WorldWideScience

Sample records for reactors algoritmos bio-inspirados

  1. Desarrollo de una aplicación para la gestión, clasificación y agrupamiento de documentos económicos con algoritmos bio-inspirados

    OpenAIRE

    Cobo Ortega, Ángel; Rocha Blanco, Eliana Rocío

    2007-01-01

    Este trabajo describe el desarrollo de una aplicación Web que utiliza técnicas bio-inspiradas para clasificar y agrupar colecciones multilingües de documentos en el campo de la economía y los negocios. La aplicación identifica grupos relacionados de documentos económicos, escritos en español e ingles, utilizando algoritmos de clustering inspirados en el comportamiento de las colonias de hormigas. Para la generación de una representación vectorial de los documentos que resulte independiente de...

  2. Desarrollo de una aplicación para la gestión, clasificación y agrupamiento de documentos económicos con algoritmos bio-inspirados

    Directory of Open Access Journals (Sweden)

    Rocha Blanco, Rocío

    2007-01-01

    Full Text Available Este trabajo describe el desarrollo de una aplicación Web que utiliza técnicas bio-inspiradas para clasificar y agrupar colecciones multilingües de documentos en el campo de la economía y los negocios. La aplicación identifica grupos relacionados de documentos económicos, escritos en español e ingles, utilizando algoritmos de clustering inspirados en el comportamiento de las colonias de hormigas. Para la generación de una representación vectorial de los documentos que resulte independiente del idioma, se utilizan varios recursos lingüísticos y herramientas de procesamiento de documentos textuales. Cada documento es representado utilizando cuatro vectores de rasgos independientes del idioma, y la similitud entre ellos es calculada mediante combinaciones lineales convexas de las similitudes de esos vectores de rasgos. El trabajo presenta resultados experimentales obtenidos en la clasificación de un corpus de 250 documentos científicos en diversas áreas de la economía y administración de empresas.

  3. Algorithms bio-inspired for the pattern obtention of control bars in BWR reactors; Algoritmos bio-inspirados para la obtencion de patrones de barras de control en reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz, J.J.; Perusquia, R.; Montes, J.L. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    In this work methods based on Genetic Algorithms and Systems based on ant colonies for the obtention of the patterns of control bars of an equilibrium cycle of 18 months for the Laguna Verde nuclear power station are presented. A comparison of obtained results with the methods and with those of design of such equilibrium cycle is presented. As consequence of the study, it was found that the algorithm based on the ant colonies reached to diminish the coast down period (decrease of power at the end of the cycle) in five and half days with respect to the original design what represents an annual saving of $US 100,000. (Author)

  4. Improvement to the pattern of control rods of the equilibrium cycle of 18 months for the CLV using bio-inspired algorithms; Mejora del patron de barras de control del ciclo de equilibrio de 18 meses para la CLV empleando algoritmos bio-inspirados

    Energy Technology Data Exchange (ETDEWEB)

    Perusquia, R.; Ortiz, J.J.; Montes, J.L. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: rpc@nuclear.inin.mx

    2003-07-01

    Nowadays in the National Institute of Nuclear Research are carried out studies with some bio-inspired optimization techniques to improve the performance of the fuel cycles of the boiling water reactors of the Laguna Verde power plant (CLV). In the present work two bio-inspired techniques were applied with the purpose of improving the performance of a balance cycle of 18 months developed for the CLV: genetic algorithms (AG) and systems based on ants colonies (SCH). The design of the reference cycle it represents in several aspects an optimal cycle proposed starting from the experience of several operation decades with the boiling water reactors (BWR initials for Boiling Water Reactor) in the world. To try to improve their performance is beforehand a difficult challenge and it puts on test the feasibility of the optimization methods in the reloads design. The study of the bio-inspired techniques was centered exclusively on the obtaining of the control rod patterns (PBC) trying to overcome the capacity factor reached in the design of the reference cycle. It was fixed the cycle length such that the decrease of the coast down period would represent an increase of the capacity factor of the cycle; so that, it diminishes the annual cost associated with the capital cost of the plant. As consequence of the study, was found that the algorithm based on the ants colonies reaches to diminish the coast down period in five and half days respect to the original balance cycle, what represents an annual saving of $US 74,000. Since the original cycle was optimized, the above-mentioned, shows the ability of the SCH for the optimization of the cycle design. With the AG it was reach to approach to the original balance cycle with a coast down period greater in seven days estimating an annual penalization of $US 130,000. (Author)

  5. Modelo Bio-inspirado para el Reconocimiento de Gestos Usando Primitivas de Movimiento en Visión

    Directory of Open Access Journals (Sweden)

    Sandra E. Nope

    2008-10-01

    Full Text Available Resumen: Se aborda el problema del reconocimiento de gestos usando la información de movimiento con el fin de obtener un modelo bio-inspirado para, en un futuro, utilizarlo en la programación de robots mediante el paradigma del aprendizaje por imitación. En este trabajo se extraen las primitivas de movimiento a partir de imágenes consecutivas, capturadas por una cámara web estándar. Para la programación por imitación de robots se identificó, como primera fase, el reconocimiento de gestos, en el cual es necesario resolver tres aspectos principales: La representación instantánea del movimiento, la integración temporal de dicha información y, la estrategia de clasificación. Estos tres aspectos serán tratados a lo largo de este trabajo y, en contraste con otros, la extracción del movimiento y su codificación está inspirada en el procesamiento del movimiento realizado en el cerebro de macacos. El modelo obtenido fue aplicado al reconocimiento de cuatro tipos de gestos realizados con la mano por diferentes personas. El porcentaje de aciertos varió entre 91.42% y 97.14%, utilizando diferentes estrategias estándar de clasificación. Palabras clave: Reconocimiento de gestos, modelo bio-inspirado, primitivas de movimiento, codificación del movimiento, integración temporal, visión artificial

  6. Algoritmos de antialiasing

    Directory of Open Access Journals (Sweden)

    Gabriel Mañana Guichón

    1993-07-01

    Full Text Available Se presentan los algoritmos desarrollados para el trazado de lineas suaves y aplicación de texto sobre imágenes, como ejemplo del trabajo de investigación que se lleva a cabo en el campo del filtrado de imágenes o antialiasing.

  7. Algoritmos para problemas de empacotamento

    OpenAIRE

    Eduardo Candido Xavier

    2006-01-01

    Resumo: Neste trabalho estudamos diversos problemas de empacotamento considerados NP-difíceis. Assumindo a hipótese de que P ? NP, sabemos que não existem algoritmos eficientes (complexidade de tempo polinomial) exatos para resolver tais problemas. Uma das abordagens consideradas para tratar tais problemas é a de algoritmos de aproximação, que são algoritmos eficientes e que geram soluções com garantia de qualidade. Neste trabalho apresentamos alguns algoritmos aproximados para problemas de e...

  8. Nuclear reactors project optimization based on neural network and genetic algorithm; Otimizacao em projetos de reatores nucleares baseada em rede neural e algoritmo genetico

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Claudio M.N.A. [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Schirru, Roberto; Martinez, Aquilino S. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia

    1997-12-01

    This work presents a prototype of a system for nuclear reactor core design optimization based on genetic algorithms and artificial neural networks. A neural network is modeled and trained in order to predict the flux and the neutron multiplication factor values based in the enrichment, network pitch and cladding thickness, with average error less than 2%. The values predicted by the neural network are used by a genetic algorithm in this heuristic search, guided by an objective function that rewards the high flux values and penalizes multiplication factors far from the required value. Associating the quick prediction - that may substitute the reactor physics calculation code - with the global optimization capacity of the genetic algorithm, it was obtained a quick and effective system for nuclear reactor core design optimization. (author). 11 refs., 8 figs., 3 tabs.

  9. Algoritmos genéticos locales

    OpenAIRE

    García-Martínez, Carlos; Lozano, Manuel

    2007-01-01

    Los Algoritmos Genéticos Locales son procedimientos que iterativamente re nan soluciones dadas. Su diferencia con procedimientos de mejora iterativa clásicos reside en el uso de operadores genéticos para realizar el re namiento. En este estudio presentamos un nuevo Algoritmo Genético Local Binario basado en un Algoritmo Genético Estacionario. Hemos comparado el Algoritmo Genético Local Binario con otros procedimientos de mejora iterativa de la literatura. Los res...

  10. Introduciendo mejoras en los algoritmos evolutivos

    OpenAIRE

    Esquivel, Susana Cecilia; Gallard, Raúl Hector

    2002-01-01

    Hoy día se conocen como algoritmos evolutivos (Aes), a una familia de algoritmos basados en lso principios de reproducción, variación aleatoria competencia y selección de individuos. Una de las clases más exitosas la constituyen aquellos basados en lo que originalmente se conoció como algoritmos genéticos. Estos tienen en particular el uso de operadores genéticos (crossover y mutación) no siempre presentes en otras clases de algoritmos evolutivos. Esta presentación muestra variantes introduci...

  11. Algoritmos genéticos

    Directory of Open Access Journals (Sweden)

    José Jesús Martínez Páez

    1998-10-01

    Full Text Available Esta técnica se basa en el concepto de evolución a través de selección de los mejores individuos, y de los operadores genéticos de selección, reproducción y mutación. Se trata entonces, de definir un espacio de soluciones para el problema que se quiere solucionar, en una cadena de bits. A esto se le conoce como la codificación del cromosoma, donde cada bit, denominado gen  tiene cierto significado especial. Inicialmente el algoritmo genera al azar muchas de estas cadenas o seres, es decir, una población, que luego confronta can un ambiente, que es el problema solucionar o función que se quiere optimizar. De esta confrontación  o evaluación a que se somete cada ser. Se obtiene información sobre cómo se comporto cada uno. A través de métodos aleatorios, pero con probabilidad de selección proporcional a su comportamiento, es decir, a mejor comportamiento mayor probabilidad, se selecciona una nueva población de seres supuestamente mejores que la generación anterior.

  12. Neuro-diffuse algorithm for neutronic power identification of TRIGA Mark III reactor; Algoritmo neuro-difuso para la identificacion de la potencia neutronica del reactor Triga Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Rojas R, E.; Benitez R, J. S. [Instituto Tecnologico de Toluca, Division de Estudios de Posgrado e Investigacion, Av. Tecnologico s/n, Ex-Rancho La Virgen, 50140 Metepec, Estado de Mexico (Mexico); Segovia de los Rios, J. A.; Rivero G, T. [ININ, Gerencia de Ciencias Aplicadas, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: jorge.benitez@inin.gob.mx

    2009-10-15

    In this work are presented the results of design and implementation of an algorithm based on diffuse logic systems and neural networks like method of neutronic power identification of TRIGA Mark III reactor. This algorithm uses the punctual kinetics equation as data generator of training, a cost function and a learning stage based on the descending gradient algorithm allow to optimize the parameters of membership functions of a diffuse system. Also, a series of criteria like part of the initial conditions of training algorithm are established. These criteria according to the carried out simulations show a quick convergence of neutronic power estimated from the first iterations. (Author)

  13. Application of the MOVE algorithm for the identification of reduced order models of a core of a BWR type reactor; Aplicacion del algoritmo MOVE para la identificacion de modelos de orden reducido del nucleo de un reactor tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Victoria R, M.A.; Morales S, J.B. [UNAM, DEPFI, Campus Morelos, en IMTA Jiutepec, Morelos (Mexico)]. e-mail: angelvr@gmail.com

    2005-07-01

    Presently work is applied the modified algorithm of the ellipsoid of optimal volume (MOVE) to a reduced order model of 5 differential equations of the core of a boiling water reactor (BWR) with the purpose of estimating the parameters that model the dynamics. The viability is analyzed of carrying out an analysis that calculates the global dynamic parameters that determine the stability of the system and the uncertainty of the estimate. The modified algorithm of the ellipsoid of optimal volume (MOVE), is a method applied to the parametric identification of systems, in particular to the estimate of groups of parameters (PSE for their initials in English). It is looked for to obtain the ellipsoid of smaller volume that guarantees to contain the real value of the parameters of the model. The PSE MOVE is a recursive identification method that can manage the sign of noise and to ponder it, the ellipsoid represents an advantage due to its easy mathematical handling in the computer, the results that surrender are very useful for the design of Robust Control since to smaller volume of the ellipsoid, better is in general the performance of the system to control. The comparison with other methods presented in the literature to estimate the reason of decline (DR) of a BWR is presented. (Author)

  14. Modelo poblacional con algoritmos genéticos

    OpenAIRE

    Veliz Quintero, Eduardo; Rodriguez Ojeda, Luis

    2009-01-01

    Para el desarrollo de este trabajo, “MODELO POBLACIONAL CON ALGORITMOS GENÉTICOS”, he investigado la rama de la inteligencia artificial, como son los algoritmos genéticos. Primero presento en forma general los aspectos que envuelven los algoritmos genéticos, parto de la necesidad de optimizar, así como su historia y posibles aplicaciones y luego he cubierto detalladamente todo lo que pude investigar sobre la teoría de los algoritmos genéticos, sus fundamentos matemáticos, tipos de algoritmos ...

  15. Algoritmo de aceptación diferida matricial

    Directory of Open Access Journals (Sweden)

    Jorge Oviedo

    2008-01-01

    Full Text Available En este artículo damos una versión matricial del algoritmo de aceptación diferida para el modelo de asignación (matching uno a uno. El algoritmo va modificando la matriz de preferencia de los agentes. Cuando el algoritmo se detiene se muestra que coincide con una asignación estable óptima de los agentes.

  16. Los algoritmos como instrumento de la matemática

    Directory of Open Access Journals (Sweden)

    Luis Roberto Ojeda Ch.

    1993-07-01

    Full Text Available El concepto de algoritmo es fundamental en múltiples campos de la actividad humana. Se relacionan en este artfculo los conceptos de función y de algoritmo para luego caracterizar un tipo especial de función: el de las recursivas. Finalmente se establece la Tesis de Alonzo Church que indica que sólo para las funciones recursivas pueden obtenerse algoritmos de evaluación.

  17. Framework de desarrollo rápido de algoritmos paralelos

    OpenAIRE

    Expósito Piñol, Luis

    2012-01-01

    El proyecto ofrece un framework de programación de algoritmos paralelos basado en el algoritmo genético BRKGA, permitiendo resolver diferentes problemas solo cambiando una parte del framework. Todo esto utilizando la GPU para tener una mayor potencia de cálculo.

  18. The use of genetic algorithms with niching methods in nuclear reactor related problems; A utilizacao dos metodos de nichos dos algoritmos geneticos na otimizacao de problemas de reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sacco, Wagner Figueiredo

    2000-03-01

    Genetic Algorithms (GAs) are biologically motivated adaptive systems which have been used, with good results, in function optimization. However, traditional GAs rapidly push an artificial population toward convergence. That is, all individuals in the population soon become nearly identical. Niching Methods allow genetic algorithms to maintain a population of diverse individuals. GAs that incorporate these methods are capable of locating multiple, optimal solutions within a single population. The purpose of this study is to test existing niching techniques and two methods introduced herein, bearing in mind their eventual application in nuclear reactor related problems, specially the nuclear reactor core reload one, which has multiple solutions. Tests are performed using widely known test functions and their results show that the new methods are quite promising, specially in real world problems like the nuclear reactor core reload. (author)

  19. Algoritmos para problemas de corte e empacotamento

    OpenAIRE

    Thiago Alves de Queiroz

    2010-01-01

    Resumo: Problemas de Corte e Empacotamento são, em sua maioria, NP-difíceis e não existem algoritmos exatos de tempo polinomial para tais se for considerado P ¿ NP. Aplicações práticas envolvendo estes problemas incluem a alocação de recursos para computadores; o corte de chapas de ferro, de madeira, de vidro, de alumínio, peças em couro, etc.; a estocagem de objetos; e, o carregamento de objetos dentro de contêineres ou caminhões-baú. Nesta tese investigamos problemas de Corte e Empacotament...

  20. Algoritmos de compresión paralela

    OpenAIRE

    Anderson, Alfredo; Dirazar, Delio

    1997-01-01

    El objetivo planteado inicialmente fue analizar la viabilidad de distribuir un compresor de datos en una red de procesadores. Además de elegir el algoritmo a implementar y definir alternativas de distribución debíamos seleccionar un lenguaje y un sistema operativo que soporten las herramientas de multiprocesamiento necesarias para la implementación de las versiones distribuidas. Nuestro primer paso fué realizar la implementación de dos compresores de datos basados en el mismo algortimo,...

  1. Algoritmo de lanczos na variedade de grassmann

    OpenAIRE

    Lopes, Ana Paula Ferreira Fernandes; Viamonte, Ana Júlia; Pascoal, António José

    2008-01-01

    O problema do cálculo de valores próprios, vectores próprios e subespaços invariantes está presente em áreas tão diversas como Engenharia, Física, Ciências de Computação e Matemática. Considerando a importância deste problema em tantas aplicações práticas, não é de surpreender que tenha sido e continue a ser objecto de intensa investigação, dando corpo a uma literatura muito vasta. Desenvolvemos um novo algoritmo de Lanczos na variedade de Grassmann. Este trabalho surgiu na ...

  2. ¿Podemos predecir en algoritmos paralelos no deterministas?

    OpenAIRE

    Fritzsche, Paula Cecilia

    2007-01-01

    ¿Podemos predecir en algoritmos paralelos no deterministas? Sí, es posible. A lo largo de este documento se demostrará esta afirmación. La evaluación científica de algoritmos para solucionar todo tipo de problemas es uno de los puntos clave en ciencias de la computación. En el terreno de ciencia computacional (una disciplina emergente) continuamente surgen nuevos desafíos.

  3. Algoritmo de cifrado para sistemas móviles

    OpenAIRE

    Castro Lechtaler, Antonio; Cipriano, Marcelo; García, Edith; Liporace, Julio César; Maiorano, Ariel; Malvacio, Eduardo; Tapia, Néstor

    2017-01-01

    Este proyecto de investigación persigue elaborar el diseño y desarrollo de un Algoritmo de Cifrado para Sistemas Móviles que por sus propiedades de velocidad, compactibili- dad y robustez; pueda ser implementado en equipos de comunicaciones que funcionan so- bre Sistemas Móviles. Se esperan obtener resultados teóricos, prácticos y la realización de un desarrollo experimental. Los modernos algoritmos criptológicos responden a principios y filosofías diferentes a las que se llevaban a cab...

  4. Análisis de eficiencia de algoritmos

    Directory of Open Access Journals (Sweden)

    Lovos, Edith

    2012-01-01

    Full Text Available La resolución de un problema usando una computadora puede ser modelada por diferentes algoritmos. De aquí la importancia de contar con herramientas que nos permitan seleccionar el algoritmo que sea más eficiente, es decir, el que insuma menos recursos del ordenador: tiempo y memoria necesarios para su ejecución. Existen dos formas de medir la complejidad de un algoritmo: análisis teórico y análisis empírico. En este trabajo se presenta la descripción del simulador, “SIMULA-ALGO”, junto con la propuesta de uso y detalles del diseño de la interfaz. Se presenta además una fundamentación teórica sobre las ventajas del uso de la simulación como recurso pedagógico-didáctico. El simulador se propone como recurso para la enseñanza aprendizaje del análisis teórico de eficiencia de algoritmos. El mismo está destinado a alumnos de los primeros años de carreras universitarias de licenciatura en sistemas. Los contenidos considerados en el simulador, requieren, para su comprensión, del uso de procesos cognitivos analíticos. El simulador pretende optimizar estos procesos en el alumno que lo usa. Así, por ejemplo, el simulador podrá realizar procesos rutinarios en forma rápida y efectiva, permitiendo que el alumno se concentre en los procesos analíticos que requiere la tarea.

  5. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

    Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

  6. Reactor

    International Nuclear Information System (INIS)

    Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

    1979-01-01

    Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

  7. Estudo comparativo entre algoritmos das transformadas discretas de Fourier e Wavelet

    OpenAIRE

    Wilson Hissamu Shirado; Márcio de Abreu Moreira; Jandira Guenka Palma; Sylvio Barbon Júnior

    2015-01-01

    Este trabalho apresenta um estudo comparativo das complexidades dos algoritmos das Transformadas Discretas de Fourier, Wavelet e Transformada Rápida de Fourier. As formalizações matemáticas e algumas características dos algoritmos são apresentadas, assim como alguns conceitos de complexidade assintótica. Por fim, é realizado um ensaio prático para comparação dos algoritmos, abrangendo questões como tempo de execução, vantagens e desvantagens de cada transformada assim como avaliações a respei...

  8. Afectos y algoritmos alternativos en las aulas de primaria

    OpenAIRE

    Gamazo Alonso, Natalia

    2017-01-01

    El presente Trabajo Fin de Grado (TFG) recoge una sencilla investigación sobre la evolución del dominio afectivo matemático de una muestra de niños que trabajan las matemáticas con el método ABN (Abierto Basado en Números) y de una muestra de alumnos que las trabajan mediante algoritmos tradicionales. Junto con el análisis de la evolución de la afectividad hacia las matemáticas a lo largo de los cursos académicos que conforman la Educación Primaria, se establece también una comparativa ent...

  9. Estudo comparativo entre algoritmos das transformadas discretas de Fourier e Wavelet

    Directory of Open Access Journals (Sweden)

    Wilson Hissamu Shirado

    2015-11-01

    Full Text Available Este trabalho apresenta um estudo comparativo das complexidades dos algoritmos das Transformadas Discretas de Fourier, Wavelet e Transformada Rápida de Fourier. As formalizações matemáticas e algumas características dos algoritmos são apresentadas, assim como alguns conceitos de complexidade assintótica. Por fim, é realizado um ensaio prático para comparação dos algoritmos, abrangendo questões como tempo de execução, vantagens e desvantagens de cada transformada assim como avaliações a respeito das diferentes resoluções tempo/frequência de cada algoritmo.

  10. Reactors

    DEFF Research Database (Denmark)

    Shah, Vivek; Vaz Salles, Marcos António

    2018-01-01

    The requirements for OLTP database systems are becoming ever more demanding. Domains such as finance and computer games increasingly mandate that developers be able to encode complex application logic and control transaction latencies in in-memory databases. At the same time, infrastructure...... engineers in these domains need to experiment with and deploy OLTP database architectures that ensure application scalability and maximize resource utilization in modern machines. In this paper, we propose a relational actor programming model for in-memory databases as a novel, holistic approach towards......-level function calls. In contrast to classic transactional models, however, reactors allow developers to take advantage of intra-transaction parallelism and state encapsulation in their applications to reduce latency and improve locality. Moreover, reactors enable a new degree of flexibility in database...

  11. Extensión del Algoritmo Evolutivo MOS con técnicas de Evolución Diferencial

    OpenAIRE

    Fernández Martín, Jaime

    2008-01-01

    Integración de un nuevo algoritmo de Evolución Diferencial en una librería de Algoritmos Evolutivos y su adaptación en forma de técnica para el algoritmo de hibridación MOS (Multiple Offspring Sampling). MOS es capaz de adaptarse a los problemas, premiando a las técnicas que mejores resutlados vayan obteniendo. Pruebas y estudios sobre los resultados obtenidos con esta nueva técnica.

  12. Algoritmo de reconocimiento de patrones basado en codificación fisiológica en cerebro de primates.

    OpenAIRE

    CASTEL BAIXAULI, ALEJANDRO

    2017-01-01

    El cerebro humano y animal es capaz de reconocer una gran cantidad de patrones, como por ejemplo caras, utilizando un limitado número de neuronas y algoritmos de procesamiento [Chang et al 2017]. Sin embargo, los algoritmos de reconocimiento de patrones utilizados en la actualidad, incluso aquellos basados en redes neuronales, requieren un alto número de operaciones y capacidad de computo. El objetivo del presente trabajo final de grado es adaptar, desarrollar y validar un algoritmo de re...

  13. Una comparación de algoritmos evolutivos para la optimización de funciones multimodales

    OpenAIRE

    Brero, Alejandro C.; Gallard, Raúl Hector

    2000-01-01

    La Computación Evolutiva (CE) ha sido reconocida recientemente como un campo de investigación que estudia un nuevo tipo de algoritmos: los algoritmos evolutivos (AEs). Opuestamente a los enfoques tradicionales que mejoran una única solución, estos algoritmos procesan poblaciones de soluciones y poseen como características comunes la reproducción, la variación aleatoria, la competición y la selección de individuos. Los algoritmos genéticos (AGs) y las estrategias evolutivas (EEs) constituye...

  14. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

    Object: To provide a boiling water reactor which can enhance a quake resisting strength and flatten power distribution. Structure: At least more than four fuel bundles, in which a plurality of fuel rods are arranged in lattice fashion which upper and lower portions are supported by tie-plates, are bundled and then covered by a square channel box. The control rod is movably arranged within a space formed by adjoining channel boxes. A spacer of trapezoidal section is disposed in the central portion on the side of the channel box over substantially full length in height direction, and a neutron instrumented tube is disposed in the central portion inside the channel box. Thus, where a horizontal load is exerted due to earthquake or the like, the spacers come into contact with each other to support the channel box and prevent it from abnormal vibrations. (Furukawa, Y.)

  15. NUEVO ALGORITMO MULTICLASIFICADOR PARA FLUJOS DE DATOS CON CAMBIOS DE CONCEPTO

    Directory of Open Access Journals (Sweden)

    Ramón Osmany Ramírez Tasé

    2016-04-01

    Full Text Available Los algoritmos multiclasificadores se han mostrado particularmente eficientes para trabajar sobre espacios de datos grandes y complejos como los llamados flujos de datos. En estos flujos, durante la clasificación, aparecen conceptos que cambian con el tiempo, por lo que los métodos para su minería, sobre todo los  que detectan y se adaptan  a estos cambios, son importantes por su aplicación en áreas como: bioinformática, medicina, economía y finanzas, industria, medio ambiente, entre otras. La presente investigación propone un nuevo algoritmo multiclasificador que se adapta a los cambios de conceptos, tiene votación ponderada con una nueva forma para ajustar los pesos y permite variar el tipo de clasificador básico. El algoritmo fue implementado en compatibilidad y bajo las exigencias del entorno de trabajo MOA (Massive Online Analysis facilitando la comparación con otros algoritmos conocidos y la generación de bases de datos sintéticas que simulan cambios de conceptos. Para la experimentación se generaron experiencias bajo conceptos artificiales conocidos, tales como: SEA, LED, STAGGER e Hiperplano; logrando mostrar la alta capacidad de adaptación y la estabilidad del algoritmo frente a diferentes situaciones simuladas.

  16. Algoritmo de criptografia RSA: análise entre a segurança e velocidade

    Directory of Open Access Journals (Sweden)

    Rafael Santos Andrade

    2012-12-01

    Full Text Available O objetivo deste trabalho é abordar a relação existente entre a busca pela segurança de dados e a velocidade de codificação e decodificação do algoritmo de criptografia RSA, que utiliza um par de números inteiros como ‘chave’. Considerando o tamanho da chave como requisito de segurança, devido à dificuldade computacional de fatorar números inteiros extensos, simulamos estes processos, com o algoritmo implementado na linguagem de programação C, utilizando chaves aleatórias de 1024, 2048 e 4096 bits. Desta forma, observamos o tempo de processamento em função do tamanho das chaves, confrontando segurança e desempenho.Palavras-chave: criptografia; algoritmo RSA; segurança; desempenho.

  17. ESTIMACIÓN DE PARÁMETROS EN MODELOS NO LINEALES: ALGORITMOS Y APLICACIONES

    Directory of Open Access Journals (Sweden)

    Óscar Cornejo Zúñiga

    Full Text Available En este artículo se muestran diferentes algoritmos para estimar parámetros en modelos no lineales. Se aplican primeramente a una base de datos de problemas clasificados difíciles. Posteriormente, se muestra el comportamiento de los algoritmos para el estudio de crecimiento de la merluza común en machos y hembras, anchoveta y sardina común ajustando un modelo de Von Bertalanffy. Se aplica el test de Cerrato para la comparación de crecimientos entre géneros para la merluza común. Los algoritmos se implementaron en ambiente MATLAB presentando un buen comportamiento en cuanto a tiempo CPU, número de iteraciones y exactitud de la solución encontrada respecto de valores certificados de los problemas de la base de datos.

  18. ANÁLISIS A LOS ALGORITMOS UTILIZADOS POR EL SOFTWARE PARA BI

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    CURTIS COOKE

    2011-12-01

    Full Text Available El propósito de este trabajo es examinar cuáles son los algoritmos que utilizan los paquetes de software más populares para BI. Una encuesta inicial informal muestra que los actuales paquetes de software de BI incluyen a la mayoría de algoritmos descritos en la literatura de los paquetes estadísticos tradicionales. Además, una de las principales diferencias entre el software para BI y los paquetes estadísticos tradicionales es que el primero tiene mejores características para los reportes.

  19. INTELIGÊNCIA ARTIFICIAL COM ENFOQUE EM ALGORITMOS GENÉTICOS

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    Renata Luiza da Costa

    2010-12-01

    Full Text Available A palestra aqui proposta aborda as principais técnicas de Inteligência Artificial dando enfoque maior a técnica chamada Algoritmos Genéticos, a qual é aplicada a problemas de otimização. Tal palestra aborda os fundamentos teóricos do assunto e apresenta uma aplicação prática, desenvolvida usando a Linguagem de Programação Delphi, onde o problema da Dieta tem suas respostas factíveis encontradas a partir do uso de um Algoritmo Genético.

  20. Algoritmos evolutivos aplicados al diseño inteligente de parques eólicos

    OpenAIRE

    Bilbao, Martín; Alba, Enrique

    2011-01-01

    En este documento se muestran dos tipos de algoritmos metaheurísticos aplicados al diseño inteligente de un parque eólico, la idea básica es utilizar CHC y algoritmos genéticos para obtener una buena configuración de molinos dentro del parque de tal manera que maximicen la energía total producida y minimicen la cantidad de molinos utilizados. En este trabajo analizaremos dos casos de estudios con una distribución real de vientos de la patagonia argentina, un terreno irregular con restriccione...

  1. Algoritmos y gramáticas : un capitulo apasionante de la teoría cognitiva

    OpenAIRE

    Pérez Alcázar, Jesús Hernando

    2012-01-01

    DOS GRANDES PROBLEMASUno de los grandes pioneros de la teoría cognitiva es el profesor norteamericano Noam Chomsky. En este ensayo presentaremos algunos de sus muy numerosos aportes al desarrollo de esta nueva teoría, limitando la atención a las relaciones entre gramaticas y algoritmos. Una manera muy sugestiva de abordar las relaciones entre los algoritmos matemáticos y las gramáticas de la teoría lingüística, la ofrece el propio Noam Chomsky en su importante trabajo "El conocimiento del len...

  2. Algoritmos para la clasificación piramidal simbólica

    Directory of Open Access Journals (Sweden)

    Oldemar Rodríguez

    2009-02-01

    Full Text Available En este artículo se define el concepto de pirámide simbólica, además se presentan dos algoritmos para generar este tipo d pirámide a partir de una matriz de datos simbólicos. El primer algoritmo (CAPS encuentra un "orden total compatible con la pirámide" de los n objetos, mientras que el segundo (CAPSO construye la pirámide a partir de un orden dado apriori en los objetos, dicho orden se recibe como entrada en el algoritmo. Ambos algoritmos, además de producir la pirámide, para cada grada encuentran el objeto simbólico asociado a cada nodo y su extensión. También se presentan los teoremas de convergencia. Palabras clave: pirámide, objeto simbólico, grada, grado de generalidad, objeto completo, componente conexa, tablas de datos simbólica.

  3. Algoritmos de aproximação para problemas de empacotamento em faixa com restrições de descarregamento

    OpenAIRE

    Jefferson Luiz Moisés da Silveira

    2011-01-01

    Resumo: Neste trabalho estudamos problemas de empacotamento com restrições de descarregamento considerados NP-difíceis. Estes problemas possuem aplicações nas áreas de logística e roteamento. Assumindo a hipótese de que P ? NP, sabemos que não existem algoritmos eficientes para resolver tais problemas. Uma das abordagens consideradas para tratar tais problemas é a de algoritmos de aproximação, que são algoritmos eficientes (complexidade de tempo polinomial) e que geram soluções com garantia d...

  4. ANÁLISIS Y COMPARACIÓN DE LOS ALGORITMOS DE CIFRADOS SIMÉTRICO EN PLATAFORMAS WINDIWS

    OpenAIRE

    Carrera Albán, Thruman Wladimir

    2016-01-01

    El objetivo principal que guía el diseño de cualquier algoritmo de cifrado debe ser la seguridad contra ataques no autorizados. Sin embargo, para todas las aplicaciones prácticas, el rendimiento y la velocidad también son preocupaciones importantes. Estas son las dos características principales que diferencian un algoritmo de cifrado de otro. Este documento proporciona la comparación de rendimiento entre dos de los algoritmos de cifrado más utilizados: AES (Rijndael) y Blowfish. La comparació...

  5. IMPLEMENTACIÓN EN HARDWARE DE UN SVPWM EN UN SOFT-CORE NIOS II PARTE II: ALGORITMO DEL SVPWM

    Directory of Open Access Journals (Sweden)

    Jorge Rivera

    2009-01-01

    Full Text Available En este trabajo se presentan los detalles de la moduclación por ancho de pulso en el espacio vectorial (SVPWM por sus siglas en inglés. Primero se plantea el escenario en donde es más usado este algoritmo, es decir, en el control de motores eléctricos trifásicos. Se explica que el algoritmo del SVPWM sirve para manejar los inversores, además se indica en qué marco de referencia deben estar las acciones de control que el algortimo del SVPWM acepta, para finalmente presentar el algoritmo de una manera clara y concisa.

  6. Algoritmos multirecombinativos aplicados al problema de ruteo de vehículos

    Directory of Open Access Journals (Sweden)

    Renzo Ramon Miño

    2014-06-01

    Full Text Available El diseño de algoritmos eficientes para resolver problemas complejos ha sido tradicionalmente uno de los aspectos más importantes en la investigación en el campo de la informática. El objetivo perseguido en este campo es fundamentalmente el desarrollo de nuevos métodos capaces de resolver problemas complejos con el menor esfuerzo computacional posible, mejorando así a los algoritmos existentes. En consecuencia, esto no sólo permite afrontar los problemas de forma más eficiente, sino afrontar tareas vedadas en el pasado debido a su alto costo computacional. Las metaheurísticas son métodos que integran procedimientos de mejora local y estrategias de alto nivel para realizar una búsqueda robusta en el espacio-problema. El problema de ruteo de vehículos es un problema de optimización combinatoria de gran importancia en diferentes entornos logísticos debido a su dificultad (NP-duros y a sus múltiples aplicaciones industriales. Se han propuestos varias soluciones a este problema haciendo uso de heurísticas y metaheurísticas. En este trabajo proponemos dos algoritmos para resolver el problema de ruteo de vehículos con capacidad limitada, utilizando como base un Algoritmo Evolutivo conocido como MCMP-SRI (Stud and Random Inmigrants combinados con Hill- Climbing. Detalles de los algoritmos y los resultados de los experimentos muestran un promisorio comportamiento para resolver el problema.

  7. Algoritmo para el cálculo de cargas de trabajo

    Directory of Open Access Journals (Sweden)

    Mauricio Becerra Fernández

    2016-04-01

    Full Text Available Este artículo presenta el desarrollo un algoritmo para el cálculo de cargas de trabajo, soportado en el análisis de estudios similares y la teoría del estudio de métodos y tiempos. El algoritmo se propone como un elemento de soporte para el análisis del nivel trabajo asignado a un cargo específico o a un grupo de trabajadores en un área determinada, ya sea en la industria de manufactura o de servicios, lo que permita nivelar el volumen de trabajo asignado mediante la definición de diversas alternativas que promuevan el aumento de la productividad, favorezcan la mejora en el clima y las condiciones laborales.

  8. Algunas relaciones entre algoritmos y resolución de problemas

    Directory of Open Access Journals (Sweden)

    Jaime Fonseca González

    2012-04-01

    Full Text Available Como parte del estudio realizado en la tesis de maestría “Uso de algoritmos en la resolución de problemas sobre isometrías del plano. Un estudio de caso”, se han identificado diversas formas en que se relacionan los algoritmos con la resolución de problemas, no sólo como procesos mecánicos, sino como fuente de información en el planteamiento de estrategias al resolver un problema, de modo que surgen algunas maneras en que se da esta relación, ejemplificando cada una de ellas con problemas cuyo objeto matemático central son las isometrías del plano.

  9. Diseño e implementación de algoritmos de unificación y matching para términos comprimidos.

    OpenAIRE

    Ramos Garrido, Lander

    2011-01-01

    Las gramáticas incontextuales se pueden utilizar como herramienta para comprimir palabras o términos. Estas gramáticas pueden permitir en casos extremos comprimir hasta un factor exponencial. Sobre este tipo de compresiones existen diferentes algoritmos que se pueden implementar sin necesidad de descomprimir la palabra o término dados. En este PFC diseñamos nuevos algoritmos probabilísticos que se puedan aplicar a este tipo de compresiones. Estos algoritmos mejoran el coste de los algoritmos ...

  10. Aplicando un Algoritmo Genético para Balancear Carga Dinámicamente en Ambientes Distribuidos Orientados a Objetos (CORBA)

    OpenAIRE

    Fco. Javier Luna Rosas; Rene Tristán Ávila; J. de Jesús Martínez Pedroza

    2003-01-01

    Balancear Carga significa como distribuir procesos entre procesadores conectados por una red, para equilibrar la carga de trabajo entre ellos. Los algoritmos de planeación distribuida global pueden ser divididos en dos grandes grupos: algoritmos de balanceo de carga dinámica y algoritmos de balanceo de carga estática. Los algoritmos de balanceo de carga estática, también referenciados como planeación de tareas obtienen la localización de todos sus requerimientos antes de comenzar su ...

  11. Análisis Comparativo de Algoritmos de Minería de Subgrafos Frecuentes

    Directory of Open Access Journals (Sweden)

    Santiago Bianco

    2016-06-01

    Full Text Available Gracias a las posibilidades que ofrecen a la hora de representar información y la abstracción conceptual que permiten manejar, los grafos son ampliamente utilizados en investigaciones relacionadas con la informática. A medida que se fueron incrementando las aplicaciones de estas estructuras, la complejidad de los elementos a representar y el volumen de información manejado, aparece la necesidad de utilizar procesos eficientes para extraer información o patrones ocultos en esa gran masa de datos, por lo que se comienza a aplicar la minería de grafos. Dentro las técnicas de minería de grafos se encuentra la búsqueda de subgrafos frecuentes, utilizada para reconocer subestructuras comunes entre un conjunto de grafos. En los últimos años se han llevado a cabo varias investigaciones que resuelven este problema, generando algoritmos diversos aplicando distintos enfoques, entre los cuales se encuentran el FSG, FFSM, gSpan y GASTON. El objetivo de este artículo es analizar el comportamiento de estos algoritmos a través de distintos experimentos diseñados para identificar si existe un algoritmo superior al resto y, en caso de que no lo haya, poder definir en qué escenarios es más recomendable la elección de cada uno.

  12. CB-SMoT+: UNA EXTENSIÓN AL ALGORITMO CB-SMoT

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    FRANCISCO MORENO

    2012-12-01

    Full Text Available Una trayectoria es un registro de la evoluciónde la posición de un objeto móvil. Por ejemplo,un vehículo que se mueve en el espacio durante unintervalo de tiempo. Una trayectoria se representamediante una secuencia de observaciones que indicanla posición y el tiempo en el que fue tomada cadaobservación. CB-SMoT es un algoritmo que identificalas partes de una trayectoria durante las cuales elobjeto mantuvo una velocidad promedio por debajode un límite dado. En este artículo se propone unaextensión para dicho algoritmo que permite identificarlas partes de una trayectoria durante las cualesel objeto mantuvo una velocidad promedio entre observacionespor debajo de un límite dado. Esto posibilitala identificación, por ejemplo, de violacionesa un límite de velocidad que no son advertidas porel algoritmo original. Para el estudio se usó el sistemade gestión de bases de datos PostgreSQL y losalgoritmos se implementaron en su lenguaje de programación,llamado PL/pgSQL. Además, se hicieronexperimentos con 100 trayectorias de vehículos conel propósito de mostrar la utilidad y la viabilidad de lapropuesta.

  13. Estudio de Algoritmos 2-Deslizantes Aplicados al Control de Pilas de Combustible

    OpenAIRE

    Cristian Kunusch; Paul F. Puleston; Miguel A. Mayosky

    2008-01-01

    Resumen: En este trabajo se hace un estudio comparativo de tres diferentes técnicas de control por modo deslizante de segundo orden, aplicadas al problema específico del control de respiración de una pila de combustible PEM. Los algoritmos diseñados se contrastan por simulación utilizando el modelo completo del sistema, poniendo particular énfasis en la respuesta transitoria y la robustez frente a perturbaciones. Palabras clave: Pilas de Combustible, Control no lineal, Modo Deslizante

  14. Estudio de Algoritmos 2-Deslizantes Aplicados al Control de Pilas de Combustible

    Directory of Open Access Journals (Sweden)

    Cristian Kunusch

    2008-07-01

    Full Text Available Resumen: En este trabajo se hace un estudio comparativo de tres diferentes técnicas de control por modo deslizante de segundo orden, aplicadas al problema específico del control de respiración de una pila de combustible PEM. Los algoritmos diseñados se contrastan por simulación utilizando el modelo completo del sistema, poniendo particular énfasis en la respuesta transitoria y la robustez frente a perturbaciones. Palabras clave: Pilas de Combustible, Control no lineal, Modo Deslizante

  15. Potenciando el aprendizaje proactivo con ILIAS&WebQuest: aprendiendo a paralelizar algoritmos con GPUs

    OpenAIRE

    Santamaría, J.; Espinilla, M.; Rivera, A. J.; Romero, S.

    2010-01-01

    Arquitectura de Computadores es una asignatura troncal de segundo ciclo de la titulación de Ingeniería de Telecomunicación (P.E. 2004) de la Universidad de Jaén, que desde el curso académico 2009/10 cuenta con una metodología de aprendizaje proactivo para motivar al alumno en la realización de las prácticas. En concreto, se ha abordado la enseñanza de la materia de paralelización de algoritmos haciendo uso de GPUs de tarjetas gráficas convencionales. Además, se ha d...

  16. Análisis de algoritmos de inteligencia artificial para videojuegos

    OpenAIRE

    Rico Zambrana, David

    2016-01-01

    Este documento contiene el Trabajo de Fin de Grado del alumno David Rico Zam- brana, estudiante del Grado en Ingeniería del Software, en la Universidad de Málaga. Este trabajo se ha realizado bajo la tutorización de Lorenzo Mandow Andaluz, pro- fesor del Departamento de Lenguajes y Ciencias de la Computación. El trabajo se titula Análisis de algoritmos de inteligencia artificial para vi- deojuegos, y consiste en el desarrollo de una aplicación usando Unity3D en la que se mue...

  17. Um sistema para o ensino e aprendizagem de algoritmos utilizando um companheiro de aprendizagem colaborativo

    OpenAIRE

    Petry, Patrícia Gerent

    2005-01-01

    Dissertação (mestrado) - Universidade Federal de Santa Catarina, Centro Tecnológico. Programa de Pós-graduação em Ciência da Computação Esta dissertação apresenta um modelo computacional de um sistema de suporte ao ensino e aprendizagem no domínio de algoritmos. O sistema inclui um companheiro de aprendizagem virtual, que utiliza a Modelagem Baseada em Restrições (Constraint-Based Modelling) como forma de representação do conhecimento e raciocínio. Os Sistemas Companheiro de Aprendizagem (...

  18. Simulador gráfico de algoritmos matemáticos

    OpenAIRE

    Alves, Luís; Balsa, Carlos; Pereira, Maria João

    2016-01-01

    O objetivo principal do trabalho de investigação foi desenvolver uma ferramenta computacional que possa ser usada por professores e alunos no ensino dos Métodos Numéricos. A ferramenta, designada por GraSMA (Graphical Simulator of Mathematical Algorithms), permite visualizar no ecrã a execução dos correspondentes algoritmos. Esta ferramenta integra vários softwares open source e baseia-se na anotação automática de código Octave com funções de inspeção que permitem captar a sucessão de valores...

  19. Algoritmo distribuido de compresión de datos : Una experiencia comparativa con sockets y PVM

    OpenAIRE

    Russo, Claudia Cecilia; Ramón, Hugo Dionisio; Anderson, Alfredo; Dirazar, Delio; De Giusti, Armando Eduardo

    1996-01-01

    Es notoria la importancia actual de la compresión de datos en al transmisión de información en redes, especialmente información multimedial Aspectos como optimización del uso del canal, tiempos de repuesta, seguridad y reducción de tráfico, justifican las tareas de investigación y desarrollo en este tema, así como al evolución de los recursos tecnológicos disponibles para implementar nuevas técnicas. En este contexto, se presentan resultados experimentales obtenidos de un algoritmo de compres...

  20. Comprensión de los algoritmos de las operaciones aritméticas en estudiantes de Magisterio

    OpenAIRE

    Salinas, María Jesús

    2003-01-01

    Partiendo de la creencia de que las matemáticas escolares deben formar parte del componente del conocimiento sobre las matemáticas del futuro maestro, se hizo un estudio sobre dos campos sistema de numeración decimal y algoritmos usuales de las operaciones aritméticas. En esta comunicación nos centramos solamente en el campo correspondiente a los algoritmos. Presentaremos los resultados generales y un análisis de las respuestas de 82 protocolos de una muestra de 467 sujetos correspondiente al...

  1. ALGORITMO PARA EL APRENDIZAJE DE REGLAS DE CLASIFICACION BASADO EN LA TEORÍA DE LOS CONJUNTOS APROXIMADOS EXTENDIDA

    Directory of Open Access Journals (Sweden)

    YAIMA FILIBERTO

    2011-01-01

    Full Text Available Los conjuntos aproximados han demostrado ser efectivos para desarrollar técnicas de aprendizaje automático, entre ellos métodos para el descubrimiento de reglas de clasificación. En este trabajo se presenta un algoritmo para generar reglas de clasificación basado en relaciones de similaridad, lo que permite que sea aplicable en casos donde los rasgos tienen dominio discreto o continuo. Los resultados experimentales muestran un desempeño satisfactorio en comparación con otros algoritmos conocidos como C4.5 y MODLEM.

  2. Algoritmos de previsión a corto plazo en base a radar meteorológico

    OpenAIRE

    Campeny Mora, Mercè

    2008-01-01

    Las consecuencias de las inundaciones suelen ser devastadoras. Los sistemas de protección tradicionales se complementan cada vez más con sistemas de prevención y alerta de inundaciones. En este sentido, el radar meteorológico y los algoritmos de previsión adquieren una importancia clave. El objetivo de la tesina es la mejora de los algoritmos de previsión en base a radar meteorológico a partir del estudio de distintos factores que intervienen.

  3. Conrprop: un algoritmo para la optimización de funciones no lineales con restricciones

    Directory of Open Access Journals (Sweden)

    Fernán Villa

    2009-01-01

    Full Text Available Resilent backpropagation (RPROP es una poderosa técnica de optimización basada en gradientes que ha sido comúnmente usada para el entrenamiento de redes neuronales artificiales, la cual usa una velocidad por cada parámetro en el modelo. Aunque esta técnica es capaz de resolver problemas de optimización multivariada sin restricciones, no hay referencias sobre su uso en la literatura de investigación de operaciones. En este artículo, se propone una modificación de resilent backpropagation que permite resolver problemas no lineales de optimización sujetos a restricciones generales no lineales. El algoritmo propuesto fue probado usando seis problemas comunes de prueba; para todos los casos, el algoritmo de resilent backpropagation restringido encontró la solución óptima, y para algunos casos encontró un punto óptimo mejor que el reportado en la literatura.

  4. El algoritmo HyRPNI y una aplicación en bioinformática

    Directory of Open Access Journals (Sweden)

    Gloria Inés Alvarez V.

    2011-06-01

    Full Text Available Proponemos un algoritmo de inferencia gramatical para lenguajes regulares que permite ahorrar cómputo al usar dos criterios diferentes para elegir los estados a ser procesados, un criterio se usa en la primera fase del proceso de inferencia (al principio y el otro en el resto del proceso. Realizamos experimentos para observar el desempeño del algoritmo, para aprender sobre el tamaño ideal de su primera fase y para mostrar su aplicación en la solución de un problema específico en bioinformática: la predicción de sitios de corte en poliproteínas codificadas por virus de la familia Potyviridae./ We propose a grammar inference algorithm for regular languages which saves computational cost by using two different criteria to choose states to be processed: one in the first phase of the inference process (the beginning and another for the rest of the process. We applied experiments to observe performance of the algorithm, to learn about the best size of its first phase and to show results of its application to solve a specific problem in Bioinformatics: the cleavage site prediction problem in polyproteins encoded by viruses of the Potyviridae family.

  5. Software para la enseñanza-aprendizaje de algoritmos estructurados

    Directory of Open Access Journals (Sweden)

    Arellano Pimentel, J. Jesús

    2012-12-01

    Full Text Available Actualmente existen diversas herramientas de software que sirven como recurso didáctico en la enseñanza-aprendizaje de algoritmos estructurados a nivel superior. Sin embargo, la gran mayoría solo hace énfasis en el diseño y prueba de los algoritmos. En el presente trabajo se propone un nuevo software, con base en la heurística de resolución de problemas de Polya, que da soporte a las fases de análisis y planteamiento del problema, además del diseño y traza completa de la prueba. Se realiza un análisis cualitativo entre el software propuesto y otras tres herramientas ampliamente utilizadas a nivel superior. La estructura y funcionalidad del software propuesto contribuye a que el estudiante adquiera, practique y ejercite la capacidad de resolver problemas de forma metódica a través de soluciones algorítmicas estructuradas.

  6. Generalización algebraica de la DFC: reflexiones por medio de un algoritmo algebraico

    Directory of Open Access Journals (Sweden)

    Antonio Geloneze Neto

    2012-01-01

    Full Text Available La Demostración de Flujos de Caja (DFC pasó a ser un informe obligatorio por la contabilidad a partir del 1 deenero de 2008 para todas las empresas de capital abierto o con patrimonio líquido superior a dos millones de realesy, de esa forma, se torna otro importante informe para la toma de decisiones gerenciales. Este trabajo tiene porobjetivo proponer una generalización algébrica para la DFC. Papeles de trabajo pueden contribuir para cerrar unalaguna didáctica en la enseñanza de la DFC y producir el método indirecto y el método directo, lado a lado consu equivalencia destacada, en una misma matriz por medio de algoritmos algebraicos. La pesquisa es de naturalezanormativa y enfatiza el carácter transversal entre la Contabilidad y la Matemática, mostrando que los informescontables y sus estructuras pueden ser vistos como matrices y sujetos a deducciones algebraicas sobre los eventosregistrados por medio de las partidas dobles. Como resultado, se pudo demostrar un algoritmo matemático conmatrices y sub-matrices y un guión en el formato de papeles de trabajo, compatibles con las orientaciones normativaspara la DFC en la legislación brasileña, que permite una DFC clara, segura y efectiva.

  7. Algoritmo Novedoso Para la Detección de Tareas Repetitivas en el Teclado

    Directory of Open Access Journals (Sweden)

    Bairon Londo

    2015-07-01

    Full Text Available En este artículo una herramienta para la detección de tareas repetitivas con secuencias lógicas realizadas a través de comandos del teclado, mediante el diseño e implementación de un algoritmo basado en el uso de autómatas finitos determinísticos y agentes de búsqueda de patrones. La novedad del algoritmo desarrollado radica en que está orientado a la detección de tareas repetitivas cuyas actividades tienen una secuencia lógica y que actualmente no se encuentran automatizadas por lo complejo que es esta labor   Abstract This paper propose a tool  for the detection of repetitive tasks with logical sequences realized across command of the keyboard is proposed, by means of the design and implementation of an algorithm based on the use of finite automata deterministic and agents of bosses' search. The innovation of the developed algorithm takes root in that it is orientated to the detection of repetitive tasks which activities have a logical sequence and that nowadays are not automated by the complex thing that is this labor.

  8. GENERALIZACIÓN ALGEBRAICA DE LA DFC: REFLEXIONES POR MEDIO DE UN ALGORITMO ALGEBRAICO

    Directory of Open Access Journals (Sweden)

    Antonio Geloneze Neto

    2012-09-01

    Full Text Available La Demostración de Flujos de Caja (DFC pasó a ser un informe obligatorio por la contabilidad a partir del 1 de enero de 2008 para todas las empresas de capital abierto o con patrimonio líquido superior a dos millones de rea¬les y, de esa forma, se torna otro importante informe para la toma de decisiones gerenciales. Este trabajo tiene por objetivo proponer una generalización algébrica para la DFC. Papeles de trabajo pueden contribuir para cerrar una laguna didáctica en la enseñanza de la DFC y producir el método indirecto y el método directo, lado a lado con su equivalencia destacada, en una misma matriz por medio de algoritmos algebraicos. La pesquisa es de naturale¬za normativa y enfatiza el carácter transversal entre la Contabilidad y la Matemática, mostrando que los informes contables y sus estructuras pueden ser vistos como matrices y sujetos a deducciones algebraicas sobre los eventos registrados por medio de las partidas dobles. Como resultado, se pudo demostrar un algoritmo matemático con matrices y sub-matrices y un guión en el formato de papeles de trabajo, compatibles con las orientaciones norma¬tivas para la DFC en la legislación brasileña, que permite una DFC clara, segura y efectiva.

  9. Identificación Inteligente de un Proceso Fermentativo Usando el Algoritmo GMDH Modificado

    Directory of Open Access Journals (Sweden)

    F. Hernández

    2012-01-01

    Full Text Available Resumen: En este trabajo se aborda, de manera particular, un método para el diseño del algoritmo conocido como Group Method of Data Handling, GMDH, típico con lazo recurrente. Una modificación en una de sus fases de entrenamiento permite ampliar el número de variables utilizadas en cada capa y con ello el área de regresión. Consecuentemente se puede obtener una estructura optimizada en sí misma de mayor complejidad, posibilitando la aparición de lazos recurrentes en las capas intermedias. Lo anterior permite una reducción del error en la modelación de procesos no lineales de lento comportamiento, como el crecimiento celular en biorreactores. El modelo se probó en una fermentación tipo feed-batch de la levadura Pichia pastoris. La estabilidad y capacidad de generalización es demostrada. El método propuesto es comparado con el GMDH típico recurrente y con otras estructuras de redes neuronales clásicas. Palabras clave: redes neuronales, recurrente, algoritmo genético, modelación, fermentación

  10. Paralelización del Algoritmo Criptográfico GOST Empleando el Paradigma de Memoria Compartida

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    Marlis Fulgueira-Camilo

    2015-06-01

    Full Text Available El artículo refiere el proceso de paralelización del algoritmo criptográfico GOST. La investigación realizada persigue como objetivo, reducir el tiempo de ejecución del algoritmo. El estudio no se encuentra enfocado al análisis de fortaleza del algoritmo criptográfico, donde se hace énfasis es en el método empleado para disminuir el tiempo de ejecución de los procesos cifre y descifre. Para ello se realiza un diseño paralelo basado en la metodología de Ian Foster, el cual es aplicado a dos implementaciones usando técnicas como: OpenMP y CUDA. Las comparaciones realizadas teniendo en cuenta, tanto al algoritmo secuencial como las implementaciones paralelas, demuestran una significativa reducción de tiempo, sin importar la técnica empleada. El mejor resultado se logra empleando CUDA.

  11. Algoritmo para el cálculo de la velocidad media óptima en una ruta (ASGA

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    V. Corcoba Magaña

    2014-10-01

    Full Text Available Resumen: En este trabajo se propone un algoritmo para obtener la velocidad media óptima para ahorrar combustible y mejorar la seguridad. El algoritmo propuesto se basa en los algoritmos genéticos. El algoritmo emplea información sobre el entorno, la carretera y el vehículo para obtener la velocidad media que minimice el consumo de combustible sin incrementar drásticamente la duración del trayecto. Además, el algoritmo propuesto mejora la seguridad ya que adecua la velocidad a las condiciones de la vía. La información sobre el entorno se obtiene de servicios web y la información sobre el vehículo se obtiene a través del puerto OBD2. El algoritmo es validado en situaciones reales con incidentes de tráfico y sin ellos. Por otra parte, se analiza el impacto de la velocidad media y los incidentes de tráfico en las aceleraciones y su influencia en el consumo de combustible. Abstract: This paper proposes an algorithm for obtaining the optimal average speed to save fuel and improve safety. The proposed algorithm is based on genetic algorithms. The algorithm uses information about the environment, the road and the vehicle for obtaining the optimal average speed which it minimizes fuel consumption without dramatically increasing the travel time. Moreover, the proposed algorithm improves safety adapting vehicle speed to road conditions. The environment information is obtained from web services and vehicle information is obtained through the OBD2 port. The algorithm is validated in situations with and without incidents. In addition, we analyze the impact of the average speed and acceleration incidents and their impact on fuel consumption. Palabras clave: Conducción eficiente, Sistemas de ayuda a la conducción, Algoritmos Genéticos, Android, Sistemas Inteligentes de Transporte., Keywords: Eco-driving, Advanced Driver Assistance Systems, Genetic Algorithms, Android, Intelligent Transport System.

  12. Algoritmo genético e espectroscopia no infravermelho - algumas aplicações na indústria cosmética

    OpenAIRE

    Marcos Coelho Amendola

    2007-01-01

    Este trabalho discute o desenvolvimento de um algoritmo genético escrito em linguagem VBA para Excel e suas aplicações. O algoritmo elaborado foi utilizado em combinação com a técnica de FTIR-ATR para o desenvolvimento de metodologias aplicáveis na indústria cosmética e de saneantes, tais como a quantificação de surfactantes e bactericidas. Algumas modificações introduzidas no algoritmo foram estudadas através das aplicações selecionadas, destacando-se a introdução de técnicas de paralelismo ...

  13. Algoritmos rápidos de detecção de colisão broad phase utilizando KD-trees

    OpenAIRE

    Rocha, Rafael de Sousa

    2010-01-01

    Neste trabalho, três novos algoritmos rápidos de detecção de colisão broad phase, os quais utilizam a estrutura de particionamento espacial conhecida como KD-Tree, foram pro- postos e implementados: KDTreeSpace, DynamicKDTreeSpace e StatelessKDTreeSpace. Estes algoritmos foram integrados à biblioteca Open Dynamics Engine (ODE), responsável pelo cálculo do movimento dos objetos dinâmicos, como possíveis alternativas aos algoritmos de broad phase disponíveis nesta biblioteca. Os algori...

  14. Análise de desempenho de algoritmos evolutivos no domínio do futebol de robôs

    OpenAIRE

    Eduardo Sacogne Fraccaroli

    2010-01-01

    Muitos problemas de otimização em ambientes multiagentes utilizam os algoritmos evolutivos para encontrar as melhores soluções. Uma das abordagens mais utilizadas consiste na aplicação de um algoritmo genético, como alternativa aos métodos tradicionais, para definir as ações dos jogadores em um time de futebol de robôs. Entretanto, conforme relatado na literatura, há inúmeras possibilidades e formas de se aplicar um algoritmo genético no domínio do futebol de robôs. Assim sendo, neste trabalh...

  15. Algoritmo para el tratamiento mínimamente invasivo de la coledocolitiasis

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    Javier Ernesto Barreras González

    Full Text Available La coledocolitiasis se presenta en más del 10 % de los pacientes jóvenes sometidos a la colecistectomía laparoscópica y se incrementa por encima de 25 % en los pacientes mayores de 60 años. Una vez que se identifica el cálculo en la vía biliar principal (VBP, esto puede convertirse en un dilema terapéutico. En la actualidad, diferentes algoritmos se han planteado y están establecidos, pero las publicaciones internacionales continúan redefiniendo las indicaciones de la colangiopancreatografía retrógrada endoscópica sobre la exploración laparoscópica de la vía biliar principal y viceversa. El objetivo de este estudio fue presentar el algoritmo para el tratamiento de la coledocolitiasis del Centro Nacional de Cirugía de Mínimo Acceso de La Habana. Se realizó una amplia revisión bibliográfica acerca del manejo actual de la coledocolitiasis con vesícula in situ y se evaluaron los resultados de dichas técnicas en el Centro Nacional de Cirugía de Mínimo Acceso. Las opciones para el manejo de la coledocolitiasis incluyen la exploración transcística de la vía biliar principal, la exploración laparoscópica de la vía biliar principal mediante coledocotomía, la colangiopancreatografía retrógrada endoscópica preoperatoria e intraoperatoria con esfinterotomía. Se presenta el algoritmo para el tratamiento mínimamente invasivo de la coledocolitiasis. El manejo de esta enfermedad en la actualidad depende de la experiencia de cada equipo quirúrgico y de su disponibilidad de acceso a los avances tecnológicos.

  16. Algoritmo PSO para identificación de parámetros en un motor DC

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    César Duarte

    2010-01-01

    Full Text Available En este artículo se presenta la aplicación del algoritmo Particle Swarm Optimization (PSO como estrategia de búsqueda para determinar los parámetros de un sistema tipo caja gris. Este proceso de identificación se ilustra utilizando la respuesta a un escalón de un motor DC en lazo abierto. Para agilizar la identificación del sistema a través del uso de PSO, se limita el espacio de búsqueda usando la información que puede extraerse de la respuesta en el dominio del tiempo del sistema a identificar. Los resultados del proceso de identificación de los parámetros del motor se obtienen utilizando la herramienta PSOt disponible para entorno Matlab® desarrollada por Brian Birge.

  17. ALGORITMO PARA DISEÑAR LÍNEAS DE TRANSMISIÓN CON CABLES PROTECTORES SEGMENTADOS

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    Héctor Silvio Llamo Laborí

    2011-02-01

    Full Text Available En las líneas de transmisión a voltajes de 220 kV y mayores, el valor de las pérdidas en loscables protectores puede justificar económicamente su segmentación para reducirlas a cero.Se presentan los resultados y las características de un algoritmo para diseñar o comprobar eldiseño de esquemas de cables protectores segmentados a partir de calcular el voltaje máximoinducido electromagnéticamente en los mismos.  In the 220 kV and higher transmission lines, the lost value in the ground wires can justifieseconomically its segmentation to reduce it to zero.Are presented the characteristics and results of an algorithm to design or test the schemesof segmented ground wires calculating the electromagnetic voltage induced on it.

  18. Un nuevo algoritmo para la optimación de estructuras: el recocido simulado

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    Vázquez Espí, Mariano

    1995-04-01

    método de resolución, salvo para ciertos casos particulares en los que la función y sus variables satisfacen condiciones específicas (continuidad, diferenciabilidad, etc.. En numerosos casos de índole práctica no se dan tales condiciones y, en consecuencia, la solución al problema se aproxima, existiendo para ello una variedad de métodos heurísticos. El recocido simulado es un algoritmo de aproximación a la solución óptima, fundado en una analogía con el comportamiento de sistemas termodinámicos simples y viene siendo utilizado en ciertos problemas de ingeniería. El presente trabajo muestra cómo usarlo en la teoría de estructuras, señalando sus ventajas (universalidad así como sus inconvenientes (lentitud. Para ello, se describen brevemente los distintos problemas de la teoría de estructuras, así como aspectos fundamentales de la teoría de algoritmos. Con mayor detalle, se describe la forma matemática del algoritmo de recocido. En ambos casos se emplea un problema paradigmático de optimación: el del viajante de comercio. Finalmente, se muestra el empleo del algoritmo para "aproximar" formas óptimas de cerchas isostáticas.

  19. Projeto de acopladores ópticos utilizando algoritmo genético

    OpenAIRE

    Jaqueline Oliveira Zampronio

    2016-01-01

    Resumo: Este projeto é uma proposta de um novo acoplador óptico para a aplicação em circuitos ópticos integrados. O dispositivo foi desenvolvido utilizando o método dos elementos finitos vetorial 3D associado com o algoritmo genético e leva em consideração guias de onda com diferentes altura, largura e índices de refração. O comprimento total do acoplador óptico é de apenas 4,22 µm e o seu funcionamento é baseado em pequenos segmentos cilíndricos que interferem na propagação da onda eletromag...

  20. Clasificación digital de masas nubosas a partir de imágenes meteorológicas usando algoritmos de aprendizaje de máquina

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    Salomón Einstein Ramírez-Fernández

    2014-01-01

    Full Text Available La identificación exacta de nubes precipitantes es una tarea difícil. En el presente trabajo se aplicaron los algoritmos Máquinas de Soporte Vectorial, Árboles de Decisión y Bosques Aleatorios para discriminar entre nubes precipitantes y nubes no precipitantes, a partir de una imagen meteorológica del satélite GOES-13 que cubre el territorio colombiano. El objetivo del trabajo fue evaluar el desempeño de los algoritmos de aprendizaje de máquina (ML, para la clasificación digital de masas nubosas, en términos de la exactitud temática de la clasificación usando como referencia el algoritmo convencional distancia de Mahalanobis. Los resultados muestran que los algoritmos ML proporcionan una clasificación de masas de nubes más exacta que la obtenida por algoritmos convencionales. La mejor exactitud fue obtenida usando Bosques Aleatorios (RF, con una exactitud temática global de 97%. Adicionalmente, la clasificación obtenida con RF fue comparada pixel a pixel con estimaciones de precipitación de la NASA Tropical Rainfall Measurement Mission (TRMM obteniendo una exactitud global del 94%. De acuerdo con este estudio, los algoritmos ML pueden ser usados para mejorar los actuales métodos de identificación de nubes precipitantes.

  1. MULTIOBJECTIVE EVOLUTIONARY ALGORITHMS APPLIED TO MICROSTRIP ANTENNAS DESIGN ALGORITMOS EVOLUTIVOS MULTIOBJETIVO APLICADOS A LOS PROYECTOS DE ANTENAS MICROSTRIP

    Directory of Open Access Journals (Sweden)

    Juliano Rodrigues Brianeze

    2009-12-01

    Full Text Available This work presents three of the main evolutionary algorithms: Genetic Algorithm, Evolution Strategy and Evolutionary Programming, applied to microstrip antennas design. Efficiency tests were performed, considering the analysis of key physical and geometrical parameters, evolution type, numerical random generators effects, evolution operators and selection criteria. These algorithms were validated through design of microstrip antennas based on the Resonant Cavity Method, and allow multiobjective optimizations, considering bandwidth, standing wave ratio and relative material permittivity. The optimal results obtained with these optimization processes, were confirmed by CST Microwave Studio commercial package.Este trabajo presenta tres de los principales algoritmos evolutivos: Algoritmo Genético, Estrategia Evolutiva y Programación Evolutiva, aplicados al diseño de antenas de microlíneas (microstrip. Se realizaron pruebas de eficiencia de los algoritmos, considerando el análisis de los parámetros físicos y geométricos, tipo de evolución, efecto de generación de números aleatorios, operadores evolutivos y los criterios de selección. Estos algoritmos fueron validados a través del diseño de antenas de microlíneas basado en el Método de Cavidades Resonantes y permiten optimizaciones multiobjetivo, considerando ancho de banda, razón de onda estacionaria y permitividad relativa del dieléctrico. Los resultados óptimos obtenidos fueron confirmados a través del software comercial CST Microwave Studio.

  2. Gerando orientações acíclicas com algoritmos probabilísticos distribuídos

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    Gladstone M. Arantes Jr

    2005-12-01

    Full Text Available Este artigo apresenta um novo algoritmo distribuído probabilístico para a geração de orientações acíclicas em um sistema distribuído anônimo de topologia arbitrária. O algoritmo é analisado tanto em termos de correção e complexidade esperada quanto velocidade de convergência. Em particular, é demonstrado que este novo algoritmo, chamado Alg-Arestas, é capaz de produzir, com alta probabilidade, orientações acíclicas quase instantaneamente, isto é, em menos de dois passos. Duas aplicações para essa forma de quebra de simetria serão discutidas: (i inicialização do Escalonamento por Reversão de Arestas (ERA, um simples e poderoso algoritmo de escalonamento distribuído, e (ii uma estratégia de distribuição de uploads em redes de computadores.This paper presents a new randomized distributed algorithm for the generation of acyclic orientations upon anonymous distributed systems of arbitrary topology. This algorithm is analyzed in terms of correctness and complexity as well as its convergence rate. In particular, it is shown that this new algorithm, called Alg-Arestas, is able to produce, with high probability, acyclic orientations quasi instantaneously, i.e., in less than two steps. Two applications of this form of symmetry breaking will be discussed: (i initialization of Scheduling by Edge Reversal (SER, a simple and powerful distributed scheduling algorithm, and (ii a strategy for distributed uploading in computer networks.

  3. Aplicativo para análise comparativa do comportamento de algoritmos de ordenação

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    João Paulo Folador

    2014-11-01

    Full Text Available Este artigo apresenta uma ferramenta prática de auxílio pedagógico para demonstrar o comportamento de alguns algoritmos de ordenação. Nesse contexto, foram estudados e confrontados os algoritmos: bubble sort, merge sort, quick sort e o shell sort, de modo a ordenar uma matriz de elementos variáveis. Na aplicação desenvolvida é permitido ao usuário configurar a quantidade de elementos da matriz a serem ordenados, quais métodos serão utilizados, a quantidade de ciclos somados e, o resultado final, é mostrado por meio de um gráfico, comparando os métodos aplicados. Ainda, como saída do processo de ordenação, são mostrados: o tempo médio de execução, o desvio padrão, o tempo mínimo e o tempo máximo gasto para ordenar os elementos da matriz. Desse modo, essa aplicação de apoio didático torna-se prática para testes feitos pelos alunos nas disciplinas que envolvem o estudo de algoritmos de ordenação facilitando, assim, o processo de aprendizagem.

  4. Diseño e integración de algoritmos criptográficos en sistemas empotrados sobre FPGA

    Directory of Open Access Journals (Sweden)

    Alejandro Cabrera Aldaya

    2013-10-01

    Full Text Available En este trabajo se integran implementaciones hardware de algoritmos criptográficos a la biblioteca OpenSSL la cual es utilizadapor aplicaciones sobre el sistema operativo Linux para asegurar redes TCP/IP. Los algoritmos implementados son el AES y las funciones resumen SHA-1 y SHA-256. Estos algoritmos son implementados como coprocesadores del procesador MicroBlaze utilizando interfaces FSL para el intercambio de datos entre ellos. Estos coprocesadores son integrados dentro de la biblioteca OpenSSL considerando la naturaleza multitarea del sistema operativo Linux, por lo que se selecciona un mecanismo de sincronización para controlar el acceso a estos dispositivos. Además son presentados los resultados de velocidad alcanzados por los coprocesadores integrados en la biblioteca utilizando la herramienta speed de la misma. Finalmente es presentado el impacto de estos coprocesadores en la velocidad de transmisión a través de una red privada virtual utilizando la herramienta OpenVPN.

  5. El problema del agente viajero: un algoritmo determinístico usando búsqueda tabú

    Directory of Open Access Journals (Sweden)

    Erasmo López

    2014-04-01

    Full Text Available Se implementa un algoritmo correspondiente al método Búsqueda Tabú, llamado EraDeterminístico, experimentado con el algoritmo básico que explora el espacio de búsqueda e incorporando la diversificación como estrategia para explorar nuevas regiones. El algoritmo se desarrolla en el ambiente de programación Visual Basic 6.0 y la implementación se orienta a encontrar soluciones cercanas a la óptima del problema NP−Completo del Agente Viajero Simétrico (AVS. Para probar la funcionalidad, el modelo se compara con algunas instancias de la Travel Salesman Problem Li- brary (TSPLIB, algunas instancias aleatorias y se aplica a tres situaciones reales. Finalmente, se presenta una sección donde se exponen recomendaciones y conclusiones, las cuales orientan posibles desarrollos futuros de ésta teoría y donde se pone en evidencian las bondades y la eficiencia de la implementación.

  6. Paralelización del Algoritmo Expectación–Maximización Utilizando OpenCL

    Directory of Open Access Journals (Sweden)

    Ernesto Insua-Suárez

    2014-12-01

    Full Text Available Actualmente, las organizaciones y empresas almacenan grandes volúmenes de datos para lograr sus propósitos. Una de las variantes para obtener información valiosa consiste en el empleo de la Minería de datos. Dentro de esta, existen diferentes tareas, una de ellas es el agrupamiento. En esta tarea los datos se agrupan según sus semejanzas entre si y diferencias con elementos de otros grupos. Dentro de los algoritmos que realizan estos agrupamientos se encuentra Expectación-Maximización, el cual presenta elevados tiempos de ejecución en la medida que aumenta el tamaño de los datos. En el presente artículo se discute acerca de la paralelización del algoritmo, utilizando técnicas de programación paralela. El diseño del algoritmo propuesto se basa en el uso de las tarjetas de procesamiento gráfico, GPU. OpenCL, lenguaje empleado para la programación en arquitecturas híbridas, permite aprovechar las arquitecturas de hardware disponibles, con lo que se logra disminuir el tiempo de ejecución de la implementación realizada. La razón principal por lo cual es posible mejorar este tiempo se debe a la cantidad de procesos paralelos que se pueden lanzar en hilos de procesamientos independientes. Para el logro de los resultados descritos se integran conocimientos del campo de la Minería de datos y la Computación Paralela y Distribuida. Como parte de esta investigación, se realizó una implementación del algoritmo utilizando las bibliotecas de OpenCL, para disminuir su tiempo de ejecución. La implementación logra disminuir en un 82% la implementación secuencial. Esto significa que el algoritmo paralelo se ejecuta 5,5 veces más rápido que su correspondiente implementación secuencial.

  7. Implementación del Algoritmo Sünter-Clare en un Convertidor Matricial 3x3

    Directory of Open Access Journals (Sweden)

    Eliher A. Ortiz Colín

    2017-10-01

    Full Text Available Resumen: En este trabajo se presenta la implementación digital del algoritmo de modulación de Sünter-Clare, para un convertidor matricial de tres hilos de 7.5 kVA. Este algoritmo es usado para calcular los ciclos de trabajo en un convertidor matricial 3x3, con lo que se generan tensiones de salida con amplitud y frecuencia constantes. El algoritmo de modulación de Sünter-Clare recalcula los tiempos y trayectorias de conmutación cada período de muestreo, con el objetivo de compensar las variaciones de amplitud y de frecuencia de las tensiones de entrada. Este algoritmo se ejecuta en cada muestreo y está en función de la tensión trifásica de entrada y de la tensión de referencia de salida, resultando adecuado para controles en lazo cerrado, cuando las señales de amplitud y de frecuencia de las tensiones de entrada son variables en el tiempo, como ocurre en los sistemas de generación de energía eléctrica a velocidad variable, que utilizan la energía del viento como fuente primaria de energía. El sistema de control para el trabajo experimental, además de la tarjeta del convertidor matricial, está compuesto por una tarjeta de arreglos de compuertas programable (FPGA y por un procesador digital de señales (DSP con una tarjeta de interfaz gráfica. Abstract: This paper presents the direct and easy way to implement digitally a Sünter-Clare modulation algorithm for a 7.5 KVA, three-wires, matrix converter. This modulation algorithm is used to calculate 3x3 matrix converter duty cycles to produce constant output voltage and frequency signals. The Sünter-Clare modulation algorithm recalculates switching patterns and switching times every sampling period in order to compensate the input voltage and frequency variations. This algorithm is defined in terms of the three-phase input and the output reference voltages at each sampling instant and is convenient for closed loop operations when the input voltage and frequency are variable in

  8. Algoritmo para Estimar los Saldos Netos Migratorios en entidades federativas mexicanas

    Directory of Open Access Journals (Sweden)

    Elmyra YBÁÑEZ-ZEPEDA

    2015-01-01

    Full Text Available En este artículo se describe el diseño, desarrollo e implementación de un Algoritmo para Estimar Saldos Netos Migratorios (ASNM en las entidades federativas de México mediante un modelo de distribución territorial de la población de Rogers en el que a través de la matriz de origendestino de la migración interna se incluyen el comportamiento del crecimiento natural y el de la inmigración y emigración internacional. Los datos requeridos son totalmente de base demográfica. Se buscó respetar al dato para que él hable por sí mismo a través de un modelo que le permita expresarse. Los resultados indican que de acuerdo con las cifras observadas por el censo de 2010 y a las estimadas por el ASNM para 2015, la contribución anual del SNM al total de la población por entidad federativa no representa más de tres por ciento.

  9. Algoritmo de tipo búsqueda tabú para un problema de programación de horarios universitarios vespertinos

    Directory of Open Access Journals (Sweden)

    Cristian David Oliva San Martín

    2013-07-01

    Full Text Available En este estudio se presenta un modelo de programación no lineal en variables enteras para un problema de programación de horarios universitarios vespertinos y se propone un algoritmo para su solución. El problema consiste en programar asignaturas en un horizonte de planificación considerando profesores, aulas, alumnos, días y un conjunto de restricciones, buscando minimizar la penalidad de no satisfacer los requerimientos de profesores, el número de cambios de sala y el número de periodos libres entre cursos. Se propone un modelo matemático y una implementación de un algoritmo de tipo búsqueda tabú. Para evaluar la efectividad del algoritmo se utilizaron casos de prueba con datos reales del Instituto IPEGE (Chile, en los que el algoritmo es capaz de obtener soluciones factibles en un tiempo razonable. Los parámetros de dicho algoritmo fueron calibrados con los casos de prueba, para posteriormente evaluar su desempeño. Se muestra que este obtuvo mejores soluciones que el método manual.

  10. Algoritmo evolucionário para otimização do plano de tratamento em radioterapia conformal 3D

    Directory of Open Access Journals (Sweden)

    Marco César Goldbarg

    2009-08-01

    Full Text Available O planejamento do tratamento por radioterapia tem por objetivo atingir um volume alvo com altas doses de radiação tomando cuidado para não expor órgãos sadios a doses elevadas. É, portanto, muito importante que se encontre um balanço ideal entre esses objetivos conflitantes. O presente trabalho relata um modelo de programação matemática multiobjetivo e introduz um Algoritmo Transgenético para o problema de seleção do direcionamento dos feixes de radiação no planejamento em radioterapia conformal 3D. A seleção das direções dos feixes é feita através de uma técnica denominada de isocentros variáveis. Com a finalidade de testar o potencial do algoritmo desenvolvido, realiza-se um experimento comparativo com um Algoritmo Genético Multiobjetivo. O experimento computacional obtém dados quantitativos e qualitativos que são analisados no trabalho.The radiotherapy treatment planning aims to achieve a target volume with high doses of radiation taking care not to expose healthy organs to high doses. It is therefore very important to find an optimal balance between these conflicting goals. This paper reports a mathematical model of multiobjective programming and presents a Transgenetic Algorithm for the problem of selecting the direction of radiation beams in 3D conformal radiotherapy planning. The selection of beams directions is done with a technique called variable isocenters. In order to test the potential of the developed algorithm, a comparative experiment with a multiobjective genetic algorithm was done. The computational experiment obtains quantitative and qualitative data that are analyzed in this paper.

  11. UN ALGORITMO SAEM PARA EL PROBLEMA DE COMPLETACIÓN DE MATRICES // A SAEM ALGORITHM FOR MATRIX COMPLETION PROBLEMS

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    Anaís Frangeline Acuña Sosa

    2015-06-01

    Full Text Available In this work we dealt with matrix completion problem. This problem arises in different fields, for example, systems and control theory, image processing and collaborative filtering. Given a probabilistic matrix factorization model, we present an approach based on Bayesian statistics and a stochastic expectation maximization algorithm to retrieve an array of data from a sample of its inputs. The proposed method does not require regularization parameters and estimates the rank of the matrix, in contrast to the BPMF method. Our results show that the proposed method outperforms to an augmented lagrangian algorithm and the BPMF method in its ability to find the rank of the matrix and in efficiency respectively. // RESUMEN En este trabajo estudiamos el problema de completación de matrices. Este problema se presenta en diversas áreas como la teoría de sistemas y control, procesamiento de imágenes y filtrado colaborativo. Considerando un modelo de factorización probabilística de matrices, establecemos una propuesta basada en estadística Bayesiana y un algoritmo EM estocástico para recubrir una matriz de datos a partir de una muestras de sus entradas. El método propuesto no requiere de parámetros de regularización y da un estimado del rango de la matriz, en contraste con el método BPMF. Los resultados muestran que el algoritmo propuesto da mejores estimados del rango de la matriz en comparación con un algoritmo basado en lagrangeanos aumentados y es más eficiente que el método BPMF.

  12. Diseño óptimo de un sistema de distribución de agua (SDA aplicando el algoritmo Simulated Annealing (SA

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    Maikel Méndez-Morales

    2014-09-01

    Full Text Available En este artículo se presenta la aplicación del algoritmo Simulated Annealing (SA en el diseño óptimo de un sistema de distribución de agua (SDA. El SA es un algoritmo metaheurístico de búsqueda, basado en una analogía entre el proceso de recocido en metales (proceso controlado de enfriamiento de un cuerpo y la solución de problemas de optimización combinatorios. El algoritmo SA, junto con diversos modelos matemáticos, ha sido utilizado exitosamente en el óptimo diseño de SDA. Como caso de estudio se utilizó el SDA a escala real de la comunidad de Marsella, en San Carlos, Costa Rica. El algoritmo SA fue implementado mediante el conocido modelo EPANET, a través de la extensión WaterNetGen. Se compararon tres diferentes variaciones automatizadas del algoritmo SA con el diseño manual del SDA Marsella llevado a cabo a prueba y error, utilizando únicamente costos unitarios de tuberías. Los resultados muestran que los tres esquemas automatizados del SA arrojaron costos unitarios por debajo del 0.49 como fracción, respecto al costo original del esquema de diseño ejecutado a prueba y error. Esto demuestra que el algoritmo SA es capaz de optimizar problemas combinatorios ligados al diseño de mínimo costo de los sistemas de distribución de agua a escala real.

  13. ESTIMACIÓN ROBUSTA DE MODELOS ADITIVOS MEDIANTE EL ALGORITMO DE BACKFITTING

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    Luis P. Yapu Quispe

    2012-07-01

    Full Text Available En este trabajo se presenta un método de estimación y simulación de un modelo aditivo a dos variables mediante splines robustos, el método general puede ser aplicado con varias variables. El software utilizado para las simulaciones es S+ y se utiliza explícitamente la función smooth.splineRob en una implementación del algoritmo de backfitting. La función smooth.splineRob ha sido escrita en base al trabajo de Cantoni y Ronchetti [3], en el cual se pone énfasis en la selección robusta del parámetro de suavizamiento utilizando una versión robusta del Cp de Mallows, RCp, y de la validación cruzada, RCV. La existencia de datos extremos o no-normales en la parte estocástica de un modelo aditivo puede provocar una mala estimación del parámetro de suavizamiento, lo que tendrá influencia global en la estimación por splines. Para la etapa de simulación se realizan las estimaciones por splines clásicos y robustos (con estimación robusta del parámetro. La estimación obtenida es muy convincente pero el tiempo de ejecución del programa es relativamente elevado tanto para RCp y RCV, aun cuando, en ciertos casos, con pocas iteraciones robustas se obtienen ya resultados más útiles que la estimación clásica.

  14. ALGORITMOS DE APRENDIZAGEM DE MÁQUINA E VARIÁVEIS DE SENSORIAMENTO REMOTO PARA O MAPEAMENTO DA CAFEICULTURA

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    Carolina Gusmão Souza

    Full Text Available A cafeicultura é uma das principais culturas agrícolas do Brasil e realizar o mapeamento e monitoramento desta cultura é fundamental para conhecer sua distribuição espacial. Porém, mapear estas áreas utilizando imagens de Sensoriamento Remoto não é uma tarefa fácil. Sendo assim, este trabalho foi realizado com o objetivo de comparar o uso de diferentes variáveis e algoritmos de classificação para o mapeamento de áreas cafeeiras. O trabalho foi desenvolvido em três áreas diferentes, que são bastante significativas na produção de café. Foram utilizados 5 algoritmos de aprendizagem de máquinas e 7 combinações de variáveis: espectrais, texturais e geométricas, associadas ao processo de classificação. Um total de 105 classificações foram realizadas, 35 classificações para cada uma das áreas. As classificações que não usaram variáveis espectrais não resultaram em bons índices de acurácia. Nas três áreas, o algoritmo que apresentou as melhores acurácias foi o Support vector machine, com acurácia global de 85,33% em Araguari, 87% em Carmo de Minas e 88,33% em Três Pontas. Os piores resultados foram encontrados com o algoritmo Random Forest em Araguari, com acurácia global de 76,66% e com o Naive Bayes em Carmo de Minas e Três Pontas, com 76% e 82% de acerto. Nas três áreas, variáveis texturais, quando associadas às espectrais, melhoraram a acurácia da classificação. O SVM apresentou o melhor desempenho para as três áreas

  15. Desarrollo de algoritmos de asignación de recursos en redes de acceso PON y TWDM-PON

    OpenAIRE

    Juárez Estévez, David

    2017-01-01

    El estudio de investigación realizado y descrito en este Trabajo Fin de Grado (TFG) se ha centrado en el desarrollo de algoritmos de gestión de recursos en redes PON (Passive Optical Network) y TWDM-PON (Time Wavelength Division Multiple Passive Optical Network), cuya arquitectura está implementada en un simulador bajo el entorno de simulación OMNET++. Así pues, inicialmente, se realizó un análisis de las redes de acceso PON, además del entorno de trabajo sobre el cual se iba a realizar es...

  16. Refuerzo de puentes por cambio de esquema estructural: optimización mediante algoritmo genético

    OpenAIRE

    Valenzuela, Matías A.; Casas Rius, Joan Ramon

    2011-01-01

    La presente comunicación entrega un estudio detallado del proceso constructivo y de tesado para el refuerzo de puentes con tipología longitudinal de vigas continuas convirtiéndolos en puentes en arco atirantado (tipo network). Se presentan las etapas básicas propuestas en aspectos de construcción, se establecen las hipótesis del estudio de tesado e implementa el método de tesado a partir de la optimización automatizada mediante algoritmos genéticos, definiendo criterios como: variables de ...

  17. Modelo origen destino para estimar el flujo de tráfico usando algoritmos genéticos

    OpenAIRE

    Aldás S., Milton R.; Flores C., Marco J.; Universidad de Cuenca; Dirección de Investigación de la Universidad de Cuenca; DIUC

    2014-01-01

    En este trabajo se ha desarrollado un nuevo método basado en Inteligencia Artificial para resolver un problema del matriz origen-destino (O-D) aplicado al caso de una red de tráfico vehicular en la ciudad de Ambato. El método implementado, basado en algoritmos genéticos (AG), resuelve el problema de minimización asociado al problema de matriz O-D. Para validar la técnica, se ha utilizado una red vial correspondiente a la zona del Mercado Modelo en la ciudad de Ambato, que es una zona de alta ...

  18. Selección y evaluación de algoritmos para clasificación de documentos

    OpenAIRE

    Vergara García, Paula María

    2014-01-01

    Este trabajo ha consistido en un estudio sobre la clasificación de documentos en castellano, basándose en el estándar IPTC. Para ello se ha utilizado un conjunto de ejemplos formado por documentos previamente etiquetados. Partiendo de los distintos tipos de aprendizaje, los algoritmos de clasificación, las herramientas de las que se disponía para la clasificación y las características de conjunto de ejemplos, se decidió utilizar las librerías proporcionadas por las herramientas Mahout, Had...

  19. Algoritmo eficiente para cálculo de mapas de visibilidade em terrenos armazenados em memória externa

    OpenAIRE

    Magalhães, Mirella Antunes de

    2009-01-01

    Com a maior disponibilidade de dados detalhados de terrenos, muitas aplicações precisam processar grandes áreas geográficas em alta resolução. O processamento massivo de dados envolvido em tais aplicações criou grandes desafios para os SIGs e necessita de algoritmos otimizados tanto para processamento interno quanto para transferência de dados. Uma dessas aplicações é o cálculo de mapas de visibilidade ou viewshed, que consiste em obter o conjunto de pontos visíveis a partir de um ponto p. Ne...

  20. Algoritmos relax-and-cut para problemas de programação inteira 0-1

    OpenAIRE

    Victor Fernandes Cavalcante

    2008-01-01

    Resumo: Uma das principais motivações para o estudo de Otimização Discreta reside no elevado número de problemas do nosso cotidiano representáveis através de modelos de Otimização Inteira e Combinatória. Em particular, muitos destes problemas podem ser formulados com Programação Inteira 0-1, o que desperta especial interesse em técnicas capazes de resolver tais modelos. Dentre as inúmeras formas de solução atualmente disponíveis para problemas desta natureza, os algoritmos baseados na técnica...

  1. Minimización de una función normal-merit mediante un algoritmo convergente globalmente

    Directory of Open Access Journals (Sweden)

    Gómez Suárez, M.

    1998-01-01

    Full Text Available En este trabajo presentamos dos conceptos relacionados con la solución de sistemas de ecuaciones no lineales y con desigualdades. El primer concepto es el de una función normal merit, que resume las propiedades básicas que tienen distintas funciones merit conocidas. El segundo concepto es el de un operador Newtoniano, cuyos valores generalizan el concepto de Hessiana para la función normal merit. Combinando el resultado del método generalizado de Newton con ciertos métodos de primer orden, obtenemos un algoritmo de convergencia global para minimizar funciones normales merit.

  2. Algoritmos GRASP para el equilibrado de líneas con riesgo ergonómico mínimo

    OpenAIRE

    Bautista Valhondo, Joaquín; Alfaro Pozo, Rocío; Batalla García, Cristina; Llovera Laborda, Sara

    2015-01-01

    Resumen - Se presenta un problema de equilibrado de líneas de montaje con ciclo compatible y número fijo de estaciones con el objetivo de minimizar el máximo riesgo ergonómico presente en las estaciones de trabajo. Tras la formu lación de un modelo matemático para el problema, se proponen procedimientos GRASP para su resolución. Los procedimientos incorporan un algoritmo greedy para regularizar el riesgo ergonómico así como diferentes tipos de mejora local. De...

  3. Obstáculos epistemológicos en la enseñanza de estructura de datos y algoritmos

    OpenAIRE

    Pérez, Daniel; Aguirre, Sofía; Filippi, José Luis

    2016-01-01

    [4 p.] il. Los obstáculos epistemológicos bajo la forma de saber-cristalizado generan una suerte de inercia que dificulta el proceso de construcción de un nuevo saber. Su abordaje es necesario para minimizar su impacto negativo y lograr mejoras en los procesos de enseñanza y aprendizaje. El objetivo de este trabajo es identificar los obstáculos que impiden a los alumnos de Estructura de datos y algoritmos de la Facultad de Ingeniería de la Universidad Nacional de La Pampa resolver satis...

  4. Algoritmos de visión para la estimación robusta de pose 3D

    OpenAIRE

    Iglesias García, Marcos

    2010-01-01

    El desarrollo de nuevos algoritmos en el campo de la visión artificial permite dotar a los robots móviles de una mayor autonomía en su funcionamiento. Si el autómata conoce el espacio que le rodea, es capaz de interactuar con el medio y realizar múltiples tareas. Tradicionalmente, los robots están equipados con microprocesadores, ordenadores a bordo que les permiten procesar la información que reciben y actuar en consecuencia. Sin embargo, carecen de inteligencia, lo que les impide reaccionar...

  5. Relleno de huecos en mallas 3D completas mediante algoritmos de restauración de imagen

    Directory of Open Access Journals (Sweden)

    Emiliano Pérez Hernàndez

    2012-10-01

    Full Text Available Resumen: En este artículo se propone un método para rellenar huecos en objetos 3D. La idea principal es la de utilizar un algoritmo de restauración de imágenes para reconstruir las partes que se han de completar. Para ello es necesario hacer una transformación de los datos de la superficie 3D en datos de imagen 2D. Por tanto, el algoritmo propuesto parte de una etapa inicial de identificación de huecos. A continuación se hace la selección, para cada hueco, de una porción de malla representativa. Seguidamente se calcula el punto de vista o plano de proyección adecuado para obtener una imagen de rango de esa porción de malla. A la imagen de rango obtenida se le aplica el algoritmo de restauración de imagen. Finalmente, se aplica una transformación inversa 2D a 3D y se integra el éresultado con la malla inicial. Se trata de un algoritmo robusto, válido para diversos tipos de huecos y diferentes tamaños de los mismos. Abstract: In this work a method for filling holes in 3D meshes based on a 2D image restoration algorithm is expounded. To do that, data must be converted to a suitable input format, a 3D to 2D transformation is executed by projecting the 3D surface onto a grid. Therefore, the proposed algorithm starts by a first stage of holes identification. Then, a meaningful mesh portiéon is choosen for each hole. Afterward, the suitable plane of projection must be computed to get the range image of the mesh portion. Later, it is applied the restauration image algorithm to the range image. Finally, an inverse transformation 2D to 3D is performed and the new produced data are integrated with the initial mesh. The result is a robust algorithm which works correctly with several kind of holes and for di_erent sizes of them. Palabras clave: visión por computador, gráficos por computador, imágenes digitales, imágenes de rango, restauración de imágenes, Keywords: computer vision, computer graphics, digital images, range images

  6. Aplicação do algoritmo de contraponto dissonante de Tenney na determinação de parciais em espectros de sons concretos

    Directory of Open Access Journals (Sweden)

    Raphael Santos

    2014-05-01

    Full Text Available Neste artigo, propomos um sistema para determinação de harmonias espectrais extraídas de sons concretos a partir da utilização do algoritmo de contraponto dissonante, desenvolvido por James Tenney. Com base nesse algoritmo, definimos um sistema composicional, descrevemos sua implementação como aplicativo computacional e o utilizamos no planejamento composicional de duas obras originais: o primeiro movimento de um quarteto de clarinetes e um quinteto de metais.

  7. Un algoritmo de clasificación incremental basado en los k vecinos más similares para datos mezclados

    Directory of Open Access Journals (Sweden)

    Guillermo Sánchez-Díaz

    2013-01-01

    Full Text Available En este trabajo, se presenta un algoritmo de clasificación incremental basado en los k vecinos más similares, el cual permite trabajar con datos mezclados y funciones de semejanza que no necesariamente son distancias. El algoritmo presentado es adecuado para procesar grandes conjuntos de datos, debido a que sólo almacena en la memoria principal de la computadora los k vecinos más similares procesados hasta el paso t, recorriendo una sola vez el conjunto de datos de entrenamiento. Se presentan resultados obtenidos con diversos conjuntos de datos sintéticos y reales.

  8. Combinación entre Algoritmos Genéticos y Aleatorios para la Programación de Horarios de Clases basado en Ritmos Cognitivos

    OpenAIRE

    Castrillón, Omar D

    2014-01-01

    Se ha diseñado un método basado en algoritmos evolutivos (genéticos y aleatorios) para programar los horarios de clases en una universidad. Esta metodología considera los ritmos cognitivos de los estudiantes que indican que es mejor enseñar algunas asignaturas en intervalos específicos de tiempo. Primero se describen las diferentes técnicas empleadas para desarrollar este problema. Luego se propone una nueva metodología basada en ritmos cognitivos y algoritmos evolutivos, para resolver todas ...

  9. Algoritmo de cifrado simétrico AES : Aceleración de tiempo de cómputo sobre arquitecturas multicore

    OpenAIRE

    Pousa, Adrián

    2011-01-01

    El objetivo de este trabajo es mostrar la aceleración en el tiempo de cómputo del algoritmo criptográfico Advanced Encryption Standard (AES) con clave de tamaño 128bits, que se obtiene al aprovechar el paralelismo que proveen las arquitecturas multicores actuales utilizando herramientas de programación paralela. AES es uno de los algoritmos de criptografía más usados en la actualidad, con el crecimiento de las redes y la información que se maneja hoy en día puede ser necesario cifra...

  10. Algoritmos paralelos numéricos para a resolução de sistemas de equações lineares

    OpenAIRE

    Maria Paula Goncalves Fachin

    1989-01-01

    Apresentamos as características de algoritmos para obter a solução de sistemas de equações lineares, utilizando computadores com arquitetura paralela e explorando os recursos de paralelismo neles embutidos. São descritos os modelos de computadores paralelos e os procedimentos para a criação de algoritmos paralelos. The characteristics of algorithms to solve systems of linear equations, using parallel computers, are presented. The abstract models of these computers are described, as well as...

  11. Algoritmo genético permutacional para el despliegue y la planificación de sistemas de tiempo real distribuidos

    OpenAIRE

    Azketa, Ekain; Gutiérrez, J. Javier; Di Natale, Marco; Almeida, Luís; Marcos, Marga

    2013-01-01

    Resumen: El despliegue y la planificación de tareas y mensajes en sistemas de tiempo real distribuidos son problemas NP-difíciles (NP- hard), por lo que no existen métodos óptimos para solucionarlos en tiempo polinómico. En consecuencia, estos problemas son adecuados para abordarse mediante algoritmos genéricos de búsqueda y optimización. En este artículo se propone un algoritmo genético multiobjetivo basado en una codificación permutacional de las soluciones para abordar el despli...

  12. Algoritmo de programação de máquinas individuais com penalidades distintas de adiantamento e atraso

    Directory of Open Access Journals (Sweden)

    Emerson C. Colin

    2000-06-01

    Full Text Available Neste trabalho consideramos o problema de máquina única, com datas de entrega e penalidades de adiantamento e atraso distintas para cada ordem. Considerando que a seqüência seja predefinida, o objetivo a ser alcançado é a minimização da soma das diferenças (adiantamentos ou atrasos penalizadas das ordens. Este trabalho é apresentado como uma generalização do algoritmo de programação de Garey et al. (1988. Através de uma estrutura computacional denominada fila de prioridade, este novo algoritmo permite a elaboração de um programa em tempo O(nlogn, enquanto que o melhor encontrado na literatura atualmente é de tempo O(n².In this work we consider the one machine problem, with distinct due-dates and penalties for earliness and tardiness. For a previously defined sequence, we utilize the sum of weighted lateness (earliness or tardiness as objective function. This work is presented as a generalization of the Garey et al. (1988 scheduling algorithm. Using a computational structure called heap, this algorithm allows a schedule construction in O(nlogn time while the best found in literature runs in O(n².

  13. Redes de Petri: Modelado e implementación de algoritmos para autómatas programables

    Directory of Open Access Journals (Sweden)

    Luis Diego Murillo

    2008-04-01

    Full Text Available El presente trabajo es una monografía orientada hacia la utilización del formalismo de las Redes de Petri, propuesto por Carl Petri en la descripción de Sistemas Dinámicos de Eventos Discretos (DEDS. Las Redes de Petri, cuyo acrónimo en inglés es PN, fueron utilizadas inicialmente para el análisis de algoritmos en la computación paralela o concurrente, pero dada la complejidad de los procesos productivos actuales, las PN son un método alternativo de diseño tanto para el procesoindustrial como para el controlador. En este sentido, este estudio hace una revisión de las referencias bibliográficas donde se indica cómo realizar el modelado y la implementación de algoritmos de control en Controladores Lógicos Programables (PLCs por sus siglas en inglés.

  14. Unificando los criterios de sepsis neonatal tardía: propuesta de un algoritmo de vigilancia diagnóstica

    Science.gov (United States)

    Zea-Vera, Alonso; Turin, Christie G.; Ochoa, Theresa J.

    2015-01-01

    Las infecciones constituyen una de las principales causas de muerte en el periodo neonatal. El diagnóstico de sepsis neonatal representa un gran desafío ya que los recién nacidos presentan signos clínicos muy inespecíficos y los exámenes auxiliares tienen una baja sensibilidad. Con el objetivo de mejorar el diagnóstico correcto de esta patología proponemos un algoritmo de vigilancia diagnóstica para sepsis neonatal tardía en el Perú y países de la región. El algoritmo permite clasificar a los episodios como sepsis confirmada, probable o posible, y sobretodo busca identificar aquellos episodios que no corresponden a sepsis, evitando calificar otras patologías como “sepsis”. Un mejor diagnóstico permitiría tener tasas más reales de sepsis neonatal, mejorar el uso de antibióticos y evitar sus efectos negativos en el recién nacido, así como una visión más exacta de su impacto en la salud pública. PMID:25123879

  15. Algoritmos Wavenet con Aplicaciones en la Aproximación de Señales: un Estudio Comparativo

    Directory of Open Access Journals (Sweden)

    C.R. Domínguez Mayorga

    2012-10-01

    Full Text Available Resumen: En este trabajo de investigación se aplican métodos adaptables en el diseño de algoritmos computacionales, dichos algoritmos emplean redes neuronales y series de wavelets para construir “neuroaproximadores” wavenets. Se muestra cómo las wavenets pueden combinarse con los métodos autosintonizables para obtener el seguimiento de señles complejas que están en función del tiempo. Los algoritmos obtenidos se aplican en la aproximación de señales que representan funciones algebraicas y funciones aleatorias, así como en una señal médica deun ECG. Se muestran los resultados en simulación numérica de dos arquitecturas de neuroaproximadores wavenets: el primero está basado en una wavenet, con el cual se aproximan las señales bajo estudio donde los parámetros de la red neuronal son ajustados en línea; el otro esquema emplea un filtro IIR a la salida de la red wavenet para discriminar las contribuciones de aquellas neuronas que tienen menos peso en la aproximación de la señal, lo que ayuda a reducir el tiempo de convergencia a un error mínimo deseado. Abstract: In this paper adaptable methods for computational algorithms are presented. These algorithms use neural networks and wavelet series to build neuro wavenets approximators. The algorithms obtained are applied to the approximation of signals that represent algebraic functions and random functions, as well as a medical EKG signal. It shows how wavenets can be combined with auto-tuning methods for tracking complex signals that are a function of time. Results are shown in numerical simulation of two architectures of neural approximators wavenets: the first is based on a wavenet with which they approach the signals under study where the parameters of the neural network are adjusted online, the other neuro approximator scheme uses an IIR filter to the output of wavenet, which serves to filter the out- put, in this way

  16. Algoritmos genéticos para la resolución de problemas de Programación por Metas Entera. Aplicación a la Economía de la Educación.

    Directory of Open Access Journals (Sweden)

    Caballero Fernández, Rafael

    2002-01-01

    Full Text Available En este trabajo se presenta un algoritmo genético para la resolución de problemas de Programación por Metas Entera. Este tipo de problemas presentan en general un gran número de dificultades para su resolución utilizando algoritmos tradicionales de Programación Entera, siendo en la mayoría de los casos de problemas reales demasiado costosa computacionalmente para afrontarla con garantías. Sin embargo, se mostrará como este nuevo tipo de algoritmos, los algoritmos genéticos, permiten resolver eficientemente problemas de este tipo con un coste computacional reducido. Como ejemplo, se resuelve en este trabajo un problema Economía de la Educación con un modelo de Programación por Metas Entera aplicando un algoritmo genético y un algoritmo tradicional. Para estas resoluciones se analiza el coste computacional de ambos tipos de resolución para poner de manifiesto las ventajas que puede suponer un algoritmo genético para la resolución de problemas reales complejos.

  17. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

    After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

  18. Control Adaptativo Fraccionario Optimizado por Algoritmos Genéticos, Aplicado a Reguladores Automáticos de Voltaje

    Directory of Open Access Journals (Sweden)

    Marco E. Ortiz-Quisbert

    2016-10-01

    Full Text Available Resumen: En este trabajo se presenta la técnica del control adaptable de orden fraccionario por modelo de referencia (CAOFMR, aplicada a los reguladores automáticos de voltaje (RAV. El artículo se enfoca en el ajuste de las ganancias adaptables y los órdenes de derivación de las leyes de ajuste del controlador CAOFMR, determinados por la minimización de una función criterio definida para el modelo simplificado del RAV, mediante la utilización de la técnica de optimización de algoritmos genéticos (AG. En base a un criterio de evaluación propuesto por otros autores, se realizan comparaciones, por medio de simulaciones, de la técnica de control propuesta con los resultados obtenidos por la técnica de control PID de orden entero (OEPID (Zamani et al., 2009. Se muestra que el controlador CAOFMR con parámetros optimizados por AG, entrega mejores resultados en términos de robustez frente a variaciones en los parámetros del sistema controlado y mejoras en relación a la velocidad de convergencia hacia las señales de referencia del sistema RAV. Abstract: The technique Fractional Order Model Reference Adaptive Control (FOMRAC applied to an Automatic Voltage Regulator (AVR is presented in this paper. The work is focused on tuning the adaptive gains and the derivation order of the adaptive laws of the FOMRAC, determined through the minimization of a criterion function defined for the simplified model of the AVR, by means of the genetic algorithm (GA optimization technique. Based on the criterion function proposed by other authors a simulated comparative study is performed, comparing the proposed methodology with the integer order PID control reported in (Zamani et al., 2009. It is shown that the FOMRAC with parameters optimized by GA provides better results in terms of robustness under parameters variations of the system under control and improvements in the convergence speed of the control error. Palabras clave: Control Adaptativo de

  19. Composición Musical a Través del Uso de Algoritmos Genéticos

    Directory of Open Access Journals (Sweden)

    Ezequiel Moldaver

    2014-06-01

    Full Text Available Este trabajo se enfocará en el uso de los algoritmos genéticos (AAGG con el fin de mezclar armonías y melodías de forma que se genere una composición musical de buen sonido para el oído, lo que significa que el contexto de cada nota respaldará la sonoridad de la misma provocando que no se genere un efecto disonante de forma permanente, que se genere una disonancia momentánea es permisible ya que es parte de la misma música generar tensión a través de pequeños intervalos poco agradables al oído.

  20. Paralelización de un algoritmo de compresión que utiliza diccionario estático

    OpenAIRE

    Ramón, Hugo Dionisio; Russo, Claudia Cecilia; Anderson, Alfredo; De Giusti, Armando Eduardo; Dirazar, Delio

    1996-01-01

    Es notoria la importancia creciente de la compresión de datos en la transmisión de información en redes. Aspectos como seguridad, reducción de tráfico, optimización del uso del canal, étc., justifican las tareas deinvestigación y desarrollo en este tema, así como la evolución de los recursos tecnológicos disponibles. En particular, por el volumen de información en juego, en los últimos años hay un esfuerzo muy notorio en la optimización de algoritmos para compresión de datos utilizando difere...

  1. Conformación de equipos de proyectos de software aplicando algoritmos metaheurísticos de trayectoria multiobjetivo

    Directory of Open Access Journals (Sweden)

    Ana Lilian Infante

    2014-12-01

    Full Text Available La inadecuada conformación de equipos de proyecto de software es un problema que afecta a la industria de software a nivel mundial. Este proceso resulta complejo, teniendo en cuenta que debe considerar varios factores, como son, asignar a los roles del equipo las personas con las competencias apropiadas, considerar las incompatibilidades entre los miembros y la carga de trabajo, entre otros. Esta situación se torna más compleja en organizaciones medianas y grandes, debido a la gran cantidad de combinaciones de asignaciones posibles, por lo que esta etapa es prácticamente imposible de abordar de manera eficiente, sin la ayuda de modelos matemáticos que representen el problema a resolver lo más objetivamente posible. Este trabajo toma como antecedente un modelo que incluye tanto factores individuales como factores de equipo y plantea: maximizar las competencias de los trabajadores, minimizar las incompatibilidades entre los miembros del equipo y balancear la carga de trabajo. Incluye además, en una versión ampliada del modelo, minimizar el costo de desarrollar software a distancia. El modelo citado responde a un problema de optimización combinatorio multiobjetivo, por lo que para su solución se utilizaron algunas variantes multiobjetivo de los algoritmos metaheurísticos: Búsqueda Tabú, Recocido Simulado y Escalador de Colinas. El estudio experimental realizado ha llevado a identificar que las variantes multiobjetivo del Escalador de Colinas: Escalador de Colinas Estocático Multiobjetivo, Escalador de Colinas Multiobjetivo por mayor distancia y Escalador de Colinas Multiobjetivo con Reinicio, así como el algoritmo Recocido Simulado Multiobjetivo Multicaso son los que mejores resultados obtienen en este problema.

  2. Algoritmo de um teste adaptativo informatizado com base na teoria da resposta ao item para a estimação da usabilidade de sites de e-commerce

    Directory of Open Access Journals (Sweden)

    Fernando de Jesus Moreira Junior

    2013-09-01

    Full Text Available O presente artigo propõe um algoritmo de um teste adaptativo informatizado baseado na teoria da resposta ao item, desenvolvido para estimar o grau de usabilidade de sites de e-commerce. Cinco algoritmos baseados no critério da máxima informação foram desenvolvidos e testados via simulação. O algoritmo com o melhor desempenho foi aplicado nos dados reais de 361 sites de e-commerce. Os resultados mostraram que o algoritmo desenvolvido consegue obter uma boa estimativa para o grau de usabilidade de sites de e-commerce com a aplicação de 13 itens.

  3. H Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

  4. Diseño e implementación de un algoritmo para translación de protocolo entre las normas IEC60870-5-104 y MODBUS TCP/IP

    OpenAIRE

    Feria Briceño, John Henry; Universidad Distrital Francisco José de Caldas

    2015-01-01

    Este artículo muestra los resultados del proceso de diseño, implementación y prueba de un algoritmo para hacer la translación de protocolo entre las normas IEC 60870-5-104 y MODBUS TCP/IP, éste modelo de algoritmos son de amplio uso en los procesos de supervisión y automatización en sub-estaciones eléctricas.

  5. Algoritmo genético permutacional para el despliegue y la planificación de sistemas de tiempo real distribuidos

    Directory of Open Access Journals (Sweden)

    Ekain Azketa

    2013-07-01

    Full Text Available Resumen: El despliegue y la planificación de tareas y mensajes en sistemas de tiempo real distribuidos son problemas NP-difíciles (NP- hard, por lo que no existen métodos óptimos para solucionarlos en tiempo polinómico. En consecuencia, estos problemas son adecuados para abordarse mediante algoritmos genéricos de búsqueda y optimización. En este artículo se propone un algoritmo genético multiobjetivo basado en una codificación permutacional de las soluciones para abordar el despliegue y la planificación de sistemas de tiempo real distribuidos. Además de desplegar tareas en computadores y de planificar tareas y mensajes, este algoritmo puede minimizar el número de computadores utilizados, la cantidad de recursos computacionales y de comunicaciones empleados y el tiempo de respuesta de peor caso medio de las aplicaciones. Los resultados experimentales muestran que este algoritmo genético permutacional puede desplegar y planificar sistemas de tiempo real distribuidos de forma satisfactoria y en tiempos razonables. Abstract: The deployment and scheduling of tasks and messages in distributed real-time systems are NP-hard problems, so there are no optimal methods to solve them in polynomial time. Consequently, these problems are suitable to be approached with generic search and optimisation algorithms. In this paper we propose a multi-objective genetic algorithm based on a permutational solution encoding for the deployment and scheduling of distributed real-time systems. Besides deploying and scheduling tasks and messages, the algorithm can minimize the number of the used computers, the utilization of computing and networking resources and the average worst-case response times of the applications. The experiments show that this genetic algorithm can successfully synthesize complex distributed real-time systems in reasonable times. Palabras clave: Sistemas de tiempo real, Algoritmos de planificaci

  6. Implantation of algorithms of diffuse control in DSPS; Implantacion de algoritmos de control difuso en DSPS

    Energy Technology Data Exchange (ETDEWEB)

    Perez C, B

    2003-07-01

    In this thesis work there are presented: a) The characteristics and main components used in an electronic system based on a Dsp guided to control applications of processes, b) The description of an algorithm of diffuse control whose objective is the regulation of neutron power in a model of the punctual kinetics of a nuclear research reactor type TRIGA, and c) The installation in language assembler and execution in real time of the control algorithm in the system based on a Dsp. With regard to the installation and execution of the algorithm, the reaches of the project have been delimited to the following: a) Readiness of the entrance values to the controller in specific registrations of the system Dsp, b) Conversion of the entrances to the numerical formats with those that one obtains the best acting in the control algorithm, c) Execution of the algorithm until the obtaining of the value of the controller's exit, and d) Placement of the result in specific registrations of the Dsp for their later reading for an external parallel interface. It is necessary to mention that the simulation of the punctual kinetics of a reactor type TRIGA in the Pc and its integration with the control system based on the one Dsp is had contemplated as continuation of this work and that one of those will constitute main activities in my project of master thesis. A brief description of the topics presented in this thesis is given next. In the chapter one it is presented a general description of the diffuse logic and some of their applications in the industry. The main characteristics of a Dsp are also presented that they make it different from a micro controller or a microprocessor of general purpose. In the chapter 2 details of the internal architecture of the Dsp TMS320CS0 of Texas Instruments that are not explained with detail in the manual of user of the same one. This chapter has as objective to understand the internal hardware of the Dsp that is used for to carry out the program in

  7. Implantation of algorithms of diffuse control in DSPS; Implantacion de algoritmos de control difuso en DSPS

    Energy Technology Data Exchange (ETDEWEB)

    Perez C, B

    2003-07-01

    In this thesis work there are presented: a) The characteristics and main components used in an electronic system based on a Dsp guided to control applications of processes, b) The description of an algorithm of diffuse control whose objective is the regulation of neutron power in a model of the punctual kinetics of a nuclear research reactor type TRIGA, and c) The installation in language assembler and execution in real time of the control algorithm in the system based on a Dsp. With regard to the installation and execution of the algorithm, the reaches of the project have been delimited to the following: a) Readiness of the entrance values to the controller in specific registrations of the system Dsp, b) Conversion of the entrances to the numerical formats with those that one obtains the best acting in the control algorithm, c) Execution of the algorithm until the obtaining of the value of the controller's exit, and d) Placement of the result in specific registrations of the Dsp for their later reading for an external parallel interface. It is necessary to mention that the simulation of the punctual kinetics of a reactor type TRIGA in the Pc and its integration with the control system based on the one Dsp is had contemplated as continuation of this work and that one of those will constitute main activities in my project of master thesis. A brief description of the topics presented in this thesis is given next. In the chapter one it is presented a general description of the diffuse logic and some of their applications in the industry. The main characteristics of a Dsp are also presented that they make it different from a micro controller or a microprocessor of general purpose. In the chapter 2 details of the internal architecture of the Dsp TMS320CS0 of Texas Instruments that are not explained with detail in the manual of user of the same one. This chapter has as objective to understand the internal hardware of the Dsp that is used for to carry out the program

  8. MINIMIZACIÓN DE UNA FUNCIÓN DE ORDEN P MEDIANTE UN ALGORITMO GENÉTICO // MINIMIZING A FUNCTION OF ORDER P USING A GENETIC ALGORITHM

    Directory of Open Access Journals (Sweden)

    Rómulo Castillo Cárdenas

    2013-06-01

    Full Text Available In this work we consider the problem OVO (order value optimization. The problem we address is to minimize f with x 2 by a genetic algorithm that by its very nature has the advantage over existing continuous optimization methods, to nd global minimizers. We illustrate the application of this algorithm on examples considered showing its e ectiveness in solving them.// RESUMEN En el presente trabajo consideramos el problema OVO (order value optimization. El problema que abordamos consiste entonces en minimizar f con x 2 por medio de un algoritmo gen etico que por su naturaleza intrínseca tiene la ventaja, sobre métodos de optimización continua existentes, de encontrar minimizadores globales. Ilus- tramos la aplicación de este algoritmo sobre ejemplos considerados mostrando su eficacia en la resolución de los mismos.

  9. Algoritmo especializado aplicado ao planejamento da expansÃo de redes aÃreas de sistemas de distribuiÃÃo

    OpenAIRE

    Willian Douglas Ferrari MendonÃa

    2014-01-01

    No presente trabalho à apresentado o desenvolvimento de um algoritmo especializado para o planejamento da expansÃo de redes aÃreas de sistemas de distribuiÃÃo. A tÃcnica utilizada para soluÃÃo à a HeurÃstica Construtiva que tem sido utilizada em conjunto com modelos matemÃticos de otimizaÃÃo para resolver o problema. No entanto o algoritmo apresentado nÃo emprega um modelo matemÃtico de otimizaÃÃo, em outras palavras, um modelo composto de funÃÃo objetivo e restriÃÃes. Assim, em vez de trabal...

  10. OTIMIZAÇÃO USANDO ALGORITMO GENÉTICO DE UM MODELO DE PROPAGÇÃO BASEADO EM EQUAÇÕES PARABÓLICAS

    Directory of Open Access Journals (Sweden)

    Antonio Carlos Vilanova

    2013-01-01

    Full Text Available Este artigo apresenta uma avaliação metodológica para otimizar parâmetros em um conhecido modelo de propagação de ondas de rádio na troposfera. O modelo de propagação é baseado no Divisor de passos de Fourier para resolver equações parabólicas. Nossa abordagem utiliza algoritmo genético para determinar os valores dos parâmetros que maximize a intensidade de campo em uma determinada posição do observador. Usando algoritmo genético o tempo necessário na busca dos parâmetros ótimos é reduzido significativamente. A avaliação preliminar dos resultados através da simulação mostra que a nossa abordagem é promissora.

  11. Algorithms for the evaluation of the reliability of networks and substations; Algoritmos para evaluar la confiabilidad de redes y subestaciones electricas

    Energy Technology Data Exchange (ETDEWEB)

    Vega Ortiz, Miguel [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

    2001-07-01

    Two algorithms are presented, one for analyzing the reliability of networks and another one to analyzing the reliability of electrical substations. The algorithms model a network or a substation by means of a graph and determine all the exits, of up to third degree, which isolates the load points. The algorithm that is used for the network analysis, is the one of p-cuts and in the case of the substations it is the one of minimum ways, for later, from these minimum p-cuts and of the minimum ways, obtains the minimum cuts. These minimum cuts are evaluated with the approximate method and give as a result the system reliability and of each one of the components that have been modeled. At the end some examples and results obtained are shown. As case of study, the algorithm is applied to two substations arrangements and to a network of industrial distribution, but it is possible to be applied to transmission and distribution networks. [Spanish] Se presentan dos algoritmos, uno para analizar la confiabilidad de redes y otro para analizar la confiabilidad de subestaciones electricas. Los algoritmos modelan una red o una subestacion por medio de un grafo y determinan todas las salidas, de hasta tercer grado, que aislan los puntos de carga. El algoritmo que se utiliza para el analisis de redes, es el de p-cortes y en el caso de las subestaciones es el de caminos minimos, para despues, a partir de estos p-cortes minimos y de los caminos minimos, obtener los cortes minimos. Estos cortes minimos se evaluan con el metodo aproximado y dan como resultado la confiabilidad del sistema y de cada una de las componentes que se hayan modelado. Al final se muestran algunos ejemplos y resultados obtenidos. Como caso de estudio, el algoritmo se aplica a dos arreglos de subestaciones y a una red de distribucion industrial, pero se puede aplicar a redes de transmision y de distribucion.

  12. Paradigma. Hacia el diseño y desarrollo de algoritmos y sistemas de control para clonación artificial en procesos industriales.

    Directory of Open Access Journals (Sweden)

    Jairo Amador

    2004-11-01

    Full Text Available Haciendo uso de Ia tecnología inteligente basada en la lógica difusa, las redes neuronales y los algoritmos genéticos, se pretende plantear un paradigma para la clonación artificial de dispositivos en procesos industriales, específicamente para sensores, los cuales deberán replicar las mismas o mejores funciones de los dispositivos reales mediante la evolución des comportamiento.

  13. METODOLOGÍA BASADA EN LOS ALGORITMOS VEGA Y MOGA PARA SOLUCIONAR UN PROBLEMA MULTIOBJETIVO EN UN SISTEMA DE PRODUCCIÓN JOB SHOP

    Directory of Open Access Journals (Sweden)

    Germán Augusto Coca Ortegón

    Full Text Available En este artículo se presenta una metodología que pretende minimizar de forma simultánea, en un ambiente de producción tipo "job shop" correspondiente a una empresa metalmecánica, las siguientes variables: tiempo de proceso, costo de mano de obra directa y, asimismo la fracción defectuosa generada por la fatiga del operario. Con este propósito se fusionan elementos de los algoritmos genéticos Vega y Moga, desarrollando para el efecto las siguientes etapas: generar la población inicial, conformar la nueva población, realizar análisis de varianza y por último, comparar con un método híbrido entre sumas ponderadas y algoritmos genéticos. De acuerdo con lo anterior, al evaluar el individuo de menor tiempo de proceso proveniente de la metodología basada en los algoritmos Vega y Moga, respecto al individuo de menor tiempo de desarrollo proveniente del método híbrido entre sumas ponderadas y algoritmos genéticos, se encuentra que el primero supera en desempeño al segundo así: en cuanto a la variable tiempo de proceso (en horas en 27,86%; en cuanto a la variable tiempo de proceso (en semanas en 1,25%; en cuanto a la variable costo de mano de obra directa (MOD en 6,73% y, en cuanto a la variable fracción defectuosa en 25,85%.

  14. Algoritmos Numéricos para el Problema de Restauración de Imágenes usando el Método de las Proyecciones Alternantes

    Directory of Open Access Journals (Sweden)

    René Escalante

    2011-04-01

    Full Text Available Los algoritmos de proyección han evolucionado a partir del algoritmo de proyección alternante propuesto por J. von Neumann en 1933, donde el espacio solución es la intersección de un número finito de subespacios o conjuntos convexos. Investigaciones recientes se han centrado en técnicas para acelerar la convergencia del método y explotar el multiprocesamiento. En este trabajo consideramos el problema de restauración de imágenes. La mayoría de las técnicas desarrolladas para resolverlo han usado algoritmos iterativos; una de ellas consiste en usar proyecciones ortogonales alternantes. Llevamos a cabo una revisión cronológica de las diferentes técnicas en las que se ha aplicado el método de las proyecciones ortogonales alternantes al problema de restauración de imágenes, hasta llegar al enfoque reciente de Combettes (1997-1999, en donde la restauración se basa en el cálculo de proyecciones aproximadas, en lugar de proyecciones exactas.

  15. ALGORITMO PARA EL ANÁLISIS PROBABILÍSTICO EN SISTEMAS DE DISTRIBUCIÓN CON GENERACIÓN DISTRIBUÍDA

    Directory of Open Access Journals (Sweden)

    CESAR AUGUSTO PEÑUELA MENESES

    2011-01-01

    Full Text Available Este artículo presenta un algoritmo eficiente para el análisis probabilístico de sistemas de distribución trifásicos desbalanceados con conexión de generadores distribuidos (sistemas levemente enmallados. Este algoritmo hace uso de la técnica del Método Estimado de Dos Puntos para el cálculo del comportamiento probabilístico de las variables aleatorias del sistema. Adicionalmente, y con el fin de explotar eficientemente las características topológicas de la red, el análisis determinístico de las variables de estado es realizado por medio de un Flujo de carga Radial Basado en Compensación (FCRBC. Para el tratamiento de la generacióndistribuida, se propone una estrategia para incorporar dentro del FCRBC un modelo simplificado del generador junto con un control de las variables de despacho en el punto de conexión con la red. De este modo, el nodo con generación distribuida puede ser modelado como un nodoPV, o nodo PQ, dependiendo del modo de control y de las condiciones operativas del generador. Para validar la eficiencia del algoritmo propuesto es usado el sistema de prueba IEEE de 37 nodos. Los resultados probabilísticos son comparados con los obtenidos usando el método de Monte Carlo.

  16. Prueba e implementación de algoritmos de control de calidad de datos de temperatura superficial del aire en un contexto operativo

    Directory of Open Access Journals (Sweden)

    José Araya

    2008-04-01

    Full Text Available Se presenta una metodología para el cálculo de rangos de temperatura, así como algoritmos de programación simple para la detección de errores obvios en datos meteorológicos con el fin de mostrar cómo un sistema de control de calidad sencillo, en tiempo real, puede implementarse de forma exitosa. Estos algoritmos fueron probados a través de su programación en un grabador de datos, el cual es el núcleo procesador en una estación meteorológica: primero, bajo condiciones controladas; y, luego, en dos estaciones meteorológicas automáticas con capacidad de transmisión en tiempo real. La investigación realizada muestra que estos algoritmos son efectivospara la detección de valores atípicos que de otra manera podrían ser detectados tardíamente y pasar inadvertidos.

  17. Algoritmos Evolutivos y su empleo en el ajuste de controladores del tipo PID: Estado Actual y Perspectivas

    Directory of Open Access Journals (Sweden)

    Gilberto Reynoso-Meza

    2013-07-01

    Full Text Available Resumen: Los controladores PID continúan siendo una solución fiable, robusta, práctica y sencilla para el control de procesos. Actualmente constituyen la primera capa de control de la gran mayoría de las aplicaciones industriales. De ahí que un número importante de trabajos de investigación se han orientado a mejorar su rendimiento y prestaciones. Las líneas de investigación en este campo van desde nuevos métodos de ajuste, pasando por nuevos tipos de estructura hasta metodologías de diseño integrales. Particularizando en el ajuste de parámetros, una de las formas de obtener una solución novedosa consiste en plantear un problema de optimización, el cual puede llegar a ser no-lineal, no-convexo y con restricciones. Dado que los algoritmos evolutivos han mostrado un buen desempeño para solucionar problemas complejos de optimización, han sido utilizados en diversas propuestas relacionadas con el ajuste de controladores PID. Este trabajo muestra un revisión de estas propuestas y las prestaciones obtenidas en cada caso. Así mismo, se identifican algunas tendencias y posibles líneas de trabajo futuras. Abstract: PID controllers are a reliable, robust, practical and easy to implement control solution for industrial processes. They provide the first control layer for a vast majority of industrial applications. Owing to this, several researches invest time and resources to improve their performance. The research lines in this field scope with new tuning methods, new types of structures and integral design methods. For tuning methods, improvements could be fulfilled stating an optimization problem, which could be non-linear, non-convex and highly constrained. In such instances, evolutionary algorithms have shown a good performance and have been used in various proposals related with PID controllers tuning. This work shows a review of these proposals and the benefits obtained in each case. Some

  18. RECONFIGURACIÓN DE REDES ELÉCTRICAS DE MEDIA TENSIÓN BASADA EN EL ALGORITMO DE PRIM RECONFIGURATION OF MEDIUM VOLTAGE NETWORKS BASED ON PRIM'S ALGORITHM

    Directory of Open Access Journals (Sweden)

    Angely Cárcamo-Gallardo

    2007-04-01

    Full Text Available En este trabajo se presenta un nuevo algoritmo que permite reconfigurar un sistema de distribución (SD de energía eléctrica minimizando la energía no suministrada (ENS. El SD se modela utilizando teoría de grafos, mientras que la ENS se formula recursivamente y se parametriza en términos de los índices de confiabilidad del SD. Empleando esta modelación se transforma el problema de optimización en el problema de encontrar el árbol de mínima expansión (AME a partir del grafo que modela al SD, donde la métrica de distancia utilizada corresponde a la ENS a cada nodo del SD. Para encontrar de manera eficiente el AME se utiliza el algoritmo de Prim, ya que pertenece a la clase de algoritmos voraces en el cálculo del AME. Adicionalmente, se propone un algoritmo que realiza una revisión del AME obtenido analizando las topologías que fueron descartadas aleatoriamente durante el proceso de decisión. El desempeño del algoritmo de optimización se evalúa en sistemas de pruebas y en dos sistemas eléctricos reales.This paper presents a novel algorithm to reconfigure an electric power distribution network (EPDN, minimizing its non-supplied energy (NSE. The EPDN is modeled using graph theory and the NSE is recursively formulated in terms of the reliability parameters of the EPDN. Based on this mathematical model, we transform the original optimization problem into the graph theory problem of finding the minimum spanning tree (MST of a given graph, which models the EPDN. The distance metric employed by the searching algorithm is the NSE. In order to efficiently find the MST, Prim's algorithm is employed due to is greedy search behavior. In addition, a backtracking algorithm is used to check the MST obtained. The backtracking algorithm analyzes all the candidate topologies that were randomly discarded during the decision process. The performance of the optimization algorithm is evaluated using testing systems and two actual EPDNs.

  19. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  20. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  1. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  2. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  3. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  4. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  5. Algoritmo para geolocalización de dispositivos móviles a partir de emisores de WIFI

    Directory of Open Access Journals (Sweden)

    María Portillo Montiel

    2015-04-01

    Full Text Available Esta investigación propone un método para la geolocalización de dispositivos móviles a partir de señales WiFi predeterminadas, prescindiendo del uso del GPS para evitar potenciales problemas de seguridad y malware. El método propuesto, se basa en la técnica conocida como Punto de Triangulación Aproximado (APIT y parte de una discretización del espacio de acción a partir de un conjunto base de emisores de señal WiFi de coordenadas y radios de acción máximos conocidos, para luego construir una rejilla que incluye las zonas de acción conjunta de todos los emisores al momento de activar la aplicación, es posible estimar con gran precisión la ubicación del dispositivo móvil determinando el área de intersección de las señales visibles en el momento. La implementación del algoritmo propuesto exhibe una complejidad temporal cuadrática respecto al tamaño de la rejilla y lineal sobre la cantidad de emisores iniciales.

  6. Claves en la aplicación del algoritmo Chaid. Un estudio del ocio físico deportivo universitario

    Directory of Open Access Journals (Sweden)

    Eva Sanz Arazuri

    2010-01-01

    Full Text Available El propósito de este artículo es argumentar y explicar la utilidad y el procedimiento de la segmentación jerárquica basada en el algoritmo CHAID como técnica de análisis multivariado. Para facilitar la comprensión de este proceso, la exposición del uso, así como, la interpretación de esta técnica nos hemos servido de una investigación realizada sobre el comportamiento físico-deportivo de tiempo libre de una población universitaria. Este estudio busca definir los perfiles de los universitarios en función de los distintos grados de satisfacción con su práctica físico-deportiva, así como, constatar la existencia de determinadas variables predictoras de dicha satisfacción al relacionar globalmente todas. En el artículo queda demostrada la valiosa capacidad que posee esta técnica de segmentación jerárquica para pronosticar y explicar determinados comportamientos, así como para determinar la relación causa-efecto de dichos comportamientos.

  7. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

    Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)

  8. Reactor decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1984-01-01

    A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

  9. RA Reactor

    International Nuclear Information System (INIS)

    1978-02-01

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation [sr

  10. Multiregion reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The study of reflected reactors can be done employing the multigroup diffusion method. The neutron conservation equations, inside the intervals, can be written by fluxes and group constants. A reflected reactor (one and two groups) for a slab geometry is studied, aplying the continuity of flux and current in the interface. At the end, the appropriated solutions for a infinite cylindrical reactor and for a spherical reactor are presented. (Author) [pt

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

    Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

  12. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  13. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  14. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  15. Un Algoritmo Genético Especializado en Planeamiento de Redes de Distribución. Parte II. Detalles del algoritmo y su aplicación; A specialized Genetic Algorithm in Distribution Network planning. Part II. Algorithm details and application

    Directory of Open Access Journals (Sweden)

    Raúl Nicolás Carvajal Pérez

    2011-05-01

    Full Text Available En la Parte I de este articulo, se expusieron las características de la planificación de redes y su influencia en la selección de métodos específicos en cada uno de los procedimientos para desarrollar los pasos del algoritmo genético especializado. Aquí se exponen las interioridades del algoritmo y el trabajo experimental para fijar la magnitud de los parámetros generales de las poblaciones y la cantidad de éstas. Se presentan casos resueltos durante el ajuste del sistema de cálculo.  The first section explained the specifics characteristics of network planning and the selected method for genetic operators. In this papers, expose details about the algorithm steps, the mathematical procedures and some applications.

  16. VALIDACIÓN DE UN ALGORITMO HÍBRIDO DEL PSO CON EL MÉTODO SIMPLEX Y DE TOPOLOGÍA DE EVOLUCIÓN PARAMÉTRICA

    OpenAIRE

    RODRIGO CORREA; OSCAR BEGAMBRE; JULIO C. CARRILLO E.

    2011-01-01

    Este artículo describe algunos de los aspectos más importantes relacionados con la experimentación numérica de un híbrido del algoritmo PSO (Particle Swarm Optimization) con el tradicional método simplex modificado de Nelder-Mead. El híbrido de estas dos técnicas de optimización sin restricciones se realizó con una topología que permite optimizar en cada iteración los parámetros del algoritmo PSO utilizando el método simplex modificado. Se realizaron experimentos numéricos con este algoritmo ...

  17. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  18. Estimativa do balanço de energia utilizando imagens TM - Landsat 5 e o algoritmo SEBAL no litoral sul de Pernambuco

    Directory of Open Access Journals (Sweden)

    Célia Cristina Machado

    2014-03-01

    Full Text Available As trocas de energia na interface solo-planta-atmosfera, por meio das componentes do balanço de radiação (Rn e dos fluxos de calor no solo (G, sensível (H e latente (LE, são essenciais para a modelagem climática e hidrológica que, por sua vez, afetam toda a biosfera. Dessa forma, esta pesquisa teve por objetivos: (1 estimar e comparar o comportamento dos componentes do balanço de energia, usando o algoritmo SEBAL - Surface Energy Balance Algorithm for Land, em diferentes tipos de uso e cobertura do solo e (2 validar o algoritmo. Para isso, foram usadas três imagens TM - Landsat 5 de órbita e ponto 214/066, com datas de passagem em 26 de agosto de 2006, 6 de setembro de 2010 e 28 de janeiro de 2011, todas recortadas para enquadrar o litoral sul de Pernambuco. Os resultados mostraram a capacidade do SEBAL de estimar a variabilidade espacial dos diferentes componentes do balanço de energia, com capacidade de distinguir diferentes ocupações do solo. O cômputo do balanço de energia possibilita observar as formas diferenciadas do uso da energia pelos diferentes tipos de cobertura do solo e verificar aqueles que propiciam melhor conforto térmico. As estimativas da evapotranspiração obtidas pelo algoritmo SEBAL apresentaram uma boa concordância com os resultados obtidos pelo método da FAO-Penman-Monteith demonstrando, dessa forma, a potencialidade da abordagem metodológica escolhida.

  19. Séries temporais de NDVI do sensor SPOT Vegetation e algoritmo SAM aplicados ao mapeamento de cana‑de‑açúcar

    Directory of Open Access Journals (Sweden)

    Luiz Eduardo Vicente

    2012-09-01

    Full Text Available O objetivo deste trabalho foi avaliar o mapeamento de área de cana‑de‑açúcar por meio de série temporal, de seis anos de dados do índice de vegetação por diferença normalizada (NDVI, oriundos do sensor Vegetation, a bordo do satélite "système pour l'observation de la Terre" (SPOT. Três classes de cobertura do solo (cana‑de‑açúcar, pasto e floresta, do Estado de São Paulo, foram selecionadas como assinaturas espectro‑temporais de referência, que serviram como membros extremos ("endmembers" para classificação com o algoritmo "spectral angle mapper" (SAM. A partir desta classificação, o mapeamento da área de cana‑de‑açúcar foi realizado com uso de limiares na imagem-regra do SAM, gerados a partir dos valores dos espectros de referência. Os resultados mostram que o algoritmo SAM pode ser aplicado a séries de dados multitemporais de resolução moderada, o que permite eficiente mapeamento de alvo agrícola em escala mesorregional. Dados oficiais de áreas de cana‑de‑açúcar, para as microrregiões paulistas, apresentam boa correlação (r² = 0,8 com os dados obtidos pelo método avaliado. A aplicação do algoritmo SAM mostrou ser útil em análises temporais. As séries temporais de NDVI do sensor SPOT Vegetation podem ser utilizadas para mapeamento da área de cana‑de‑açúcar em baixa resolução.

  20. Desarrollo de un algoritmo en MATLAB para la optimización de la resolución de una tarjeta USRP B210 para aplicaciones SDRadar

    Directory of Open Access Journals (Sweden)

    David Moreno Avilés

    2017-11-01

    Full Text Available En este documento se analizan las limitaciones y características que tiene la tarjeta USRP (Universal Software Radio Peripheral B210 para desarrollar aplicaciones de radar definidos por software (SDRadar. Para el desarrollo del algoritmo se utilizó un radar de onda continua modulada en frecuencia (FMCW que implementa una señal chirp, al considerar que 25 MHz es el máximo ancho de banda que la tarjeta puede proporcionar se obtiene como resultado una resolución de 6 metros. El método utilizado para optimizar la resolución de la tarjeta fue transmitir un determinado número de señales con distintos anchos de banda, lo que resulta en una resolución diferente, al detectar y almacenar el objetivo en una matriz. Después de las pruebas correspondientes el algoritmo estableció que con 14 mediciones con variaciones de ancho de banda de 0.5 MHz, entre cada señal, se obtiene la mayor optimización para mejorar la resolución de la tarjeta. Se obtuvo finalmente dos zonas de optimización, donde la primera zona está limitada por un error de medición menor a 1 metro, y en la segunda zona con un error de medición entre 1 y 2 metros con 69.15% y 30.85% de objetivos detectados respectivamente, lo que determina su efectividad y confiabilidad. Este trabajo ha demostrado que el algoritmo utilizado es útil en aplicaciones SDRadar para detectar objetivos para aplicaciones topográficas o sistemas SAR.

  1. Aplicación de algoritmos heurísticos en la construcción de la población inicial de algoritmos genéticos que resuelven el problema de planeamiento de la expansión de la transmisión

    Directory of Open Access Journals (Sweden)

    Antonio H. Escobar Z.

    2011-01-01

    Full Text Available En este artículo se analiza el impacto de seleccionar poblaciones iníciales de buena calidad para ser usadas en algoritmos genéticos, con el propósito de obtener mayor velocidad de convergencia y mejor calidad en las soluciones alcanzadas cuando se resuelve el problema del planeamiento de la expansión a largo plazo de los sistemas de transmisión de energía eléctrica. Los sistemas de prueba que se analizan corresponden a sistemas de alta complejidad, tradicionalmente usados en la literatura especializada. Para generar soluciones iníciales de buena calidad se utilizan algoritmos heurísticos constructivos, particularmente los más utilizados en problemas de planeamiento de la expansión de sistemas de transmisión. Se comparan los resultados obtenidos con los que entregan los algoritmos genéticos que usan poblaciones iniciales aleatorias. Los resultados muestran que una población inicial generada en forma heurística permite obtener soluciones de mejor o igual calidad y con esfuerzos computacionales menores, cuando se resuelven sistemas eléctricos de gran complejidad.

  2. Um algoritmo polinomial para o problema de empacotamento de contêineres com estabillidade estática da carga

    Directory of Open Access Journals (Sweden)

    José Lassance de Castro Silva

    2003-01-01

    Full Text Available O objetivo deste artigo é apresentar um algoritmo polinomial na quantidade de recursos computacionais utilizados, que encontre boas soluções para o problema de empacotamento de bins tridimensionais; tendo como maior contribuição, considerações sobre a estabilidade estática da carga. Os critérios para o empacotamento estável dos itens dentro dos bins são apresentados com detalhes. O procedimento para o preenchimento dos itens dentro dos bins utiliza o bem conhecido princípio da alocação em pontos de cantos. O problema é NP-difícil no sentido forte e extremamente difícil de ser resolvido na prática. Apresenta-se grande quantidade de experimentos computacionais para problemas com até 90 itens (com e sem estabilidade estática e os resultados são comparados com aqueles obtidos da literatura.A polynomial computational bounded resources heuristic for the Three-Dimensional Bin Packing Problem (3D-BPP is suggested. The major contribution is the introduction of static stability of the packing and the criteria used for such a packing are described in details. The filling process follows the well known 3-D corner approach. The problem is NP-Hard in the strong sense and extremely difficult to be solved in the practice. Extensive computational experiments are also presented, with instances up to 90 items, with and without static stability. The results are compared with those obtained from the literature.

  3. Cinemática inversa de robot serial utilizando algoritmo genético basado en MCDS

    Directory of Open Access Journals (Sweden)

    Juan Jairo Vaca González

    2015-04-01

    Full Text Available Los robots manipuladores seriales son herramientas eficaces para realizar tareas repetitivas y de precisión en la industria, siempre que se comprenda la cinemática involucrada en el posicionamiento y orientación del efector final. Este artículo presenta una metodología para resolver el problema cinemático inverso de un robot serial (Melfa RV-2A utilizando un algoritmo genético (AG a partir del modelo cinemático directo Screws (MCDS. Para esto, se obtienen los parámetros Screw que modelan el robot, se calcula el espacio de trabajo asociado y se diseña el AG contemplando una función multi-objetivo de alcance de posición y orientación en que se sitúa el efector final, con respecto a una coordenada y orientación de un punto objetivo establecido. La validación del AG se realiza según la aptitud, el tiempo de convergencia y la cantidad de generaciones usadas por la función para alcanzar el objetivo. Por tanto, la implementación de un AG basado en un MCDS es una herramienta prometedora que podría utilizarse para calcular la cinemática inversa de robots seriales. Esta novedosa implementación permite establecer por primera vez la exposición matricial de un sistema cinemático directo para obtener la solución cinemática inversa de un robot serial. En consecuencia, se demuestra que esta es una metodología factible y eficiente para solucionar la cinemática inversa de cualquier tipo de robot manipulador.

  4. Vectorización de algoritmos generales de convergencia fuerte para la solución de ecuaciones diferenciales estocásticas (SDE)

    OpenAIRE

    Quiñones Botero, Carlos Eduardo

    2007-01-01

    La teoría de las Ecuaciones Diferenciales Estocásticas (SDE) ha sido desarrollada en el último medio siglo, pero no se ha creado una librería para la solución numérica de este tipo de ecuaciones. A pesar de que actualmente existen métodos numéricos de alta eficiencia para la solución de las SDE y de que existen aplicaciones académicas e industriales en donde se utilizan, no se ha desarrollado una librería de fuente abierta que implemente vectorizadamente los mejores algoritmos disponibles act...

  5. PSAL : estudio, análisis e implementación de algoritmos de síntesis de alto nivel

    OpenAIRE

    Sánchez Espeso, Pablo Pedro

    2011-01-01

    En los últimos años se ha producido un gran avance en el desarrollo de herramientas de diseño asistido por computador (cad) en microelectrónica, motivado en gran medida por la creciente complejidad de los circuitos integrados digitales. Este proceso ha incidido principalmente en la automatización del diseño desde el nivel lógico al layout, mientras que las etapas iniciales (especificación del algoritmo y determinación de la arquitectura) siguen dependiendo del diseñador. En la presente tes...

  6. OPTIMIZACIÓN DE REDES 3G UTILIZANDO ALGORITMOS CONTROL DE ADMISIÓN DE LLAMADA (CAC Y REORGANIZACIÓN DE CARGA (LDR

    Directory of Open Access Journals (Sweden)

    Darío Fernando Romo Cabrera

    2012-08-01

    Full Text Available Este artículo presenta el comportamiento de los algoritmos control de admisión de llamada CAC y reorganización de la carga LDR. Se  analizan dos escenarios donde son utilizados para mejorar el rendimiento de la red 3G. En el primero de ellos se presenta un caso de congestión de potencia en el uplink y en el segundo se analiza el nivel de congestión de elementos de canal CE en el uplink.

  7. Algoritmo para monitoramento da incidência da malária na Amazônia brasileira, 2003 a 2010

    Directory of Open Access Journals (Sweden)

    Rui Moreira Braz

    2014-03-01

    Full Text Available OBJETIVO: Avaliar um algoritmo para detecção da variação da incidência da malária nos municípios da Amazônia brasileira. MÉTODOS: Avaliou-se um sistema de monitoramento automatizado, baseado em um algoritmo desenvolvido anteriormente pelos autores. O algoritmo utiliza o diagrama de controle por quartis para classificação dos municípios em quatro grupos, conforme a variação da incidência da malária: grupo 1 (redução da incidência-aqueles com incidência abaixo dos valores esperados; grupo 2 (incidência esperada-aqueles com incidência dentro dos valores esperados; grupo 3 (epidemia-aqueles com incidência acima dos valores esperados; grupo 4 (caso esporádico-aqueles com apenas um caso durante o ano. O período de análise foi de 2003 a 2010. Foram estudados todos os municípios existentes nos nove estados que compõem a Amazônia brasileira (805 municípios em 2003 e 807 a partir de 2004. RESULTADOS: Com base nessa metodologia, os municípios da região foram assim classificados: grupo 1, 152 municípios (18,8% da região em 2003 e 109 (13,5% em 2010; grupo 2, 206 (25,6% em 2003 e 331 (41,0% em 2010; grupo 3, 391 (48,6% em 2003 e 308 (38,2% em 2010; e grupo 4, 56 (7,0% em 2003 e 59 (7,3% em 2010. CONCLUSÕES: O algoritmo possibilitou verificar que, na Amazônia brasileira, o número de municípios com epidemias de malária em 2010 diminuiu em relação a 2003, enquanto o número de municípios com incidência esperada aumentou. No mesmo período, houve pouca variação no número de municípios com redução da incidência e daqueles com casos esporádicos.

  8. Optimización topológica mediante algoritmos genéticos, estrategias evolutivas y el método de Baluja

    OpenAIRE

    Estupiñan, J.; Oñate, E.; Suárez, B.

    1998-01-01

    El trabajo presenta la aplicación de varios mdtodos evolutivos al campo de la optimización topológica de estructuras. El trabajo desarrollado se basa en la búsqueda de una distribución de material dentro de un dominio específico y bajo unas condiciones de contorno concretas. Los algoritmos evolutivos obedecen a las leyes de superviviencia del mejor dotado de Darwiri y a su base genético molecular: mutación y recombinación del material genético. Los métodos evolutivos (ME) que se presentan ...

  9. Nossa experiência com a paralelizâçao de um algoritmo de processamento de imagens geográficas

    OpenAIRE

    Shishido, Henrique Yoshikazu; Silva, Anderson Faustino da; Gonçalves, Ronaldo Augusto de Lara; Batista, Ligia Flavia Antunes

    2010-01-01

    O processamento de imagem digital tem sido usado em diversas áreas de pesquisa como instrumento para o reconhecimento de padres e de filtragens específicas nas imagens. Entretanto, dependendo das características da aplicação o tempo de processamento pode ser extremamente alto e dificultar o avanço das pesquisas associadas. Nesse contexto, este trabalho propõe a paralelização de um algoritmo para o processamento de imagem digital utilizado no cálculo de índice de fragmentação multidimensional....

  10. Efecto del tamaño del alfabeto en el rendimiento de un algoritmo de compresión probabilístico

    Directory of Open Access Journals (Sweden)

    Carlos Rincón

    2012-12-01

    Full Text Available El presente trabajo tuvo como finalidad determinar el efecto del tamaño del alfabeto de un mensaje, en el rendimiento del algoritmo de compresión probabilístico basado en la posición de los símbolos, el cual propusimos en un trabajo previo (Rincón, Acurero, Bracho y Jakymec, 2008. La metodología utilizada consistió en 7 etapas: (a determinación de las variables dependientes e independientes a objeto de estudio, (b desarrollo e implementación del algoritmo propuesto, (c construcción de los archivos de prueba, (d ejecución del algoritmo implementado sobre los archivos de prueba, (e determinación del modelo matemático que explique el comportamiento de las variables dependientes, (f aplicación del método estadístico análisis de varianza, (g análisis de los resultados obtenidos. Las variables dependientes seleccionadas fueron el tiempo de compresión y la relación de compresión. El diseño del modelo estadístico seleccionado fue un totalmente aleatorizado con tratamiento en un arreglo factorial 4x2, con dos factores: tamaño del alfabeto (4,8,12 y 16 símbolos y distribucción probabilística del alfabeto (aleatorio y equiprobable. Del análisis de varianza se obtuvo diferencias significativas para todas las variables independientes y su interacción en todas las variables dependientes, corroborando así el efecto que tiene el tamaño del alfabeto en el rendimiento del algoritmo de compresión estudiado. La prueba de Tukey determinó que para la variable tiempo de compresión el mejor rendimiento se obtiene con la distribución aleatoria y el mayor tamaño del alfabeto (12 y 16, mientras que para la variable relación de compresión, el mejor rendimiento se obtiene con la distribución aleatoria y el menor tamaño del alfabeto.

  11. ESCENARIOS PARA LA UBICACIÓN ÓPTIMA DE GENERACIÓN DISTRIBUIDA CON BASE EN UN ALGORITMO ANALÍTICO

    Directory of Open Access Journals (Sweden)

    Diego Leonardo González Herrera

    2013-09-01

    Full Text Available En este artículo se presentan los escenarios de simulación planteados en base a un algoritmo analítico para la ubicación de la generación distribuida. En primera instancia se hace un recorrido por el estado del arte referente a los factores involucrados en la planeación de la demanda  y estudios de cortocircuito. Así mismo, se exhibe la propuesta metodológica para evaluar el impacto y algunos resultados preliminares obtenidos.

  12. Estudo comparativo entre dois algoritmos de identificação de estrelas para um sensor de estrelas autônomo de campo largo.

    OpenAIRE

    Márcio Afonso Arimura Fialho

    2007-01-01

    Neste trabalho é feito um estudo comparativo entre dois algoritmos de identificação de estrelas desenvolvidos para um sensor de estrelas autônomo de campo largo em projeto no INPE - Instituto Nacional de Pesquisas Espaciais. A comparação é realizada com base nas especificações técnicas deste sensor de estrelas, cujas principais características são: campo de visada quadrado de 25,5 x 25,5 , matriz fotodetectora de 1024 1024 pixels de tecnologia CMOS-APS e precisão na determinação de atitude...

  13. Otimização da largura de banda de ganho de um amplificador Raman na banda "O" baseada em algoritmo genético

    OpenAIRE

    David Steinberg

    2011-01-01

    Neste trabalho a otimização da largura de banda de ganho de um amplificador Raman discreto na banda "O" utilizando algoritmo genético de um simulador comercial foi realizada. O objetivo principal do trabalho foi otimizar a maior largura de banda de ganho do amplificador Raman obtendo valores de variação de ganho menores que 0.5 dB. Utilizando uma fibra DCF (Dispersion Compensating Fiber) como meio de ganho do amplificador Raman, o número de bombeio foi variado e a variação de ganho para ca...

  14. Algoritmos de deteção de comportamento de indivíduos com autismo: análise comparativa

    OpenAIRE

    Ferreira, Miguel Proença Brás

    2013-01-01

    A elevada prevalência de doenças relacionadas com o autismo e a necessidade de descoberta desta patologia de difícil diagnóstico e convivência, levou a que seja imprescindível o desenvolvimento de mecanismos de deteção e avaliação da atividade de pacientes. Esta tese tem como principal objetivo colmatar estas necessidades. Os algoritmos testados são direcionados à melhoria da monitorização de doentes com autismo e com necessidades especiais. Estes têm ...

  15. Aplicación de Algoritmos de Visión Artificial para el Control de Robots Cooperativos Móviles Dentro De Espacios Semi Estructurados

    OpenAIRE

    Pérez Checa, Aníbal Roberto

    2016-01-01

    Este trabajo presenta la aplicación de algoritmos de visión artificial para el control de dos agentes robóticos que mediante su operación en forma cooperativa desplazan al objeto dentro del espacio semi estructurado desde un punto de partida hasta un punto de llegada. El sistema funciona en base de una cámara cenital que captura la imagen que es transmitida a un computador personal el mismo que está provisto de Matlab R2013a, en el cual se procesa la información y determina las acciones de co...

  16. Organización del conocimiento de la asignatura “estructuras de datos y algoritmosâ€� para ingeniería informática basada en mapas conceptuales

    OpenAIRE

    SOLER PELLICER, YOLANDA; LEZCANO BRITO, MATEO GERÓNIMO

    2009-01-01

    Las asignaturas de Programación y Algoritmos deben lograr que los estudiantes escriban algoritmos eficientes. Ese objetivo se ve afectado por el hecho de que los estudiantes no saben escoger y diseñar las estructuras de datos adecuadas para representar la información. Tomando en cuenta este hecho, el Centro de Estudios de Informática Educativa (C EIE ) de la Universidad de Granma y el Centro de Estudios Informáticos (CEI) de la Universidad Central “Marta Abreuâ€� de Las Villas, Cuba, propon...

  17. Reactor container

    International Nuclear Information System (INIS)

    Naruse, Yoshihiro.

    1990-01-01

    The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

  18. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  19. Nuclear reactor

    International Nuclear Information System (INIS)

    Garabedian, G.

    1988-01-01

    A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Batheja, P.; Huber, R.; Rau, P.

    1985-01-01

    Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

  1. Heterogeneous reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

  2. Cálculo, mediante la aplicación del algoritmo de ajuste por mínimos cuadrados, de los componentes de velocidad para estaciones GNSS continuas

    Directory of Open Access Journals (Sweden)

    Jorge Moya Zamora

    2014-07-01

    Full Text Available El cálculo de la velocidad de una estación de observación continua GNSS representa un insumo fundamental en la geodesia moderna. El hecho de determinar la posición de las estaciones GNSS de forma diaria implica que se puedan establecer las series temporales de las estaciones, con base en las cuales se puede obtener información de la influencia de fenómenos que afecten el comportamiento de estas. En este artículo se plantea una descripción del algoritmo de ajuste por mínimos cuadrados adaptado y aplicado a la determinación de los componentes de velocidad de estaciones de observación continua. Además, se aplica este algoritmo para la calcular la velocidad de la estación ETCG, perteneciente al Sistema Geocéntrico para las Américas (SIRGAS.

  3. Desempeño de Algoritmos Gusano en la Navegación de una Plataforma Robótica Móvil

    Directory of Open Access Journals (Sweden)

    Luis Alvarez

    2013-11-01

    Full Text Available El presente trabajo presenta la implementación de algoritmos de navegación denominados gusano 1 y gusano 2 sobre la plataforma robotica móvil de iRobot Create, los cuales se brindaron la capacidad de autonomía para navegar dentro de entornos desconocidos. Además, se utilizaron los módulos de radio frecuencia, que funcionan bajo el estándar ZigBee, para dotar de comunicación inalambrica entre el robot y una PC. Se realizaron pruebas de comunicación para determinar la máxima distancia de trabajo a la que pueden funcionar los módulos RF en interiores; mientras que, para el análisis de desempeño de los algoritmos básicos de navegación montados sobre la plataforma robótica móvil se definieron tres escenarios diferentes donde se verificó la certeza de haber alcanzado la meta por el robot.

  4. Evaluación del comportamiento de un algoritmo para la secuenciación en un taller de flujo con tiempos dependientes de la secuencia

    Directory of Open Access Journals (Sweden)

    Adriano da Silva-Carvalho

    2010-01-01

    Full Text Available En el trabajo se realiza la evaluación del comportamiento de un algoritmo propuesto para la secuenciación en un taller de flujo con tiempos dependientes de la secuencia, utilizando un método híbrido basado en el Algoritmo de Búsqueda del Extremo de una Función de un Código Variable y la metaheurística de Búsqueda Dispersa. Asimismo, se analizan casos obtenidos de la aplicación en un taller mecánico de una industria nacional.In this paper the evaluation of the behaviour of a proposed algorithm is made for the sequence of events in a stream flow in a workshop with dependent moments of the sequence using a hybrid method based on the SEARCH OF THE EXTREME OF A FUNTION OF A VARIABLE CODE ALGORITHM AND THE DISPERSED SEARCH METHOD ALGORITHM In the same way, cases obtained from the application in a workshop of the national mechanical industry are analysed.

  5. ALGORITMO DE BÚSQUEDA TABÚ ESPECIALIZADO APLICADO AL DISEÑO DE REDES SECUNDARIAS DE ENERGÍA ELÉCTRICA

    Directory of Open Access Journals (Sweden)

    Víctor Mario Vélez Marín

    Full Text Available En este artículo se presenta una metodología para solucionar el problema del planeamiento de sistemas de distribución secundarios empleando como técnica de solución el algoritmo de Búsqueda Tabú. El problema se formula como un modelo no lineal entero-mixto, en el cual se tienen en cuenta la ubicación y capacidad de nuevos elementos (transformadores de distribución y tramos de red primaria y secundaria, reubicación de transformadores de distribución existentes, aumento de capacidades de elementos existentes, reconfiguración de red secundaria y balance de fases. Adicionalmente, se consideran los costos asociados a la conexión entre red primaria y secundaria y las pérdidas de energía en transformadores. Se emplean dos casos de prueba; en el primero se realizan ensayos comparativos con el algoritmo genético de Chu-Beasley para verificar la eficiencia del método propuesto y, en el segundo, se analizan los resultados obtenidos en un sistema de distribución colombiano. En ambos casos los resultados obtenidos son de gran calidad, lo que respalda lo propuesto en este trabajo.

  6. ASIGNACIÓN DE SUPERVISORES FORESTALES: RESOLUCIÓN MEDIANTE UN ALGORITMO TABU SEARCH ASSIGNMENT OF FOREST SUPERVISORS: RESOLUTION BY MEANS OF A TABU SEARCH ALGORITHM

    Directory of Open Access Journals (Sweden)

    Lorena Pradenas Rojas

    2008-12-01

    Full Text Available En este estudio se presenta un modelo matemático para un problema genérico de asignación de personal. Se implementa y evalúa un procedimiento de solución mediante la metaheurística Tabu Search. El algoritmo propuesto es usado para resolver un caso real de asignación de supervisores forestales. Los resultados muestran que el algoritmo desarrollado es eficiente en la resolución de este tipo de problema y tiene un amplio rango de aplicación para otras situaciones reales.This study presents a mathematical model for a generic problem of staff allocation. A solution is implemented and evaluated by means of the Tabu Search metaheuristic. The proposed algorithm is used to solve a real case of forestry supervisors' allocation. The results show that the developed algorithm is efficient solving this kind of problems and that it has a wide range of application for other real situations.

  7. Evaluación del impacto ambiental del proceso de obtención de alcohol carburante utilizando el algoritmo de reducción de residuos

    Directory of Open Access Journals (Sweden)

    María Isabel Montoya R.

    2006-01-01

    Full Text Available En el presente trabajo se evalúa el desempeño ambiental de dos procesos para la obtención de etanol a partir de materias primas propias del país como el maíz y la caña de azúcar. Inicialmente se realizó la simulación de los procesos en el software comercial Aspen Plus. Obtenidos los balances de materia y energía de los procesos, se efectuó el análisis de impacto ambiental utilizando el algoritmo de reducción de residuos (algoritmo WAR, el cual evalúa la amigabilidad ambiental de un proceso. De los resultados obtenidos, el proceso a partir de maíz presenta un menor potencial de impacto ambiental de salida que el proceso a partir de caña de azúcar. Igualmente, la mayor generación de impacto ambiental en ambos procesos se da en la categoría de potencial de toxicidad acuática, debido principalmente a la elevada carga orgánica que involucran las vinazas producidas en este proceso.

  8. Análisis paramétrico de volúmenes arquitectónicos con algoritmos genéticos

    Directory of Open Access Journals (Sweden)

    Pedro Salcedo Lagos

    2012-06-01

    Full Text Available En el último tiempo el diseño arquitectónico ha venido evolucionando, debido entre otros aspectos, a la aparición de técnicas de diseño digital que permiten la generación de geometrías a partir de la definición de parámetros iniciales y la programación de las relaciones formales entre ellos. Los procesos de diseño basados en estas tecnologías permiten describir formas con capacidad de variar y adaptarse a requerimientos múltiples o a criterios de evaluación específicos, surgiendo así el problema de identificar la mejor solución arquitectónica, lo que se ha planteado en varias experiencias, gracias a la utilización de la técnica de algoritmos genéticos. En este trabajo se demuestra la posibilidad de implementar un análisis paramétrico de volúmenes arquitectónicos con algoritmos genéticos, logrando compatibilizar requerimientos funcionales, ambientales y estructurales, con un método efectivo de búsqueda para seleccionar una variedad de soluciones apropiadas gracias a las tecnologías digitales.

  9. Algoritmo de alocação de recursos discretos com análise de envoltória de dados

    Directory of Open Access Journals (Sweden)

    João Carlos Correia Baptista Soares de Mello

    2006-08-01

    Full Text Available A alocação de recursos é um dos problemas clássicos abordados pela Pesquisa Operacional. A inserção de modelos de Análise de Envoltória de Dados (DEA nesse contexto traz novas possibilidades de estudo, em especial quando combinada com o uso de algoritmos de programação inteira. Este artigo apresenta um algoritmo para distribuição de recursos discretos usando modelos DEA de forma seqüencial. O método proposto é aplicado no estudo de caso da alocação de vagas docentes na Universidade Federal Fluminense. Os resultados são comparados com aqueles obtidos pela comissão encarregada da distribuição das vagas.The resource allocation is one of the main problems in Operational Research. The use of Data Envelopment Analysis (DEA in this field is a new feature with a great potential, mainly when combined with integer programming problems. This paper presents an algorithm to allocate integer resources using a step-by-step DEA algorithm. We applied the proposed approach to a real case study, which consists in allocating teacher positions in some departments of Universidade Federal Fluminense. We compare the results with those obtained by the official commission.

  10. CREACIÓN DEL ALGORITMO HEURÍSTICO PARA LA PLANIFICACIÓN Y PROGRAMACIÓN DE CARTERAS DE PROYECTOS CON RECURSOS LIMITADOS

    Directory of Open Access Journals (Sweden)

    Mª Antonia Simón Rodríguez

    2014-12-01

    Full Text Available Existen numerosas empresas que tienen implantada una Oficina de Proyectos y los gestionan de manera unificada. Uno de los principales problemas que se encuentran es la asignación de los recursos humanos a los proyectos de cara a cumplir con los plazos establecidos. El objetivo del presente artículo es crear un nuevo algoritmo heurístico que logre resolverlo en un entorno dinámico, que tenga en cuenta las incidencias que van sucediendo, buscando el cumplimiento de hitos intermedios, dando continuidad a los recursos en un mismo proyecto y asignando distintas prioridades. Se ha realizado un estudio de la literatura referente al entorno multiproyecto y para el caso particular de carteras de proyectos. El algoritmo resultante logra satisfacer los objetivos propuestos con gran eficacia y eficiencia, logrando cumplir el plazo para todos los proyectos con prioridad crítica, respetar las fechas intermedias y logrando la nivelación de los recursos humanos disponibles.

  11. Slurry reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuerten, H; Zehner, P [BASF A.G., Ludwigshafen am Rhein (Germany, F.R.)

    1979-08-01

    Slurry reactors are designed on the basis of empirical data and model investigations. It is as yet not possible to calculate the flow behavior of such reactors. The swarm of gas bubbles and cluster formations of solid particles and their interaction in industrial reactors are not known. These effects control to a large extent the gas hold-up, the gas-liquid interface and, similarly as in bubble columns, the back-mixing of liquids and solids. These hydrodynamic problems are illustrated in slurry reactors which constructionally may be bubble columns, stirred tanks or jet loop reactors. The expected effects are predicted by means of tests with model systems modified to represent the conditions in industrial hydrogenation reactors. In his book 'Mass Transfer in Heterogeneous Catalysis' (1970) Satterfield complained of the lack of knowledge about the design of slurry reactors and hence of the impossible task of the engineer who has to design a plant according to accepted rules. There have been no fundamental changes since then. This paper presents the problems facing the engineer in designing slurry reactors, and shows new development trends.

  12. Reactor safety

    International Nuclear Information System (INIS)

    Butz, H.P.; Heuser, F.W.; May, H.

    1985-01-01

    The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Mysels, K.J.; Shenoy, A.S.

    1976-01-01

    A nuclear reactor is described in which the core consists of a number of fuel regions through each of which regulated coolant flows. The coolant from neighbouring fuel regions is combined in a manner which results in an averaging of the coolant temperature at the outlet of the core. By this method the presence of hot streaks in the reactor is reduced. (UK)

  14. Reactor container

    International Nuclear Information System (INIS)

    Kato, Masami; Nishio, Masahide.

    1987-01-01

    Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

  15. RA Reactor

    International Nuclear Information System (INIS)

    1989-01-01

    This chapter includes the following: General description of the RA reactor, organization of work, responsibilities of leadership and operators team, regulations concerning operation and behaviour in the reactor building, regulations for performing experiments, regulations and instructions for inserting samples into experimental channels [sr

  16. Reactor physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1998-01-01

    Progress in research on reactor physics in 1997 at the Belgian Nuclear Research Centre SCK/CEN is described. Activities in the following four domains are discussed: core physics, ex-core neutron transport, experiments in Materials Testing Reactors, international benchmarks

  17. Reactor core

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

    In a BWR type reactor, a great number of pipes (spectral shift pipes) are disposed in the reactor core. Moderators having a small moderating cross section (heavy water) are circulated in the spectral shift pipes to suppress the excess reactivity while increasing the conversion ratio at an initial stage of the operation cycle. After the intermediate stage of the operation cycle in which the reactor core reactivity is lowered, reactivity is increased by circulating moderators having a great moderating cross section (light water) to extend the taken up burnup degree. Further, neutron absorbers such as boron are mixed to the moderator in the spectral shift pipe to control the concentration thereof. With such a constitution, control rods and driving mechanisms are no more necessary, to simplify the structure of the reactor core. This can increase the fuel conversion ratio and control great excess reactivity. Accordingly, a nuclear reactor core of high conversion and high burnup degree can be attained. (I.N.)

  18. Reactor container

    International Nuclear Information System (INIS)

    Fukazawa, Masanori.

    1991-01-01

    A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

  19. Reactor container

    International Nuclear Information System (INIS)

    Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

    1997-01-01

    In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

    A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

  1. Algoritmo de actuación en la prevención de la mutilación genital femenina. Estudio de casos desde atención primaria

    Directory of Open Access Journals (Sweden)

    Carolina Alcón Belchí

    2016-03-01

    Conclusión: El algoritmo diseñado orienta a los profesionales en su actuación, consiguiendo una eficaz detección y prevención de mutilación genital de las niñas y resulta una primera aproximación para el desarrollo de un protocolo regional.

  2. Algoritmo genético para reducir el makespan en un flow shop híbrido flexible con máquinas paralelas no relacionadas y tiempos de alistamiento dependientes de la secuencia

    Directory of Open Access Journals (Sweden)

    Juan Camilo López-Vargas

    2015-01-01

    Full Text Available El artículo propone el algoritmo genético simple o estándar (AGS como enfoque de solución al problema de programación de produc - ción para un ambiente tipo flow shop híbrido flexible minimizando el makespan. La codificación del algoritmo propuesto permite obtener resultados con tiempos de cómputo bastante razonables y con un nivel de convergencia del makespan cercano al 2%, con mejores solu - ciones que un algoritmo alternativo diseñado para el mismo caso de programación de producción. A partir de los resultados obtenidos en el proceso de experimentación y del posterior análisis comparativo, se concluye que a partir del modelamiento más completo de las condiciones reales de producción, el algoritmo genético ejecuta la programación de producción reduciendo el tiempo máximo de procesamiento, o makespan. En futuros trabajos, el enfoque de investigación será la búsqueda de más escenarios alternativos de producción, con el fin de incrementar la aplicación de este tipo de herramientas y generar impacto en los entornos empresariales reales.

  3. Reactor building

    International Nuclear Information System (INIS)

    Maruyama, Toru; Murata, Ritsuko.

    1996-01-01

    In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

  4. Reactor container

    International Nuclear Information System (INIS)

    Shibata, Satoru; Kawashima, Hiroaki

    1984-01-01

    Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

    The reactor core of nuclear reactors usually is composed of individual elongated fuel elements that may be vertically arranged and through which coolant flows in axial direction, preferably from bottom to top. With their lower end the fuel elements gear in an opening of a lower support grid forming part of the core structure. According to the invention a locking is provided there, part of which is a control element that is movable along the fuel element axis. The corresponding locking element is engaged behind a lateral projection in the opening of the support grid. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  6. UN ALGORITMO GENÉTICO HÍBRIDO Y UN ENFRIAMIENTO SIMULADO PARA SOLUCIONAR EL PROBLEMA DE PROGRAMACIÓN DE PEDIDOS JOB SHOP UM ALGORITMO GENÉTICO HÍBRIDO E UM ESFRIAMENTO SIMULADO PARA SOLUCIONAR O PROBLEMA DE PROGRAMAÇÃO DE PEDIDOS JOB SHOP A HYBRID GENETIC ALGORITHM AND A SIMULATED ANNEALING FOR SOLVING THE JOB SHOP SCHEDULING PROBLEM

    Directory of Open Access Journals (Sweden)

    José David Meisel

    2010-07-01

    Full Text Available La programación de pedidos para el problema de producción Job Shop (JSP, catalogado como NP-Hard, ha constituido un reto para la comunidad científica, debido a que alcanzar una solución óptima a este problema se dificulta en la medida que crece en número de máquinas y trabajos. Numerosas técnicas, entre ellas las metaheurísticas, se han empleado para su solución, sin embargo, su eficiencia, en cuanto a tiempo computacional, no ha sido muy satisfactoria. Por lo anterior y para contribuir a la solución de este problema, se planteó el uso de un enfriamiento simulado propuesto (ESP y de un algoritmo genético mejorado (AGM. Para el AGM se implementó una estrategia de enfriamiento simulado en la fase de mutación, que permite al algoritmo intensificar y diversificar las soluciones al mismo tiempo, con el fin de que no converja prematuramente a un óptimo local. Los resultados mostraron que los algoritmos propuestos arrojan buenos resultados, con desviaciones alrededor de los mejores valores encontrados que no superan el 5 % para los problemas más complejos.A programação de pedidos para o problema de produção Job Shop (JSP, catalogado como NP-Hard, tem constituído um desafio para a comunidade científica, devido a que alcançar uma solução ótima a este problema se dificulta na medida em que cresce em número de máquinas e trabalhos. Numerosas técnicas, entre elas as metaheurísticas, foram empregadas para sua solução, no entanto, sua eficiência, em quanto a tempo computacional, não há sido muito satisfatória. Pelo anterior e para contribuir à solução deste problema, propôs-se o uso de um esfriamento simulado proposto (ESP e de um algoritmo genético melhorado (AGM. Para o AGM se implementou uma estratégia de esfriamento simulado na fase de mutação, que permite ao algoritmo intensificar e diversificar as soluções ao mesmo tempo, com o objetivo de que não convirja prematuramente a um ótimo local. Os resultados

  7. Automatic optimization of a nuclear reactor reload using the algorithm Ant-Q; A otimizacao automatica da recarga nuclear utilizando o algoritmo Ant-Q

    Energy Technology Data Exchange (ETDEWEB)

    Machado, Liana; Schirru, Roberto [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear

    2002-07-01

    The nuclear fuel reload optimization is a NP-Complete combinatorial optimization problem. For decades this problem was solved using an expert's knowledge. From the eighties, however there have been efforts to automatic fuel reload and the more recent ones show the Genetic Algorithm's (GA) efficiency on this problem. Following this trend, our aim is to optimization nuclear fuel reload using Ant-Q, artificial theory based algorithms. Ant-Q's results on the Traveling salesman Problem, which is conceptuality similar to fuel reload, are better than GA's. Ant-Q was tested in real application on the cycle 7 reload of Angra I. Comparing Ant-Q result with the GA's, it can be verified that, even without a local heuristics, the former algorithm, as it superiority comparing the GA in Angra I show. Is a valid technique to solve the nuclear fuel reload problem. (author)

  8. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    A nuclear reactor containment vessel faced internally with a metal liner is provided with thermal insulation for the liner, comprising one or more layers of compressible material such as ceramic fiber, such as would be conventional in an advanced gas-cooled reactor and also a superposed layer of ceramic bricks or tiles in combination with retention means therefor, the retention means (comprising studs projecting from the liner, and bolts or nuts in threaded engagement with the studs) being themselves insulated from the vessel interior so that the coolant temperatures achieved in a High-Temperature Reactor or a Fast Reactor can be tolerated with the vessel. The layer(s) of compressible material is held under a degree of compression either by the ceramic bricks or tiles themselves or by cover plates held on the studs, in which case the bricks or tiles are preferably bedded on a yielding layer (for example of carbon fibers) rather than directly on the cover plates

  9. Nuclear reactor

    International Nuclear Information System (INIS)

    Miyashita, Akio.

    1981-01-01

    Purpose: To facilitate and accelerate a leakage test of valves of a main steam pipe by adding a leakage test partition valve thereto. Constitution: A leakage testing partition valve is provided between a pressure vessel for a nuclear reactor and the most upstream side valve of a plurality of valves to be tested for leakage, a testing branch pipe is communicated with the downstream side of the partition valve, and the testing water for preventing leakage is introduced thereto through the branch pipe. Since main steam pipe can be simply isolated by closing the partition valve in the leakage test, the leakage test can be conducted without raising or lowering the water level in the pressure vessel, and since interference with other work in the reactor can be eliminated, the leakage test can be readily conducted parallel with other work in the reactor in a short time. Clean water can be used without using reactor water as the test water. (Yoshihara, H.)

  10. Reactor container

    International Nuclear Information System (INIS)

    Abe, Yoshihito; Sano, Tamotsu; Ueda, Sabuo; Tanaka, Kazuhisa.

    1987-01-01

    Purpose: To improve the liquid surface disturbance in LMFBR type reactors. Constitution: A horizontal flow suppressing mechanism mainly comprising vertical members is suspended near the free liquid surface of coolants in the upper plenum. The horizontal flow of coolants near the free liquid surface is reduced by the suppressing mechanism to effectively reduce the surface disturbance. The reduction in the liquid surface disturbance further prevails to the entire surface region with no particular vertical variations to the free liquid surface to remarkably improve the preventive performance for the liquid surface disturbance. Accordingly, it is also possible to attain the advantageous effects such as prevention for the thermal fatigue in reactor vessel walls, reactor upper mechanisms, etc. and prevention of burning damage to the reactor core due to the reduction of envolved Ar gas. (Kamimura, M.)

  11. REACTOR SHIELD

    Science.gov (United States)

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  12. 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.

  13. Algoritmo incremental de agrupamiento con traslape para el procesamiento de grandes colecciones de datos (Overlapping clustering incremental algorithm for large data collections processing

    Directory of Open Access Journals (Sweden)

    Lázaro Janier González-Soler

    2015-12-01

    Full Text Available Spanish abstract Existen diversos problemas en el Reconocimiento de Patrones y en la Minería de Datos que, por su naturaleza, consideran que los objetos pueden pertenecer a más de una clase o grupo. DClustR es un algoritmo dinámico de agrupamiento con traslape que ha mostrado, en tareas de agrupamiento de documentos, el mejor balance entre calidad de los grupos y eficiencia entre los algoritmos dinámicos de agrupamiento con traslape reportados en la literatura. A pesar de obtener buenos resultados, DClustR puede ser poco útil en aplicaciones que trabajen con grandes colecciones de documentos, debido a que tiene una complejidad computacional y a la cantidad de memoria que utiliza para el procesamiento de las colecciones. En este trabajo se presenta una versión paralela basada en GPU del algoritmo DClustR, llamada CUDA-DClus, para mejorar la eficiencia de DClustR en aplicaciones que lidien con largas colecciones de documentos. Los experimentos fueron realizados sobre varias colecciones estándares de documentos y en ellos se muestra el buen rendimiento de CUDA-DClus en términos de eficiencia y consumo de memoria. English abstract There are several problems in Pattern Recognition and Data Mining that, by its inherent nature, consider that the objects can belong to more than a class or cluster. DClustR is a dynamic overlapping clustering algorithm that has shown, in document clustering tasks, the best trade-off between cluster’s quality and efficiency among existing dynamic overlapping clustering algorithms. However, DClustR could be less useful when working in applications that deal with large data collections, due to its computational complexity and memory demanded for processing them. In this paper, a GPU-based parallel algorithm of DClustR, named CUDA-DClus is suggested to enhance DClustR efficiency in applications dealing with large data collections. The experimental phase conducted over various standard data collections showed that

  14. Breeder reactors

    International Nuclear Information System (INIS)

    Gollion, H.

    1977-01-01

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components [fr

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Schulze, I.; Gutscher, E.

    1980-01-01

    The core contains a critical mass of UN or U 2 N 3 in the form of a noncritical solution with melted Sn being kept below a N atmosphere. The lining of the reactor core consists of graphite. If fission progresses part of the melted metal solution is removed and cleaned from fission products. The reactor temperatures lie in the range of 300 to 2000 0 C. (Examples and tables). (RW) [de

  16. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

    This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

  17. Reactor containment

    International Nuclear Information System (INIS)

    Kawabe, Ryuhei; Yamaki, Rika.

    1990-01-01

    A water vessel is disposed and the gas phase portion of the water vessel is connected to a reactor container by a pipeline having a valve disposed at the midway thereof. A pipe in communication with external air is extended upwardly from the liquid phase portion to a considerable height so as to resist against the back pressure by a waterhead in the pipeline. Accordingly, when the pressure in the container is reduced to a negative level, air passes through the pipeline and uprises through the liquid phase portion in the water vessel in the form of bubbles and then flows into the reactor container. When the pressure inside of the reactor goes higher, since the liquid surface in the water vessel is forced down, water is pushed up into the pipeline. Since the waterhead pressure of a column of water in the pipeline and the pressure of the reactor container are well-balanced, gases in the reactor container are not leaked to the outside. Further, in a case if a great positive pressure is formed in the reactor container, the inner pressure overcomes the waterhead of the column of water, so that the gases containing radioactive aerosol uprise in the pipeline. Since water and the gases flow being in contact with each other, this can provide the effect of removing aerosol. (T.M.)

  18. Fast reactors

    International Nuclear Information System (INIS)

    Vasile, A.

    2001-01-01

    Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

  19. Generation IV reactors: reactor concepts

    International Nuclear Information System (INIS)

    Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

    2003-01-01

    Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

  20. Estudo da ocorrência de cyberbullying contra professores na rede social Twitter por meio de um algoritmo de classificação bayesiano

    Directory of Open Access Journals (Sweden)

    Rafael José de Alencar Almeida

    2012-04-01

    Full Text Available O presente trabalho pretende contribuir com o mapeamento e a mensuração da ocorrência da violência virtual contra professores na rede social Twitter, por meio de técnicas computacionais baseadas em mineração de dados da Internet (web mining e aprendizagem de máquina (machine learning. Para tal, foi realizada, durante uma semana, a coleta de postagens referentes a professores na rede social, as quais foram normalizadas e submetidas a um algoritmo de classificação Bayesiano capaz de realizar automaticamente a categorização do teor das mensagens como positivas, negativas ou neutras. Como resultado, obteve-se uma visualização gráfica hierárquica dos dados capaz de fornecer uma visão geral da gravidade e abrangência do fenômeno.

  1. ¿Es la ciudad de México policéntrica? Nuevos datos y algoritmos para la detección de centralidades urbanas

    Directory of Open Access Journals (Sweden)

    Jorge Alberto Montejano-Escamilla

    2015-01-01

    Full Text Available Con la emergencia de nuevos algoritmos para el análisis de redes y la aparición de bases de datos económicas desagregadas a nivel de unidad, se plantea un método distinto a los anteriormente reportados en la literatura especializada para detectar centralidades urbanas. La primera parte define la centralidad urbana y presenta una disertación teórica sobre la condición policéntrica. Posteriormente, se muestran los métodos anteriormente usados para la medición de las centralidades y se describen las nuevas herramientas empleadas en esta investigación. Finalmente, se presentan algunos resultados de este método aplicado como caso de estudio en la ciudad de México.

  2. Algorithm for the calculation of a steam generator efficiency; Algoritmo para el calculo de la eficiencia de un generador de vapor

    Energy Technology Data Exchange (ETDEWEB)

    Franco, David; Ambriz, Juan Jose; Romero Paredes, Hernando [Universidad Autonoma Metropolitana-Iztapalapa, Mexico, D. F. (Mexico)

    1994-12-31

    The efficiency calculation of steam generators is not always simple. The purpose of this paper is to propose an algorithm for the calculation of steam generators efficiency, easy to understand and carry out, in the form of a series of steps to be followed. It takes as starting point that the person in charge of applying these calculations has knowledge of the combustion processes and thermodynamic principles that rule such processes. [Espanol] El calculo de la eficiencia de los generadores de vapor no siempre es sencillo, el presente trabajo tiene como objetivo el de proponer un algoritmo de calculo de eficiencia de generadores de vapor, el cual sea facil de entender y de llevar a cabo, en forma de una serie de pasos a seguir. Se toma como punto de partida, que la persona encargada de aplicar estos calculos tenga el conocimiento de los procesos de combustion y principios termodinamicos que rigen tales procesos.

  3. Aplicación de algoritmos metaheurísticos en procesamiento de señales, imágenes y energías alternativas

    OpenAIRE

    Oliva Navarro, Diego Alberto

    2016-01-01

    En años recientes se ha incrementado el interés por cómo la naturaleza da solución a diversos problemas como son: búsqueda de fuentes de alimento, organización de conjuntos de animales o insectos, atracción y repulsión de cargas, etc. De aquí surgen los algoritmos metaheurísticos (AM), los cuales simulan comportamientos naturales básicos para solucionar tareas complejas. El uso de estos métodos se ha extendido desde la optimización matemática hasta la ingeniería o la economía.En este trabajo ...

  4. Algoritmo del murciélago virtual en el desarrollo de la Integral de Duhamel para sistemas estructurales con un grado de libertad

    Directory of Open Access Journals (Sweden)

    Sergio Vanegas

    2013-01-01

    Full Text Available En este artículo se propone el uso del algoritmo de optimización de murciélagos virtuales para resolver la Integral de Duhamel en sistemas dinámicos con un grado de libertad. Se desarrollaron ejercicios a titulo demostrativo, para el cálculo de máximos globales. Los resultados fueron muy comparables, tanto en precisión, como en exactitud frente a aquellos obtenidos por otros métodos de cálculo. Se utilizó igualmente el acelerograma del sismo de Chile (2010, para el que se reporta la respuesta dinámica y el desplazamiento máximo. Se variaron para estos ejemplos la cantidad de murciélagos virtuales notándose su influencia sobre el tiempo de computación.

  5. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

  6. Detección de daños en estructuras: estudio comparativo entre los algoritmos de optimización AGs y PSO

    Directory of Open Access Journals (Sweden)

    Robinson Barrera

    2014-01-01

    Full Text Available En este artículo se comparan las técnicas de optimización de enjambre de partículas, PSO (de sus siglas en inglés, Particle Swarm Optimization y Algoritmos Genéticos (AG, ambas usadas en la implementación de un sistema para detectar y diagnosticar fallas en una estructura usando la respuesta modal. Diferentes episodios de daños (daño simple y daño múltiple con y sin ruido, permiten simular las condiciones reales en una estructura tipo viga y armadura para determinar el desempeño en la detección y diagnóstico de los sistemas propuestos. Adicionalmente, ambos sistemas propuestos se evalúan variando los volúmenes de información, es decir, el número de modos de vibración. La respuesta dinámica de la estructura en condición normal o de falla se obtiene usando la herramienta de uso libre OPENSEES® y los algoritmos de optimización PSO y AGs se implementan en ambiente Matlab®. La comparación de desempeño de las dos técnicas en cuanto a sus capacidades de detección y diagnóstico se realizan en una viga segmentada en 10 partes y simplemente apoyada y una armadura de 13 elementos. Resultados experimentales mostraron la eficacia y robustez de los sistemas propuestos en la determinación del estado del sistema en diversos ambientes de ruido y con diferentes volúmenes de información. Sin embargo su desempeño varía según el sistema monitoreado y la función objetivo utilizada

  7. El algoritmo de la transferencia como antecesor del discurso del amo. // The algorithm of transference as a predecessor of the master`s discourse.

    Directory of Open Access Journals (Sweden)

    Alexander Cruz Aponasenko.

    2010-06-01

    Full Text Available This work establishes the counter argument between Lacan’s elaboration discussed in the Proposition of October 9 on the Psychoanalyst of the School, regarding the transference, and the quadripode called “master’s discourse”, delivered in the 1969-1970 seminar. In the “Proposition”, Lacan shows a formula commonly known as “algorithm of transference”, which formalizes the opening to the unconscious through the transference signifier operation and allows the possibility of the analytical work by the installation of the subject-supposed-to-know. We will see how this algorithm precedes the master’s discourse or the discourse of the unconscious. Thus we are going to establish a directionality in the analytical cure by observing the reversal of the master’s discourse that is the discourse of the analyst. // El trabajo establece un contrapunto entre la elaboración de Lacan presentada en la proposición del 9 de octubre sobre el psicoanalista de la escuela, en relación a la transferencia, y el cuadrípodo denominado "discurso del amo", presentado en el seminario del año 1969-1970. En la “proposición” Lacan presenta una fórmula conocida coloquialmente como "algoritmo de la transferencia", que permite formalizar la apertura al inconsciente mediante la operación del significante de la transferencia y producir allí la posibilidad del trabajo analítico vía la instalación del sujeto supuesto saber. Veremos cómo este algoritmo antecede al discurso del amo o discurso del inconsciente. Esto nos permitirá establecer una direccionalidad en la cura analítica observando la inversión del discurso del amo que es el discurso del analista.

  8. Nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Prescott, R F; George, B V; Baglin, C J

    1978-05-10

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given.

  9. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1978-01-01

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given. (UK)

  10. Bioconversion reactor

    Science.gov (United States)

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    Scholz, M.

    1976-01-01

    An improvement of the accessibility of that part of a nuclear reactor serving for biological shield is proposed. It is intended to provide within the biological shield, distributed around the circumference of the reactor pressure vessel, several shielding chambers filled with shielding material, which are isolated gastight from the outside by means of glass panes with a given bursting strength. It is advantageous that, on the one hand, inspection and maintenance will be possible without great effort and, on the other, a large relief cross section will be at desposal if required. (UWI) [de

  12. NEUTRONIC REACTOR

    Science.gov (United States)

    Wigner, E.P.; Weinberg, A.W.; Young, G.J.

    1958-04-15

    A nuclear reactor which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The reactor is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.

  13. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    The method of operating a water-cooled neutronic reactor having a graphite moderator is described which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40--60 volume percent of the mixture, in contact with the graphite moderator. 2 claims, 4 figures

  14. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

  15. Reactor facility

    International Nuclear Information System (INIS)

    Suzuki, Hiroaki; Murase, Michio; Yokomizo, Osamu.

    1997-01-01

    The present invention provides a BWR type reactor facility capable of suppressing the amount of steams generated by the mutual effect of a failed reactor core and coolants upon occurrence of an imaginal accident, and not requiring spacial countermeasures for enhancing the pressure resistance of the container vessel. Namely, a means for supplying cooling water at a temperature not lower by 30degC than the saturated temperature corresponding to the inner pressure of the containing vessel upon occurrence of an accident is disposed to a lower dry well below the pressure vessel. As a result, upon occurrence of such an accident that the reactor core should be melted and flown downward of the pressure vessel, when cooling water at a temperature not lower than the saturated temperature, for example, cooling water at 100degC or higher is supplied to the lower dry well, abrupt generation of steams by the mutual effect of the failed reactor core and cooling water is scarcely caused compared with a case of supplying cooling water at a temperature lower than the saturation temperature by 30degC or more. Accordingly, the amount of steams to be generated can be suppressed, and special countermeasure is no more necessary for enhancing the pressure resistance of the container vessel is no more necessary. (I.S.)

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

    An improved cover structure for liquid metal cooled fast breeder type reactors is described which it is claimed reduces the temperature differential across the intermediate grid plate of the core cover structure and thereby reduces its subjection to thermal stresses. (UK)

  17. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sekine, Katsuhisa.

    1987-01-01

    Purpose: To decrease the thickness of a reactor container and reduce the height and the height and plate thickness of a roof slab without using mechanical vibration stoppers. Constitution: Earthquake proofness is improved by filling fluids such as liquid metal between a reactor container and a secondary container and connecting the outer surface of the reactor container with the inner surface of the secondary container by means of bellows. That is, for the horizontal seismic vibrations, horizontal loads can be supported by the secondary container without providing mechanical vibration stoppers to the reactor container and the wall thickness can be reduced thereby enabling to simplify thermal insulation structure for the reduction of thermal stresses. Further, for the vertical seismic vibrations, verical loads can be transmitted to the secondary container thereby enabling to reduce the wall thickness in the same manner as for the horizontal load. By the effect of transferring the point of action of the container load applied to the roof slab to the outer circumferential portion, the intended purpose can be attained and, in addition, the radiation dose rate at the upper surface of the roof slab can be decreased. (Kamimura, M.)

  19. Reactor system

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Narabayashi, Naoshi.

    1990-01-01

    The represent invention concerns a reactor system with improved water injection means to a pressure vessel of a BWR type reactor. A steam pump is connected to a heat removing system pipeline, a high pressure water injection system pipeline and a low pressure water injection system pipeline for injecting water into the pressure vessel. A pump actuation pipeline is disposed being branched from a main steam pump or a steam relieaf pipeline system, through which steams are supplied to actuate the steam pump and supply cooling water into the pressure vessel thereby cooling the reactor core. The steam pump converts the heat energy into the kinetic energy and elevates the pressure of water to a level higher than the pressure of the steams supplied by way of a pressure-elevating diffuser. Cooling water can be supplied to the pressure vessel by the pressure elevation. This can surely inject cooling water into the pressure vessel upon loss of coolant accident or in a case if reactor scram is necessary, without using an additional power source. (I.N.)

  20. Reactor core

    International Nuclear Information System (INIS)

    Matsuura, Tetsuaki; Nomura, Teiji; Tokunaga, Kensuke; Okuda, Shin-ichi

    1990-01-01

    Fuel assemblies in the portions where the gradient of fast neutron fluxes between two opposing faces of a channel box is great are kept loaded at the outermost peripheral position of the reactor core also in the second operation cycle in the order to prevent interference between a control rod and the channel box due to bending deformation of the channel box. Further, the fuel assemblies in the second row from the outer most periphery in the first operation cycle are also kept loaded at the second row in the second operation cycle. Since the gradient of the fast neutrons in the reactor core is especially great at the outer circumference of the reactor core, the channel box at the outer circumference is bent such that the surface facing to the center of the reactor core is convexed and the channel box in the second row is also bent to the identical direction, the insertion of the control rod is not interfered. Further, if the positions for the fuels at the outermost periphery and the fuels in the second row are not altered in the second operation cycle, the gaps are not reduced to prevent the interference between the control rod and the channel box. (N.H.)

  1. New about research reactors

    International Nuclear Information System (INIS)

    Egorenkov, P.M.

    2001-01-01

    The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

  2. Algoritmos de métodos numéricos codificados en lenguaje de programación C++ para la solución de problemas de análisis numérico

    OpenAIRE

    León Zárate, Elmer Alberto

    2014-01-01

    La presente investigación tuvo como propósito la elaboración de un sistema computacional en el lenguaje de programación C++ que permita codificar los algoritmos para la solución de problemas de análisis numéricos. Este trabajo de investigación tiene por título: "ALGORITMOS DE MÉTODOS NUMÉRICOS CODIFICADOS EN LENGUAJE DE PROGRAMACION C++ PARA LA SOLUCION DE PROBLEMAS DE ANÁLISIS NUMÉRICO" y ha sido preparado para apoyar la formación de los estudiantes de ciencias e ingeniería, quienes podrán a...

  3. Impacto de la memoria cache en la aceleración de la ejecución de algoritmo de detección de rostros en sistemas empotrados

    Directory of Open Access Journals (Sweden)

    Alejandro Cabrera Aldaya

    2012-06-01

    Full Text Available En este trabajo se analiza el impacto de la memoria cache sobre la aceleración de la ejecución del algoritmo de detección de rostros de Viola-Jones en un sistema de procesamiento basado en el procesador Microblaze empotrado en un FPGA. Se expone el algoritmo, se describe una implementación software del mismo y se analizan sus funciones más relevantes y las características de localidad de las instrucciones y los datos. Se analiza el impacto de las memorias cache de instrucciones y de datos, tanto de sus capacidades (entre 2 y 16 kB como de tamaño de línea (de 4 y 8 palabras. Los resultados obtenidos utilizando una placa de desarrollo Spartan3A Starter Kit basada en un FPGA Spartan3A XC3S700A, con el procesador Microblaze a 62,5 MHz y 64 MB de memoria externa DDR2 a 125 MHz,  muestran un mayor impacto de la cache de instrucciones que la de datos, con valores óptimos de 8kB para la cache de instrucciones y entre 4 y 16kB para la cache de datos. Con estas memorias se alcanza una aceleración de 17 veces con relación a la ejecución del algoritmo en memoria externa. El tamaño de la línea de cache tiene poca influencia sobre la aceleración del algoritmo.

  4. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

    1994-01-01

    In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

  5. Un algoritmo basado en búsqueda tabú granular para la solución de un problema de ruteo de vehículos considerando flota heterogénea

    Directory of Open Access Journals (Sweden)

    Duván Eduardo Puenayán

    2014-12-01

    Full Text Available Este artículo aborda el problema de ruteo de vehículos con flota heterogénea (VRPH, en el cual se busca determinar las rutas a ser construidas para satisfacer las demandas de los clientes, considerando una flota de vehículos con capacidad y costos no homogéneos. El objetivo es minimizar la distancia total de las rutas recorridas por los diferentes vehículos. En este artículo, se propone un algoritmo metaheurístico basado en una búsqueda tabú granular para la solución del problema. El algoritmo acepta soluciones infactibles penalizadas por un factor dinámico que se ajusta durante la búsqueda. Experimentos computacionales en instancias reales de una compañía colombiana muestran que el algoritmo propuesto es capaz de obtener, en tiempos computacionales reducidos, mejores soluciones que las obtenidas por el método tradicional de planificación de rutas, usado en la compañía.

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Gibbons, J.F.; McLaughlin, D.J.

    1978-01-01

    In the pressure vessel of the water-cooled nuclear reactor there is provided an internal flange on which the one- or two-part core barrel is hanging by means of an external flange. A cylinder is extending from the reactor vessel closure downwards to a seat on the core cupport structure and serves as compression element for the transmission of the clamping load from the closure head to the core barrel (upper guide structure). With the core barrel, subject to tensile stress, between the vessel internal flange and its seat on one hand and the compression of the cylinder resp. hold-down element between the closure head and the seat on the other a very strong, elastic sprung structure is obtained. (DG) [de

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    Sasaki, Tomozo.

    1987-01-01

    Purpose: To improve the nuclear reactor availability by enabling to continuously exchange fuels in the natural-slightly enriched uranium region during operation. Constitution: A control rod is withdrawn to the midway of a highly enriched uranium region by means of control rod drives and the highly enriched uranium region is burnt to maintain the nuclear reactor always at a critical state. At the same time, fresh uranium-slightly enriched uranium is continuously supplied gravitationally from a fresh fuel reservoir through fuel reservoir to each of fuel pipes in the natural-slightly enriched uranium region. Then, spent fuels reduced with the reactivity by the burn up are successively taken out from the bottom of each of the fuel pipes through an exit duct and a solenoid valve to the inside of a spent fuel reservoir and the burn up in the natural-slightly enriched uranium region is conducted continuously. (Kawakami, Y.)

  8. Nuclear reactor

    International Nuclear Information System (INIS)

    Sakurai, Mikio; Yamauchi, Koki.

    1983-01-01

    Purpose: To improve the channel stability and the reactor core stability in a spontaneous circulation state of coolants. Constitution: A reactor core stabilizing device comprising a differential pressure automatic ON-OFF valve is disposed between each of a plurality of jet pumps arranged on a pump deck. The stabilizing device comprises a piston exerted with a pressure on the lower side of the pump deck by way of a pipeway and a valve for flowing coolants through the bypass opening disposed to the pump deck by the opening and closure of the valve ON-OFF. In a case where the jet pumps are stopped, since the differential pressure between the upper and the lower sides of the pump deck is removed, the valve lowers gravitationally into an opened state, whereby the coolants flow through the bypass opening to increase the spontaneous circulation amount thereby improve the stability. (Yoshino, Y.)

  9. Nuclear reactor

    International Nuclear Information System (INIS)

    Aleite, W.; Bock, H.W.; Struensee, S.

    1976-01-01

    The invention concerns the use of burnable poisons in a nuclear reactor, especially in PWRs, in order to improve the controllability of the reactor. An unsymmetrical arrangement in the lattice is provided, if necessary also by insertion of special rods for these additions. It is proposed to arrange the burnable poisons in fuel elements taken over from a previous burn-up cycle and to distribute them, going out from the side facing the control rods, over not more than 20% of the lenth of the fuel elements. It seems sufficient, for the burnable poisons to bind an initial reactivity of only 0.1% and to become ineffective after normal operation of 3 to 4 months. (ORU) [de

  10. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Saba, Kazuhisa.

    1979-01-01

    Purpose: To improve the earthquake resistance as well as reduce the size of a container for a nuclear reactor with no adverse effects on the decrease of impact shock to the container and shortening of construction step. Constitution: Reinforcing profile steel materials are welded longitudinally and transversely to the inner surface of a container, and inner steel plates are secured to the above profile steel materials while keeping a gap between the materials and the container. Reactor shielding wall planted to the base concrete of the container is mounted to the pressure vessel, and main steam pipeways secured by the transverse beams and led to the outside of container is connected. This can improve the rigidity earthquake strength and the safetiness against the increase in the inside pressure upon failures of the container. (Yoshino, Y.)

  11. Reactor container

    International Nuclear Information System (INIS)

    Oyamada, Osamu; Furukawa, Hideyasu; Uozumi, Hiroto.

    1979-01-01

    Purpose: To lower the position of an intermediate slab within a reactor container and fitting a heat insulating material to the inner wall of said intermediate slab, whereby a space for a control rod exchanging device and thermal stresses of the inner peripheral wall are lowered. Constitution: In the pedestal at the lower part of a reactor pressure vessel there is formed an intermediate slab at a position lower than diaphragm floor slab of the outer periphery of the pedestal thereby to secure a space for providing automatic exchanging device of a control rod driving device. Futhermore, a heat insulating material is fitted to the inner peripheral wall at the upper side of the intermediate slab part, and the temperature gradient in the wall thickness direction at the time of a piping rupture trouble is made gentle, and thermal stresses at the inner peripheral wall are lowered. (Sekiya, K.)

  12. Variabilidade local e regional da evapotranspiração estimada pelo algoritmo SEBAL Local and regional variability of evapotranspiration estimated by SEBAL algorithm

    Directory of Open Access Journals (Sweden)

    Luis C. J. Moreira

    2010-12-01

    Full Text Available Em face da importância em conhecer a evapotranspiração (ET para uso racional da água na irrigação no contexto atual de escassez desse recurso, algoritmos de estimativa da ET a nível regional foram desenvolvidos utilizando-se de ferramentas de sensoriamento remoto. Este estudo objetivou aplicar o algoritmo SEBAL (Surface Energy Balance Algorithms for Land em três imagens do satélite Landsat 5, do segundo semestre de 2006. As imagens correspondem a áreas irrigadas, floresta nativa densa e a Caatinga do Estado do Ceará (Baixo Acaraú, Chapada do Apodi e Chapada do Araripe. Este algoritmo calcula a evapotranspiração horária a partir do fluxo de calor latente, estimado como resíduo do balanço de energia na superfície. Os valores de ET obtidos nas três regiões foram superiores a 0,60 mm h-1 nas áreas irrigadas ou de vegetação nativa densa. As áreas de vegetação nativa menos densa apresentaram taxa da ET horária de 0,35 a 0,60 mm h-1, e valores quase nulos em áreas degradadas. A análise das médias de evapotranspiração horária pelo teste de Tukey a 5% de probabilidade permitiu evidenciar uma variabilidade significativa local, bem como regional no Estado do Ceará.In the context of water resources scarcity, the rational use of water for irrigation is necessary, implying precise estimations of the actual evapotranspiration (ET. With the recent progresses of remote-sensed technologies, regional algorithms estimating evapotranspiration from satellite observations were developed. This work aimed at applying the SEBAL algorithm (Surface Energy Balance Algorithms for Land at three Landsat-5 images during the second semester of 2006. These images cover irrigated areas, dense native forest areas and caatinga areas in three regions of the state of Ceará (Baixo Acaraú, Chapada do Apodi and Chapada do Araripe. The SEBAL algorithm calculates the hourly evapotranspiration from the latent heat flux, estimated from the surface energy

  13. Usando algoritmos e ábaco no estudo do sistema de numeração decimal em um curso de Pedagogia

    Directory of Open Access Journals (Sweden)

    Viegas, Elis Regina dos Santos

    2015-05-01

    Full Text Available Studies in Mathematics Education have described difficulties of teachers in the use of algorithms in arithmetic teaching in the initial grades, difficulties leading to questions about the quality of theoretical and practical training provided for teachers in this area. In this context, the present study aimed to investigate the formation of concepts and construction of mathematical knowledge of Pedagogy students in relation to arithmetic teaching, basic operations using abacus and algorithms, as well as the decimal numbering system. In the theoretical approach, the authors reflect on initial teacher training for Mathematics teachers in the initial grades, the necessity of training grounded in knowledge to the process of teaching/learning and the importance of teacher training in methodological contents and in specific contents. A qualitative and quantitative approach was used, the data collection occurred with the use of semi-structured questionnaires, procedures in the activities report, direct observation and video recording. The results showed that studies with both methodological approaches, abacus and algorithms, might contribute to the formation, reframing concepts and construction of mathematical knowledge, but also could provide information for a better pedagogical and specific training. Estudos em Educação Matemática têm descrito dificuldades de professores na utilização de algoritmos no ensino de aritmética nas séries iniciais, dificuldades que provocam questionamentos quanto à qualidade da formação teórico-prática oferecida para a docência nessa área. Nesse contexto, o presente estudo teve como objetivo investigar a formação de conceitos e construção do conhecimento matemático de estudantes de Pedagogia em relação ao ensino de aritmética, das operações fundamentais com a utilização de ábaco e algoritmos, bem como, do sistema de numeração decimal. No referencial teórico adotado, os autores refletem sobre

  14. Neutronic reactor

    International Nuclear Information System (INIS)

    Lewis, W.R.

    1978-01-01

    Disclosed is a graphite-moderated, water-cooled nuclear reactor including a plurality of rectangular graphite blocks stacked in abutting relationship in layers, alternate layers having axes which are normal to one another, alternate rows of blocks in alternate layers being provided with a channel extending through the blocks, said channeled blocks being provided with concave sides and having smaller vertical dimensions than adjacent blocks in the same layer, there being nuclear fuel in the channels

  15. Nuclear reactors

    International Nuclear Information System (INIS)

    Humphreys, P.; Davidson, D.F.; Thatcher, G.

    1980-01-01

    The cooling system of a liquid metal cooled fast breeder nuclear reactor of the pool kind is described. It has an intermediate heat exchange module comprising a tube-in-shell heat exchanger and an electromagnetic flow coupler in the base region of the module. Primary coolant is flowed through the heat exchanger being driven by electromagnetic interaction with secondary liquid metal coolant flow effected by a mechanical pump. (author)

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Jungmann, A.

    1975-01-01

    Between a PWR's reactor pressure vessel made of steel and the biological shield made of concrete there is a gap. This gap is filled up with a heat insulation facting the reactor pressure vessel, for example with insulating concrete segments jacketed with sheet steel and with an additional layer. This layer serves for smooth absorption of compressive forces originating in radial direction from the reactor pressure vessel. It consists of cylinder-segment shaped bricks made of on situ concrete, for instance. The bricks have cooling agent ports in one or several rows which run parallel to the wall of the pressure vessel and in alignment with superposed bricks. Between the layer of bricks and the biological shield or rather the heat insulation, there are joints which are filled, however, with injected mortar. That guarantees a smooth series of connected components resistant tom compression. Besides, a slip foil can be set between the heat insulation and the joining joint filled with mortar for the reduction of the friction at thermal expansions. (TK) [de

  17. Reactor building

    International Nuclear Information System (INIS)

    Ebata, Sakae.

    1990-01-01

    At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

  18. Nuclear reactors

    International Nuclear Information System (INIS)

    Yoshioka, Michiko.

    1985-01-01

    Purpose: To obtain an optimum structural arrangement of IRM having a satisfactory responsibility to the inoperable state of a nuclear reactor and capable of detecting the reactor power in an averaged manner. Constitution: As the structural arrangement of IRM, from 6 to 16 even number of IRM are bisected into equial number so as to belong two trip systems respectively, in which all of the detectors are arranged at an equal pitch along a circumference of a circle with a radius rl having the center at the position of the central control rod in one trip system, while one detector is disposed near the central control rod and other detectors are arranged substantially at an equal pitch along the circumference of a circle with a radius r2 having the center at the position for the central control rod in another trip system. Furthermore, the radius r1 and r2 are set such that r1 = 0.3 R, r2 = 0.5 R in the case where there are 6 IRM and r1 = 0.4 R and R2 = 0.8 R where there are eight IRM where R represents the radius of the reactor core. (Kawakami, Y.)

  19. MLR reactor

    International Nuclear Information System (INIS)

    Ryazantsev, E.P.; Egorenkov, P.M.; Nasonov, V.A.; Smimov, A.M.; Taliev, A.V.; Gromov, B.F.; Kousin, V.V.; Lantsov, M.N.; Radchenko, V.P.; Sharapov, V.N.

    1998-01-01

    The Material Testing Loop Reactor (MLR) development was commenced in 1991 with the aim of updating and widening Russia's experimental base to validate the selected directions of further progress of the nuclear power industry in Russia and to enhance its reliability and safety. The MLR reactor is the pool-type one. As coolant it applies light water and as side reflector beryllium. The direction of water circulation in the core is upward. The core comprises 30 FA arranged as hexagonal lattice with the 90-95 mm pitch. The central materials channel and six loop channels are sited in the core. The reflector includes up to 11 loop channels. The reactor power is 100 MW. The average power density of the core is 0.4 MW/I (maximal value 1.0 MW/l). The maximum neutron flux density is 7.10 14 n/cm 2 s in the core (E>0.1 MeV), and 5.10 14 n/cm 2 s in the reflector (E<0.625 eV). In 1995 due to the lack of funding the MLR designing was suspended. (author)

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1979-01-01

    Purpose: To prevent cladding tube injuries due to thermal expansion of each of the pellets by successively extracting each of the control rods loaded in the reactor core from those having less number of notches, as well as facilitate the handling work for the control rods. Constitution: A recycle flow control device is provided to a circulation pump for forcibly circulating coolants in the reactor container and an operational device is provided for receiving each of the signals concerning number of notches for each of the control rods and flow control depending on the xenon poisoning effect obtained from the signals derived from the in-core instrument system connected to the reactor core. The operational device is connected with a control rod drive for moving each of the control rods up and down and a recycle flow control device. The operational device is set with a pattern for the aimed control rod power and the sequence of extraction. Upon extraction of the control rods, they are extracted successively from those having less notch numbers. (Moriyama, K.)

  1. Reactor container

    International Nuclear Information System (INIS)

    Hidaka, Masataka; Hatamiya, Shigeo; Kawasaki, Terufumi; Fukui, Toru; Suzuki, Hiroaki; Kataoka, Yoshiyuki; Kawabe, Ryuhei; Murase, Michio; Naito, Masanori.

    1990-01-01

    In order to suppress the pressure elevation in a reactor container due to high temperature and high pressure steams jetted out upon pipeway rupture accidents in the reactor container, the steams are introduced to a pressure suppression chamber for condensating them in stored coolants. However, the ability for suppressing the pressure elevation and steam coagulation are deteriorated due to the presence of inactive incondensible gases. Then, there are disposed a vent channel for introducing the steams in a dry well to a pressure suppression chamber in the reactor pressure vessel, a closed space disposed at the position lower than a usual liquid level, a first channel having an inlet in the pressure suppression chamber and an exit in the closed space and a second means connected by way of a backflow checking means for preventing the flow directing to the closed space. The first paths are present by plurality, a portion of which constitutes a syphon. The incondensible gases and the steams are discharged to the dry well at high pressure by using the difference of the water head for a long cooling time after the pipeway rupture accident. Then, safety can be improved without using dynamic equipments as driving source. (N.H.)

  2. Reactor core in FBR type reactor

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

    1989-01-01

    In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

  3. Comparación de algoritmos basados en la criptografía simétrica DES, AES y 3DES

    Directory of Open Access Journals (Sweden)

    Yuri Tatiana Medina Vargas

    2015-12-01

    Full Text Available RESUMEN La seguridad es uno los aspectos más desafiantes de la internet y las aplicaciones de red. Las cuales están creciendo muy rápido, por lo que la importancia y el valor de los datos intercambiados a través de Internet u otros tipos de medios están aumentando. De ahí la búsqueda de la mejor solución para ofrecer la protección necesaria contra ataques de intrusos a nuestros datos, junto con la prestación de estos servicios en el tiempo es uno de los temas más interesantes en las comunidades relacionadas con la seguridad. La criptografía es la una de las principales categorías de la seguridad informática que convierte la información de su forma normal en un formato ilegible. Las dos características principales que identifican y diferencian algoritmo de cifrado uno de otro son su capacidad para asegurar los datos protegidos contra ataques y su velocidad y eficiencia en hacerlo. Este artículo ofrece una comparación equitativa de tres algoritmos de criptografía de clave simétrica más comunes: DES, AES y 3DES. ABSTRACT Security is one of the most challenging aspects of the internet and network applications. Which are growing very quickly, so that the importance and value of the data exchanged via the Internet or other media types are increasing. Hence the search for the best solution to provide the necessary protection against attacks by intruders to our data, together with the provision of these services in the time it is one of the most interesting topics in the communities related to security. Cryptography is the one of the major categories of computer security that converts the information from its normal form in an unreadable format the two main characteristics that identify and differentiat encryption algorithm from one another are its ability to ensure the data protected against attacks and their speed and efficiency to do so. This article provides a fair comparison of three algorithms for symmetric key cryptography

  4. Aplicación de algoritmos genéticos a la identificación de la estructura de enlaces en portales web

    Directory of Open Access Journals (Sweden)

    Martínez-Torres, María del Rocío

    2011-06-01

    imposibilitaría la obtención de una solución óptima. Por ello, en este trabajo se propone la utilización de una búsqueda genética sobre el conjunto de indicadores de partida. Los algoritmos genéticos son capaces de proporcionar un subconjunto de indicadores que optimizan una función objetivo. Los resultados obtenidos categorizan los portales webs corporativos en cuanto a su estructura de enlaces y destacan las posibilidades de los algoritmos genéticos como herramienta para descubrir nuevo conocimiento.

  5. Un algoritmo genético para el problema de Job Shop Flexible A genetic algorithm for the Flexible Job Shop problem

    Directory of Open Access Journals (Sweden)

    Rosa Medina Durán

    2011-06-01

    Full Text Available En este estudio se propone e implementa computacionalmente un algoritmo genético secuencial para resolver el problema del Job Shop Flexible (existente en la Gestión de Operaciones, el cual es parte de la familia de los problemas de programación de tareas o trabajos (Scheduling en un taller que funciona a pedido. Surge como una generalización del problema del Job Shop y permite optimizar el uso de los recursos (máquinas con mayor flexibilidad, ya que cada máquina puede realizar más de una operación. Este problema ha sido estudiado por numerosos autores, los que han propuesto diversos modelos matemáticos y enfoques heurísticos. Debido a la naturaleza combinatoria, los métodos exactos que resuelven modelos matemáticos encuentran soluciones sólo para instancias pequeñas o simples del problema mencionado. Los resultados muestran la efectividad del algoritmo propuesto para entregar buenas soluciones en tiempos computacionales razonables en más de 130 instancias encontradas en la literatura.This study proposes and computationally implements a sequential genetic algorithm to solve the Flexible Job Shop problem (found in Operations Management, which is part of the family of job or task scheduling problems in a shop that works on demand. It is a generalization of the Job Shop problem, and allows optimizing the use of resources (machines in the shop, with greater flexibility, since each machine can perform more than one operation. This problem has been studied by many authors, who have proposed various mathematical models and heuristic approaches. Due to the combinatorial nature of the problem, the exact methods that solve the mathematical models are often solutions for small and simple instances of the problem. The results show the effectiveness of the proposed algorithm to provide good solutions in reasonable computational times in over 130 instances found in the literatura.

  6. Algoritmo genético aplicado a la programación en talleres de maquinado//Genetic algorithm applied to scheduling in machine shops

    Directory of Open Access Journals (Sweden)

    José Eduardo Márquez-Delgado

    2012-09-01

    Full Text Available En este trabajo se utiliza la metaheurística nombrada algoritmo genético, para dos variantes típicas de problemas de planificación presentes en un taller de maquinado de piezas: las variantes flujo general y flujo regular, y se ha seleccionado la minimización del tiempo de finalización de todos los trabajos ocamino máximo, como objetivo a optimizar en un plan de trabajo. Este problema es considerado de difícil solución y es típico de la optimización combinatoria. Los resultados demuestran la calidad de las soluciones encontradas en correspondencia con el tiempo de cómputo empleado, al ser comparados conproblemas clásicos reportados por otros autores. La representación propuesta de cada cromosoma genera el universo completo de soluciones factibles, donde es posible encontrar valores óptimos globales de solución y cumple con las restricciones del problema.Palabras claves: algoritmo genético, cromosomas, flujo general, flujo regular, planificación, camino máximo._____________________________________________________________________________AbstractIn this paper we use the metaheuristic named genetic algorithm, for two typical variants of problems of scheduling present in a in a machine shop parts: the variant job shop and flow shop, and the minimization of the time of finalization of all the works has been selected, good known as makespan, as objective tooptimize in a work schedule. This problem is considered to be a difficult solution and is typical in combinatory optimization. The results demonstrate the quality of the solutions found in correspondence with the time of used computation, when being compared with classic problems reported by other authors.The proposed representation of each chromosome generates the complete universe of feasible solutions, where it is possible to find global good values of solution and it fulfills the restrictions of the problem.Key words: genetic algorithm, chromosomes, flow shop, job shop

  7. Un algoritmo de replanificación en tiempo real basado en un índice de estabilidad de Lyapunov para líneas de metro

    Directory of Open Access Journals (Sweden)

    A. Berbey

    2014-04-01

    Full Text Available Resumen: En este trabajo, se propone un nuevo índice basado en el método directo de Lyapunov para el diseño de un algoritmo de reprogramación en tiempo real para líneas de metro. En este estudio se utiliza una versión modificada de un modelo de espacio de estados en tiempo real discreto, que considera los efectos de saturación en la línea de metro. Una vez que el modelo de espacio de estados se ha obtenido, el método directo de Lyapunov se aplica con el fin de analizar la estabilidad del sistema de la línea de metro. Como resultado de este análisis no sólo se propone un nuevo índice de estabilidad, sino también la creación de tres zonas de estabilidad para indicar el estado actual del sistema. Finalmente, se presenta un nuevo algoritmo que permite la reprogramación del calendario de los trenes en tiempo real en presencia de perturbaciones medianas. Abstract: A new Lyapunov-based index for designing a rescheduling algorithm in real time for metro lines has been proposed in this paper. A modified real time discrete space state model which considers saturation effects in the metro line has been utilized in this study. Once the space state model has been obtained, the direct method of Lyapunov is applied in order to analyze the stability of the metro line system. As a result of this analysis not only a new stability index is proposed, but also the establishment of three stability zones to indicate the current state of the system. Finally, a new algorithm which allows the rescheduling of the timetable in the real time of the trains under presence of medium disturbances has been presented. Palabras clave: Sistema de metro, estabilidad de Lyapunov, planificación en tiempo real, Keywords: Metro system, Lyapunov stability, real time planning, traffic regulation

  8. Algoritmo de manejo del trauma craneoencefálico leve: Una necesidad social en Cuba Algorism for mild craneo - encephalic trauma management social necessity in Cuba

    Directory of Open Access Journals (Sweden)

    Ariel Varela Hernández

    2006-08-01

    Full Text Available El tema del traumatismo craneoencefálico leve ha sido poco estudiado es Cuba por lo que se presenta este artículo con el objetivo de demostrar la necesidad social de la aplicación de un algoritmo de manejo de estos pacientes que se adapte al contexto social cubano. Se ofrecen conceptos actualizados sobre la importancia de la ciencia y la tecnología en la sociedad moderna y se aborda la significación de la innovación tecnológica para el desarrollo de la tecnociencia en Cuba. Se trata, basado en una epistemología compleja, las relaciones que se establecen entre el desarrollo social y los servicios de salud, así como entre la evolución de la tecnociencia y el trauma craneoencefálico. Se argumenta la relevancia social del traumatismo craneoencefálico leve tanto a nivel mundial como local, así como el impacto favorable de la aplicación de un algoritmo de manejo de estos enfermos, realizado sobre una base científica, el cual permite un empleo óptimo y racional de las tecnologías imagenológicas de avanzada con que se cuenta.The topic about mild cranium-encephalic traumatism has been little studied in Cuba, that is why this article is presented with the objective to demonstrate the social necessity to apply an algorism for these patient's handling adapted to the Cuban social context. The article offers present-day concepts about the importance of science and technology in modern society and the significance of the technological innovation in the development of the techno-science in Cuba. The relationships between the social development and health services, as well as between the evolution of the techno-science and the cranium-encephalic trauma is treated, based on a complex apistemiology. The article argues the social relevance of the mild cranium-encephalic traumatism in the world and in the country, and the favourable impact of the application of an algorism of these sick persons' handling, carried out upon a scientific base which

  9. Adaptação e aplicabilidade de um algoritmo de diurético para pacientes com insuficiência cardíaca

    Directory of Open Access Journals (Sweden)

    Maria Karolina Echer Ferreira Feijó

    2013-06-01

    Full Text Available FUNDAMENTO: Estados congestivos podem ser identificados e manejados através de algoritmos como o Diuretic Treatment Algorithm (DTA para ajuste de diurético por telefone, com enfoque na avaliação clínica. Porém, o DTA está disponível somente em língua inglesa. OBJETIVO: Adaptar o DTA e testar sua aplicabilidade para uso no Brasil em pacientes ambulatoriais com IC. MÉTODOS: Seguiram-se as etapas de tradução, síntese, retrotradução, avaliação por comitê de especialistas e pré-teste (aplicabilidade clínica por meio de ensaio clínico randomizado. O DTA foi denominado, na versão para o Brasil, algoritmo de ajuste de diurético (AAD. Os pacientes foram randomizados para grupo intervenção (GI - ajuste de diurético conforme o AAD - ou grupo controle (GC - ajuste convencional. Foi avaliado o escore clínico de congestão (ECC e o peso para ambos os grupos. RESULTADOS: Foram realizadas 12 modificações no DTA. Incluíram-se 34 pacientes. Para aqueles congestos, o aumento de diurético guiado pelo AAD resultou em maior resolução da congestão, com redução de dois pontos no ECC para 50% da amostra -2 (-3,5; -1,0, enquanto a mediana para o GC foi 0 (-1,25; -1,0, (p < 0,001. A mediana de variação de peso foi maior no GI -1,4 (-1,7; -0,5 quando comparado ao GC 0,1 (1,2; -0,6, p = 0,001. CONCLUSÕES: O ADD mostrou-se aplicável na prática clínica após adaptação e parece resultar em melhor controle da congestão em pacientes com IC. A efetividade clínica da ferramenta merece ser testada em amostra maior de pacientes visando sua validação para uso no Brasil (Universal Trial Number: U1111-1130-5749 (Arq Bras Cardiol. 2013; [online]. ahead print, PP.0-0.

  10. Valoración epidemiológica de la linfadenitis tuberculosa en un distrito de Barcelona: propuesta de algoritmo diagnóstico

    Directory of Open Access Journals (Sweden)

    Silvia Aguilar-Duran

    2014-01-01

    Full Text Available Fundamentos: Barcelona ha experimentado un cambio en su demografía que ha afectado la epidemiología local de la linfadenitis tuberculosa (LT. El objetivo del estudio es conocer los factores actualmente asociados a LT en un distrito de Barcelona con una incidencia media de TB superior a 50 casos por 10.000 habitantes/año así como plantear un algoritmo diagnóstico. Métodos: estudio de cohortes retrospectivo de todos los casos de LT diagnosticados entre 1990 y 2009 en el Hospital del Mar de Barcelona. De acuerdo a los cambios demográficos, se establecieron dos periodos de estudio (1990-1999 y 2000-2009 y se analizaron y compararon las características sociodemográficas, clínicas y diagnósticas de los sujetos con LT para la posterior realización del algoritmo. La información se obtuvo de las encuestas epidemiológicas realizadas a los pacientes diagnosticados de LT en el Hospital del Mar y notificadas a la Agència de Salut Pública de Barcelona. Resultados: en el primer periodo, 152 pacientes presentaron LT (siendo 73,7% autóctonos y en el segundo 147 (siendo 70,7% inmigrantes. En el primer periodo, el porcentaje de hombres immigrantes fue del 70,5% y 57,1% menores de 35 años, aunque en el segundo periodo se observó en autóctonos e l 58,1% de mujeres y 69,8% mayores de 35 años. El porcentaje de pacientes autóctonos con VIH disminuyó de 66,9% a 44,2% en el segundo periodo y hubo aumento de pacientes en tratamiento inmunosupresor (9,3%. El análisis multivariante dio como resultado (OR 8,2;IC 95% 3,4-19,8 para el uso de drogas intravenosas y OR 4,8 (IC95% 2,7-8,3para la inmigración como factores de riesgo a LT. Conclusiones: los varones inmigrantes menores de 35 años procedentes de zonas endémicas de tuberculosis y los autóctonos mayores de 35 años con VIH (aunque con un menor porcentaje de coinfección que antes del año 2000 o en tratamiento inmunosupresor son los grupos con más riesgo de presentar LT en nuestro distrito.

  11. Molten salt reactors: reactor cores

    International Nuclear Information System (INIS)

    1983-01-01

    In this critical analysis of the MSBR I project are examined the problems concerning the reactor core. Advantages of breeding depend essentially upon solutions to technological problems like continuous reprocessing or graphite behavior under neutron irradiation. Graphite deformation, moderator unloading, control rods and core instrumentation require more studies. Neutronics of the core, influence of core geometry and salt composition, fuel evolution, and thermohydraulics are reviewed [fr

  12. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

    Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

  13. Nuclear research reactors

    International Nuclear Information System (INIS)

    1985-01-01

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

  14. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    Baeten, P.

    2006-01-01

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Jolly, R.

    1979-01-01

    The support grid for the fuel rods of a liquid metal cooled fast breeder reactor has a regular hexagonal contour and contains a large number of unit cells arranged honeycomb fashion. The totality of these cells make up a hexagonal shape. The grid contains a number of strips of material, and there is a window in each of three sidewalls staggered by one sidewall. The other sidewalls have embossed protrusions, thus generating a guide lining or guide bead. The windows reduce the rigidity of the areas in the middle between the ends of the cells. (DG) [de

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Anthony, A.J.; Gruber, E.A.

    1979-01-01

    A nuclear reactor with control rods in channels between fuel assemblies wherein the fuel assemblies incorporate guide rods which protrude outwardly into the control rod channels to prevent the control rods from engaging the fuel elements. The guide rods also extend back into the fuel assembly such that they are relatively rigid members. The guide rods are tied to the fuel assembly end or support plates and serve as structural members which are supported independently of the fuel element. Fuel element spacing and support means may be attached to the guide rods. 9 claims

  17. Evaluation of adjustment functions in a heuristic algorithm; Evaluacion de funciones de ajuste en un algoritmo heuristico

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-11-15

    At present the techniques of evolution al computation receive an increasing attention in the scientific and technological areas. This situation is due to its enormous potential in the optimization applied to problems of discussed computational complexity. In the nuclear area these techniques are used in diverse problems of combinatory optimization related with designing cores of power reactors. A distinctive characteristic of the evolution al and/or meta-heuristic algorithms is that appeal in each one from their applications to an adjustment function, fitness or of quality. This function allows to discriminate or to evaluate potentials solutions of the problem to solve. The definition of this situation is very important since it allows following the search of the algorithm toward different regions of the search space. In this work the impact that has the election of this function in the quality of the found solution is shown. The optimization technique by ant colonies or Acs (ant colony system) was used applied to the radial design of fuel cells for a boiling water power reactor. The notable results of the Acs allowed to propose the adjustment method of the importance and with this to obtain adjustment functions that guide the search of solutions of collective algorithms efficiently, basic capacity to develop the proposal of emulation of the natural selection and to investigate the possibility that on order of specify goals, to obtain the corresponding decision variables. A variety of re tro-exit (re tro-out) complementary process of feedback (re tro-in) that opens extended application perspectives of be feasible. (Author)

  18. Optimización en la solución del problema inverso en geofísica usando el algoritmo de entrenamiento supervisado de Levenberg-Marquardt

    Directory of Open Access Journals (Sweden)

    Figueredo Baez Yaqueline

    2002-08-01

    Full Text Available

    In this work it is introduced a methodology for the supervised training of the Neural Networks, using Levenberg Marquardt's algorithm. This method is applied in gravimetry for the optimization in the convergence at the inverse problem.

    En este trabajo se presenta una metodología para el entrenamiento supervisado de redes neuronales, utilizando el algoritmo de Levenberg-Marquardt. Este método se aplica en gravimetría para optimizar la convergencia en el problema de inversión.

  19. MODELAMIENTO DE UN ALGORITMO PARA LA ASIGNACION DE LONGITUDES DE ONDA EN UN MULTIPLEXOR DWDM MINIMIZANDO EL PROCESO DE MEZCLADO DE LA CUARTA ONDA FWM (FOUR WAVE MIXING

    Directory of Open Access Journals (Sweden)

    Jorge Arturo Mojica Cáceres

    2013-07-01

    Full Text Available Uno de los medios de transmisión de alta velocidad más utilizados en nuestro entorno es la fibra óptica especificada en el estándar ITU-T G.625; sin embargo, su despliegue y utilización plantea en la actualidad varios desafíos a resolver debido a su característica de no linealidad, dentro de los cuales se encuentra el relacionado con la disminución del nivel de interferencia. Con el ánimo de brindar un aporte en la solución de esta problemática se propone modelar el comportamiento no lineal de FWM cuando se implementan sistemas de multiplexación de longitudes de onda por un único hilo de fibra óptica a fin de poder estimar las características fundamentales que rige esta tecnología y poder plantear un algoritmo que sea capaz de reducir la interferencia no lineal de cuarta onda (FWM. Como conclusión principal se encontró que el modelo propuesto reduce la interferencia no lineal FWM, lo que permite un aumento en la asignación de canales DWDM aumentando el ancho de banda establecido en cada enlace óptico.

  20. Maximización de la función de Verosimilitud de Distribuciones de Probabilidad usando Algoritmos Genéticos

    Directory of Open Access Journals (Sweden)

    Oscar Arturo Fuentes Mariles

    2015-01-01

    Full Text Available Tradicionalmente, para obtener los parámetros de una función de distribución con el método de máxima verosimilitud se acostumbra igualar a cero la derivada del logaritmo de la función de verosimilitud y resolver el sistema de ecuaciones no lineales que resulta. La popularidad del procedimiento se debe a su sencillez; sin embargo, cuando la función de verosimilitud no es suficientemente regular, puede llevar a obtener un valor muy alejado del máximo Por ese motivo, en este documento se presenta el uso de un algoritmo genético que permite encontrar los parámetros de la función de distribución (con los que se maximiza directamente la función de verosimilitud, o su logaritmo, sin recurrir a la derivada de los logaritmos de dicha función. Se halló buena concordancia de los resultados respecto a los obtenidos usando un software de uso frecuente en México, para el caso las funciones Gumbel y Gumbel de dos poblaciones. 

  1. DESIGN OF ALGORITHMS BASED ON BEHAVIOUR FOR THE CONTROL OF MINIBOTS // DISEÑO DE ALGORITMOS BASADOS EN COMPORTAMIENTOS PARA EL CONTROL DE MINIBOTS

    Directory of Open Access Journals (Sweden)

    Maritza Bracho de Rodríguez

    2012-12-01

    Full Text Available Using the Distributed Artificial Intelligence and the Distributed Robotics as a frame of reference, in this work are designed, developed and implemented algorithms to control autonomous, mobile, reactive, rational, proactive and sociable small robots. These minibots are capable to exhibit behaviors inspired in biological societies. Through the development of this work it was found that if the robot has to perform simple tasks, a reactive architecture is more convenient, efficient and effective. While for the performance of tasks of medium or greater complexity, is recommend the use of a hybrid architecture that allows the incorporation of deliberative reasoning.// RESUMEN: Tomando como marco de referencia a la Inteligencia Artificial Distribuida y la Robótica Distribuida, en este trabajo se diseñan, desarrollan e implementan algoritmos para el control de pequeños robots autónomos, móviles, reactivos, racionales, proactivos y sociables. Estos minibots son capaces de exhibir comportamientos inspirados en las sociedades biológicas. En los resultados alcanzados durante el desarrollo de este trabajo se encontró que cuando el robot debe ejecutar tareas simples, la arquitectura reactiva es la más conveniente, eficiente y efectiva, mientras que para la ejecución de tareas de complejidad mediana o mayor, es más recomendable el uso de arquitecturas hibridas que permitan la incorporación de procesos deliberativos.

  2. Algoritmo Tabú para un problema de distribución de espacios || Tabu search algorithm for a room allocation problem

    Directory of Open Access Journals (Sweden)

    Molina Luque, Julián

    2006-06-01

    Full Text Available La distribución de espacios es un problema que habitualmente se presenta en situaciones reales cuando se deben asignar simultáneamente diferentes conjuntos de espacios (despachos, habitaciones, salas, etc. distribuidos entre edificios y/o plantas entre varios grupos de personas de tal forma que se minimicen las distancias entre los espacios asignados a cada grupo y lasede de dicho grupo. Esta situación da lugar a un problema combinatorio con una función objetivo cuadrática, lo cual complica enormemente su resolución mediante un método exacto. Por este motivo, proponemos para su resolución un metaheurístico basado en Búsqueda Tabú con dos grupos de movimientos claramente diferenciados: intercambio de despachos y reasignación de sedes. Finalmente, aplicamos dicho algoritmo a un caso real en la Universidad Pablo de Olavide de Sevilla (España.

  3. Algoritmo para el control metabólico del paciente diabético en el periodo posoperatorio de la cirugía cardiovascular

    Directory of Open Access Journals (Sweden)

    Maikel Rodulfo García

    2014-07-01

    Full Text Available El paciente con diabetes mellitus en el periodo posoperatorio de la cirugía cardiovascular, frecuentemente presenta descontrol en sus niveles de glucemia, debido a las consecuencias metabólicas que traen consigo, tanto el aumento de hormonas contra-reguladoras como la resistencia y/o disminución de los niveles de insulina, causado por el estrés quirúrgico al cual se expone el organismo. Su control es esencial durante la cirugía y luego de esta, pues de ello depende la evolución de los afectados; por tanto, es de vital importancia poseer una guía que permita orientarse para mantener las cifras de glucemia en valores adecuados. Se presenta un algoritmo terapéutico de fácil aplicación, elaborado en el Servicio de Cirugía Cardiovascular del Hospital Provincial Docente Clinicoquirúrgico "Saturnino Lora Torres" de Santiago de Cuba, con vistas a tratar la hiperglucemia, que pueda generalizarse al resto de los centros del país

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1979-01-01

    In a nuclear reactor (e.g. one having coolant down-flow through a core to a hearth below) thermal insulation (e.g. of a floor of the hearth) comprises a layer of bricks and a layer of tiles thereon, with smaller clearances between the tiles than between the bricks but with the bricks being of reduced cross-section immediately adjacent the tiles so as to be surrounded by interconnected passages, of relatively large dimensions, constituting a continuous chamber extending behind the layer of tiles. By this arrangement, lateral coolant flow in the inter-brick clearances is much reduced. The reactor core is preferably formed of hexagonal columns, supported on diamond-shaped plates each supported on a pillar resting on one of the hearth-floor tiles. Each plate has an internal duct, four upper channels connecting the duct with coolant ducts in four core columns supported by the plate, and lower channels connecting the duct to a downwardly-open recess common to three plates, grouped to form a hexagon, at their mutually-adjacent corners. This provides mixing, and temperature-averaging, of coolant from twelve columns

  5. Reactor container

    International Nuclear Information System (INIS)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-01-01

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.)

  6. Reactor monitor

    International Nuclear Information System (INIS)

    Takada, Tamotsu.

    1992-01-01

    The device of the present invention monitors a reactor so that each of the operations for the relocation of fuel assemblies and the withdrawal and the insertion of control rods upon exchange of fuel assemblies and control rods in the reactor. That is, when an operator conducts relocating operation by way of a fuel assembly operation section, the device of the present invention judges whether the operation indication is adequate or not, based on the information of control rod arrangement in a control rod memory section. When the operation indication is wrong, a stop signal is sent to a fuel assembly relocating device. Further, when the operator conducts control rod operation by way of a control rod operation section, the device of the present invention judges in the control rod withdrawal judging section, as to whether the operation indication given by the operator is adequate or not by comparing it with fuel assembly arrangement information. When the operation indication is wrong, a stop signal is sent to control rod drives. With such procedures, increase of nuclear heating upon occurrence of erroneous operation can be prevented. (I.S.)

  7. Nuclear reactors

    International Nuclear Information System (INIS)

    Matheson, J.E.

    1983-01-01

    A nuclear reactor has an upper and a lower grid plate. Protrusions project from the upper grid plate. Fuel assemblies having end fittings fit between the grid plates. An arrangement is provided for accepting axial forces generated during the operation of the nuclear reactor by the flow of the cooling medium and thermal expansion and irradiation-induced growth of the fuel assembly, which comprises rods. Each fuel assembly rests on the lower grid plate and its upper end is elastically supported against the upper grid plate by the above-mentioned arrangement. The arrangement comprises four (for example) torsion springs each having a torsion tube and a torsion bar nested within the torsion tube and connected at one end thereto. The other end of the torsion bar is connected to an associated one of four lever arms. The torsion tube is rigidly connected to the other end fitting and the springs are disposed such that the lever arms are biassed against the protrusions. (author)

  8. Reactor core fuel management

    International Nuclear Information System (INIS)

    Silvennoinen, P.

    1976-01-01

    The subject is covered in chapters, entitled: concepts of reactor physics; neutron diffusion; core heat transfer; reactivity; reactor operation; variables of core management; computer code modules; alternative reactor concepts; methods of optimization; general system aspects. (U.K.)

  9. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T [Huntington Beach, CA; Sahimi, Muhammad [Altadena, CA; Fayyaz-Najafi, Babak [Richmond, CA; Harale, Aadesh [Los Angeles, CA; Park, Byoung-Gi [Yeosu, KR; Liu, Paul K. T. [Lafayette Hill, PA

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  10. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-11-01

    This single page document is the November 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the production reactor.

  11. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-01

    This single page document is the October 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  12. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-15

    This single page document is the October 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  13. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-09-15

    This single page document is the September 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  14. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-15

    This single page document is the December 16, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  15. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-01

    This single page document is the December 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  16. Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

    Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

  17. The CEA research reactors

    International Nuclear Information System (INIS)

    Schwartz, J.P.

    1993-01-01

    Two main research reactors, specifically designed, PEGASE reactor and Laue-Langevin high flux reactor, are presented. The PEGASE reactor was designed at the end of the 50s for the study of the gas cooled reactor fuel element behaviour under irradiation; the HFR reactor, was designed in the late 60s to serve as a high yield and high level neutron source. Historical backgrounds, core and fuel characteristics and design, flux characteristics, etc., are presented. 5 figs

  18. Atomic reactor thermal engineering

    International Nuclear Information System (INIS)

    Kim, Gwang Ryong

    1983-02-01

    This book starts the introduction of atomic reactor thermal engineering including atomic reaction, chemical reaction, nuclear reaction neutron energy and soon. It explains heat transfer, heat production in the atomic reactor, heat transfer of fuel element in atomic reactor, heat transfer and flow of cooler, thermal design of atomic reactor, design of thermodynamics of atomic reactor and various. This deals with the basic knowledge of thermal engineering for atomic reactor.

  19. Nuclear reactor types

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

  20. Reactor safety

    International Nuclear Information System (INIS)

    Meneley, D.A.

    The people of Ontario have begun to receive the benefits of a low cost, assured supply of electrical energy from CANDU nuclear stations. This indigenous energy source also has excellent safety characteristics. Safety has been one of the central themes of the CANDU development program from its very beginning. A great deal of work has been done to establish that public risks are small. However, safety design criteria are now undergoing extensive review, with a real prospect of more stringent requirements being applied in the future. Considering the newness of the technology it is not surprising that a consensus does not yet exist; this makes it imperative to discuss the issues. It is time to examine the policies and practice of reactor safety management in Canada to decide whether or not further restrictions are justified in the light of current knowledge

  1. Nuclear reactor

    International Nuclear Information System (INIS)

    Schabert, H.P.; Weber, R.; Bauer, A.

    1975-01-01

    The refuelling of a PWR power reactor of about 1,200 MWe is performed by a transport pipe in the containment leading from an external to an internal fuel pit. A wagon to transport the fuel elements can go from a vertical loading position to an also vertical deloading position in the inner fuel pit via guide rollers. The necessary horizontal movement is effected by means of a cable line through the transport pipe which is inclined at least 10 0 . Gravity thus helps in the movement to the deloading position. The cable line with winch is fastened outside the containment. Swivelling devices tip the wagon from the horizontal to the vertical position or vice versa. Loading and deloading are done laterally. (TK/LH) [de

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    Schweiger, F.; Glahe, E.

    1976-01-01

    In a nuclear reactor of the kind which is charged with spherical reaction elements and in which control rods are arranged to be thrust directly into the charge, each control rod has at least one screw thread on its external surface so that as the rod is thrust into the charge it is caused to rotate and thus make penetration easier. The length of each control rod may have two distinct portions, a latter portion which carries a screw thread and a lead-in portion which is shorter than the latter portion and which may carry a thread of greater pitch than that on the latter portion or may have a number of axially extending ribs instead of a thread

  3. Reactor container

    International Nuclear Information System (INIS)

    Furukawa, Hideyasu; Oyamada, Osamu; Uozumi, Hiroto.

    1976-01-01

    Purpose: To provide a container for a reactor provided with a pressure suppressing chamber pool which can prevent bubble vibrating load, particularly negative pressure generated at the time of starting to release exhaust from a main steam escape-safety valve from being transmitted to a lower liner plate of the container. Constitution: This arrangement is characterized in that a safety valve exhaust pool for main steam escape, in which a pressure suppressing chamber pool is separated and intercepted from pool water in the pressure suppressing chamber pool, a safety valve exhaust pipe is open into said safety valve exhaust pool, and an isolator member, which isolates the bottom liner plate in the pressure suppressing chamber pool from the pool water, is disposed on the bottom of the safety valve exhaust pool. (Nakamura, S.)

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    In the system described the fuel elements are arranged vertically in groups and are supported in such a manner as to tend to tilt them towards the center of the respective group, the fuel elements being urged laterally into abutment with one another. The elements have interlocking bearing pads, whereby lateral movement of adjacent elements is resisted; this improves the stability of the reactor core during refuelling operations. Fuel elements may comprise clusters of parallel fuel pins enclosed in a wrapper of hexagonal cross section, with bearing pads in the form of spline-like ribs located on each side of the wrapper and extending parallel to the longitudinal axis of the fuel element, being interlockable with ribs on pads of adjacent fuel elements. The arrangement is applicable to a reactor core in which fuel elements and control rod guide tubes are arranged in modules each of which comprises a cluster of at least three fuel elements, one of which is rigidly supported whilst the others are resiliently tilted towards the center of the cluster so as to lean on the rigidly supported element. It is also applicable to modules comprising a cluster of six fuel elements, each resiliently tilted towards a central void to form a circular arch. The modules may include additional fuel elements located outside the clusters and also resiliently tilted towards the central voids, the latter being used to accommodate control rod guide tubes. The need for separate structural members to act as leaning posts is thus avoided. Such structural members are liable to irradiation embrittlement, that could lead to core failure. (U.K.)

  5. Nuclear reactor neutron shielding

    Science.gov (United States)

    Speaker, Daniel P; Neeley, Gary W; Inman, James B

    2017-09-12

    A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

  6. Solución de un problema de secuenciamiento en configuración jobshop flexible utilizando un Algoritmo de Estimación de Distribuciones.

    Directory of Open Access Journals (Sweden)

    R. Pérez

    2015-01-01

    Full Text Available Resumen: El problema de secuenciamiento en configuración jobshop flexible se refiere en asignar operaciones de diversos trabajos a un conjunto de equipos disponibles. La asignación mencionada busca generalmente minimizar el tiempo de culminación de todos los trabajos conocido en la literatura como ‘makespan’. Se propone un Algoritmo de Estimación de Distribuciones para Secuenciamiento, AEDS por simplicidad y funcionalidad. El AEDS intenta encontrar una relación o interacción entre las variables de entrada, trabajos, operaciones y turnos de trabajo, para optimizar la variable de salida de procesos de manufactura reales, el makespan. En este sentido el algoritmo AEDS es usado para guiar la búsqueda y resolver el problema. En el marco del algoritmo, tres modelos gráficos fueron usados para encontrar mejores soluciones. Establecer horas fuera de servicio para los operadores antes de iniciar sus actividades en cada turno de trabajo como parámetro de entrada y su desarrollo a través del algoritmo AEDS constituye una novedad de esta investigación respecto los trabajos existentes. La comparación entre AEDS y un algoritmo genético muestra la efectividad del AEDS resolviendo el problema enunciado. Usando el AEDS propuesto, el desempeño de procesos de manufactura reales mejora notablemente cuando diferentes equipos disponibles son asignados a diferentes programas de producción. Abstract: The flexible jobshop scheduling problem permits the operation of each job to be processed by more than one machine. The configuration mentioned generally seeks to minimize the completion time of all jobs known in the literature as ‘makespan’. We propose an Estimation of Distribution Algorithm for Sequencing, AEDS for simplicity and functionality. The AEDS attempts to find a relationship or interaction between the input variables, jobs, operations and shifts to optimize the output variable of real

  7. Identification of related multilingual documents using ant clustering algorithms Identificación de documentos multilingües relacionados mediante algoritmos de clustering de hormigas

    Directory of Open Access Journals (Sweden)

    Ángel Cobo

    2011-12-01

    Full Text Available This paper presents a document representation strategy and a bio-inspired algorithm to cluster multilingual collections of documents in the field of economics and business. The proposed approach allows the user to identify groups of related economics documents written in Spanish and English using techniques inspired on clustering and sorting behaviours observed in some types of ants. In order to obtain a language independent vector representation of each document two multilingual resources are used: an economic glossary and a thesaurus. Each document is represented using four feature vectors: words, proper names, economic terms in the glossary and thesaurus descriptors. The proper name identification, word extraction and lemmatization are performed using specific tools. The tf-idf scheme is used to measure the importance of each feature in the document, and a convex linear combination of angular separations between feature vectors is used as similarity measure of documents. The paper shows experimental results of the application of the proposed algorithm in a Spanish-English corpus of research papers in economics and management areas. The results demonstrate the usefulness and effectiveness of the ant clustering algorithm and the proposed representation scheme.Este artículo presenta una estrategia de representación documental y un algoritmo bioinspirado para realizar procesos de agrupamiento en colecciones multilingües de documentos en las áreas de la economía y la empresa. El enfoque propuesto permite al usuario identificar grupos de documentos económicos relacionados escritos en español o inglés usando técnicas inspiradas en comportamientos de organización y agrupamiento de objetos observados en algunos tipos de hormigas. Para conseguir una representación vectorial de cada documento independiente del idioma, se han utilizado dos recursos lingüísticos: un glosario económico y un tesauro. Cada documento es representado usando

  8. Adaptación del algoritmo MARACAS para segmentación de la arteria carótida y cuantificación de estenosis en imágenes TAC

    Directory of Open Access Journals (Sweden)

    Marcela Hernandez

    2010-09-01

    Full Text Available En este artículo se describen las adaptaciones hechas al algoritmo MARACAS para segmentar y cuantificar estructuras vasculares en imágenes TAC de la arteria carótida. El algoritmo MARACAS, que está basado en un modelo elástico y en un análisis de los valores y vectores propios de la matriz de inercia, fue inicialmente diseñado para segmentar una sola arteria en imágenes ARM. Las modificaciones están principalmente enfocadas a tratar las especificidades de las imágenes TAC, así como la presencia de bifurcaciones. Los algoritmos implementados en esta nueva versión se clasifican en dos niveles. 1 Los procesamientos de bajo nivel (filtrado de ruido y de artificios direccionales, presegmentación y realce destinados a mejorar la calidad de la imagen y presegmentarla. Estas técnicas están basadas en información a priori sobre el ruido, los artificios y los intervalos típicos de niveles de gris del lumen, del fondo y de las calcificaciones. 2 Los procesamientos de alto nivel para extraer la línea central de la arteria, segmentar el lumen y cuantificar la estenosis. A este nivel, se aplican conocimientos a priori sobre la forma y anatomía de las estructuras vasculares. El método fue evaluado en 31 imágenes suministradas en el concurso “Carotid Lumen Segmentation and Stenosis Grading Grand Challenge” 2009. Los resultados obtenidos en la segmentación arrojaron un coeficiente de similitud de Dice promedio de 80.4% comparado con la segmentación de referencia, y el error promedio de la cuantificación de estenosis fue 14.4%.

  9. Optimization of a water resource system expansion using the Genetic Algorithm and Simulated Annealing methods; Optimizacion de la expansion de un sistema de recursos hidricos utilizados las metodologias del algoritmo genetico y el recocido simulado

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Camacho, Enrique; Andreu Alvarez, Joaquin [Universidad Politecnica de Valencia (Spain)

    2001-06-01

    Two numerical procedures, based on the Genetic Algorithm (GA) and the Simulated Annealing (SA), are developed to solve the problem of the expansion of capacity of a water resource system. The problem was divided into two subproblems: capital availability and operation policy. Both are optimisation-simulation models, the first one is solved by means of the GA and SA, in each case, while the second one is solved using the Out-of-kilter algorithm (OKA), in both models. The objective function considers the usual benefits and costs in this kind of systems, such as irrigation and hydropower benefits, costs of dam construction and system maintenance. The strength and weakness of both models are evaluated by comparing their results with those obtained with the branch and bound technique, which was classically used to solve this kind of problems. [Spanish] Un par de metodos numericos fundamentados en dos tecnicas de busqueda globales. Algoritmos Genetico (AG) y Recocido Simulado (RS), son desarrollados para resolver el problema de expansion de capacidad de un sistema de recursos hidricos. La estrategia ha sido dividir al problema en dos subproblemas: el de disponibilidad de capital y el de la politica de operacion. Ambos modelos son de optimizacion-simulacion, el primero se realiza mediante los algoritmos del RS y el AG en cada caso, en tanto que el segundo lleva a cabo a traves del algoritmo del Out-of-kilter (AOK) en los dos modelos. La funcion objetivo con que se trabaja considera los beneficios y costos mas comunes en este tipo de sistema, tales como beneficios por riego, por hidroelectricidad y costos de construccion de los embalses y mantenimiento del sistema. La potencia y debilidades delos dos modelos se evaluan mediante la comparacion con los resultados obtenidos a traves de una de las tecnicas mas usadas en este tipo de problemas: la de ramificacion y acotacion.

  10. FBR type reactor

    International Nuclear Information System (INIS)

    Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

    1994-01-01

    In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

  11. The prototype fast reactor

    International Nuclear Information System (INIS)

    Broomfield, A.M.

    1985-01-01

    The paper concerns the Prototype Fast Reactor (PFR), which is a liquid metal cooled fast reactor power station, situated at Dounreay, Scotland. The principal design features of a Fast Reactor and the PFR are given, along with key points of operating history, and health and safety features. The role of the PFR in the development programme for commercial reactors is discussed. (U.K.)

  12. Department of reactor technology

    International Nuclear Information System (INIS)

    1980-01-01

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  13. NCSU Reactor Sharing Program

    International Nuclear Information System (INIS)

    Perez, P.B.

    1993-01-01

    The Nuclear Reactor Program at North Carolina State University provides the PULSTAR Research Reactor and associated facilities to eligible institutions with support, in part, from the Department of Energy Reactor Sharing Program. Participation in the NCSU Reactor Sharing Program continues to increase steadily with visitors ranging from advance high school physics and chemistry students to Ph.D. level research from neighboring universities

  14. Reactor safety method

    International Nuclear Information System (INIS)

    Vachon, L.J.

    1980-01-01

    This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature

  15. Simulación de un algoritmo para controlar el nivel en tolva ante alimentación discontinua de caña

    Directory of Open Access Journals (Sweden)

    Fabricio Garelli

    2009-07-01

    Full Text Available Resumen: Los actuales métodos de control del transporte y preparación de la materia prima provocan graves problemas de discontinuidad en la alimentación al tren de molinos de caña en la industria azucarera en Cuba. La introducción masiva de la tecnología de convertidores de frecuencia para el control de velocidad de motores asincrónicos permite proponer la utilización de la velocidad de las esteras como variable manipulada para el control del nivel de la tolva. Este trabajo presenta una variante de control por velocidad considerando la altura del colchón de caña en la estera elevadora como una perturbación multiplicativa a la entrada de la planta. Se propone un algoritmo de adaptación de set-point por modo deslizante para limitar los transitorios en el nivel de caña en tolva provocados por las fluctuaciones en la alimentación de caña. El método propuesto requiere realimentar únicamente variables accesibles y es robusto ante cambios en la densidad de caña y/o ruido de medición. Su implementación es extremadamente sencilla para lazos de control por velocidad tipo PID. Palabras Clave: molienda de caña de azúcar, estera transportadora, molinos de caña, control PID, control de velocidad, modo deslizante, set-point adaptivo

  16. Algoritmo para el cálculo de la transformada Z inversa utilizando DERIVE // Algorithm for the calculation of the transformed inverse Z using the mathematical assistant DERIVE.

    Directory of Open Access Journals (Sweden)

    D. Galán Martínez

    2000-07-01

    Full Text Available Una de las herramientas matemáticas más utilizadas en ingeniería en el estudio de los denominados sistemas de control dedatos muestreados es la transformada Z. La transformada Z como método operacional puede ser utilizada en la resoluciónde ecuaciones en diferencias finitas; las cuales formulan la dinámica de los sistemas de control de datos muestreados. Estatransformada juega un papel similar que el de la transformada de Laplace en el análisis de los sistemas de control de tiempocontinuo.El presente trabajo tiene como objetivo la confección de un programa para computadora digital, utilizando el asistentematemático DERIVE, para la determinación de la transformada Z inversa de una función algebraica racional, las cualesmodelan matemáticamente los sistemas de control de datos muestreados lineales que aparecen con mucha frecuencia en elestudio de los procesos de ingeniería.Palabras claves: Algoritmo, transformada Z, DERIVE, función algebraica racional, modelo matemático._______________________________________________________________________AbstractOne of the mathematical tools more used in engineering in the study of the denominated systems of data control samples isthe transformed Z. The transformed Z like as an operational method can be used in the resolution of equations in finitedifferences; which formulate the dynamics of the systems of data control samples. This transformed plays a similar paperthat the Laplace transformed in the analysis of the systems of control in continuous time.The present work has as objective the confection of a program for digital computer, using the mathematical assistantDERIVES, for the determination of the Z inverse transformed of a rational algebraic function, which model mathematicallythe systems of lineal data control samples that appear very frecuently in the study of the engineering processesKey words: algorithm, Z inverse transformed, Derives, Digital computer program, Rational

  17. Representación de problemas matemáticos asociados al uso del algoritmo de signación en población sorda

    Directory of Open Access Journals (Sweden)

    Nohemy M. Bedoya Ríos

    2013-01-01

    Full Text Available Objetivo. La presente investigación pretende describir el cambio en los desempeños (logro y tipos de representación utilizados de estudiantes de una escuela para población sord a de la ciudad de Cali después de recibir instrucción en el uso del algoritmo de signación, propuesto por Nunes y Moreno (1998b. Método. Para ello, se realizó un estudio con diseño descriptivo, en el que se empleó el formato de pretest y postest, así como comparación descriptiva con grupo control. Ocho estudiantes participaron para con formar dos grupos de cuatro integrantes. Como instrumento de evaluación se aplicó una batería de prob lemas aritméticos en formato arábigo y en lengua de señas colombiana (LSC tanto en el pre como en el postest . La intervención consistió de cinco sesiones, donde se explicó a los estudiantes el uso del algo ritmo al resolver problemas aditivos. Resultados. Se realizaron análisis de estadística descriptiva para variables categóricas, los cuales mostraron diferencias en los porcentajes de logro, formas de representación del problema y uso de estrategias en el grupo intervenido en el postest. Conclusión. Los resultados permiten concluir que una estrategia educativa pensada para la población sorda puede contribuir a mejorar los aprendizajes de concept os matemáticos básicos.

  18. Análisis de portafolio por sectores mediante el uso de algoritmos genéticos: caso aplicado a la Bolsa Mexicana de Valores

    Directory of Open Access Journals (Sweden)

    Martha del Pilar Rodríguez García

    2015-01-01

    Full Text Available El tipo de sector, el tamaño de la empresa, el número de trabajadores, etc. son variables que se consideran de control en una gran cantidad de publicaciones. En este trabajo consideramos estudiar la variable sector —más que como una variable de control— como una variable determinante del desempeño financiero (Baird et al. 2012 y del riesgo (Artikis y Nifora, 2011. Así, se analiza seis sectores de la economía mexicana divididos de acuerdo con la Bolsa Mexicana de Valores en Industrial, Productos de consumo básico, Materiales, Productos de consumo no básico, Telecomunicaciones y Servicios financieros. La muestra se compone de 30 empresas mexicanas dentro del periodo de 2007-2012. Para medir el desempeño del portafolio se utilizan dos indicadores clásicos: (1 Alfa de Jensen y (2 Ratio de Sharpe; se utiliza una métrica condicional que mide el número de veces que el rendimiento del portafolio supera el rendimiento promedio del mercado. El objetivo es encontrar un portafolio que maximice estos parámetros y comparar los resultados entre los diferentes sectores bajo estudio. Debido a un problema de programación no lineal, se utilizan algoritmos genéticos para obtener el portafolio óptimo que maximice estas métricas. Los resultados muestran un mejor desempeño financiero ajustado a riesgo en el sector de Materiales y Servicios financieros y un desempeño más bajo en sectores como el Industrial y el de Telecomunicaciones.

  19. Algoritmos genéticos aplicados a la optimización de antenas Yagi-Uda Genetic algorithms applied to Yagi-Uda antenna optimization

    Directory of Open Access Journals (Sweden)

    Edgardo César De La Asunción López

    2009-07-01

    Full Text Available En el presente artículo se muestra un proceso de optimización implementado usando algoritmos genéticos. La población inicial del AG está compuesta por 128 cromosomas con 11 genes por cromosoma. Los cromosomas del AG están compuestos por las longitudes y separaciones de los elementos de la antena Yagi-Uda; los rangos de estos genes fueron escogidos siguiendo estándares de diseño para dichas antenas. Los genes pasan un proceso de análisis para medir cada una las antenas de cada generación de del AG para asignar la aptitud de los individuos. Con el fin de verificar los resultados obtenidos, se aplicaron varias pruebas, entre ellas la construcción de una antena Yagi-Uda optimizada a la cual se le midieron y verificaron sus características electromagnéticas.This paper describes an optimization process implemented using Genetic Algorithms. The initial population of the GA is composed of 128 chromosomes with 11 genes per chromosome. The chromosomes of the GA are composed by the length and separations of the elements of the Yagi-Uda antenna; the ranks of this genes where chosen by design standards for such antennas. All genes undergo a process of analysis to assess every one of the antennas of each generation of the GA to assign the fitness of the individuals. In order to verify the obtained results, various tests were made, and among them excel the construction of the optimized Yagi-Uda antenna to measure and verify it electromagnetic characteristics.

  20. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    Baeten, Peter

    2006-01-01

    This course gives an introduction to Nuclear Reactor Physics. The first chapter explains the most important parameters and concepts in nuclear reactor physics such as fission, cross sections and the effective multiplication factor. Further on, in the second chapter, the flux distributions in a stationary reactor are derived from the diffusion equation. Reactor kinetics, reactor control and reactor dynamics (feedback effects) are described in the following three chapters. The course concludes with a short description of the different types of existing and future reactors. (author)

  1. Reactor core and initially loaded reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Koyama, Jun-ichi; Aoyama, Motoo.

    1989-01-01

    In BWR type reactors, improvement for the reactor shutdown margin is an important characteristic condition togehter with power distribution flattening . However, in the reactor core at high burnup degree, the reactor shutdown margin is different depending on the radial position of the reactor core. That is , the reactor shutdown margin is smaller in the outer peripheral region than in the central region of the reactor core. In view of the above, the reactor core is divided radially into a central region and as outer region. The amount of fissionable material of first fuel assemblies newly loaded in the outer region is made less than the amount of the fissionable material of second fuel assemblies newly loaded in the central region, to thereby improve the reactor shutdown margin in the outer region. Further, the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower portion of the first fuel assemblies is made smaller than the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower region of the second fuel assemblies, to thereby obtain a sufficient thermal margin in the central region. (K.M.)

  2. Desarrollo de un algoritmo para la generación y elección de soluciones de corte en la operación de canteo y despuntado en aserraderos

    OpenAIRE

    Francisco Vergara González; Felipe Baesler Abufarde; Mario Ramos Maldonado

    2011-01-01

    En este trabajo se desarrolló un algoritmo que integra las mejores prácticas aplicadas en los aserraderos y una metodología de análisis geométrico de líneas de corte. La aplicación fue programada en lenguaje C++, siendo alimentada con las dimensiones de las piezas deseadas de producir, sus respectivos precios y la geometría en 2-D de la tapa a cortar, generando como resultado una solución de corte en ancho y largo para tapa ingresada. Las soluciones obtenidas se compararon con un patrón que c...

  3. Aplicações e algoritmos de segurança rodoviária com o uso de sistemas de GPS e de comunicações WAVE

    OpenAIRE

    Cardoso, Fábio

    2013-01-01

    Trabalho Final de Mestrado para obtenção do grau de Mestre em Engenharia de Electrónica e Telecomunicações Os acidentes rodoviários são um problema de grande importância para toda a humanidade. O objetivo desta tese é desenvolver um sistema, através de comunicação WAVE, vehicle-tovehicle, capaz de alertar os automobilistas de risco de colisões. O sistema desenvolvido utiliza os dados recebidos por um sistema de GPS para o processamento dos algoritmos de segurança, estudados no estado ...

  4. Estudio comparativo sobre la aplicación de los algoritmos PSO y SQP en la optimización de pórticos planos de concreto armado

    OpenAIRE

    Lapadula Sequera, Víctor Antonio

    2014-01-01

    Esta investigación presenta la comparación de las técnicas SQP (Sequential Cuadratic Programming) y PSO (Particle Swarm optimization) al ser aplicadas al problema de optimización de pórticos planos de concreto armado. El SQP y el PSO son algoritmos de optimización provenientes de filosofías diferentes. El primero es una técnica clásica basada en cálculo diferencial, mientras que el segundo es una meta-heurística inspirada en comportamientos observados en la naturaleza. Como función objetivo d...

  5. Algoritmo con mínimo almacenamiento de memoria para el cálculo de caída de tensión en redes de distribución

    OpenAIRE

    Sánchez Miño, Santiago; Ruiz Ruiz, Raúl A.

    1987-01-01

    El presente trabajo describe algunas técnicas de mínimo almacenamiento de matrices porosas. Se hace un análisis de las ventajas de uno de estos algoritmos sobre los métodos tradicionales que utilizan técnicas matriciales para resolver las redes de sistemas de energía eléctrica. Finalmente, se describe los programas de computación para aplicar el método de mínimo almacenamiento en el cálculo de la caída de tensión en redes de distribución.

  6. Reliability optimization in compound electric power systems with the aid of evolutionary algorithms; Optimizacion de la confiabilidad en sistemas electricos de potencia compuestos utilizando algoritmos evolucionarios

    Energy Technology Data Exchange (ETDEWEB)

    Gomez Hernandez, Jose Alberto

    2001-11-15

    and branches, that contributes the most to the voltage collapse or singular point. The obtained results show the feasibility of the proposed algorithm for optimization of reliability considering conditions of security. The tested systems used are: Reliability test system of 24 nodes of the IEEE, Roy Billinton test system of 6 nodes and eastern area equivalent of the Mexican grid of 31 nodes of the Comision Federal de Electricidad. [Spanish] El proposito de evaluar la confiabilidad de Sistemas Electricos de Potencia (SEP) es para estimar la habilidad del sistema para desempenar su funcion de llevar la energia de las estaciones generadoras a los puntos de carga. Esto involucra la confiabilidad de fuentes de generacion y medios de transmision que afecta en la transferencia de potencia a traves del sistema de transmision que conlleva a perdida de carga y caidas de voltaje entre la generacion y los centros de consumo. En esta tesis se desarrolla una metodologia hibrida que optimiza la confiabilidad en sistemas compuestos (generacion-transmision) utilizando algoritmos evolucionarios. Esta tecnica de optimizacion determina el numero optimo de componentes (redundancia paralela en lineas de transmision) y asignacion de compensacion en derivacion en nodos de carga de la red necesarios para maximizar la confiabilidad sujeta a restricciones de costo, considerando condiciones de seguridad en estado estacionario usando la tecnica del minimo valor singular (MVS) como indicador a la inestabilidad de voltaje. La funcion objetivo se define como una funcion estocastica, donde la medida de interes es el MVS de la matriz Jacobiana de flujos de potencia del evento mas severo de acuerdo a la evaluacion de confiabilidad del sistema compuesto, esta formulacion es una combinacion de programacion no lineal entera y continua, donde los algoritmos convencionales de programacion matematica presentan dificultades en robustez y en la busqueda del optimo global. Los eventos de falla de las unidades

  7. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

    This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

  8. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Yasutomi, Yoshiyuki; Nakagawa, Moroo; Sawai, Yuichi; Chiba, Akio; Suzuki, Yasutaka.

    1997-01-01

    Silicon composited with reinforcing metals is used for a divertor cooling substrate having an effect as a cooling tube to provide a silicon base composite material having increased electric resistance and toughness. The blending ratio of reinforcing materials in the form of granules, whiskers or long fibers is controlled in order to control heat conductivity, electric resistivity and mechanical performances. The divertor cooling substrate comprising the silicon base composite material is integrated with a plasma facing material. The production method therefor includes ordinary metal matrix composite forming methods such as powder metallurgy, melting penetration method, high pressure solidification casting method, centrifugal casting method and vacuum casting method. Since the cooling plate is constituted with the light metal and highly electric resistant metal base composite material, sharing force due to eddy current can be reduced, and radiation exposure can be minimized. Accordingly, a cooling structure for a thermonuclear reactor effective for the improvement of environmental problems caused by waste disposal can be attained. (N.H.)

  9. Nuclear reactor

    International Nuclear Information System (INIS)

    Irion, L.; Tautz, J.; Ulrych, G.

    1976-01-01

    This additional patent complements the arrangement of non-return valves to prevent loss of cooling water on fracture of external tubes in the main coolant circuit (according to PS 24 24 427.7) by ensuring that the easily movable valves only operate in case of a fault, but do not flutter in operation, because the direction of flow is not the same at each location where they are installed. The remedy for this undesirable effect consists of allocating 1 non-return valve unit with 5 to 10 valves to each (of several) ducts for the cooling water intake. These units are installed in the annular space between the reactor vessel and the pressure vessel below the inlet of the ducts. Due to flow guidance surfaces in the same space, the incoming cooling water is deflected downwards and as the guiding surfaces are closed at the sides, must pass parallel to the valves of the non-return valve unit. On fracture of the external cooling water inlet pipe concerned, all valves of this unit close due to reversal of flow on the outlet side. (TK) [de

  10. Nuclear reactors

    International Nuclear Information System (INIS)

    Pearson, K.G.

    1977-01-01

    Reference is made to auxiliary means of cooling the nuclear fuel clusters used in light or heavy water cooled nuclear reactors. One method is to provide one or more spray cooling tubes. From holes in the side walls of those tubes coolant water may be sprayed laterally into the cluster against the rods. The flow of main coolant may thus be supplemented or even replaced by the auxiliary coolant. A difficulty, however, is that only those fuel rods close to a spray cooling tube can readily be reached by the auxiliary coolant. In the arrangement described, where the fuel rods are spaced apart by transverse grids, at least one of the interspaces between the grids is provided with an axially extending auxiliary coolant conduit having lateral holes through which an auxiliary coolant is sprayed into the cluster. A deflector is provided that extends from a transverse grid into a position in front of the holes and deflects auxiliary coolant on to parts of the fuel rods otherwise inaccessible to the auxiliary coolant. The construction of the deflector is described. (U.K.)

  11. Nuclear reactor coolant channels

    International Nuclear Information System (INIS)

    Macbeth, R.V.

    1978-01-01

    A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

  12. Fast breeder reactors

    International Nuclear Information System (INIS)

    Heinzel, V.

    1975-01-01

    The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

  13. IDENTIFICACIÓN EFICIENTE DE ERRORES EN ESTIMACIÓN DE ESTADO USANDO UN ALGORITMO GENÉTICO ESPECIALIZADO IDENTIFICAÇÃO EFICAZ DOS ERROS EM ESTIMATIVA DE ESTADO USANDO UM ALGORITMO GENÉTICO ESPECIALIZADO EFFICIENT IDENTIFICATION OF ERRORS IN STATE ESTIMATION THROUGH A SPECIALIZED GENETIC ALGORITHM

    Directory of Open Access Journals (Sweden)

    Hugo Andrés Ruiz

    2012-06-01

    Full Text Available En este artículo se presenta un método para resolver el problema de estimación de estado en sistemas eléctricos usando optimización combinatoria. Su objetivo es el estudio de mediciones con errores de difícil detección, que afectan el desempeño y calidad de los resultados cuando se emplea un estimador de estado clásico. Dada su complejidad matemática, se deducen indicadores de sensibilidad de la teoría de puntos de apalancamiento que se usan en el algoritmo de optimización de Chu-Beasley, con el fin de disminuir el esfuerzo computacional y mejorar la calidad de los resultados. El método propuesto se valida en un sistema IEEE de 30 nodos.Neste artigo apresenta-se um método para resolver o problema de estimativa de estado em sistemas elétricos usando otimização combinatória. Seu objetivo é o estudo de medidas com erros de difícil detecção, que afetam o desempenho e qualidade dos resultados quando se emprega um estimador de estado clássico. Dada sua complexidade matemática, deduzem-se indicadores de sensibilidade da teoria de pontos de alavancagem que se usam no algoritmo de otimização de Chu-Beasley, com o fim de diminuir o esforço computacional e melhorar a qualidade dos resultados. O método proposto se valida em um sistema IEEE de 30 nós.In this paper a method to solve the state estimation problem in electric systems applying combinatorial optimization is presented. Its objective is the study of measures with difficult detection errors, which affect the performance and quality of the results when a classic state estimator is used. Due to the mathematical complexity, sensibility indicators are deduced from the theory of leverage points used in the Chu-Beasley optimization algorithm with the purpose of reducing the computational effort and enhance the quality of the results. The proposed method is validated in a 30-node IEEE system.

  14. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  15. The fast breeder reactor

    International Nuclear Information System (INIS)

    Collier, J.

    1990-01-01

    The arguments for and against the fast breeder reactor are debated. The case for the fast reactor is that the world energy demand will increase due to increasing population over the next forty years and that the damage to the global environment from burning fossil fuels which contribute to the greenhouse effect. Nuclear fission is the only large scale energy source which can achieve a cut in the use of carbon based fuels although energy conservation and renewable sources will also be important. Fast reactors produce more energy from uranium than other types of (thermal) reactors such as AGRs and PWRs. Fast reactors would be important from about 2020 onwards especially as by then many thermal reactors will need to be replaced. Fast reactors are also safer than normal reactors. The arguments against fast reactors are largely economic. The cost, especially the capital cost is very high. The viability of the technology is also questioned. (UK)

  16. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

    The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

  17. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  18. Guide to power reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

    The IAEA's major first scientific publication is the Directory of Power Reactors now in operation or under construction in various parts of the world. The purpose of the directory is to present important details of various power projects in such a way as to provide a source of easy reference for anyone interested in the development of the peaceful uses of atomic energy, either at the technical or management level. Six pages have been devoted to each reactor the first of which contains general information, reactor physics data and information about the core. The second and third contain sketches of the fuel element or of the fuel element assembly, and of the horizontal and vertical sections of the reactor. On the fourth page information is grouped under the following heads: fuel element, core heat transfer, control, reactor vessel and over-all dimensions, and fluid flow. The fifth page shows a simplified flow diagram, while the sixth provides information on reflector and shielding, containment and turbo generator. Some information has also been given, when available, on cost estimates and operating staff requirements. Remarks and a bibliography constitute the last part of the description of each reactor. Reactor projects included in this directory are pressurized light water cooled power reactors. Boiling light water cooled power reactors, heavy water cooled power reactors, gas cooled power reactors, organic cooled power reactors liquid metal cooled power reactors and liquid metal cooled power reactors

  19. Reactor core of FBR type reactor

    International Nuclear Information System (INIS)

    Hayashi, Hideyuki; Ichimiya, Masakazu.

    1994-01-01

    A reactor core is a homogeneous reactor core divided into two regions of an inner reactor core region at the center and an outer reactor core region surrounding the outside of the inner reactor core region. In this case, the inner reactor core region has a lower plutonium enrichment degree and less amount of neutron leakage in the radial direction, and the outer reactor core region has higher plutonium enrichment degree and greater amount of neutron leakage in the radial direction. Moderator materials containing hydrogen are added only to the inner reactor core fuels in the inner reactor core region. Pins loaded with the fuels with addition of the moderator materials are inserted at a ratio of from 3 to 10% of the total number of the fuel pins. The moderator materials containing hydrogen comprise zirconium hydride, titanium hydride, or calcium hydride. With such a constitution, fluctuation of the power distribution in the radial direction along with burning is suppressed. In addition, an absolute value of the Doppler coefficient can be increased, and a temperature coefficient of coolants can be reduced. (I.N.)

  20. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

    1987-01-01

    Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

  1. Analisis comparativo de una metaheuristica en base a algoritmo genetico vs un metodo de ramificacion y corte para un caso de entrega y recolección con restricciones de ventana de horario

    Directory of Open Access Journals (Sweden)

    Lopez, F.

    2004-07-01

    Full Text Available En la solución de problemas combinatorios, es importante evaluar el costo-beneficio entre la obtención de soluciones de alta calidad en detrimento de los recursos computacionales requeridos. El problema planteado es para el ruteo de un vehículo con entrega y recolección de producto y con restricciones de ventana de horario. En la práctica, dicho problema requiere ser atendido con instancias de gran escala (nodos ≥100. Existe un fuerte porcentaje de ventanas de horario activas (≥90% y con factores de amplitud ≥75%. El problema es NP-hard y por tal motivo la aplicación de un método de solución exacta para resolverlo en la práctica, está limitado por el tiempo requerido para la actividad de ruteo. Se propone un algoritmo genético especializado, el cual ofrece soluciones de buena calidad (% de optimalidad aceptables y en tiempos de ejecución computacional que hacen útil su aplicación en la práctica de la logística. Para comprobar la eficacia de la propuesta algorítmica se desarrolla un diseño experimental el cual hará uso de las soluciones óptimas obtenidas mediante un algoritmo de ramificación y corte sin límite de tiempo. Los resultados son favorables.

  2. Pronóstico puntos críticos de la serie temporal "consumo de energía eléctrica del sector industrial en la ciudad de Medellín,", usando algoritmos genéticos

    Directory of Open Access Journals (Sweden)

    Héctor Tabares

    2007-01-01

    Full Text Available Los algoritmos genéticos (AG están inspirados en el principio darwiniano de la evolución de las especies y en la genética. Son algoritmos probabilísticos que ofrecen un mecanismo de búsqueda paralela y adaptativa, basado en el principio de supervivencia de los más aptos y en la reproducción.Este artículo presenta una introducción a los fundamentos de los AG. También enseña el simulador software AG_UdeA desarrollado con un propósito didáctico para la enseñanza de los AG. El principal aporte consiste en la aplicación de los AG para pronosticar los puntos críticos de consumo de energía eléctrica del sector industrial de la ciudad de Medellín para un período de 24 horas.

  3. Tokamak reactor studies

    International Nuclear Information System (INIS)

    Baker, C.C.

    1981-01-01

    This paper presents an overview of tokamak reactor studies with particular attention to commercial reactor concepts developed within the last three years. Emphasis is placed on DT fueled reactors for electricity production. A brief history of tokamak reactor studies is presented. The STARFIRE, NUWMAK, and HFCTR studies are highlighted. Recent developments that have increased the commercial attractiveness of tokamak reactor designs are discussed. These developments include smaller plant sizes, higher first wall loadings, improved maintenance concepts, steady-state operation, non-divertor particle control, and improved reactor safety features

  4. Glucose isomerization in simulated moving bed reactor by Glucose isomerase

    Directory of Open Access Journals (Sweden)

    Eduardo Alberto Borges da Silva

    2006-05-01

    Full Text Available Studies were carried out on the production of high-fructose syrup by Simulated Moving Bed (SMB technology. A mathematical model and numerical methodology were used to predict the behavior and performance of the simulated moving bed reactors and to verify some important aspects for application of this technology in the isomerization process. The developed algorithm used the strategy that considered equivalences between simulated moving bed reactors and true moving bed reactors. The kinetic parameters of the enzymatic reaction were obtained experimentally using discontinuous reactors by the Lineweaver-Burk technique. Mass transfer effects in the reaction conversion using the immobilized enzyme glucose isomerase were investigated. In the SMB reactive system, the operational variable flow rate of feed stream was evaluated to determine its influence on system performance. Results showed that there were some flow rate values at which greater purities could be obtained.Neste trabalho a tecnologia de Leito Móvel Simulado (LMS reativo é aplicada no processo de isomerização da glicose visando à produção de xarope concentrado de frutose. É apresentada a modelagem matemática e uma metodologia numérica para predizer o comportamento e o desempenho de unidades reativas de leito móvel simulado para verificar alguns aspectos importantes para o emprego desta tecnologia no processo de isomerização. O algoritmo desenvolvido utiliza a abordagem que considera as equivalências entre as unidades reativas de leito móvel simulado e leito móvel verdadeiro. Parâmetros cinéticos da reação enzimática são obtidos experimentalmente usando reatores em batelada pela técnica Lineweaver-Burk. Efeitos da transferência de massa na conversão de reação usando a enzima imobilizada glicose isomerase são verificados. No sistema reativo de LMS, a variável operacional vazão da corrente de alimentação é avaliada para conhecer o efeito de sua influência no

  5. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  6. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  7. Algoritmos para visualización a través de módulos LCD gráficos

    Directory of Open Access Journals (Sweden)

    Yosvany Vento Ramos

    2012-02-01

    Full Text Available Normal 0 21 false false false ES X-NONE X-NONE /* Style Definitions */ table.MsoNormalTable {mso-style-name:"Tabla normal"; mso-tstyle-rowband-size:0; mso-tstyle-colband-size:0; mso-style-noshow:yes; mso-style-priority:99; mso-style-qformat:yes; mso-style-parent:""; mso-padding-alt:0cm 5.4pt 0cm 5.4pt; mso-para-margin:0cm; mso-para-margin-bottom:.0001pt; mso-pagination:widow-orphan; font-size:11.0pt; font-family:"Calibri","sans-serif"; mso-ascii-font-family:Calibri; mso-ascii-theme-font:minor-latin; mso-fareast-font-family:"Times New Roman"; mso-fareast-theme-font:minor-fareast; mso-hansi-font-family:Calibri; mso-hansi-theme-font:minor-latin; mso-bidi-font-family:"Times New Roman"; mso-bidi-theme-font:minor-bidi;} El desarrollo de sistemas embebidos (como el que se acomete en los laboratorios del Grupo de Investigaciones para el Diagnóstico Avanzado de Maquinarias(GIDAM de la universidad de Pinar del Río(UPR en general presenta limitaciones para realizar de manera autónoma la visualización de datos y resultados de procesamiento, así como para posibilitar una interfaz visual efectiva de interacción con los usuarios. Este problema encuentra solución en el empleo de pantallas de cristal líquido o módulos LCD (Liquid Cristal Display. Por ello, el objetivo de este trabajo consistió en desarrollar y validar un paquete de algoritmos de programación para un módulo gráfico LCD. El sistema desarrollado es una aplicación a microcontrolador para manejar el LCD. Inicialmente se logró la visualización esperada en forma de simulación, y posteriormente se desarrolló su implementación práctica. Se obtuvieron los resultados esperados, presentando las visualizaciones de las señales graficadas una calidad comparable con las de programas profesionales.

  8. Solución del problema de localización de condensadores en circuitos de distribución primaria mediante algoritmo genético

    Directory of Open Access Journals (Sweden)

    Julio Rafael Gómez Sarduy

    2011-10-01

    Full Text Available Este trabajo está relacionado con el problema de la ubicación de condensadores para mejorar la eficiencia en la explotación de las redes logrando una disminución de las pérdidas técnicas. Se presenta el desarrollo teórico y la validación de un modelo empleado para la selección y localización de bancos de condensadores, sujeto a restricciones técnicas y operativas propias de los sistemas eléctricos. Para solucionarlo se utiliza un algoritmo genético (AG con funciones de cruzamiento y mutación modificadas, cuya población inicial se genera de maneraaleatoriamente controlada. Para validar el modelo se emplea un circuito de 33 nodos utilizado por otros investigadores y se aplica posteriormente al circuito 81 de distribución de la Ciudad de Cienfuegos, tomado comocaso de estudio. Se calculan las pérdidas antes y después de la compensación y los beneficios asociados a la reducción de las mismas. El programa devuelve las capacidades y localizaciones del esquema de compensación. The problem of the placement of capacitors achieving a decrease of the technical losses and improve of the efficiency is considered in this paper. Theoretical model and validation for selection and placement capacitors have been realized. The technical and operating restrictions of electric systems are considered. A basic genetic algorithm is constituted by a controlled random creation of the initial population and the functions of crossover and mutation are modified for the quest of the optimal solution.One circuit of 11 kV and 33 nodes are used to validate the model, which have been utilized by another investigators are utilized too. Methodology is applicable at the 81 circuit of Cienfuegos's city. Losses before of the compensation and the benefits are calculated by this methodology. The program returns the capabilities and locations of the capacitors in the scheme of optimal compensation proposed.

  9. Optimización multiobjetivo para enrutamiento multicast en overlay networks utilizando algoritmos evolutivos Multiobjective Optimization for Multicast Routing in Overlay Networks using Evolutionary Algorithms

    Directory of Open Access Journals (Sweden)

    Juan Carlos Montoya M.

    2008-06-01

    Full Text Available Multicast juega un papel muy importante para soportar una nueva generación de aplicaciones. En la actualidad y por diferentes razones, técnicas y no técnicas, multicast IP no ha sido totalmente adoptado en Internet. Durante los últimos a˜nos, un área de investigación activa es la de implementar este tipo de tráfico desde la perspectiva del nivel de aplicación, donde la funcionalidad de multicast no es responsabilidad de los enrutadores sino de los hosts, a lo que se le conoce como Multicast Overlay Network (MON. En este artículo se plantea el enrutamiento en MON como un problema de Optimización Multiobjetivo (MOP donde se optimizan dos funciones: 1 el retardo total extremo a extremo del árbol multicast, y 2 la máxima utilización de los enlaces. La optimización simultánea de estas dos funciones es un problema NP completo y para resolverlo se propone utilizar Algoritmos Evolutivos Multiobjetivos (MOEA, específicamente NSGAIMulticast plays an important role in supporting a new generation of applications. At present and for different reasons, technical and non–technical, multicast IP hasn’t yet been totally adopted for Internet. During recent years, an active area of research is that of implementing this kind of traffic in the application layer where the multicast functionality isn´t a responsibility of the routers but that of the hosts, which we know as Multicast Overlay Networks (MON. In this article, routing in an MON is put forward as a multiobjective optimization problem (MOP where two functions are optimized: 1 the total end to end delay of the multicast tree and 2 the maximum link utilization. The simultaneous optimization of these two functions is an NP–Complete problem and to solve this we suggest using Multiobjective Evolutionary Algorithms (MOEA, specifically NSGA–II.

  10. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    Edwards, R.M.; Power, M.A.; Bryan, M.

    1992-01-01

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

  11. Reactor System Design

    International Nuclear Information System (INIS)

    Chi, S. K.; Kim, G. K.; Yeo, J. W.

    2006-08-01

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  12. Fusion reactor design studies

    International Nuclear Information System (INIS)

    Emmert, G.A.; Kulcinski, G.L.; Santarius, J.F.

    1990-01-01

    This report discusses the following topics on the ARIES tokamak: systems; plasma power balance; impurity control and fusion ash removal; fusion product ripple loss; energy conversion; reactor fueling; first wall design; shield design; reactor safety; and fuel cost and resources

  13. Nuclear reactors; graphical symbols

    International Nuclear Information System (INIS)

    1987-11-01

    This standard contains graphical symbols that reveal the type of nuclear reactor and is used to design graphical and technical presentations. Distinguishing features for nuclear reactors are laid down in graphical symbols. (orig.) [de

  14. Control for nuclear reactor

    International Nuclear Information System (INIS)

    Ash, E.B.; Bernath, L.; Facha, J.V.

    1980-01-01

    A nuclear reactor is provided with several hydraulically-supported spherical bodies having a high neutron absorption cross section, which fall by gravity into the core region of the reactor when the flow of supporting fluid is shut off. (auth)

  15. Hybrid plasmachemical reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lelevkin, V. M., E-mail: lelevkin44@mail.ru; Smirnova, Yu. G.; Tokarev, A. V. [Kyrgyz-Russian Slavic University (Kyrgyzstan)

    2015-04-15

    A hybrid plasmachemical reactor on the basis of a dielectric barrier discharge in a transformer is developed. The characteristics of the reactor as functions of the dielectric barrier discharge parameters are determined.

  16. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    Fribourg, Ch.

    2002-01-01

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  17. Guidebook to nuclear reactors

    International Nuclear Information System (INIS)

    Nero, A.V. Jr.

    1976-05-01

    A general introduction to reactor physics and theory is followed by descriptions of commercial nuclear reactor types. Future directions for nuclear power are also discussed. The technical level of the material is suitable for laymen

  18. continuous stirred tank reactor (CSTR)

    African Journals Online (AJOL)

    AFRICAN JOURNALS ONLINE (AJOL) · Journals · Advanced Search ... stirred tank reactor (CSTR) and the small and large intestines as plug flow reactor (PFR) ... from the two equations are used for the reactor sizing of the modeled reactors.

  19. Reactor physics aspects of CANDU reactors

    International Nuclear Information System (INIS)

    Critoph, E.

    1980-01-01

    These four lectures are being given at the Winter Course on Nuclear Physics at Trieste during 1978 February. They constitute part of the third week's lectures in Part II: Reactor Theory and Power Reactors. A physical description of CANDU reactors is given, followed by an overview of CANDU characteristics and some of the design options. Basic lattice physics is discussed in terms of zero energy lattice experiments, irradiation effects and analytical methods. Start-up and commissioning experiments in CANDU reactors are reviewed, and some of the more interesting aspects of operation discussed - fuel management, flux mapping and control of the power distribution. Finally, some of the characteristics of advanced fuel cycles that have been proposed for CANDU reactors are summarized. (author)

  20. Molten salt breeder reactor

    International Nuclear Information System (INIS)

    1977-01-01

    MSBR Study Group formed in October 1974 has studied molten salt breeder reactor and its various aspects. Usage of a molten salt fuel, extremely interesting as reactor chemistry, is a great feature to MSBR; there is no need for separate fuel making, reprocessing, waste storage facilities. The group studied the following, and these results are presented: molten salt technology, molten salt fuel chemistry and reprocessing, reactor characteristics, economy, reactor structural materials, etc. (Mori, K.)

  1. Zero energy reactor 'RB'

    Energy Technology Data Exchange (ETDEWEB)

    Popovic, D; Takac, S; Markovic, H; Raisic, N; Zdravkovic, Z; Radanovic, Lj [Boris Kidric Institute of Nuclear Sciences, Vinca, Beograd (Yugoslavia)

    1959-03-15

    In 1958 the zero energy reactor RB was built with the purpose of enabling critical experiments with various reactor systems to be carried out. The first core assembly built in this reactor consists of heavy water as moderator and natural uranium metal as fuel. In order to be able to obtain very accurate results when measuring the main characteristics of the assembly the reactor was built as a completely bare system. (author)

  2. Reactor utilization, Annex A

    International Nuclear Information System (INIS)

    Martinc, R.; Stanic, A.

    1984-01-01

    Reactor was operated until August 1984 due to prohibition issued by the Ministry since the reactor does not have the emergency cooling system nor special filters in the ventilation system yet. This means that the operation plan was fulfilled by 69%. This annex includes detailed tables containing data about utilization of reactor experimental channels, irradiated samples, as well as interruptions of operation. Detailed data about reactor power during this period are shown as well

  3. PUSPATI TRIGA Reactor

    International Nuclear Information System (INIS)

    Masood, Z.

    2016-01-01

    The PUSPATI TRIGA Reactor is the only research reactor in Malaysia. This 1 MW TRIGA Mk II reactor first reached criticality on 28 June 1982 and is located at the Malaysian Nuclear Agency premise in Bangi, Malaysia. This reactor has been mainly utilised for research, training and education and isotope production. Over the years several systems have been refurbished or modernised to overcome ageing and obsolescence problems. Major achievements and milestones will also be elaborated in this paper. (author)

  4. Nuclear reactor shutdown system

    International Nuclear Information System (INIS)

    Mangus, J.D.; Cooper, M.H.

    1982-01-01

    An improved nuclear reactor shutdown system is described comprising a temperature sensitive device connected to control the electric power supply to a magnetic latch holding a body of a neutron absorbing material. The temperature sensitive device is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause deenergization of the magnetic latch to allow the body of neutron absorbing material to enter the reactor core. (author)

  5. The fast reactor

    International Nuclear Information System (INIS)

    1980-02-01

    The subject is discussed as follows: brief description of fast reactors; advantage in conserving uranium resources; experience, in UK and elsewhere, in fast reactor design, construction and operation; safety; production of plutonium, security aspects; consideration of future UK fast reactor programme. (U.K.)

  6. Mirror fusion reactor design

    International Nuclear Information System (INIS)

    Neef, W.S. Jr.; Carlson, G.A.

    1979-01-01

    Recent conceptual reactor designs based on mirror confinement are described. Four components of mirror reactors for which materials considerations and structural mechanics analysis must play an important role in successful design are discussed. The reactor components are: (a) first-wall and thermal conversion blanket, (b) superconducting magnets and their force restraining structure, (c) neutral beam injectors, and (d) plasma direct energy converters

  7. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    1993-11-01

    The results of nuclear fusion researches in JAERI are summarized. In this report, following themes are collected: the concept of fusion reactor (including ITER), fusion reactor safety, plasma confinement, fusion reactor equipment, and so on. Includes glossary. (J.P.N.)

  8. Rotating reactors : a review

    NARCIS (Netherlands)

    Visscher, F.; Schaaf, van der J.; Nijhuis, T.A.; Schouten, J.C.

    2013-01-01

    This review-perspective paper describes the current state-of-the-art in the field of rotating reactors. The paper has a focus on rotating reactor technology with applications at lab scale, pilot scale and industrial scale. Rotating reactors are classified and discussed according to their geometry:

  9. Refuelling nuclear reactors

    International Nuclear Information System (INIS)

    Stacey, J.; Webb, J.; White, W.P.; McLaren, N.H.

    1981-01-01

    An improved nuclear reactor refuelling machine is described which can be left in the reactor vault to reduce the off-load refuelling time for the reactor. The system comprises a gripper device rangeable within a tubular chute, the gripper device being movable by a pantograph. (U.K.)

  10. Reactor power measuring device

    International Nuclear Information System (INIS)

    Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

    1993-01-01

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  11. Ulysse, mentor reactor

    International Nuclear Information System (INIS)

    Bouquin, B.; Rio, I.; Safieh, J.

    1997-01-01

    On July 23, 1961, the ULYSSE reactor began its first power rise. Designed at that time to train nuclear engineering students and reactor operators, this reactor still remains an indispensable tool for nuclear teaching and a choice instrument for scientists. (author)

  12. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Sherwood, D.G.; Wilson, J.F.; Salton, R.B.; Fensterer, H.F.

    1981-01-01

    A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus includes drivemechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displayer rods through the reactor vessel

  13. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Sherwood, D.G.; Wilson, J.F.; Salton, R.B.; Fensterer, H.F.

    1982-01-01

    A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus includes drive mechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displacer rods through the reactor vessel. (author)

  14. Neutron behavior, reactor control, and reactor heat transfer. Volume four

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant)

  15. Reactor as furnace and reactor as lamp

    International Nuclear Information System (INIS)

    Goldanskii, V.I.

    1992-01-01

    There are presented general characteristics of the following ways of transforming of nuclear energy released in reactors into chemical : ordinary way (i.e. trough the heat, mechanical energy and electricity); chemonuclear synthesis ; use of high-temperature fuel elements (reactor as furnace); use of the mixed nγ-radiation of reactors; use of the radiation loops; radiation - photochemical synthesis (reactor as lamp). Advantage and disadvantages of all above variants are compared. The yield of the primary product of fixation of nitrogen (nitric oxide NO) in reactor with the high-temperature (above ca. 1900degC) fuel elements (reactor-furnace) can exceed W ∼ 200 kg per gram of burned uranium. For the latter variant (reactor-lamp) the yield of chemical products can reach W ∼ 60 kg. per gram of uranium. Such values of W are close to or even strongly exceed the yields of chemical products for other abovementioned variants and - what is particularly important - are not connected to the necessity of archscrupulous removal of radioactive contamination of products. (author)

  16. 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

  17. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  18. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1981-12-01

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around the nuclear reactors. The curricula of the courses contain also the subject material of chemistry. With reference to the foreign curricula, a plan of educational subject material of chemistry in the Nuclear Engineering School of JAERI was considered, and the fundamental part of reactor chemistry was reviewed in this report. Since the students of the Nuclear Engineering School are not chemists, the knowledge necessary in and around the nuclear reactors was emphasized in order to familiarize the students with the reactor chemistry. The teaching experience of the fundamentals of reactor chemistry is also given. (author)

  19. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    2010-03-01

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  20. The fast breeder reactor

    International Nuclear Information System (INIS)

    Davis, D.A.; Baker, M.A.W.; Hall, R.S.

    1990-01-01

    Following submission of written evidence, the Energy Committee members asked questions of three witnesses from the Central Electricity Generating Board and Nuclear Electric (which will be the government owned company running nuclear power stations after privatisation). Both questions and answers are reported verbatim. The points raised include where the responsibility for the future fast reactor programme should lie, with government only or with private enterprise or both and the viability of fast breeder reactors in the future. The case for the fast reactor was stated as essentially strategic not economic. This raised the issue of nuclear cost which has both a construction and a decommissioning element. There was considerable discussion as to the cost of building a European Fast reactor and the cost of the electricity it would generate compared with PWR type reactors. The likely demand for fast reactors will not arrive for 20-30 years and the need to build a fast reactor now is questioned. (UK)

  1. One piece reactor removal

    International Nuclear Information System (INIS)

    Chia, Wei-Min; Wang, Song-Feng

    1993-01-01

    The strategy of Taiwan Research Reactor Renewal plan is to remove the old reactor block with One Piece Reactor Removal (OPRR) method for installing a new research reactor in original building. In this paper, the engineering design of each transportation works including the work method, the major equipments, the design policy and design criteria is described and discussed. In addition, to ensure the reactor block is safety transported for storage and to guarantee the integrity of reactor base mat is maintained for new reactor, operation safety is drawn special attention, particularly under seismic condition, to warrant safe operation of OPRR. ALARA principle and Below Regulatory Concern (BRC) practice were also incorporated in the planning to minimize the collective dose and the total amount of radioactive wastes. All these activities are introduced in this paper. (J.P.N.)

  2. Reactor power control device

    International Nuclear Information System (INIS)

    Ishii, Yoshihiko; Arita, Setsuo; Miyamoto, Yoshiyuki; Fukazawa, Yukihisa; Ishii, Kazuhiko

    1998-01-01

    The present invention provides a reactor power control device capable of enhancing an operation efficiency while keeping high reliability and safety in a BWR type nuclear power plant. Namely, the device of the present invention comprises (1) a means for inputting a set value of a generator power and a set value of a reactor power, (2) a means for controlling the reactor power to either smaller one of the reactor power corresponding to the set value of the generator power and the set value of the reactor power. With such procedures, even if the nuclear power plant is set so as to operate it to make the reactor power 100%, when the generator power reaches the upper limit, the reactor power is controlled with a preference given to the upper limit value of the generator power. Accordingly, safety and reliability are not deteriorated. The operation efficiency of the plant can be improved. (I.S.)

  3. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Dogen, Ayumi; Ozawa, Michihiro.

    1983-01-01

    Purpose: To significantly improve the working efficiency of a nuclear reactor by reflecting the control rod history effect on thermal variants required for the monitoring of the reactor operation. Constitution: An incore power distribution calculation section reads the incore neutron fluxes detected by neutron detectors disposed in the reactor to calculate the incore power distribution. A burnup degree distribution calculation section calculates the burnup degree distribution in the reactor based on the thus calculated incore power distribution. A control rod history date store device supplied with the burnup degree distribution renews the stored control rod history data based on the present control rod pattern and the burnup degree distribution. Then, thermal variants of the nuclear reactor are calculated based on the thus renewed control rod history data. Since the control rod history effect is reflected on the thermal variants required for the monitoring of the reactor operation, the working efficiency of the nuclear reactor can be improved significantly. (Seki, T.)

  4. The Maple reactor project

    International Nuclear Information System (INIS)

    Malkoske, G.R.; Labrie, J.-P.

    2003-01-01

    MDS Nordion supplies the majority of the world's reactor-produced medical isotopes. These isotopes are currently produced in the NRU reactor at AECL's Chalk River Laboratories (CRL). Medical isotopes and related technology are relied upon around the world to prevent, diagnose and treat disease. The NRU reactor, which has played a key role in supplying medical isotopes to date, has been in operation for over 40 years. Replacing this aging reactor has been a priority for MDS Nordion to assure the global nuclear medicine community that Canada will continue to be a dependable supplier of medical isotopes. MDS Nordion contracted AECL to construct two MAPLE reactors dedicated to the production of medical isotopes. The MDS Nordion Medical Isotope Reactor (MMIR) project started in September 1996. This paper describes the MAPLE reactors that AECL has built at its CRL site, and will operate for MDS Nordion. (author)

  5. Fission reactors and materials

    International Nuclear Information System (INIS)

    Frost, B.R.T.

    1981-12-01

    The American-designed boiling water reactor and pressurized water reactor dominate the designs currently in use and under construction worldwide. As in all energy systems, materials problems have appeared during service; these include stress-corrosion of stainless steel pipes and heat exchangers and questions regarding crack behavior in pressure vessels. To obtain the maximum potential energy from our limited uranium supplies is is essential to develop the fast breeder reactor. The materials in these reactors are subjected to higher temperatures and neutron fluxes but lower pressures than in the water reactors. The performance required of the fuel elements is more arduous in the breeder than in water reactors. Extensive materials programs are in progress in test reactors and in large test rigs to ensure that materials will be available to meet these conditions

  6. PLANEAMIENTO MULTIOBJETIVO DE SISTEMAS DE DISTRIBUCIÓN USANDO UN ALGORITMO EVOLUTIVO NSGA-II PLANEJAMENTO MULTIOBJETIVO DE SISTEMAS DE DISTRIBUIÇÃO USANDO UM ALGORITMO EVOLUTIVO NSGA-II MULTIOBJECTIVE DISTRIBUTION SYSTEM PLANNING USING AN NSGA-II EVOLUTIONARY ALGORITHM

    Directory of Open Access Journals (Sweden)

    Libardo López

    2011-06-01

    Full Text Available En este artículo se presenta una metodología para solucionar el problema del planeamiento de sistemas de distribución empleando una técnica de optimización multiobjetivo. En el modelo propuesto se consideran la ubicación y dimensionamiento de nuevos elementos y la repotenciación de elementos existentes. En el planteamiento del problema se incluyen en la función objetivo los costos de inversión y de operación y la confiabilidad de la red. Este tema de investigación es de relevancia para las empresas distribuidoras de energía eléctrica, ya que permite contar con nuevas herramientas que acercan el problema a situaciones reales, tales como considerar varios objetivos, lo cual incide favorablemente en las finanzas y en la operación del sistema. En la solución del modelo se emplea un algoritmo elitista de ordenamiento no dominado (NSGA-II, y para verificar su eficiencia se recurre a un caso de la literatura especializada, que corresponde a una red de distribución de un sistema eléctrico.Neste artigo apresenta-se uma metodologia para solucionar o problema do planejamento de sistemas de distribuição empregando uma técnica de otimização multiobjetivo. No modelo proposto considera-se a localização e dimensionamento de novos elementos e a repotenciação de elementos existentes. Na abordagem do problema incluem-se na função objetivo os custos de investimento e de operação e a confiabilidade da rede. Este tema de pesquisa é de relevância para as empresas distribuidoras de energia elétrica, já que permite contar com novas ferramentas que acercam o problema a situações reais, tais como considerar vários objetivos, o qual incide favoravelmente nas finanças e na operação do sistema. Na solução do modelo emprega-se um algoritmo elitista de ordenamento não-dominado (NSGA-II, e para verificar sua eficiência se emprega um caso da literatura especializada, que corresponde a uma rede de distribuição de um sistema el

  7. Un Algoritmo de Estimación de Distribuciones copulado con la Distribución Generalizada de Mallows para el Problema de Ruteo de Autobuses Escolares con Selección de Paradas

    Directory of Open Access Journals (Sweden)

    Ricardo Pérez-Rodríguez

    2017-07-01

    Full Text Available Resumen: Aunque los algoritmos de estimación de distribuciones fueron originalmente diseñados para resolver problemas con dominio de valores reales o enteros, en esta contribución se utilizan para la resolución de un problema basado en permutaciones. El ruteo de autobuses escolares con selección de paradas es resuelto utilizando la distribución generalizada de Mallows como un intento para describir y obtener una distribución de probabilidad explicita sobre un conjunto de rutas de autobuses escolares. Además, un operador de mutación es considerado para mejorar la estimación de la permutación central, un parámetro de la distribución de Mallows. Diferentes y diversas instancias sirvieron como parámetro de entrada y prueba para mostrar que problemas basados en permutaciones tales como el ruteo de autobuses escolares con selección de paradas pueden ser resueltos por medio de un modelo de probabilidad, y mejorar la estimación de la permutación central ayuda al desempeño del algoritmo. Abstract: Although the estimation of distribution algorithms were originally designed for solving integer or real-valued domains, this contribution applies the algorithms mentioned to deal with a permutation-based problem, called school bus routing problem with bus stop selection, using the generalized Mallows distribution as an attempt to describe and obtain an explicit probability distribution over a set of school bus routes. In addition, a mutation operator is considered for improving the estimation of the central permutation, a parameter of the Mallows distribution. Different and diverse instances served as input and test parameters in order to show that permutation-based optimization problems such as the school bus routing problem with bus stop selection can be solved by means of a probability model, and improving the estimation of the central permutation helps the performance of the algorithm. Palabras clave: Algoritmo de estimación de

  8. Predicción de la generación interna volumétrica de calor y la capacidad calorífica durante un tratamiento electromagnético del material usando algoritmos híbridos

    Directory of Open Access Journals (Sweden)

    Edgar García-Morantes

    2018-01-01

    Full Text Available Este trabajo considera la estimación de la generación interna volumétrica de calor y la capacidad calorífica de una muestra esférica sólida calentada por un campo electromagnético homogéneo variante en el tiempo. Para tal fin, la estrategia numérica soluciona el correspondiente problema inverso. Tres formas funcionales (lineal, senoidal y exponencial para el campo electromagnético fueron considerados. Ruido blanco fue agregado al perfil de temperatura teórica (i.e. la solución del problema directo para simular una situación más realística. La temperatura se pretendió que fuera leída por cuatro sensores. El problema inverso fue solucionado a través de tres diferentes enfoques: usando un optimizador tradicional, usando técnicas modernas y usando una mezcla de ambos. En el primer caso, usamos un algoritmo determinístico tradicional como lo es el de Levenberg-Marquardt (LM. En el segundo, consideramos tres metaheurísticos estocásticos: El Algoritmo de optimización de la espiral (SOA, la Búsqueda en vórtice (VS, y el método de atracción ponderada (WAM. Para el caso final, proponemos híbridos entre el LM y los algoritmos metahehurísticos. Los resultados muestran que LM converge a la solución esperada solo si las condiciones iniciales (IC están dentro de un rango limitado. Por otra parte, los metaheurísticos convergen en un amplio rango de IC pero muestra baja precisión. Los enfoques híbridos convergen y mejoran la precisión obtenida con los metaheurísticos. La diferencia entre los valores esperados y obtenidos, así como, los errores RMS son reportados y comparados para los tres métodos.

  9. Reactor Vessel Surveillance Program for Advanced Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

    2008-10-15

    This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

  10. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Carlos Ruben Calabrese

    1999-01-01

    Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

  11. Siting of research reactors

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose of this document is to develop criteria for siting and the site-related design basis for research reactors. The concepts presented in this document are intended as recommendations for new reactors and are not suggested for backfitting purposes for facilities already in existence. In siting research reactors serious consideration is given to minimizing the effects of the site on the reactor and the reactor on the site and the potential impact of the reactor on the environment. In this document guidance is first provided on the evaluation of the radiological impact of the installation under normal reactor operation and accident conditions. A classification of research reactors in groups is then proposed, together with a different approach for each group, to take into account the relevant safety problems associated with facilities of different characteristics. Guidance is also provided for both extreme natural events and for man-induced external events which could affect the safe operation of the reactor. Extreme natural events include earthquakes, flooding for river or coastal sites and extreme meteorological phenomena. The feasibility of emergency planning is finally considered for each group of reactors

  12. Reactor core for FBR type reactor

    International Nuclear Information System (INIS)

    Fujita, Tomoko; Watanabe, Hisao; Kasai, Shigeo; Yokoyama, Tsugio; Matsumoto, Hiroshi.

    1996-01-01

    In a gas-sealed assembly for a FBR type reactor, two or more kinds of assemblies having different eigen frequency and a structure for suppressing oscillation of liquid surface are disposed in a reactor core. Coolant introduction channels for introducing coolants from inside and outside are disposed in the inside of structural members of an upper shielding member to form a shielding member-cooling structure in the reactor core. A structure for promoting heat conduction between a sealed gas in the assembly and coolants at the inner side or the outside of the assembly is disposed in the reactor core. A material which generates heat by neutron irradiation is disposed in the assembly to heat the sealed gases positively by radiation heat from the heat generation member also upon occurrence of power elevation-type event to cause temperature expansion. Namely, the coolants flown out from or into the gas sealed-assemblies cause differential fluctuation on the liquid surface, and the change of the capacity of a gas region is also different on every gas-sealed assemblies thereby enabling to suppress fluctuation of the reactor power. Pressure loss is increased by a baffle plate or the like to lower the liquid surface of the sodium coolants or decrease the elevating speed thereof thereby suppressing fluctuation of the reactor power. (N.H.)

  13. Thai research reactor

    International Nuclear Information System (INIS)

    Aramrattana, M.

    1987-01-01

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  14. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

    An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

  15. Compensación de potencia reactiva en sistemas desbalanceados utilizando algoritmos genéticos Reactive power compensation in unbalanced systems using genetic algorithms

    Directory of Open Access Journals (Sweden)

    Davel Borges Vasconcellos

    2012-12-01

    Full Text Available La eficiencia energética de un sistema eléctrico depende en gran medida del factor de potencia con que opera y de una eficaz compensación de potencia reactiva si esta es necesaria. Una de las vías más utilizadas para efectuar la compensación del reactivo es el empleo de bancos de capacitores. La óptima aplicación de estos presupone tres aspectos: la selección de la capacidad más adecuada de los bancos, el tipo de compensador a utilizar, fijo o variable, así como la ubicación en el sistema de suministro eléctrico. En determinadas publicaciones, estos aspectos se tratan de forma independiente. Sin embargo, desde el punto de vista técnico ellos están mutuamente vinculados y todos poseen una implicación económica, lo que obliga a la necesidad de considerarlos en conjunto para un problema de optimización dado. Existen referencias de otros trabajos que desarrollan métodos que consideran estos aspectos de manera conjunta, pero presentan limitantes para ser aplicados en los sistemas de suministro eléctrico del sector terciario y donde predominan condiciones de desbalance. En este trabajo se presenta un método con el empleo de los algoritmos genéticos que posibilita una formulación más exacta del problema arrojando soluciones de mayor calidad. El programa desarrollado se soporta sobre software MATLAB, versión 7.8 (R2009a, utilizando las estructuras de programación de Genetic Algorithm and Direct Search Toolbox. La efectividad de su aplicación se muestra en casos de estudio correspondientes a sistemas de suministro eléctrico de dos hoteles pertenecientes al sector terciario en la provincia de Camagüey, Cuba.The energy efficiency of an electric system depends in great extent of the reactive power compensation that is carried out. One of the ways most used for reactive is power of capacitor banks. A good selection of these, presupposes three aspects: the selection of the banks capacity, the compensator type to be used and the

  16. Evaluation and tuning of control algorithms for power system stabilizers; Evaluacion y sintonizacion de algoritmos de control para el estabilizador de sistemas de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez Gonzalez, Miguel

    1998-08-01

    desventajas del diseno de ciertos ESP`s basados en tecnicas de control adaptable, logica difusa y redes neuronales artificiales. De los resultados de este estudio y considerando las caracteristicas complejas de los sistemas de potencia, posteriormente se disena y desarrolla un estabilizador basado en teoria de conjuntos difusos que utiliza como senales de entrada el error de velocidad ({Delta}{omega}) de la maquina sincrona y su aceleracion ({Delta}{omega}). Los parametros del ESP de adelanto-atraso y el desempeno del ESP difuso se validan medinte simulaciones en el dominio del tiempo empleando dos escenarios de prueba diferentes: un sistema de potencia maquina-bus infinito y un sistema multimaquina. Todas las simulaciones se efectuan utilizando una herramienta para el estudio de la estabilidad de sistemas de potencia basada en algoritmos desarrollados en MATLAB.

  17. Detección de obstáculos y espacios transitables en entornos urbanos para sistemas de ayuda a la conducción basados en algoritmos de visión estéreo implementados en GPU

    Directory of Open Access Journals (Sweden)

    B. Musleh

    2012-10-01

    Full Text Available Resumen: Tanto los sistemas avanzados de ayuda a la conducción (ADAS aplicados a la mejora de la seguridad vial, como los sistemas de navegación autónoma de vehículos, demandan sensores y algoritmos cada vez más complejos, capaces de obtener e interpretar información del entorno vial. En concreto, las mayores dificultades surgen a la hora de analizar la información proveniente de los entornos urbanos, debido a la diversidad de elementos con distintas características que existen en áreas urbanas. Estos sistemas requieren, cada vez más, que la interpretación de la información se realice en tiempo real para mejorar la toma de decisiones. Por otra parte, la visión estéreo es ampliamente utilizada en sistemas de modelado, dada la gran cantidad de información que proporciona, pero al mismo tiempo, los algoritmos basados en esta técnica requieren de un elevado tiempo de cómputo que dificulta su implementación en aplicaciones de tiempo real. En este trabajo se presenta un algoritmo basado en visión estéreo para la detección tanto de obstáculos como de espacios transitables en entornos urbanos y que ha sido implementado principalmente en GPU (Unidad de Procesamiento Gráfico para reducir el tiempo de cómputo y conseguir un funcionamiento en tiempo real. Abstract: Both advanced driver assistance systems (ADAS applied to the improvement of road safety, and autonomous navigation vehicle systems require more and more complex sensors and algorithms capable of obtaining and interpreting the information of the road environment. The greatest difficulties arise in analysing the information of the urban environments, because of the large number of elements which have different characteristics in urban areas. These systems require to interpret the information in real time to improve the decision-making. On the other hand, the stereo vision is usable in modeling systems because of the great amount of information that it provides, but at the

  18. Aplicação de um algoritmo genético para o problema do carteiro chinês em uma situação real de cobertura de arcos

    Directory of Open Access Journals (Sweden)

    Flavia Konowalenko

    2012-04-01

    Full Text Available O Problema do Carteiro Chinês é um problema de otimização que objetiva cobrir todos os arcos de um grafo, minimizando a distância total percorrida. Pode ser aplicado a grafos não-direcionados (ruas de mão dupla, direcionados (ruas de mão única ou mistos (algumas ruas de mão dupla e outras de mão única. A busca pela rota é feita por algoritmos que geram soluções aproximadas. Neste trabalho será utilizado um Algoritmo Genético para a construção de rotas que se aproximem da solução ótima. O objetivo principal será o de minimizar o custo do percurso da coleta e transporte dos resíduos sólidos urbanos, na cidade de Irati (PR, Brasil. O objetivo da modelagem foi a redução dos gastos dos recursos públicos, gerando economia à Prefeitura da cidade. A aplicação do algoritmo foi realizada em uma região central da cidade. Foram utilizados para mapeamento, dados reais cedidos por funcionários da Prefeitura. Com o auxílio do aplicativo online Google Earth, foram obtidas as coordenadas geográficas dos vértices do grafo associado ao problema. Os resultados gerados pelo algoritmo genético foram comparados com a solução ótima obtida através do software LINGO®12.0. Estes resultados se mostraram satisfatórios para a pequena instância do problema analisado. The Chinese Postman Problem is an optimization problem that aims to cover all the arcs of a graph, minimizing the total distance traveled. Can be applied to non-directed graphs (two-way streets, directed (one-way streets or mixed (some two-way streets and other one-way.These arch for the route is done by algorithms that generate approximate solutions. In this work we used a genetic algorithm for the construction of routes that approximate the optimal solution. The main objective is to minimize the cost of the course of collection and transportation solid waste in the city of Irati (PR, Brazil. The application of the algorithm was performed in a downtown area. Were used

  19. A intensidade dos algoritmos nas séries iniciais: uma imposição sócio-histórico-estrutural ou opção valiosa? p.55-76

    OpenAIRE

    Mendonça, Maria do Carmo Domite

    2009-01-01

    Como nós professores podemos reconhecer/valorizar ou não o quadro que aí está em Educação Matemática? Como os professores-pesquisadores podemos compreender a ansiedade existente em treinar os algoritmos convencionais, quando o assunto é o cálculo das operações aritméticas básicas? Um caminho para a mudança seria focalizar/discutir o que, naturalmente, tem bloqueado atitudes de maior autonomia frente a esse fato matemático, imobilizando-os mesmo para qualquer inovação. Então, usando argumentos...

  20. Elaboración de un modelo evolutivo híbrido de algoritmos genéticos y redes neuronales artificiales para dosificaciones de mezclas de concreto reforzadas con fibras metálicas

    Directory of Open Access Journals (Sweden)

    Luis Octavio González Salcedo

    2016-06-01

    Full Text Available En un ambiente computacional, un modelo evolutivo es desarrollado para proponer dosificaciones de mezclas de concretos reforzados con fibras metálicas, para solicitudes de resistencia a la compresión. El modelo es híbrido al incluir un sistema de dosificación basado en algoritmos genéticos y un sistema de estimación de propiedades basado en redes neuronales artificiales. Los resultados obtenidos son comparados con un sistema de dosificaciones reportado experimentalmente. Estas comparaciones muestran una aproximación en el proceso de simulación. Además, por las características del modelo, se considera de aporte en la tecnología del concreto.

  1. Metaheurística algoritmo genético para solução de problemas de planejamento florestal com restrições de integridade Genetic algorithm metaheuristic to solve forest planning problem with integer constraints

    Directory of Open Access Journals (Sweden)

    Flávio Lopes Rodrigues

    2004-04-01

    Full Text Available Os objetivos deste trabalho foram desenvolver e testar um algoritmo genético (AG para a solução de problemas de gerenciamento florestal com restrições de integridade. O AG foi testado em quatro problemas, contendo entre 93 e 423 variáveis de decisão, sujeitos às restrições de singularidade, produção mínima e produção máxima, periodicamente. Todos os problemas tiveram como objetivo a maximização do valor presente líquido. O AG foi codificado em ambiente delphi 5.0 e os testes foram realizados em um microcomputador AMD K6II 500 MHZ, com memória RAM de 64 MB e disco rígido de 15GB. O desempenho do AG foi avaliado de acordo com as medidas de eficácia e eficiência. Os valores ou categorias dos parâmetros do AG foram testados e comparados quanto aos seus efeitos na eficácia do algoritmo. A seleção da melhor configuração de parâmetros foi feita com o teste L&O, a 1% de probabilidade, e as análises foram realizadas através de estatísticas descritivas. A melhor configuração de parâmetros propiciou ao AG eficácia média de 94,28%, valor mínimo de 90,01%, valor máximo de 98,48%, com coeficiente de variação de 2,08% do ótimo matemático, obtido pelo algoritmo exato branch and bound. Para o problema de maior porte, a eficiência do AG foi cinco vezes superior à eficiência do algoritmo exato branch and bound. O AG apresentou-se como uma abordagem bastante atrativa para solução de importantes problemas de gerenciamento florestal.The objectives of this work was to develop and test a Genetic Algorithm (GA to solve problems of forest management with integer constraints. GA was tested in five problems containing 93 - 423 decision variables, periodically subject to singularity constraints, minimum and maximum production. The problems had the objective of maximizing the net present value. GA was codified into delphi 5.0 language and the tests were performed in a microcomputer AMD K6II 500 MHZ, with RAM memory of 64 MB

  2. Comparación de algoritmos numéricos en problemas de lubricación hidrodinámica con cavitación en dimensión uno

    OpenAIRE

    Durany, José; Calvo, N.; Vázquez Hurtado, Carlos

    2009-01-01

    En este trabajo se analizan algunos algoritmos numéricos para problemas matem,áticos unidimensionales de frontera libre que aparecen en la lubricación hidrodinámica de dispositivos eje-cojinete. Los modelos matemáticos de estos problemas de la mecánica de fluidos en capas delgadas se basan en la ecuación de Reynolds, acompañada de ciertas condiciones que tienen en cuenta los fenómenos de cavitación. En este sentido, se compara el modelo de cavitación de Elrod-Adams y el modelo de cavitación d...

  3. Uso de algoritmo de otimização na determinação de tipos de animal funcional Use of optimization algorithm for determining of animal functional types

    Directory of Open Access Journals (Sweden)

    Carlos Eduardo Nogueira Martins

    2012-08-01

    Full Text Available O presente trabalho teve como objetivo avaliar o uso de algoritmo de otimização na determinação de tipos funcionais de animais da raça Braford para diferentes condições ambientais. Foram utilizados algoritmos específicos de otimização por meio do progama computacional SYNCSA, com o objetivo de determinar subconjuntos ótimos de atributos que definem diferentes tipos funcionais, tendo em vista a eficiência de utilização da pastagem pelos animais. Tais algoritmos estão fundamentados na definição de matrizes de incidência que relacionam as variáveis de interesse. No presente estudo, a matriz B definiu a relação animais x medidas corporais; a matriz W, a relação produtividade acumulada x graus de sangue; e a matriz E, a relação graus de sangue x ambientes (com e sem restrição alimentar. Os resultados mostraram a existência de três tipos funcionais: animais de maior estrutura corporal; animais de estrutura intermediária e animais com menor estrutura, com exceção do atributo largura do peito. Os animais de maior estrutura corporal obtiveram 30 e 47,7kg a mais de terneiros desmamados, no ambiente sem restrição alimentar, que os animais de estrutura corporal média e pequena, respectivamente. No ambiente com restrição alimentar, o tipo de animal de estrutura média apresentou melhor desempenho produtivo, sendo este 18,5 e 36,8% superior aos tipos de maior e menor estrutura corporal, respectivamente. Os resultados deste trabalho demonstram que o algoritmo criado para determinação de tipos funcionais pode ser utilizado na busca do melhor biótipo animal para os diferentes sistemas de produção.This study aimed to evaluate the use of optimization algorithm to determine functional types of animals Braford for different environmental conditions. We used specific optimization algorithms through the computer program SYNCSA in order to determine optimal subsets of attributes that define different functional types in view

  4. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    Kouts, H.

    1986-01-01

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

  5. Multipurpose research reactors

    International Nuclear Information System (INIS)

    1988-01-01

    The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  6. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

  7. Fast Spectrum Reactors

    CERN Document Server

    Todd, Donald; Tsvetkov, Pavel

    2012-01-01

    Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

  8. Upgradation of Apsara reactor

    International Nuclear Information System (INIS)

    Mammen, S.; Mukherjee, P.; Bhatnagar, A.; Sasidharan, K.; Raina, V.K.

    2009-01-01

    Apsara is a 1 MW swimming pool type research reactor using high enriched uranium as fuel with light water as coolant and moderator. The reactor is in operation for more than five decades and has been extensively used for basic research, radioisotope production, neutron radiography, detector testing, shielding experiments etc. In view of its long service period, it is planned to carry out refurbishment of the reactor to extend its useful life. During refurbishment, it is also planned to upgrade the reactor to a 2 MW reactor to improve its utilization and to upgrade the structure, system and components in line with the current safety standards. This paper gives a brief account of the design features and safety aspects of the upgraded Apsara reactor. (author)

  9. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1980-09-01

    Research activities in the Division of Reactor Engineering in fiscal 1979 are described. The work of the Division is closely related to development of multi-purpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committees on Reactor Physics and on Decomissioning of Nuclear Facilities. (author)

  10. Spectral shift reactor control method

    International Nuclear Information System (INIS)

    Impink, A.J. Jr.

    1981-01-01

    A method of operating a nuclear reactor having a core and coolant displacer elements arranged in the core wherein is established a reator coolant temperature set point at which it is desired to operate said reactor and first reactor coolant temperature band limits are provided within which said set point is located and it is desired to operate said reactor charactrized in that said reactor coolant displacer elements are moved relative to the reactor core for adjusting the volume of reactor coolant in said core as said reactor coolant temperature approaches said first band limits thereby to maintain said reactor coolant temperature near said set point and within said first band limits

  11. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1985-08-01

    Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

  12. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Matsuura, Shojiro; Nakahara, Yasuaki; Takano, Hideki

    1982-09-01

    Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

  13. Power reactors operational diagnosis

    International Nuclear Information System (INIS)

    Dach, K.; Pecinka, L.

    1976-01-01

    The definition of reactor operational diagnostics is presented and the fundamental trends of research are determined. The possible sources of power reactor malfunctions, the methods of defect detection, the data evaluation and the analysis of the results are discussed in detail. In view of scarcity of a theoretical basis and of insufficient in-core instrumentation, operational diagnostics cannot be as yet incorporated in a computer-aided reactor control system. (author)

  14. Fast reactors worldwide

    International Nuclear Information System (INIS)

    Hall, R.S.; Vignon, D.

    1985-01-01

    The paper concerns the evolution of fast reactors over the past 30 years, and their present status. Fast reactor development in different countries is described, and the present position, with emphasis on cost reduction and collaboration, is examined. The French development of the fast breeder type reactor is reviewed, and includes: the acquisition of technical skills, the search for competitive costs and the spx2 project, and more advanced designs. Future prospects are also discussed. (U.K.)

  15. Pressurised water reactor operation

    International Nuclear Information System (INIS)

    Birnie, S.; Lamonby, J.K.

    1987-01-01

    The operation of a pressurized water reactor (PWR) is described with respect to the procedure for a unit start-up. The systems details and numerical data are for a four loop PWR station of the design proposed for Sizewell-'B', United Kingdom. A description is given of: the initial conditions, filling the reactor coolant system (RCS), heat-up and pressurisation of the RCS, secondary system preparations, reactor start-up, and reactivity control at power. (UK)

  16. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of four main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents, the development of an expert system for the aid to diagnosis; the development and application of a probabilistic reactor dynamics method. Main achievements in 1999 are reported

  17. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The aim of this invention is the provision of improved seals for reactor vessels in which fuel assemblies are located together with inlets and outlets for the circulation of a coolant. The object is to provide a seal arrangement for the rotatable plugs of nuclear reactor closure heads which has good sealing capacities over a wide gap during operation of the reactor but which also permits uninhibited rotation of the plugs for maintenance. (U.K.)

  18. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported.

  19. The Dragon reactor experiment

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The concept on which the Dragon Reactor Experiment was based was evolved at the Atomic Energy Research Establishment at Harwell in 1956, and in February of that year a High Temperature Gas- cooled Reactor Project Group was set up to study the feasibility of a helium-cooled reactor with a graphite or beryllium moderator, and with the emphasis on the thorium fuel cycle [af

  20. The replacement research reactor

    International Nuclear Information System (INIS)

    Cameron, R.

    1999-01-01

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  1. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

  2. Integral fast reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1989-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics

  3. Reactor BR2

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

  4. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1988-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  5. ALGORITMO ETAPA A ETAPA PARA LA SIMULACIÓN DE CASCADAS DE EXTRACCIÓN EN FASE LÍQUIDA APLICANDO EL MODELO DE EQUILIBRIO ALGORITMO ETAPA A ETAPA PARA A SIMULAÇÃO DE CASCATAS DE EXTRAÇÃO EM FASE LÍQUIDA APLICANDO O MODELO DE EQUILÍBRIO STAGE-BY-STAGE ALGORITHM FOR SIMULATION OF LIQUID PHASE EXTRACTION CASCADES APPLYING THE EQUILIBRIUM MODEL

    Directory of Open Access Journals (Sweden)

    César A Sánchez

    2009-12-01

    Full Text Available Se presenta un método de solución etapa a etapa para el conjunto de ecuaciones de balance de masa, relaciones de equilibrio, suma de composiciones y entalpía (MESH, mass equilibrium sum enthalpy que representan el modelo de equilibrio para un arreglo a contracorriente de etapas de extracción en fase líquida. El fundamento teórico se encuentra en la termodinámica: equilibrio líquido-líquido, flash isotérmico y flash adiabático. El algoritmo supera los alcances de los métodos gráficos e isotérmicos típicos en el estudio de los procesos de extracción y es aplicable a situaciones adicionales muy comunes: transferencia de calor en las etapas, etapas adiabáticas, temperaturas diferentes para los flujos de alimentación y solvente. El algoritmo se ilustra en tres ejemplos, los dos primeros en operación isotérmica con tres componentes (agua, ácido acético y acetato de butilo y diez etapas, y un tercero más elaborado que involucra transferencia de calor con cuatro componentes (agua, ácido acético, butanol y acetato de butilo y quince etapas.Apresenta-se um método de solução etapa a etapa para o conjunto de equações de balanço de massa, relações de equilíbrio, soma de composições e entalpia (MESH mass equilibrium sum enthalpy que representam o modelo de equilíbrio para um arranjo en contracorrente de períodos de extração em fase líquida. O fundamento teórico se encontra na termodinâmica: equilíbrio líquido-líquido, flash isotérmico e flash adiabático. O algoritmo supera os alcances dos métodos gráficos e isotérmicos típicos no estudo dos processos de extração e é aplicável a situações adicionais muito comuns: transferência de calor nas etapas, etapas adiabáticas, temperaturas diferentes para os fluxos de alimentação e solvente. O algoritmo se ilustra em três exemplos, os dois primeiros em operação isotérmica com três componentes (água, ácido acético e acetato de butila e dez etapas, e um

  6. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

  7. HOMOGENEOUS NUCLEAR POWER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1959-09-01

    A homogeneous nuclear power reactor utilizing forced circulation of the liquid fuel is described. The reactor does not require fuel handling outside of the reactor vessel during any normal operation including complete shutdown to room temperature, the reactor being selfregulating under extreme operating conditions and controlled by the thermal expansion of the liquid fuel. The liquid fuel utilized is a uranium, phosphoric acid, and water solution which requires no gus exhaust system or independent gas recombining system, thereby eliminating the handling of radioiytic gas.

  8. Australian research reactor studies

    International Nuclear Information System (INIS)

    McCulloch, D.B.

    1978-01-01

    The Australian AEC has two research reactors at the Lucas Heights Research Establishment, a 10 HW DIDO class materials testing reactor, HIFAR, and a smaller 100kW reactor MOATA, which was recently upgraded from 10kW power level. Because of the HIFAR being some 20 years old, major renewal and repair programmes are necessary to keep it operational. To enable meeting projected increases in demand for radioisotopes, plans for a new reactor to replace the HIFAR have been made and the design criteria are described in the paper. (author)

  9. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Moir, R.W.

    1978-01-01

    We have carried out conceptual design studies of fusion reactors based on the three current mirror confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fission fuel for fission reactors. We have designed a large commercial hybrid based on standard mirror confinement, and also a small pilot plant hybrid. Tandem mirror designs include a commercial 1000 MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single cell pilot plant

  10. Reactor feedwater system

    International Nuclear Information System (INIS)

    Hikabe, Katsumi.

    1978-01-01

    Purpose: In order to prevent thermal stresses of a core of PWR type reactor, described has been a method for feeding heated recirculating water to the core in the case of the reactor start-up or shut-down. Constitution: A recirculating water is degassed, cleaned up and heated in the steam condensers, and then feeds the water to the reactor, characterized in that heaters are provided in the bypasses of the turbine, so that heated water is constantly supplied to the reactor. (Nakamura, S.)

  11. Remote Reactor Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Bernstein, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dazeley, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dobie, Doug [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Marleau, Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brennan, Jim [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gerling, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sumner, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sweany, Melinda [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-10-21

    The overall goal of the WATCHMAN project is to experimentally demonstrate the potential of water Cerenkov antineutrino detectors as a tool for remote monitoring of nuclear reactors. In particular, the project seeks to field a large prototype gadolinium-doped, water-based antineutrino detector to demonstrate sensitivity to a power reactor at ~10 kilometer standoff using a kiloton scale detector. The technology under development, when fully realized at large scale, could provide remote near-real-time information about reactor existence and operational status for small operating nuclear reactors out to distances of many hundreds of kilometers.

  12. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2002-01-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed

  13. Trench reactor: an overview

    International Nuclear Information System (INIS)

    Spinrad, B.I.; Rohach, A.F.; Razzaque, M.M.; Sankoorikal, J.T.; Schmidt, R.S.; Lofshult, J.; Ramin, T.; Sokmen, N.; Lin, L.C.

    1988-01-01

    Recent fast, sodium-cooled reactor designs reflect new conditions. In nuclear energy these conditions are (a) emphasis on maintainability and operability, (b) design for more transparent safety, and (c) a surplus of uranium and enrichment availability that eases concerns about light water reactor fueling costs. In utility practice the demand is for less capital exposure, short construction time, smaller new unit sizes, and low capital cost. The PRISM, SAFR, and integral fast reactor (IFR) concepts are responses to these conditions. Fast reactors will not soon be deployed commercially, so more radical designs can be considered. The trench reactor is the product of such thinking. Its concepts are intended as contributions to the literature, which may be picked up by one of the existing programs or used in a new experimental project. The trench reactor is a thin-slab, pool-type reactor operated at very low power density and- for sodium-modest temperature. The thin slab is repeated in the sodium tank and the reactor core. The low power density permits a longer than conventional core height and a large-diameter fuel pin. Control is by borated steel slabs that can be lowered between the core and lateral sodium reflector. Shutdown is by semaphore slabs that can be swung into place just outside the control slabs. The paper presents major characteristics of the trench reactor that have been changed since the last report

  14. New reactor concepts

    International Nuclear Information System (INIS)

    Meskens, G.; Govaerts, P.; Baugnet, J.-M.; Delbrassine, A.

    1998-11-01

    The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

  15. Advanced CANDU reactors

    International Nuclear Information System (INIS)

    Dunn, J.T.; Finlay, R.B.; Olmstead, R.A.

    1988-12-01

    AECL has undertaken the design and development of a series of advanced CANDU reactors in the 700-1150 MW(e) size range. These advanced reactor designs are the product of ongoing generic research and development programs on CANDU technology and design studies for advanced CANDU reactors. The prime objective is to create a series of advanced CANDU reactors which are cost competitive with coal-fired plants in the market for large electricity generating stations. Specific plant designs in the advanced CANDU series will be ready for project commitment in the early 1990s and will be capable of further development to remain competitive well into the next century

  16. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Doshi, P.K.; George, R.A.; Dollard, W.J.

    1982-01-01

    A mechanical spectral shift arrangement for controlling a nuclear reactor includes a plurality of reactor coolant displacer members which are inserted into a reactor core at the beginning of the core life to reduce the volume of reactor coolant-moderator in the core at start-up. However, as the reactivity of the core declines with fuel depletion, selected displacer members are withdrawn from the core at selected time intervals to increase core moderation at a time when fuel reactivity is declining. (author)

  17. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  18. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-02-15

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation. [Serbo-Croat] Pored osnovnih karakeristika reaktora RA, organizacije rada i finansijskih pokazatelja, razmatra se stanje opreme reaktora nakon 18 godina rada, pitanja dozvole za rad sa 80% obogacenim gorivom, problem skladistenja isluzenog goriva u bazenu zgrade reaktora i potreba za obnavljanjem komponenti opreme, pre svega elektronske.

  19. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    Frisch, E.; Andrews, H.N.

    1976-01-01

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  20. Multi purpose research reactor

    International Nuclear Information System (INIS)

    Raina, V.K.; Sasidharan, K.; Sengupta, Samiran; Singh, Tej

    2006-01-01

    At present Dhruva and Cirus reactors provide the majority of research reactor based facilities to cater to the various needs of a vast pool of researchers in the field of material sciences, physics, chemistry, bio sciences, research and development work for nuclear power plants and production of radio isotopes. With a view to further consolidate and expand the scope of research and development in nuclear and allied sciences, a new 20 MWt multi purpose research reactor is being designed. This paper describes some of the design features and safety aspects of this reactor

  1. FBR type reactors

    International Nuclear Information System (INIS)

    Suzuoki, Akira; Yamakawa, Masanori.

    1985-01-01

    Purpose: To enable safety and reliable after-heat removal from a reactor core. Constitution: During ordinary operation of a FBR type reactor, sodium coolants heated to a high temperature in a reactor core are exhausted therefrom, collide against the reactor core upper mechanisms to radially change the flowing direction and then enter between each of the guide vanes. In the case if a main recycling pump is failed and stopped during reactor operation and the recycling force is eliminated, the swirling stream of sodium that has been resulted by the flow guide mechanism during normal reactor operation is continuously maintained within a plenum at a high temperature. Accordingly, the sodium recycling force in the coolant flow channels within the reactor vessel can surely be maintained for a long period of time due to the centrifugal force of the sodium swirling stream. In this way, since the reactor core recycling flow rate can be secured even after the stopping of the main recycling pump, after-heat from the reactor core can safely and surely be removed. (Seki, T.)

  2. FBR type reactor

    International Nuclear Information System (INIS)

    Hayase, Tamotsu.

    1991-01-01

    The present invention concerns an FBR type reactor in which transuranium elements are eliminated by nuclear conversion. There are loaded reactor core fuels being charged with mixed oxides of plutonium and uranium, and blanket fuels mainly comprising depleted uranium. Further, liquid sodium is used as coolants. As transuranium elements, isotope elements of neptunium, americium and curium contained in wastes taken out from light water reactors or the composition thereof are used. The reactor core comprises a region with a greater mixing ratio and a region with a less mixing ratio of the transuranium elements. The mixing ratio of the transuranium elements is made greater for the fuels in the reactor core region at the boundary with the blanket of great neutron leakage. With such a constitution, since the positive reactivity value at the reactor core central portion is small in the Na void reactivity distribution in the reactor core, the positive reactivity is small upon Na boiling in the reactor core central region upon occurrence of imaginable accident, to attain reactor safety. (I.N.)

  3. Farewell to a reactor

    International Nuclear Information System (INIS)

    Skanborg, P.

    1976-01-01

    Denmark's second reactor, DR 2, whose first criticality took place the night of 18/19 December 1958 was shut down for the last time on 31 October 1975. It was a light-water moderrated and cooled reactor of swimming-pool type with a thermal power of 5 MW, using 90% enriched uranium. The operation is described. The reactor and auxiliary equipment are now being put 'in store' - all fuel elements sent for reprocessing, the reactor tank and cooling circuits emptied, and a lead shielding placed over the tank opening. The rest of the equipment will remain in place. (B.P.)

  4. Indian advanced nuclear reactors

    International Nuclear Information System (INIS)

    Saha, D.; Sinha, R.K.

    2005-01-01

    For sustainable development of nuclear energy, a number of important issues like safety, waste management, economics etc. are to be addressed. To do this, a number of advanced reactor designs as well as fuel cycle technologies are being pursued worldwide. The advanced reactors being developed in India are the AHWR and the CHTR. Both the reactors use thorium based fuel and have many passive features. This paper describes the Indian advanced reactors and gives a brief account of the international initiatives for the sustainable development of nuclear energy. (author)

  5. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

    Barral, J.C.; Zaetta, A.; Johner, J.; Mathoniere, G.

    2000-01-01

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  6. RB Research nuclear reactor RB reactor, Annual report for 2000

    International Nuclear Information System (INIS)

    Milosevic, M.

    2000-12-01

    Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

  7. FFTF reactor assembly system technology

    International Nuclear Information System (INIS)

    Mangelsdorf, T.A.

    1975-01-01

    An overview is presented of the FFTF reactor and plant together with descriptions of core components, core internals, core system, primary and secondary control rod system, reactor instrumentation, reactor vessel and closure head, and supporting test programs

  8. Reactor building for a nuclear reactor

    International Nuclear Information System (INIS)

    Haidlen, F.

    1976-01-01

    The invention concerns the improvement of the design of a liner, supported by a latticed steel girder structure and destined for guaranteeing a gastight closure for the plant compartments in the reactor building of a pressurized water reactor. It is intended to provide the steel girder structure on their top side with grates, being suited for walking upon, and to hang on their lower side diaphragms in modular construction as a liner. At the edges they may be sealed with bellows in order to avoid thermal stresses. The steel girder structure may at the same time serve as supports for parts of the steam pipe. (RW) [de

  9. Revitalization of reactor usage through reactor sharing

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1986-01-01

    The purpose of this work was to renew interest in using the University Florida Training Reactor (UFTR) for educational and training purposes outside the Nuclear Engineering Sciences (NES) and Environmental Engineering Sciences (EES) Departments at the University of Florida and for research by others outside the NES Department. The availability of the UFTR made possible through a US Department of Energy (DOE) Reactor Sharing Grant provided the mechanism to pursue generation of renewed interest at all levels both within the University of Florida and from other educational and corporate institutions

  10. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

    An improvement is proposed concerning the easier disengagement of the coupling at the reactor coolant pump for a nuclear reactor transporting a pressurized coolant. According to the invention the disengaging coupling consists of two parts separated by screws. At least one of the screws contains a propellent charge ananged within a bore and provided with a speed-dependent ignition device in such a way that by separation of the screws at overspeeds the coupling is disengaged. The sub-claims are concerned with the kind of ignition ot the propellent charge. (UWI) [de

  11. The fusion reactor

    International Nuclear Information System (INIS)

    Brennan, M.H.

    1974-01-01

    Basic principles of the fusion reactor are outlined. Plasma heating and confinement schemes are described. These confinement systems include the linear Z pinch, magnetic mirrors and Tokamaks. A fusion reactor is described and a discussion is given of its environmental impact and its fuel situation. (R.L.)

  12. Molten salt reactor concept

    International Nuclear Information System (INIS)

    Sood, D.D.

    1980-01-01

    Molten salt reactor is an advanced breeder concept which is suited for the utilization of thorium for nuclear power production. This reactor is based on the use of solutions of uranium or plutonium fluorides in LiF-BeF 2 -ThF 4 as fuel. Unlike the conventional reactors, no external coolant is used in the reactor core and the fuel salt itself is circulated through heat exchangers to transfer the fission produced heat to a secondary salt (NaF-NaBF 4 ) for steam generation. A part of the fuel stream is continuously processed to isolate 233 Pa, so that it can decay to fissile 233 U without getting converted to 234 Pa, and for the removal of neutron absorbing fission products. This on-line processing scheme makes this reactor concept to achieve a breeding ratio of 1.07 which is the highest for any thermal breeder reactor. Experimental studies at the Bhabha Atomic Research Centre, Bombay, have established the use of plutonium as fuel for this reactor. This molten salt reactor concept is described and the work conducted at the Bhabha Atomic Research Centre is summarised. (auth.)

  13. The heavy water reactors

    International Nuclear Information System (INIS)

    Brudermueller, G.

    1976-01-01

    This is a survey of the development so far of this reactor line which is in operation all over the world in various types (e.g. BHWR, PHWR). MZFR and the CANDU-type reactors are discussed in more detail. (UA) [de

  14. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1983-01-01

    Purpose : To flatten the radial power distribution in the reactor core thereby improve the thermal performance of the reactor core by making the moderator-fuel ratio of fuel assemblies different depending on their position in the reactor core. Constitution : The volume of fuels disposed in the peripheral area of the reactor core is decreased by the increase of the volume of moderators in fuel assemblies disposed in the peripheral area of the reactor core to thereby make the moderator-fuel volume greater in the peripheral area than that in the central area. The moderator-fuel ratio adjustment is attained by making the number of water rods greater, decreasing the diameter of fuel pellets or decreasing the number of fuel pins in fuel assemblies disposed at the peripheral area of the reactor core as compared with fuel assemblies disposed at the central area of the reactor core. In this way, the infinite multiplication factors of fuels can be increased to thereby improve the reactor core performance. (Aizawa, K.)

  15. Osiris reactor descriptive report

    International Nuclear Information System (INIS)

    1976-03-01

    OSIRIS is a swimming pool reactor of 70 MW thermal power. Its main purpose is the irradiation of reactor materials in high neutron flux. A description is given of the air conditioning, ventilation, and radioactive gas removal system. (R.L.)

  16. FBR type reactor core

    International Nuclear Information System (INIS)

    Tamiya, Tadashi; Kawashima, Katsuyuki; Fujimura, Koji; Murakami, Tomoko.

    1995-01-01

    Neutron reflectors are disposed at the periphery of a reactor core fuel region and a blanket region, and a neutron shielding region is disposed at the periphery of them. The neutron reflector has a hollow duct structure having a sealed upper portion, a lower portion opened to cooling water, in which a gas and coolants separately sealed in the inside thereof. A driving pressure of a primary recycling pump is lowered upon reduction of coolant flow rate, then the liquid level of coolants in the neutron reflector is lowered due to imbalance between the driving pressure and a gas pressure, so that coolants having an effect as a reflector are eliminated from the outer circumference of the reactor core. Therefore, the amount of neutrons leaking from the reactor core is increased, and negative reactivity is charged to the reactor core. The negative reactivity of the neutron reflector is made greater than a power compensation reactivity. Since this enables reactor scram by using an inherent performance of the reactor core, the reactor core safety of an LMFBR-type reactor can be improved. (I.N.)

  17. Mirror hybrid reactor studies

    International Nuclear Information System (INIS)

    Bender, D.J.

    1978-01-01

    The hybrid reactor studies are reviewed. The optimization of the point design and work on a reference design are described. The status of the nuclear analysis of fast spectrum blankets, systems studies for fissile fuel producing hybrid reactor, and the mechanical design of the machine are reviewed

  18. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    2000-01-01

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of two main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents. Main achievements in 1999 are reported

  19. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.; Lineberry, M.J.

    1990-01-01

    Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 5 refs., 3 figs

  20. Gas-cooled reactors

    International Nuclear Information System (INIS)

    Vakilian, M.

    1977-05-01

    The present study is the second part of a general survey of Gas Cooled Reactors (GCRs). In this part, the course of development, overall performance and present development status of High Temperature Gas Cooled Reactors (HTCRs) and advances of HTGR systems are reviewed. (author)

  1. A nuclear power reactor

    International Nuclear Information System (INIS)

    Borrman, B.E.; Broden, P.; Lundin, N.

    1979-12-01

    The invention consists of shock absorbing support beams fastened to the underside of the reactor tank lid of a BWR type reactor, whose purpose is to provide support to the steam separator and dryer unit against accelerations due to earthquakes, without causing undue thermal stresses in the unit due to differential expansion. (J.I.W.)

  2. International thermal reactor development

    International Nuclear Information System (INIS)

    Zebroski, E.L.

    1977-01-01

    The worldwide development of nuclear power plants is reviewed. Charts are presented which show the commitment to light-water reactor capacity construction with breakdown by region and country. Additional charts show the major nuclear research centers which have substantial scope in light water reactor development and extensive international activities

  3. Thermal reactor strategy

    International Nuclear Information System (INIS)

    1981-01-01

    This statement sets down briefly the CEGB's views on the requirement for nuclear power and outlines current progress in the implementation of the CEGB's thermal reactor strategy. The programme is traced historically, together with statements of Government policy. The place of Magnox, AGR, SGHWR, PWR and fast breeder reactors is discussed. Advantages and problems associated with the various types are outlined. (U.K.)

  4. Supercritical Water Reactors

    International Nuclear Information System (INIS)

    Bouchter, J.C.; Dufour, P.; Guidez, J.; Latge, C.; Renault, C.; Rimpault, G.

    2014-01-01

    The supercritical water reactor (SCWR) is one of the 6 concepts selected for the 4. generation of nuclear reactors. SCWR is a new concept, it is an attempt to optimize boiling water reactors by using the main advantages of supercritical water: only liquid phase and a high calorific capacity. The SCWR requires very high temperatures (over 375 C degrees) and very high pressures (over 22.1 MPa) to operate which allows a high conversion yield (44% instead of 33% for a PWR). Low volumes of coolant are necessary which makes the neutron spectrum shift towards higher energies and it is then possible to consider fast reactors operating with supercritical water. The main drawbacks of supercritical water is the necessity to use very high pressures which has important constraints on the reactor design, its physical properties (density, calorific capacity) that vary strongly with temperatures and pressures and its very high corrosiveness. The feasibility of the concept is not yet assured in terms of adequate materials that resist to corrosion, reactor stability, reactor safety, and reactor behaviour in accidental situations. (A.C.)

  5. Reactor Materials Research

    International Nuclear Information System (INIS)

    Van Walle, E.

    2001-01-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  6. Fusion reactors - types - problems

    International Nuclear Information System (INIS)

    Schmitter, K.H.

    1979-07-01

    A short account is given of the principles of fusion reactions and of the expected advantages of fusion reactors. Descriptions are presented of various Tokamak experimental devices being developed in a number of countries and of some mirror machines. The technical obstacles to be overcome before a fusion reactor could be self-supporting are discussed. (U.K.)

  7. Reactor cost driving items

    International Nuclear Information System (INIS)

    Spears, W.R.

    1987-01-01

    Assuming that the design solutions presently perceived for NET can be extrapolated for use in a power reactor, and using costing experience with present day fusion experiments and with fission power plants, the major components of the cost of a tokamak fusion power reactor are described. The analysis shows the emphasis worth placing on various areas of plant design to reduce costs

  8. Tank type reactor

    International Nuclear Information System (INIS)

    Otsuka, Fumio.

    1989-01-01

    The present invention concerns a tank type reactor capable of securing reactor core integrity by preventing incorporation of gases to an intermediate heat exchanger, thgereby improving the reliability. In a conventional tank type reactor, since vortex flows are easily caused near the inlet of an intermediate heat exchanger, there is a fear that cover gases are involved into the coolant main streams to induce fetal accidents. In the present invention, a reactor core is suspended by way of a suspending body to the inside of a reactor vessel and an intermediate heat exchanger and a pump are disposed between the suspending body and the reactor vessel, in which a vortex current preventive plate is attached at the outside near the coolant inlet on the primary circuit of the intermediate heat exchanger. In this way vortex or turbulence near the inlet of the intermediate heata exchanger or near the surface of coolants can be prevented. Accordingly, the cover gases are no more involved, to insure the reactor core integrity and obtain a tank type nuclear reactor of high reliability. (I.S.)

  9. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2001-04-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  10. Space Nuclear Reactor Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Poston, David Irvin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-03-06

    We needed to find a space reactor concept that could be attractive to NASA for flight and proven with a rapid turnaround, low-cost nuclear test. Heat-pipe-cooled reactors coupled to Stirling engines long identified as the easiest path to near-term, low-cost concept.

  11. Reactor dynamics calculations

    International Nuclear Information System (INIS)

    Devooght, J.; Lefvert, T.; Stankiewiez, J.

    1981-01-01

    This chapter deals with the work done in reactor dynamics within the Coordinated Research Program on Transport Theory and Advanced Reactor Calculations by three groups in Belgium, Poland, Sweden and Italy. Discretization methods in diffusion theory, collision probability methods in time-dependent neutron transport and singular perturbation method are represented in this paper

  12. Practical considerations for the implantation of a fuzzy control algorithm in a DSP; Consideraciones practicas para la implantacion de un algoritmo de control difuso en un DSP

    Energy Technology Data Exchange (ETDEWEB)

    Perez C, B.; Benitez R, J.S.; Pacheco S, J.O. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    The development of a digital system based on a DSP to implant a Mamdani type algorithm of fuzzy control whose objective is to regulate the neutron power in a nuclear research reactor Type TRIGA Mark III is presented. Its are simultaneously carried out the aggregation des fuzzy stages discreeting the universe of the output variable. The format MPF for the handling of the floating point in the arithmetic operations is used. (Author)

  13. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ballagny, A. [Commissariat a l`Energie Atomique, Saclay (France)

    1997-08-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm{sup 3}. The OSIRIS reactor has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 2} fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU.

  14. Compact torsatron reactors

    International Nuclear Information System (INIS)

    Lyon, J.F.; Carreras, B.A.; Lynch, V.E.; Tolliver, J.S.; Sviatoslavsky, I.N.

    1988-05-01

    Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R 0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R 0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

  15. Iris reactor conceptual design

    International Nuclear Information System (INIS)

    Carelli, M.D.; Conway, L.E.; Petrovic, B.; Paramonov, D.V.; Galvin, M.; Todreas, N.E.; Lombardi, C.V.; Maldari, F.; Ricotti, M.E.; Cinotti, L.

    2001-01-01

    IRIS (International Reactor Innovative and Secure) is a modular, integral, light water cooled, low-to-medium power (100-350 MWe) reactor which addresses the requirements defined by the US DOE for Generation IV reactors, i.e., proliferation resistance, enhanced safety, improved economics and fuel cycle sustainability. It relies on the proven technology of light water reactors and features innovative engineering, but it does not require new technology development. This paper discusses the current reference IRIS design, which features a 1000 MWt thermal core with proven 5%-enriched uranium oxide fuel and five-year long straight burn fuel cycle, integral reactor vessel housing helical tube steam generators and immersed spool pumps. Other major contributors to the high level of safety and economic attractiveness are the safety by design and optimized maintenance approaches, which allow elimination of some classes of accidents, lower capital cost, long operating cycle, and high capacity factors. (author)

  16. The secure heating reactor

    International Nuclear Information System (INIS)

    Pind, C.

    1987-01-01

    The SECURE heating reactor was designed by ASEA-ATOM as a realistic alternative for district heating in urban areas and for supplying heat to process industries. SECURE has unique safety characteristics, that are based on fundamental laws of physics. The safety does not depend on active components or operator intervention for shutdown and cooling of the reactor. The inherent safety characteristics of the plant cannot be affected by operator errors. Due to its very low environment impact, it can be sited close to heat consumers. The SECURE heating reactor has been shown to be competitive in comparison with other alternatives for heating Helsinki and Seoul. The SECURE heating reactor forms a basis for the power-producing SECURE-P reactor known as PIUS (Process Inherent Ultimate Safety), which is based on the same inherent safety principles. The thermohydraulic function and transient response have been demonstrated in a large electrically heated loop at the ASEA-ATOM laboratories

  17. Nuclear reactor design

    CERN Document Server

    2014-01-01

    This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

  18. Mirror reactor surface study

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, A. L.; Damm, C. C.; Futch, A. H.; Hiskes, J. R.; Meisenheimer, R. G.; Moir, R. W.; Simonen, T. C.; Stallard, B. W.; Taylor, C. E.

    1976-09-01

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included.

  19. Reactor control device

    International Nuclear Information System (INIS)

    Fukami, Haruo; Morimoto, Yoshinori.

    1981-01-01

    Purpose: To operate a reactor always with safety operation while eliminating the danger of tripping. Constitution: In a reactor control device adapted to detect the process variants of a reactor, control a control rod drive controlling system based on the detected signal to thereby control the driving the control rods, control the reactor power and control the electric power generated from an electric generator by the output from the reactor, detection means is provided for the detection of the electric power from said electric generator, and a compensation device is provided for outputting control rod driving compensation signals to the control rod driving controlling system in accordance with the amount of variation in the detected value. (Seki, T.)

  20. Reactor feedwater device

    International Nuclear Information System (INIS)

    Igarashi, Noboru.

    1986-01-01

    Purpose: To suppress soluble radioactive corrosion products in a feedwater device. Method: In a light water cooled nuclear reactor, an iron injection system is connected to feedwater pipeways and the iron concentration in the feedwater or reactor coolant is adjusted between twice and ten times of the nickel concentration. When the nickel/iron ratio in the reactor coolant or feedwater goes nearer to 1/2, iron ions are injected together with iron particles to the reactor coolant to suppress the leaching of stainless steels, decrease the nickel in water and increase the iron concentration. As a result, it is possible to suppress the intrusion of nickel as one of parent nuclide of radioactive nuclides. Further, since the iron particles intruded into the reactor constitute nuclei for capturing the radioactive nuclides to reduce the soluble radioactive corrosion products, the radioactive nuclides deposited uniformly to the inside of the pipeways in each of the coolant circuits can be reduced. (Kawakami, Y.)

  1. Research reactor DHRUVA

    International Nuclear Information System (INIS)

    Veeraraghaven, N.

    1990-01-01

    DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 10 14 n/cm 2 /sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

  2. Reactor power control device

    International Nuclear Information System (INIS)

    Kobayashi, Akira.

    1980-01-01

    Purpose: To prevent misoperation in a control system for the adjustment of core coolant flow rate, and the increase in the neutron flux density caused from the misoperation in BWR type reactors. Constitution: In a reactor power control system adapted to control the reactor power by the adjustment of core flow rate, average neutron flux signals of a reactor core, entire core flow rate signals and operation state signals for coolant recycling system are inputted to a microcomputer. The outputs from the computer are sent to a recycling MG set speed controller to control the reactor core flow rate. The computer calculates the change ratio with time in the average neutron flux signals, correlation between the average neutron flux signals and the entire core flow rate signals, change ratio with time in the operation state signals for the coolant recycling system and the like and judges the abnormality in the coolant recycling system based on the calculated results. (Ikeda, J.)

  3. Fusion reactor pumped laser

    International Nuclear Information System (INIS)

    Jassby, D.L.

    1988-01-01

    A nuclear pumped laser is described comprising: a toroidal fusion reactor, the reactor generating energetic neutrons; an annular gas cell disposed around the outer periphery of the reactor, the cell including an annular reflecting mirror disposed at the bottom of the cell and an annular output window disposed at the top of the cell; a gas lasing medium disposed within the annular cell for generating output laser radiation; neutron reflector material means disposed around the annular cell for reflecting neutrons incident thereon back into the gas cell; neutron moderator material means disposed between the reactor and the gas cell and between the gas cell and the neutron reflector material for moderating the energy of energetic neutrons from the reactor; converting means for converting energy from the moderated neutrons to energy pumping means for pumping the gas lasing medium; and beam compactor means for receiving output laser radiation from the annular output window and generating a single output laser beam therefrom

  4. Reactor core cooling device

    International Nuclear Information System (INIS)

    Kobayashi, Masahiro.

    1986-01-01

    Purpose: To safely and effectively cool down the reactor core after it has been shut down but is still hot due to after-heat. Constitution: Since the coolant extraction nozzle is situated at a location higher than the coolant injection nozzle, the coolant sprayed from the nozzle, is free from sucking immediately from the extraction nozzle and is therefore used effectively to cool the reactor core. As all the portions from the top to the bottom of the reactor are cooled simultaneously, the efficiency of the reactor cooling process is increased. Since the coolant extraction nozzle can be installed at a point considerably higher than the coolant injection nozzle, the distance from the coolant surface to the point of the coolant extraction nozzle can be made large, preventing cavitation near the coolant extraction nozzle. Therefore, without increasing the capacity of the heat exchanger, the reactor can be cooled down after a shutdown safely and efficiently. (Kawakami, Y.)

  5. Mirror reactor surface study

    International Nuclear Information System (INIS)

    Hunt, A.L.; Damm, C.C.; Futch, A.H.; Hiskes, J.R.; Meisenheimer, R.G.; Moir, R.W.; Simonen, T.C.; Stallard, B.W.; Taylor, C.E.

    1976-01-01

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included

  6. Status of French reactors

    International Nuclear Information System (INIS)

    Ballagny, A.

    1997-01-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm 3 . The OSIRIS reactor has already been converted to LEU. It will use U 3 Si 2 as soon as its present stock of UO 2 fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU

  7. The CAREM reactor and present currents in reactor design

    International Nuclear Information System (INIS)

    Ordonez, J.P.

    1990-01-01

    INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author) [es

  8. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Hirota, Jitsuya; Asaoka, Takumi; Suzuki, Tomoo; Mitani, Hiroshi; Akino, Fujiyoshi

    1977-09-01

    Research activities in the Division of Reactor Engineering in fiscal 1976 are described. Works of the division concern mainly the development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and the development of Liquid Metal Fast Breeder Reactor in Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and activities of the Committee on Reactor Physics. (auth.)

  9. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1978-10-01

    Research activities in the Division of Reactor Engineering in fiscal 1977 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committee on Reactor Physics. (Author)

  10. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1976-09-01

    Research activities conducted in Reactor Engineering Division in fiscal 1975 are summarized in this report. Works in the division are closely related to the development of multi-purpose High-temperature Gas Cooled Reactor, the development of Liquid Metal Fast Breeder Reactor by Power Reactor and Nuclear Fuel Development Corporation, and engineering research of thermonuclear fusion reactor. Many achievements are described concerning nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology and activities of the Committee on Reactor Physics. (auth.)

  11. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1984-08-01

    Research and development activities in the Department of Reactor Engineering in fiscal 1983 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  12. Multi-purpose reactor

    International Nuclear Information System (INIS)

    1991-05-01

    The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MW t h, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co 60 ) production capacity is 50000 Ci/yr, 200 Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N 16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

  13. Mirror reactor studies

    International Nuclear Information System (INIS)

    Moir, R.W.; Barr, W.L.; Bender, D.J.

    1977-01-01

    Design studies of a fusion mirror reactor, a fusion-fission mirror reactor, and two small mirror reactors are summarized. The fusion reactor uses 150-keV neutral-beam injectors based on the acceleration of negative ions. The injectors provide over 1 GW of continuous power at an efficiency greater than 80%. The fusion reactor has three-stage, modularized, Venetian blind, plasma direct converter with a predicted efficiency of 59% and a new concept for removal of the lune-shaped blanket: a crane is brought between the two halves of the Yin-Yang magnet, which are separated by a float. The design has desirable features such as steady-state operation, minimal impurity problems, and low first-wall thermal stress. The major disadvantage is low Q resulting in high re-circulating power and hence high cost of electrical power. However, the direct capital cost per unit of gross electrical power is reasonable [$1000/kW(e)]. By contrast, the fusion-fission reactor design is not penalized by re-circulating power and uses relatively near-term fusion technology being developed for the fusion power program. New results are presented on the Th- 233 U and the U- 239 Pu fuel cycles. The purpose of this hybrid is fuel production, with projected costs at $55/g of Pu or $127/g of 233 U. Blanket and cooling system designs, including an emergency cooling system, by General Atomic Company, lead us to the opinion that the reactor can meet expected safety standards for licensing. The smallest mirror reactor having only a shield between the plasma and the coil is the 4.2-m long fusion engineering research facility (FERF) designed for material irradiation. The smallest mirror reactor having both a blanket and shield is the 7.5-m long experimental power reactor (EPR), which has both a fusion and a fusion-fission version. (author)

  14. Análisis y estudio de las técnicas de compresión de datos para la integración de la tecnología PDH/SDH sobre redes ethernet e implementación de un algoritmo de compresión mediante software de simulación

    OpenAIRE

    Gálvez Castillo, Juan Carlos; Morocho Vallejo, Luis Roberto

    2010-01-01

    El presente Proyecto de Grado, titulado: Análisis y estudio de las técnicas de compresión de datos para la integración de la tecnología PDH/SDH sobre redes Ethernet e implementación de un algoritmo de compresión mediante software de simulación, comprende un estudio investigativo de las características, ventajas y desventajas de las técnicas de compresión de datos, comprende también de la implementación de un algoritmo de compresión que demuestre mediante un software de simulación dichas venta...

  15. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    Hicks, D.

    1970-04-01

    The principles of nuclear, thermal and hydraulic performance calculations for water cooled reactors are discussed. The principles are illustrated by describing their implementation in the UKAEA PATRIARCH scheme of computer codes. This material was originally delivered as a course of lectures at the Technical University of Helsinki in Summer of 1969.

  16. Reactor scram device for FBR type reactor

    International Nuclear Information System (INIS)

    Kumasaka, Katsuyuki; Arashida, Genji; Itooka, Satoshi.

    1991-01-01

    In a control rod attaching structure in a reactor scram device of an FBR type reactor, an anti-rising mechanism proposed so far against external upward force upon occurrence of earthquakes relies on the engagement of a mechanical structure but temperature condition is not taken into consideration. Then, in the present invention, a material having curie temperature characteristics and which exhibits ferromagnetism only under low temperature condition and a magnet device are disposed to one of a movable control rod and a portion secured to the reactor. Alternatively, a bimetal member or a shape memory alloy which actuates to fix to the mating member only under low temperature condition is secured. The fixing device is adapted to operate so as to secure the control rods when the low temperature state is caused depending on the temperature condition. With such a constitution, when the control rods are separated from a driving device, they are prevented from rising even if they undergo external upward force due to earthquakes and so on, which can improve the reactor safety. (N.H.)

  17. Fourth Generation Reactor Concepts

    International Nuclear Information System (INIS)

    Furtek, A.

    2008-01-01

    Concerns over energy resources availability, climate changes and energy supply security suggest an important role for nuclear energy in future energy supplies. So far nuclear energy evolved through three generations and is still evolving into new generation that is now being extensively studied. Nuclear Power Plants are producing 16% of the world's electricity. Today the world is moving towards hydrogen economy. Nuclear technologies can provide energy to dissociate water into oxygen and hydrogen and to production of synthetic fuel from coal gasification. The introduction of breeder reactors would turn nuclear energy from depletable energy supply into an unlimited supply. From the early beginnings of nuclear energy in the 1940s to the present, three generations of nuclear power reactors have been developed: First generation reactors: introduced during the period 1950-1970. Second generation: includes commercial power reactors built during 1970-1990 (PWR, BWR, Candu, Russian RBMK and VVER). Third generation: started being deployed in the 1990s and is composed of Advanced LWR (ALWR), Advanced BWR (ABWR) and Passive AP600 to be deployed in 2010-2030. Future advances of the nuclear technology designs can broaden opportunities for use of nuclear energy. The fourth generation reactors are expected to be deployed by 2030 in time to replace ageing reactors built in the 1970s and 1980s. The new reactors are to be designed with a view of the following objectives: economic competitiveness, enhanced safety, minimal radioactive waste production, proliferation resistance. The Generation IV International Forum (GIF) was established in January 2000 to investigate innovative nuclear energy system concepts. GIF members include Argentina, Brazil, Canada, Euratom, France Japan, South Africa, South Korea, Switzerland, United Kingdom and United States with the IAEA and OECD's NEA as permanent observers. China and Russia are expected to join the GIF initiative. The following six systems

  18. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1993-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  19. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    1990-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1989 (April 1, 1989 - March 31, 1990). One of major Department's programs is the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Development of a high energy proton linear accelerator for the nuclear engineering including is also TRU incineration promoted. Other major tasks of the Department are various basic researches on nuclear data and group constants, theoretical methods and code development, on reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  20. Algoritmos evolucionários na determinação da configuração de custo mínimo de sistemas de co-geração de energia com base no gás natural

    Directory of Open Access Journals (Sweden)

    Marco César Goldbarg

    2005-08-01

    Full Text Available Esse trabalho apresenta um caso especial do problema geral da determinação de uma configuração para um sistema de co-geração de energia que utiliza o gás natural como fonte energética. O problema visa determinar a configuração de custo mínimo de um sistema de co-geração. É um problema computacionalmente difícil devido a restrições técnicas, operacionais e econômicas. Para solucioná-lo, são apresentados e comparados algoritmos evolucionários desenvolvidos de acordo com as metáforas dos Algoritmos Genéticos, Algoritmos Meméticos e da Transgenética Computacional. Os algoritmos são aplicados a um conjunto de trinta e cinco instâncias geradas de acordo com cinco diferentes ciclos de co-geração. Os experimentos computacionais relatados nesse trabalho indicam uma dominância de melhores resultados da metáfora transgenética.This work presents a special case of the general problem of determining the configuration of cogeneration systems in which the primary source of energy is natural gas. The objective is to determine the configuration with the minimum cost. Technical, operational and economic features impose constraints to the problem making it computationally hard to solve. Evolutionary algorithms based upon genetic, memetic and transgenetic algorithms are presented to solve the problem. A computational experiment with thirty-five instances generated in accordance with five distinct cogeneration cycles is reported. The results show that the transgenetic algorithm exhibits an overall best performance.