETDEWEB)

    Friar, J.L.

    1998-12-01

    Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the {pi}-{gamma} force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted.

  7. Nuclear Scales

    CERN Document Server

    Friar, J L

    1998-01-01

    Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the $\\pi$-$\\gamma$ force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted.

  8. Nuclear astrophysics

    CERN Document Server

    Arnould, M

    1999-01-01

    Nuclear astrophysics is that branch of astrophysics which helps understanding some of the many facets of the Universe through the knowledge of the microcosm of the atomic nucleus. In the last decades much advance has been made in nuclear astrophysics thanks to the sometimes spectacular progress in the modelling of the structure and evolution of the stars, in the quality and diversity of the astronomical observations, as well as in the experimental and theoretical understanding of the atomic nucleus and of its spontaneous or induced transformations. Developments in other sub-fields of physics and chemistry have also contributed to that advance. Many long-standing problems remain to be solved, however, and the theoretical understanding of a large variety of observational facts needs to be put on safer grounds. In addition, new questions are continuously emerging, and new facts endanger old ideas. This review shows that astrophysics has been, and still is, highly demanding to nuclear physics in both its experime...

  9. Nuclear Models

    Science.gov (United States)

    Fossión, Rubén

    2010-09-01

    The atomic nucleus is a typical example of a many-body problem. On the one hand, the number of nucleons (protons and neutrons) that constitute the nucleus is too large to allow for exact calculations. On the other hand, the number of constituent particles is too small for the individual nuclear excitation states to be explained by statistical methods. Another problem, particular for the atomic nucleus, is that the nucleon-nucleon (n-n) interaction is not one of the fundamental forces of Nature, and is hard to put in a single closed equation. The nucleon-nucleon interaction also behaves differently between two free nucleons (bare interaction) and between two nucleons in the nuclear medium (dressed interaction). Because of the above reasons, specific nuclear many-body models have been devised of which each one sheds light on some selected aspects of nuclear structure. Only combining the viewpoints of different models, a global insight of the atomic nucleus can be gained. In this chapter, we revise the the Nuclear Shell Model as an example of the microscopic approach, and the Collective Model as an example of the geometric approach. Finally, we study the statistical properties of nuclear spectra, basing on symmetry principles, to find out whether there is quantum chaos in the atomic nucleus. All three major approaches have been rewarded with the Nobel Prize of Physics. In the text, we will stress how each approach introduces its own series of approximations to reduce the prohibitingly large number of degrees of freedom of the full many-body problem to a smaller manageable number of effective degrees of freedom.

  10. Nuclear Assessment

    Institute of Scientific and Technical Information of China (English)

    CHARLES K.EBINGER; JOHN P.BANKS

    2010-01-01

    @@ In President Barack Obama's State of the Union address in January 2009,he called for the building of "a new generation of safe,clean nuclear power plants" This was followed by his highprofile speech in Prague in April 2009,in which he noted the need "to harness the power of nuclear energy on behalf of our efforts to combat climate change."In December 2009 in Copenhagen,he pledged the United States will reduce carbon dioxide (CO2) emissions 17 percent from 2005 levels by 2020.

  11. Nuclear winter or nuclear fall?

    Science.gov (United States)

    Berger, André

    Climate is universal. If a major modern nuclear war (i.e., with a large number of small-yield weapons) were to happen, it is not even necessary to have a specific part of the world directly involved for there to be cause to worry about the consequences for its inhabitants and their future. Indeed, smoke from fires ignited by the nuclear explosions would be transported by winds all over the world, causing dark and cold. According to the first study, by Turco et al. [1983], air surface temperature over continental areas of the northern mid-latitudes (assumed to be the nuclear war theatre) would fall to winter levels even in summer (hence the term “nuclear winter”) and induce drastic climatic conditions for several months at least. The devastating effects of a nuclear war would thus last much longer than was assumed initially. Discussing to what extent these estimations of long-term impacts on climate are reliable is the purpose of this article.

  12. Potencial del agua del suelo

    OpenAIRE

    Bustamante Heliodoro

    2012-01-01

    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...

  13. Nuclear Assessment

    Institute of Scientific and Technical Information of China (English)

    CHARLES; K.; EBINGER; JOHN; P.; BANKS

    2010-01-01

    The United States needs a comprehensive policy and market-based solutions to address the challenges and demands of energy provision in President Barack Obama’s State of the Union address in January 2009, he called for the building of "a new generation of safe, clean nuclear power plants." This was followed by his high- profile speech in Prague in April 2009,

  14. Nuclear Science.

    Science.gov (United States)

    Pennsylvania State Dept. of Education, Harrisburg. Bureau of Curriculum Services.

    This document is a report on a course in nuclear science for the high school curriculum. The course is designed to provide a basic but comprehensive understanding of the atom in the light of modern knowledge, and to show how people attempt to harness the tremendous energy liberated through fission and fusion reactions. The course crosses what are…

  15. 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)

  16. CASPAR - Nuclear Astrophysics Underground

    Science.gov (United States)

    Strieder, Frank; Robertson, Daniel; Couder, Manoel; Greife, Uwe; Wells, Doug; Wiescher, Michael

    2015-10-01

    The work of the LUNA Collaboration at the Laboratori Nationali del Gran Sasso demonstrated the research potential of an underground accelerator for the field of nuclear astrophysics. Several key reactions could be studied at LUNA, some directly at the Gamow peak for solar hydrogen burning. The CASPAR (Compact Accelerator System for Performing Astrophysical Research) Collaboration will implement a high intensity 1 MV accelerator at the Sanford Underground Research Facility (SURF) and overcome the current limitation at LUNA. The installation of the accelerator in the recently rehabilitated underground cavity at SURF started in Summer 2015 and first beam should be delivered by the end of the year. This project will primarily focus on the neutron sources for the s-process, e.g. 13C(α , n) 16O and 22Ne(α , n) 25Mg , and lead to unprecedented measurements compared to previous studies. A detailed overview of the science goals of CASPAR will be presented.

  17. LUNA: Nuclear astrophysics underground

    Energy Technology Data Exchange (ETDEWEB)

    Best, A. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali del Gran Sasso, Assergi (Italy)

    2015-02-24

    Underground nuclear astrophysics with LUNA at the Laboratori Nazionali del Gran Sasso spans a history of 20 years. By using the rock overburden of the Gran Sasso mountain chain as a natural cosmic-ray shield very low signal rates compared to an experiment on the surface can be tolerated. The cross sectons of important astrophysical reactions directly in the stellar energy range have been successfully measured. In this proceeding we give an overview over the key accomplishments of the experiment and an outlook on its future with the expected addition of an additional accelerator to the underground facilities, enabling the coverage of a wider energy range and the measurement of previously inaccessible reactions.

  18. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-04-01

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

  1. Nuclear Physics

    Science.gov (United States)

    Contents: V Dinucleons, published in The Physical Review , v93 n4 p908-909, 15 Feb 1954; Concentration of a Cyclotron Beam by Strong Focusing Lenses...published in The Review of Scientific Instruments, v25 n4 p365-367, Apr 1954; and Photon Splitting in a Nuclear Electrostatic Field, published in The Physical Review , v94 n2 p367-368, 15 Apr 1954.

  2. Nuclear Waffles

    CERN Document Server

    Schneider, A S; Briggs, C M; Caplan, M E; Horowitz, C J

    2014-01-01

    The dense neutron-rich matter found in supernovae and neutron stars is expected to form complex nonuniform phases referred to as nuclear pasta. The pasta shapes depend on density, temperature and proton fraction and determine many transport properties in supernovae and neutron star crusts. We use two recently developed hybrid CPU/GPU codes to perform large scale molecular dynamics (MD) simulations with $51200$ and $409600$ nucleons of nuclear pasta. From the output of the MD simulations we characterize the topology and compute two observables, the radial distribution function $g(r)$ and the structure factor $S(q)$, for systems with proton fractions $Y_p=0.10, 0.20, 0.30$ and $0.40$ at about one third of nuclear saturation density and temperatures near $1.0$ MeV. We observe that the two lowest proton fraction systems simulated, $Y_p=0.10$ and $0.20$, equilibrate quickly and form liquid-like structures. Meanwhile, the two higher proton fraction systems, $Y_p=0.30$ and $0.40$, take a longer time to equilibrate a...

  3. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... are the limitations of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a ... of your child's body. top of page How is the procedure performed? Nuclear medicine imaging is usually ...

  4. 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.

  5. 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.

  6. 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.

  7. Nuclear photonics

    Science.gov (United States)

    Habs, D.; Günther, M. M.; Jentschel, M.; Thirolf, P. G.

    2012-07-01

    With the planned new γ-beam facilities like MEGa-ray at LLNL (USA) or ELI-NP at Bucharest (Romania) with 1013 γ/s and a band width of ΔEγ/Eγ≈10-3, a new era of γ beams with energies up to 20MeV comes into operation, compared to the present world-leading HIγS facility at Duke University (USA) with 108 γ/s and ΔEγ/Eγ≈3ṡ10-2. In the long run even a seeded quantum FEL for γ beams may become possible, with much higher brilliance and spectral flux. At the same time new exciting possibilities open up for focused γ beams. Here we describe a new experiment at the γ beam of the ILL reactor (Grenoble, France), where we observed for the first time that the index of refraction for γ beams is determined by virtual pair creation. Using a combination of refractive and reflective optics, efficient monochromators for γ beams are being developed. Thus, we have to optimize the total system: the γ-beam facility, the γ-beam optics and γ detectors. We can trade γ intensity for band width, going down to ΔEγ/Eγ≈10-6 and address individual nuclear levels. The term "nuclear photonics" stresses the importance of nuclear applications. We can address with γ-beams individual nuclear isotopes and not just elements like with X-ray beams. Compared to X rays, γ beams can penetrate much deeper into big samples like radioactive waste barrels, motors or batteries. We can perform tomography and microscopy studies by focusing down to μm resolution using Nuclear Resonance Fluorescence (NRF) for detection with eV resolution and high spatial resolution at the same time. We discuss the dominating M1 and E1 excitations like the scissors mode, two-phonon quadrupole octupole excitations, pygmy dipole excitations or giant dipole excitations under the new facet of applications. We find many new applications in biomedicine, green energy, radioactive waste management or homeland security. Also more brilliant secondary beams of neutrons and positrons can be produced.

  8. 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...

  9. Nuclear tele medicine; Telemedicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Vargas, L.; Hernandez, F.; Fernandez, R. [Departamento de Medicina Nuclear, Imagenologia Diagnostica, Xalapa, Veracruz (Mexico)

    2005-07-01

    The great majority of the digital images of nuclear medicine are susceptible of being sent through internet. This has allowed that the work in diagnosis cabinets by image it can benefit of this modern technology. We have presented in previous congresses works related with tele medicine, however, due to the speed in the evolution of the computer programs and the internet, becomes necessary to make a current position in this modality of work. (Author)

  10. The nuclear arsenals and nuclear disarmament.

    Science.gov (United States)

    Barnaby, F

    1998-01-01

    Current world stockpiles of nuclear weapons and the status of treaties for nuclear disarmament and the ultimate elimination of nuclear weapons are summarised. The need for including stockpiles of civil plutonium in a programme for ending production and disposing of fissile materials is emphasized, and the ultimate difficulty of disposing of the last few nuclear weapons discussed.

  11. Nuclear energy.

    Science.gov (United States)

    Grandin, Karl; Jagers, Peter; Kullander, Sven

    2010-01-01

    Nuclear energy can play a role in carbon free production of electrical energy, thus making it interesting for tomorrow's energy mix. However, several issues have to be addressed. In fission technology, the design of so-called fourth generation reactors show great promise, in particular in addressing materials efficiency and safety issues. If successfully developed, such reactors may have an important and sustainable part in future energy production. Working fusion reactors may be even more materials efficient and environmental friendly, but also need more development and research. The roadmap for development of fourth generation fission and fusion reactors, therefore, asks for attention and research in these fields must be strengthened.

  12. 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

  13. 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

  14. 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

  15. 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)

  16. Applications of nuclear physics

    Science.gov (United States)

    Hayes, A. C.

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  17. Nuclear Photonics

    CERN Document Server

    Habs, D; Jentschel, M; Thirolf, P G

    2012-01-01

    With new gamma-beam facilities like MEGa-ray at LLNL (USA) or ELI-NP at Bucharest with 10^13 g/s and a bandwidth of Delta E_g/E_g ~10^-3, a new era of g-beams with energies <=20 MeV comes into operation, compared to the present world-leading HIGS facility (Duke Univ., USA) with 10^8 g/s and Delta E_g/E_g~0.03. Even a seeded quantum FEL for g-beams may become possible, with much higher brilliance and spectral flux. At the same time new exciting possibilities open up for focused g-beams. We describe a new experiment at the g-beam of the ILL reactor (Grenoble), where we observed for the first time that the index of refraction for g-beams is determined by virtual pair creation. Using a combination of refractive and reflective optics, efficient monochromators for g-beams are being developed. Thus we have to optimize the system of the g-beam facility, the g-beam optics and g-detectors. We can trade g-intensity for band width, going down to Delta E_g/E_g ~ 10^-6 and address individual nuclear levels. 'Nuclear pho...

  18. 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)

  19. 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)

  20. Contribution and modelization of basic processes for development of the spent nuclear fuel matrix; Contribucion experimental y modelizacion de procesos basicos para el desarrollo del modelo de alteracion de la matriz delcombustible irradiado

    Energy Technology Data Exchange (ETDEWEB)

    Pablo, J. de; Casa, I.; Clarens, F.; Gimenez, J.; Rovira, M.

    2003-07-01

    The behaviour of the spent nuclear fuel in the conditions expected in a deep geological repository depends on some basic processes such as the formation of oxidizing species due to the radiolysis of water, the effect of these species on the spent nuclear fuel matrix oxidation and dissolution, and the precipitation of secondary solid phases. In this work, some of those processes have been studied in detail. In particular, both uranium dioxide oxidation and dissolution rates have been determined in the presence of oxygen an hydrogen per-oxide (the most important molecular species formed in the radiolysis of water). In addition, the precipitation of secondary phases on the UO{sub 2} surfaces in the presence of hydrogen peroxide has also been fool owed by means of the Atomic Force Microscope allowing the identification of studies (UO{sub 4}.H{sub 2}O). On the other hand, the radiolytical models of the dissolution of spent nuclear fuel need to estimate the surface site densities of the solid. In this sense, we have studied surface site densities of three different uranium oxides: UO{sub 2}, U{sub 3}O{sub 8}, and UO{sub 3}.4H{sub 2}O. (Author) 42 refs.

  1. Dictionary of nuclear engineering

    Energy Technology Data Exchange (ETDEWEB)

    Sube, R.

    1985-01-01

    Ralf Sube, an experienced compiler of three wellknown four-language reference works has now prepared this glossary of nuclear engineering terms in English, German, French and Russian. Based on the proven lexicography of the Technik-Worterbuch series, it comprises about 30,000 terms in each language covering the following: Nuclear and Atomic Physics; Nuclear Radiation and Isotopes; Nuclear Materials; Nuclear Facilties; Nuclear Power Industry; Nuclear Weapons.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-10-15

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

  3. Nuclear "waffles"

    Science.gov (United States)

    Schneider, A. S.; Berry, D. K.; Briggs, C. M.; Caplan, M. E.; Horowitz, C. J.

    2014-11-01

    Background: The dense neutron-rich matter found in supernovae and inside neutron stars is expected to form complex nonuniform phases, often referred to as nuclear pasta. The pasta shapes depend on density, temperature and proton fraction and determine many transport properties in supernovae and neutron star crusts. Purpose: To characterize the topology and compute two observables, the radial distribution function (RDF) g (r ) and the structure factor S (q ) , for systems with proton fractions Yp=0.10 ,0.20 ,0.30 , and 0.40 at about one-third of nuclear saturation density, n =0.050 fm-3 , and temperatures near k T =1 MeV . Methods: We use two recently developed hybrid CPU/GPU codes to perform large scale molecular dynamics (MD) simulations with 51 200 and 409 600 nucleons. From the output of the MD simulations we obtain the two desired observables. Results: We compute and discuss the differences in topology and observables for each simulation. We observe that the two lowest proton fraction systems simulated, Yp=0.10 and 0.20 , equilibrate quickly and form liquidlike structures. Meanwhile, the two higher proton fraction systems, Yp=0.30 and 0.40 , take a longer time to equilibrate and organize themselves in solidlike periodic structures. Furthermore, the Yp=0.40 system is made up of slabs, lasagna phase, interconnected by defects while the Yp=0.30 systems consist of a stack of perforated plates, the nuclear waffle phase. Conclusions: The periodic configurations observed in our MD simulations for proton fractions Yp≥0.30 have important consequences for the structure factors S (q ) of protons and neutrons, which relate to many transport properties of supernovae and neutron star crust. A detailed study of the waffle phase and how its structure depends on temperature, size of the simulation, and the screening length showed that finite-size effects appear to be under control and, also, that the plates in the waffle phase merge at temperatures slightly above 1.0 MeV and

  4. Nuclear nirvana?

    Energy Technology Data Exchange (ETDEWEB)

    Sacks, T.

    1997-06-10

    This article describes a proposed method of processing high-level radioactive wastes from existing PWR reactors and weapons grade plutonium to produce relatively benign medium-level wastes, which is easier to handle and store. The energy amplifier proposed by Carlo Rubbia, ex-director-general of CERN, causes fission to occur as a result of nuclear cascades, rather than chain reactions, by bombarding a thorium-based mixture of radioactive materials with a high-intensity beam of sub-atomic particles. He claims that, as it depends largely on proven technology it could be in commercial operation with ten years, well ahead of even a prototype fusion reactor and thus provide a viable, sustainable and more environmentally acceptable power source. (Author).

  5. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  6. del Norte

    Directory of Open Access Journals (Sweden)

    Heydi Robles

    2005-01-01

    Full Text Available Este artículo muestra los resultados de una investigación sobre la ansiedad causada por el aprendizaje de idiomas. Está centrado en la ansiedad relacionada con la habilidad de producción oral. El objetivo del estudio era identificar los factores externos que producen ansiedad en el desarrollo de la competencia oral en un grupo de estudiantes de Psicología. Para lograr su objetivo, la investigación utilizó diarios, cuestionarios, grabaciones (opiniones personales, presentaciones orales breves y entrevistas. Con respecto de los factores externos que producen ansiedad en relación con las actividades, los resultados muestran que todas las actividades orales producen un alto grado de ansiedades en los estudiantes, especialmente las actividades no programadas. También muestran una falta de participación en clase con un fuerte rechazo a las actividades orales. Entre las posibles causas de reticencia puede estar el hecho de que los estudiantes no quieren ser objeto de burla. Además, la habilidad de producción oral no fue estimulada en los niveles anteriores del programa de inglés. Es vital mencionar que los alumnos son conscientes de sus carencias en algunos aspectos del idioma como vocabulario, gramática y fluidez.

  7. Nuclear exoticism

    Science.gov (United States)

    Penionzhkevich, Yu. E.

    2016-07-01

    Extreme states of nuclearmatter (such that feature high spins, large deformations, high density and temperature, or a large excess of neutrons and protons) play an important role in studying fundamental properties of nuclei and are helpful in solving the problem of constructing the equation of state for nuclear matter. The synthesis of neutron-rich nuclei near the nucleon drip lines and investigation of their properties permit drawing conclusions about the positions of these boundaries and deducing information about unusual states of such nuclei and about their decays. At the present time, experimental investigations along these lines can only be performed via the cooperation of leading research centers that possess powerful heavy-ion accelerators, such as the Large Hadron Collider (LHC) at CERN and the heavy-ion cyclotrons at the Joint Institute for Nuclear Research (JINR, Dubna), where respective experiments are being conducted by physicists from about 20 JINR member countries. The present article gives a survey of the most recent results in the realms of super neutron-rich nuclei. Implications of the change in the structure of such nuclei near the nucleon drip lines are discussed. Information about the results obtained by measuring the masses (binding energies) of exotic nuclei, the nucleon-distribution radii (neutron halo) and momentum distributions in them, and their deformations and quantum properties is presented. It is shown that the properties of nuclei lying near the stability boundaries differ strongly from the properties of other nuclei. The problem of the stability of nuclei that is associated with the magic numbers of 20 and 28 is discussed along with the effect of new magic numbers.

  8. Reconversion of nuclear weapons

    CERN Document Server

    Kapitza, Sergei P

    1993-01-01

    The nuclear predicament or nuclear option. Synopsis of three lectures : 1- The physical basis of nuclear technology. Physics of fission. Chain reaction in reactors and weapons. Fission fragments. Separration of isotopes. Radiochemistry.2- Nuclear reactors with slow and fast neutrons. Power, size, fuel and waste. Plutonium production. Dose rate, shielding and health hazard. The lessons of Chernobyl3- Nuclear weapons. Types, energy, blast and fallout. Fusion and hydrogen bombs. What to do with nuclear weapons when you cannot use them? Testing. Nonmilittary use. Can we get rid of the nuclear weapon? Nuclear proliferation. Is there a nuclear future?

  9. 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:

    ·         

  10. Utilización de la discografía para el diagnóstico del dolor discogénico: Comparación con la resonancia magnética nuclear Use of diskography for the diagnosis of diskogenic pain: Comparison with nuclear magnetic resonance

    Directory of Open Access Journals (Sweden)

    D. Abejón

    2004-03-01

    Full Text Available Objetivos: La discografía es un procedimiento diagnóstico invasivo, realizado bajo control fluoroscópico, por el que mediante la punción de un disco intervertebral se introduce contraste radiológico en el núcleo pulposo. La discografía permite la evaluación del disco respecto a su capacidad volumétrica, manométrica, su imagen radiológica y la respuesta al test de provocación. La RMN proporciona una información precoz de la degeneración de los discos sin las complicaciones de una prueba intervencionista. El objetivo de este estudio es valorar la eficacia de la discografía como técnica diagnóstica en el dolor lumbar de origen discogénico y comparar la imagen discográfica y la RMN así como la correlación al realizar el test de provocación del dolor. Material y métodos: Se evalúan, desde abril de 2000 hasta abril del 2001, 60 discos en 29 pacientes. Todos los pacientes estaban sintomáticos y eran evaluados por un dolor lumbar o lumbociático. El tiempo medio de evolución fue de 17 meses. La edad media fue de 43 años (rango de 75-26 años. La muestra estaba compuesta por 11 varones y 18 mujeres. La discografía se dividió según su visión radiológica en tres estadios: normal, degenerada y herniada. La clasificación del test de provocación del dolor la dividimos en cuatro estadios: no doloroso, dolor no concordante, dolor similar y dolor concordante. La imagen obtenida por la RMN la dividimos en tres estadios, siendo normal, degenerado y herniado. Se analiza la utilidad de las pruebas en el diagnóstico del dolor así como la correlación entre ambas pruebas, tanto en la imagen como en la provocación del dolor. También se estudia el número de complicaciones derivadas de la discografía. Resultados: En 35 de los 54 niveles (64,8%, la RMN fue adecuada para predecir si la morfología del disco era normal o anormal en la discografía. De los 23 pacientes con una fisura completa todos los pacientes excepto 2 (8

  11. No Nuclear Worries

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    China National Nuclear Corp.will learn lessons from the Fukushima accident while expanding its operations As Japan’s Fukushima nuclear crisis sparks a global debate over nuclear safety,China National Nuclear Corp.(CNNC),the country’s largest nuclear power operator,comes under

  12. Trends in Nuclear Astrophysics

    OpenAIRE

    Schatz, Hendrik

    2016-01-01

    Nuclear Astrophysics is a vibrant field at the intersection of nuclear physics and astrophysics that encompasses research in nuclear physics, astrophysics, astronomy, and computational science. This paper is not a review. It is intended to provide an incomplete personal perspective on current trends in nuclear astrophysics and the specific role of nuclear physics in this field.

  13. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  15. 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.

  16. 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)

  17. 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

  18. El Principalismo en la Medicina Nuclear.

    Directory of Open Access Journals (Sweden)

    Amilkar Faildes López

    2007-10-01

    Full Text Available Este trabajo aborda una de las teorías bioéticas más difundidas desde la perspectiva de la medicina nuclear en Cuba. Su objetivo general es el estudio de la bioética en el contexto de los procedimientos tecnológicos que se emplean para los estudios in vivo o in vitro de enfermedades con radiofármacos. Los objetivos específicos son explicar los efectos biológicos de las radiaciones ionizantes, exponer la relación entre los principios del principalismo y los de protección radiológica, valorar la importancia del consentimiento informado y la jerarquización de los principios del principalismo en un Departamento de Medicina Nuclear Cubano. Finalmente se concluye que la revisión bibliográfica realizada permitió fundamentar la relación que existe entre los principios de la protección radiológica y de la teoría principalista, se ofrece un cuestionario que recoge todos los datos necesarios para poner en práctica el consentimiento informado del paciente en el procedimiento que se le aplique y se explica cuál debe ser la jerarquización de los principios del principalismo en el sistema nacional de salud cubano.

  19. 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.

  20. Nuclear analytical chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Brune, D.; Forkman, B.; Persson, B.

    1984-01-01

    This book covers the general theories and techniques of nuclear chemical analysis, directed at applications in analytical chemistry, nuclear medicine, radiophysics, agriculture, environmental sciences, geological exploration, industrial process control, etc. The main principles of nuclear physics and nuclear detection on which the analysis is based are briefly outlined. An attempt is made to emphasise the fundamentals of activation analysis, detection and activation methods, as well as their applications. The book provides guidance in analytical chemistry, agriculture, environmental and biomedical sciences, etc. The contents include: the nuclear periodic system; nuclear decay; nuclear reactions; nuclear radiation sources; interaction of radiation with matter; principles of radiation detectors; nuclear electronics; statistical methods and spectral analysis; methods of radiation detection; neutron activation analysis; charged particle activation analysis; photon activation analysis; sample preparation and chemical separation; nuclear chemical analysis in biological and medical research; the use of nuclear chemical analysis in the field of criminology; nuclear chemical analysis in environmental sciences, geology and mineral exploration; and radiation protection.

  1. Mean nuclear volume

    DEFF Research Database (Denmark)

    Mogensen, O.; Sørensen, Flemming Brandt; Bichel, P.

    1999-01-01

    We evaluated the following nine parameters with respect to their prognostic value in females with endometrial cancer: four stereologic parameters [mean nuclear volume (MNV), nuclear volume fraction, nuclear index and mitotic index], the immunohistochemical expression of cancer antigen (CA125...

  2. Cold nuclear fusion

    National Research Council Canada - National Science Library

    Huang Zhenqiang Huang Yuxiang

    2013-01-01

    ...... And with a magnetic moment of light nuclei controlled cold nuclear collide fusion, belongs to the nuclear energy research and development in the field of applied technology "cold nuclear collide fusion...

  3. Nuclear Quadrupole Moments and Nuclear Shell Structure

    Science.gov (United States)

    Townes, C. H.; Foley, H. M.; Low, W.

    1950-06-23

    Describes a simple model, based on nuclear shell considerations, which leads to the proper behavior of known nuclear quadrupole moments, although predictions of the magnitudes of some quadrupole moments are seriously in error.

  4. Las triadas en familias nucleares con hijo único. Estudio en consulta de intervención en el departamento de orientación y bienestar estudiantil sección primaria del Colegio Experimental Británico Internacional

    OpenAIRE

    Gordón Morales, Jacqueline Alejandra

    2008-01-01

    Un solo hijo es una opción elegida cada vez más por los padres del mundo. Muchas personas consideran ventajoso el hecho de tener un solo hijo por razones económicas y sociales, pero también son muchos los que toman esta decisión por el compromiso que implica la crianza. Tradicionalmente las parejas con un único hijo debían tal situación a algún impedimento físico de uno o de ambos padres para engendrar más niños y, aunque de modo excepcional, a políticas demográficas (como las que en 1...

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

    OpenAIRE

    Margarita Zuleta; Luz Yaneth Orozco

    2000-01-01

    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 d...

  6. Nuclear energy data 2010

    CERN Document Server

    2010-01-01

    This 2010 edition of Nuclear Energy Data , the OECD Nuclear Energy Agency's annual compilation of official statistics and country reports on nuclear energy, provides key information on plans for new nuclear plant construction, nuclear fuel cycle developments as well as current and projected nuclear generating capacity to 2035 in OECD member countries. This comprehensive overview provides authoritative information for policy makers, experts and other interested stakeholders.

  7. Consolidation: Thwarting Nuclear Theft

    OpenAIRE

    Bunn, Matthew G.; Harrell, Eben

    2013-01-01

    At the first nuclear security summit in April 2010, the assembled leaders agreed on the goal of securing all vulnerable nuclear material worldwide within four years, including consolidating plutonium and highly enriched uranium (HEU) to fewer locations and minimizing the use of HEU “where technically and economically feasible.†Reducing the number of buildings and sites where nuclear weapons and weapons-usable nuclear material exist is a key element of preventing nuclear theft and nuclear ...

  8. Nuclear Fuel Cycle & Vulnerabilities

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, Brian D. [Los Alamos National Laboratory

    2012-06-18

    The objective of safeguards is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection. The safeguards system should be designed to provide credible assurances that there has been no diversion of declared nuclear material and no undeclared nuclear material and activities.

  9. Nuclear Entalpies

    CERN Document Server

    Rozynek, J

    2013-01-01

    In a compressed Nuclear Matter (NM) an increasing pressure between the nucleons starts to increase the ratio of a nucleon Fermi to average single particle energy and in accordance with the Hugenholtz-van Hove theorem the longitudinal Momentum Sum Rule (MSR) is broken in a Relativistic Mean Field (RMF) approach. We propose to benefit from the concept of enthalpy in order to show how to fulfill the MSR above a saturation density with pressure corrections. As a result a nucleon mass can decrease with density, making the Equation of State (EoS) softer. The course of the EoS in our modified RMF model is close to a semi-empirical estimate and to results obtained from extensive DBHF calculations with a Bonn A potential, which produce the EoS stiff enough to describe neutron star properties (mass-radius constraint), especially the most massive known neutron star. The presented model has proper saturation properties, including good values of a compressibility and a spin-orbit term.

  10. Nuclear Data and Nuclear Model Methods

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    Developing nuclear data needs towards to sustainable development on fission reactor design and many nuclear applications out the field of fission reactor technology that are growing economicsignificance and that have substantial data requirements are introduced. International standard codes used in nuclear data evaluations and calculations are introduced and compared each other. Generally

  11. Italy’s Nuclear Choices

    Directory of Open Access Journals (Sweden)

    Leopoldo Nuti

    2011-01-01

    Full Text Available La política militar y nuclear italiana a lo largo de la Guerra Fría intentó promover las aspiraciones del país de conseguir una posición de paridad con otras potencias europeas. El tema de su propio rango y posición en la jerarquía internacional de potencias fue central en su política exterior desde el nacimiento mismo del país, y la nueva generación de políticos que dieron forma a la política exterior italiana tras la Segunda Guerra Mundial no eran menos conscientes de tan crítico factor que sus predecesores. La nuclearización de la OTAN hizo inevitable que solo aquellos países que tuvieran acceso a las bombas nucleares acabasen tomando las decisiones más cruciales en el futuro de la alianza. El gobierno italiano llegó a la conclusión de que la única manera de alcanzar el estatus nuclear era a través de una estrecha colaboración con la OTAN y los EEUU. Entre 1955 y 1959 la aceptación de bombas nucleares en territorio italiano acabó evolucionando hacia un patrón que formó la base de las políticas nucleares italianas en los 10 año siguientess. Italia era muy reticente a la firma del NPT y ello llevó a establecer una alianza con los principales oponentes europeos, la República Federal Alemana entre ellos, y a establecer una larga serie de contactos con otros posibles opositores al tratado, desde Japón a la India. En 1979 Italia aceptó la presencia de los nuevos Euromisiles en su territorio, considerando de nuevo a los Euromisiles como carta ganadora, un instrumento a usar para reducir las diferencias con otros socios europeos. La relación crucial con los EEUU explica en gran parte las razones de Italia para construir su política nuclear. Desde que los EEUU se convirtiesen en el pilar principal de su orientación internacional, estaba claro que albergar armas nucleares americanas era considerado como un medio para reforzar la asociación. El fin último de la política exterior italiana, la igualdad de estatus con

  12. Del Derecho laboral al Derecho del trabajo

    OpenAIRE

    Jaramillo Jassir, Ivan Daniel

    2011-01-01

    El Derecho Laboral hijo de la revolución industrial, calificado como el acontecimiento jurídico del siglo XX, reduce su ámbito de estudio al trabajo subordinado. Los cambios del sistema de producción superan la centralidad del contrato de trabajo subordinado a tiempo indeterminado, situación que demanda ampliación del ámbito de aplicación subjetivo y objetivo de la materia, dando paso al Derecho del Trabajo que se ocupa del trabajo en todas sus modalidades como fuente de ingreso para satisfac...

  13. Nuclear energy data 2011

    CERN Document Server

    2011-01-01

     . Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of statistics and country reports on nuclear energy, contains official information provided by OECD member country governments on plans for new nuclear plant construction, nuclear fuel cycle developments as well as current and projected nuclear generating capacity to 2035. For the first time, it includes data for Chile, Estonia, Israel and Slovenia, which recently became OECD members. Key elements of this edition show a 2% increase in nuclear and total electricity production and a 0.5% increase in nuclear generating ca

  14. Nuclear weapons modernizations

    Energy Technology Data Exchange (ETDEWEB)

    Kristensen, Hans M. [Federation of American Scientists, Washington, DC (United States)

    2014-05-09

    This article reviews the nuclear weapons modernization programs underway in the world's nine nuclear weapons states. It concludes that despite significant reductions in overall weapons inventories since the end of the Cold War, the pace of reductions is slowing - four of the nuclear weapons states are even increasing their arsenals, and all the nuclear weapons states are busy modernizing their remaining arsenals in what appears to be a dynamic and counterproductive nuclear competition. The author questions whether perpetual modernization combined with no specific plan for the elimination of nuclear weapons is consistent with the nuclear Non-Proliferation Treaty and concludes that new limits on nuclear modernizations are needed.

  15. Aspectos de diseno de un entorno de programacion colaborativo

    National Research Council Canada - National Science Library

    Rincon, Carlos; Acurero, Alfredo; Bracho, David

    2008-01-01

    ..., estructura e implementacion de este tipo de entornos. Como resultado se obtuvo que desde el punto de vista del diseno, la comunicacion entre desarrolladores, la revision de codigo y la construccion del proyecto de software son los principales aspectos a considerar, y desde el punto de vista de la implementacion se propone utilizar el modelo cliente--servidor y una arquitectura multiplataforma.

  16. 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)

  17. 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)

  18. 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)

  19. 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

  20. Clinical significance of mixed anti-nuclear and anti-cytoplasmic antibody pattern Significado clínico del patrón mixto de anticuerpos (antinucleares y anticitoplsamáticos

    Directory of Open Access Journals (Sweden)

    Robert A. Turner

    1990-01-01

    Full Text Available

    To date, the clinical significance of combined antinuclear (ANA and anti-cytoplasmic (ACA indirect immunofluorescent staining has not been comprehensively studied. ANA + ACA staining was observed in 43 (0.6% out of 7.121 consecutive sera during ANA screening for immunologic disorders in a referral hospital; both inpatient and outpatient population were included. Homogeneous ANA + cytoplasmic was by far the most common staining pattern among 6 different fluorescent combinations detected. Disease distribution was similar in groups of patients with ANA + ACA and in those with only ANA +. We conclude that information provided by mixed antibody pattern is similar to the one obtained with the sole presence of ANA; also that the presence of the mixed pattern does not characterize any particular subgroup of LES patiens.

    Aunque se ha investigado extensamente el significado clínico de los anticuerpos antinucleares (ANA y se han reconocido algunas correlaciones, no está establecido el valor diagnóstico del patrón mixto de ANA y anticitoplasmáticos (ANA + ACA. Nosotros observamos dicho patrón mixto en el suero de 43 pacientes de un total de 7.121 examinados (0.6%. La combinación más común fue con el patrón homogéneo de ANA. Las entidades asociadas al patrón mixto son básicamente las mismas que se asocian con los diferentes ANA; el Lupus Eritematoso Sistémico (LES es la más frecuente. Concluimos que la información obtenida del hallazgo de un patrón combinado ANA + ACA es la misma que se obtiene con los ANA positivos y que su presencia en pacientes con LES no caracteriza a ningún subgrupo de la enfermedad en particular.

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

    Directory of Open Access Journals (Sweden)

    DOMINGO QUILICI

    2013-06-01

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

  3. JPRS Report, Nuclear Developments

    Science.gov (United States)

    2016-03-24

    I Foreign Ministry on Algerian Nuclear Reactor [ZHONGGUO XINWEN SHE] .............................. I...Nuclear Facilities Urged [Seoul YONHAP] .................................................... 5 WPK’s ’Anti- War , Anti-Nuke’ Policy Viewed [KCNA...34 JPRS-TND-91-008 31 May 1991 CHINA 1 Algerian Nuclear Reactor Algeria signed a protocol on nuclear cooperation, in which China agreed

  4. Ensuring Nuclear Safety

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima accident precipitates overall safety inspection by China Guangdong Nuclear Power Holding Corp The Fukushima nuclear accident in Japan had barely made headlines around the world when China Guangdong Nuclear Power Holding Corp.(CGNPC),a nuclear power magnate in China,organized

  5. 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.

  6. Energy from nuclear fission(*

    Directory of Open Access Journals (Sweden)

    Ripani M.

    2015-01-01

    Full Text Available The main features of nuclear fission as physical phenomenon will be revisited, emphasizing its peculiarities with respect to other nuclear reactions. Some basic concepts underlying the operation of nuclear reactors and the main types of reactors will be illustrated, including fast reactors, showing the most important differences among them. The nuclear cycle and radioactive-nuclear-waste production will be also discussed, along with the perspectives offered by next generation nuclear assemblies being proposed. The current situation of nuclear power in the world, its role in reducing carbon emission and the available resources will be briefly illustrated.

  7. [Chilean nuclear policy].

    Science.gov (United States)

    Bobadilla, E

    1996-06-01

    This official document is statement of the President of the Chilean Nuclear Energy Commission, Dr. Eduardo Bobadilla, about the nuclear policy of the Chilean State, Thanks to the international policy adopted by presidents Aylwin (1990-1994) and his successor Frei Ruiz Tagle (1994-), a nuclear development plan, protected by the Chilean entrance to the nuclear weapons non proliferation treaty and Tlatelolco Denuclearization treaty, has started. Chile will be able to develop without interference, an autonomous nuclear electrical system and other pacific uses of nuclear energy. Chile also supports a new international treaty to ban nuclear weapon tests.

  8. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  10. Nuclear energy data 2005

    CERN Document Server

    Publishing, OECD

    2005-01-01

    This 2005 edition of Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of essential statistics on nuclear energy in OECD countries, offers a projection horizon lengthened to 2025 for the first time.  It presents the reader with a comprehensive overview on the status and trends in nuclear electricity generation in OECD countries and in the various sectors of the nuclear fuel cycle.

  11. LA POLITICA SOCIAL DEL "GOBIERNO DEL CAMBIO"

    OpenAIRE

    Laura Mota Díaz

    2002-01-01

    El artículo se centra en la política social del actual sexenio foxista , la cual se ha definido como incluyente y equitativa dentro del marco de un gobierno autodenominado del cambio, no sólo por lo que se refiere a la alternancia política del poder, sino porque además pretende ser un gobierno con una visión más amplia del desarrollo. Todo ello se traduce en nuevas estrategias para alcanzar la democracia, la equidad, la justicia social y el bienestar general de la población. El ob...

  12. 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

  13. Evaluation and mitigation of the degradation by corrosion in the components of the service water system of a nuclear power plant; Evaluacion y mitigacion de la degradacion por corrosion en los componentes del sistema de agua de servicio de una planta nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Salaices A, E.; Salaices, M.; Ovando, R. [IIE, Av. Reforma 113 Col. Palmira, 62490 Cuernavaca, Morelos (Mexico)]. e-mail: sal@iie.org.mx

    2005-07-01

    One of the main problems that face the nuclear power stations is the degradation by corrosion in the service water systems. The corrosion causes lost substantial in energy generation and a high cost in maintenance and repairs. In this work, the results of a study of the degradation by the MIC mechanisms (microorganisms influenced corrosion), incrustations in heat exchangers and erosion for solid particles in the components of a typical service water system of a nuclear plant are presented. Diverse mitigation options are analyzed for these mechanisms. In the analysis, it was used the CHECWORKS-CWA code to carry out the evaluation of the degradation so much as well as the mitigation of the caused damage. The results are presented in susceptibility indexes and degradation rates component-by-component. A significant decrement could be observed in the susceptibility to MIC when changing the operation conditions of stagnated flow to continuous flow. With respect to the erosion by solid particles, it was found a significant reduction of the damage it when adding filters to the system. Finally, in the case of the heat exchangers, it is shown that one of the more viable options to diminish incrustations and existent calcium deposits it is the reduction of the pH of the service water. (Author)

  14. Environmental radioactivity database 1990 - 2016 Nuclear Center “RACSO”

    OpenAIRE

    Osores, José

    2016-01-01

    Se presentan los datos evaluados para el control de radiactividad ambiental en la zona de emplazamiento del Centro Nuclear RACSO, donde opera el reactor nuclear de investigación RP-10. Los datos monitoreados corresponden a radiactividad en el aire, radiactividad en hierbas, radiactividad en aguas fecales, radiactividad en lodos de aguas residuales, radiactividad en superficie de suelo, radiactividad en plantas silvestres y radiactividad en leche para el período comprendido entre los años 199...

  15. Analysis of the microstructural evolution of the damage by neutron irradiation in the pressure vessel of a nuclear power reactor BWR; Analisis de la evolucion microestructural del dano por irradiacion neutronica en la vasija de presion de un reactor nuclear de potencia BWR

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel y R, M.

    2012-07-01

    Nuclear reactor pressure vessel type BWR, installed in Mexico and in many other countries, are made of an alloy of low carbon steel. The American Society for Testing and Materials (Astm) classifies this alloy as A533-B, class 1. Both the vessel and other internal structures are continuously exposed to the neutron flux from the reactions of fission in nuclear fuel. A large number of neutrons reach the vessel and penetrate certain depth depending on their energy. Its penetration in the neutron collides with the nuclei of the atoms out of their positions in the crystal lattice of steel, producing vacancies, interstitial, segregations, among other defects, capable of affecting its mechanical properties. Analyze the micro-structural damage to the vessel due to neutron irradiation, is essential for reasons of integrity of this enclosure and safety of any nuclear power plant. The objective of this thesis work is theoretical and experimentally determine the microstructural damage of a type nuclear reactor vessel steel BWR, due to neutron radiation from the reactor core, using microscopic and spectroscopic techniques as well as Monte Carlo simulation. Microscopy Optical, Scanning Electron Microscopy, Transmission Electron Microscopy, Energy Dispersion of X-rays Spectrometry and X-rays Diffractometry were the techniques used in this research. These techniques helped in the characterization of both the basis of design of pressure vessel steel and steel irradiated, after eight years of neutron irradiation on the vessel, allowing know the surface morphology and crystal structures of the previous steel and post-irradiation, analyze the change in the microstructure of the steel vessel, morphological damage to surface level in an irradiated sample, among which are cavities in the order of microns produced by Atomic displacements due to the impact of neutronic, above all in the first layers of thickness of the vessel, the effect of swelling, regions of greater damage and Atomic

  16. 77 FR 70847 - Entergy Nuclear Indian Point 2, LLC; Entergy Nuclear Operations, Inc., Indian Point Nuclear...

    Science.gov (United States)

    2012-11-27

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Indian Point 2, LLC; Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit No. 2, Request for Action AGENCY: Nuclear Regulatory Commission. ACTION: Request for...

  17. 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)

  18. 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.

  19. Technology Roadmaps: Nuclear Energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This nuclear energy roadmap has been prepared jointly by the IEA and the OECD Nuclear Energy Agency (NEA). Unlike most other low-carbon energy sources, nuclear energy is a mature technology that has been in use for more than 50 years. The latest designs for nuclear power plants build on this experience to offer enhanced safety and performance, and are ready for wider deployment over the next few years. Several countries are reactivating dormant nuclear programmes, while others are considering nuclear for the first time. China in particular is already embarking on a rapid nuclear expansion. In the longer term, there is great potential for new developments in nuclear energy technology to enhance nuclear's role in a sustainable energy future.

  20. Meteorological database 1994 – 2015 Nuclear Center “RACSO”

    OpenAIRE

    Osores, José

    2016-01-01

    Se presenta los datos meteorológicos diarios relativos a la presión atmosférica, temperatura, humedad relativa, dirección y velocidad del viento, de la zona de emplazamiento del Centro Nuclear RACSO, distrito de Carabayllo, provincia de Lima, correspondientes al período 1994 al 31 de diciembre de 2015. El CN RACSO se encuentra ubicado a 410 metros sobre el nivel del mar, a 11°47’45” de latitud sur y 77°00’29”de longitud oeste.

  1. Gramáticas "nucleares" de raíz pragmática ("core grammars" basadas en corpus orales de español nativo y no nativo. A propósito de la investigación de la producción oral por escenarios propuesta en los modelos del Consejo de Europa y el MCER

    Directory of Open Access Journals (Sweden)

    Díaz Rodríguez, Lourdes

    2013-12-01

    ísticas de la lengua en la interacción en situación no solo experimental, por poner algunos ejemplos. (Ver: Díaz, L., 2010, Lenguas de especialidad y su enseñanza, en marcoELE, para algunos ejemplos; Ruiz Fajardo 2012; etc.. Quede constancia del valor de estas miradas como una ventana de facto sobre la lengua real de los nativos, sobre el uso (pragmático real y el encarecimiento de la urgencia de descripciones y explicaciones similares pero para la L2. El reto, por tanto, está servido. Un punto de partida válido lo constituye la aplicación de los métodos de trabajo con corpus a nuevas situaciones de interacción específicas –escenarios– en esta ocasión ya entre nativos y no nativos o exclusivamente entre no nativos, a través de las que empezar a atisbar cómo pueden ser las gramáticas nucleares (core grammars de esas situaciones con vistas a que constituyen el modelo específico para las aulas de lenguas extranjeras.

  2. Nuclear and radiochemistry

    CERN Document Server

    Konya, Jozsef

    2012-01-01

    The field of nuclear and radiochemistry is wide-reaching, with results having functions and use across a variety of disciplines. Drawing on 40 years of experience in teaching and research, this concise book explains the basic principles and applications of the primary areas of nuclear and radiochemistry. Separate chapters cover each main area of recent radiochemistry. This includes nuclear medicine and chemical aspects of nuclear power plants, namely the problems of nuclear wastes and nuclear analysis (both bulk and surface analysis), with the analytical methods based on the interactions of

  3. Nuclear domains and the nuclear matrix.

    Science.gov (United States)

    van Driel, R; Wansink, D G; van Steensel, B; Grande, M A; Schul, W; de Jong, L

    1995-01-01

    This overview describes the spatial distribution of several enzymatic machineries and functions in the interphase nucleus. Three general observations can be made. First, many components of the different nuclear machineries are distributed in the nucleus in a characteristic way for each component. They are often found concentrated in specific domains. Second, nuclear machineries for the synthesis and processing of RNA and DNA are associated with an insoluble nuclear structure, called nuclear matrix. Evidently, handling of DNA and RNA is done by immobilized enzyme systems. Finally, the nucleus seems to be divided in two major compartments. One is occupied by compact chromosomes, the other compartment is the space between the chromosomes. In the latter, transcription takes place at the surface of chromosomal domains and it houses the splicing machinery. The relevance of nuclear organization for efficient gene expression is discussed.

  4. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  5. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Nuclear Medicine? Nuclear medicine is a branch of medical imaging that uses small amounts of radioactive material to ... a radiologist or other physician. To locate a medical imaging or radiation oncology provider in your community, you ...

  6. Nuclear fear revisited

    Science.gov (United States)

    Crease, Robert P.

    2010-10-01

    In 1988 the science historian Spencer Weart published a groundbreaking book called Nuclear Fear: A History of Images, which examined visions of radiation damage and nuclear disaster in newspapers, television, film, literature, advertisements and popular culture.

  7. Triangle Universities Nuclear Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    This report contains brief papers that discusses the following topics: Fundamental Symmetries in the Nucleus; Internucleon Interactions; Dynamics of Very Light Nuclei; Facets of the Nuclear Many-Body Problem; and Nuclear Instruments and Methods.

  8. Theory of nuclear matter

    Energy Technology Data Exchange (ETDEWEB)

    Avakyan, R.M.; Sarkisyan, A.V.

    1987-07-01

    The properties of degenerate stellar matter in the region of nuclear densities are considered. The threshold of the transition of the electron-nucleus phase to the state of continuous nuclear matter is found.

  9. RBC nuclear scan

    Science.gov (United States)

    ... page: //medlineplus.gov/ency/article/003835.htm RBC nuclear scan To use the sharing features on this page, please enable JavaScript. An RBC nuclear scan uses small amounts of radioactive material to ...

  10. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Us News Physician Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine ... physicians diagnose and evaluate medical conditions. These imaging scans use radioactive materials called radiopharmaceuticals or radiotracers . Depending ...

  11. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... its earliest stages as well as a patient’s immediate response to therapeutic interventions. Children's (pediatric) nuclear medicine ... leaving the nuclear medicine facility. Through the natural process of radioactive decay, the small amount of radiotracer ...

  12. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Tell your doctor about your child’s recent illnesses, medical conditions, medications and allergies. Depending on the type ... Nuclear Medicine? Nuclear medicine is a branch of medical imaging that uses small amounts of radioactive material ...

  13. Nuclear disarmament verification

    Energy Technology Data Exchange (ETDEWEB)

    DeVolpi, A.

    1993-12-31

    Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification.

  14. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... of page What are some common uses of the procedure? Children's (pediatric) nuclear medicine imaging is performed ... the thyroid gland. top of page How does the nuclear medicine procedure work? With ordinary x-ray ...

  15. Nuclear air cushion vehicles.

    Science.gov (United States)

    Anderson, J. L.

    1973-01-01

    This paper serves several functions. It identifies the 'state-of-the-art' of the still-conceptual nuclear air cushion vehicle, particularly the nuclear powerplant. Using mission studies and cost estimates, the report describes some of the advantages of nuclear power for large air cushion vehicles. The paper also summarizes the technology studies on mobile nuclear powerplants and conceptual ACV systems/missions studies that have been performed at NASA Lewis Research Center.

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

    Directory of Open Access Journals (Sweden)

    Gerardo Moreno

    2012-02-01

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

  17. Generalized Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    2017-03-15

    This software is code related to reading/writing/manipulating nuclear data in the Generalized Nuclear Data (GND) format, a new format for sharing nuclear data among institutions. In addition to the software and its documentation, notes and documentation from the WPEC Subgroup 43 will be included. WPEC Subgroup 43 is an international committee charged with creating the API for the GND format.

  18. Nuclear fact book

    Energy Technology Data Exchange (ETDEWEB)

    Hill, O. F.; Platt, A. M.; Robinson, J. V. [comps

    1983-05-01

    This reference provides significant highlights and summary facts in the following areas: general energy; nuclear energy; nuclear fuel cycle; uranium supply and enrichment; nuclear reactors; spent fuel and advanced repacking concepts; reprocessing; high-level waste; gaseous waste; transuranic waste; low-level waste; remedial action; transportation; disposal; radiation information; environment; legislation; socio-political aspects; conversion factors; and a glossary. (GHT)

  19. Basic Nuclear Physics.

    Science.gov (United States)

    Bureau of Naval Personnel, Washington, DC.

    Basic concepts of nuclear structures, radiation, nuclear reactions, and health physics are presented in this text, prepared for naval officers. Applications to the area of nuclear power are described in connection with pressurized water reactors, experimental boiling water reactors, homogeneous reactor experiments, and experimental breeder…

  20. Nuclear Power in China

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    China’s vigorous efforts to propel development of nuclear power are paying off as the country’s nuclear power sector advances at an amazing pace. At present, China has set up three enormous nuclear power bases, one each in Qinshan of Zhejiang Province, Dayawan of Guangdong

  1. RETHINKING NUCLEAR POWER SAFETY

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident sounds alarm bells in China’s nuclear power industry In the wake of the Fukushima nucleara ccident caused by the earthquake andt sunami in Japan,the safety of nuclearp ower plants and the development of nuclear power have raised concerns,

  2. Revitalizing Nuclear Safety Research.

    Science.gov (United States)

    National Academy of Sciences - National Research Council, Washington, DC.

    This report covers the general issues involved in nuclear safety research and points out the areas needing detailed consideration. Topics included are: (1) "Principles of Nuclear Safety Research" (examining who should fund, who should conduct, and who should set the agenda for nuclear safety research); (2) "Elements of a Future…

  3. Nuclear energy technology

    Science.gov (United States)

    Buden, David

    1992-01-01

    An overview of space nuclear energy technologies is presented. The development and characteristics of radioisotope thermoelectric generators (RTG's) and space nuclear power reactors are discussed. In addition, the policy and issues related to public safety and the use of nuclear power sources in space are addressed.

  4. Operational tests and irradiation programming proposal for the industrial production of {sup 131} I in the TRIGA Mark III reactor of the Nuclear Centre (ININ); Pruebas operacionales y propuesta de programacion de irradiacion para la produccion industrial de {sup 131} I en el reactor TRIGA Mark III del Centro Nuclear (ININ)

    Energy Technology Data Exchange (ETDEWEB)

    Alanis M, J.; Reyes J, J.L.; Ruiz C, M.A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    In the National Institute of Nuclear Research it was recently finished the project for the production of I-131 at industrial level, the one which can divide basically in: (a) Preparation of the raw materials (TeO{sub 2}), (b) Sintering, (c) Neutron irradiation and (d) Separation of the I-131. With the end of starting the industrial production of this process, in this work it is presented the operational tests and an irradiation proposal of the TeO{sub 2} to obtain quantities of I-131 that cover, if not totally, partially the national market. For this, they were carried out irradiation tests of 6 samples to different flows of neutrons. The result of these tests settles down that irradiating a mass of 240 g TeO{sub 2} to a neutron flow of 6.53 x 10{sup 12} n/cm{sup 2}s in 4 cycles of 30 h per week approximately 2.54 Ci/week of I-131 distilled are obtained, which represents 35% of the demand of the Plant of Radioisotopes production of the ININ. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-10-15

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

  6. Las catástrofes nucleares y el desplazamiento

    OpenAIRE

    Meybatyan, Silva

    2014-01-01

    Las enseñanzas que podemos extraer del accidente nuclear de Fukushima en 2011 parece que son las mismas que en Chernóbil veinticinco años antes, pese a ser entornos políticos diferentes. Por lo visto no hemos aprendido mucho.

  7. Estudio del comportamiento acustico de recubrimientos de suelo derivados de la madera

    Science.gov (United States)

    Gadea Borrell, Jose Maria

    This work describes a study of the vibroacoustic behaviour of laminate flooring and is partly accomplished by means of an experimental method somewhat simpler than that normally used at the present time and partly by a hybrid FEM-FDTD numerical method that reproduces the proposed experiment. The experimental configuration records the sounds emitted by laminate floors when impacted and the numerical method allows the sound produced by the laminate floor to be determined before installation by previously reproducing its sound. The registers obtained from both methods are evaluated from the psychoacoustic perspective with the aim of determining the relevant parameters involved in their perception, and thus provide a method of distinguishing the effect of the different component materials on the sound produced by this type of floor covering. In the field of building acoustics, with which this work is involved, laminate flooring is seen as a good solution for deadening the noise of impacts. This question has now become important due to stricter building acoustic regulations (DB-HR Proteccion frente al ruido" del Codigo Tecnico de la Edificacion, CTE). Laminate floors possess the advantage that they can be installed over existing floor coverings. Their lightness, which adds little additional strain to structures, and the fact that they are easy to fit, make them an attractive solution at the present time and gives them promising prospects for the future. Of the different types available, synthetic laminate floors are now the most popular by far in almost all types of building and for this reason research is being carried out on the users' opinion of their quality and convenience. Among the factors that affect the latter quality is their acoustic behaviour as regards both the insulation of sound transmitted to neighbouring rooms and the sound reflected from the floor in the room in which it is installed. The conclusions reached in this work are related to the latter

  8. Relation between nuclear envelope and nuclear lamina in nuclear assembly in vitro

    Institute of Scientific and Technical Information of China (English)

    蔡树涛; 翟中和

    1997-01-01

    Xenopus laevis egg extracts cell-free nuclear assembly system was used as an experimental model to study the process of nuclear lamina assembly in nuclear reconstitution in vitro. The experimental results showed that lamin was involved in the nuclear assembly in vitro. The assembly of nuclear lamina was preceded by the assembly of nuclear matrix, and probably, inner nuclear matrix assembly provided the basis for nuclear lamina assembly. Inhibition of normal assembly of nuclear lamina, by preincubating egg extracts cell-free system with anti-lamin antibodies, resulted in abnormal assembly of nuclear envelope, suggesting that nuclear envelope assembly is closely associated with nuclear lamina assembly.

  9. Activities report in nuclear physics

    NARCIS (Netherlands)

    Jansen, J. F. W.; Scholten, O.

    1987-01-01

    Experimental studies of giant resonances, nuclear structure, light mass systems, and heavy mass systems are summarized. Theoretical studies of nuclear structure, and dynamics are described. Electroweak interactions; atomic and surface physics; applied nuclear physics; and nuclear medicine are discus

  10. Automation of the computational programs and codes used in the methodology of neutronic and thermohydraulic calculation for the IEA-R1 nuclear reactor; Automatizacao dos programas e codigos computacionais utilizados na metodologia de calculo neutronico e termohidraulico do reator nuclear IEA-R1

    Energy Technology Data Exchange (ETDEWEB)

    Stefani, Giovanni Laranjo de, E-mail: gstefani@ipen.b [Universidade de Sao Paulo (USP), SP (Brazil). Inst. de Fisica; Conti, Thadeu das Neves, E-mail: tnconti@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2009-07-01

    This work proceeds the elaboration of a computational program for execution of various neutron and thermalhydraulic calculation methodology programs of the IEA-R1-Sao Paulo, Brazil, making the process more practical and safe, besides transforming de output data of each program an automatic process. This reactor is largely used for production of radioisotopes for medical use, material irradiation, personnel training and also for basic research. For that purposes it is necessary to change his core configuration in order to adapt the reactor for different uses. The work will transform various existent programs into subroutines of a principal program, i.e.,a program which call each of the programs automatically when necessary, and create another programs for manipulation the output data and therefore making practical the process

  11. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

  12. Nuclear Egress of Herpesviruses

    Institute of Scientific and Technical Information of China (English)

    Richard J.Roller

    2008-01-01

    Herpesviruses assemble and fill their capsids in the infected cell nucleus,and must then move this enormous macromolecular assembly across the nuclear membrane and into the cytoplasm.Doing so is a complex,multi-step process that involves envelopment of the capsid at the inner nuclear membrane and de-envelopment by fusion with the outer nuclear membrane.This process is orchestrated by viral proteins,but requires the modification of cellular structures and mechanisms including the nuclear lamina.In this review I summarize recent research on the mechanism of nuclear envelopment and the viral and cellular systems involved in its execution.

  13. Nuclear parton distributions

    Directory of Open Access Journals (Sweden)

    Kulagin S. A.

    2017-01-01

    Full Text Available We review a microscopic model of the nuclear parton distribution functions, which accounts for a number of nuclear effects including Fermi motion and nuclear binding, nuclear meson-exchange currents, off-shell corrections to bound nucleon distributions and nuclear shadowing. We also discuss applications of this model to a number of processes including lepton-nucleus deep inelastic scattering, proton-nucleus Drell-Yan lepton pair production at Fermilab, as well as W± and Z0 boson production in proton-lead collisions at the LHC.

  14. Nuclear energy; Le nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    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.)

  15. Nuclear education and training

    CERN Document Server

    2012-01-01

    The OECD Nuclear Energy Agency (NEA) first published in 2000 Nuclear Education and Training: Cause for Concern? , which highlighted significant issues in the availability of human resources for the nuclear industry. Ten years on, Nuclear Education and Training: From Concern to Capability considers what has changed in that time and finds that, while some countries have taken positive actions, in a number of others human resources could soon be facing serious challenges in coping with existing and potential new nuclear facilities. This is exacerbated by the increasing rate of retirement as the w

  16. Consideraciones alrededor del Libro del Almismo, el Libro del Pensar.

    OpenAIRE

    MartaLucía Tamayo Fernandez

    1999-01-01

    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” qu...

  17. History of Nuclear India

    Science.gov (United States)

    Chaturvedi, Ram

    2000-04-01

    India emerged as a free and democratic country in 1947, and entered into the nuclear age in 1948 by establishing the Atomic Energy Commission (AEC), with Homi Bhabha as the chairman. Later on the Department of Atomic Energy (DAE) was created under the Office of the Prime Minister Jawahar Lal Nehru. Initially the AEC and DAE received international cooperation, and by 1963 India had two research reactors and four nuclear power reactors. In spite of the humiliating defeat in the border war by China in 1962 and China's nuclear testing in 1964, India continued to adhere to the peaceful uses of nuclear energy. On May 18, 1974 India performed a 15 kt Peaceful Nuclear Explosion (PNE). The western powers considered it nuclear weapons proliferation and cut off all financial and technical help, even for the production of nuclear power. However, India used existing infrastructure to build nuclear power reactors and exploded both fission and fusion devices on May 11 and 13, 1998. The international community viewed the later activity as a serious road block for the Non-Proliferation Treaty and the Comprehensive Test Ban Treaty; both deemed essential to stop the spread of nuclear weapons. India considers these treaties favoring nuclear states and is prepared to sign if genuine nuclear disarmament is included as an integral part of these treaties.

  18. The nuclear symmetry energy

    Science.gov (United States)

    Baldo, M.; Burgio, G. F.

    2016-11-01

    The nuclear symmetry energy characterizes the variation of the binding energy as the neutron to proton ratio of a nuclear system is varied. This is one of the most important features of nuclear physics in general, since it is just related to the two component nature of the nuclear systems. As such it is one of the most relevant physical parameters that affect the physics of many phenomena and nuclear processes. This review paper presents a survey of the role and relevance of the nuclear symmetry energy in different fields of research and of the accuracy of its determination from the phenomenology and from the microscopic many-body theory. In recent years, a great interest was devoted not only to the Nuclear Matter symmetry energy at saturation density but also to its whole density dependence, which is an essential ingredient for our understanding of many phenomena. We analyze the nuclear symmetry energy in different realms of nuclear physics and astrophysics. In particular we consider the nuclear symmetry energy in relation to nuclear structure, astrophysics of Neutron Stars and supernovae, and heavy ion collision experiments, trying to elucidate the connections of these different fields on the basis of the symmetry energy peculiarities. The interplay between experimental and observational data and theoretical developments is stressed. The expected future developments and improvements are schematically addressed, together with most demanded experimental and theoretical advances for the next few years.

  19. Dynamic nuclear spin polarization

    Energy Technology Data Exchange (ETDEWEB)

    Stuhrmann, H.B. [GKSS-Forschungszentrum Geesthacht GmbH (Germany)

    1996-11-01

    Polarized neutron scattering from dynamic polarized targets has been applied to various hydrogenous materials at different laboratories. In situ structures of macromolecular components have been determined by nuclear spin contrast variation with an unprecedented precision. The experiments of selective nuclear spin depolarisation not only opened a new dimension to structural studies but also revealed phenomena related to propagation of nuclear spin polarization and the interplay of nuclear polarisation with the electronic spin system. The observation of electron spin label dependent nuclear spin polarisation domains by NMR and polarized neutron scattering opens a way to generalize the method of nuclear spin contrast variation and most importantly it avoids precontrasting by specific deuteration. It also likely might tell us more about the mechanism of dynamic nuclear spin polarisation. (author) 4 figs., refs.

  20. Overview of nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Firestone, R.B.

    2003-06-30

    For many years, nuclear structure and decay data have been compiled and disseminated by an International Network of Nuclear Structure and Decay Data (NSDD) evaluators under the auspices of the International Nuclear Data Committee (INDC) of the International Atomic Energy Agency (IAEA). In this lecture I will discuss the kinds of data that are available and describe various ways to obtain this information. We will learn about some of the publications that are available and Internet sources of nuclear data. You will be introduced to Isotope Explorer software for retrieving and displaying nuclear structure and radioactive decay data. The on-line resources Table of Radioactive Isotopes, PGAA Database Viewer, Nuclear Science Reference Search, Table of Isotopes Educational Website, and other information sources will be discussed. Exercises will be provided to increase your ability to understand, access, and use nuclear data.

  1. Cold nuclear fusion

    Directory of Open Access Journals (Sweden)

    Huang Zhenqiang Huang Yuxiang

    2013-10-01

    Full Text Available In normal temperature condition, the nuclear force constraint inertial guidance method, realize the combination of deuterium and tritium, helium and lithium... And with a magnetic moment of light nuclei controlled cold nuclear collide fusion, belongs to the nuclear energy research and development in the field of applied technology "cold nuclear collide fusion". According to the similarity of the nuclear force constraint inertial guidance system, the different velocity and energy of the ion beam mixing control, developed ion speed dc transformer, it is cold nuclear fusion collide, issue of motivation and the nuclear power plant start-up fusion and power transfer system of the important equipment, so the merger to apply for a patent

  2. Bibliografía

    Directory of Open Access Journals (Sweden)

    Juan Arce Murgia

    1964-12-01

    Full Text Available NOCIONES DE DER'f.lCHO PROCESAL Y COMENTO DEL CODIGO DEPROCEDIMIENTOS CIVILES, por el Doctor REMIGIO PINO CARPIOOBJETIVO DE LA POLITICA TRIBUTARIA NACIONAL.-Imprenta de laUniversidad Nacional Mayor de San Marcos.-Lima 1964; por MANUEL.BELAUNDE GUINASSI.-

  3. Índice General. Revista Con-texto

    National Research Council Canada - National Science Library

    Jose Manuel Alvarez

    2014-01-01

    ... al Codigo Oivil argentino de 1998 8 Homero Cuevas Sex and reason de Richard a. Posner 9 Carlos A. Ghersi El Derecho de chance. Fundamentacion epistemologica economica 9 Pietro Milazzo El regimen de procesos concursales colombiano entro en concordato ... 10 Edigson Perez y jaime osorio El futuro del sector petrolero en Colombia 10 javier Lop...

  4. 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

  5. Efficiency of the low energy detection system for the measurement of {sup 235} U in lung of the Nuclear Regulatory Authority; Eficiencia del sistema de deteccion de baja energia para la medicion de {sup 235} U en pulmon de la Autoridad Regulatoria Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Spinella, M.R.; Krimer, M.; Gregori, B.N.; Rojo, A.M. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250 (C1429BNP), Buenos Aires (Argentina)]. e-mail: mspinell@cae.arn.gov.ar

    2006-07-01

    This work presents the results of the calibration process of the detection system of {sup 235} U in lung of the Nuclear Regulatory Authority. The phantom used in the calibration is the denominated Lawrence Livermore Realistic Phantom, provided of lungs and active nodules and of 4 thoracic covers that its simulate muscular tissue with thickness that vary between 1.638 and 3.871 cm. The spectra are acquired by four detecting of denominated LEGe ACTII Canberra marks, each one with an active area of 3800 mm{sup 2}, a diameter of 70 mm and a thickness of 20 mm, the sign is processed by a SYSTEM100 multichannel and the spectra are analyzed with the GENIE2K program. The detectors are suspended by mobile structures that allow to vary the position with regard to a horizontal stretcher that defines the measurement geometry. The whole system is located in the interior of an armored enclosure of 200 x 150 x 200 cm{sup 3} of steel of 15 cm thickness, inside recovered with layers of 0.5 cm lead and 0.05 cm cadmium. The total weight of the enclosure is 40 ton. For the described system the efficiency curves versus muscular thoracic tissue thickness (ETM) corresponding to the energy of 143.76, 163.358 and 185.72 keV of the {sup 235} U radioisotope were obtained. Its were also practiced displacements of those detectors of approximately 1 cm with respect to the reference position and its were analyzed the corresponding changes of magnitude in the efficiencies. The obtained variations oscillate, for vertical displacements, between 5% and 7.8% for the smallest value in ETM (1.638 cm) and between 4.2% to 6.7% for the ETM 3.871 cm. While for the practiced lateral displacements, the variations go from 4% to 15%. The detection limits corresponding to each energy and thickness were determined. The results showed for the photopeak of 185.72 keV, the more outstanding in the evaluations that saying limit it oscillates between 3.7 and 6.4 Bq {sup 235} U inside the considered thickness range

  6. Del territorio del sujeto al emplazamiento del Común

    Directory of Open Access Journals (Sweden)

    Mariano Adrían Ferretti

    2016-01-01

    Full Text Available La construcción de lo público abarca una variedad de dinámicas que condicionan el resultado físico de los espacios donde actúan los individuos en sus necesidades de habitar, modificando su realidad desde la diferenciación y la singularización subjetiva del entorno que derivan en nuevas formas de territorialidad de lo público a partir de la dialéctica entre lo público y lo privado. Sin embargo, los resultados de tales representaciones entendidas como acciones colectivas –y por tanto comunes- no siempre explican los valores que desde lo simbólico partiendo del sujeto constituyan un estatus diferente de lo público en los procesos de territorialización. Se propone una aproximación que aborde de manera teórica cuestiones tales como: los vínculos del individuo con los procesos de acumulación material y transformación del territorio y las implicaciones que dichos fenómenos tienen en la posibilidad de constitución de un sujeto que trascendiendo al individuo sea capaz de conformar un nuevo estatus del sujeto o, dicho de otro modo, un emplazamiento del Común.

  7. 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.

  8. 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)

  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. 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)

  11. 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)

  12. 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)

  13. 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)

  14. Pre-test simulation of the CIP3-1 experiment of the CABRI water loop with FRAPCON-3.4a and FRAPTRAN 1.4 codes; Simulacion pre-test del experimento CIP-1 del proyecto CABRI Lazo de agua con los codigos FRAPCON-3,4 y FRAPTRAN 1.4

    Energy Technology Data Exchange (ETDEWEB)

    Vallejo, I.; Huguet, A.; Herranz, L. E.

    2010-07-01

    The main objective of this paper is to estimate the thermomechanical behavior expected of the bar part during the reactivity insertion CIP3-1 experiment, that will be done in the new CABRI facility. these pre-test calculations provide an experimental support to find out about the results expected according to the current capabilities of simulation codes.

  15. The Nuclear Symmetry Energy

    CERN Document Server

    Baldo, M

    2016-01-01

    The nuclear symmetry energy characterizes the variation of the binding energy as the neutron to proton ratio of a nuclear system is varied. This is one of the most important features of nuclear physics in general, since it is just related to the two component nature of the nuclear systems. As such it is one of the most relevant physical parameters that affect the physics of many phenomena and nuclear processes. This review paper presents a survey of the role and relevance of the nuclear symmetry energy in different fields of research and of the accuracy of its determination from the phenomenology and from the microscopic many-body theory. In recent years, a great interest was devoted not only to the Nuclear Matter symmetry energy at saturation density but also to its whole density dependence, which is an essential ingredient for our understanding of many phenomena. We analyze the nuclear symmetry energy in different realms of nuclear physics and astrophysics. In particular we consider the nuclear symmetry ene...

  16. Nuclear energy efficiency improvements

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; Nonboel, E. [Technical Univ. of Denmark. DTU Nutech, Roskilde (Denmark); Kyrki-Rajamaeki, R. [Lappeenranta Univ. of Technology (Finland)

    2012-11-15

    Nuclear energy already today plays an important role in decarbonisation of the electricity sector while providing energy security and being economically competitive. Nuclear energy is characterized by its very high energy density and is well suited for large-scale, baseload electricity supply. Similar to renewable energy sources such as wind, solar or biomass, nuclear power is characterized by an abundant supply of its primary energy source, uranium, but is not limited to the same extent as these renewable energy sources from being an intermittent energy supply or imposing severe restrictions on land-use. Improving energy efficiency of nuclear power plants has contributed to a better utilization of the uranium resources and has helped improving the economic performance of nuclear power plants. This is to a large degree accomplished through optimisation of nuclear fuel assemblies as well as renewing turbines and generators. More importantly however, the overall economy of nuclear power has improved though better plant management leading to higher capacity factors and by extending the lifetimes of existing nuclear power plants. Provided that improved safety, economics and successful waste management can be demonstrated nuclear power is likely to grow in the future. Non-electricity applications may further boost the growth of nuclear energy, especially with the development of new reactor systems allowing for cogeneration of electricity and hydrogen or biofuels for transport. (Author)

  17. Historia del genoma humano

    OpenAIRE

    Castaño Valencia, Óscar

    2006-01-01

    En 1990 el Doctor Charles de Lisi presentó el proyecto del GENOMA HUMANO en asocio del Instituto de Salud Americano, el Instituto Whithead de Cambridge, la Universidad de Washingtong, el Colegio Médico de Baylor y el Instituto del Genoma Humano, de California.Estos organismos han venido actuando desde esa época, contando con la financiación de los gobiernos del Japón, Alemania, Francia, China y naturalmente del americano.En sus fases iniciales fue orientado por el Dr. James Watson quien contó...

  18. Los nudos del sistema

    OpenAIRE

    2000-01-01

    Pieza central del antiguo régimen; pacto, acuerdo o trato con algunos actores decisivos del sistema político susceptible de ser revisado; forma cultural de relaciones de poder o de intercambio; pirámide de organizaciones o estructura sectorial: ¿qué tan invisible sigue siendo, qué tan montada sigue estando la pirámide del corporativismo mexicano antes y después del 2 de julio de 2000? Este fenómeno constituye el eje central de las reflexiones del presente ensayo. En torno al mismo, se pres...

  19. Nuclear energy - some aspects; Energia nuclear - alguns aspectos

    Energy Technology Data Exchange (ETDEWEB)

    Bandeira, Fausto de Paula Menezes

    2005-05-15

    This work presents a brief history of research and development concerning to nuclear technology worldwide and in Brazil, also information about radiations and radioactive elements as well; the nuclear technology applications; nuclear reactor types and functioning of thermonuclear power plants; the number of existing nuclear power plants; the nuclear hazards occurred; the national fiscalization of nuclear sector; the Brazilian legislation in effect and the propositions under proceduring at House of Representatives related to the nuclear energy.

  20. Development of a gamma ray spectrometry software for neutron activation analysis using the open source concept; Desenvolvimento de um software de espectrometria gama para analise por ativacao com neutrons utilizando o conceito de codigo livre

    Energy Technology Data Exchange (ETDEWEB)

    Lucia, Silvio Rogerio de

    2008-07-01

    This study developed a specific software for gamma ray spectra analysis for researchers of the Neutron Activation Laboratory (LAN), which was named SAANI (Instrumental Neutron Activation Analysis Software). The LAN laboratory of the Institute for Research and Nuclear Energy (IPEN-CNEN/SP), uses a multielemental analytical technique, based on irradiation of a sample by a flux of neutrons from a nuclear reactor, which induces radioactivity. The sample is then placed in a gamma-ray spectrometer, to obtain the spectrum. With free software philosophy in mind, this software will replace the existing software VISPECT / VERSION 2. The new software's main features are: a friendlier interface; easier standardization procedure carried out by LAN staff and researchers; adapted to the use of plug technology; multi platform and code free. The software was developed using the programming Python language, the library Trolltech Qt graphics and some of their scientific extensions. Preliminary results using the SANNI software were compared to those obtained with the existing software and were considered good. There were some errors in accuracy during the implementation of the software. The SAANI software has been installed in selected computers to be used for routine analysis in order to verify its strength, accuracy and usability. (author)

  1. Thermomechanical analysis of a fuel rod in a BWR reactor using the FUELSIM code; Analisis termomecanico de una barra de combustible de un reactor BWR utilizando el codigo FUELSIM

    Energy Technology Data Exchange (ETDEWEB)

    Pantoja C, R. [Escuela Superior de Fisica y Matematicas, Departamento de Ingenieria Nuclear, IPN, Av. Instituto Politecnico Nacional s/n, Col. San Pedro Zacatenco, 07738 Mexico, D. F. (Mexico); Ortiz V, J.; Araiza M, E. [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: rapaca78@yahoo.com.mx

    2009-10-15

    The thermomechanical behaviour of a fuel rod exposed to irradiation is a complex process in which are coupled great quantity of interrelated physical-chemical phenomena, for that analysis of rod performance in the core of a nuclear power reactor is realized generally with computation codes that integrate several phenomena expected during the time life of fuel rod in the core. An application of this type of thermomechanical codes is to predict, inside certain reliability margin, the design parameters that would be required to adjust, in order to get a better economy or rod performance, for a systematic approach to the fuel design optimization. FUELSIM is a thermomechanical code based on the models of FRAPCON code, which was developed under auspice of Nuclear Regulatory Commission of USA. FUELSIM allows iterative calculations like part of its programming structure, allowing search of extreme cases of behaviour, probabilistic analysis (or statistical), parametric analysis (or sensibility) and also can include as entrance data to the uncertainties associated with production data, code parameters and associated models. In this work is reported a first analysis of thermomechanical performance of a typical fuel rod used in a BWR 5/6. Results of maximum temperatures are presented in the fuel center and of axial deformation, for the 10 axial nodes in that the active longitude of fuel rod was divided. (Author)

  2. 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)

  3. 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)

  4. 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)

  5. Nuclear Threats and Security

    Directory of Open Access Journals (Sweden)

    Garry Jacobs

    2012-10-01

    Full Text Available This article presents highlights and insights from the International Conference on “Nuclear Threats and Security” organized by the World Academy of Art and Science in association with the European Leadership Network and the Dag Hammarskjöld University College of International Relations and Diplomacy and sponsored by NATO at the Inter-University Centre, Dubrovnik on September 14-16, 2012. The conference examined important issues related to nuclear non-proliferation and disarmament, the legality of nuclear weapons and their use, illicit trade in nuclear materials, the dangers of nuclear terrorism, nuclear- and cyber-security. Papers and video recordings of the major presentations and session summaries can be found here.

  6. Safety and nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Gittus, John; Gunning, Angela.

    1988-05-01

    Representatives of the supporters and opponents of civil nuclear power put forward the arguments they feel the public should consider when making up their mind about the nuclear industry. The main argument in favour of nuclear power is about the low risk in comparison with other risks and the amount of radiation received on average by the population in the United Kingdom from different sources. The aim is to show that the nuclear industry is fully committed to the cause of safety and this has resulted in a healthy workforce and a safe environment for the public. The arguments against are that the nuclear industry is deceitful, secretive and politically motivated and thus its arguments about safety, risks, etc, cannot be trusted. The question of safety is considered further - in particular the perceptions, definitions and responsibility. The economic case for nuclear electricity is not accepted. (U.K.).

  7. Nuclear power industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-04-28

    This press dossier presented in Shanghai (China) in April 1999, describes first the activities of the Framatome group in the people`s republic of China with a short presentation of the Daya Bay power plant and of the future Ling Ao project, and with a description of the technological cooperation with China in the nuclear domain (technology transfers, nuclear fuels) and in other industrial domains (mechanics, oil and gas, connectors, food and agriculture, paper industry etc..). The general activities of the Framatome group in the domain of energy (nuclear realizations in France, EPR project, export activities, nuclear services, nuclear fuels, nuclear equipments, industrial equipments) and of connectors engineering are presented in a second and third part with the 1998 performances. (J.S.)

  8. Nuclear Power Feasibility 2007

    OpenAIRE

    Aragonés Beltrán, José María; Hill, Barrie Frederick; Kadak, Andrew C.; Shultz, Donald F.; Spitalnik, Jorge

    2008-01-01

    Nuclear power is a proven technology and has the potential to generate virtually limitless energy with no significant greenhouse gas emissions. Nuclear power can become one of the main options to contribute to substantial cuts in global greenhouse gas emissions. Modern development of nuclear power technology and the established framework of international agreements and conventions are responding to the major political, economic and environmental issues -high capital costs, the risks posed by ...

  9. Absolute nuclear material assay

    Science.gov (United States)

    Prasad, Manoj K [Pleasanton, CA; Snyderman, Neal J [Berkeley, CA; Rowland, Mark S [Alamo, CA

    2012-05-15

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

  10. Nuclear spirals in galaxies

    OpenAIRE

    Maciejewski, Witold

    2006-01-01

    Recent high-resolution observations indicate that nuclear spirals are often present in the innermost few hundred parsecs of disc galaxies. My models show that nuclear spirals form naturally as a gas response to non-axisymmetry in the gravitational potential. Some nuclear spirals take the form of spiral shocks, resulting in streaming motions in the gas, and in inflow comparable to the accretion rates needed to power local Active Galactic Nuclei. Recently streaming motions of amplitude expected...

  11. Nonstrategic Nuclear Weapons

    Science.gov (United States)

    2014-01-03

    William Potter , and Nikolai Sokov, Reducing and Regulating Tactical (Nonstrategic) Nuclear Weapons in Europe, The James Martin Center For...See William C. Potter and Nikolai Sokov, “Nuclear Weapons that People Forget,” International Herald Tribune, May 31, 2000. 87 Sam Nunn, Igor...their security.97 94 Kent Harris , “NATO Allies Want U.S. Nuclear Weapons out of Europe

  12. Nuclear Fabrication Consortium

    Energy Technology Data Exchange (ETDEWEB)

    Levesque, Stephen [EWI, Columbus, OH (United States)

    2013-04-05

    This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) Office of Nuclear Energy (NE) for the management and operation of the Nuclear Fabrication Consortium (NFC). The NFC was established by EWI to independently develop, evaluate, and deploy fabrication approaches and data that support the re-establishment of the U.S. nuclear industry: ensuring that the supply chain will be competitive on a global stage, enabling more cost-effective and reliable nuclear power in a carbon constrained environment. The NFC provided a forum for member original equipment manufactures (OEM), fabricators, manufacturers, and materials suppliers to effectively engage with each other and rebuild the capacity of this supply chain by : Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. Providing and facilitating detailed scientific-based studies on new approaches and technologies that will have positive impacts on the cost of building of nuclear plants. Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. Supporting industry in helping to create a larger qualified nuclear supplier network. Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. Serving as a focal point for technology, policy, and politically interested parties to share ideas and concepts associated with fabrication across the nuclear industry. The report the objectives and summaries of the Nuclear Fabrication Consortium

  13. Nuclear South Asia

    Science.gov (United States)

    2007-11-02

    nuclear equation in South Asia, the geopolitical and geoeconomic realities will keep China out of the South Asian nuclear picture. As Pakistan...remain unipolar for quite some time with the United States as the global superpower. There is predominance of geoeconomics as against geopolitical...to drag China into the nuclear equation in South Asia, the geopolitical and geoeconomic realities will likely keep China out of the South Asian

  14. Facilitating Global Nuclear Disarmament

    Institute of Scientific and Technical Information of China (English)

    Wu; Junr

    2014-01-01

    <正>I.Introduction Since the advent of nuclear weapons,especially after the United States dropped atomic bombs in Hiroshima and Nagasaki,the capacity of massive and indiscriminate annihilation of nuclear weapons have made people of insight across the world realize that such weapons cannot be used arbitrarily.In the 1960s,the then Chinese leader Mao Zedong said that to throw them(nuclear weapons)about at will is committing a

  15. Nuclear electronic instrumentation; Instrumentacion electronica nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez J, F. J., E-mail: francisco.ramirez@inin.gob.m [ININ, Departamento de Sistemas Electronicos, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-07-01

    The activities carried out in the Instituto Nacional de Investigaciones Nucleares (ININ) in the field of the nuclear electronic instrumentation included those activities corresponding to the design and production of nuclear instruments in a first stage, as well as the internal activities of design, repair and maintenance that have supported to other projects of the institution during many years. It is mentioned of the presence and constant collaboration of the ININ with the IAEA in different projects and programs. Also, it is mentioned on the establishment of the Radiation Detectors Laboratory, which for their characteristics and repair capacities of radiation detectors of cooled semiconductor, it is only in their specialty. It is emphasized the investigation and the development in the field of new radiation detectors and applications, as well as the important contribution in this field, in institutions like: Mexican Petroleum, National Commission of Nuclear Safety and Safeguards and Federal Commission of Electricity. Finally a position of the future of these activities is made, considering the speed of the advances of the electronic and nuclear technology. (Author)

  16. Nuclear medicine physics

    CERN Document Server

    De Lima, Joao Jose

    2011-01-01

    Edited by a renowned international expert in the field, Nuclear Medicine Physics offers an up-to-date, state-of-the-art account of the physics behind the theoretical foundation and applications of nuclear medicine. It covers important physical aspects of the methods and instruments involved in modern nuclear medicine, along with related biological topics. The book first discusses the physics of and machines for producing radioisotopes suitable for use in conventional nuclear medicine and PET. After focusing on positron physics and the applications of positrons in medicine and biology, it descr

  17. Nuclear safety in perspective

    Directory of Open Access Journals (Sweden)

    J. K. Basson

    1983-03-01

    Full Text Available The impending operation of South Africa’s first nuclear power station, Koeberg, necessitates a thorough analysis of nuclear safety under local conditions. More is known, worldwide, about radiation effects than about any other health hazard, and international norms have already been accepted since 1928. The widespread use of X-rays and radio-isotopes, the extraction and processing of uranium, visits by nuclear-powered ships and, especially, the nuclear-reactor operation in South Africa. Consequently, the pre-operational investigations of Koeberg could be completed thoroughly, with full confidence in its safe commissioning.

  18. Nuclear level density predictions

    Directory of Open Access Journals (Sweden)

    Bucurescu Dorel

    2015-01-01

    Full Text Available Simple formulas depending only on nuclear masses were previously proposed for the parameters of the Back-Shifted Fermi Gas (BSFG model and of the Constant Temperature (CT model of the nuclear level density, respectively. They are now applied for the prediction of the level density parameters of all nuclei with available masses. Both masses from the new 2012 mass table and from different models are considered and the predictions are discussed in connection with nuclear regions most affected by shell corrections and nuclear structure effects and relevant for the nucleosynthesis.

  19. Nuclear power in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Gittus, J. (British Nuclear Forum, London (UK))

    1991-04-01

    The 1990s are turning out to be a most crucial phase for the nuclear industries of Europe. A time of uncertainty, as well as considerable opportunity, lies ahead. Despite a measure of public and political opposition to nuclear power, many are beginning to realise that, as a method of generating electricity that produces only 1% of greenhouse gases compared to coal per unit of electricity, nuclear energy may be the best alternative to the burning of fossil fuels. Although advances have been made in renewable energy, nuclear power is still the main non-fossil fuel source that can cope with today's energy demands. (author).

  20. Nuclear medium effects in $\

    CERN Document Server

    Haider, H; Athar, M Sajjad; Vacas, M J Vicente

    2011-01-01

    We study the nuclear medium effects in the weak structure functions $F_2(x,Q^2)$ and $F_3(x,Q^2)$ in the deep inelastic neutrino/antineutrino reactions in nuclei. We use a theoretical model for the nuclear spectral functions which incorporates the conventional nuclear effects, such as Fermi motion, binding and nucleon correlations. We also consider the pion and rho meson cloud contributions calculated from a microscopic model for meson-nucleus self-energies. The calculations have been performed using relativistic nuclear spectral functions which include nucleon correlations. Our results are compared with the experimental data of NuTeV and CDHSW.