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Sample records for bwr usando algoritmos

  1. Radial optimization of a BWR fuel cell using genetic algorithms; Optimizacion radial de una celda de combustible BWR usando algoritmos geneticos

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    Martin del Campo M, C.; Carmona H, R.; Oropeza C, I.P. [UNAM, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)]. e-mail: cmcm@fi-b.unam.mx

    2006-07-01

    The development of the application of the Genetic Algorithms (GA) to the optimization of the radial distribution of enrichment in a cell of fuel of a BWR (Boiling Water Reactor) is presented. The optimization process it was ties to the HELIOS simulator, which is a transport code of neutron simulation of fuel cells that has been validated for the calculation of nuclear banks for BWRs. With heterogeneous radial designs can improve the radial distribution of the power, for what the radial design of fuel has a strong influence in the global design of fuel recharges. The optimum radial distribution of fuel bars is looked for with different enrichments of U{sup 235} and contents of consumable poison. For it is necessary to define the representation of the solution, the objective function and the implementation of the specific optimization process to the solution of the problem. The optimization process it was coded in 'C' language, it was automated the creation of the entrances to the simulator, the execution of the simulator and the extraction, in the exit of the simulator, of the parameters that intervene in the objective function. The objective function includes four parameters: average enrichment of the cell, average gadolinia concentration of the cell, peak factor of radial power and k-infinite multiplication factor. To be able to calculate the parameters that intervene in the objective function, the one evaluation process of GA was ties to the HELIOS code executed in a Compaq Alpha workstation. It was applied to the design of a fuel cell of 10 x 10 that it can be employee in the fuel assemble designs that are used at the moment in the Laguna Verde Nucleo electric Central. Its were considered 10 different fuel compositions which four contain gadolinia. Three heuristic rules that consist in prohibiting the placement of bars with gadolinia in the ends of the cell, to place the compositions with the smallest enrichment in the corners of the cell and to fix

  2. A methodology for obtaining the control rod patterns in a BWR using genetic algorithms; Una metodologia para obtener los patrones de barras de control en un BWR usando algoritmos geneticos

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    Ortiz S, J.J.; Montes T, J.L. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico); Requena R, I. [Universidad de Granada, 18071 Granada (Spain)]. e-mail: jjortiz@nuclear.inin.mx

    2003-07-01

    In this work the GACRP system based on the genetic algorithms technique for the obtaining of the drivers of control bars in a BWR reactor is presented. This methodology was applied to a transition cycle and a one of balance of the Laguna Verde nuclear power station (CNLV). For each one of the studied cycles, it was executed the methodology with a fixed length of the cycle and it was compared the effective multiplication factor of neutrons at the end of the cycle that it is obtained with the proposed drivers of control bars and the multiplication factor of neutrons obtained by means of a Haling calculation. It was found that it is possible to extend several days the length of both cycles with regard to the one Haling calculation. (Author)

  3. 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.

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

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    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.

  5. Curvas de Bezier em grupos de Lie e esferas S2 usando o algoritmo de De Casteljau

    OpenAIRE

    Tiago da Silva Alencar

    2010-01-01

    Neste trabalho estudaremos uma generalizaÃÃo do algoritmo de De Casteljau, que à um procedimento recursivo para construÃÃo de curvas de Bezier em espaÃos euclidianos, para grupos de Lie e esferas S2, com Ãnfase nas curvas de Bezier de grau 3. In this paper we study a generalization of the De Casteljau algorithm, which is a recursive procedure for constructing Bezier curves in euclidean space, for Lie groups and spheres S2, with emphasis on Bezier curves of degree 3.

  6. Alineamiento de múltiples secuencias de aminoácidos usando algoritmos genéticos

    OpenAIRE

    Solanilla, Luis Felipe

    2006-01-01

    El presente artículo describe un algoritmo genético y su implementación, que permite el alineamiento de múltiples secuencias de aminoácidos mediante reacomodaciones que simulan la inserción de gaps (huecos) y acciones de recombinación para obtener puntajes más altos en el alineamiento. Tales puntajes se obtienen mediante el método de la suma de pares, en el cual se consideran todas las posibles combinaciones de aminoácidos en cada columna del alineamiento y se califican basándose en las puntu...

  7. Optimization of fuel reloads for a BWR using the ant colony system; Optimizacion de recargas de combustible para un BWR usando el sistema de colonia de hormigas

    Energy Technology Data Exchange (ETDEWEB)

    Esquivel E, J. [Universidad Autonoma del Estado de Mexico, Facultad de Ingenieria, Cerro de Coatepec s/n, Ciudad Universitaria, 50110 Toluca, Estado de Mexico (Mexico); Ortiz S, J. J. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: jaime.es.jaime@gmail.com

    2009-10-15

    In this work some results obtained during the development of optimization systems are presented, which are employees for the fuel reload design in a BWR. The systems use the ant colony optimization technique. As first instance, a system is developed that was adapted at travel salesman problem applied for the 32 state capitals of Mexican Republic. The purpose of this implementation is that a similarity exists with the design of fuel reload, since the two problems are of combinatorial optimization with decision variables that have similarity between both. The system was coupled to simulator SIMULATE-3, obtaining good results when being applied to an operation cycle in equilibrium for reactors of nuclear power plant of Laguna Verde. (Author)

  8. Obtention control bars patterns for a BWR using Tabo search; Obtencion de patrones de barras de control para un BWR usando busqueda Tabu

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    Castillo, A.; Ortiz, J.J.; Alonso, G. [Instituto Nacional de Investigaciones Nucleares, Km. 36.5 Carretera Mexico-Toluca, Ocoyoacac, Estado de Mexico 52045 (Mexico); Morales, L.B. [UNAM, IIMAS, Ciudad Universitaria, D. F. 04510 (Mexico); Valle, E. del [IPN, ESFM, Unidad Profesional ' Adolfo Lopez Mateos' , Col. Lindavista 07738, D. F. (Mexico)]. e-mail: jacm@nuclear.inin.mx

    2004-07-01

    The obtained results when implementing the technique of tabu search, for to optimize patterns of control bars in a BWR type reactor, using the CM-PRESTO code are presented. The patterns of control bars were obtained for the designs of fuel reloads obtained in a previous work, using the same technique. The obtained results correspond to a cycle of 18 months using 112 fresh fuels enriched at the 3.53 of U-235. The used technique of tabu search, prohibits recently visited movements, in the position that correspond to the axial positions of the control bars, additionally the tiempo{sub t}abu matrix is used for to manage a size of variable tabu list and the objective function is punished with the frequency of the forbidden movements. The obtained patterns of control bars improve the longitude of the cycle with regard to the reference values and they complete the restrictions of safety. (Author)

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

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    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. 

  10. 3D simulation of a core operation cycle of a BWR using Serpent; Simulacion 3D de un ciclo de operacion del nucleo de un BWR usando SERPENT

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    Barrera Ch, M. A.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Col. Lindavista, 07738 Ciudad de Mexico (Mexico); Gomez T, A. M., E-mail: rionchez@icloud.com [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    This work had the main goal to develop a methodology to obtain the length of an operating cycle of the core of a BWR under different operating states using the Serpent code. The reactor core modeled in Serpent is composed of 444 fuel assemblies (120 with fresh fuels and 324 fuels from previous cycles), 109 cruciform control rods and light water as moderator and coolant. Once the core of the reactor was modeled in Serpent (Three-dimensional) without considering the cruciform control rods, a simulation was carried out with different steps of burning in the operational state with the average values of the fuel temperature (900 K), moderator temperature (600 K) and voids fraction equal to 0.4. In addition, the thermal power considered was 2017 MWt. This operational state was chosen because a previous analysis (not shown in this work) was carried out in 4 types of control cells. The first and second control cell has all of its natural uranium fuel pellets, with control rod and without control rod respectively. The third and fourth control cell types have various types of enrichment, both natural uranium and gadolinium in their fuel pellets, with control rod and without control rod. The conclusion of this previous analysis was that the behavior of the effective multiplication factor along the fuel burnout within the four control cell types was almost unaffected by the fuel temperature but was affected by the voids fraction. Thus, for this operating cycle in the operating state defined above, its length was 14,63052 GW t/Tm. In addition, at the end of this cycle, the decay heat obtained was equal to 116.71 MWt and the inventory of the most important isotopes to be considered was obtained, such as some isotopes of uranium, neptune, plutonium, americium and curio. (Author)

  11. Cálculo dimensional óptimo de una plata forma paralela tipo Stewart –Gough para aplicaciones pedagógicas usando algoritmos genéticos

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    César Augusto Peña

    2011-01-01

    Full Text Available En este artículo se propone el diseño óptimo de una plataforma paralela tipo Stewart-Gough que cubre un espacio de trabajo esférico. El cálculo de las dimensiones del robot se realizó por medio de técnicas de algoritmos genéticos. Ilustra los cálculos de cinemática inversa y del espacio de trabajo. Esta plataforma esta diseñada para aplicaciones pedagógicas en las áreas de teleoperación, control, visión y automatización usando robótica paralela. La plataforma experimental puede ser operada remotamente por usuarios de diversas universidades utilizando un lenguaje de programación bastante intuitivo y común.

  12. Cálculo dimensional óptimo de una plata forma paralela tipo Stewart –Gough para aplicaciones pedagógicas usando algoritmos genéticos

    OpenAIRE

    César Augusto Peña; Eugenio Yime Rodríguez; Ilka Banfield

    2011-01-01

    En este artículo se propone el diseño óptimo de una plataforma paralela tipo Stewart-Gough que cubre un espacio de trabajo esférico. El cálculo de las dimensiones del robot se realizó por medio de técnicas de algoritmos genéticos. Ilustra los cálculos de cinemática inversa y del espacio de trabajo. Esta plataforma esta diseñada para aplicaciones pedagógicas en las áreas de teleoperación, control, visión y automatización usando robótica paralela. La plataforma experimental puede ser operada re...

  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

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    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. Cálculo de equivalentes dinâmicos de sistema de potência usando algoritmos genéticos

    OpenAIRE

    2014-01-01

    Esta dissertação apresenta um método baseado em algoritmos genéticos para cálculo de equivalentes dinâmicos de sistemas de potência visando representar partes de um sistema para estudos de análise de estabilidade transitória. O modelo do equivalente dinâmico é obtido por meio da identificação de parâmetros de geradores síncronos, localizados nas barras de fronteira entre o sistema externo e o subsistema em estudo. Um indicie é usado para avaliar a proximidade entre as simulaçõe...

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

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    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

  16. Planeación de sistemas secundarios de distribución usando el algoritmo Branch and Bound Secondary distribution system planning using branch and bound

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    Ricardo Alberto Hincapie-Isaza

    2011-06-01

    Full Text Available En este trabajo se plantea una metodología para la solución del problema delplaneamiento de sistemas secundarios de distribución considerando un modelode programación lineal entero mixto (PLEM, el cual considera la ubicación y dimensionamiento de transformadores de distribución, el dimensionamientoy rutas de circuitos secundarios y sus costos variables. Para la solución delproblema se emplea el algoritmo Branch and Bound. Los resultados obtenidosen un sistema de prueba empleado en la literatura especializada muestran lavalidez y efectividad de la metodología propuesta.This paper presents a methodology for solving secondary distribution systems planning problem as a mixed integer linear programming problem (MILP. The algorithm takes into account several design issues such as the capacity and location of distribution transformers and secondary feeders. Variable costs of secondary feeders are also considered. The problem is solved using branch and bound algorithm. Numerical results show that the mathematical model and the solution technique are effective for this kind of problems.

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

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    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.

  18. Otimização de métodos de controle de qualidade de fármacos usando algoritmo genético e busca tabu

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    Konzen Pedro Henrique de Almeida

    2003-01-01

    Full Text Available Neste trabalho novas metodologias de análise para a quantificação de princípios ativos em fármacos são estudadas, empregando técnicas de otimização meta-heurísticas em modelos de regressão multivariada e dados de espectroscopia por reflexão difusa no infravermelho com transformada de Fourier (DRIFTS. Inicialmente foram preparadas amostras do princípio ativo hidroclorotiazida, a partir de um planejamento experimental. Os espectros foram coletados empregando um espectrofotômetro, sendo aplicada a correção multiplicativa de sinal (MSC. Foram construídos modelos de calibração por mínimos quadrados parciais (PLS, sendo implementados métodos de otimização dos Algoritmos Genético (AG e Busca Tabu (BT, objetivando minimizar o erro das amostras de validação (SEV. Os melhores modelos foram selecionados com base no coeficiente de regressão (R² e comparados. Ambas as técnicas de otimização resultaram em modelos de calibração com excelente capacidade de quantificação do princípio ativo, sendo adequadas para a utilização no controle de qualidade do processo produtivo.

  19. Simulation in 3 dimensions of a cycle 18 months for an BWR type reactor using the Nod3D program; Simulacion en 3 dimensiones de un ciclo de 18 meses para un reactor BWR usando el programa Nod3D

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez, N.; Alonso, G. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)]. E-mail: nhm@nuclear.inin.mx; Valle, E. del [IPN, ESFM, 07738 Mexico D.F. (Mexico)

    2004-07-01

    The development of own codes that you/they allow the simulation in 3 dimensions of the nucleus of a reactor and be of easy maintenance, without the consequent payment of expensive use licenses, it can be a factor that propitiates the technological independence. In the Department of Nuclear Engineering (DIN) of the Superior School of Physics and Mathematics (ESFM) of the National Polytechnic Institute (IPN) a denominated program Nod3D has been developed with the one that one can simulate the operation of a reactor BWR in 3 dimensions calculating the effective multiplication factor (kJJ3, as well as the distribution of the flow neutronic and of the axial and radial profiles of the power, inside a means of well-known characteristics solving the equations of diffusion of neutrons numerically in stationary state and geometry XYZ using the mathematical nodal method RTN0 (Raviart-Thomas-Nedelec of index zero). One of the limitations of the program Nod3D is that it doesn't allow to consider the burnt of the fuel in an independent way considering feedback, this makes it in an implicit way considering the effective sections in each step of burnt and these sections are obtained of the code Core Master LEND. However even given this limitation, the results obtained in the simulation of a cycle of typical operation of a reactor of the type BWR are similar to those reported by the code Core Master LENDS. The results of the keJ - that were obtained with the program Nod3D they were compared with the results of the code Core Master LEND, presenting a difference smaller than 0.2% (200 pcm), and in the case of the axial profile of power, the maxim differs it was of 2.5%. (Author)

  20. Optimización Termoeconómica y Ambiental usando Algoritmos Genéticos Multiobjetivo Thermoeconomic and Environment Optimization using Multiobjective Genetic Algorithms

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    Marlon J Bastidas

    2010-01-01

    Full Text Available En este trabajo, se presenta un análisis multiobjetivo incluyendo variables del entorno de un sistema energético el cual es condicionado por el uso de combustibles sólidos, razón por la cual en el análisis se incluye la características externas del recurso (combustible, del residuo (cenizas y del producto (electricidad/vapor. El sistema energético utilizado es Termocesar, un proceso colombiano de generación eléctrica que usa del carbón. Se analiza tres funciones denominadas función objetivo termoeconómica, función objetivo tecnológica y función objetivo ambiental, con el fin de determinar la mejor ubicación del sistema. Se usa el método de los algoritmos genéticos para la optimización del sistema. Los resultados fueron analizados para nueve combinaciones de pesos y muestran que para la mayoría de los casos el óptimo incluye carbones procedentes de la región del departamento del Cesar en Colombia.This paper presents a multiobjective analysis including variables of the environment of the energy system which is conditioned by the use of solid fuels, for this reason the analysis includes the external characteristics of the resource (fuel of residue (ash and the product (electricity/steam. The energy system used is Termocesar, a Colombian process for generating electricity from carbon. Three functions named thermoeconomic objective function, technology objective function and environmental objective function, are analyzed to establish the best location of the energy The genetic algorithm method is used for the optimization of the system. The results were analyzed for nine combinations of weights and show that for most of the cases the optimum includes coals from the Department of Cesar in Colombia.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-15

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

  2. Solution of the transport equation in stationary state, in one and two dimensions, for BWR assemblies using nodal methods; Solucion de la ecuacion de transporte en estado estacionario, en 1 y 2 dimensiones, para ensambles tipo BWR usando metodos nodales

    Energy Technology Data Exchange (ETDEWEB)

    Xolocostli M, J.V

    2002-07-01

    The main objective of this work is to solve the neutron transport equation in one and two dimensions (slab geometry and X Y geometry, respectively), with no time dependence, for BWR assemblies using nodal methods. In slab geometry, the nodal methods here used are the polynomial continuous (CMPk) and discontinuous (DMPk) families but only the Linear Continuous (also known as Diamond Difference), the Quadratic Continuous (QC), the Cubic Continuous (CC), the Step Discontinuous (also known as Backward Euler), the Linear Discontinuous (LD) and the Quadratic Discontinuous (QD) were considered. In all these schemes the unknown function, the angular neutron flux, is approximated as a sum of basis functions in terms of Legendre polynomials, associated to the values of the neutron flux in the edges (left, right, or both) and the Legendre moments in the cell, depending on the nodal scheme used. All these schemes were implemented in a computer program developed in previous thesis works and known with the name TNX. This program was modified for the purposes of this work. The program discreetizes the domain of concern in one dimension and determines numerically the angular neutron flux for each point of the discretization when the number of energy groups and regions are known starting from an initial approximation for the angular neutron flux being consistent with the boundary condition imposed for a given problem. Although only problems with two-energy groups were studied the computer program does not have limitations regarding the number of energy groups and the number of regions. The two problems analyzed with the program TNX have practically the same characteristics (fuel and water), with the difference that one of them has a control rod. In the part corresponding to two-dimensional problems, the implemented nodal methods were those designated as hybrids that consider not only the edge and cell Legendre moments, but also the values of the neutron flux in the corner points

  3. Solution of the transport equation in stationary state, in one and two dimensions, for BWR assemblies using nodal methods; Solucion de la ecuacion de transporte en estado estacionario, en 1 y 2 dimensiones, para ensambles tipo BWR usando metodos nodales

    Energy Technology Data Exchange (ETDEWEB)

    Xolocostli M, J.V

    2002-07-01

    The main objective of this work is to solve the neutron transport equation in one and two dimensions (slab geometry and X Y geometry, respectively), with no time dependence, for BWR assemblies using nodal methods. In slab geometry, the nodal methods here used are the polynomial continuous (CMPk) and discontinuous (DMPk) families but only the Linear Continuous (also known as Diamond Difference), the Quadratic Continuous (QC), the Cubic Continuous (CC), the Step Discontinuous (also known as Backward Euler), the Linear Discontinuous (LD) and the Quadratic Discontinuous (QD) were considered. In all these schemes the unknown function, the angular neutron flux, is approximated as a sum of basis functions in terms of Legendre polynomials, associated to the values of the neutron flux in the edges (left, right, or both) and the Legendre moments in the cell, depending on the nodal scheme used. All these schemes were implemented in a computer program developed in previous thesis works and known with the name TNX. This program was modified for the purposes of this work. The program discreetizes the domain of concern in one dimension and determines numerically the angular neutron flux for each point of the discretization when the number of energy groups and regions are known starting from an initial approximation for the angular neutron flux being consistent with the boundary condition imposed for a given problem. Although only problems with two-energy groups were studied the computer program does not have limitations regarding the number of energy groups and the number of regions. The two problems analyzed with the program TNX have practically the same characteristics (fuel and water), with the difference that one of them has a control rod. In the part corresponding to two-dimensional problems, the implemented nodal methods were those designated as hybrids that consider not only the edge and cell Legendre moments, but also the values of the neutron flux in the corner points

  4. Algoritmo eficiente en la generación de una tabla de primalidad de números usando Programación Funcional [An application of a simple and efficient algorithm to generate a prime number table using Functional Programming

    OpenAIRE

    TREJOS BURITICÁ, Omar Iván; Universidad Tecnológica de Pereira

    2014-01-01

    Resumen En el presente artículo se acude a la Programación Funcional para generar una tabla de análisis de primalidad de números en un rango dado a partir del uso de un algoritmo que, por las necesidades del mismo objetivo, tiene características de ser eficiente. Se plantea la fundamentación de dicho algoritmo y además se aprovecha su estructura lógica para resolver el problema propuesto. El propósito de este artículo es mostrar una arista útil de la eficiencia algorítmica teniendo en cuenta ...

  5. Percepção de fala dos deficientes auditivos usando aparelho de amplificação com algoritmo de redução de ruído

    OpenAIRE

    OLIVEIRA, Jerusa Roberta Massola de; Lopes, Eymar Sampaio; Alves, Alceu Ferreira [UNESP

    2010-01-01

    Frequentemente, os indivíduos com perda auditiva têm dificuldade de entender a fala no ambiente ruidoso. OBJETIVO: O objetivo deste estudo foi avaliar clinicamente o desempenho dos indivíduos adultos com deficiência auditiva neurossensorial, com relação à percepção da fala, utilizando o aparelho de amplificação sonora individual digital com o algoritmo de redução de ruído denominado Speech Sensitive Processing, ativado e desativado na presença de um ruído. MATERIAL E MÉTODO: Este estudo de ca...

  6. Un algoritmo para el registro del tiempo de atoro en máquinas cosechadoras de caña

    Directory of Open Access Journals (Sweden)

    Juan Carlos Sepúlveda Peña

    2009-01-01

    Full Text Available El algoritmo descrito fue desarrollado para detectar el atoro en máquinas cosechadoras de caña usando los datos primarios captados por el "computador de a bordo" AGM-200A o el AGM-200B. El algoritmo igualmente pudiera ser aplicado a problemas similares que afrontan otros tipos de cosechadoras agrícolas.

  7. Class Schedule Assignment Based on Students Learning Rhythms Using A Genetic Algorithm Asignación de horarios de clase basado en los ritmos de aprendizaje de los estudiantes usando un algoritmo genético

    Directory of Open Access Journals (Sweden)

    Victor F. Suarez Chilma

    2013-03-01

    Full Text Available The objective of this proposal is to implement a school day agenda focused on the learning rhythms of students of elementary and secondary schools using a genetic algorithm. The methodology of this proposal takes into account legal requirements and constraints on the assignment of teachers and classrooms in public educational institutions in Colombia. In addition, this proposal provides a set of constraints focused on cognitive rhythms and subjects are scheduled at the most convenient times according to the area of knowledge. The genetic algorithm evolves through a process of mutation and selection and builds a total solution based on the best solutions for each group. Sixteen groups in a school are tested and the results of class schedule assignments are presented. The quality of the solution obtained through the established approach is validated by comparing the results to the solutions obtained using another algorithm.El objetivo de esta propuesta es implementar un horario escolar que tenga en cuenta los ritmos de aprendizaje en los estudiantes de educación primaria y secundaria, utilizando un algoritmo genético. La metodología considera los requerimientos legales y las restricciones necesarias para la asignación de maestros y aulas en instituciones educativas públicas de Colombia. Adicionalmente, se establecen un conjunto de restricciones relacionadas con el enfoque en los ritmos cognitivos, determinando las horas de la jornada en las que es más conveniente la ubicación de ciertas materias de acuerdo al área del conocimiento al que pertenecen. El algoritmo genético evoluciona mediante un proceso de mutación y selección, a través del cual se construye una solución completa a partir de la búsqueda de las mejores soluciones por grupo. Se presentan los resultados de las pruebas realizadas para la asignación de una institución con 16 grupos. La calidad de las soluciones obtenidas de acuerdo al enfoque establecido es validada

  8. Solution of a benchmark set problems for BWR and PWR reactors with UO{sub 2} and MOX fuels using CASMO-4; Solucion de un Conjunto de Problemas Benchmark para Reactores BWR y PWR con Combustible UO{sub 2} y MOX Usando CASMO-4

    Energy Technology Data Exchange (ETDEWEB)

    Martinez F, M.A.; Valle G, E. del; Alonso V, G. [IPN, ESFM, 07738 Mexico D.F. (Mexico)]. e-mail: mike_ipn_esfm@hotmail. com

    2007-07-01

    In this work some of the results for a group of benchmark problems of light water reactors that allow to study the physics of the fuels of these reactors are presented. These benchmark problems were proposed by Akio Yamamoto and collaborators in 2002 and they include two fuel types; uranium dioxide (UO{sub 2}) and mixed oxides (MOX). The range of problems that its cover embraces three different configurations: unitary cell for a fuel bar, fuel assemble of PWR and fuel assemble of BWR what allows to carry out an understanding analysis of the problems related with the fuel performance of new generation in light water reactors with high burnt. Also these benchmark problems help to understand the fuel administration in core of a BWR like of a PWR. The calculations were carried out with CMS (of their initials in English Core Management Software), particularly with CASMO-4 that is a code designed to carry out analysis of fuels burnt of fuel bars cells as well as fuel assemblies as much for PWR as for BWR and that it is part in turn of the CMS code. (Author)

  9. Algoritmos de antialiasing

    Directory of Open Access Journals (Sweden)

    Gabriel Mañana Guichón

    2011-01-01

    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.

  10. FEEDER RECONFIGURATION AND CAPACITOR PLACEMENT IN DISTRIBUTION SYSTEMS: AN APPROACH FOR SIMULTANEOUS SOLUTION USING A GENETIC ALGORITHM RECONFIGURACIÓN Y UBICACIÓN DE CONDENSADORES EN SISTEMAS DE DISTRIBUCIÓN: METODOLOGÍA DE SOLUCIÓN SIMULTÁNEA USANDO ALGORITMOS GENÉTICOS

    Directory of Open Access Journals (Sweden)

    Horacio Díaz R

    2010-04-01

    Full Text Available This paper presents an effective approach to simultaneous solution of capacitor placement and feeder reconfiguration for power-energy loss cost minimization and voltage profile enhancement in radial distribution systems. Considering a time variation load, an optimization method using a genetic algorithm is proposed to determine the optimal location and size of fixed and switchable capacitors, as well as the open/closed states of the sectionalizing and tie switches. Reduction of overall power and energy losses and capacitor costs are involved in problem formulation. The proposed approach is demonstrated using example systems from the literature and results show that taken into account both capacitor placement and feeder reconfiguration simultaneously can generate around 10% more energy and peak loss reduction than considering them separately. Simulations results are presented for a 16 bus IEEE system and for a 733 bus practical distribution network.Este trabajo presenta una metodología para la solución simultánea de los problemas de ubicación de condensadores y reconfiguración de alimentadores en sistemas eléctricos de distribución radiales, con el fin de mejorar el perfil de voltaje de la red y, al mismo tiempo, reducir los costos asociados a las pérdidas de energía y potencia. Considerando un perfil de carga dado, se propone un método de optimización usando un algoritmo genético para determinar el tamaño óptimo, ubicación, tipo y número de condensadores fijos o conmutables, así como los estados abierto/cerrado de las llaves (switches seccionadoras y de interconexión. La formulación del problema considera la minimización de los costos totales, incluyendo costos fijos y variables de los bancos de condensadores. El método propuesto se ha probado en diversas redes y los resultados muestran que considerando ambos problemas simultáneamente los costos debidos a las pérdidas se pueden minimizar hasta un 10% más que tomando

  11. CFD analysis for the hydrogen transport in the primary contention of a BWR using the codes OpenFOAM and Gas-Flow; Analisis CFD para el transporte de hidrogeno en la contencion primaria de un reactor BWR usando los codigos OpenFOAM y GasFlow

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez P, D. A.

    2014-07-01

    using a limited number of semi-empirical data, and instead, mathematical relationships are used taking into account the various physical phenomena as well the interactions that occur among them, such as heat transfer between the fluid and the solid walls condensation of water vapor on the walls, the turbulent effects in areas of restricted passage, etc. Taking into account these advantages, this study presents a qualitative and quantitative comparison between the CFD codes OpenFOAM and Gas-Flow related to the transport phenomena of Hydrogen and other gases in the primary containment of a BWR reactor. Gas-Flow is a code of commercial license that is well validated, developed in Germany to analyze the transport of gases in nuclear reactor containments. On the other hand, OpenFOAM is an open source CFD code offering several solvers for different phenomena assessments, in this work, the reacting Foam solver is used because it has a strong similarity to the intended application of Hydrogen transport. In this thesis the results obtained using the reacting Foam solver of OpenFOAM for the calculation of transport of Hydrogen are compared with the results of the Gas-Flow code in order to assess if it is feasible to use the open source code OpenFOAM in the case of Hydrogen transport in primary containment of a BWR reactor. Some differences in the qualitative and quantitative results from both codes were found, the differences (with a maximum error rate of 4%) in the quantitative results were found are small and are considered more than acceptable for this type of analysis, moreover, these differences are mainly attributed to the transport models used, mainly because OpenFOAM uses a homogeneous mixture model and Gas-Flow a heterogeneous one. Implementing appropriate solvers in codes like OpenFOAM has the goal to develop own tools that are applicable to the transport of Hydrogen in the primary containment of a BWR reactor and thus, to gain some independence while not relying on

  12. INTELIGÊNCIA ARTIFICIAL COM ENFOQUE EM ALGORITMOS GENÉTICOS

    Directory of Open Access Journals (Sweden)

    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.

  13. INTELIGÊNCIA ARTIFICIAL COM ENFOQUE EM ALGORITMOS GENÉTICOS

    OpenAIRE

    2010-01-01

    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.

  14. Implementación de algoritmo de scan-matching basado en PSO

    OpenAIRE

    Gallo Merino, Carlos Alberto

    2015-01-01

    Uno de los campos en los que se está centrando la robótica los últimos años es el desarrollo de nuevos algoritmos que permitan localizar el robot en un entorno con el objetivo de mejorar su autonomía. Este problema ha llevado al desarrollo de algoritmos de SLAM (Simultaneous Localization and Mapping) que buscan localizar al robot mientras se construye un mapa de su entorno y a la vez se explora el mismo usando este mapa. Un aspecto relativo a esta tarea en particular es el problema de scan...

  15. Diseño de criptoprocesadores de curva elíptica sobre gf(2^163) usando bases normales gaussianas

    OpenAIRE

    Realpe, Paulo Cesar; Trujillo-Olaya, Vladimir; Velasco-Medina, Jaime

    2014-01-01

    En este trabajo se presenta la implementación eficiente en hardware de criptoprocesadores que permiten llevar a cabo la multiplicación escalar kP sobre el campo finito GF(2163) usando dos multiplicadores a nivel de digito. Las operaciones aritméticas de campo finito fueron implementadas usando la representación de bases normales Gaussianas (GNB), y la multiplicación escalar kP fue implementada usando el algoritmo de López-Dahab, el algoritmo de bisección de punto 2-NAF y el método w-tNAF para...

  16. BWR AXIAL PROFILE

    Energy Technology Data Exchange (ETDEWEB)

    J. Huffer

    2004-09-28

    The purpose of this calculation is to develop axial profiles for estimating the axial variation in burnup of a boiling water reactor (BWR) assembly spent nuclear fuel (SNF) given the average burnup of an assembly. A discharged fuel assembly typically exhibits higher burnup in the center and lower burnup at the ends of the assembly. Criticality safety analyses taking credit for SNF burnup must account for axially varying burnup relative to calculations based on uniformly distributed assembly average burnup due to the under-burned tips. Thus, accounting for axially varying burnup in criticality analyses is also referred to as accounting for the ''end effect'' reactivity. The magnitude of the reactivity change due to ''end effect'' is dependent on the initial assembly enrichment, the assembly average burnup, and the particular axial profile characterizing the burnup distribution. The set of bounding axial profiles should incorporate multiple BWR core designs and provide statistical confidence (95 percent confidence that 95 percent of the population is bound by the profile) that end nodes are conservatively represented. The profiles should also conserve the overall burnup of the fuel assembly. More background on BWR axial profiles is provided in Attachment I.

  17. 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.

  18. Algoritmos de enjambre de partículas para agrupamiento y clasificación de patrones

    OpenAIRE

    García Martínez, Edgar Alfonso

    2016-01-01

    En esta tesis se abordan diferentes variantes de algoritmos de enjambre de partículas (PSO) adaptados para resolver problemas de agrupamiento de patrones; se proponen dos nuevas variantes de PSO, la primera incorpora una etapa de búsqueda local usando un algoritmo en escalada y la segunda utiliza un µPSO para encontrar el número óptimo de grupos en un conjunto de datos. Se presenta una plataforma que lleva por nombre Heuristic Pattern Recognition Studio cuyo objetivo es asistir a los inve...

  19. Percepção de fala dos deficientes auditivos usando aparelho de amplificação com algoritmo de redução de ruído Speech perception of hearing impaired people using a hearing aid with noise supression algorithms

    Directory of Open Access Journals (Sweden)

    Jerusa Roberta Massola de Oliveira

    2010-02-01

    Full Text Available Frequentemente, os indivíduos com perda auditiva têm dificuldade de entender a fala no ambiente ruidoso. OBJETIVO: O objetivo deste estudo foi avaliar clinicamente o desempenho dos indivíduos adultos com deficiência auditiva neurossensorial, com relação à percepção da fala, utilizando o aparelho de amplificação sonora individual digital com o algoritmo de redução de ruído denominado Speech Sensitive Processing, ativado e desativado na presença de um ruído. MATERIAL E MÉTODO: Este estudo de casos foi realizado em 32 indivíduos com deficiência auditiva neurossensorial de graus leve, moderado ou leve a moderado. Foi realizada a avaliação por meio de um teste de percepção de fala, onde se pesquisou o reconhecimento de sentenças na presença de um ruído, para obter a relação sinal/ruído, utilizando o aparelho auditivo digital. RESULTADOS: O algoritmo pôde proporcionar benefício para a maioria dos indivíduos deficientes auditivos, na pesquisa da relação sinal/ruído e os resultados apontaram diferença estatisticamente significante na condição em que o algoritmo encontrava-se ativado, comparado quando o algoritmo não se encontrava ativado. CONCLUSÃO: O uso do algoritmo de redução de ruído deve ser pensado como alternativa clínica, pois observamos a eficácia desse sistema na redução do ruído, melhorando a percepção da fala.Often, individuals with hearing loss have difficulties understanding speech in noisy environments. AIM: It was the aim of this study to assess the performance of adult individuals with sensorineural hearing loss, associated with speech perception using digital hearing aids with a sound reduction algorithm called Speech Sensitive Processing, on and off, in the presence of noise. MATERIALS AND METHODS: This case study was performed with 32 individuals with sensorineural hearing loss of mild, moderate or mild to moderate level. Our evaluation involved a speech perception test, where we

  20. Programación de Horarios Escolares basados en Ritmos Cognitivos usando un Algoritmo Genético de Clasificación No-dominada, NSGA-II Scheduling of School Hours based on Cognitive Rhythms using a Non-dominated Sorting Genetic Algorithm, NSGA-II

    Directory of Open Access Journals (Sweden)

    Víctor F Suárez

    2013-01-01

    Full Text Available Se plantea la solución del problema de programación óptima de horarios escolares de una escuela pública Colombiana. Esto se hace considerando no solo la asignación adecuada de salones y docentes sino también los ritmos cognitivos que presentan los estudiantes como el factor más importante en el proceso de optimización. Se propone como método de solución el Algoritmo Genético de Clasificación No-dominada, NSGA-II. Los resultados muestran una mayor eficiencia del algoritmo en comparación con otros aplicados al mismo problema y evaluados en la misma forma. A nivel experimental, la metodología evidencia que los grupos programados mediante la orientación descrita presentan una reducción en los niveles de mortalidad académica en comparación con una programación horaria que no consideran los ritmos cognitivos de los estudiantesAbstract This paper proposes the implementation of an optimum academic agenda to solve the problem of scheduling a school day in Colombia. This is done by taking into account not only the appropriate assignment of rooms and professors but considering the cognitive rhythms of the students as the most relevant factor in the optimization. The Non-dominated Sorting Genetic Algorithm, NSGA-II is proposed as a solution method. The results show a higher efficiency of the algorithm when compared to other algorithms applied to the same problem and evaluated in the same form. At the experimental level the methodology shows a reduction in academic mortality rates in the groups where the methodology was implemented compared to groups that did not considered the cognitive rhythms of the students.

  1. Programación de Máquinas Paralelas no Relacionadas con Tiempos de Montaje dependientes de la Secuencia y Entrada Dinámica usando Algoritmos Genéticos Scheduling of Non-Related Parallel Machines with Sequence Dependent Setup Times and Dynamic Entry using Genetic Algorithms

    Directory of Open Access Journals (Sweden)

    Jaime A Arango

    2013-01-01

    Full Text Available Este trabajo describe una propuesta de solución al problema de procesar n trabajos en m máquinas paralelas no relacionadas. Es un problema de asignación generalizado de orden lineal y tipo combinatorial que considera tiempos de montaje dependientes de la secuencia y entrada dinámica de trabajos. Se propone un algoritmo genético con codificación entera y conformación de la población, selección de padres, cruzamiento y mutación aleatorios. Hay dos descendientes por generación que compiten contra el peor elemento existente para entrar a la población. Se itera un número de generaciones proporcional al producto de nxm para obtener la solución En cada máquina se secuencian los trabajos por fecha de entrega y los tiempos computacionales son aceptables. Se concluye que el problema pudo ser solucionado mediante el algoritmo genético propuesto de forma eficaz y eficiente y que las soluciones se enfocan en reducir el tiempo de procesamiento y cumplimiento de fechas de entrega.This paper describes a solution method to the problem of processing n jobs on m non-related parallel machines. It is a linear and combinatorial generalized allocation problem that considered a sequence-dependent setup time and dynamic job entry. A genetic algorithm with integer coding and random generation of population, parent selection, crossover and mutation is proposed. There are two descendants per generation that are compared against the worst existing element to enter to population. After a number of generations that is proportional to the product of nxm the solution is generated. The jobs are sequenced on each machine by due date and computational times are acceptable. It is concluded that the proposed genetic algorithm is an effective and efficient solution that focuses on reducing processing time and on meeting deadlines.

  2. High Fidelity BWR Fuel Simulations

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Su Jong [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-08-01

    This report describes the Consortium for Advanced Simulation of Light Water Reactors (CASL) work conducted for completion of the Thermal Hydraulics Methods (THM) Level 3 milestone THM.CFD.P13.03: High Fidelity BWR Fuel Simulation. High fidelity computational fluid dynamics (CFD) simulation for Boiling Water Reactor (BWR) was conducted to investigate the applicability and robustness performance of BWR closures. As a preliminary study, a CFD model with simplified Ferrule spacer grid geometry of NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) benchmark has been implemented. Performance of multiphase segregated solver with baseline boiling closures has been evaluated. Although the mean values of void fraction and exit quality of CFD result for BFBT case 4101-61 agreed with experimental data, the local void distribution was not predicted accurately. The mesh quality was one of the critical factors to obtain converged result. The stability and robustness of the simulation was mainly affected by the mesh quality, combination of BWR closure models. In addition, the CFD modeling of fully-detailed spacer grid geometry with mixing vane is necessary for improving the accuracy of CFD simulation.

  3. Análisis de algoritmos

    OpenAIRE

    Ruiz Lizama, Edgar; FII-UNMSM

    2014-01-01

    Presenta los fundamentos matemáticos para el análisis de algoritmos a fin de determinar su eficiencia, con el cuál se puede decidir por uno entre varios algoritmos en pugna Presents the mathematical foundations for analyzing algorithms to determine their efficiency, with which you can decide for one of several competing algorithms

  4. Algoritmos array para filtragem de sistemas lineares

    OpenAIRE

    Gildson Queiroz de Jesus

    2007-01-01

    Esta dissertação desenvolve filtro de informação, algoritmos array para estimador do erro médio mínimo quadrático para sistemas lineares sujeitos a saltos Markovianos e algoritmos array rápidos para filtragem de sistemas singulares convencionais. Exemplos numéricos serão apresentados para mostrarem as vantagens dos algoritmos array deduzidos. Parte dos resultados obtidos nesta pesquisa serão publicados no seguinte artigo: Terra et al. (2007). Terra, M. H., Ishihara, J. Y. and Jesus, G. Q. (20...

  5. DETECCION DE FALLAS CON EL ALGORITMO

    OpenAIRE

    Delgado Cascante, Geovanny

    2011-01-01

    En este artículo se presenta un método sistemático para la detección de fallas en sistemas digitales combinacionales: el algoritmo D. En la primera parte se estudian algunas definiciones sobre este algoritmo, esta sección se ha denominado Calculo D, a partir del cual se define la cobertura Singular, lo Cubos Primitivos de Falla y los Cubos de Propagación de Falla. Luego se presenta el algoritmo D constituido por el Conducto D y la Operación de Consistencia. Finalmente el trabajo se enriquece ...

  6. Optimal Phase Balancing Planning for Loss Reduction in Distribution Systems using a Specialized Genetic Algorithm Planeamiento Optimo de Balance de Fases para Reducción de Perdidas en Sistemas de Distribución usando un Algoritmo Genético Especializado

    Directory of Open Access Journals (Sweden)

    Mauricio Granada Echeverri

    2012-06-01

    propone una formulación no lineal entera mixta. Por otro lado, la técnica de solución propuesta consiste en un algoritmo genético especializado. Para mostrar la eficacia de la metodología propuesta varios ensayos son realizados con dos sistemas de distribución de 37 y 19 barras, este último con diferentes modelos de carga. Los resultados muestran que además de conseguir el objetivo principal de reducción de pérdidas, el balance de fases permite obtener otros beneficios técnicos como el mejoramiento del perfil de tensiones y reducción de la congestión en las líneas del sistema.

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

    Directory of Open Access Journals (Sweden)

    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.

  8. BWR Steam Dryer Alternating Stress Assessment Procedures

    Energy Technology Data Exchange (ETDEWEB)

    Morante, R. J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Hambric, S. A. [Brookhaven National Lab. (BNL), Upton, NY (United States); Ziada, S. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2016-12-01

    This report presents an overview of Boiling Water Reactor (BWR) steam dryer design; the fatigue cracking failures that occurred at the Quad Cities (QC) plants and their root causes; a history of BWR Extended Power Uprates (EPUs) in the USA; and a discussion of steam dryer modifications/replacements, alternating stress mechanisms on steam dryers, and structural integrity evaluations (static and alternating stress).

  9. Implementación de una memoria asociativa lineal usando el lenguaje r

    OpenAIRE

    2011-01-01

    Como un aspecto fundamental en muchos cursos de redes neuronales artificiales, el desarrollo de destrezas de programación es un objetivo fundamental. Este artículo tiene dos objetivos: el primero es presentar el lenguaje R para el cómputo estadístico como una poderosa herramienta para ejemplificar algoritmos, para ejecutar cálculos numéricos, y para ilustrar conceptos usando gráficos complejos. El segundo objetivo es ilustrar la implementación práctica de un modelo de redes neuronales en el l...

  10. 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 ...

  11. BWR Assembly Optimization for Minor Actinide Recycling

    Energy Technology Data Exchange (ETDEWEB)

    G. Ivan Maldonado; John M. Christenson; J.P. Renier; T.F. Marcille; J. Casal

    2010-03-22

    The Primary objective of the proposed project is to apply and extend the latest advancements in LWR fuel management optimization to the design of advanced boiling water reactor (BWR) fuel assemblies specifically for the recycling of minor actinides (MAs).

  12. 44 BWR Waste Package Loading Curve Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    J.M. Scaglione

    2001-11-05

    The objective of this calculation is to evaluate the required minimum burnup as a function of average initial boiling water reactor (BWR) assembly enrichment that would permit loading of fuel into a potential 44 BWR waste package (WP). The potential WP design is illustrated in Attachment I. The scope of this calculation covers a range of initial enrichments from 1.5 through 5.0 weight percent U-235, and a burnup range of 0 through 50 GWd/mtU.

  13. Algoritmo para la Inspección de Anillos de Compresión

    Directory of Open Access Journals (Sweden)

    J. Mauricio de Anda

    2006-01-01

    Full Text Available En el presente trabajo se describe el procedimiento utilizado en el análisis de anillos de compresión para el motor de un auto. Dicho análisis se lleva a cabo usando técnicas de procesamiento de imágenes con la finalidad de determinar si el anillo cumple con los requerimientos suficientes de calidad. El sistema de inspección está integrado por una cámara de video, un sistema de iluminación por leds blancos de alta luminosidad, una tarjeta que recibe la señal de video convirtiéndola a una señal digital y una serie de algoritmos de procesamiento de imágenes.

  14. Composición musical usando algoritmos genéticos

    Directory of Open Access Journals (Sweden)

    Julio César Carvajal Ramírez

    2012-09-01

    Full Text Available This paper presents a model of discrete musical composition based on musical writing techniques proposed by Johann Sebastian Bach. The model was implemented using the Meta-heuristics strategy, namely using Genetic algorithms implemented on the JGap Framework, producing musical results with a syntax that matches writing and music composition techniques. This approach is applied to the natural musical scale, and also to synthesized sounds of the natural-piano octave. Chords were created by taking the corresponding grades in the scale; additionally, notes and chords were grouped to become actual score bars.Using the proposed model, the following is obtained: 1 A set of notes grouped in bars with their corresponding interpretation, following the guidelines of syntactic JFugue Framework; 2 the score of the fragments produced written on a stave that complies with the rules of formal notation. Three MIDI files corresponding to three compositions (made by the computer are presented, showing a strong evolution of sound and, as such, an audible result of a song.

  15. Composición musical usando algoritmos genéticos

    National Research Council Canada - National Science Library

    Julio César Carvajal Ramírez; Fabián Andrés Giraldo Giraldo

    2012-01-01

    .... The model was implemented using the Meta-heuristics strategy, namely using Genetic algorithms implemented on the J Gap Framework, producing musical results with a syntax that matches writing and...

  16. Algoritmo de posicionamento e backtracking para seguidor solar

    OpenAIRE

    Nascimento, Bruno André Marques

    2015-01-01

    Nesta dissertação foi implementado um algoritmo de posicionamento solar e desenvolvido um algoritmo de backtracking num autómato programável (PLC) para o controlo de seguidores solares de um eixo da empresa Martifer Solar. Optou-se por implementar o algoritmo de posicionamento solar SPA devido à elevada precisão nos resultados apresentados. Para além disso foi desenvolvido um algoritmo de backtracking com o objetivo de evitar as sombras resultantes da posição dos painéis vizinh...

  17. Process inherent ultimate safety/boiling-water reactor PIUS/BWR

    Energy Technology Data Exchange (ETDEWEB)

    Forsberg, C.W.

    1985-01-01

    This document is a series of viewgraphs on: design basis of PIUS/BWR, definition of PIUS/BWR, mechanisms of safe shutdown and afterheat cooling, advantages of PIUS/BWR, and research and development requirements. (DLC)

  18. Assessment of two BWR accident management strategies

    Energy Technology Data Exchange (ETDEWEB)

    Hodge, S.A.; Petek, M.

    1991-01-01

    Candidate mitigative strategies for management of in-vessel events during the late phase (after core degradation has occurred) of postulated BWR severe accidents were considered at Oak Ridge National Laboratory (ORNL) during 1990. The identification of new strategies was subject to the constraint that they should, to the maximum extent possible, make use of the existing equipment and water resources of the BWR facilities and not require major equipment modifications or additions. As a result of this effort, two of these candidate strategies were recommended for additional assessment. The first is a strategy for containment flooding to maintain the core and structural debris within the reactor vessel in the event that vessel injection cannot be restored to terminate a severe accident sequence. The second strategy pertains to the opposite case, for which vessel injection would be restored after control blade melting had begun; its purpose is to provide an injection source of borated water at the concentration necessary to preclude criticality upon recovering a damaged BWR core. Assessments of these two strategies have been performed during 1991 under the auspices of the Detailed Assessment of BWR In-Vessel Strategies Program. This paper provides a discussion of the motivation for and purpose of these strategies and the potential for their success. 33 refs., 9 figs.

  19. BWR mechanics and materials technology update

    Energy Technology Data Exchange (ETDEWEB)

    Kiss, E.

    1983-05-01

    This paper discusses technical results obtained from a variety of important programs underway at General Electric's Nuclear Engineering Division. The principal objective of these programs is to qualify and improve BWR product related technologies that fall broadly under the disciplines of Applied Mechanics and Materials Engineering. The paper identifies and deals with current technical issues that are of general importance to the LWR industry albeit the specific focus is directed to the development and qualification of analytical predictive methods and criteria, and improved materials for use in the design of the BWR. In this paper, specific results and accomplishments are summarized to provide a braod perspective of technology advances. Results are presented in sections which discuss: dynamic analysis and modeling; fatigue and fracture evaluation; materials engineering advances; and flow induced vibration.

  20. BWR Refill-Reflood Program, Task 4. 7 - model development: TRAC-BWR component models

    Energy Technology Data Exchange (ETDEWEB)

    Cheung, Y K; Parameswaran, V; Shaug, J C

    1983-09-01

    TRAC (Transient Reactor Analysis Code) is a computer code for best-estimate analysis for the thermal hydraulic conditions in a reactor system. The development and assessment of the BWR component models developed under the Refill/Reflood Program that are necessary to structure a BWR-version of TRAC are described in this report. These component models are the jet pump, steam separator, steam dryer, two-phase level tracking model, and upper-plenum mixing model. These models have been implemented into TRAC-B02. Also a single-channel option has been developed for individual fuel-channel analysis following a system-response calculation.

  1. 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.

  2. Desarrollo de curvas espectrales del crecimiento anual de la vegetación, usando sensores remotos

    Directory of Open Access Journals (Sweden)

    Fernando Paz-Pellat

    2011-01-01

    Full Text Available El desarrollo de curvas del crecimiento de la vegetación (pastizales y matorrales, a nivel histórico, plantea retos importantes por falta de estadísticas en México. La tecnología de sensores remotos en plataformas espaciales, por medio de índices de vegetación o IV, permite realizar una aproximación en esta dirección. Este trabajo discute un esquema de modelación paramétrica (indirecta de la curva de crecimiento de la biomasa en píxeles individuales de sensores Advanced Very High Resolution Radiometer o AVHRR y Moderate Resolution Imaging Spectroradiometer o MODIS, permitiendo así su caracterización usando algoritmos de pre y post-proceso. Los resultados obtenidos de la aplicación de los algoritmos discutidos en este trabajo, permiten la obtención de curvas anuales del crecimiento a la escala de 100 ha (AVHRR y 6.25 ha (MODIS, que pueden ser usadas en estudios de cambio climático y del manejo de agostaderos en México.

  3. MONITOREO PRELIMINAR DE INCIDENCIA DE FISIOPATÍAS EN CULTIVOS DE FRESA USANDO PROCESAMIENTO DIGITAL DE IMÁGENES

    Directory of Open Access Journals (Sweden)

    JUAN DAVID SANDINO-MORA

    Full Text Available La identificación de diferentes anomalías en cultivos agrícolas usando procesamiento de imágenes, ha demostrado cada vez más su efectividad, contrario con los métodos de ejecución tradicionales, los cuales arrancan los folíolos y frutos de la planta, para realizar el estudio. En este trabajo se presentan los resultados del desarrollo e validación de un algoritmo, que permita realizar monitoreo de incidencia en cultivos de fresa (Fragaria x ananassa, capaz de dar una primera aproximación para distinguir senescencia y daños mecánicos en sus foliolos, implementando una metodología indirecta (no destructiva. Las técnicas de procesamiento de imágenes implementadas incluyen Suavizado, Erosión, Dilatación, Detección de Contornos, Correspondencia de Patrones, Umbralización, entre otros. Los resultados obtenidos se visualizaron en una aplicación desarrollada en C# usando la librería Emgu CV, mostrando al usuario un diagnóstico de la planta de estudio. Se concluye que es posible ofrecer un servicio de monitoreo preliminar de incidencia usando este algoritmo, ahorrando tiempo para productores e investigadores que requieran una primera aproximación del estado del cultivo, con la posibilidad de ejecutarse tanto en computadores e robots aéreos (drones para hacer más eficiente esta tarea.

  4. Sobre algunos algoritmos de la lagrangiana aumentada

    Directory of Open Access Journals (Sweden)

    Seijas, J. A.

    1999-01-01

    Full Text Available El término método Lagrangiano aumentado lo usamos en el sentido que el parámetro penalty lo hacemos tender a cero en vez de mantenerlo acotado lejos del cero. El espíritu del algoritmo es que a partir un método clásico penalty calculamos una estimación de los multiplicadores de Lagrange,. Gould (1989 Siam J. Numer. Anal. 26, 107 ha obtenido una convergencia local superlineal doble-paso, resultado de una estimación de un multiplicador de Lagrange constante. Dussault y otro han generalizado otro camino, la convergencia y la razón de convergencia resultan de métodos Lagrangianos aumentados respecto a la convergencia de las variables duales, sin el esfuerzo de obtener soluciones aproximadas de la minimizaciones primales sin condiciones. En el trabajo consideramos varias reglas de cálculo para la estimación de los multiplicadores de Lagrange y obtenemos resultados de razones de convergencia para variables primales y duales, una convergencia superlineal doble-paso de orden alfa, con alfa<2. En cada iteración usamos la solución de un sistema lineal primal-dual. Observamos que esto no mejora la razón de convergencia de los métodos simples penalty, pero mejora alguna cancelación de errores en cálculos internos.

  5. LBB application in Swedish BWR design

    Energy Technology Data Exchange (ETDEWEB)

    Kornfeldt, H.; Bjoerk, K.O.; Ekstroem, P. [ABB Atom, Vaesteras (Sweden)

    1997-04-01

    The protection against dynamic effects in connection with potential pipe breaks has been implemented in different ways in the development of BWR reactor designs. First-generation plant designs reflect code requirements in effect at that time which means that no piping restraint systems were designed and built into those plants. Modern designs have, in contrast, implemented full protection against damage in connection with postulated pipe breaks, as required in current codes and regulations. Moderns standards and current regulatory demands can be met for the older plants by backfitting pipe whip restraint hardware. This could lead to several practical difficulties as these installations were not anticipated in the original plant design and layout. Meeting the new demands by analysis would in this situation have great advantages. Application of leak-before-break criteria gives an alternative opportunity of meeting modem standards in reactor safety design. Analysis takes into account data specific to BWR primary system operation, actual pipe material properties, piping loads and leak detection capability. Special attention must be given to ensure that the data used reflects actual plant conditions.

  6. A BWR licensing experience in the USA

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J.; Ogura, C. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Arai, K. [Toshiba Corporation, Yokohama, Kanagawa (Japan); Thomas, S.; Mookhoek, B., E-mail: jim.powers@toshiba.com [Nuclear Innovation North America, Lake Jackson, Texas (United States)

    2015-09-15

    The US-Advanced Boiling Water Reactor (A BWR), certified by the United States Nuclear Regulatory Commission (US NRC), is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The STP3-4 project has finished the US NRC technical review of the Cola through the final meeting of the Advisory Committee on Reactor Safeguards (ACRS), and the Final Safety Evaluation Report (FSER) is scheduled to be issued by the US NRC in the middle of 2015. The next steps are to support the Mandatory Hearing process, and voting by the NRC commissioners on the motion to grant the Combined License, which is scheduled beginning of 2016 according to US NRC schedule as of March 30, 2015. This paper summarizes the history and progress of the US-A BWR licensing, including the experiences of the Licensee, Nina, and Toshiba as the Epc team worked through the Code of Federal Regulations Title 10 (10-Cfr) Part 52 process, and provides some perspectives on how the related licensing material would also be of value within a 10-Cfr Part 50, two-step process to minimize schedule and financial risks which could arise from ongoing technical developments and regulatory reviews. (Author)

  7. Diseño e implementación de un algoritmo para asignación de hsn en una red gsm y evaluación del mismo en el simulador smart

    OpenAIRE

    Franco, Xavier; Monsalve Arteaga, Carlos

    2009-01-01

    De todos los parámetros que conforman el plan de frecuencias para la capa de saltos de una red GSM, el Número de Secuencia de Saltos (HSN) es el que mayor controversia genera. Hasta la actualidad no se ha unificado un criterio para asignarlo entre las celdas de una red debido a dos razones potenciales, por un lado es una entrada al algoritmo seudo aleatorio de asignación de canales y por otro la mayoría de operadores han venido usando redes no sincronizadas, minimizando asi el grado de influ...

  8. Behaviour of the reactivity for BWR fuel cells; Comportamiento de la reactividad para celdas de combustible BWR

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, J. A.; Alonso, G.; Delfin, A.; Vargas, S. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E., E-mail: galonso@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, U. P. Adolfo Lopez Mateos, Col. Lindavista, 07738 Mexico D. F. (Mexico)

    2011-11-15

    In this work the behaviour of the reactivity of a fuel assembly type BWR was studied, the objective is to obtain some expressions that consider the average enrichment of U-235 and the gadolinium concentration like a function of the fuel cells burnt. Also, the applicability of the lineal reactivity model was analyzed for fuel cells type BWR. The analysis was carried out with the CASMO-4 code. (Author)

  9. Tópicos sobre optimización de algoritmos

    OpenAIRE

    Gloria Inés Giraldo Echeverry

    2011-01-01

    El presente artículo pretende ilustrar cómo, en el desarrollo de sofware, un primer algoritmo que se construya en la solución de un problema puede mejorarse muchísimo. analizando dónde se gasta su tiempo.

  10. Tópicos sobre optimización de algoritmos

    Directory of Open Access Journals (Sweden)

    Gloria Inés Giraldo Echeverry

    2011-01-01

    Full Text Available El presente artículo pretende ilustrar cómo, en el desarrollo de sofware, un primer algoritmo que se construya en la solución de un problema puede mejorarse muchísimo. analizando dónde se gasta su tiempo.

  11. Optimización de un ruteo vehicular usando algoritmo genético simple chu-beasley

    Directory of Open Access Journals (Sweden)

    Guillermo Roberto Solarte Martínez

    2015-04-01

    Full Text Available The research presented in the article is geared towards the area of genetic algorithms in the optimization of resources and processes, and then a case study is set based on vehicular routing and optimization of the same, applying the genetic algorithm of Chu-Beasley. This study, which started on November 2013 and finished on March 2014, was applied in Bogotá city, as it is the capital of Colombia. This metropolis counts with many industrial areas, gathering centers, warehouses and other commercial activities. Likewise, the growing of the capital in the last years has been significant, which has generated an exponential territorial extension, causing mobility problems and transport. For that reason, it is imperative for some warehouses that have to distribute their products, to optimize the routes and guarantee effectiveness and efficiency in delivery.  

  12. Planning DMPO pelvis using the algorithm of Pinnacle; Planificacion de pelvis usando el algoritmo DMPO de Pinnacle

    Energy Technology Data Exchange (ETDEWEB)

    Dorado Rodriguez, M. P.; Exposito, R. D.; Planes Meseguer, D.

    2011-07-01

    This paper presents a planning protocol for pelvic pathologies using the algorithm Direct Machine Parameter Optimization (DMPO) from Philips Pinnacle3, improves compliance rate (Conformation Number of van't Riet et al.) of PTVs and significantly reduces the dosage in organs at risk, without incurring a large increase in the planning time or irradiation, and in which verification is possible monitor routine unit.

  13. Control Neuronal por Modelo Inverso de un Servosistema Usando Algoritmos de Aprendizaje Levenberg-Marquardt y Bayesiano

    CERN Document Server

    Rodriguez-Toro, Victor A; Lopez, Jesus A

    2011-01-01

    In this paper we present the experimental results of the neural network control of a servo-system in order to control its speed. The control strategy is implemented by using an inverse-model control based on Artificial Neural Networks (ANNs). The network training was performed using two learning algorithms: Levenberg-Marquardt and Bayesian regularization. We evaluate the generalization capability for each method according to both the correct operation of the controller to follow the reference signal, and the control efforts developed by the ANN-based controller.

  14. BWR ASSEMBLY SOURCE TERMS FOR WASTE PACKAGE DESIGN

    Energy Technology Data Exchange (ETDEWEB)

    T.L. Lotz

    1997-02-15

    This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to provide boiling water reactor (BWR) assembly radiation source term data for use during Waste Package (WP) design. The BWR assembly radiation source terms are to be used for evaluation of radiolysis effects at the WP surface, and for personnel shielding requirements during assembly or WP handling operations. The objectives of this evaluation are to generate BWR assembly radiation source terms that bound selected groupings of BWR assemblies, with regard to assembly average burnup and cooling time, which comprise the anticipated MGDS BWR commercial spent nuclear fuel (SNF) waste stream. The source term data is to be provided in a form which can easily be utilized in subsequent shielding/radiation dose calculations. Since these calculations may also be used for Total System Performance Assessment (TSPA), with appropriate justification provided by TSPA, or radionuclide release rate analysis, the grams of each element and additional cooling times out to 25 years will also be calculated and the data included in the output files.

  15. 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.

  16. Status update of the BWR cask simulator

    Energy Technology Data Exchange (ETDEWEB)

    Lindgren, Eric R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Durbin, Samuel G. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    The performance of commercial nuclear spent fuel dry storage casks are typically evaluated through detailed numerical analysis of the system's thermal performance. These modeling efforts are performed by the vendor to demonstrate the performance and regulatory compliance and are independently verified by the Nuclear Regulatory Commission (NRC). Carefully measured data sets generated from testing of full sized casks or smaller cask analogs are widely recognized as vital for validating these models. Numerous studies have been previously conducted. Recent advances in dry storage cask designs have moved the storage location from above ground to below ground and significantly increased the maximum thermal load allowed in a cask in part by increasing the canister helium pressure. Previous cask performance validation testing did not capture these parameters. The purpose of the investigation described in this report is to produce a data set that can be used to test the validity of the assumptions associated with the calculations presently used to determine steady-state cladding temperatures in modern dry casks. These modern cask designs utilize elevated helium pressure in the sealed canister or are intended for subsurface storage. The BWR cask simulator (BCS) has been designed in detail for both the above ground and below ground venting configurations. The pressure vessel representing the canister has been designed, fabricated, and pressure tested for a maximum allowable pressure (MAWP) rating of 24 bar at 400 C. An existing electrically heated but otherwise prototypic BWR Incoloy-clad test assembly is being deployed inside of a representative storage basket and cylindrical pressure vessel that represents the canister. The symmetric single assembly geometry with well-controlled boundary conditions simplifies interpretation of results. Various configurations of outer concentric ducting will be used to mimic conditions for above and below ground storage configurations

  17. BWR Source Term Generation and Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    J.C. Ryman

    2003-07-31

    This calculation is a revision of a previous calculation (Ref. 7.5) that bears the same title and has the document identifier BBAC00000-01717-0210-00006 REV 01. The purpose of this revision is to remove TBV (to-be-verified) -41 10 associated with the output files of the previous version (Ref. 7.30). The purpose of this and the previous calculation is to generate source terms for a representative boiling water reactor (BWR) spent nuclear fuel (SNF) assembly for the first one million years after the SNF is discharged from the reactors. This calculation includes an examination of several ways to represent BWR assemblies and operating conditions in SAS2H in order to quantify the effects these representations may have on source terms. These source terms provide information characterizing the neutron and gamma spectra in particles per second, the decay heat in watts, and radionuclide inventories in curies. Source terms are generated for a range of burnups and enrichments (see Table 2) that are representative of the waste stream and stainless steel (SS) clad assemblies. During this revision, it was determined that the burnups used for the computer runs of the previous revision were actually about 1.7% less than the stated, or nominal, burnups. See Section 6.6 for a discussion of how to account for this effect before using any source terms from this calculation. The source term due to the activation of corrosion products deposited on the surfaces of the assembly from the coolant is also calculated. The results of this calculation support many areas of the Monitored Geologic Repository (MGR), which include thermal evaluation, radiation dose determination, radiological safety analyses, surface and subsurface facility designs, and total system performance assessment. This includes MGR items classified as Quality Level 1, for example, the Uncanistered Spent Nuclear Fuel Disposal Container (Ref. 7.27, page 7). Therefore, this calculation is subject to the requirements of the

  18. 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.

  19. An overview of the BWR ECCS strainer blockage issues

    Energy Technology Data Exchange (ETDEWEB)

    Serkiz, A.W.; Marshall, M.L. Jr.; Elliott, R. [Nuclear Regulatory Commission, Washington, DC (United States)

    1996-03-01

    This Paper provides a brief overview of actions taken in the mid 1980s to resolve Unresolved Safety Issue (USI) A-43, {open_quotes}Containment Emergency Sump Performance,{close_quotes} and their relationship to the BWR strainer blockage issue; the importance of insights gained from the Barseback-2 (a Swedish BWR) incident in 1992 and from ECCS strainer testing and inspections at the Perry nuclear power plant in 1992 and 1993; an analysis of an US BWR/4 with a Mark I containment; an international community sharing of knowledge relevant to ECCS strainer blockage, additional experimental programs; and identification of actions needed to resolve the strainer blockage issue and the status of such efforts.

  20. Seismic risk assessment of a BWR: status report

    Energy Technology Data Exchange (ETDEWEB)

    Chuang, T.Y.; Bernreuter, D.L.; Wells, J.E.; Johnson, J.J.

    1985-02-01

    The seismic risk methodology developed in the US NRC Seismic Safety Margins Research Program (SSMRP) was demonstrated by its application to the Zion nuclear power plant, a pressurized water reactor (PWR). A detailed model of Zion, including systems analysis models (initiating events, event trees, and fault trees), SSI and structure models, and piping models was developed and analyzed. The SSMRP methodology can equally be applied to a boiling water reactor (BWR). To demonstrate its applicability, to identify fundamental differences in seismic risk between a PWR and a BWR, and to provide a basis of comparison of seismic risk between a PWR and a BWR when analyzed with comparable methodology and assumptions, a seismic risk analysis is being performed on the LaSalle County Station nuclear power plant.

  1. TOMA DE DECISIONES BASADAS EN EL ALGORITMO DE DIJKSTRA

    Directory of Open Access Journals (Sweden)

    Laura Méndez Martínez

    2014-05-01

    Full Text Available Una de las funciones que realiza un ‘Radio Cognitivo’ es la toma de decisiones sobre el espectro radioeléctrico, esto a partir del análisis que realiza de su entorno. En este trabajo de investigación, se propone un método para la toma de decisiones para la selección de una banda en el espectro radioeléctrico que cumpla con ciertos criterios requeridos para una aplicación. Esta toma de decisiones se basa en un algoritmo de búsqueda del camino más corto similar al Algoritmo de Dijkstra. Para encontrar el camino más corto, el cual representa a la banda de frecuencia requerida, se especifican los atributos o parámetros a considerar para cada una de las bandas de acuerdo a una aplicación en particular o servicio requerido. A estos atributos o parámetros se les asignan valores es decir, pesos que determinan la prioridad e importancia para cada servicio. El algoritmo propuesto basado en Dijkstra, evalúa los parámetros del conjunto de bandas disponibles considerando el peso asignado, e indica la banda a seleccionar y que cubre con los criterios de la toma de decisiones. Se realizaron simulaciones por computadora para caracterizar los servicios identificados como mejor esfuerzo ‘Best Effort’ y tiempo real ‘Real Time’, obteniendo como resultado una latencia reducida que representa un tiempo práctico para ser implementado en un Radio Cognitivo en su toma de decisiones. Se observó también que los tiempos mostraron una mejora al ser comparados con los resultados obtenidos al implementar el Algoritmo de AHP.

  2. Evaluation of PWR and BWR pin cell benchmark results

    Energy Technology Data Exchange (ETDEWEB)

    Pijlgroms, B.J.; Gruppelaar, H.; Janssen, A.J. (Unit Nuclear Energy, Netherlands Energy Research Foundation ECN, Petten (Netherlands)); Hoogenboorm, J.E.; De Leege, P.F.A. (International Reactor Institute IRI, University of Leiden, Leiden (Netherlands)); Van de Voet, J.; Verhagen, F.C.M. (KEMA NV, Arnhem (Netherlands))

    1992-01-01

    In order to carry out reliable reactor core calculations for a boiled water reactor (BWR) or a pressurized water reactor (PWR) first reactivity calculations have to be carried out for which several calculation programs are available. The purpose of the title project is to exchange experiences to improve the knowledge of this reactivity calculations. In a large number of institutes reactivity calculations of PWR and BWR pin cells were executed by means of available computer codes. Results are compared. It is concluded that the variations in the calculated results are problem dependent. Part of the results is satisfactory. However, further research is necessary.

  3. PROPOSICIÓN Y SIMULACIÓN DE UN ALGORITMO ADAPTATIVO PARA SISTEMAS DE ANTENAS INTELIGENTES

    OpenAIRE

    Espinosa Díaz,Perla; Villarroel González,Carlos

    2007-01-01

    En este trabajo se describen brevemente los sistemas de antenas inteligentes. Se presentan algunos algoritmos adaptativos que hacen que el sistema sea inteligente. Los algoritmos que se presentan son LMS y el RLS y serán sometidos a un análisis matemático para su posterior simulación vía MatLab. Éstos se escogen por su relación con un algoritmo híbrido desarrollado. Cada algoritmo será evaluado respecto a diferentes parámetros tales como convergencia, rapidez, estabilidad, etc

  4. Full system decontamination experience in BWR

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, N.; Sugai, K.; Katayouse, N.; Fujimori, A.; Iida, K.; Hayashi, K. [Tokyo Electric Power Company, Tokyo (Japan); Kanasaki, T.; Inami, I. [Toshiba Corporation, Yokohama (Japan); Strohmer, F. [Framatome ANP Gmbh, Eelangen (Germany)

    2002-07-01

    At the Fukushima Daiichi Nuclear Power Station unit 3, unit 2, unit 5 and unit 1 of Tokyo Electric Power Company (TEPCO), the replacement of the core shroud and internals has been conducted since 1997 in this order. The welded core internals in operating BWR plants were replaced to improve stress corrosion cracking (SCC) resistance. At present these units are operating smoothly. The developed technology concept is to restore those internals in open air inside the reactor pressure vessel (RPV). To reduce the radiation dose rate inside the RPV, not only a shielding method was applied to cut the radiation from the irradiated structures but also a chemical decontamination method was applied to dissolve the radioactive crud deposited on the surface by using chemical agents. The calculated decontamination factor (DF) at the RPV bottom reached 35-117. As result, the dose rate decreased to approximately 0.1 mSv/h under water. Before and after the installation of the in-vessel shielding, a mechanical cleaning was extensively applied inside the RPV to remove the residual crud as well as the swarf, chips from cutting. As a result, the dose rate at the RPV bottom decreased to ranging from 0.2 to 0.4 mSv/h in air. A working environment for human access, which was better than expected, was established inside the RPV, resulting in 70, 140, 50 and 70 man-Sv (estimated) saving respectively at unit 3 (1F-3), unit 2(1F-2), unit 5(1F-5) and unit 1(1F-1). All four full system decontamination (FSDs) contributed to the successful realization of the core shroud replacement project under the dry condition in RPV.

  5. BWR stability using a reducing dynamical model; Estabilidad de un BWR con un modelo dinamico reducido

    Energy Technology Data Exchange (ETDEWEB)

    Ballestrin Bolea, J. M.; Blazquez Martinez, J. B.

    1990-07-01

    BWR stability can be treated with reduced order dynamical models. When the parameters of the model came from dynamical models. When the parameters of the model came from experimental data, the predictions are accurate. In this work an alternative derivation for the void fraction equation is made, but remarking the physical structure of the parameters. As the poles of power/reactivity transfer function are related with the parameters, the measurement of the poles by other techniques such as noise analysis will lead to the parameters, but the system of equations is non-linear. Simple parametric calculation of decay ratio are performed, showing why BWRs become unstable when they are operated at low flow and high power. (Author)

  6. Parallel strategies for a multi-criteria GRASP algorithm Estratégias de paralelização para um algoritmo GRASP multicritério

    Directory of Open Access Journals (Sweden)

    Dalessandro Soares Vianna

    2007-04-01

    Full Text Available This paper proposes different strategies of parallelizing a multi-criteria GRASP (Greedy Randomized Adaptive Search Problem algorithm. The parallel GRASP algorithm is applied to the multi-criteria minimum spanning tree problem, which is NP-hard. In this problem, a vector of costs is defined for each edge of the graph and the goal is to find all the efficient or Pareto optimal spanning trees (Pareto-optimal solutions. Each process finds a subset of efficient solutions. These subsets are joined using different strategies to obtain the final set of efficient solutions. The multi-criteria GRASP algorithm with the different parallel strategies are tested on complete graphs with n = 20, 30 and 50 nodes and r = 2 and 3 criteria. The computational results show that the proposed parallel algorithms reduce the execution time and the results obtained by the sequential version were improved.Este artigo propõe diferentes estratégias de paralelização de um algoritmo GRASP (Greedy Randomized Adaptive Search Procedure multicritério. O algoritmo paralelo proposto é aplicado ao problema da árvore geradora mínima multicritério, que é NP-difícil. Neste problema, um vetor de custos é definido para cada aresta do grafo e o objetivo é encontrar as árvores geradoras eficientes (soluções Pareto-ótimas. Cada processo encontra um subconjunto de soluções eficientes. Estes subconjuntos são reunidos usando diferentes estratégias para obter o conjunto final de soluções eficientes. O algoritmo proposto é testado em grafos completos com n = 20, 30 e 50 nós e r = 2 e 3 critérios. Os resultados computacionais mostram que a proposta de se paralelizar o algoritmo reduz o tempo de execução e os resultados obtidos pela versão seqüencial foram melhorados.

  7. Evaluation of PWR and BWR pin cell benchmark results

    Energy Technology Data Exchange (ETDEWEB)

    Pijlgroms, B.J.; Gruppelaar, H.; Janssen, A.J. (Netherlands Energy Research Foundation (ECN), Petten (Netherlands)); Hoogenboom, J.E.; Leege, P.F.A. de (Interuniversitair Reactor Inst., Delft (Netherlands)); Voet, J. van der (Gemeenschappelijke Kernenergiecentrale Nederland NV, Dodewaard (Netherlands)); Verhagen, F.C.M. (Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands))

    1991-12-01

    Benchmark results of the Dutch PINK working group on PWR and BWR pin cell calculational benchmark as defined by EPRI are presented and evaluated. The observed discrepancies are problem dependent: a part of the results is satisfactory, some other results require further analysis. A brief overview is given of the different code packages used in this analysis. (author). 14 refs., 9 figs., 30 tabs.

  8. The Advanced BWR Nuclear Plant: Safe, economic nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Redding, J.R. [GE Nuclear Energy, San Jose, CA (United States)

    1994-12-31

    The safety and economics of Advanced BWR Nuclear Power Plants are outlined. The topics discussed include: ABWR Programs: status in US and Japan; ABWR competitiveness: safety and economics; SBWR status; combining ABWR and SBWR: the passive ABWR; and Korean/GE partnership.

  9. BWR refill-reflood program: core spray distribution experimental task plan

    Energy Technology Data Exchange (ETDEWEB)

    Eckert, T.

    1981-02-01

    An experimental task plan for the BWR/4 core spray task of the Refill-Reflood Test Program is presented. The test program will provide core spray distribution data for a 30 degree sector of the BWR/4 and 5-218 design. This design uses different nozzle types and different sparger elevations than the BWR/6-218 design which was tested previously. Test parameter ranges are specified; individual tests are defined; and measurement and data utilization plans are defined.

  10. Classificação de sons cardíacos usando Motifs: desenvolvimento de uma aplicação móvel

    OpenAIRE

    Oliveira, Soraia Carvalho da Cruz

    2014-01-01

    Este documento foi redigido no âmbito da Tese, do Mestrado em Engenharia Informática na área de Tecnologias do Conhecimento e Decisão, do Departamento de Engenharia Informática, do ISEP, cujo tema é classificação de sons cardíacos usando motifs. Neste trabalho, apresenta-se um algoritmo de classificação de sons cardíacos, capaz de identificar patologias cardíacas. A classificação do som cardíaco é um trabalho desafiante dada a dificuldade em separar os sons ambiente (vozes, respiração, con...

  11. Determinación de eventos de diseño de funciones bivariadas usando el método de bisección

    OpenAIRE

    Maritza Arganis Juárez; José Luis Herrera Alanís; Ramón Domínguez Mora

    2013-01-01

    En este artículo se presenta la determinación de parejas de valores de caudal y de volumen correspondientes a distintos periodos de retorno para la estación hidrométrica Huites, Sinaloa, México, usando métodos determinísticos cerrados y abiertos de búsqueda de raíces; tal es el caso del algoritmo numérico de bisección y el método de la secante, respectivamente; la función de distribución bivariada de las variables analizadas fue una Gumbel de dos poblaciones cuyos parámetros fueron obtenidos ...

  12. Vertical Drop of 44-BWR Waste Package With Lifting Collars

    Energy Technology Data Exchange (ETDEWEB)

    A.K. Scheider

    2005-08-23

    The objective of this calculation is to determine the structural response of a waste package (WP) dropped flat on its bottom from a specified height. The WP used for that purpose is the 44-Boiling Water Reactor (BWR) WP. The scope of this document is limited to reporting the calculation results in terms of stress intensities. The Uncanistered Waste Disposal Container System is classified as Quality Level 1 (Ref. 4, page 7). Therefore, this calculation is subject to the requirements of the Quality Assurance Requirements and Description (Ref. 16). AP-3. 12Q, Design Calculations and Analyses (Ref. 11) is used to perform the calculation and develop the document. The information provided by the sketches attached to this calculation is that of the potential design of the type of 44-BWR WP considered in this calculation and provides the potential dimensions and materials for that design.

  13. Development of advanced BWR fuel bundle with spectral shift rod - BWR core characteristics with SSR

    Energy Technology Data Exchange (ETDEWEB)

    Hino, T.; Kondo, T.; Chaki, M.; Ohga, Y. [Hitachi-GE Nuclear Energy, Ltd., 1-1, Saiwai-cho, 3-chome, Hitachi-shi, Ibaraki-ken, 317-0073 (Japan); Makigami, T. [Tokyo Electric Power Company Inc., 1-1-3, Uchisaiwai-cho, Chiyoda-ku, Tokyo, 100-0011 (Japan)

    2012-07-01

    The neutron energy spectrum can be varied during an operation cycle to generate and utilize more plutonium from the non-fissile {sup 238}U by changing the void fraction in the core through control of the core coolant flow rate. This operation method, which is called a spectral shift operation, is practiced in BWRs to save natural uranium. A new component called a spectral shift rod (SSR), which is utilized instead of a conventional water rod, has been introduced to amplify the void fraction change and increase the spectral shift effect. In this study, fuel bundle design with the SSR and core design were carried out for the ABWR and the next generation BWR, HP-ABWR (High-Performance ABWR).The core characteristics with the SSR were evaluated and compared with those when using the conventional water rod. Influences of uncertainty of the water level in the SSR on the safety limit minimum critical power ratio (SLMCPR) were considered for evaluation of the uranium saving effect attained by the SSR. As a result, it was found that the amount of natural uranium needed for an operation cycle could be reduced more than 3% with 20% core coolant flow change and more than 5% with 30% core coolant flow change, in the form of increased discharge exposure by using the SSR compared with the conventional water rod use. (authors)

  14. Evaluation of PWR and BWR pin cell benchmark results

    Energy Technology Data Exchange (ETDEWEB)

    Pilgroms, B.J.; Gruppelaar, H.; Janssen, A.J. (Netherlands Energy Research Foundation (ECN), Petten (Netherlands)); Hoogenboom, J.E.; Leege, P.F.A. de (Interuniversitair Reactor Inst., Delft (Netherlands)); Voet, J. van der (Gemeenschappelijke Kernenergiecentrale Nederland NV, Dodewaard (Netherlands)); Verhagen, F.C.M. (Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands))

    1991-12-01

    Benchmark results of the Dutch PINK working group on the PWR and BWR pin cell calculational benchmark as defined by EPRI are presented and evaluated. The observed discrepancies are problem dependent: a part of the results is satisfactory, some other results require further analysis. A brief overview is given of the different code packages used in this analysis. (author). 14 refs.; 9 figs.; 30 tabs.

  15. Latest experiences in inspecting the inside of BWR vessel shields

    Energy Technology Data Exchange (ETDEWEB)

    Alberdi, R.; Gonzalez, E.

    2001-07-01

    In the last few years, the owners of BWR nuclear power plants have been forced to address new fuel shield inspection requirements, TECNATOM has responded to this situation by launching the TEIDE projects, which include development of an inspection machine and the corresponding Non-Destructive Tests to examine the inside of this shield. With these projects, TECNATOM has performed more than 12 fuel shield inspections in different countries. This article describes the experience gained in the last three years. (Author)

  16. 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...

  17. 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...

  18. Thermohydraulic stability coupled to the neutronic in a BWR; Estabilidad termohidraulica acoplada a la neutronica en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Calleros M, G.; Zapata Y, M.; Gomez H, R.A.; Mendez M, A. [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Cardel-Nautla Km. 42.5, Mpio. Alto Lucero, Veracruz (Mexico); Castlllo D, R. [ININ, Carretera Mexico-Toluca Km 36.5, La Marquesa, Estado de Mexico (Mexico)]. e-mail: gcm9acpp@cfe.gob.mx

    2006-07-01

    In a BWR type reactor the phenomenon of the nuclear fission is presented, in which are liberated in stochastic form neutrons, originating that the population of the same ones varies in statistic form around a mean value. This variation will cause that when the neutron flow impacts on the neutron detectors, its are had as a result neutron flow signals with fluctuations around an average value. In this article it is shown that it conforms it lapses the time, this variations in the neutron flow (and therefore, in the flow signal due only to the fission), they presented oscillations inside a stable range, which won't be divergent. Considering that the BWR is characterized because boiling phenomena are presented, which affect the moderation of the neutrons, additional variations will be had in the signal coming from the neutron detectors, with relationship to the fission itself, which will be influenced by the feedback of the moderator's reactivity and of the temperature of the fuel pellet. Also, as the BWR it has coupled control systems to maintain the coolant level one and of the thermal power of the reactor, for each control action it was affected the neutron population. This means that the reactor could end up straying of a stable state condition. By it previously described, the study of the thermohydraulic stability coupled to the neutronic is complex. In this work it is shown the phenomenology, the mathematical models and the theoretical behavior associated to the stability of the BWR type reactor; the variables that affect it are identified, the models that reproduce the behavior of the thermohydraulic stability coupled to the neutronic, the way to maintain stable the reactor and the instrumentation that can settle to detect and to suppress uncertainties is described. In particular, is make reference to the evolution of the methods to maintain the stability of the reactor and the detection system and suppression of uncertainties implemented in the

  19. Algoritmo de Encriptación de Archivo de Texto Plano

    OpenAIRE

    2010-01-01

    El presente proyecto es del tipo exploratorio y trata acerca de la implementación de un algoritmo de encriptación basado en el método de Hills y RSA, por el cual se leen las líneas de un archivo de texto plano, para luego ser codificado o decodificado según el proceder del usuario.Trabajamos con el código ASCII para la aplicación del algoritmo, debido a que el algoritmo se basa en aritmética modular. Las características notables del algoritmo son:• Facilidad de conversión de cualquier carácte...

  20. 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.

  1. Detección daño estructural empleando el vector de fuerza residual modificado y el algoritmo Simulated Annealing (SA Damage Detection Using the Modified Residual Force Vector and the Simulated Annealing Algorithm (SA

    Directory of Open Access Journals (Sweden)

    Óscar Begambre

    2010-01-01

    Full Text Available En este trabajo, el algoritmo Simulated Annealing (SA es empleado para solucionar el problema inverso de detección de daño en vigas usando información modal contaminada con ruido. La formulación de la función objetivo para el procedimiento de optimización, basado en el SA, está fundamentada en el método de la fuerza residual modificada. El desempeño del SA empleado en este estudio superó el de un algoritmo genético (AG en dos funciones de prueba reportadas en la literatura internacional. El procedimiento de evaluación de integridad aquí propuesto se confirmó y validó numéricamente empleando la teoría de vigas de Euler-Bernoulli y un Modelo de Elementos Finitos (MEF de vigas en voladizo y apoyadas libremente.In this research, the Simulated Annealing Algorithm (SA is employed to solve damage detection problems in beam type structures using noisy polluted modal data. The formulation of the objective function for the SA optimization procedure is based on the modified residual force method. The SA used in this research performs better than the Genetic Algorithm (GA in two difficult benchmark functions. The proposed structural damage-identification scheme is confirmed and assessed using a Finite Element Model (FEM of cantilever and a free-free Euler-Bernoulli beam model

  2. Algoritmo de busca dispersa aplicado ao problema clássico de roteamento de veículos

    Directory of Open Access Journals (Sweden)

    Nélida Gladys Maquera Sosa

    2007-08-01

    Full Text Available Neste artigo apresentamos heurísticas usando o conceito da meta-heurística Busca Dispersa (BD, desenvolvidas para a solução do Problema de Roteamento de Veículos (PRV Clássico, detalhando cada uma de suas etapas básicas quando aplicadas ao problema em questão. A Busca Dispersa é um método evolutivo que combina soluções com a finalidade de criar novas soluções de melhor qualidade; ainda que apresente similaridades com os algoritmos genéticos difere dos mesmos em princípios fundamentais. Um aspecto importante da BD é formar soluções com alta qualidade para dirigir a busca a regiões promissoras. Experimentos computacionais foram realizados em quatro conjuntos de dados disponíveis na literatura. Os resultados mostram que a BD é robusta e competitiva em termos de qualidade das soluções obtidas e tempo computacional para o PRV Clássico, para os conjuntos de dados testados.In this paper we present a Scatter Search algorithm designed for the solution of the Classical Vehicle Routing Problem, giving details of each of its basic phases when applied to the routing problem. Scatter Search is an evolutionary meta-heuristic that combines solutions with the objective of obtaining new solutions of higher quality; even though there are similarities between Scatter Search and Genetic Algorithms, the two methods differ in basic principles. An important aspect of Scatter Search is to construct high quality solutions in order to direct the search to promising regions. Computational experiments were conducted using four data sets available in the literature. The results show that Scatter Search is robust and competitive in terms of both the quality of solutions and computational times, for the VRP data sets we used.

  3. Teorema de Hall y un algoritmo para detectar sistemas de representantes distintos

    Directory of Open Access Journals (Sweden)

    Edwin Carranza Vargas

    2012-04-01

    Full Text Available Este trabajo presenta dos aportes a la combinatoria aplicada el primerola relación de equivalencia de los Teoremas de Ford- Fulkerson, Menger,Köning, Dilworth y Hall, además presenta una nueva prueba al Teoremade Hall que sirve como algoritmo para detectar sistemas de representantes distintos.En cada sección se establecen generalidades de los teoremas mencionados y finalmente el algoritmo con su respectiva justificación.

  4. Prony's method application for BWR instabilities characterization

    Energy Technology Data Exchange (ETDEWEB)

    Castillo, Rogelio, E-mail: rogelio.castillo@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Ramírez, J. Ramón, E-mail: ramon.ramirez@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Alonso, Gustavo, E-mail: gustavo.alonso@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Instituto Politecnico Nacional, Unidad Profesional Adolfo Lopez Mateos, Ed. 9, Lindavista, D.F. 07300 (Mexico); Ortiz-Villafuerte, Javier, E-mail: javier.ortiz@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico)

    2015-04-01

    Highlights: • Prony's method application for BWR instability events. • Several BWR instability benchmark are assessed using this method. • DR and frequency are obtained and a new parameter is proposed to eliminate false signals. • Adequate characterization of in-phase and out-of-phase events is obtained. • The Prony's method application is validated. - Abstract: Several methods have been developed for the analysis of reactor power signals during BWR power oscillations. Among them is the Prony's method, its application provides the DR and the frequency of oscillations. In this paper another characteristic of the method is proposed to determine the type of oscillations that can occur, in-phase or out-of-phase. Prony's method decomposes a given signal in all the frequencies that it contains, therefore the DR of the fundamental mode and the first harmonic are obtained. To determine the more dominant pole of the system a normalized amplitude W of the system is calculated, which depends on the amplitude and the damping coefficient. With this term, it can be analyzed which type of oscillations is present, if W of the fundamental mode frequency is the greater, the type of oscillations is in-phase, if W of the first harmonic frequency is the greater, the type of oscillations is out-of-phase. The method is applied to several stability benchmarks to assess its validity. Results show the applicability of the method as an alternative analysis method to determine the type of oscillations occurred.

  5. Prevention of organic iodide formation in BWR`s

    Energy Technology Data Exchange (ETDEWEB)

    Karjunen, T. [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland); Laitinen, T.; Piippo, J.; Sirkiae, P. [VTT Manufacturing Technology (Finland)

    1996-12-01

    During an accident, many different forms of iodine may emerge. Organic iodides, such as methyl iodide and ethyl iodide, are relatively volatile, and thus their appearance leads to increased concentration of gaseous iodine. Since organic iodides are also relatively immune to most accident mitigation measures, such as sprays and filters, they can affect the accident source term significantly even when only a small portion of iodine is in organic form. Formation of organic iodides may not be limited by the amount of organic substances available. Excessive amounts of methane can be produced, for example, during oxidation of boron carbide, which is used in BWR`s as a neutron absorber material. Another important source is cable insulation. In a BWR, a large quantity of cables is placed below the pressure vessel. Thus a large quantity of pyrolyse gases will be produced, should the vessel fail. Organic iodides can be formed as a result of many different reactions, but at least in certain conditions the main reaction takes place between an organic radical produced by radiolysis and elemental iodine. A necessary requirement for prevention of organic iodide production is therefore that the pH in the containment water pools is kept high enough to eliminate formation of elemental iodine. In a typical BWR the suppression pool water is usually unbuffered. As a result, the pH may be dominated by chemicals introduced during an accident. If no system for adding basic chemicals is operable, the main factor affecting pool water pH may be hydrochloric acid released during cable degradation. Should this occur, the conditions could be very favorable for production of elemental iodine and, consequently, formation of organic iodides. Although high pH is necessary for iodine retention, it could have also adverse effects. High pH may, for example, accelerate corrosion of containment materials and alter the characteristics of the solid corrosion products. (author) 6 figs., 1 tab., 13 refs.

  6. Stability prediction of continuous surveillance in BWR reactor; Predictor de estabilidad para la vigilancia continua de un reactor tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Tofino Gomez, Y.

    2006-07-01

    As result of the susceptibility of the Boiling Water Reactors (BWR) to suffer from power instabilities, the program LIP has been developed (LAPUR Input Preprocessor), which automatically determines the decay ratio (DR), as stability margin indication. For DR calculation, LAPUR program is a good predictive alternative: a fast execution for an acceptable precision. LAPUR demands a complex input, dependent on the instantaneous core configuration, requiring an exhaustive control of its generation. LIP, with a modular character, automatically generates the input from the core monitoring system, CAPRICORE (based on Simulate-3), obtaining the DR during the operation. This tool can accelerate the start-up maneuvers and other transients, increasing the plant availability. (Author)

  7. Neutron dosimetry. Environmental monitoring in a BWR type reactor; Dosimetria de neutrones. Monitoreo ambiental en un reactor del tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Tavera D, L.; Camacho L, M.E

    1991-01-15

    The measurements carried out on reactor dosimetry are applied mainly to the study on the effects of the radiation in 108 materials of the reactor; little is on the environmental dosimetry outside of the primary container of BWR reactors. In this work the application of a neutron spectrometer formed by plastic detectors of nuclear traces manufactured in the ININ, for the environmental monitoring in penetrations around the primary container of the unit I of the Laguna Verde central is presented. The neutron monitoring carries out with purposes of radiological protection, during the operational tests of the reactor. (Author)

  8. BWR online monitoring system based on noise analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz-Villafuerte, Javier [Departamento de Sistemas Nucleares, Instituto Nacional de Investigaciones Nucleares, Carr. Mexico-Toluca S/N, Ocoyoacac, Edo. de Mexico, 52750 (Mexico)]. E-mail: jov@nuclear.inin.mx; Castillo-Duran, Rogelio [Departamento de Sistemas Nucleares, Instituto Nacional de Investigaciones Nucleares, Carr. Mexico-Toluca S/N, Ocoyoacac, Edo. de Mexico, 52750 (Mexico)]. E-mail: rcd@nuclear.inin.mx; Alonso, Gustavo [Departamento de Sistemas Nucleares, Instituto Nacional de Investigaciones Nucleares, Carr. Mexico-Toluca S/N, Ocoyoacac, Edo. de Mexico, 52750 (Mexico)]. E-mail: galonso@nuclear.inin.mx; Calleros-Micheland, Gabriel [Central Nuclear de Laguna Verde, Comision Federal de Electricidad, Carr. Cardel-Nautla, km. 42.5, Alto Lucero, Veracruz (Mexico)]. E-mail: gcm9acpp@cfe.gob.mx

    2006-11-15

    A monitoring system for during operation early detection of an anomaly and/or faulty behavior of equipment and systems related to the dynamics of a boiling water reactor (BWR) has been developed. The monitoring system is based on the analysis of the 'noise' or fluctuations of a signal from a sensor or measurement device. An efficient prime factor algorithm to compute the fast Fourier transform allows the continuous, real-time comparison of the normalized power spectrum density function of the signal against previously stored reference patterns in a continuously evolving matrix. The monitoring system has been successfully tested offline. Four examples of the application of the monitoring system to the detection and diagnostic of faulty equipment behavior are presented in this work: the detection of two different events of partial blockage at the jet pump inlet nozzle, miss-calibration of a recirculation mass flow sensor, and detection of a faulty data acquisition card. The events occurred at the two BWR Units of the Laguna Verde Nuclear Power Plant. The monitoring system and its possible coupling to the data and processing information system of the Laguna Verde Nuclear Power Plant are described. The signal processing methodology is presented along with the introduction of the application of the evolutionary matrix concept for determining the base signature of reactor equipment or component and the detection of off normal operation conditions.

  9. A detailed BWR recirculation loop model for RELAP

    Energy Technology Data Exchange (ETDEWEB)

    Araiza-Martínez, Enrique, E-mail: enrique.araiza@inin.gob.mx; Ortiz-Villafuerte, Javier, E-mail: javier.ortiz@inin.gob.mx; Castillo-Durán, Rogelio, E-mail: rogelio.castillo@inin.gob.mx

    2017-01-15

    Highlights: • A new detailed BWR recirculation loop model was developed for RELAP. • All jet pumps, risers, manifold, suction and control valves, and recirculation pump are modeled. • Model is tested against data from partial blockage of two jet pumps. • For practical applications, simulation results showed good agreement with available data. - Abstract: A new detailed geometric model of the whole recirculation loop of a BWR has been developed for the code RELAP. This detailed model includes the 10 jet pumps, 5 risers, manifold, suction and control valves, and the recirculation pump, per recirculation loop. The model is tested against data from an event of partial blockage at the entrance nozzle of one jet pump in both recirculation loops. For practical applications, simulation results showed good agreement with data. Then, values of parameters considered as figure of merit (reactor power, dome pressure, core flow, among others) for this event are compared against those from the common 1 jet pump per loop model. The results show that new detailed model led to a closer prediction of the reported power change. The detailed recirculation loop model can provide more reliable boundary condition data to a CFD models for studies of, for example, flow induced vibration, wear, and crack initiation.

  10. BWR Servicing and Refueling Improvement Program: Phase I summary report

    Energy Technology Data Exchange (ETDEWEB)

    Perry, D.R.

    1978-09-01

    Under the U.S. Department of Energy sponsorship, General Electric Co. (GE) undertook a study of boiling water reactor (BWR) refueling outages for the purpose of recommending the development and demonstration of critical path time savings improvements. The Tennessee Valley Authority (TVA) joined the study as a subcontractor, providing monitoring assistance and making the Browns Ferry Site available for improvement demonstrations. Agreement was also reached with Georgia Power Co., Power Authority of the State of New York, and Commonwealth Edison Co. for monitoring and data collection at Hatch 1, FitzPatrick, and Quad Cities 1 nuclear plants, respectively. The objective was to identify, develop, and demonstrate improved refueling, maintenance, and inspection procedures and equipment. The improvements recommended in this study are applicable to BWR nuclear plants currently in operation as well as those in the design and construction phases. The recommendations and outage information can be used as a basis to plan and conduct the first outages of new plants and to improve the planning and facilities of currently operating plants. Many of the recommendations can readily be incorporated in plants currently in the design and construction phases as well as in the design of future plants. Many of these recommended improvements can be implemented immediately by utilities without further technical development.

  11. A comparison between genetic algorithms and neural networks for optimizing fuel recharges in BWR; Una comparacion entre algoritmos geneticos y redes neuronales para optimizar recargas de combustible en BWR's

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz J, J. [Instituto Nacional de Investigaciones Nucleares, Depto. Sistemas Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico); Requena, I. [Universidad de Granada (Spain)

    2002-07-01

    In this work the results of a genetic algorithm (AG) and a neural recurrent multi state network (RNRME) for optimizing the fuel reload of 5 cycles of the Laguna Verde nuclear power plant (CNLV) are presented. The fuel reload obtained by both methods are compared and it was observed that the RNRME creates better fuel distributions that the AG. Moreover a comparison of the utility for using one or another one techniques is make. (Author)

  12. 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)

  13. Diseño de una biblioteca de compuertas MCML utilizando un algoritmo genético y optimización multiobjetivo

    Directory of Open Access Journals (Sweden)

    Roberto Pereira-Arroyo

    2014-11-01

    Full Text Available En este documento se alude al problema de dimensionamiento de circuitos MCML (MOS Current Mode Logic. Se introduce el Frente de Pareto como una herramienta de análisis útil para explorar el espacio de diseño de las distintas compuertas que conforman nuestra biblioteca básica MCML. Un algoritmo genético (GA es implementado para detectar automáticamente este frente, en un proceso que busca eficientemente las parametrizaciones óptimas del diseño y sus correspondientes valores en un espacio de aptitudes. Las mediciones del consumo de potencia, el retardo de propagación y el rango del voltaje de salida se usan como funciones de aptitud, puesto que el problema se trata como una tarea de optimización multiobjetiva. Finalmente, se presentan los resultados de las simulaciones postlayout, usando la tecnología de fabricación AMS 0,35 μm.

  14. 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.

  15. Studies of fragileness in steels of vessels of BWR reactors; Estudios de fragilizacion en aceros de vasija de reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Robles, E.F.; Balcazar, M.; Alpizar, A.M.; Calderon, B.E. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    The structural materials with those that are manufactured the pressure vessels of the BWR reactors, suffer degradation in its mechanical properties mainly to the damage taken place by the fast neutrons (E > 1 MeV) coming from the reactor core. Its are experimentally studied those mechanisms of neutron damage in this material type, by means of the irradiation of steel vessel in experimental reactors to age them quickly. Alternatively it is simulated the neutron damage by means of irradiation of steel with heavy ions. In this work those are shown first results of the damage induced by irradiation from a similar steel to the vessel of a BWR reactor. The irradiation was carried out with fast neutrons (E > 1 MeV, fluence of 1.45 x 10{sup 18} n/cm{sup 2}) in the TRIGA MARK lll reactor and separately with Ni{sup +3} ions in a Tandetrom accelerator, E = 4.8 MeV and range of the ionic flow of 0.1 to 53 iones/A{sup 2}. (Author)

  16. System control model of a turbine for a BWR; Modelo del sistema de control de una turbina para un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Vargas O, Y. [Universidad del Valle de Mexico, Campus Toluca, Av. Las Palmas No. 136, Col. San Jorge Pueblo Nuevo, 52140 Metepec, Estado de Mexico (Mexico); Amador G, R.; Ortiz V, J.; Castillo D, R.; Delfin L, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: rodolfo.amador@inin.gob.mx

    2009-10-15

    In this work is presented a design of a control system of a turbine for a nuclear power plant with a BWR like energy source. The model seeks to implement later on at thermal hydraulics code of better estimate RELAP/SCDAPSIM. The model is developed for control and protection of turbine, and the consequent protection to the BWR, considering that the turbine control could be employed for one or several turbines in series. The quality of present designs of control pattern of turbine it is that it considers the parameters more important in the operation of a turbine besides that is has incorporated at control the secondary parameters that will be activated originally as true when the turbine model is substituted by a model more detailed. The development of control model of a turbine will be good in short and medium term to realize analysis about the operation of turbine with different operation conditions, of vapor extraction specific steps of turbine to feed other equipment s, besides analyzing the separate effect and integrated effect. (Author)

  17. Comparación entre algoritmos recursivos e iterativos y su medición en términos de eficiencia

    OpenAIRE

    Juan de Dios Murillo Morera; Santiago Caamaño Polini

    2013-01-01

    Se llevarán a cabo comparaciones simples entre algoritmos recursivos e iterativos, para determinar el grado de eficiencia de un problema en particular. Se efectuaron pruebas de comparación y análisis utilizando tres ejemplos en ambos tipos de algoritmos, a los cuales se les aplicaron los criterios de análisis de algoritmos

  18. 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

  19. 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.

  20. Validation and Application of the Thermal Hydraulic System Code TRACE for Analysis of BWR Transients

    Directory of Open Access Journals (Sweden)

    V. H. Sánchez

    2012-01-01

    Full Text Available The Karlsruhe Institute of Technology (KIT is participating on (Code Applications and Maintenance Program CAMP of the US Nuclear Regulatory Commission (NRC to validate TRACE code for LWR transient analysis. The application of TRACE for the safety assessment of BWR requires a throughout verification and validation using experimental data from separate effect and integral tests but also using plant data. The validation process is normally focused on safety-relevant phenomena for example, pressure drop, void fraction, heat transfer, and critical power models. The purpose of this paper is to validate selected BWR-relevant TRACE-models using both data of bundle tests such as the (Boiling Water Reactor Full-Size Fine-Mesh Bundle Test BFBT and plant data recorded during a turbine trip event (TUSA occurred in a Type-72 German BWR plant. For the validation, TRACE models of the BFBT bundle and of the BWR plant were developed. The performed investigations have shown that the TRACE code is appropriate to describe main BWR-safety-relevant phenomena (pressure drop, void fraction, and critical power with acceptable accuracy. The comparison of the predicted global BWR plant parameters for the TUSA event with the measured plant data indicates that the code predictions are following the main trends of the measured parameters such as dome pressure and reactor power.

  1. Oxide evolution on Alloy X-750 in simulated BWR environment

    Science.gov (United States)

    Tuzi, Silvia; Göransson, Kenneth; Rahman, Seikh M. H.; Eriksson, Sten G.; Liu, Fang; Thuvander, Mattias; Stiller, Krystyna

    2016-12-01

    In order to simulate the environment experienced by spacer grids in a boiling water reactor (BWR), specimens of the Ni-based Alloy X-750 were exposed to a water jet in an autoclave at a temperature of 286 °C and a pressure of 80 bar. The oxide microstructure of specimens exposed for 2 h, 24 h, 168 h and 840 h has been investigated mainly using electron microscopy. The specimens suffer mass loss due to dissolution during exposure. At the same time a complex layered oxide develops. After the longest exposure the oxide consists of two outer spinel layers consisting of blocky crystals, one intermediate layer of nickel oxide interspersed with Ti-rich oxide needles, and an inner layer of oxidized base metal. The evolution of the oxide leading up to this structure is discussed and a model is presented.

  2. Algoritmo eficiente para procesos de estimación geoestadísticos

    Directory of Open Access Journals (Sweden)

    Mirelis Rasúa-López

    2001-03-01

    Full Text Available En el presente artículo se expone un algoritmo que permite disminuir de manera sustancial el número de operaciones usualmente requerido para realizar la estimación del valor de una variable regionalizada, a partir de los valores conocidos de la misma en un conjunto de puntos del espacio o del plano. El algoritmo puede usarse para acelerar la estimación por Kriging, o por el método de las funciones de autocorrelación permitiendo, por tanto, mayor rapidez en la generación de mapas y otros cálculos asociados

  3. Algoritmo de suspensión activa para vehículos ferroviarios

    OpenAIRE

    Bustos Caballero, Alejandro

    2012-01-01

    En este proyecto se abordará el desarrollo de un sistema de suspensión activa basado en un nuevo algoritmo, propuesto por el grupo MAQLAB de la Universidad Carlos III de Madrid, que hace uso de la característica determinista del ferrocarril. Para llevarlo a cabo se desarrollará un modelo de vehículo ½ sobre el entorno Simulink/SimMechanics que se validará mediante comparación con otro software de reconocido prestigio. Por otra parte, se planteará el nuevo algoritmo y se implementará en nuestr...

  4. Algunos algoritmos iterativos en álgebra lineal numérica

    OpenAIRE

    Uslé Laza, Laura

    2016-01-01

    RESUMEN: En este trabajo estudiamos algunos de los grandes problemas a los que se enfrenta el Álgebra Lineal Numérica, como el cálculo de los valores propios de una matriz, así como la resolución de sistemas de ecuaciones mediante distintos algoritmos. Se realiza un estudio sobre diversos algoritmos, implementándolos en Matlab. Para el análisis de resultados tomamos matrices aleatorias de tamaño 100, 500 y 1000 tanto para matrices reales como complejas, simétricas/hermíticas o no. Concluimos...

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

    OpenAIRE

    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...

  6. Algoritmos de predicción en la modelación cuadrática

    OpenAIRE

    Mendoza, Marvin; Díaz, Leonora; Arrieta, Jaime

    2014-01-01

    Este trabajo reporta la emergencia, evolución y cosificación de algoritmos de predicción al modelar un fenómeno, en este caso el vaciado de un estanque cilíndrico, por modelos cuadráticos. La trayectoria que siguen este algoritmo se evidencia en el análisis de las producciones de profesores de matemáticas al participar en puestas en escena de un diseño de aprendizaje. Este análisis revela los procedimientos que siguen los actores, las herramientas con que actúan y los argumentos que esgrimen ...

  7. Algoritmo multiobjetivo NSGA-II aplicado al problema de la mochila

    OpenAIRE

    2008-01-01

    Este trabajo presenta la filosofía del algoritmo multiobjetivo elitista NSGA-II, explicando su esquema de funcionamiento y los mecanismos especiales que permiten la preservación y la evolución de soluciones Pareto-óptimas. Este algoritmo se aplica sobre el problema de optimización clásico correspondiente al problema de la mochila adaptado para optimización multiobjetivo. También se desarrolla una propuesta alternativa para ser comparada con el esquema básico del NSGA-II. This paper...

  8. Debilidad SAC en el algoritmo de cifrado en flujo RC4

    Directory of Open Access Journals (Sweden)

    Evaristo J. Madarro Capó

    2017-05-01

    Full Text Available En este trabajo se describe una interesante vía para la detección de la existencia de entradas de colisión en el algoritmo de cifrado en flujo RC4 basado en el criterio estricto de avalancha y se discuten los resultados obtenidos en comparación con las debilidades y ataques reportados sobre el RC4 que plantean la existencia de una fuerte correlación entre los parámetros de entrada y salida del algoritmo.

  9. PWR and BWR spent fuel assembly gamma spectra measurements

    Science.gov (United States)

    Vaccaro, S.; Tobin, S. J.; Favalli, A.; Grogan, B.; Jansson, P.; Liljenfeldt, H.; Mozin, V.; Hu, J.; Schwalbach, P.; Sjöland, A.; Trellue, H.; Vo, D.

    2016-10-01

    A project to research the application of nondestructive assay (NDA) to spent fuel assemblies is underway. The research team comprises the European Atomic Energy Community (EURATOM), embodied by the European Commission, DG Energy, Directorate EURATOM Safeguards; the Swedish Nuclear Fuel and Waste Management Company (SKB); two universities; and several United States national laboratories. The Next Generation of Safeguards Initiative-Spent Fuel project team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins, (3) estimate the plutonium mass, (4) estimate the decay heat, and (5) determine the reactivity of spent fuel assemblies. This study focuses on spectrally resolved gamma-ray measurements performed on a diverse set of 50 assemblies [25 pressurized water reactor (PWR) assemblies and 25 boiling water reactor (BWR) assemblies]; these same 50 assemblies will be measured with neutron-based NDA instruments and a full-length calorimeter. Given that encapsulation/repository and dry storage safeguards are the primarily intended applications, the analysis focused on the dominant gamma-ray lines of 137Cs, 154Eu, and 134Cs because these isotopes will be the primary gamma-ray emitters during the time frames of interest to these applications. This study addresses the impact on the measured passive gamma-ray signals due to the following factors: burnup, initial enrichment, cooling time, assembly type (eight different PWR and six different BWR fuel designs), presence of gadolinium rods, and anomalies in operating history. To compare the measured results with theory, a limited number of ORIGEN-ARP simulations were performed.

  10. Técnicas de Marca de Agua para Video MPEG usando Sensibilidad Visual y Vectores de Movimiento Video Watermarking Technique using Visual Sensibility and Motion Vector

    Directory of Open Access Journals (Sweden)

    Antonio Cedillo

    2008-01-01

    Full Text Available Se propone un algoritmo de marca de agua para video digital, en donde la inserción y detección de la marca de agua se realiza durante el proceso de codificación MPEG-2. La señal de marca de agua esta incrustada en los coeficientes de DCT en el canal azul de los cuadros I y P del video MPEG. La energía de la marca de agua se calcula usando la sensibilidad visual de los cuadros (I y P y la magnitud de los vectores de movimiento en los cuadros de P. Los resultados de simulación computacional muestran la imperceptibilidad de marca de agua, obteniendo un PSNR mayor a 45dB, conservando la robustez de la misma cuando es sometida a diversas distorsiones, tales como contaminación por ruido, recorte, y eliminación de cuadros, entre otros. El algoritmo propuesto tiene una influencia mínima en la velocidad del proceso de codificación MPEG.A video watermarking algorithm, in which watermark embedding and detection process are carried out during the MPEG-2 coding process is proposed. The watermark signal is embedded in the DCT coefficients of blue channel of I-frames and P-frames. The embedding energy is computed adaptively using perceptual information of the I-frames and the P-frames, and motion vectors information in the P-frame. Computer simulation results show the watermark imperceptibility, obtaining a PSNR greater than 45 dB and maintaining its robustness to common signal distortions such as contamination by noise, cropping, frame dropping, frame swapping and frame averaging, among others. The proposed algorithm has very little influence on the MPEG decoding speed.

  11. Estimação dos parâmetros do modelo do motor de indução usando o algoritmo Talus

    Directory of Open Access Journals (Sweden)

    Eurico Souza Filho Bezerra de

    2004-01-01

    Full Text Available In this paper, the algorithm Talus is applied to problem of parameter estimation of induction motor. The solution of the estimation problem is achieved minimizing a quadratic cost function. The data source used in the algorithm is the measured value of current end power in standard laboratory. The estimated parameters are compared with classical test (no-load and locked rotor either by simulation and experimentally

  12. Adaptive Beamforming for Moving Targets Using Genetic AlgorithmsFormación de Haz Adaptativo para Objetos Móviles usando Algoritmos Genéticos

    Directory of Open Access Journals (Sweden)

    Diego Fernando Burgos Beltrán

    2016-05-01

    Conclusions: The simulation results confirm that the GA is able to obtain a convergent and accurate tool for beamforming and tracking of moving targets, given a reference signal. Hence, GA turns to be promising in replacing LMS on Smart Antenna Systems for increasing channel capacity.

  13. Optimización en la solución del problema inverso en geofísica usando el algoritmo de entrenamiento supervisado de levenberg-marquardt

    OpenAIRE

    Figueredo Baez Yaqueline; Díaz Campos Ramiro León

    2012-01-01

    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.

  14. 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.

  15. Analysis of the behavior of irradiated BWR fuel rod in storage dry conditions; Analisis del comportamiento de una barra combustible irradiada BWR en condiciones de almacenamiento en seco

    Energy Technology Data Exchange (ETDEWEB)

    Munoz, A.; Montes, D.; Ruiz-Hervias, J.; Munoz-Reja, C.

    2014-07-01

    In order to complete previous studies of creep on PWR sheath material, developed a joint experimental program by CSN, ENRESA and ENUSA about BWR (Zircaloy-2) sheath material. This program consisted in creep tests and then on the material under creep, compression testing diametral obtaining the permissible displacement of the sheath to break. (Author)

  16. Desarrollo de un agente 3D con uso de algoritmos evolutivos y minería de datos

    OpenAIRE

    Reyes Santiago, Pedro Jesús

    2014-01-01

    En este Trabajo Fin de Grado se lleva a cabo la implementación de un mundo 3D a través del uso del entorno Unity en el se cual realizará el desarrollo de un agente 3D el cual interactúe con el entorno que le rodea. Para ello haremos uso de algoritmos relacionado con la inteligencia artificial así como aplicación de algoritmos relacionados con la minería de datos tales como redes neuronales basando su aprendizaje en algoritmos evolutivos o arboles de decisión, respectivamente. A...

  17. Mejoras a un Algoritmo Genético Simple, aplicando conceptos de Computación Evolutiva

    OpenAIRE

    Claudia Hurtado González; Beatriz Izquierdo Rivera; Marcela López Aguado Hernández; Armando Nicolás Cruz; Eduardo Gómez Ramírez

    2004-01-01

    Uno de los problemas con que se enfrentan los algoritmos evolutivos es la gran cantidad de tiempo que requieren para converger en la solución óptima. Por esta razón es muy importante el desarrollo de algoritmos que mejoren su desempeño. En este artículo se presenta una versión mejorada de Algoritmo Genético, así como la manera en que distintos parámetros internos, como mutaciónnúmero de padres afectan en la convergencia. Las pruebas propuestas se evaluaron estadísticamente, median...

  18. 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.

  19. 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.

  20. An A BWR demonstration simulator for training and developing technical staff

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Yonezawa, H.; Aoyagi, Y.; Kataoka, K., E-mail: jim.powers@toshiba.com [Toshiba Corporation, Kawasaki, Kanagawa (Japan)

    2015-09-15

    The US-Advanced Boiling Water Reactor (A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. Toshiba has developed a Demonstration Simulator of the A BWR control room that provides a realistic experience for training and education on BWR principles and operations fundamentals. The Demonstration Simulator is located in the Toshiba America Nuclear Energy (Tane) office in Charlotte, North Carolina and is composed of standard office computer equipment set up in a specific arrangement that is representative of the layout of an A BWR control room. The Demonstration Simulator is not intended for licensed operator training, but can provide a framework for encouraging entry level technically oriented nuclear workers to enter the operations field; strengthening the linkage between university energy field curricula and real-life application of theory; and, improving understanding of integrated plant operations for developing station technical staff. This paper describes the A BWR Demonstration Simulator and its applications for training and educating future nuclear workers. (Author)

  1. Key Parameters for Operator Diagnosis of BWR Plant Condition during a Severe Accident

    Energy Technology Data Exchange (ETDEWEB)

    Clayton, Dwight A [ORNL; Poore III, Willis P [ORNL

    2015-01-01

    The objective of this research is to examine the key information needed from nuclear power plant instrumentation to guide severe accident management and mitigation for boiling water reactor (BWR) designs (specifically, a BWR/4-Mark I), estimate environmental conditions that the instrumentation will experience during a severe accident, and identify potential gaps in existing instrumentation that may require further research and development. This report notes the key parameters that instrumentation needs to measure to help operators respond to severe accidents. A follow-up report will assess severe accident environmental conditions as estimated by severe accident simulation model analysis for a specific US BWR/4-Mark I plant for those instrumentation systems considered most important for accident management purposes.

  2. Effect of Control Blade History, and Axial Coolant Density and Burnup Profiles on BWR Burnup Credit

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, William BJ J [ORNL

    2016-01-01

    A technical basis for peak reactivity boiling water reactor (BWR) burnup credit (BUC) methods was recently generated, and the technical basis for extended BWR BUC is now being developed. In this paper, a number of effects related to extended BWR BUC are analyzed, including three major operational effects in BWRs: the coolant density axial distribution, the use of control blades during operation, and the axial burnup profile. Specifically, uniform axial moderator density profiles are analyzed and compared to previous results and an additional temporal fidelity study combing moderator density profiles for three different fuel assemblies is presented. Realistic control blade histories and cask criticality results are compared to previously generated constructed control blade histories. Finally, a preliminary study of the axial burnup profile is provided.

  3. A New Methodology for Early Anomaly Detection of BWR Instabilities

    Energy Technology Data Exchange (ETDEWEB)

    Ivanov, K. N.

    2005-11-27

    The objective of the performed research is to develop an early anomaly detection methodology so as to enhance safety, availability, and operational flexibility of Boiling Water Reactor (BWR) nuclear power plants. The technical approach relies on suppression of potential power oscillations in BWRs by detecting small anomalies at an early stage and taking appropriate prognostic actions based on an anticipated operation schedule. The research utilizes a model of coupled (two-phase) thermal-hydraulic and neutron flux dynamics, which is used as a generator of time series data for anomaly detection at an early stage. The model captures critical nonlinear features of coupled thermal-hydraulic and nuclear reactor dynamics and (slow time-scale) evolution of the anomalies as non-stationary parameters. The time series data derived from this nonlinear non-stationary model serves as the source of information for generating the symbolic dynamics for characterization of model parameter changes that quantitatively represent small anomalies. The major focus of the presented research activity was on developing and qualifying algorithms of pattern recognition for power instability based on anomaly detection from time series data, which later can be used to formulate real-time decision and control algorithms for suppression of power oscillations for a variety of anticipated operating conditions. The research being performed in the framework of this project is essential to make significant improvement in the capability of thermal instability analyses for enhancing safety, availability, and operational flexibility of currently operating and next generation BWRs.

  4. BWR/5 Pressure-Suppression Pool Response during an SBO

    Directory of Open Access Journals (Sweden)

    Javier Ortiz-Villafuerte

    2013-01-01

    Full Text Available RELAP/SCDAPSIM Mod 3.4 has been used to simulate a station blackout occurring at a BWR/5 power station. Further, a simplified model of a wet well and dry well has been added to the NSSS model to study the response of the primary containment during the evolution of this accident. The initial event leading to severe accident was considered to be a LOOP with simultaneous scram. The results show that RCIC alone can keep the core fully covered, but even in this case about 30% of the original liquid water inventory in the PSP is vaporized. During the SBO, without RCIC, this inventory is reduced about 5% more within six hours. Further, a significant pressure rise occurs in containment at about the time when a sharp increase of heat generation occurs in RPV due to cladding oxidation. Failure temperature of fuel clad is also reached at this point. As the accident progresses, conditions for containment venting can be reached in about nine hours, although there still exists considerable margin before reaching containment design pressure. Detailed information of accident progress in reactor vessel and containment is presented and discussed.

  5. A New Methodology for Early Anomaly Detection of BWR Instabilities

    Energy Technology Data Exchange (ETDEWEB)

    Ivanov, K. N.

    2005-11-27

    The objective of the performed research is to develop an early anomaly detection methodology so as to enhance safety, availability, and operational flexibility of Boiling Water Reactor (BWR) nuclear power plants. The technical approach relies on suppression of potential power oscillations in BWRs by detecting small anomalies at an early stage and taking appropriate prognostic actions based on an anticipated operation schedule. The research utilizes a model of coupled (two-phase) thermal-hydraulic and neutron flux dynamics, which is used as a generator of time series data for anomaly detection at an early stage. The model captures critical nonlinear features of coupled thermal-hydraulic and nuclear reactor dynamics and (slow time-scale) evolution of the anomalies as non-stationary parameters. The time series data derived from this nonlinear non-stationary model serves as the source of information for generating the symbolic dynamics for characterization of model parameter changes that quantitatively represent small anomalies. The major focus of the presented research activity was on developing and qualifying algorithms of pattern recognition for power instability based on anomaly detection from time series data, which later can be used to formulate real-time decision and control algorithms for suppression of power oscillations for a variety of anticipated operating conditions. The research being performed in the framework of this project is essential to make significant improvement in the capability of thermal instability analyses for enhancing safety, availability, and operational flexibility of currently operating and next generation BWRs.

  6. A methodology for obtaining the control rods patterns in a BWR using systems based on ants colonies; Una metodologia para obtener los patrones de barras de control en un BWR usando sistemas basados en colonias de hormigas

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz S, J.J. [Depto. de Sistemas Nucleares, ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico); Requena R, I. [Universidad de Granada, 18071 Granada (Spain)]. e-mail: jjortiz@nuclear.inin.mx

    2003-07-01

    In this work the AZCATL-PBC system based on a technique of ants colonies for the search of control rods patterns of those reactors of the Nuclear Power station of Laguna Verde (CNLV) is presented. The technique was applied to a transition cycle and one of balance. For both cycles they were compared the k{sub ef} values obtained with a Haling calculation and the control rods pattern proposed by AZCATL-PBC for a burnt one fixed. It was found that the methodology is able to extend the length of the cycle with respect to the Haling prediction, maintaining sure to the reactor. (Author)

  7. Validation of SCALE (SAS2H) Isotopic Predictions for BWR Spent Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Hermann, O.W.

    1998-01-01

    Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been modeled at Oak Ridge National Laboratory using the SAS2H sequence of the SCALE code system. The SAS2H sequence uses transport methods combined with the depletion and decay capabilities of the ORIGEN-S code to estimate the isotopic composition of fuel as a function of its burnup history. Results of these calculations are compared with chemical assay measurements of spent fuel inventories for each sample. Results show reasonable agreement between measured and predicted isotopic concentrations for important actinides; however, little data are available for most fission products considered to be important for spent fuel concerns (e.g., burnup credit, shielding, source-term calculations, etc.). This work is a follow-up to earlier works that studied the ability to predict spent fuel compositions in pressurized-water-reactor (PWR) fuel pins. Biases and uncertainties associated with BWR isotopic predictions are found to be larger than those of PWR calculations. Such behavior is expected, as the operation of a BWR is significantly more complex than that of a PWR plant, and in general the design of a BWR has a more heterogeneous configuration than that of a PWR. Nevertheless, this work shows that the simple models employed using SAS2H to represent such complexities result in agreement to within 5% (and often less than 1%) or less for most nuclides important for spent fuel applications. On the other hand, however, the set of fuel samples analyzed represent a small subset of the BWR fuel population, and results reported herein may not be representative of the full population of BWR spent fuel.

  8. Validation of SCALE (SAS2H) isotopic predictions for BWR spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Hermann, O.W.; DeHart, M.D.

    1998-09-01

    Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been modeled at Oak Ridge National Laboratory using the SAS2H sequence of the SCALE code system. The SAS2H sequence uses transport methods combined with the depletion and decay capabilities of the ORIGEN-S code to estimate the isotopic composition of fuel as a function of its burnup history. Results of these calculations are compared with chemical assay measurements of spent fuel inventories for each sample. Results show reasonable agreement between measured and predicted isotopic concentrations for important actinides; however, little data are available for most fission products considered to be important for spent fuel concerns (e.g., burnup credit, shielding, source-term calculations, etc.). This work is a follow-up to earlier works that studied the ability to predict spent fuel compositions in pressurized-water-reactor (PWR) fuel pins. Biases and uncertainties associated with BWR isotopic predictions are found to be larger than those of PWR calculations. Such behavior is expected, as the operation of a BWR is significantly more complex than that of a PWR plant, and in general the design of a BWR has a more heterogeneous configuration than that of a PWR. Nevertheless, this work shows that the simple models employed using SAS2H to represent such complexities result in agreement to within 5% (and often less than 1%) or less for most nuclides important for spent fuel applications. On the other hand, however, the set of fuel samples analyzed represent a small subset of the BWR fuel population, and results reported herein may not be representative of the full population of BWR spent fuel.

  9. APLICACIÓN DEL ALGORITMO EVOLUTIVO NSGAII EN LA UBICACIÓN DE CENTRALES TELEFÓNICAS EN UNÁREA GEOGRÁFICA DETERMINADA // APPLICATION OF EVOLUTIONARY ALGORITHM ON THE LOCATION OF NSGAII TELEPHONE EXCHANGES IN A GIVEN GEOGRAPHIC AREA

    Directory of Open Access Journals (Sweden)

    Clavel Quintana

    2010-06-01

    Full Text Available Almeida, Amarilla y Barán estudiaron el problema de minimización multiobjetivo de costo a corto, mediano y largo plazo para la ubicación de centrales telefónicas en la ciudad de la Asunción, Paraguay, determinando el número de centrales y la ubicación ´optima de estas centrales usando el algoritmo evolutivo SPEAII. Proponemos en este trabajo aplicar el algoritmo evolutivo NSGAII al problema de ubicar centrales telefónicas en Cabudare, Estado Lara, Venezuela; demostrando que constituye una opción valida para abordar el problema multiobjetivo. // Abstract: Almeida, Amarilla and Baran studied the problem of cost-minimization multi-objective in short, medium and long term for the location of telephone exchanges in the city of Asuncion, Paraguay, determining the number of central and convenient location of these plants SPEAII using evolutionary algorithm. We propose in this paper to apply the evolutionary algorithm NSGAII the problem of locating telephone exchanges in Cabudare, Estado Lara, Venezuela; demonstrating that an option to address multiobjective problems.

  10. 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.

  11. AREVA solutions to licensing challenges in PWR and BWR reload and safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Curca-Tivig, Florin [AREVA GmbH, Erlangen (Germany)

    2016-05-15

    Regulatory requirements for reload and safety analyses are evolving: new safety criteria, request for enlarged qualification databases, statistical applications, uncertainty propagation.. In order to address these challenges and access more predictable licensing processes, AVERA is implementing consistent code and methodology suites for PWR and BWR core design and safety analysis, based on first principles modeling and extremely broad verification and validation data base. Thanks to the high computational power increase in the last decades methods' development and application now include new capabilities. An overview of the main AREVA codes and methods developments is given covering PWR and BWR applications in different licensing environments.

  12. Identification of the reduced order models of a BWR reactor; Identificacion de modelos de orden reducido de un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez S, A. [UNAM, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, DEPFI, Campus Morelos, en IMTA Jiutepec, Morelos (Mexico)]. e-mail: augusto@correo.unam.mx

    2004-07-01

    The present work has as objective to analyze the relative stability of a BWR type reactor. It is analyzed that so adaptive it turns out to identify the parameters of a model of reduced order so that this it reproduces a condition of given uncertainty. This will take of a real fact happened in the La Salle plant under certain operation conditions of power and flow of coolant. The parametric identification is carried out by means of an algorithm of recursive least square and an Output Error model (Output Error), measuring the output power of the reactor when the instability is present, and considering that it is produced by a change in the reactivity of the system in the same way that a sign of type step. Also it is carried out an analytic comparison of the relative stability, analyzing two types of answers: the original answer of the uncertainty of the reactor vs. the obtained response identifying the parameters of the model of reduced order, reaching the conclusion that it is very viable to adapt a model of reduced order to study the stability of a reactor, under the only condition to consider that the dynamics of the reactivity is of step type. (Author)

  13. Design of a redundant meteorological station for a BWR reactor; Diseno de una estacion meteorologica redundante para un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, R.; Celis del Angel, L.; Bucio, F.; Rivero, T.; Palacios, J. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: ramses@nuclear.inin.mx

    2008-07-01

    In this work the design of a meteorological station for a reactor type BWR is proposed. Two independent channels of data acquisition that allow him to have a bigger readiness is exposed. It is incorporate sensors without mobile parts to measure speed, wind direction and pluvial precipitation. It also counts, with sensors of global solar radiation, net radiation, barometric pressure, relative humidity and ambient temperature; with them they are possible to be calculated, moreover, other variables as temperature differential, dew point and atmospheric stability. The sensors are placed on a tower to different heights and send their information (each second) to a local registration system, the one which in turn, it remits the data to the monitoring office so that a computer is linked with the system, display and management the information in real time and automatic way. The redundant structure allows that in the event of maintenance the data acquisition is not interrupted, even if the information is transferred to another place. In all the station sections it is used protocols of standard communication to allow that a great quantity of devices can be connected without major problem. The above-mentioned would allow to the operators in the control room to have reliable information during the whole time of the reactor operation. (Author)

  14. Reconocimiento de Huellas Dactilares Usando Características Locales

    Directory of Open Access Journals (Sweden)

    Gualberto Aguilar

    2008-01-01

    Full Text Available El reconocimiento de huellas dactilares es uno de los métodos más populares usados con mayor grado de éxito para la identificación de personas. La huella dactilar tiene características únicas llamadas minucias, las cuales son puntos donde los bordes terminan o se dividen. Los sistemas de identificación que usan patrones biométricos de huella dactilar se denominan AFIS (Sistema de Identificación Automático de Huella Dactilar. En este trabajo se realizó un sistema para reconocimiento de huella dactilar usando combinación de Transformada Rápida de Fourier (FFT con Filtros de Gabor para aclarar la imagen y después un novedoso método para el reconocimiento usando características locales.

  15. Identification and control of electromechanical systems by jeans of a neural multimodel; Identificacion y control de sistemas electromecanicos usando un multimodelo neuronal

    Energy Technology Data Exchange (ETDEWEB)

    Baruch, Ieroham [Instituto Politecnico Nacional, Mexico D.F. (Mexico); Beltran Lopez, Rafael [Becario del CONACY-Mexico, D.F. (Mexico); Gortcheva, Elena [Instituto Politecnico Nacional, Mexico D.F. (Mexico)

    2004-07-15

    A Recurrent Trainable Neural Network (Rant) and dynamic backpropagation learning are implemented in the control of complex nonlinear plants. In the present paper, a neural multimodel, composed by two Rants, is used. The control schemes proposed are an indirect and a direct adaptive trajectory tracking control, using states and parameters, issued by a neural multimodel identifier. Both control schemes are applied to control a continuous-time model of electromechanical system with friction and backlash, obtaining a good simulation results, confirmed also by convergent experimental results, using a DC motor. [Spanish] Una red neuronal recurrente entrenable (RNRE) y un algoritmo de retropropagacion dinamica como metodo de aparendizaje, son implementados para control de plantas no lineales complejas. En el presente trabajo se usa un multimodelo neuronal, el cual esta compuesto de dos RNRE. Los esquemas de control neuronal propuestos son: control indirecto y directo adaptable, usando los estados y los parametros proporcionados por un multimodelo de identificacion. Ambos sistemas de control son aplicados a un modelo continuo de un sistema electromecanico con friccion y efecto backlash en la salida, obteniendo buenos resultados en la simulacion y tambien confirmados con resultados experimentales convergentes, obtenidos con un motor de CD.

  16. 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.

  17. Búsqueda de algoritmos cuánticamente no Turning-computables

    OpenAIRE

    Ballesteros del Val, José Luis

    2017-01-01

    La computación cuántica constituye una de las líneas de investigación principales, tanto en física, por su parte experimental, centrada en la implementación, como en informática teórica y ciencias de la computación, por su parte teórica, centrada en el diseño de algoritmos. Esta realiza aportaciones fundamentales tanto en la reducción de complejidad en la resolución de algoritmos, asunto que se trata en el presente escrito, as como da pie al planteamiento de problemas de índ...

  18. Algoritmo memético con operadores de inteligencia artificial para el CARP con inicio y fin no determinado y bi-objetivo

    National Research Council Canada - National Science Library

    B J Macías; C A Amaya

    2016-01-01

    ... y minimizar el costo total. Adicionalmente se propone complementar la heurística, la cual es basada en algoritmos genéticos, con operadores de inteligencia artificial. Palabras clave: algoritmo genético; algoritmo memético; optimización multiobjetivo; CARP; OCARP; MO-OCARP; redes neuronales; búsqueda local; ruteo de vehículos sobre arcos. Hybrid Algorithm...

  19. Comparación entre algoritmos recursivos e iterativos y su medición en términos de eficiencia

    Directory of Open Access Journals (Sweden)

    Juan de Dios Murillo Morera

    2013-03-01

    Full Text Available Se llevarán a cabo comparaciones simples entre algoritmos recursivos e iterativos, para determinar el grado de eficiencia de un problema en particular. Se efectuaron pruebas de comparación y análisis utilizando tres ejemplos en ambos tipos de algoritmos, a los cuales se les aplicaron los criterios de análisis de algoritmos

  20. Applied methods for mitigation of damage by stress corrosion in BWR type reactors; Metodos aplicados para la mitigacion del dano por corrosion bajo esfuerzo en reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez C, R.; Diaz S, A.; Gachuz M, M.; Arganis J, C. [Instituto Nacional de Investigaciones Nucleares, Gerencia de Ciencia de Materiales, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1998-07-01

    The Boiling Water nuclear Reactors (BWR) have presented stress corrosion problems, mainly in components and pipes of the primary system, provoking negative impacts in the performance of energy generator plants, as well as the increasing in the radiation exposure to personnel involucred. This problem has caused development of research programs, which are guided to find solution alternatives for the phenomena control. Among results of greater relevance the control for the reactor water chemistry stands out particularly in the impurities concentration and oxidation of radiolysis products; as well as the supervision in the materials selection and the stresses levels reduction. The present work presents the methods which can be applied to diminish the problems of stress corrosion in BWR reactors. (Author)

  1. Algoritmo para coordinar exclusión mutua y concurrencia de grupos de procesos

    OpenAIRE

    Cenci, Karina M.; Ardenghi, Jorge Raúl

    2002-01-01

    Las aplicaciones distribuidas están formadas por un conjunto de procesos, los cuales pueden competir por utilizar un recurso o trabajar en forma conjunta para resolver una tarea. Estas aplicaciones requieren protocolos que permitan concurrencia entre los procesos que trabajan cooperativamente y exclusión mutua para aquellos que compiten por utilizar el recurso. En este trabajo se presenta un algoritmo que permite que grupos utilicen el recurso, donde cada uno de los grupos está integrado p...

  2. THERMAL EVALUATION OF THE USE OF BWR MOX SNF IN THE WASTE PACKAGE DESIGN (SCPB: N/A)

    Energy Technology Data Exchange (ETDEWEB)

    H. Wang

    1997-01-23

    This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8,4-11,4-24, 5-1, and 5-13; Ref. 5.10) and Waste Package Plan (pp. 3-15,3-17, and 3-24; Ref. 5.9). The design data request addressed herein is: (1) Characterize the conceptual 40 BWR and 24 BWR Multi-Purpose Canister (MPC) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. (2) Characterize the conceptual 44 BWR and 24 BWR Uncanistered Fuel (UCF) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. The purpose of this analysis is to respond to a concern that the long-term disposal thermal issues for the WP Design, if used with SNF designed for a MOX fuel cycle, do not preclude WP compatibility with the MGDS. The objective of this analysis is to provide thermal parameter information for the conceptual WP design with disposal container which is loaded with BWR MOX SNF under nominal MGDS repository conditions. The results are intended to show that the design has a reasonable chance to meet the MGDS design requirements for normal MGDS operation, and to provide the required guidance to determining the major design issues for future design efforts, and to show that the BWR MOX SNF loaded WP performance is similar to an WP loaded with commercial BWR SNF.

  3. Minor Actinides Loading Optimization for Proliferation Resistant Fuel Design - BWR

    Energy Technology Data Exchange (ETDEWEB)

    G. S. Chang; Hongbin Zhang

    2009-09-01

    One approach to address the United States Nuclear Power (NP) 2010 program for the advanced light water reactor (LWR) (Gen-III+) intermediate-term spent fuel disposal need is to reduce spent fuel storage volume while enhancing proliferation resistance. One proposed solution includes increasing burnup of the discharged spent fuel and mixing minor actinide (MA) transuranic nuclides (237Np and 241Am) in the high burnup fuel. Thus, we can reduce the spent fuel volume while increasing the proliferation resistance by increasing the isotopic ratio of 238Pu/Pu. For future advanced nuclear systems, MAs are viewed more as a resource to be recycled, and transmuted to less hazardous and possibly more useful forms, rather than simply disposed of as a waste stream in an expensive repository facility. MAs play a much larger part in the design of advanced systems and fuel cycles, not only as additional sources of useful energy, but also as direct contributors to the reactivity control of the systems into which they are incorporated. A typical boiling water reactor (BWR) fuel unit lattice cell model with UO2 fuel pins will be used to investigate the effectiveness of adding MAs (237Np and/or 241Am) to enhance proliferation resistance and improve fuel cycle performance for the intermediate-term goal of future nuclear energy systems. However, adding MAs will increase plutonium production in the discharged spent fuel. In this work, the Monte-Carlo coupling with ORIGEN-2.2 (MCWO) method was used to optimize the MA loading in the UO2 fuel such that the discharged spent fuel demonstrates enhanced proliferation resistance, while minimizing plutonium production. The axial averaged MA transmutation characteristics at different burnup were compared and their impact on neutronics criticality and the ratio of 238Pu/Pu discussed.

  4. Numerical simulation of boron injection in a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Tinoco, Hernan, E-mail: htb@forsmark.vattenfall.s [Forsmarks Kraftgrupp AB, SE-742 03 Osthammar (Sweden); Buchwald, Przemyslaw [Reactor Technology, Royal Institute of Technology, SE-100 44 Stockholm (Sweden); Frid, Wiktor, E-mail: wiktor@reactor.sci.kth.s [Reactor Technology, Royal Institute of Technology, SE-100 44 Stockholm (Sweden)

    2010-02-15

    The present study constitutes a first step to understand the process of boron injection, transport and mixing in a BWR. It consists of transient CFD simulations of boron injection in a model of the downcomer of Forsmark's Unit 3 containing about 6 million elements. The two cases studied are unintentional start of boron injection under normal operation and loss of offsite power with partial ATWS leaving 10% of the core power uncontrolled. The flow conditions of the second case are defined by means of an analysis with RELAP5, assuming boron injection start directly after the first ECCS injection. Recent publications show that meaningful conservative results may be obtained for boron or thermal mixing in PWRs with grids as coarse as that utilized here, provided that higher order discretization schemes are used to minimize numerical diffusion. The obtained results indicate an apparently strong influence of the scenario in the behavior of the injection process. The normal operation simulation shows that virtually all boron solution flows down to the Main Recirculation Pump inlet located directly below the boron inlet nozzle. The loss of offsite power simulation shows initially a spread of the boron solution over the entire sectional area of the lower part of the downcomer filled with colder water. This remaining effect of the ECCS injection lasts until all this water has left the downcomer. Above this region, the boron injection jet develops in a vertical streak, eventually resembling the injection of the normal operation scenario. Due to the initial spread, this boron injection will probably cause larger temporal and spatial concentration variations in the core. In both cases, these variations may cause reactivity transients and fuel damage due to local power escalation. To settle this issue, an analysis using an extended model containing the downcomer, the MRPs and the Lower Plenum will be carried out. Also, the simulation time will be extended to a scale of

  5. Propagation of cracks by stress corrosion in conditions of BWR type reactor; Propagacion de grietas por corrosion bajo esfuerzo en condiciones de reactor de agua en ebullicion (BWR)

    Energy Technology Data Exchange (ETDEWEB)

    Merino C, F.J. [ININ, 52045 Estado de Mexico (Mexico); Fuentes C, P. [ITT, Metepec, Estado de Mexico (Mexico)]. E-mail: fjmc@nuclear.inin.mx

    2004-07-01

    In this work, the obtained results when applying the Hydrogen Chemistry to a test tube type Compact Tension (CT), built in austenitic stainless steel 304l, simulating the conditions to those that it operates a Boiling Water Reactor (BWR), temperature 288 C and pressure of 8 MPa are presented. With the application of this water chemistry, seeks to be proven the diminution of the crack propagation speed. (Author)

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

    Directory of Open Access Journals (Sweden)

    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.

  7. 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.

  8. Algoritmo assistencial de enfermagem para infusão de amiodarona intravenosa

    Directory of Open Access Journals (Sweden)

    Francimar Tinoco de Oliveira

    2014-01-01

    Full Text Available Los objetivos fueron identificar publicaciones científicas sobre flebitis causado por amiodarona y proponer un algoritmo de atención de enfermería para intervenciones en la administración intravenosa de amiodarona, basada en la Infusion Nursing Society y Center for Disease Control and Prevention . Estudio descriptivo, llevado a cabo por revisión integradora en bases MedLine, LILACS, IBECS, BDENF, Biblioteca Cochrane y Scielo, publicados de 2006 a 2013. La muestra consistió de nueve artículos. Las evidencias señalaron incidencia de flebitis debido a la infusión de amiodarona y la necesidad de su control. El algoritmo propuesto nortea los materiales que deben ser utilizados y el procedimiento de administración del medicamento, objetivando minimizar agravios. Esto algoritmo, además de subsidiar el desarrollo de futuros estudios, también promueve la incorporación de mejores recomendaciones para la práctica clínica de forma intervencionista y legítima.

  9. Introducción a los algoritmos genéticos y sus aplicaciones

    Directory of Open Access Journals (Sweden)

    Piedad Tolmos Rodríguez-Piñero

    2002-01-01

    Full Text Available Los algoritmos genéticos son un logro más de la Inteligencia Artificial en su intento de replicar comportamientos biológicos, con los avances científicos que ello implica, mediante la computación. Se trata de algoritmos de búsqueda basados en la mecánica de la selección natural y de la genética. Utilizan la información histórica para encontrar nuevos puntos de búsqueda de una solución óptima del problema planteado, con esperanzas de mejorar los resultados. En el presente artículo se realizará una introducción a los Algoritmos Genéticos: qué son, de dónde proceden, y en qué difieren de otros métodos de búsqueda, comentándose, asimismo, sus aplicaciones principales.

  10. 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 ...

  11. Analysis CFD for the hydrogen transport in the primary containment of a BWR; Analisis CFD para el transporte de hidrogeno en la contencion primaria de un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez P, D. A.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Gomez T, A. M., E-mail: guerreroazteca_69@hotmail.com [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    This study presents a qualitative and quantitative comparison among the CFD GASFLOW and OpenFOAM codes which are related with the phenomenon of hydrogen transport and other gases in the primary containment of a Boiling Water Reactor (BWR). GASFLOW is a commercial license code that is well validated and that was developed in Germany for the analysis of the gases transport in containments of nuclear reactors. On the other hand, OpenFOAM is an open source code that offers several evaluation solvers for different types of phenomena; in this case, the solver reacting-Foam is used to analyze the hydrogen transport inside the primary containment of the BWR. The results that offer the solver reacting-Foam of OpenFOAM are evaluated in the hydrogen transport calculation and the results are compared with those of the program of commercial license GASFLOW to see if is viable the use of the open source code in the case of the hydrogen transport in the primary containment of a BWR. Of the obtained results so much quantitative as qualitative some differences were identified between both codes, the differences (with a percentage of maximum error of 4%) in the quantitative results are small and they are considered acceptable for this analysis type, also, these differences are attributed mainly to the used transport models, considering that OpenFOAM uses a homogeneous model and GASFLOW uses a heterogeneous model. (Author)

  12. Predictions by the proper orthogonal decomposition reduced order methodology regarding non-linear BWR stability

    Energy Technology Data Exchange (ETDEWEB)

    Prill, Dennis; Class, Andreas G. [Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany). AREVA Nuclear Professional School (ANPS)

    2013-07-01

    Unexpected non-linear boiling water reactor (BWR) instability events in various plants, e.g. LaSalle II in 1988 and Oskarshamn II in 1990 amongst others, emphasize the major safety relevance and the existence of parameter regions with unstable behavior. A detailed description of the complete dynamical non-linear behavior is of paramount importance for BWR operation. An extension of state-of-the-art methodology towards a more general stability description, also applicable in the non-linear region, could lead to a deeper understanding of non-linear BWR stability phenomena. With the intention of a full non-linear stability analysis of the two-phase BWR system, the present paper aims at a general non-linear methodology capable to achieve reliable and numerical stable reduced order models (ROMs), representing the dynamical behavior of an original system based on a small number of transients. Model-specific options and aspects of the proposed methodology are focused on and illustrated by means of a strongly non-linear dynamical system showing complex oscillating behavior. Prediction capability of the proposed methodology is also addressed. (orig.)

  13. Plutonium and Minor Actinides Recycling in Standard BWR using Equilibrium Burnup Model

    Directory of Open Access Journals (Sweden)

    Abdul Waris

    2008-03-01

    Full Text Available Plutonium (Pu and minor actinides (MA recycling in standard BWR with equilibrium burnup model has been studied. We considered the equilibrium burnup model as a simple time independent burnup method, which can manage all possible produced nuclides in any nuclear system. The equilibrium burnup code was bundled with a SRAC cell-calculation code to become a coupled cell-burnup calculation code system. The results show that the uranium enrichment for the criticality of the reactor, the amount of loaded fuel and the required natural uranium supply per year decrease for the Pu recycling and even much lower for the Pu & MA recycling case compared to those of the standard once-through BWR case. The neutron spectra become harder with the increasing number of recycled heavy nuclides in the reactor core. The total fissile rises from 4.77% of the total nuclides number density in the reactor core for the standard once-through BWR case to 6.64% and 6.72% for the Plutonium recycling case and the Pu & MA recycling case, respectively. The two later data may become the main basis why the required uranium enrichment declines and consequently diminishes the annual loaded fuel and the required natural uranium supply. All these facts demonstrate the advantage of plutonium and minor actinides recycling in BWR.

  14. Development and Testing of CTF to Support Modeling of BWR Operating Conditions

    Energy Technology Data Exchange (ETDEWEB)

    Salko, Robert K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wysocki, Aaron [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Collins, Benjamin S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Godfrey, Andrew T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gosdin, Chris [Pennsylvania State Univ., University Park, PA (United States); Avramova, Maria [North Carolina State Univ., Raleigh, NC (United States)

    2016-01-29

    This milestone supports developing and assessing COBRA-TF (CTF) for the modeling of boiling water reactors (BWRs). This is achieved in three stages. First, a new preprocessor utility that is capable of handling BWR-specic design elements (e.g., channel boxes and large water rods) is developed. A previous milestone (L3:PHI.CTF.P12.01) led to the development of this preprocessor capability for single assembly models. This current milestone expands this utility so that it is applicable to multi-assembly BWR models that can be modeled in either serial or parallel. The second stage involves making necessary modications to CTF so that it can execute these new models. Specically, this means implementing an outer-iteration loop, specic to BWR models, that equalizes the pressure loss over all assemblies in the core (which are not connected due to the channel boxes) by adjusting inlet mass ow rate. A third stage involves assessing the standard convergence metrics that are used by CTF to determine when a simulation is steady-state. The nal stage has resulted in the implementation of new metrics in the code that give a better indication of how steady the solution is at convergence. This report summarizes these eorts and provides a demonstration of CTF's BWR-modeling capabilities. CASL-U-2016-1030-000

  15. Signal analysis of acoustic and flow-induced vibrations of BWR main steam line

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa-Paredes, G., E-mail: gepe@xanum.uam.mx [División de Ciencias Básicas e Ingeniería, Universidad Autónoma Metropolitana-Iztapalapa, México, D.F. 09340 (Mexico); Prieto-Guerrero, A. [División de Ciencias Básicas e Ingeniería, Universidad Autónoma Metropolitana-Iztapalapa, México, D.F. 09340 (Mexico); Núñez-Carrera, A. [Comisión Nacional de Seguridad Nuclear y Salvaguardias, Doctor Barragán 779, Col. Narvarte, México, D.F. 03020 (Mexico); Vázquez-Rodríguez, A. [División de Ciencias Básicas e Ingeniería, Universidad Autónoma Metropolitana-Iztapalapa, México, D.F. 09340 (Mexico); Centeno-Pérez, J. [Instituto Politécnico Nacional, Escuela Superior de Física y Matemáticas Unidad Profesional “Adolfo López Mateos”, Av. IPN, s/n, México, D.F. 07738 (Mexico); Espinosa-Martínez, E.-G. [Departamento de Sistemas Energéticos, Universidad Nacional Autónoma de México, México, D.F. 04510 (Mexico); and others

    2016-05-15

    Highlights: • Acoustic and flow-induced vibrations of BWR are analyzed. • BWR performance after extended power uprate is considered. • Effect of acoustic side branches (ASB) is analyzed. • The ASB represents a reduction in the acoustic loads to the steam dryer. • Methodology developed for simultaneous analyzing the signals in the MSL. - Abstract: The aim of this work is the signal analysis of acoustic waves due to phenomenon known as singing in Safety Relief Valves (SRV) of the main steam lines (MSL) in a typical BWR5. The acoustic resonance in SRV standpipes and fluctuating pressure is propagated from SRV to the dryer through the MSL. The signals are analyzed with a novel method based on the Multivariate Empirical Mode Decomposition (M-EMD). The M-EMD algorithm has the potential to find common oscillatory modes (IMF) within multivariate data. Based on this fact, we implement the M-EMD technique to find the oscillatory mode in BWR considering the measurements obtained collected by the strain gauges located around the MSL. These IMF, analyzed simultaneously in time, allow obtaining an estimation of the effects of the multiple-SRV in the MSL. Two scenarios are analyzed: the first is the signal obtained before the installation of the acoustic dampers (ASB), and the second, the signal obtained after installation. The results show the effectiveness of the ASB to damp the strong resonances when the steam flow increases, which represents an important reduction in the acoustic loads to the steam dryer.

  16. Identification of dose-reduction techniques for BWR and PWR repetitive high-dose jobs

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Baum, J.W.

    1984-01-01

    As a result of concern about the apparent increase in collective radiation dose to workers at nuclear power plants, this project will provide information to industry in preplanning for radiation protection during maintenance operations. This study identifies Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) repetitive jobs, and respective collective dose trends and dose reduction techniques. 3 references, 2 tables. (ACR)

  17. Assessment of the Prony's method for BWR stability analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz-Villafuerte, Javier, E-mail: javier.ortiz@inin.gob.m [Gerencia de Ciencias Aplicadas, Instituto Nacional de Investigaciones Nucleares, Carr. Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Edo. Mexico 52750 (Mexico); Castillo-Duran, Rogelio, E-mail: rogelio.castillo@inin.gob.m [Gerencia de Ciencias Aplicadas, Instituto Nacional de Investigaciones Nucleares, Carr. Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Edo. Mexico 52750 (Mexico); Palacios-Hernandez, Javier C., E-mail: javier.palacios@inin.gob.m [Gerencia de Ciencias Aplicadas, Instituto Nacional de Investigaciones Nucleares, Carr. Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Edo. Mexico 52750 (Mexico)

    2011-05-15

    Highlights: This paper describes a method to determine the degree of stability of a BWR. Performance comparison between Prony's and common AR techniques is presented. Benchmark data and actual BWR transient data are used for comparison. DR and f results are presented and discussed. The Prony's method is shown to be a robust technique for BWR stability. - Abstract: It is known that Boiling Water Reactors are susceptible to present power oscillations in regions of high power and low coolant flow, in the power-flow operational map. It is possible to fall in one of such instability regions during reactor startup, since both power and coolant flow are being increased but not proportionally. One other possibility for falling into those areas is the occurrence of a trip of recirculation pumps. Stability monitoring in such cases can be difficult, because the amount or quality of power signal data required for calculation of the stability key parameters may not be enough to provide reliable results in an adequate time range. In this work, the Prony's Method is presented as one complementary alternative to determine the degree of stability of a BWR, through time series data. This analysis method can provide information about decay ratio and oscillation frequency from power signals obtained during transient events. However, so far not many applications in Boiling Water Reactors operation have been reported and supported to establish the scope of using such analysis for actual transient events. This work presents first a comparison of decay ratio and frequency oscillation results obtained by Prony's method and those results obtained by the participants of the Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark using diverse techniques. Then, a comparison of decay ratio and frequency oscillation results is performed for four real BWR transient event data, using Prony's method and two other techniques based on an autoregressive modeling. The four

  18. Flex concept for US-A BWR extended loss of AC power events

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Aoyagi, Y.; Kataoka, K. [Toshiba Corporation, Kawasaki, Kanagawa (Japan); Thomas, S.; Mookhoek, B., E-mail: jim.powers@toshiba.com [Nuclear Innovation North America, Lake Jackson, Texas (United States)

    2015-09-15

    The US-Advanced Boiling Water Reactor (US-A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (Stp 3 and 4) Combined License Application (Cola) and incorporates numerous design and technology enhancements for improved safety performance. Nuclear Innovation North America (NINA) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The Stp 3 and 4 project has finished the US NRC technical review of the Cola, and the final safety evaluation report (FSER) is scheduled to be issued by the US NRC in 2015. Following the accident at the Fukushima Dai-ichi plant, the US-A BWR was reviewed for Beyond Design Basis Event (BDBE) safety using industry and regulatory guidance for US NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation of Beyond Design Basis External Events (BDBEE). By virtue of the design approach, the US-A BWR is capable of providing an indefinite coping period for a station blackout. The use of installed systems with extended coping times is a significant advantage of the US-A BWR compared to most of the plants currently operating in the U.S. In addition, the Stp 3 and 4 design incorporates enhancements consistent with the current US industry Diverse and Flexible Coping Strategies (Flex) initiative. The final technical topic requiring review by the US NRC Advisory Committee on Reactor Safeguards was the Flex Integrated Plan submitted by NINA, and this review was successfully completed. This paper summarizes the progress of the US-A BWR in licensing the Flex Integrated Plan for the project, and describes the technology and features of the US-A BWR design that contribute to safety post-Fukushima. It also provides an informational comparison of the design capabilities of the US-A BWR for extreme external events, and relates these capabilities to re

  19. Axial profiles of burned and fraction of holes for calculations of criticality with credit for BWR fuel burning; Perfiles axiales de quemado y fraccion de huecos para calculos de criticidad con credito al quemado para combustible BWR

    Energy Technology Data Exchange (ETDEWEB)

    Casado Sanchez, C.; Rubio Oviedo, P.

    2014-07-01

    This paper presents a method to define surround profiles of burning and fraction of holes suited for use in applications of credit to burning of BWR fuel from results obtained with the module STARBUCS of SCALE. (Author)

  20. Validation and application of the system code ATHLET-CD for BWR severe accident analyses

    Energy Technology Data Exchange (ETDEWEB)

    Di Marcello, Valentino, E-mail: valentino.marcello@kit.edu; Imke, Uwe; Sanchez, Victor

    2016-10-15

    Highlights: • We present the application of the system code ATHLET-CD code for BWR safety analyses. • Validation of core in-vessel models is performed based on KIT CORA experiments. • A SB-LOCA scenario is simulated on a generic German BWR plant up to vessel failure. • Different core reflooding possibilities are investigated to mitigate the accident consequences. • ATHLET-CD modelling features reflect the current state of the art of severe accident codes. - Abstract: This paper is aimed at the validation and application of the system code ATHLET-CD for the simulation of severe accident phenomena in Boiling Water Reactors (BWR). The corresponding models for core degradation behaviour e.g., oxidation, melting and relocation of core structural components are validated against experimental data available from the CORA-16 and -17 bundle tests. Model weaknesses are discussed along with needs for further code improvements. With the validated ATHLET-CD code, calculations are performed to assess the code capabilities for the prediction of in-vessel late phase core behaviour and reflooding of damaged fuel rods. For this purpose, a small break LOCA scenario for a generic German BWR with postulated multiple failures of the safety systems was selected. In the analysis, accident management measures represented by cold water injection into the damaged reactor core are addressed to investigate the efficacy in avoiding or delaying the failure of the reactor pressure vessel. Results show that ATHLET-CD is applicable to the description of BWR plant behaviour with reliable physical models and numerical methods adopted for the description of key in-vessel phenomena.

  1. Aplicación de un Algoritmo Evolutivo en la Solución de Problemas Job Shop-Open Shop Application of an Evolutionary Algorithm to solve Job Shop-Open Shop Problems

    Directory of Open Access Journals (Sweden)

    Omar D Castrillón

    2011-01-01

    Full Text Available El objetivo del trabajo que se presenta fue disminuir el tiempo de proceso y el tiempo muerto, y aumentar la utilización de las máquinas, en un ambiente Job Shop-Open Shop, usando una nueva metodología basada en un algoritmo evolutivo. El estudio se realizó en una empresa del sector metalmecánico. La metodología propuesta es fácil de replicar y los resultados obtenidos son altamente consistentes, como se demuestra con un análisis de varianza realizado. Con la metodología propuesta se logró reducir el tiempo total de proceso en un 33% y el tiempo muerto en un 51% con una aproximación del 99%, respecto a la solución óptima estimada.The aim of the work presented in this paper was to reduce makespan time and idle time, and to increase machine utilization, in Job Shop-Open Shop environment, using a new methodology based on evolutionary algorithms. The study was done in an enterprise of the metal-mechanics sector. The proposed methodology is easy to implement and apply and the results are highiy consistent, as shown by a variance analysis. The methodology allows reducing the total processing time by 33% and idle time by 51 % with 99% approximation with respect to the optimum solution.

  2. Filtrado de imágenes usando hardware dedicado

    OpenAIRE

    Acosta, Nelson; Tosini, Marcelo Alejandro

    2004-01-01

    Este artículo propone el diseño de una arquitectura dedicada para el procesamiento de imágenes. Se presenta el ciclo de desarrollo, en el cual el punto de partida es la implementación de la solución software, la que es migrada a VHDL para las etapas de simulación y síntesis. El funcionamiento y rendimiento del método fueron verificados usando Synopsys VHDL y simulaciones de computadora.

  3. Current and anticipated use of thermal-hydraulic codes for BWR transient and accident analyses in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Arai, Kenji; Ebata, Shigeo [Toshiba Corp., Yokohama (Japan)

    1997-07-01

    This paper summarizes the current and anticipated use of the thermal-hydraulic and neutronic codes for the BWR transient and accident analyses in Japan. The codes may be categorized into the licensing codes and the best estimate codes for the BWR transient and accident analyses. Most of the licensing codes have been originally developed by General Electric. Some codes have been updated based on the technical knowledge obtained in the thermal hydraulic study in Japan, and according to the BWR design changes. The best estimates codes have been used to support the licensing calculations and to obtain the phenomenological understanding of the thermal hydraulic phenomena during a BWR transient or accident. The best estimate codes can be also applied to a design study for a next generation BWR to which the current licensing model may not be directly applied. In order to rationalize the margin included in the current BWR design and develop a next generation reactor with appropriate design margin, it will be required to improve the accuracy of the thermal-hydraulic and neutronic model. In addition, regarding the current best estimate codes, the improvement in the user interface and the numerics will be needed.

  4. Impact in long-term planning of optimization algorithms and mineral deposit geometry Impacto de diferentes algoritmos e geometria de depósitos minerais no planejamento de longo prazo

    Directory of Open Access Journals (Sweden)

    Mateus Toniolo Candido

    2013-03-01

    engenheiro de projeto ou, simplesmente, por disponibilidade. Além disso, variações nos aspectos técnicos e geométricos do projeto podem ser impostas provocando diferenças nos resultados. Existem muitos algoritmos implementados em diversos programas comerciais para o cálculo da cava final e sequenciamento de longo prazo, e, por isso, um dos objetivos desse trabalho é verificar a eficácia dos algoritmos que obtiveram maior reconhecimento dentro da indústria mineral e verificar se existem diferenças relacionadas com o tipo de mineralização e depósito onde eles são aplicados. A comparação é realizada usando dois programas comerciais e dois algoritmos diferentes para determinar se as diferenças podem ser observadas para tipos de mineralização distintos. A aplicação da metodologia foi executada em modelos de blocos tridimensionais estimados e os resultados analisados para os três tipos de depósitos: um corpo de minério de cobre disseminado, um grande depósito de fosfato de origem ígnea e uma mineralização aurífera, de espessura pequena relativamente à extensão em profundidade, apresentando um mergulho subvertical.

  5. Design and axial optimization of nuclear fuel for BWR reactors; Diseno y optimizacion axial de combustible nuclear para reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Garcia V, M.A

    2006-07-01

    In the present thesis, the modifications made to the axial optimization system based on Tabu Search (BT) for the axial design of BWR fuel type are presented, developed previously in the Nuclear Engineering Group of the UNAM Engineering Faculty. With the modifications what is mainly looked is to consider the particular characteristics of the mechanical design of the GE12 fuel type, used at the moment in the Laguna Verde Nucleo electric Central (CNLV) and that it considers the fuel bars of partial longitude. The information obtained in this thesis will allow to plan nuclear fuel reloads with the best conditions to operate in a certain cycle guaranteeing a better yield and use in the fuel burnt, additionally people in charge in the reload planning will be favored with the changes carried out to the system for the design and axial optimization of nuclear fuel, which facilitate their handling and it reduces their execution time. This thesis this developed in five chapters that are understood in the following way in general: Chapter 1: It approaches the basic concepts of the nuclear energy, it describes the physical and chemical composition of the atoms as well as that of the uranium isotopes, the handling of the uranium isotope by means of the nuclear fission until arriving to the operation of the nuclear reactors. Chapter 2: The nuclear fuel cycle is described, the methods for its extraction, its conversion and its enrichment to arrive to the stages of the nuclear fuel management used in the reactors are described. Beginning by the radial design, the axial design and the core design of the nuclear reactor related with the fuel assemblies design. Chapter 3: the optimization methods of nuclear fuel previously used are exposed among those that are: the genetic algorithms method, the search methods based on heuristic rules and the application of the tabu search method, which was used for the development of this thesis. Chapter 4: In this part the used methodology to the

  6. Aplicación de algoritmos genéticos en la planificación de redes de telefonia celular

    OpenAIRE

    Figueroa de la Cruz, Mario M.; Zakour, José; Juarez, Gustavo; Ibarra, Daniel

    2007-01-01

    Este trabajo analiza la problemática que tiene la planificación celular considerando el crecimiento y la evolución hacia nuevas tecnologías proponiendo como alternativa de planificación el uso de algoritmos de Inteligencia Artificial como son los Algoritmos Genéticos.

  7. Coolant Density and Control Blade History Effects in Extended BWR Burnup Credit

    Energy Technology Data Exchange (ETDEWEB)

    Ade, Brian J [ORNL; Marshall, William BJ J [ORNL; Bowman, Stephen M [ORNL; Gauld, Ian C [ORNL; Ilas, Germina [ORNL; Martinez-Gonzalez, Jesus S [ORNL

    2015-01-01

    Oak Ridge National Laboratory and the US Nuclear Regulatory Commission have initiated a multiyear project to investigate the application of burnup credit (BUC) for boiling water reactor (BWR) fuel in storage and transportation casks. This project includes two phases. The first phase investigates the applicability of peak reactivity methods currently used for spent fuel pools to spent fuel storage and transportation casks and the validation of reactivity (keff) calculations and predicted spent fuel compositions. The second phase focuses on extending BUC beyond peak reactivity. This paper documents work performed to date investigating some aspects of extended BUC. (The technical basis for application of peak reactivity methods to BWR fuel in storage and transportation systems is presented in a companion paper.) Two reactor operating parameters are being evaluated to establish an adequate basis for extended BWR BUC: (1) the effect of axial void profile and (2) the effect of control blade utilization during operation. A detailed analysis of core simulator data for one cycle of a modern operating BWR plant was performed to determine the range of void profiles and the variability of the profile experienced during irradiation. Although a single cycle does not provide complete data, the data obtained are sufficient to determine the primary effects and to identify conservative modeling approaches. These data were used in a study of the effect of axial void profile. The first stage of the study was determination of the necessary moderator density temporal fidelity in depletion modeling. After the required temporal fidelity was established, multiple void profiles were used to examine the effect on cask reactivity. The results of these studies are being used to develop recommendations for conservatively modeling the void profile effects for BWR depletion calculations. The second operational parameter studied was control blade history. Control blades are inserted in

  8. MLRul: un algoritmo para la generación de reglas borrosas para la clasificación

    Directory of Open Access Journals (Sweden)

    Pedro R. Piñero

    2011-10-01

    Full Text Available En este trabajo se investiga acerca de las técnicas del soft computing y sus potencialidades en el aprendizaje automático y la clasificación. Se presenta un nuevo algoritmo MLRul que permite aprender y generalizar en forma de reglas borrosas del tipo Sugeno grado cero el conocimiento implícito en bases de casos. Para la prueba del algoritmo se presenta el sistema MLClassif version 1.0 que implementa el algoritmo y un módulo que posibilita la explotación de la base de reglas generadas por MLRul. Se comparan los resultados experimentales de aplicar MLClassif con reglas generadas por MLRul con otros sistemas clasificadores sobre bases de datos publicadas en el repositorio de aprendizaje automático de la Universidad de California Irvine.

  9. Flujo de potencia óptimo usando el método del gradiente para reducción de pérdidas en sistemas de potencia Optimal power flow using the gradient method to reduce electrical losses in power systems

    Directory of Open Access Journals (Sweden)

    Jesús María López Lezama

    2008-06-01

    Full Text Available En este artículo se presenta un modelo de flujo de potencia óptimo por elmétodo del gradiente para la reducción de pérdidas en sistemas de potencia.El algoritmo permite ajustar un conjunto de variables de control con el finde obtener un punto de operación que minimice las pérdidas de potencia activa.El método se basa en la solución del flujo de potencia por el método deNewton. Los límites de las variables independientes son manejados mediantefunciones de penalidad. El desempeño del algoritmo es evaluado usando dosmétodos diferentes para calcular el tamaño del paso a lo largo de la direcciónfactible: un paso constante y un paso variable usando el método de ajuste depar´abola.This paper presents an optimal power flow model using the gradient method for the reduction of losses in power systems. The algorithm allows adjusting a set of control variables to find an operation point that minimizes active power losses. The method is based on the power flow solution by Newton’s method. Limits on idependent variables are handled using penalty functions. The algorithm performance is tested using two different approaches to calculate the step size along the feasible direction: a constant step size and a variable step size using the parable adjustment method.

  10. Optimización multiobjetivo en redes ópticas con transmisión Multicast, utilizando algoritmos evolutivos y lógica difusa

    Directory of Open Access Journals (Sweden)

    Luis Tovar

    2007-01-01

    Full Text Available En el presente artículo se desarrolla un modelo analítico difuso, el cual resuelve un problema multiobjetivo en transmisión multicast con árboles estáticos sobre redes GMPLS. Para ello, se utilizó como base el modelo propuesto en Donoso [4]. El problema multiobjetivo planteado se soluciona mediante metaheurística con algoritmos evolutivos, específicamente el SPEA2, resolviendo un problema NP-Hard en tiempo polinomial. Adicionalmente, se implementa un algoritmo evolutivo difuso, basado en el algoritmo evolutivo SPEA2, para resolver el modelo desarrollado. Por último, se analiza el comportamiento del algoritmo propuesto (FSPEA2 frente al algoritmo original (SPEA2 y se presentan las respectivas conclusiones

  11. Algoritmo de agregación de mappings basado en reglas de selección

    OpenAIRE

    Ramos, JA.; Fernández-López, M.; Gómez-Pérez, A.

    2009-01-01

    Los sistemas de integración de información resuelven las diferencias entre las fuentes, en la mayoría de los casos, mediante la creación de mappings, puentes semánticos entre los elementos de las fuentes. Hasta ahora se han propuesto técnicas para generar un conjunto de mappings para cada par de elementos de las fuentes a integrar, sin embargo, hasta la publicación del presente trabajo, no se disponía de un algoritmo de agregación público y general para distintos tipos de fuentes que permitie...

  12. Diabetes gestacional : um algoritmo de tratamento multidisciplinar=Gestational diabetes management: a multidisciplinary treatment algorithm

    OpenAIRE

    Weinert, Letícia Schwerz; Silveiro, Sandra Pinho; Oppermann, Maria Lúcia Rocha; Salazar, Cristiano Caetano; Simionato, Bárbara Marina; Siebeneichler, Aline Stalder; Reichelt, Angela de Azevedo Jacob

    2011-01-01

    O tratamento do diabetes gestacional é importante para evitar a morbimortalidade materno- -fetal. O objetivo deste artigo é descrever o tratamento atualmente disponível para o manejo otimizado da hiperglicemia na gestação e sugerir um algoritmo de tratamento multidisciplinar. A terapia nutricional é a primeira opção de tratamento para as gestantes, e a prática de exercício físico leve a moderado deve ser estimulada na ausência de contraindicações obstétricas. O tratamento medicamentoso está r...

  13. Identificación en lazo cerrado mediante algoritmos genéticos

    OpenAIRE

    Alfredo Gómez Infante; Abelardo del Pozo Quintero; Alberto Aguado Behar

    2010-01-01

    La identificación  en lazo cerrado de sistemas continuos es un problema de optimización no lineal que resulta de difícil solución mediante métodos convencionales.  En este trabajo se propone el uso de algoritmos genéticos (AG) para esta tarea y se muestra mediante simulaciones que los modelos obtenidos pueden reproducir fielmente el comportamiento de la planta, aun en el caso de sistemas inestables o que presentan algún tipo de no-linealidad. Estos modelos pueden utilizarse para el ajuste ...

  14. Sistemas de ecuaciones polinomiales ralas: aspectos teóricos y algoritmos

    OpenAIRE

    Herrero, María Isabel

    2013-01-01

    Esta tesis se centra en la resolución efectiva de sistemas de ecuaciones polinomiales reales (es decir, dadas por polinomios con estructura monomial prefijada). A lo largo del trabajo, se analizan distintos aspectos teóricos de las variedades afines definidas por estos sistemas y, en base a los resultados de este análisis, se diseñan nuevos algoritmos simbólicos probabilísticos para describirlas cuyas complejidades dependen de invariantes algebraico-combinatorios asociados al sistema. En prim...

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

    OpenAIRE

    Ramón Osmany Ramírez Tasé; Alberto Verdecia Cabrera; Agustín Alejandro Ortiz Díaz; Isvani Frías Blanco

    2016-01-01

    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. L...

  16. Análisis sintáctico ascendente con un algoritmo evolutivo

    OpenAIRE

    Araujo Serna, Lourdes

    2003-01-01

    Los métodos de análisis sintáctico clásicos buscan las distintas interpretaciones de una sentencia mediante técnicas de búsqueda completas. Pero el tamaño del espacio de búsqueda crece exponencialmente con la longitud de la sentencia y el tamaño de la gramática, de forma que los métodos de búsqueda exhaustivos pueden ser insuficientes. Sin embargo, existen otras técnicas de búsqueda, como los algoritmos evolutivos, que aunque no garantizan encontrar el valor óptimo, permiten ajustar la calida...

  17. Evaluación de algoritmos de ruteo de paquetes en redes de computadoras

    OpenAIRE

    2004-01-01

    Las MANets (Mobile Ad hoc Networks) y las Redes sin Cables (Wireless Networks) son redes de computadoras que funcionan sin una infraestructura de conexión fija. En estos tipos de redes, el ruteo de paquetes debe seguir estrategias diferentes a las conocidas debido a que la organización de la red cambia constantemente. La Geometría Computacional brinda un marco teórico y formal para el diseño de estructuras y análisis de algoritmos que solucionan problemas de tipo geométrico en diferentes área...

  18. Algoritmo para el manejo hospitalario del trauma craneoencefálico leve

    OpenAIRE

    Varela Hernández, Ariel

    2008-01-01

    Esta investigación representa una innovación tecnológica de carácter organizacional, donde se aplicó un algoritmo para el cribaje de los lesionados con trauma craneoencefálico leve en el servicio de urgencias hospitalario, con el objetivo de optimizar el empleo de la tomografía computarizada de cráneo y mejorar los resultados del tratamiento. El estudio se realizó en tres etapas: en la primera se practicó la caracterización de estos enfermos, donde se demostró que existían degradaciones de co...

  19. Evaluación de algoritmos de ruteo en redes de computadoras

    OpenAIRE

    Gagliardi, Edilma Olinda; Berón, Mario; Hernández Peñalver, Gregorio

    2003-01-01

    En este trabajo, se presenta una línea de investigación que se encarga del análisis de algoritmos de ruteo de paquetes en una red de computadoras. Nuestra herramienta trabaja en la capa de aplicación dentro de un protocolo de redes, obteniendo una colección de métricas que determinan el mejor ruteo de paquetes en cada momento. Presentamos los aspectos más relevantes del diseño de la herramienta, sus alcances y futuras etapas en este proyecto, como así también enlaces de interés.

  20. BWR Spent Nuclear Fuel Interfacial Bonding Efficiency Study

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Jy-An John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Jiang, Hao [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-04-30

    The objective of this project is to perform a systematic study of spent nuclear fuel (SNF, also known as “used nuclear fuel” [UNF]) integrity under simulated transportation environments using the Cyclic Integrated Reversible-Bending Fatigue Tester (CIRFT) hot-cell testing technology developed at Oak Ridge National Laboratory (ORNL) in August 2013. Under Nuclear Regulatory Commission (NRC) sponsorship, ORNL completed four benchmark tests, four static tests, and twelve dynamic or cycle tests on H. B. Robinson (HBR) high burn-up (HBU) fuel. The clad of the HBR fuels was made of Zircaloy-4. Testing was continued in fiscal year (FY) 2014 using Department of Energy (DOE) funds. Additional CIRFT testing was conducted on three HBR rods; two specimens failed, and one specimen was tested to over 2.23 × 107 cycles without failing. The data analysis on all the HBR SNF rods demonstrated that it is necessary to characterize the fatigue life of the SNF rods in terms of (1) the curvature amplitude and (2) the maximum absolute of curvature extremes. The maximum extremes are significant because they signify the maximum tensile stress for the outer fiber of the bending rod. CIRFT testing has also addressed a large variation in hydrogen content on the HBR rods. While the load amplitude is the dominant factor that controls the fatigue life of bending rods, the hydrogen content also has an important effect on the lifetime attained at each load range tested. In FY 15, eleven SNF rod segments from the Limerick BWR were tested using the ORNL CIRFT equipment; one test under static conditions and ten tests under dynamic loading conditions. Under static unidirectional loading, a moment of 85 N·m was obtained at a maximum curvature of 4.0 m-1. The specimen did not show any sign of failure during three repeated loading cycles to a similar maximum curvature. Ten cyclic tests were conducted with amplitudes varying from 15.2 to 7.1 N·m. Failure was observed in nine of

  1. Uma estratégia de testes logarítmica para o algoritmo HI-ADSD

    OpenAIRE

    Ruoso, Vinicius Kwiecien

    2013-01-01

    Resumo: O objetivo do diagnóstico distribuído e permitir que os nodos sem-falha de um sistema determinem o estado - falho ou sem-falha - de todos os nodos do sistema. Assume-se que os nodos sao capazes de testar outros nodos e os nodos sem-falha determinam o estado dos nodos testados corretamente. O algoritmo Hierarchical Adaptive Distributed Systemlevel Diagnosis (Hi-ADSD) [9] e um algoritmo de diagnóstico distribuído que cria uma topologia virtual baseada em um hipercubo. O hipercubo óe uma...

  2. Los algoritmos genéticos y el método de generación y prueba

    Directory of Open Access Journals (Sweden)

    Luis Roberto Ojeda Ch.

    2011-01-01

    Full Text Available Este trabajo pretende mostrar dos paradigmas de solución de problemas en inteligencia artificial. Los algoritmos genéticos han tomado una posición destacada en los últimos tiempos y el método de generación y prueba, cuyo perfil se aproxima al fundamento de los algoritmos genéticos constituye la forma de diseño de DENDRAL, un producto ampliamente reconocido en IA. Se desea mostrar que ambos paradigmas se ubican naturalmente dentro de las expectativas de la inteligencia artificial.

  3. Desarrollo de algoritmos de procesamiento de imágenes basados en "Operadores de Ventana" sobre una FPGA

    OpenAIRE

    Quijano, Antonio Adrián; Rapallini, José Antonio; Aróztegui, Walter J.; Osio, Jorge R.

    2011-01-01

    Con el avance de la tecnología las FPGAs se han convertido en una herramienta indispensable en el diseño rápido y eficiente de proyectos que requieren procesamiento digital y lógica programable. Es por eso que se ha convertido en la principal herramienta para la implementación de los algoritmos de procesamiento Digital de imágenes presentados en este trabajo [1]. Debido a la gran cantidad de algoritmos para procesamiento de imágenes basados en los Operadores de Ventana, se llega a la necesida...

  4. Uso de técnicas de paralelización para el algoritmo de los Filtros de Kalman

    OpenAIRE

    Rodríguez Arroyo, Javier

    2012-01-01

    El objetivo principal del proyecto es realizar el análisis, el diseño y la implementación en C++ de un sistema en tiempo real de calidad de servicio para la aplicación del algoritmo del filtro de Kalman lineal o discreto a varios objetos. La consecución de este propósito se puede desglosar en los siguientes subobjetivos: *Estudio del funcionamiento del algoritmo del filtro de Kalman discreto. *Familiarización con el lenguaje de programación C++ y con el estándar ISO/IEC C++ 2011.*Implem...

  5. Algoritmo híbrido para avaliação da integridade estrutural: uma abordagem heurística

    OpenAIRE

    Oscar Javier Begambre Carrillo

    2007-01-01

    Neste estudo, o novo algoritmo hibrido autoconfigurado PSOS (Particle Swarm Optimization - Simplex) para avaliação da integridade estrutural a partir de respostas dinâmicas é apresentado. A formulação da função objetivo para o problema de minimização definido emprega funções de resposta em freqüência e/ou dados modais do sistema. Uma nova estratégia para o controle dos parâmetros do algoritmo Particle Swarm Optimization (PSO), baseada no uso do método de Nelder - Mead é desenvolvida; conseqüe...

  6. 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.

  7. Comparativa de algoritmos para la optimización de un sistema de recursos hídricos

    OpenAIRE

    2015-01-01

    De manera tradicional, las técnicas de obtención de reglas de gestión (RG) en sistemas multiembalse han consistido en emplear modelos de simulación que permiten evaluar el comportamiento del sistema una vez definida dicha RG. Se trata de un proceso largo y repetitivo hasta encontrar la RG apropiada. El objetivo de este artículo es comparar dos algoritmos evolutivos empleados para la obtención de RG. Para ello, se ha desarrollado una metodología que acopla los algoritmo...

  8. Aportación al análisis de espectros de radiación: estructuras y algoritmos

    OpenAIRE

    Díaz Martín, Juan Carlos

    2015-01-01

    A lo largo del presente trabajo se investiga la viabilidad de la descomposición automática de espectros de radiación gamma por medio de algoritmos de resolución de sistemas de ecuaciones algebraicas lineales basados en técnicas de pseudoinversión. La determinación de dichos algoritmos ha sido realizada teniendo en cuenta su posible implementación sobre procesadores de propósito específico de baja complejidad. En el primer capítulo se resumen las técnicas para la detección y ...

  9. Um algoritmo evolutivo híbrido para o problema de recobrimento de rotas com coletas de premios.

    OpenAIRE

    Silva, Matheus de Souza Alves; Mine, Marcio Tadayuki; Ochi, Luiz Satoru; Souza,Marcone Jamilson Freitas

    2010-01-01

    Este artigo propõe um algoritmo evolutivo híbrido para obter soluções aproximadas para o Problema de Recobrimento de Rotas com Coleta de Prêmios (PRRCP). O algoritmo proposto combina estratégias heurísticas baseadas nos procedimentos Busca Local Iterada, Busca em Vizinhança Variável, Reconexão por Caminhos e GENIUS. Resultados computacionais para um conjunto de instancias mostram a eficiência e a robustez da heurística proposta. _________________________________________________________________...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-15

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

  11. 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

  12. Full scale stability and void fraction measurements for the ATRIUM trademark 10XM BWR fuel bundle

    Energy Technology Data Exchange (ETDEWEB)

    Wehle, Franz; Velten, Roger; Kronenberg, Juris; Beisiegel, Achim [AREVA NP GmbH, Erlangen (Germany); Pruitt, D.W.; Greene, K.R. [AREVA NP Inc., Lynchburg, VA (United States); Farawila, Y.M. [Farawila et al., Inc., Richland, WA (United States)

    2011-07-01

    This paper describes recent advances in BWR fuel testing at AREVA NP's KATHY loop including stability and void fraction measurements. The stability tests for the ATRIUM trademark 10XM bundle with corner PLFR's were expanded in scope compared with previous campaigns to include simulated reactivity and power feedback essentially reproducing BWR operational environment. The oscillation magnitude was allowed to grow to explore inlet flow reversal and cyclical dryout and rewetting. The void fraction measurements employed a gamma ray computed tomography technique that reveals not only the average but the detailed sub-channel void distribution, and the range of measured void fraction has been expanded to higher values than was previously attained. With the completion of the required licensing tests and stability performance demonstration, the ATRIUM trademark 10XM is available and fully qualified for reload supply. (orig.)

  13. Development of a scatter search optimization algorithm for BWR fuel lattice design

    Energy Technology Data Exchange (ETDEWEB)

    Francois, J.L.; Martin-del-Campo, C. [Mexico Univ. Nacional Autonoma, Facultad de Ingenieria (Mexico); Morales, L.B.; Palomera, M.A. [Mexico Univ. Nacional Autonoma, Instituto de Investigaciones en Matematicas Aplicadas y Sistemas, D.F. (Mexico)

    2005-07-01

    A basic Scatter Search (SS) method, applied to the optimization of radial enrichment and gadolinia distributions for BWR fuel lattices, is presented in this paper. Scatter search is considered as an evolutionary algorithm that constructs solutions by combining others. The goal of this methodology is to enable the implementation of solution procedures that can derive new solutions from combined elements. The main mechanism for combining solutions is such that a new solution is created from the strategic combination of two other solutions to explore the solutions' space. Results show that the Scatter Search method is an efficient optimization algorithm applied to the BWR design and optimization problem. Its main features are based on the use of heuristic rules since the beginning of the process, which allows directing the optimization process to the solution, and to use the diversity mechanism in the combination operator, which allows covering the search space in an efficient way. (authors)

  14. Effect of Control Blade History, and Axial Coolant Density and Burnup Profiles on BWR Burnup Credit

    Energy Technology Data Exchange (ETDEWEB)

    Ade, Brian J [ORNL; Marshall, William BJ J [ORNL; Martinez-Gonzalez, Jesus S [ORNL

    2015-05-01

    Oak Ridge National Laboratory (ORNL) and the US Nuclear Regulatory Commission (NRC) have initiated a multiyear project to investigate the application of burnup credit (BUC) for boiling water reactor (BWR) fuel in storage and transportation systems (often referred to as casks) and spent fuel pools (SFPs). This work is divided into two main phases. The first phase investigated the applicability of peak reactivity methods currently used in SFPs to transportation and storage casks and the validation of reactivity calculations and spent fuel compositions within these methods. The second phase focuses on extending BUC beyond peak reactivity. This paper documents the analysis of the effects of control blade insertion history, and moderator density and burnup axial profiles for extended BWR BUC.

  15. Impact of Reactor Operating Parameters on Cask Reactivity in BWR Burnup Credit

    Energy Technology Data Exchange (ETDEWEB)

    Ilas, Germina [ORNL; Betzler, Benjamin R [ORNL; Ade, Brian J [ORNL

    2017-01-01

    This paper discusses the effect of reactor operating parameters used in fuel depletion calculations on spent fuel cask reactivity, with relevance for boiling-water reactor (BWR) burnup credit (BUC) applications. Assessments that used generic BWR fuel assembly and spent fuel cask configurations are presented. The considered operating parameters, which were independently varied in the depletion simulations for the assembly, included fuel temperature, bypass water density, specific power, and operating history. Different operating history scenarios were considered for the assembly depletion to determine the effect of relative power distribution during the irradiation cycles, as well as the downtime between cycles. Depletion, decay, and criticality simulations were performed using computer codes and associated nuclear data within the SCALE code system. Results quantifying the dependence of cask reactivity on the assembly depletion parameters are presented herein.

  16. Valuation of power oscillations in a BWR after control rod banks withdrawal events

    Energy Technology Data Exchange (ETDEWEB)

    Costa, A. L.; Pereira, C.; Da Silva, C. A. M.; Veloso, M. A. F. [Departamento de Engenharia Nuclear, Universidade Federal de Minas Gerais, Av. Antonio Carlos, 6627, CEP 31270-90, Belo Horizonte, MG (Brazil); Instituto Nacional de Ciencias e Tecnologia de Reatores Nucleares Inovadores/CNPq (Brazil)

    2009-07-01

    The out-of-phase mode of oscillation is a very challenging type of instability occurring in BWR (Boiling Water Reactor) and its study is relevant because of the safety implications related to the capability to promptly detect any such inadvertent occurrence by in-core neutron detectors, thus triggering the necessary countermeasures in terms of selected rod insertion or even reactor shutdown. In this work, control rod banks (CRB) withdrawal transient was considered to study the power instability occurring in a BWR. To simulate this transient, the control rod banks were continuously removed from the BWR core in different cases. The simulation resulted in a very large increase of power. To perform the instability simulations, the RELAP5/MOD3.3 thermal hydraulic system code was coupled with the PARCS/2.4 3D neutron kinetic code. Data from a real BWR, the Peach Bottom, have been used as reference conditions and reactor parameters. The trend of the mass flow rate, pressure, coolant temperature and the void fraction to four thermal hydraulic channels symmetrically located in the core with respect to the core centre, were taken. It appears that the velocity of the rod bank withdrawal is a very important aspect for reactor stability. The slowest CRB withdrawal (180 s) did not cause power perturbation while the fast removal (20 s) triggered a slow power oscillation that little by little amplified to reach levels of more 100% of the initial power after about 210 s. The investigation of the related thermo hydraulic parameters showed that the mass flow rate, the void fraction and also the coolant temperature began to oscillate at approximately the same time interval

  17. Predictive uncertainty reduction in coupled neutron-kinetics/thermal hydraulics modeling of the BWR-TT2 benchmark

    Energy Technology Data Exchange (ETDEWEB)

    Badea, Aurelian F., E-mail: aurelian.badea@kit.edu [Karlsruhe Institute of Technology, Vincenz-Prießnitz-Str. 3, 76131 Karlsruhe (Germany); Cacuci, Dan G. [Center for Nuclear Science and Energy/Dept. of ME, University of South Carolina, 300 Main Street, Columbia, SC 29208 (United States)

    2017-03-15

    Highlights: • BWR Turbine Trip 2 (BWR-TT2) benchmark. • Substantial (up to 50%) reduction of uncertainties in the predicted transient power. • 6660 uncertain model parameters were calibrated. - Abstract: By applying a comprehensive predictive modeling methodology, this work demonstrates a substantial (up to 50%) reduction of uncertainties in the predicted total transient power in the BWR Turbine Trip 2 (BWR-TT2) benchmark while calibrating the numerical simulation of this benchmark, comprising 6090 macroscopic cross sections, and 570 thermal-hydraulics parameters involved in modeling the phase-slip correlation, transient outlet pressure, and total mass flow. The BWR-TT2 benchmark is based on an experiment that was carried out in 1977 in the NPP Peach Bottom 2, involving the closure of the turbine stop valve which caused a pressure wave that propagated with attenuation into the reactor core. The condensation of the steam in the reactor core caused by the pressure increase led to a positive reactivity insertion. The subsequent rise of power was limited by the feedback and the insertion of the control rods. The BWR-TT2 benchmark was modeled with the three-dimensional reactor physics code system DYN3D, by coupling neutron kinetics with two-phase thermal-hydraulics. All 6660 DYN3D model parameters were calibrated by applying a predictive modeling methodology that combines experimental and computational information to produce optimally predicted best-estimate results with reduced predicted uncertainties. Simultaneously, the predictive modeling methodology yields optimally predicted values for the BWR total transient power while reducing significantly the accompanying predicted standard deviations.

  18. MELCOR 1.8.2 assessment: The DF-4 BWR Damaged Fuel experiment

    Energy Technology Data Exchange (ETDEWEB)

    Tautges, T.J.

    1993-10-01

    MELCOR is a fully integrated, engineering-level computer code being developed at Sandia National Laboratories for the USNRC, that models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs. As a part of an ongoing assessment, program, MELCOR has been used to model the ACRR in-pile DF-4 Damaged Fuel experiment. DF-4 provided data for early phase melt progression in BWR fuel assemblies, particularly for phenomena associated with eutectic interactions in the BWR control blade and zircaloy oxidation in the canister and cladding. MELCOR provided good agreement with experimental data in the key areas of eutectic material behavior and canister and cladding oxidation. Several shortcomings associated with the MELCOR modeling of BWR geometries were found and corrected. Twenty-five sensitivity studies were performed on COR, HS and CVH parameters. These studies showed that the new MELCOR eutectics model played an important role in predicting control blade behavior. These studies revealed slight time step dependence and no machine dependencies. Comparisons made with the results from four best-estimate codes showed that MELCOR did as well as these codes in matching DF-4 experimental data.

  19. Status report: Intergranular stress corrosion cracking of BWR core shrouds and other internal components

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    On July 25, 1994, the US Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 94-03 to obtain information needed to assess compliance with regulatory requirements regarding the structural integrity of core shrouds in domestic boiling water reactors (BWRs). This report begins with a brief description of the safety significance of intergranular stress corrosion cracking (IGSCC) as it relates to the design and function of BWR core shrouds and other internal components. It then presents a brief history of shroud cracking events both in the US and abroad, followed by an indepth summary of the industry actions to address the issue of IGSCC in BWR core shrouds and other internal components. This report summarizes the staff`s basis for issuing GL 94-03, as well as the staff`s assessment of plant-specific responses to GL 94-03. The staff is continually evaluating the licensee inspection programs and the results from examinations of BWR core shrouds and other internal components. This report is representative of submittals to and evaluations by the staff as of September 30, 1995. An update of this report will be issued at a later date.

  20. Characterization of corrosion layers on irradiated and non-irradiated surfaces in BWR conditions

    Energy Technology Data Exchange (ETDEWEB)

    Kysela, J.; Balek, V.; Zmitko, M.; Brozova, A.; Burda, J. [Nuclear Research Inst., Rez (Czech Republic); Hoffmann, H.; Ruehle, W. [VGB Essen (Germany); Bezdicka, P. [Institute of Inorganic Chemistry, ASCR, Rez (Czech Republic)

    2002-07-01

    Stress corrosion cracking of low-alloyed steel 22NiMoCr37 is evaluated with the goal to determine crack growth rate in irradiated steel under conditions simulating closely conditions of BWR RPV under operation. For the experiment, in pile BWR experimental loop has been built at Nuclear Research Institute, Rez. During the experiment, specimens are loaded by cyclic and constant load. Crack growth is monitored by means of potential drop measurement and COD. Corrosion layers formed on specimens in reactor water loop exposed to BWR primary water chemistry and radiation were studied. Two sets of specimens were placed in loop channels. One set of specimens was situated in reactor conditions and the second set out of reactor, other parameters like water chemistry (e.g. concentration of hydrogen, oxygen and conductivity), temperature and flow rate were identical. By means of this an effect of radiation could be studied. The differences in chemical composition, structure and microstructure of corrosion products were characterized by SEM and X-ray powder diffractometry. The differences in microstructure of corrosion layer formed under different conditions were observed. (authors)

  1. 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.

  2. 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.

  3. APLICAÇÃO DO ALGORITMO DA SEPSE POR ENFERMEIROS NA UNIDADE DE TERAPIA INTENSIVA

    Directory of Open Access Journals (Sweden)

    Paula Pedroso Peninck

    2012-01-01

    Full Text Available La sepsis es un síndrome clínico con respuesta inflamatoria sistémica asociada con foco infeccioso, que puede determinar la disfunción o falencia de múltiples órganos. Los objetivos fueron verificar la aplicación del algoritmo de la sepsis en la Unidad de Cuidados Intensivos y crear una guía de asistencia para enfermeros. Estudio exploratorio, descriptivo, con enfoque cuantitativo. Se desarrolló un instrumento de recopilación de datos basado en la literatura pertinente, sometido, corregido y validado. La muestra fue de 20 enfermeros de unidades de cuidados intensivos. Se obtuvo desempeño satisfactorio de los enfermeros, pero algunas cuestiones no alcanzaron 50% de aciertos. Se señala la importancia de que más profesionales conozcan y apliquen correctamente el algoritmo de la sepsis. Se creó una guía de asistencia de enfermería al paciente séptico, basado en dificultades ante variables aplicadas en la investigación y pertinencia literaria.

  4. 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.

  5. 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.

  6. Implementación de un algoritmo de búsqueda de posiciones de equilibrio ponderado

    Directory of Open Access Journals (Sweden)

    Rodrigo, Javier

    2008-01-01

    Full Text Available En esta ponencia se presenta un algoritmo que determina las posiciones de equilibrio en un juego de competición política entre dos partidos representados en el plano de políticas por dos puntos. Para modelar una situación que se ajuste lo más posible a la realidad política de los diferentes países, se considera que los votantes están distribuidos en tipos posicionados en el plano por puntos que representan sus preferencias políticas y que dichos tipos no están equidistribuidos (se les asigna un peso. El estudio teórico de la existencia y unicidad de posiciones de equilibrio en el sentido clásico de Nash se hace aplicando herramientas geométricas como son los cierres convexos. El algoritmo de búsqueda de dichas posiciones de equilibrio cuando existen, se implementa en un caso práctico de la política en España, basado en el estudio 2742 (BARÓMETRO NOVIEMBRE 2007 realizado por el CIS.

  7. Control adaptable indirecto usando Redes Neuronales Dinámicas

    Directory of Open Access Journals (Sweden)

    M. A. Moreno Armendariz

    2001-01-01

    Full Text Available En este trabajo se propone un nuevo tipo de control no-lineal por retroalimentación para una clase de sistemas continuos no-lineales de una entrada y una salida de la siguiente forma: Se supone que el sistema no-lineal es desconocido, así una red neuronal dinámica multicapa es usada para identificarlo. Usando un análisis tipo Lyapunov, una nueva ley de actualización estable es presentada, además la estabilidad global es probada. Finalmente, se presenta la aplicación de dicha técnica al sistema no-lineal TORA mediante simulaciones.

  8. Damage by radiation in structural materials of BWR reactor vessels; Dano por radiacion en materiales estructurales de vasijas de reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Robles, E.; Balcazar, M.; Alpizar, A.M.; Calderon, B.E. [Departamento de Sintesis y Caracterizacion de Materiales, Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    The structural materials which are manufactured the pressure vessels of the BWR reactors undergo degradation in their mechanical properties mainly due to the damage produced by the fast neutrons (E> 1 MeV) coming from the reactor core. The mechanisms of neutron damage in this type of materials are experimentally studied, through the irradiation of vessel steel in experimental reactors for a quickly ageing. Alternately the neutron damage through steel irradiation with heavy ions is simulated. In this work the first results of the damage induced by irradiation of a similar steel to the vessel of a BWR reactor are shown. The irradiation was performed with fast neutrons (E> 1 MeV, fluence of 1.45 x 10{sup 18} n/cm{sup 2}) in the TRIGA Mark III Salazar reactor and separately with Ni{sup +3} ions in a Tandetrom accelerator (E= 4.8 MeV and an ion flux rank of 0.1 to 53 ions/A{sup 2}). (Author)

  9. Logical model for the control of a BWR turbine;Modelo logico para el control de una turbina de un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Vargas O, Y. [Universidad del Valle de Mexico, Campus Toluca, Av. Las Palmas No. 136, Col. San Jorge Pueblo Nuevo, 52140 Metepec, Estado de Mexico (Mexico); Amador G, R.; Ortiz V, J.; Castillo D, R., E-mail: yonaeton@hotmail.co [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2009-07-01

    In this work a design of a logical model is presented for the turbine control of a nuclear power plant with a BWR like energy source. The model is sought to implement later on inside the thermal hydraulics code of better estimate RELAP/SCDAPSIM. The logical model is developed for the control and protection of the turbine, and the consequent protection to the BWR, considering that the turbine control will be been able to use for one or several turbines in series. The quality of the present design of the logical model of the turbine control is that it considers the most important parameters in the operation of a turbine, besides that they have incorporated to the logical model the secondary parameters that will be activated originally as true when the turbine model is substituted by a detailed model. The development of the logical model of a turbine will be of utility in the short and medium term to carry out analysis on the turbine operation with different operation conditions, of vapor extraction, specific steps of the turbine to feed other equipment s, in addition to analyze the separate and the integrated effect. (Author)

  10. Entrainment and deposition modeling of liquid films with applications for BWR fuel rod dryout

    Science.gov (United States)

    Ratnayake, Ruwan Kumara

    While best estimate computer codes provide the licensing basis for nuclear power facilities, they also serve as analytical tools in overall plant and component design procedures. An ideal best estimate code would comprise of universally applicable mechanistic models for all its components. However, due to the limited understanding in these specific areas, many of the models and correlations used in these codes reflect high levels of empiricism. As a result, the use of such models is strictly limited to the range of parameters within which the experiments have been conducted. Disagreements between best estimate code predictions and experimental results are often explained by the mechanistic inadequacies of embedded models. Significant mismatches between calculated and experimental critical power values are common observations in the analyses of Boiling Water Reactors (BWR). Based on experimental observations and calculations, these mismatches are attributed to the additional entrainment and deposition caused by spacer grids in BWR fuel assemblies. In COBRA-TF (Coolant Boiling in Rod Arrays-Two Fluid); a state of the art industrial best estimate code, these disagreements are hypothesized to occur due the absence of an appropriate spacer grid model. In this thesis, development of a suitably detailed spacer grid model and integrating it to COBRA-TF is documented. The new spacer grid model is highly mechanistic so that the applicability of it is not seriously affected by geometric variations in different spacer grid designs. COBRA-TF (original version) simulations performed on single tube tests and BWR rod bundles with spacer grids showed that single tube predictions were more accurate than those of the rod bundles. This observation is understood to arise from the non-availability of a suitable spacer grid model in COBRA-TF. Air water entrainment experiments were conducted in a test section simulating two adjacent BWR sub channels to visualize the flow behavior at

  11. Operadores de mutación en algoritmos genéticos celulares aplicados a problemas continuos

    Directory of Open Access Journals (Sweden)

    Hernán Sosa

    2014-10-01

    Full Text Available El diseño de algoritmos eficientes para resolver problemas complejos es unouno de los aspectos más importantes de investigación en el campo de la informática. El objetivo perseguido es fundamentalmente el desarrollo de nuevos métodos capaces de resolver problemas complejos con el menor esfuerzo computacional posible, mejorando así a los algoritmos existentes de una forma eficaz.Los Algoritmos Genéticos Celulares (cGAs forman parte de las herramientasde optimización más populares. Estos algoritmos se enfocan en encontrar soluciones óptimos en un tiempo reducido en comparación a métodos exactos.En este trabajo se propone un estudio comparativo de diferentes operadoresde mutación en un cGa aplicado a problemas académicos clásicos de optimización continua.

  12. Um sistema baseado em conhecimento para configuração e supervisão de algoritmos de controle adaptativo

    OpenAIRE

    Ruben Mario Nazzaretta

    1991-01-01

    Resumo: O presente trabalho detalha o desenvolvimento de um sistema baseado em conhecimento para o auxílio nas tarefas de configuração e supervisão de algoritmos de modelagem e controle de processos. O sistema consta dos seguintes módulos: Módulo de controle onde encontram-se os algoritmos de controle, de três termos (PID), de Variância Mínima Generalizada (GMV) e o Controlador Preditivo Generalizado (GPC); Módulo de identificação com o algoritmo de matriz estendida; Módulo de detecção de não...

  13. Diseño de algoritmo para la detección de adelantamientos de vehículos en plataforma Android

    OpenAIRE

    García Zamora, María Isabel

    2015-01-01

    El presente proyecto consiste en el estudio de la posibilidad de crear una aplicación Android con el objetivo de detectar si el vehículo en el cual se circula es adelantado. Para ello se utilizará un dispositivo Android con cámara incorporada y un algoritmo de flujo óptico que permita obtener vectores de movimiento. Dicho algoritmo es el algoritmo de Lucas-Kanade que permite identificar regiones de una imagen cuyo movimiento es similar y por tanto, mediante dos fotogramas consecutivos, obt...

  14. PVT modeling of reservoir fluids using PC-SAFT EoS and Soave-BWR EoS

    DEFF Research Database (Denmark)

    Yan, Wei; Varzandeh, Farhad; Stenby, Erling Halfdan

    2015-01-01

    non-cubic EoS models, such as the Perturbed Chain Statistical Associating Fluid Theory (PC-SAFT) EoS and the Soave modified Benedict-Webb-Rubin (Soave-BWR) EoS, may partly replace the roles of these classical cubic models in the upstream oil industry. Here, we attempt to make a comparative study...... of non-cubic models (PC-SAFT and Soave-BWR) and cubic models (SRK and PR) in several important aspects related to PVT modeling of reservoir fluids, including density description for typical pure components in reservoir fluids, description of binary VLE, prediction of multicomponent phase envelopes...... and Soave-BWR. For PC-SAFT, new correlations for estimating its model parameters in heptanes plus are developed. The results reveal that the non-cubic models are clearly advantageous in density calculation of pure components. For binary VLE and multicomponent phase envelopes, the results are similar...

  15. Analysis of high fidelity of a BWR fuel element with COBRA-TF/PARCS codes and TRACE; Analisis de Alta Fidelidad de un Elemento Combustible BWR con los codigos COBRA-TF/PARCS y TRACE

    Energy Technology Data Exchange (ETDEWEB)

    Abarca, A.; Miro, R.; Barrachina, T.; Verdu, G.; Solar, A.; Concejal, A.; Melara, J.; Albendea, M.

    2013-07-01

    It has been modeled a 10 x 10 BWR fuel element, containing 91 fuel rods (81 of 10 partial length and total length) and a great water bar of square section in the central part of it. Such fuel element has been modeled in detail: at the level of sub-channel code COBRA-TF and using parametric models for fuel elements BWR that owns the plant code TRACE. Has been an exercise in comparison of the results obtained by both codes in the simulation of a stationary and a small transient flow injection, highlighting the differences observed.

  16. Una modificación al método varimax para delimitar Regiones Urbanas Funcionales usando la vecindad espacial

    Directory of Open Access Journals (Sweden)

    Melisa Abalos Choque

    2014-01-01

    para incorporar los efectos de la conmutación de larga distancia. Nuestros resultados indican que las RUF construidas a partir del algoritmo Intramax incorporando criterios para tratar la conmutación a larga distancia presentan mayores beneficios.

  17. Algoritmos evolutivos para predição de estruturas de proteínas

    OpenAIRE

    Telma Woerle de Lima

    2006-01-01

    A Determinação da Estrutura tridimensional de Proteínas (DEP) a partir da sua seqüência de aminoácidos é importante para a engenharia de proteínas e o desenvolvimento de novos fármacos. Uma alternativa para este problema tem sido a aplicação de técnicas de computação evolutiva. As abordagens utilizando Algoritmos Evolutivos (AEs) tem obtido resultados relevantes, porém estão restritas a pequenas proteínas, com dezenas de aminoácidos e a algumas classes de proteínas. Este trabalho propõe a inv...

  18. AGRUPAMIENTO HOMOGÉNEO DE ELEMENTOS CON MÚLTIPLES ATRIBUTOS MEDIANTE ALGORITMOS GENÉTICOS

    Directory of Open Access Journals (Sweden)

    JULIAN MORENO

    2011-01-01

    Full Text Available Este artículo describe el problema general de agrupamiento, particularmente aquel en el que se busca conformar grupos de igual tamaño y equitativos respecto a más de un atributo, como un problema de optimización multiobjetivo, cuya solución por medio de una búsqueda exhaustiva no siempre será conveniente dada la explosión combinatoria que puede presentarse. Como alternativa a esta situación, se propone un método basado en algoritmos genéticos donde las soluciones posibles se codifican en estructuras tipo cromosoma a manera de matrices y donde por medio de un proceso iterativo en el que intervienen los operadores genéticos de selección, cruce y mutación, se guía el proceso de búsqueda hasta dar con una solución satisfactoria.

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

    Directory of Open Access Journals (Sweden)

    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.

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

    Directory of Open Access Journals (Sweden)

    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.

  1. Comparação de algoritmos para alocação de infraestruturas virtuais

    Directory of Open Access Journals (Sweden)

    Denivy Braiam Ruck

    2014-11-01

    Full Text Available Com o surgimento da Computação em Nuvem, empresas passaram a adotá-la em virtude das diversas vantagens que apresenta, como por exemplo, baixo investimento inicial e alta escalabilidade. Nesse contexto, um provedor de Infrastructure as a Service (IaaS oferece recursos computacionais a seus clientes de forma virtualizada, que, por sua vez, podem realizar a solicitação de máquinas virtuais para implantar e disponibilizar suas aplicações. Uma proposta recente incrementou os serviços do provedor IaaS, possibilitando alocar uma rede de máquinas e roteadores virtuais interconectados por canais virtuais, ou seja, uma Infraestrutura Virtual (IV. Porém, a tarefa de alocar IVs sobre o substrato físico é complexa, caracterizada como um problema NP-Díficil, no qual algoritmos ótimos são impraticáveis em cenários reais (o tempo para encontrar uma solução ótima é exponencial. Tendo em vista esse fato, este trabalho estende o simulador CloudSim, implementando quatro algoritmos on-line para a alocação de recursos, comparando as métricas: taxa de aceitação, utilização do substrato computacional e distância entre os recursos virtuais. Tais métricas representam as perspectivas dos provedores e dos usuários requisitantes.

  2. Behavior of irradiated BWR fuel under reactivity-initiated-accident conditions; Results of tests FK-1, -2 and -3

    OpenAIRE

    2004-01-01

    Boiling water reactor (BWR) fuels with burnups of 41 to 45 GWd/tU were pulse-irradiated in the Nuclear Safety Research Reactor (NSRR) to investigate fuel behavior under cold startup reactivity-initiated-accident (RIA) conditions. BWR fuel segment rods of 8times8BJ (STEP I) type from Fukushima-Daiichi Unit 3 nuclear power plant were refabricated into short test rods, and they were subjected to prompt enthalpy insertion from 293 to 607 J/g (70 to 145 cal/g) within about 20 ms. The fuel cladding...

  3. Crack growth tests on a ferritic reactor pressure vessel steel under the simultaneous influence of simulated BWR coolant and irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, H. [VGB PowerTech e.V., Essen (Germany); Huettner, F. [Hamburgische Electricitaets-Werke AG, Hamburg (Germany); Ilg, U. [EnBW Kraftwerke AG, Philippsburg (Germany); Wachter, O. [E.ON Kernkraft GmbH, Hannover(Germany); Widera, M. [RWE Power AG, Essen (Germany); Brozova, A.; Ernestova, M.; Kysela, J.; Vsolak, R. [Nuclear Research Institute Rez plc (Czech Republic)

    2004-07-01

    Crack growth tests under constant load with initial in-situ cycling were performed on the low alloy reactor pressure vessel (RPV) steel 22 NiMoCr 3 7 (A 508 Cl. 2) with the goal to determine crack growth rates of irradiated and non-irradiated steel under the simultaneous influence of simulated BWR coolant and irradiation. The tests were performed under conditions as near as possible to operational conditions in a commercial BWR reactor. The research results are summarized and are compared with international data. (orig.)

  4. Parámetros Numéricos en el Método de los Algoritmos Genéticos para el Cálculo de la Solubilidad y la Presión de Sublimación Numerical Parameters in the Genetic Algorithms Method for Calculating the Solubility and the Sublimation Pressure

    Directory of Open Access Journals (Sweden)

    José O Valderrama

    2006-01-01

    Full Text Available Se ha analizado el efecto de algunos parámetros numéricos en la determinación de la presión de sublimación de un sólido usando datos de solubilidad del sólido en un gas a alta presión. El estudio se basa en un trabajo presentado por Valderrama y Zavaleta (2005 en el que se utiliza algoritmos genéticos como método de optimización. Los valores de algunos parámetros involucrados en el método de los algoritmos genéticos, como el número de individuos, el número de generaciones, la probabilidad de cruzamiento, y la probabilidad de mutación, no fueron analizados con detalle por los autores. En este estudio se analizan los resultados obtenidos haciendo variar el valor de estos parámetros y usando como función objetivo la desviación en la solubilidad en la presión de sublimación calculada. El estudio permite concluir sobre el efecto de estos parámetros y recomienda los mejores valores para este tipo de estudios.The effect of some numerical parameters on the determination of the sublimation pressure of a solid using solubility of the solid in a high pressure gas was specially analyzed. The study is based on a paper presented by Valderrama y Zavaleta (2005 in which genetic algorithms are used as optimization method. The values of some parameters involved in the genetic algorithm method such as number of individuals, number of generations, the crossover probability and the mutation probability, were not analyzed by these authors. In this study the results obtained by varying the values of these parameters using the deviation in the solubility as the objective function is analyzed with details. The study allows to conclude on the effect of these parameters and on the best values of the parameters for the cases studied.

  5. Study of transient rod extraction failure without RBM in a BWR; Estudio del transitorio error de extraccion de barra sin RBM en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Vallejo Q, J. A.; Martin del Campo M, C.; Fuentes M, L.; Francois L, J. L., E-mail: amhed_jvq@hotmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2015-09-15

    The study and analysis of the operational transients are important for predicting the behavior of a system to short-term events and the impact that would cause this transient. For the nuclear industry these studies are indispensable due to economic, environmental and social impacts that could cause an accident during the operation of a nuclear reactor. In this paper the preparation, simulation and analysis results of the transient rod extraction failure in which not taken into operation the RBM is presented. The study was conducted for a BWR of 2027 MWt, in an intermediate cycle of its useful life and using the computer code Simulate-3K a scenario of anomalies was created in the core reactivity which gave a coherent prediction to the type of presented event. (Author)

  6. Study of transient turbine shot without bypass in a BWR; Estudio del transitorio disparo de turbina sin bypass en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Vallejo Q, J. A.; Martin del Campo M, C.; Fuentes M, L.; Francois L, J. L., E-mail: amhed_jvq@hotmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2015-09-15

    The study and analysis of operational transients are important for predicting the behavior of a system to short-terms events and the impact that would cause this transition. For the nuclear industry these studies are indispensable due to economic, environmental and social impacts that could result in an accident during the operation of a nuclear reactor. In this paper the preparation, simulation and analysis of results of a turbine shot transient, which is not taken into operation the bypass is presented. The study is realized for a BWR of 2027 MWt, to an intermediate cycle life and using the computer code Simulate-3K a depressurization stage of the vessel is created which shows the response of other security systems and gives a coherent prediction to the event presented type. (Author)

  7. Thermal hydraulics characterization of the core and the reactor vessel type BWR; Caracterizacion termohidraulica del nucleo y de la vasija de un reactor tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Zapata Y, M.; Lopez H, L.E. [CFE, Carretera Cardel-Nautla Km. 42.5, Municipio Alto Lucero, Veracruz (Mexico)]. e-mail: marxlenin.zapata@cfe.gob.mx

    2008-07-01

    The thermal hydraulics design of a reactor type BWR 5 as the employees in the nuclear power plant of Laguna Verde involves the coupling of at least six control volumes: Pumps jet region, Stratification region, Core region, Vapor dryer region, Humidity separator region and Reactor region. Except by the regions of the core and reactor, these control volumes only are used for design considerations and their importance as operative data source is limited. It is for that is fundamental to complement the thermal hydraulics relations to obtain major data that allow to determine the efficiency of internal components, such as pumps jet, humidity separator and vapor dryer. Like example of the previous thing, calculations are realized on the humidity of the principal vapor during starting, comparing it with the values at the moment incorporated in the data banks of the computers of process of both units. (Author)

  8. Analysis of assemblies exchange in the core of a reactor BWR; Analisis del intercambio de ensambles en el nucleo de un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Kauil U, J. S. [Universidad Autonoma de Yucatan, Facultad de Ingenieria, Av. Industrias no contaminantes por Anillo Periferico Norte s/n, Apdo. Postal 150 Cordemex, Merida, Yucatan (Mexico); Fuentes M, L.; Castillo M, J. A.; Ortiz S, J. J.; Perusquia del Cueto, R., E-mail: san_dino@hotmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2012-10-15

    The performance of the core of a boiling water reactor (BWR) was evaluated when two assemblies are exchanged during the fuel reload in erroneous way. All with the purpose of analyzing the value of the neutrons effective multiplication factor and the thermal limits for an exchange of assemblies. In their realization the mentioned study was based in a transition cycle of the Unit 1 of the nuclear power plant of Laguna Verde. The obtained results demonstrate that when carrying out an exchange between two fuel assemblies in erroneous way, with regard to the original reload, the changes in the neutrons effective multiplication factor do not present a serious problem, unless the exchange has been carried out among a very burnt assembly with one fresh, where this last is taken to the periphery. (Author)

  9. Estimation of dose rate around the spent control rods of a BWR; Estimacion de la rapidez de dosis alrededor de las barras de control gastadas de un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Cancino P, G.

    2016-10-01

    The energy can come from fossil renewable sources (solar (natural gas, oil), wind, hydro, tidal, geothermal, biomass, bio energy and nuclear. Nuclear power can be obtained by fission reactions and fusion (still under investigation) atomic nuclei. Fission, is a partition of a very heavy nucleus (Uranium 235, for example) into two lighter nuclei. Much of the world's electric power is generated from the energy released by fission processes. In a nuclear power reactor, light water as the BWR, there are many important elements that allow safe driving operation, one of them are the elements or control systems, the burnable poison or neutron absorber inherently allow control power reactor. The control rods, which consist mostly of stainless steel and absorbing elements (such as boron carbide, hafnium, cadmium, among others) of thermal neutrons is able to initiate, regulate or stop the reactor power. These, due to the use of depleted burned or absorbing material and therefore reach their lifespan, which can be 15 years or have other values depending on the manufacturer. Control rods worn should be removed, stored or confined in expressly places. Precisely at this stage arises the importance of knowing their radiological condition to manipulate safely and without incident to the people health responsible for conducting these proceedings state arises. This thesis consists in the estimation of the dose rate in spent control rod made of boron carbide, from a typical BWR reactor. It will be estimated by direct radiation measurements with measurement equipment for radiotherapy ionization chamber, in six spent control rods, which were taken at different reactor operating cycles and are in a spent fuel pool. Using bracket electromechanical and electronic equipment for positioning and lifting equipment for radiation measurement around the control rod in the axial and radial arrangement for proper scanning. Finally will be presented a graphic corresponding to the dose

  10. Crack growth rate in core shroud horizontal welds using two models for a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Arganis Juárez, C.R., E-mail: carlos.arganis@inin.gob.mx; Hernández Callejas, R.; Medina Almazán, A.L.

    2015-05-15

    Highlights: • Two models were used to predict SCC growth rate in a core shroud of a BWR. • A weld residual stress distribution with 30% stress relaxation by neutron was used. • Agreement is shown between the measurements of SCC growth rate and the predictions. • Slip–oxidation model is better at low fluences and empirical model at high fluences. - Abstract: An empirical crack growth rate correlation model and a predictive model based on the slip–oxidation mechanism for Stress Corrosion Cracking (SCC) were used to calculate the crack growth rate in a BWR core shroud. In this study, the crack growth rate was calculated by accounting for the environmental factors related to aqueous environment, neutron irradiation to high fluence and the complex residual stress conditions resulting from welding. In estimating the SCC behavior the crack growth measurements data from a Boiling Water Reactor (BWR) plant are referred to, and the stress intensity factor vs crack depth throughout thickness is calculated using a generic weld residual stress distribution for a core shroud, with a 30% stress relaxation induced by neutron irradiation. Quantitative agreement is shown between the measurements of SCC growth rate and the predictions of the slip–oxidation mechanism model for relatively low fluences (5 × 10{sup 24} n/m{sup 2}), and the empirical model predicted better the SCC growth rate than the slip–oxidation model for high fluences (>1 × 10{sup 25} n/m{sup 2}). The relevance of the models predictions for SCC growth rate behavior depends on knowing the model parameters.

  11. TRACE code validation for BWR spray cooling injection based on GOTA facility experiments

    Energy Technology Data Exchange (ETDEWEB)

    Racca, S. [San Piero a Grado Nuclear Research Group (GRNSPG), Pisa (Italy); Kozlowski, T. [Royal Inst. of Tech., Stockholm (Sweden)

    2011-07-01

    Best estimate codes have been used in the past thirty years for the design, licensing and safety of NPP. Nevertheless, large efforts are necessary for the qualification and the assessment of such codes. The aim of this work is to study the main phenomena involved in the emergency spray cooling injection in a Swedish designed BWR. For this purpose, data from the Swedish separate effect test facility GOTA have been simulated using TRACE version 5.0 Patch 2. Furthermore, uncertainty calculations have been performed with the propagation of input errors method and the identification of the input parameters that mostly influence the peak cladding temperature has been performed. (author)

  12. LOCA steam condensation loads in BWR Mark II pressure suppression containment system

    Energy Technology Data Exchange (ETDEWEB)

    Kukita, Y.; Namatame, K.; Takeshita, I.; Shiba, M.

    1987-06-01

    Hydrodynamic loads induced in the BWR Mark II pressure suppression containment system during a loss-of-coolant accident (LOCA) were investigated using a large scale test facility. The maximum-bounding loading conditions on the pressure suppression pool-boundary structures were defined by conducting experiments for a wide range of parameters. The maximum-bounding loads occurred when steam, with air concentration less than 1% in weight, was injected at moderate rates (approx. = 30 kg/m/sup 2/.s) into a low-temperature (below 310 K) pool. Such conditions are most likely to be encountered during LOCAs with intermediate break sizes.

  13. LOCA air-injection loads in BWR Mark II pressure suppression containment systems

    Energy Technology Data Exchange (ETDEWEB)

    Kukita, Y.; Shiba, M. (Japan Atomic Energy Research Inst., Tokai, Ibaraki); Namatame, K. (Institute of Nuclear Safety, Tokyo (Japan))

    1984-02-01

    Large-scale blowdown tests were conducted to investigate the thermal-hydrodynamic response of a boiling-water reactor (BWR) Mark II pressure suppression containment system to a postulated loss-of-coolant accident. This paper presents the test results on the early blowdown transients, where air in the drywell is injected into the pressure suppression pool and induces various hydrodynamic loads onto the containment pressure boundary and internal structures. The test data are compared to predictions by analytical models used for the licensing evaluation of the hydrodynamic loads to assess these models.

  14. Effect of non-heterogeneous wetwell boundaries on pressure suppression system response. [BWR

    Energy Technology Data Exchange (ETDEWEB)

    McCauley, E.W.; Holman, G.S.; Namatame, K.; Kukita, Y.; Shiba, M.

    1980-08-29

    The Full-Scale Mark II CRT (Containment Response Test) Program is in progress at the Tokai-Mura Establishment of the Japan Atomic Energy Research Institute (JAERI). The primary objective of the on-going CRT Program is to provide a data base for evaluation of the pressure suppression pool (wetwell) hydrodynamic loads associated with a postulated loss-of-coolant accident (LOCA) in the BWR Mark II containment system. The test facility is 1/18 of full scale in volume and has a wetwell which is a full-scale geometric replica of one 20/sup 0/-sector of a reference 1100MWe Mark II.

  15. A Mechanistic Approach for the Prediction of Critical Power in BWR Fuel Bundles

    Science.gov (United States)

    Chandraker, Dinesh Kumar; Vijayan, Pallipattu Krishnan; Sinha, Ratan Kumar; Aritomi, Masanori

    The critical power corresponding to the Critical Heat Flux (CHF) or dryout condition is an important design parameter for the evaluation of safety margins in a nuclear fuel bundle. The empirical approaches for the prediction of CHF in a rod bundle are highly geometric specific and proprietary in nature. The critical power experiments are very expensive and technically challenging owing to the stringent simulation requirements for the rod bundle tests involving radial and axial power profiles. In view of this, the mechanistic approach has gained momentum in the thermal hydraulic community. The Liquid Film Dryout (LFD) in an annular flow is the mechanism of CHF under BWR conditions and the dryout modeling has been found to predict the CHF quite accurately for a tubular geometry. The successful extension of the mechanistic model of dryout to the rod bundle application is vital for the evaluation of critical power in the rod bundle. The present work proposes the uniform film flow approach around the rod by analyzing individual film of the subchannel bounded by rods with different heat fluxes resulting in different film flow rates around a rod and subsequently distributing the varying film flow rates of a rod to arrive at the uniform film flow rate as it has been found that the liquid film has a strong tendency to be uniform around the rod. The FIDOM-Rod code developed for the dryout prediction in BWR assemblies provides detailed solution of the multiple liquid films in a subchannel. The approach of uniform film flow rate around the rod simplifies the liquid film cross flow modeling and was found to provide dryout prediction with a good accuracy when compared with the experimental data of 16, 19 and 37 rod bundles under BWR conditions. The critical power has been predicted for a newly designed 54 rod bundle of the Advanced Heavy Water Reactor (AHWR). The selected constitutive models for the droplet entrainment and deposition rates validated for the dryout in tube were

  16. Electrical equipment performance under severe accident conditions (BWR/Mark 1 plant analysis): Summary report

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, P.R.; Kolaczkowski, A.M.; Medford, G.T.

    1986-09-01

    The purpose of the Performance Evaluation of Electrical Equipment during Severe Accident States Program is to determine the performance of electrical equipment, important to safety, under severe accident conditions. In FY85, a method was devised to identify important electrical equipment and the severe accident environments in which the equipment was likely to fail. This method was used to evaluate the equipment and severe accident environments for Browns Ferry Unit 1, a BWR/Mark I. Following this work, a test plan was written in FY86 to experimentally determine the performance of one selected component to two severe accident environments.

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

    Directory of Open Access Journals (Sweden)

    Fco. Javier Luna Rosas

    2003-01-01

    Full Text Available 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 ejecución. Los algoritmos de balanceo de carga dinámica intentan equilibrar la carga en tiempo de ejecución. Este artículo propone una nueva forma de balancear la carga dinámicamente aplicando algoritmos genéticos en ambientes distribuidos orientados a objetos CORBA sobre arquitecturas de demanda adaptativa, el artículo se centra en la manera de balancear carga dinámicamente en réplicas homogéneas utilizando el mismo tipo de procesador, requerimiento y velocidad de procesamiento y en réplicas heterogéneas aplicando diferentes procesadores y velocidades de procesamiento.

  18. Algoritmo para la Inspección de Anillos de Compresión

    OpenAIRE

    J. Mauricio de Anda; J.J. Soto Bernal; J.C. Martínez Romo

    2006-01-01

    En el presente trabajo se describe el procedimiento utilizado en el análisis de anillos de compresión para el motor de un auto. Dicho análisis se lleva a cabo usando técnicas de procesamiento de imágenes con la finalidad de determinar si el anillo cumple con los requerimientos suficientes de calidad. El sistema de inspección está integrado por una cámara de video, un sistema de iluminación por leds blancos de alta luminosidad, una tarjeta que recibe la señal de video c...

  19. Um algoritmo genético híbrido para o problema de corte industrial bidimensional

    Directory of Open Access Journals (Sweden)

    Ademir Aparecido Constantino

    2002-04-01

    Full Text Available O objetivo deste trabalho é a implementação de um algoritmo eficaz que solucione o problema de corte bi-dimensional, ou seja, que encontre uma solução muito boa (viável e rápida para este problema, otimizando o uso das chapas para diminuir o desperdício gerado com os cortes que são feitos sobre a mesma. Para a sua implementação, foram utilizados Algoritmos Genéticos como uma técnica de otimização, e o Bottom-Left como uma técnica de encaixe das peças na chapa retangular. Alguns testes foram executados e os resultados ficaram no máximo 10% acima da solução ótima.

  20. Integrando Jogos de Lógica Matemática no Ensino de Algoritmos: Relatos de Experimentos

    Directory of Open Access Journals (Sweden)

    Marcelo Batista de Souza

    2015-11-01

    Full Text Available A dificuldade na aprendizagem de algoritmos é uma realidade enfrentada por estudantes de graduação da área de ciências exatas. Contudo, diferentes abordagens colaboram para minimizar o problema. O presente artigo descreve uma experiência que utilizou lógica matemática e diferentes recursos de programação estruturada na construção do Jogo da Velha e das Tabelas Mágicas e com o objetivo de explorar o raciocínio dos estudantes que culmine na aprendizagem dos conteúdos sobre o assunto. Na implementação, foi utilizado a IDE Free Pascal. O ambiente Moodle apoiou as discussões sobre o tema. Os resultados da pesquisa apontaram avanços no desenvolvimento de algoritmos e programas de computador.

  1. Un algoritmo lingüístico-estadístico para resumen automático de textos especializados

    Directory of Open Access Journals (Sweden)

    Iria Da Cunha

    2009-12-01

    Full Text Available En este trabajo se presenta un nuevo algoritmo de resumen automático de textos especializados, en concreto del dominio médico, que aúna estrategias lingüísticas y estadísticas. La novedad del artículo radica en la correcta combinación de dichas estrategias de cara a demostrar que los sistemas híbridos pueden obtener mejores resultados que los sistemas estadísticos o lingüísticos por sí solos. Se aplica el algoritmo sobre un corpus de textos médicos y se evalúa siguiendo el protocolo de NIST y utilizando el paquete Rouge. Se obtienen excelentes resultados en comparación con otros sistemas y se observa que los resúmenes realizados son muy similares a los de los especialistas del dominio.

  2. 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.

  3. Gerando orientações acíclicas com algoritmos probabilísticos distribuídos

    Directory of Open Access Journals (Sweden)

    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.

  4. Optimización de rutas de transporte público con algoritmos genéticos

    OpenAIRE

    Genovard Abad, Magdalena

    2016-01-01

    Optimización de las líneas de transporte público de una ciudad a través del uso de algoritmos genéticos. Optimization of public transport routes in an ideal city using a genetic algorithm approach. Optimització de les línies de transport públic d'una ciutat a través de l'ús d'algoritmes genètics.

  5. Aulas-laboratorios de bajo costo, usando TIC

    Directory of Open Access Journals (Sweden)

    Silvia E. Calderón

    2015-01-01

    Full Text Available En este trabajo se presentan los resultados de una propuesta educativa orientada a promover el desarrollo de un pensamiento critico y un mayor interes por las ciencias experimentales. Con este fin desarrollamos propuestas de proyectos educativos susceptibles de ser destinadas a las aulas y laboratorios de las escuelas secundarias y primeros anos de la universidad, que resaltan los aspectos metodologicos de las ciencias. Aqui, realizamos una compilacion de varios proyectos, que ilustran formas de incorporar las tecnologias de la informacion y la comunicacion (TIC en diversos experimentos de ciencias, muchos de ellos publicados individualmente anteriormente, y que en conjunto se pueden utilizar para implementar un aula-laboratorio de bajo costo. Con TIC hacemos referencia a la convergencia de computadoras, sistemas audiovisuales, Internet, telefonia, y diversos equipos que se integran con algunos de ellos. Los proyectos intentan integrar areas como fisica, matematica, quimica, informatica, arte, etc. y apuntan a que los estudiantes puedan responder a las preguntas: .Como sabemos esto?, .Por que creemos en aquello? Preguntas que ilustran la naturaleza del pensamiento cientifico. Nuestra contribucion mas significativa es haber desarrollado ≪aulas-laboratorios≫ de muy bajo costo, usando TIC. Con el advenimiento de programas como ≪Una Laptop por Nino≫ que se estan implementando en varios paises de Latinoamerica, resulta oportuno utilizar este recurso como base para generar laboratorios de bajo costo, que creemos pueden ser una herramienta util para mejorar el aprendizaje de las ciencias, incentivar vocaciones y contribuir a desarrollar un pensamiento critico, a la par de desarrollar habilidades con el uso de las TIC que pueden ser de utilidad en diversos ambitos academicos y laborales.

  6. Effect of sensitization and cold work on stress corrosion susceptibility of austenitic stainless steels in BWR and PWR conditions

    Energy Technology Data Exchange (ETDEWEB)

    Haenninen, H.; Aho-Mantila, I.

    1981-05-01

    The influence of metallurgical variables on stress corrosion cracking of austenitic stainless steels, in particular AISI 304 and OX18H10T, has been examined both in O2-enriched BWR-conditions (8 ppm O2) and in typical PWR-conditions.

  7. Analysis of containment venting following a core damage at a BWR Mark I using THALES-2

    Energy Technology Data Exchange (ETDEWEB)

    Widodo, Surip [Nuclear Safety Technology Development Center, National Nuclear Energy Agency (BATAN), Tangerang (Indonesia); Ishikawa, Jun; Muramatsu, Ken [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Sakamoto, Toru [Toshiba Advanced System Co., Kawasaki, Kanagawa (Japan)

    2000-11-01

    Analysis of containment venting following a core damage at a boiling water reactor (BWR) Mark I using THALES-2 was performed. In this analysis, the effect of various parameters, namely, the areas of the vent path, containment venting pressure, and accident sequences on the containment thermodynamic response, and radionuclide transport and release in the containment venting at a BWR was examined. The code THALES-2B developed by the Japan Atomic Energy Research Institute (JAERI) was used in this analysis. The model plant in this analysis was the Browns Ferry plant. From this analysis was found that the 4-inch pipe of containment venting flow path is sufficient to maintain the containment pressure in the specified range if the containment was pressurized by the decay heat power. The entrainment by the pool swelling as well as by the flashing was not occurred during the containment venting. The source terms are not sensitive to the variation of containment venting flow path area. The containment venting pressure operation setting point has important rule in the containment venting. In the containment venting, the source terms are not sensitive to the accident sequence, except for Sr source term. In order to get better understanding on the containment venting strategy, the following analyses are necessary. Analyses of accident sequence which has a high power such as anticipated transient without scram are necessary, as well as analyses of accident sequence which pressurize the containment before the core damage. (author)

  8. TRACE Model for Simulation of Anticipated Transients Without Scram in a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Cheng L. Y.; Baek J.; Cuadra,A.; Aronson, A.; Diamond, D.; Yarsky, P.

    2013-11-10

    A TRACE model has been developed for using theTRACE/PARCS computational package [1, 2] to simulate anticipated transients without scram (ATWS) events in a boiling water reactor (BWR). The model represents a BWR/5 housed in a Mark II containment. The reactor and the balance of plant systems are modeled in sufficient detail to enable the evaluation of plant responses and theeffectiveness of automatic and operator actions tomitigate this beyond design basis accident.The TRACE model implements features thatfacilitate the simulation of ATWS events initiated by turbine trip and closure of the main steam isolation valves (MSIV). It also incorporates control logic to initiate actions to mitigate the ATWS events, such as water levelcontrol, emergency depressurization, and injection of boron via the standby liquid control system (SLCS). Two different approaches have been used to model boron mixing in the lower plenum of the reactor vessel: modulate coolant flow in the lower plenum by a flow valve, and use control logic to modular.

  9. On the Decay Ratio Determination in BWR Stability Analysis by Auto-Correlation Function Techniques

    Energy Technology Data Exchange (ETDEWEB)

    Behringer, K.; Hennig, D

    2002-11-01

    A novel auto-correlation function (ACF) method has been investigated for determining the oscillation frequency and the decay ratio in BWR stability analyses. The neutron signals are band-pass filtered to separate the oscillation peak in the power spectral density (PSD) from background. Two linear second-order oscillation models are considered. These models, corrected for signal filtering and including a background term under the peak in the PSD, are then least-squares fitted to the ACF of the previously filtered neutron signal, in order to determine the oscillation frequency and the decay ratio. Our method uses fast Fourier transform techniques with signal segmentation for filtering and ACF estimation. Gliding 'short-term' ACF estimates on a record allow the evaluation of uncertainties. Numerical results are given which have been obtained from neutron data of the recent Forsmark I and Forsmark II NEA benchmark project. Our results are compared with those obtained by other participants in the benchmark project. The present PSI report is an extended version of the publication K. Behringer, D. Hennig 'A novel auto-correlation function method for the determination of the decay ratio in BWR stability studies' (Behringer, Hennig, 2002)

  10. TRACE Model for Simulation of Anticipated Transients Without Scram in a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Cheng L. Y.; Baek J.; Cuadra,A.; Aronson, A.; Diamond, D.; Yarsky, P.

    2013-11-10

    A TRACE model has been developed for using theTRACE/PARCS computational package [1, 2] to simulate anticipated transients without scram (ATWS) events in a boiling water reactor (BWR). The model represents a BWR/5 housed in a Mark II containment. The reactor and the balance of plant systems are modeled in sufficient detail to enable the evaluation of plant responses and theeffectiveness of automatic and operator actions tomitigate this beyond design basis accident.The TRACE model implements features thatfacilitate the simulation of ATWS events initiated by turbine trip and closure of the main steam isolation valves (MSIV). It also incorporates control logic to initiate actions to mitigate the ATWS events, such as water levelcontrol, emergency depressurization, and injection of boron via the standby liquid control system (SLCS). Two different approaches have been used to model boron mixing in the lower plenum of the reactor vessel: modulate coolant flow in the lower plenum by a flow valve, and use control logic to modular.

  11. High-fidelity multiphysics simulation of BWR assembly with coupled TORT-TD/CTF

    Energy Technology Data Exchange (ETDEWEB)

    Magedanz, J. [Dept. of Mechanical and Nuclear Engineering, Pennsylvania State Univ., Reber Building, Univ. Park, PA 16802 (United States); Perin, Y. [Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS mbH, Forschungsinstitute, D-85748 Garching (Germany); Avramova, M. [Dept. of Mechanical and Nuclear Engineering, Pennsylvania State Univ., Reber Building, Univ. Park, PA 16802 (United States); Pautz, A.; Puente-Espel, F.; Seubert, A.; Sureda, A.; Velkov, K.; Zwermann, W. [Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS mbH, Forschungsinstitute, D-85748 Garching (Germany)

    2012-07-01

    This paper describes the application of the coupled codes TORT-TD and CTF to the pin-by-pin modeling of a BWR fuel assembly with thermal-hydraulic feedback. TORT-TD, developed at GRS, is a time-dependent three dimensional discrete ordinates code. CTF is the PSU's improved version of the subchannel code COBRA-TF, which uses a two-fluid, three-field model to represent two-phase flow with entrained droplets, and is commonly applied to evaluate LWR safety margins. The coupled codes system TORT-TD/CTF, already applied to several PWR cases involving MOX, was adapted from PWR to BWR applications. The purpose of the research described in this paper is to verify the coupling for modeling two-phase flow at the pin cell level. Using an ATRIUM-10 assembly, the system's steady-state capabilities were tested on two cases: one without control blade insertion and another with partially inserted blades. The influence of the neutron absorber on local axial and radial parameters is presented. The description of an inlet flow reduction transient is an example for the time-dependent capability of the coupled system. (authors)

  12. Investigation of control rod worth and nuclear end of life of BWR control rods

    Energy Technology Data Exchange (ETDEWEB)

    Magnusson, Per

    2008-01-15

    This work has investigated the Control Rod Worth (CRW) and Nuclear End of Life (NEOL) values for BWR control rods. A study of how different parameters affect NEOL was performed with the transport code PHOENIX4. It was found that NEOL, expressed in terms of {sup 10}B depletion, can be generalized beyond the conditions for which the rod is depleted, such as different power densities and void fractions, the corresponding variation in the NEOL will be about 0.2-0.4% {sup 10}B. It was also found that NEOL results for different fuel types and different fuel enrichments have a variation of about 2-3% in {sup 10}B depletion. A comparative study on NHOL and CRW was made between PHOENIX4 and the stochastic Monte Carlo code MCNP. It was found that there is a significant difference, both due to differences in the codes and to limitations in the geometrical modeling in PHOENIX4. Since MCNP is considered more physically correct, a methodology was developed to calculate the nuclear end of life of BWR control rods with MCNP. The advantages of the methodology are that it does not require other codes to perform the depletion of the absorber material, it can describe control rods of any design and it can deplete the control rod absorber material without burning the fuel. The disadvantage of the method is that is it time-consuming.

  13. Transient and stability analysis of a BWR core with thorium-uranium fuel

    Energy Technology Data Exchange (ETDEWEB)

    Nunez-Carrera, Alejandro [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779 Col. Narvarte, 03020 Mexico, DF (Mexico); Espinosa-Paredes, Gilberto [Division de Ciencias Basicas e Ingenieria, Universidad Autonoma Metropolitana, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico, DF (Mexico)], E-mail: gepe@xanum.uam.mx; Francois, Juan-Luis [Departamento de Sistemas Energeticos, Facultad de Ingenieria, Universidad Nacional Autonoma de Mexico, Paseo Cuauhnahuac 8532, 62550 Jiutepec Mor. (Mexico)

    2008-08-15

    The kinetic response of a boiling water reactor (BWR) equilibrium core using thorium as a nuclear material, in an integrated blanket-seed assembly, is presented in this work. Additionally an in-house code was developed to evaluate this core under steady state and transient conditions including a stability analysis. The code has two modules: (a) the time domain module for transient analysis and (b) the frequency domain module for stability analysis. The thermal-hydraulic process is modeled by a set of five equations, considering no homogeneous flow with drift-flux approximation and non-equilibrium thermodynamic. The neutronic process is calculated with a point kinetics model. Typical BWR reactivity effects are considered: void fraction, fuel temperature, moderator temperature and control rod density. Collapsed parameters were included in the code to represent the core using an average fuel channel. For the stability analysis, in the frequency domain, the transfer function is determined by applying Laplace-transforming to the calculated pressure drop perturbations in each of the considered regions where a constant total pressure drop was considered. The transfer function was used to study the system response in the frequency domain when an inlet flow perturbation is applied. The results show that the neutronic behavior of the core with thorium uranium fuel is similar to a UO{sub 2} core, even during transient conditions. The stability and transient analysis show that the thorium-uranium fuel can be operated safely in current BWRs.

  14. Identification and initial assessment of candidate BWR late-phase in-vessel accident management strategies

    Energy Technology Data Exchange (ETDEWEB)

    Hodge, S.A.

    1991-04-15

    Work sponsored by the United States Nuclear Regulatory Commission (USNRC) to identify and perform preliminary assessments of candidate BWR (boiling water reactor) in-vessel accident management strategies was completed at Oak Ridge National Laboratory (ORNL) during fiscal year 1990. Mitigative strategies for containment events have been the subject of a companion study at Brookhaven National Laboratory. The focus of this Oak Ridge effort was the development of new strategies for mitigation of the late phase events, that is, the events that would occur in-vessel after the onset of significant core damage. The work began with an investigation of the current status of BWR in-vessel accident management procedures and proceeded through a preliminary evaluation of several candidate new strategies. The steps leading to the identification of the candidate strategies are described. The four new candidate late-phase (in-vessel) accident mitigation strategies identified by this study and discussed in the report are: (1) keep the reactor vessel depressurized; (2) restore injection in a controlled manner; (3) inject boron if control blade damage has occurred; and (4) containment flooding to maintain core and structural debris in-vessel. Additional assessments of these strategies are proposed.

  15. Algoritmo de roteamento com balanceamento de carga adaptado a redes ópticas elásticas

    Directory of Open Access Journals (Sweden)

    Ítalo Barbosa Brasileiro

    2017-05-01

    Full Text Available Com a evolução dos meios de transmissão de dados, surgem as Redes Ópticas que utilizam a tecnologia Orthogonal Frequency-Division Multiplexing (OFDM, transportando o dados em slots de frequência, que podem ser agrupados para formar canais com maior capacidade de transmissão. Para estabelecer um lightpath entre dois nós da rede, é necessário escolher uma rota e um conjunto de slots, exigindo a criação de algoritmos de roteamento e alocação de espectro que melhor utilizem os recursos disponíveis na rede. O algoritmo proposto neste trabalho é uma adaptação do algoritmo de roteamento fixo LBR, permitindo escolher rotas para os pares de nós de modo a balancear a carga total da rede. O desempenho foi avaliado através de simulações, na qual o LBR é comparado ao Dijkstra e apresenta desempenho superior.

  16. Un algoritmo para la realización de grafos con las actividades en los arcos -grafos pert-

    Directory of Open Access Journals (Sweden)

    Angel M. Gento Municio

    2005-01-01

    Full Text Available El problema de dibujar redes con las actividades en los arcos (redes PERT es un problema NP-completo. Diferentes autores (Syslo, 1984 han establecido límites al mismo. En primer lugar debemos diferenciar entre redes con actividades en los nudos y redes con actividades en los arcos. Si las actividades están en los nudos, el dibujo de la red es muy fácil, pero cuando las actividades están en los arcos, generalmente es necesaria la utilización de actividades ficticias para mantener de forma correcta las relaciones entre las actividades. En este artículo se propone un sencillo y didáctico algoritmo para el caso de un pequeño número de nodos donde es necesario un algoritmo intuitivo. En el algoritmo se definen cuatro tipos diferentes de nodos que pueden aparecer en el grafo, permitiéndonos identificar las actividades ficticias tal y como se muestra en un ejemplo.

  17. 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.

  18. 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.

  19. Implementación del algoritmo del replicador dinámico en Lenguaje R

    Directory of Open Access Journals (Sweden)

    Isabel Quintas Pereira

    2013-01-01

    Full Text Available Se presenta la implementación en Lenguaje R de una derivación del replicador dinámico para analizar y simular características culturales de la sociedad con el modelo evolutivo, similar al enfoque utilizado en biología. El algoritmo escrito es una solución por diferencias finitas de la versión del replicador dinámico presentada por Bowles y Gintis con un alto nivel de generalidad para permitir al investigador utilizarlo para modelar distintas situaciones, con sólo definir las funciones de probabilidades de contacto e interacción entre grupos y las funciones de pagos. Se decidió utilizar el Lenguaje R porque a pesar de su creación como una herramienta estadística, se difunde en una diversidad de aplicaciones; además su calidad de intérprete lo hace accesible a personas sin educación formal en cómputo.

  20. Algoritmo de Compresión de Datos para la Arquitectura MOLAP

    Directory of Open Access Journals (Sweden)

    María Trinidad Serna Encinas

    2012-01-01

    Full Text Available La tecnología para el procesamiento analítico en línea (OLAP se mueve cada vez más hacia el uso de manejadores de bases de datos multidimensionales. Debido a su naturaleza física, la forma en que estos sistemas funcionan y al crecimiento en el volumen de datos, llevan a las empresas a incrementar la capacidad de almacenamiento de sus sistemas, además del poder de procesamiento de éstos. La compresión de los cubos de datos generados por los sistemas de procesamiento analítico multidimensional en línea (MOLAP, puede reducir de forma significativa el tamaño del archivo y por consiguiente, el espacio en disco requerido. Este artículo propone un algoritmo capaz de comprimir un cubo de datos, que sea capaz de atender consultas de forma rápida y eficiente, para el manejo de información contenida en un almacén de datos, sin causar un impacto en el manejo de otros recursos.

  1. Analysis of a German BWR core with TRACE/PARCS using different cross section sets

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann, C., E-mail: Christoph.Hartmann@kit.edu [Karlsruhe Inst. of Tech. (KIT), Inst. for Neutron Physics and Reactor Technology (INR), Eggenstein-Leopoldshafen (Germany); Westinghouse Electric Germany GmbH, Mannheim (Germany); Sanchez, V.H. [Karlsruhe Inst. of Tech. (KIT), Inst. for Neutron Physics and Reactor Technology (INR), Eggenstein-Leopoldshafen (Germany); Tietsch, W. [Westinghouse Electric Germany GmbH, Mannheim (Germany)

    2011-07-01

    'Full text:' Coupled Thermal-hydraulic/Neutron-kinetic (TH/NK) simulations of Boiling Water Reactor transients require well validated and accurate simulation tools as well as appropriate cross sections (XS) libraries depending on the individual thermal hydraulic state parameters. Problem-dependent XS-sets for 3D core simulations are being generated mainly by well validated, fast running and user-friendly lattice codes such as Casco and Helios. At research institutions and universities, alternative tools to the commercial ones with full access to the source code as well as moderate cost are urgently needed. The Scale system is being developed and improved for lattice physics calculations of real core loading of Light Water Reactors (LWR). It represents a promising alternative to the commercial lattice codes. At Karlsruhe Institute of Technology (Kit) a computational route based on Scale/Triton/Newt for BWR core loading is under development. The generated XS-data sets have to be transformed in PMAXS-format for use in the reactor dynamic code PARCS. This task is performed by the module GenPMAXS being developed and tested at the Michigan University. To verify the computational route, a BWR fuel assembly depletion problem was calculated by PARCS and compared to the CASMO results. Since the SCALE/TRITON XS-file does actually not contain all required neutronic data, FORTRAN routines have been developed to incorporate the missing data e.g. the yields of Iodine, Xenon and Promethium into the XS-data sets in the PMAXS-format. The comparison of the results obtained with PARCS (using the corrected PMAXS file) and CASMO for the depletion problem exhibited a good agreement. Consequently, this approach was followed for the generation of a complete XS-set for a real BWR core to be used in subsequent transient analysis. Then 3D neutronic and thermal hydraulic core model were elaborated for a TRACE/PARCS analysis. The thermal hydraulic model is based on the 3D VESSEL

  2. Prediction of the stability of BWR reactors during the start-up process; Prediccion de la estabilidad de reactores BWR durante el proceso de arranque

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz E, J.A.; Castillo D, R. [ININ, Km. 36.5 Carretera Mexico-Toluca, 52045 Salazar, Estado de Mexico (Mexico); Blazquez M, J.B. [Centro de Investigaciones Energetics, Medioambientales y Tecnologicas, Av Complutense 22, 28040 Madrid (Spain)

    2004-07-01

    The Boiling Water Reactors (BWR) are susceptible of uncertainties of power when they are operated to low flows of coolant (W) and high powers (P), being presented this situation mainly in the start-up process. The start-up process could be made but sure if the operator knew the value of the stability index Decay reason (Dr) before going up power and therefore to guarantee the stability. The power and the flow are constantly measures, the index Dr could also be considered its value in real time. The index Dr depends on the power, flow and many other values, such as, the distribution of the flow axial and radial neutronic, the temperature of the feeding water, the fraction of holes and other thermohydraulic and nuclear parameters. A simple relationship of Dr is derived leaving of the pattern reduced of March-Leuba, where three independent variables are had that are the power, the flow and a parameter that it contains the rest of the phenomenology, that is to say all the other quantities that affect the value of Dr. This relationship developed work presently and verified its prediction with data of start-up of commercial reactors could be used for the design of a practical procedure practice of start-up, what would support to the operator to prevent this type of events of uncertainty. (Author)

  3. Optimization of fuel cells for BWR based in Tabu modified search; Optimizacion de celdas de combustible para BWR basada en busqueda Tabu modificada

    Energy Technology Data Exchange (ETDEWEB)

    Martin del Campo M, C.; Francois L, J.L. [Facultad de Ingenieria, UNAM, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Palomera P, M.A. [Facultad de Ingenieria, UNAM, Posgrado en Ingenieria en Computacion, Circuito exterior s/n, Ciudad Universitaria, Mexico, D.F. (Mexico)]. e-mail: cmcm@fi-b.unam.mx

    2004-07-01

    The advances in the development of a computational system for the design and optimization of cells for assemble of fuel of Boiling Water Reactors (BWR) are presented. The method of optimization is based on the technique of Tabu Search (Tabu Search, TS) implemented in progressive stages designed to accelerate the search and to reduce the time used in the process of optimization. It was programed an algorithm to create the first solution. Also for to diversify the generation of random numbers, required by the technical TS, it was used the Makoto Matsumoto function obtaining excellent results. The objective function has been coded in such a way that can adapt to optimize different parameters like they can be the enrichment average or the peak factor of radial power. The neutronic evaluation of the cells is carried out in a fine way by means of the HELIOS simulator. In the work the main characteristics of the system are described and an application example is presented to the design of a cell of 10x10 bars of fuel with 10 different enrichment compositions and gadolinium content. (Author)

  4. SUN-RAH: a nucleoelectric BWR university simulator based in reduced order models; SUN-RAH: simulador universitario de nucleoelectrica BWR basado en modelos de orden reducido

    Energy Technology Data Exchange (ETDEWEB)

    Morales S, J.B.; Lopez R, A.; Sanchez B, A.; Sanchez S, R.; Hernandez S, A. [DEPFI, Campus Morelos, en IMTA Jiutepec, Morelos (Mexico)]. e-mail: jms0620@yahoo.com

    2003-07-01

    The development of a simulator that allows to represent the dynamics of a nucleo electric central, with nuclear reactor of the BWR type, using reduced order models is presented. These models present the characteristics defined by the dominant poles of the system (1) and most of those premature operation transitories in a power station can be reproduced with considerable fidelity if the models are identified with data of plant or references of a code of better estimate like RAMONA, TRAC (2) or RELAP. The models of the simulator are developments or own simplifications starting from the physical laws and retaining the main terms. This work describes the objective of the project and the general specifications of the University student of Nucleo electric simulator with Boiling Water Reactor type (SUN-RAH) as well as the finished parts that fundamentally are the nuclear reactor, the one of steam supply (NSSS), the plant balance (BOP), the main controllers of the plant and the implemented graphic interfaces. The pendent goals as well as the future developments and applications of SUN-RAH are described. (Author)

  5. Artificial intelligence applied to fuel management in BWR type reactors; Inteligencia artificial aplicada a la administracion de combustible en reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz S, J.J

    1998-10-01

    In this work two techniques of artificial intelligence, neural networks and genetic algorithms were applied to a practical problem of nuclear fuel management; the determination of the optimal fuel reload for a BWR type reactor. This is an important problem in the design of the operation cycle of the reactor. As a result of the application of these techniques, comparable or even better reloads proposals than those given by expert companies in the subject were obtained. Additionally, two other simpler problems in reactor physics were solved: the determination of the axial power profile and the prediction of the value of some variables of interest at the end of the operation cycle of the reactor. Neural networks and genetic algorithms have been applied to solve many problems of engineering because of their versatility but they have been rarely used in the area of fuel management. The results obtained in this thesis indicates the convenience of undertaking further work on this area and suggest the application of these techniques of artificial intelligence to the solution of other problems in nuclear reactor physics. (Author)

  6. 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.

  7. Secuenciación de tareas en el ámbito de la producción: Una aplicación del algoritmo del recocido simulado.

    Directory of Open Access Journals (Sweden)

    Paloma Martínez Almodóvar

    2004-01-01

    Full Text Available Un problema esencial en la Dirección de Operaciones en entornos industriales y manufactureros es la determinación de la secuencia óptima en la que ejecutar los distintos lotes de productos de manera que se minimicen los tiempos de preparación de máquinas. Se trata de un problema de optimización combinatoria que obliga a utilizar técnicas heurísticas ante la imposibilidad práctica de llevar a cabo búsquedas exhaustivas. Un algoritmo muy conocido por su sencillez es el de Kaufmann, que tiene el inconveniente de que proporciona un óptimo local que puede ser poco adecuado. En nuestro trabajo hemos elaborado un programa de ordenador en lenguaje C que implementa dicho algoritmo con algunas modificaciones y otro programa que implementa el algoritmo del Recocido Simulado, el cual suele proporcionar buenos resultados en problemas de optimización combinatoria al conseguir evitar óptimos locales. Para la implementación se ha utilizado una serie de subrutinas en C proporcionadas por la GNU Scientific Library. Se ha comparado el desempeño de ambos algoritmos y se han buscado los parámetros que permiten ajustar de forma adecuada el algoritmo del Recocido Simulado para su uso eficiente en estos problemas de minimización de los tiempos de preparación de máquinas.

  8. Kuosheng BWR/6 containment pressure and temperature responses after recirculation line break using GOTHIC code

    Energy Technology Data Exchange (ETDEWEB)

    Lin, A.; Wang, J-R.; Chen, Y-S., E-mail: samuellin1999@iner.gov.tw, E-mail: jrwang@iner.gov.tw, E-mail: yschen@iner.gov.tw [Inst. of Nuclear Energy Research Atomic Energy Council (China); Shih, C., E-mail: ckshih@ess.nthu.edu.tw [National Tsing Hua Univ., Dept. of Engineering and System Science (China)

    2011-07-01

    In this study, we presented the calculated results of the containment P/T (pressure and temperature) response after the recirculation line break (RCLB) accident of a GE-designed twin-unit BWR/6 plant, which can be served as the design basis for the containment system. During the simulation, a power of SPU (stretch power uprate) range was used and a model of the Mark III type containment was built using the GOTHIC (Generation of Thermal-Hydraulic Information for Containments) code. The calculated results, similar to the FSAR (Final Safety Analysis Report) results, indicate the GOTHIC code has the capability to simulate the containment P/T response to the RCLB accident. (author)

  9. Experimental simulation of the water cooling of corium spread over the floor of a BWR containment

    Energy Technology Data Exchange (ETDEWEB)

    Morage, F.; Lahey, R.T. Jr.; Podowski, M.Z. [Rensselaer Polytechnic Institute, Troy, NY (United States)

    1995-09-01

    This paper is concerned with an experimental investigation of the cooling effect of water collected on the surface of corium released onto the floor of a BWR drywell. In the present experiments, the actual reactor materials were replaced by simulant materials. Specifically, the results are shown for Freon-11 film boiling over liquid Wood`s metal spread above a solid porous surface through which argon gas was injected. An analysis of the obtained experimental data revealed that the actual film boiling heat transfer between a molten pool of corium and the water above the pool should be more efficient than predicted by using standard correlations for boiling over solid surfaces. This effect will be further augmented by the gas released due to the ablation of concrete floor beneath the corium and percolating towards its upper surface and into through the water layer above.

  10. Optimized clearing work concept for the BWR containment; Optimiertes Raeumungskonzept fuer SWR-Sicherheitsbehaelter

    Energy Technology Data Exchange (ETDEWEB)

    Kraps, Uwe [AREVA NP GmbH (Germany)

    2012-11-01

    Based on the experiences of reactor dismantling in the NPPs Wuergasse, Obrigheim and Stade an optimized clearing work concept for the BWR containment including the reactor pressure vessel and the biological shield was developed. The concept is focused on the safety objective, the reduction of the collective dose and the reduction of the execution time. Precondition for the decommissioning license was up to now the removal of fuel elements from the reactor; due to the significantly increased period until fulfillment of this premises concepts are developed that can be performed with simultaneous reduction of the radiological inventories and the fire loads. The most important step of the guideline of the concept is the transition from hot to cold. The in-situ disassembling of the reactor internals can be performed with decreased water level in the reactor pressure vessel, with following water treatment and complete shutdown of operational systems. This status allows an accelerated further dismantling of the plant.

  11. Non-local two phase flow momentum transport in S BWR

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa P, G.; Salinas M, L.; Vazquez R, A., E-mail: gepe@xanum.uam.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Area de Ingenieria en Recursos Energeticos, Apdo. Postal 55-535, 09340 Ciudad de Mexico (Mexico)

    2015-09-15

    The non-local momentum transport equations derived in this work contain new terms related with non-local transport effects due to accumulation, convection, diffusion and transport properties for two-phase flow. For instance, they can be applied in the boundary between a two-phase flow and a solid phase, or in the boundary of the transition region of two-phase flows where the local volume averaging equations fail. The S BWR was considered to study the non-local effects on the two-phase flow thermal-hydraulic core performance in steady-state, and the results were compared with the classical local averaging volume conservation equations. (Author)

  12. Revised uranium--plutonium cycle PWR and BWR models for the ORIGEN computer code

    Energy Technology Data Exchange (ETDEWEB)

    Croff, A. G.; Bjerke, M. A.; Morrison, G. W.; Petrie, L. M.

    1978-09-01

    Reactor physics calculations and literature searches have been conducted, leading to the creation of revised enriched-uranium and enriched-uranium/mixed-oxide-fueled PWR and BWR reactor models for the ORIGEN computer code. These ORIGEN reactor models are based on cross sections that have been taken directly from the reactor physics codes and eliminate the need to make adjustments in uncorrected cross sections in order to obtain correct depletion results. Revised values of the ORIGEN flux parameters THERM, RES, and FAST were calculated along with new parameters related to the activation of fuel-assembly structural materials not located in the active fuel zone. Recommended fuel and structural material masses and compositions are presented. A summary of the new ORIGEN reactor models is given.

  13. Safety/relief valve quencher loads: evaluation for BWR Mark II and III containments

    Energy Technology Data Exchange (ETDEWEB)

    Su, T.M.

    1982-10-01

    Boiling water reactor (BWR) plants are equipped with safety/relief valves (SRVs) to protect the reactor from overpressurization. Plant operational transients, such as turbine trips, will actuate the SRV. Once the SRV opens, the air column within the partially submerged discharge line is compressed by the high-pressure steam released from the reactor. The compressed air discharged into the suppression pool produces high-pressure bubbles. Oscillatory expansion and contraction of these bubbles create hydrodynamic loads on the containment structures, piping, and equipment inside containment. This report presents the results of the staff's evaluation of SRV loads. The evaluation, however, is limited to the quencher devices used in Mark II and III containments. With respect to Mark I containments, the SRV acceptance criteria are presented in NUREG-0661 issued July 1980. The staff acceptance criteria for SRV loads for Mark II and III containments are presented in this report.

  14. Modeling of BWR core meltdown accidents - for application in the MELRPI. MOD2 computer code

    Energy Technology Data Exchange (ETDEWEB)

    Koh, B R; Kim, S H; Taleyarkhan, R P; Podowski, M Z; Lahey, Jr, R T

    1985-04-01

    This report summarizes improvements and modifications made in the MELRPI computer code. A major difference between this new, updated version of the code, called MELRPI.MOD2, and the one reported previously, concerns the inclusion of a model for the BWR emergency core cooling systems (ECCS). This model and its computer implementation, the ECCRPI subroutine, account for various emergency injection modes, for both intact and rubblized geometries. Other changes to MELRPI deal with an improved model for canister wall oxidation, rubble bed modeling, and numerical integration of system equations. A complete documentation of the entire MELRPI.MOD2 code is also given, including an input guide, list of subroutines, sample input/output and program listing.

  15. Development of a parametric containment event tree model for a severe BWR accident

    Energy Technology Data Exchange (ETDEWEB)

    Okkonen, T. [OTO-Consulting Ay, Helsinki (Finland)

    1995-04-01

    A containment event tree (CET) is built for analysis of severe accidents at the TVO boiling water reactor (BWR) units. Parametric models of severe accident progression and fission product behaviour are developed and integrated in order to construct a compact and self-contained Level 2 PSA model. The model can be easily updated to correspond to new research results. The analyses of the study are limited to severe accidents starting from full-power operation and leading to core melting, and are focused mainly on the use and effects of the dedicated severe accident management (SAM) systems. Severe accident progression from eight plant damage states (PDS), involving different pre-core-damage accident evolution, is examined, but the inclusion of their relative or absolute probabilities, by integration with Level 1, is deferred to integral safety assessments. (33 refs., 5 figs., 7 tabs.).

  16. Simulation of Thermal Stratification in BWR Suppression Pools with One Dimensional Modeling Method

    Energy Technology Data Exchange (ETDEWEB)

    Haihua Zhao; Ling Zou; Hongbin Zhang

    2014-01-01

    The suppression pool in a boiling water reactor (BWR) plant not only is the major heat sink within the containment system, but also provides the major emergency cooling water for the reactor core. In several accident scenarios, such as a loss-of-coolant accident and extended station blackout, thermal stratification tends to form in the pool after the initial rapid venting stage. Accurately predicting the pool stratification phenomenon is important because it affects the peak containment pressure; the pool temperature distribution also affects the NPSHa (available net positive suction head) and therefore the performance of the Emergency Core Cooling System and Reactor Core Isolation Cooling System pumps that draw cooling water back to the core. Current safety analysis codes use zero dimensional (0-D) lumped parameter models to calculate the energy and mass balance in the pool; therefore, they have large uncertainties in the prediction of scenarios in which stratification and mixing are important. While three-dimensional (3-D) computational fluid dynamics (CFD) methods can be used to analyze realistic 3-D configurations, these methods normally require very fine grid resolution to resolve thin substructures such as jets and wall boundaries, resulting in a long simulation time. For mixing in stably stratified large enclosures, the BMIX++ code (Berkeley mechanistic MIXing code in C++) has been developed to implement a highly efficient analysis method for stratification where the ambient fluid volume is represented by one-dimensional (1-D) transient partial differential equations and substructures (such as free or wall jets) are modeled with 1-D integral models. This allows very large reductions in computational effort compared to multi-dimensional CFD modeling. One heat-up experiment performed at the Finland POOLEX facility, which was designed to study phenomena relevant to Nordic design BWR suppression pool including thermal stratification and mixing, is used for

  17. An efficient modeling method for thermal stratification simulation in a BWR suppression pool

    Energy Technology Data Exchange (ETDEWEB)

    Haihua Zhao; Ling Zou; Hongbin Zhang; Hua Li; Walter Villanueva; Pavel Kudinov

    2012-09-01

    The suppression pool in a BWR plant not only is the major heat sink within the containment system, but also provides major emergency cooling water for the reactor core. In several accident scenarios, such as LOCA and extended station blackout, thermal stratification tends to form in the pool after the initial rapid venting stage. Accurately predicting the pool stratification phenomenon is important because it affects the peak containment pressure; and the pool temperature distribution also affects the NPSHa (Available Net Positive Suction Head) and therefore the performance of the pump which draws cooling water back to the core. Current safety analysis codes use 0-D lumped parameter methods to calculate the energy and mass balance in the pool and therefore have large uncertainty in prediction of scenarios in which stratification and mixing are important. While 3-D CFD methods can be used to analyze realistic 3D configurations, these methods normally require very fine grid resolution to resolve thin substructures such as jets and wall boundaries, therefore long simulation time. For mixing in stably stratified large enclosures, the BMIX++ code has been developed to implement a highly efficient analysis method for stratification where the ambient fluid volume is represented by 1-D transient partial differential equations and substructures such as free or wall jets are modeled with 1-D integral models. This allows very large reductions in computational effort compared to 3-D CFD modeling. The POOLEX experiments at Finland, which was designed to study phenomena relevant to Nordic design BWR suppression pool including thermal stratification and mixing, are used for validation. GOTHIC lumped parameter models are used to obtain boundary conditions for BMIX++ code and CFD simulations. Comparison between the BMIX++, GOTHIC, and CFD calculations against the POOLEX experimental data is discussed in detail.

  18. Influence of iron and nickel species upon activity buildup under simulated BWR conditions

    Energy Technology Data Exchange (ETDEWEB)

    Bjornsson, S.; Chen, J. [Studsvik Nuclear AB, Nykoping (Sweden); Lejon, J. [OKG AB, Oskarshamn (Sweden); Granath, G. [Ringhals AB, Varobacka (Sweden); Tanse-Larsson, M. [Forsmarks Kraftgrupp AB, Osthammar (Sweden)

    2010-07-01

    Activity build-up in BWR systems are of importance for service- and maintenance work performed at the plants. Minimizing the activity build-up is desirable for minimizing doses of personnel at the plants. Numerous studies have been carried out in this important field to understand the activity uptake mechanisms. This paper studied the possible role of Fe(II/III) and Ni(II) impurities in reactor water in activity uptake on stainless steel surfaces. The study was carried out by using a test loop with simulated BWR water containing Fe(II/III), Ni(II) and Co-60 marked Co(II) species of varied concentration and 500 ppb O{sub 2}. The test tube section in the loop system was pre-exposed type 316L stainless steel material. The microstructures of the formed oxide films were examined with high resolution electron microscopy (FE-SEM and FE-TEM). The activity monitoring on the test section showed that injection of 10 ppb Ni(II) and 0.1 ppb Fe(II/III) in the water with 0.1 ppb Co(II) was capable of stopping completely activity uptake. When Co(II) addition in the loop was stopped no activity return to the water could be seen. In another exposure test, injection of combined 2 ppb Fe(II/III) and 0.5∼10 ppb Ni(II) profoundly increased activity uptake on the test section with a maximum in activity buildup at 5 ppb Ni(II). When Co(II) addition in the loop was stopped a slight activity return was seen. The observed differences as seen in the two tests are discussed in view of the microstructures of the oxide films formed. (author)

  19. CSAU methodology and results for an ATWS event in a BWR using information theory methods

    Energy Technology Data Exchange (ETDEWEB)

    Munoz-Cobo, J.L., E-mail: jlcobos@iqn.upv.es [Universitat Politècnica de València, Thermal-Hydraulics and Nuclear Engineering Group (TIN), Institute for Energy Engineering (IEE), Valencia (Spain); Escrivá, A., E-mail: aescriva@iqn.upv.es [Universitat Politècnica de València, Thermal-Hydraulics and Nuclear Engineering Group (TIN), Institute for Energy Engineering (IEE), Valencia (Spain); Mendizabal, R., E-mail: rmsanz@csn.es [Consejo de Seguridad Nuclear, 28040 Madrid (Spain); Pelayo, F., E-mail: fpl@csn.es [Consejo de Seguridad Nuclear, 28040 Madrid (Spain); Melara, J., E-mail: jls@iberdrola.es [IBERINCO, IBERDROLA Ingeniería y Construcción, Madrid (Spain)

    2014-10-15

    Highlights: • We apply the CSAU methodology to an ATWS in a BWR using information theory methods. • We show how to perform the selection of the most influential inputs on the critical safety parameter. • We apply the maximum entropy principle to get the input parameter distribution. • We examine the maximum relative entropy principle to update the input parameter PDF. • We quantify the uncertainty of the critical safety parameter using order statistics and information theory. - Abstract: This paper shows an application of the CSAU methodology to an ATWS in a BWR reactor, when the temperature of the suppression pool is taken as the critical safety parameter. The method combines CSAU methodology with recent techniques of information theory. In this paper we use auxiliary tools to help in the evaluation and improvement of the parameters distribution that enter in the elements II and III of CSAU based methodologies. These tools have been implemented in two FORTRAN programs: GEDIPA (Generation of the Parameter Distribution) and UNTHERCO (Uncertainty in Thermal Hydraulic Codes). The first one analyzes the information data available on a given parameter or parameters with the goal to know all the information about the probability distribution function of these parameters. The second apply information theory methods, as the maximum entropy principle (MEP) and the maximum relative entropy Principle (MREP), in order to build conservative distribution functions for the parameters from the available data. Also, the distribution function of a given parameter can be updated using the MREP principle when new information is provided. UNTHERCO performs the MONTECARLO sampling for a given set of parameters when the distribution function of these parameters is previously known. If the distribution of a parameter is unknown, then, the MEP is applied to deduce the distribution function for this parameter.

  20. Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Y. [Argonne National Lab. (ANL), Argonne, IL (United States); Chopra, O. K. [Argonne National Lab. (ANL), Argonne, IL (United States); Gruber, Eugene E. [Argonne National Lab. (ANL), Argonne, IL (United States); Shack, William J. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2010-06-01

    The internal components of light water reactors are exposed to high-energy neutron irradiation and high-temperature reactor coolant. The exposure to neutron irradiation increases the susceptibility of austenitic stainless steels (SSs) to stress corrosion cracking (SCC) because of the elevated corrosion potential of the reactor coolant and the introduction of new embrittlement mechanisms through radiation damage. Various nonsensitized SSs and nickel alloys have been found to be prone to intergranular cracking after extended neutron exposure. Such cracks have been seen in a number of internal components in boiling water reactors (BWRs). The elevated susceptibility to SCC in irradiated materials, commonly referred to as irradiation-assisted stress corrosion cracking (IASCC), is a complex phenomenon that involves simultaneous actions of irradiation, stress, and corrosion. In recent years, as nuclear power plants have aged and irradiation dose increased, IASCC has become an increasingly important issue. Post-irradiation crack growth rate and fracture toughness tests have been performed to provide data and technical support for the NRC to address various issues related to aging degradation of reactor-core internal structures and components. This report summarizes the results of the last group of tests on compact tension specimens from the Halden-II irradiation. The IASCC susceptibility of austenitic SSs and heat-affected-zone (HAZ) materials sectioned from submerged arc and shielded metal arc welds was evaluated by conducting crack growth rate and fracture toughness tests in a simulated BWR environment. The fracture and cracking behavior of HAZ materials, thermally sensitized SSs and grain-boundary engineered SSs was investigated at several doses (≤3 dpa). These latest results were combined with previous results from Halden-I and II irradiations to analyze the effects of neutron dose, water chemistry, alloy compositions, and welding and processing conditions on IASCC

  1. Cofrentes EOC16B poolside measurements of channels from the three BWR vendors

    Energy Technology Data Exchange (ETDEWEB)

    Sedano, Pablo J. Garcia; Ayuela, Javier Iglesias [Iberdrola Ingenieria Construccion SAU, Veronica Anaures (Mexico); Albendea, Manuel [Iberdrola Generation S. A., Plaza Euskadi, 5 48009 BILBAO (Spain)

    2008-10-15

    As part of the EPRI Fuel Reliability Program, a fuel channel focus group was formed in 2002 to initiate measurements on irradiated BWR fuel channels. Fuel channels from GNF and AREVA have been measured in campaigns performed during 2004{approx}2007. Fuel channels designed and supplied by Westinghouse were of particular interest since no measurement information had been previously taken on modern Westinghouse channels operating on conventional loading pattern cycles, either in European or U.S. plants. Conventional loading pattern cycles are more susceptible to experience shadow corrosion induced bow since the fresh bundles are exposed to control blade influence early in life. During summer of 2007 extensive poolside measurements of a total of 180 fuel channels (24 SVEA-96 +/L, 68 SVEA-96 Optima-2, 36 GE-12, 42 GE-14 and 10 ATRIUM-10XP) have been performed by Westinghouse at Cofrentes NPP (Spanish BWR-6 operating on 24 month cycle strategy). This campaign has been co-sponsored by EPRI, Iberdrola and Westinghouse Sweden. Channels covering a range of exposure and control blade history were selected in order to determine the dependency of the channel deformation with those parameters. Channels with the most limiting conditions of exposure and control blade history were included. Channel bow, bulge and twist have been measured and fast neutron fluence calculations have been performed in order to determine the effects of neutron fluence gradient and shadow corrosion on the total channel deformation. Additionally channel oxide measurements have been performed on 20 channels from the three fuel vendors.The results indicate that channel bow and bulge remained at anticipated levels with no indication of significant channel bow due to shadow corrosion phenomenon. Destructive metallographic evaluations of samples taken from one cycle Westinghouse channels with high control blade exposure are underway at Studsvik hot cell facilities. These examinations will provide additional

  2. Analysis of the performance of fuel cells BWR with a single enrichment and radial distribution of enrichments; Analisis del desempeno de celdas combustibles BWR con un solo enriquecimiento y con distribucion radial de enriquecimientos

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, J. A.; Vargas, S.; Alonso, G.; Del Valle, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Col. Lindavista, Mexico D. F. 07738 (Mexico); Xolocostli M, J. V. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: govaj666@hotmail.com

    2008-07-01

    The efficient use of the fuel is one of the objectives in the assemblies design of type BWR. The present tendency in the assemblies design of type BWR is through a radial distribution of enrichments. The present work has like object showing the because of this decision, for what a comparison of the neutronic performance of two fuel cells with the same enrichment average but one of them with radial distribution of enrichment and the other with a single enrichment equal to the average. The cells were analyzed with the CASMO-4 code and the obtained results of the behavior of the neutron flow and the power sustain the because of the radial distribution of enrichments. (Author)

  3. Comparative analysis of results between CASMO, MCNP and Serpent for a suite of Benchmark problems on BWR reactors; Analisis comparativo de resultados entre CASMO, MCNP y SERPENT para una suite de problemas Benchmark en reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Xolocostli M, J. V.; Vargas E, S.; Gomez T, A. M. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Reyes F, M. del C.; Del Valle G, E., E-mail: vicente.xolocostli@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, UP - Adolfo Lopez Mateos, Edif. 9, 07738 Mexico D. F. (Mexico)

    2014-10-15

    In this paper a comparison is made in analyzing the suite of Benchmark problems for reactors type BWR between CASMO-4, MCNP6 and Serpent code. The Benchmark problem consists of two different geometries: a fuel cell of a pin and assembly type BWR. To facilitate the study of reactors physics in the fuel pin their nuclear characteristics are provided to detail, such as burnt dependence, the reactivity of selected nuclide, etc. With respect to the fuel assembly, the presented results are regarding to infinite multiplication factor for burning different steps and different vacuum conditions. Making the analysis of this set of Benchmark problems provides comprehensive test problems for the next fuels generation of BWR reactors with high extended burned. It is important to note that when making this comparison the purpose is to validate the methodologies used in modeling for different operating conditions, if the case is of other BWR assembly. The results will be within a range with some uncertainty, considering that does not depend on code that is used. Escuela Superior de Fisica y Matematicas of Instituto Politecnico Nacional (IPN (Mexico) has accumulated some experience in using Serpent, due to the potential of this code over other commercial codes such as CASMO and MCNP. The obtained results for the infinite multiplication factor are encouraging and motivate the studies to continue with the generation of the X S of a core to a next step a respective nuclear data library is constructed and this can be used by codes developed as part of the development project of the Mexican Analysis Platform of Nuclear Reactors AZTLAN. (Author)

  4. Análisis comparativo de la ejecución del algoritmo voraz de PRIM en modo lineal y paralelo (LAM-MPI

    Directory of Open Access Journals (Sweden)

    José Márquez Diaz

    2003-01-01

    Full Text Available En este trabajo se muestra cómo funciona el algoritmo voraz PRlM, tanto en ambientes paralelos como en secuenciales. El objetivo de estas pruebas es ver cómo la herramienta mpi puede trabajar en red y mostrar cómo los algoritmos voraces en lafase de ejecución pueden arrojar resultados satisfactorios al momento de utilizarlos. Para poder ejecutar el algoritmo voraz PRlM se usó un entorno de procesamiento secuencial utilizando un único computador y un entorno de procesamiento paralelo a partir de la implementaci6n dada con la programación de paso de mensajes (MP¡, denominada l.AM (Local Area MuIticomputer sobre el sistema operativo Linux. Los resultados obtenidos permiten concluir que a través del paralelismo virtual se logra disminuir el tiempo de procesamiento de un programa de esta naturaleza.

  5. Clonación artificial de un controlador on-line, basado en lógica difusa y algoritmos genéticos

    Directory of Open Access Journals (Sweden)

    Javier Ballesteros

    2006-10-01

    Full Text Available Los Algoritmos Genéticos son procedimientos adaptativos para la búsqueda de soluciones en espacios complejos, inspirados en la evolución biológica, con patrones de operaciones basados en el principio darwiniano de reproducción y supervivencia de los individuos que mejor se adaptan al entorno en que viven. En este artículo se presenta un estudio sobre los Algoritmos Genéticos y la Lógica Difusa, para desarrollar una metodología propuesta y replicar la caja negra de un controlador, utilizando procedimientos de obtención del conjunto de reglas de inferencia, agrupamiento difuso y después aplicar el desarrollo del algoritmo genético simple con algunas alteraciones, buscando el objetivo del trabajo propuesto.

  6. Algoritmo de classificação de especialistas em áreas na base de currículos Lattes

    Directory of Open Access Journals (Sweden)

    Fellipe de Melo Chagas

    2015-08-01

    Full Text Available Este trabalho propõe um algoritmo para construir um ranking de especialistas na base de currículos Lattes. Para isto, foi elaborado um algoritmo composto por três estágios de processamento: Score Alfa, que analisa os títulos dos documentos baseado na ontologia definida para selecionar os assuntos e importâncias destes assuntos para cada publicação; Score Beta, que analisa a qualidade das publicações utilizando conceitos definidos pela CAPES para beneficiar produções publicadas em veículos mais importantes; e Score Propagated, que analisa a importância de estar bem conectado a demais pesquisadores especialistas propagando o conhecimento obtido. Para o teste de precisão do algoritmo, utilizaram-se dados reais da área de Nanotecnologia.

  7. Propuesta de un algoritmo para evaluar la causalidad de eventos adversos en los Ensayos Clínicos de Vacunas.

    Directory of Open Access Journals (Sweden)

    María de los A. Peña.

    2008-12-01

    Full Text Available En el transcurso de los ensayos clínicos usualmente se designa a una comisión, la cual se encarga de evaluar la causalidad de los eventos adversos que se reportan y transcriben en los cuadernos de recogida de datos. Para llegar a contestar la pregunta de: ¿si una vacuna que se está estudiando ha causado un evento adverso?, los decisores pueden tomar diferentes caminos, por lo que obviamente la conclusión final podría variar mucho y la evaluación deficiente puede generar conclusiones erróneas, lo que confirma la necesidad de disponer de un procedimiento para definir las categorías que se utilizarán para analizar y clasificar la relación de causalidad. Una forma de contestar a la pregunta es mediante la construcción de un algoritmo. En relación con los ensayos clínicos no encontramos en la literatura un algoritmo que sea el "patrón clave" para establecer o descartar la causalidad, sin embargo es factible diseñarlo partiendo de la metodología internacional utilizada poscomercialización, lo cual fue el propósito de este trabajo. Se diseñó una primera propuesta que fue analizada individual y colectivamente por el grupo multidisciplinario de la Gerencia Médica del Instituto Finlay. Finalmente se aprobó por consenso el algoritmo que puede ser útil para aplicar en los ensayos clínicos dentro y fuera de la institución.

  8. 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.

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

    Directory of Open Access Journals (Sweden)

    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.

  10. Estimate of coolant flow in assemblies of a natural circulation BWR applying and equivalent electric model; Estimacion del flujo de refrigerante en los ensambles de un BWR de circulacion natural aplicando un modelo electrico equivalente

    Energy Technology Data Exchange (ETDEWEB)

    Valle H, J.; Morales S, J. B. [UNAM, DEPFI, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)], e-mail: julfi_jg@yahoo.com.mx

    2009-10-15

    The present work exposes the design and implementation of an advanced controller that it allows to estimate the coolant flow in fuel assemblies of a natural circulation BWR in real time. the complete development of this study is part of a doctoral project in course. In this work the construction of optimal controller is shown that allows to estimate the coolant flows in reactor and its operation applied to an equivalent electric model to natural circulation ESBWR. The controller design that allows the completely automatic starter of natural circulation reactor, required of a variables estimator not meter directly of nuclear power plant and use of local distributions estimates of coolant flow, (this controller type at the moment is utilized in the A BWR and several BWR in operation in Japan). The construction of estimator controller is mathematically based in the theory referring to Kalman filter, whose algorithm provides an advanced control of system. To prove the estimator operation was developed a simplified model that reproduces the basic dynamic of coolant flowing in the ESBWR, a practice way and very interesting of representing this phenomenon is by means the use of an equivalent electric model, which was developed starting from analogies that there is among the relation that keep the pressure differences with the mass flow and differences of electric potential with electric current. A detailed analysis of equivalence among models will be presented in a later article. (Author)

  11. Pre-study of dynamic loads on the internals caused by a large pipe break in a BWR; Foerstudie av stroemningsinducerade laster paa interndelar vid brott i huvudcirkulationskretsarna i BWR

    Energy Technology Data Exchange (ETDEWEB)

    Marcinkiewicz, Jerzy; Lindgren, Anders [Det Norske Veritas Nuclear Technology AB, Stockholm (Sweden)

    2002-12-01

    Det Norske Veritas Nuclear Technology has performed a literature study of dynamic load on a BWR (Boiling Water Reactor) internals caused by a large pipe break. The goal of the study was to improve the knowledge about the physics of phenomena occurring in the RPV (Reactor Pressure Vessel) after pipe break in the main circulation system and also to make a review of calculation methods, models and computer programs including their capabilities when calculating the dynamic loads. The report presents description of relevant parts of a BWR, initial and boundary conditions, and phenomena determining the loads - rapid depressurization and propagation of pressure wave (including none-equilibrium). Furthermore, the report generally describes possible methodologies for calculating the dynamic loads on internals after the pipe break and the experiences from calculations the dynamic loads with different methods (computer programs) including comparisons with experimental data. Fluid-Structure Interaction methodology and its importance for calculation of dynamic loads on reactor internals is discussed based on experimental data. A very intensive research program for studying and calculating the dynamic loads on internals after pipe breaks has been performed in USA and Germany during the seventies and the eighties. Several computer programs have been developed and a number of large-scale experiments have been performed to calibrate the calculation methods. In spite of the fact that all experiments were performed for PWR several experiences should be valid also for BWR. These experiences, connected mainly to capabilities of computer programs calculating dynamic loads, are discussed in the report.

  12. Cómo reescribir funciones aleatorias multivariadas como univariadas para hacer cokrigeage. Un algoritmo flexible

    Directory of Open Access Journals (Sweden)

    Adrian Martínez-Vargas

    2010-03-01

    Full Text Available La mayoría de los software para geoestadísticas poseen un limitado número de modelos de krigeage y no son lo suficientemente flexibles para definir nuevos o complicados modelos. Con el objetivo de obtener un algoritmo flexible de krigeage se empleó la notación de funciones aleatorias regionalizadas (RF multivariadas escritas como una RF univariada Z(x, i, con un drift m(x, i, j, donde i y j son identificadores de variables. Se programó en C++ una librería geoestadística llamada OpenKriging, con una función que se puede llamar desde código escrito en Python, la cual es capaz de construir el sistema de krigeage de la RF mencionada, sin restricciones en el número de dimensiones espaciales, variables y monomios en el drift. Se implementaron dos tipos de drift: los geográficos y los drift externos, estos pueden ser independientes o no. La función responsable de construir el sistema de ecuaciones krigeage no se programó para un modelo predefinido, el modelo es definido por el usuario pasando desde el código en Python los datos y argumentos apropiados y modificando el sistema antes de resolverlo. La librería resultante puede asimilar muchos de los modelos conocidos de krigeage y también modelos nuevos o poco comunes; esta es fácil de modificar para incrementar su funcionalidad, la cual se mostró a través de dos ejemplos de modelos de krigeage: uno con definición complicada y el otro poco común.

  13. Identificación en lazo cerrado mediante algoritmos genéticos

    Directory of Open Access Journals (Sweden)

    Alfredo Gómez Infante

    2010-11-01

    Full Text Available Normal 0 21 false false false MicrosoftInternetExplorer4 st1:*{behavior:url(#ieooui } /* 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-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:10.0pt; font-family:"Times New Roman"; mso-ansi-language:#0400; mso-fareast-language:#0400; mso-bidi-language:#0400;} La identificación  en lazo cerrado de sistemas continuos es un problema de optimización no lineal que resulta de difícil solución mediante métodos convencionales.  En este trabajo se propone el uso de algoritmos genéticos (AG para esta tarea y se muestra mediante simulaciones que los modelos obtenidos pueden reproducir fielmente el comportamiento de la planta, aun en el caso de sistemas inestables o que presentan algún tipo de no-linealidad. Estos modelos pueden utilizarse para el ajuste de los parámetros de reguladores PID utilizando un método también basado en AG, como se muestra en dos ejemplos: un sistema inestable en lazo cerrado y otro de alto orden con retardo.  La metodología propuesta se aplica también  a la identificación del modelo AC5A de la IEEE, que incluye una no-linealidad del tipo saturación,  para unidades de generación eléctrica.

  14. VIPRE-W / MEFISTO-T - A mechanistic tool for transient prediction of dryout in BWR fuel

    Energy Technology Data Exchange (ETDEWEB)

    Adamsson, C., E-mail: carl.adamsson@psi.ch [Westinhouse Electric Sweden, Vasteras (Sweden); Paul Scherrer Institut, Villigen (Switzerland); Le Corre, J-M., E-mail: lecorrjm@westinghouse.com [Westinhouse Electric Sweden, Vasteras (Sweden)

    2011-07-01

    The VIPRE-W/MEFISTO-T code package constitutes a simplified approach to sub-channel film-flow analysis whereby the transport equations for the liquid films are decoupled from each other. The approach allows fast and robust simulation with high axial resolution of realistic BWR transients. It has previously been shown that a steady-state version of the model agrees well with dryout measurements in full-scale fuel assembly mock-ups performed at the Westinghouse FRIGG loop. In this paper, we present validation of the transient version of the code with around 300 transient dryout experiments from the same loop. The transients involve realistic variations of flow and power and three different axial power distributions at conditions typical for BWR operation. The results from the film-flow analysis show high precision in the dryout prediction but a hitherto unexplained bias that reduces the accuracy. (author)

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

    Directory of Open Access Journals (Sweden)

    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.

  16. Análisis de un algoritmo de control para un robot andador mediante simulación con ADAMS

    OpenAIRE

    Martín Torrejón, Víctor

    2011-01-01

    El objetivo principal de este proyecto es estudiar la robustez del algoritmo de control propuesto para un bípedo simple formado por dos patas actuadas desde un disco. Para ello se realizarán numerosas simulaciones con el programa Adams View del caminar del bípedo variando parámetros de control, como son el periodo y la amplitud de paso, así como el coeficiente de rozamiento entre las patas y el suelo. Objetivos secundarios que se desprenden de éste son: - Realizar una revisión del estado d...

  17. Relaciones dosis-respuesta. Acción conjunta de tóxicos. Algoritmos de cálculo

    OpenAIRE

    Muñiz, Mariano; Gil, Alejandro.

    1990-01-01

    La presente publicación recoge un resumen del trabajo realizado por los autores en los últimos diez años sobre el análisis de la respuesta cuantal, ofreciendo a los interesados en este campo tanto las hipótesis que han de cumplirse en los diferentes métodos alternativos que analizan la relación dosis-respuesta y la acción conjunta de tóxicos, como los algoritmos de cálculo correspondientes a las diferentes transformaciones y los resultados de algunos experimentos biológicos obtenidos al aplic...

  18. Algoritmos genéticos multiobjetivos aplicados ao roteamento multicast com qualidade de serviço

    OpenAIRE

    Vita, Stéfano Schwenck Borges Vale

    2009-01-01

    Roteamento multicast é uma maneira eficaz de se comunicar entre múltiplos roteadores em redes de computadores. Geralmente, a Qualidade de Serviço (QoS) é exigida como garantia na maior parte das aplicações multicast. Vários pesquisadores têm investigado a aplicação dos Algoritmos Genéticos em roteamento multicast com restrições QoS. Os ambientes evolutivos de roteamento que são propostos neste trabalho empregam uma abordagem multiobjetivos adotando o conceito de Ótimo de Pareto...

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

    OpenAIRE

    Luis Diego Murillo

    2008-01-01

    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 com...

  20. 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.

  1. Algoritmo de control anticipatorio assisted-as-needed para neurorrehabilitación funcional de extremidad superior

    OpenAIRE

    Pérez Rodríguez, Rodrigo; Costa Boned, U.; Cáceres Taladriz, César; Tormos Muñoz, Josep M.; Medina Casanovas, J.; Gómez Aguilera, Enrique J.

    2012-01-01

    Los dispositivos robóticos se están convirtiendo en una alternativa muy extendida a las terapias de neurorrehabilitación funcional tradicionales al ofrecer una práctica más intensiva sin incrementar el tiempo empleado en la supervisión por parte de los terapeutas especialistas. Por ello, este trabajo de investigación propone un algoritmo de control anticipatorio que, bajo el paradigma 'assisted-as-needed', proporcione a una ortesis robótica las capacidades de actuación necesarias para ...

  2. 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 ...

  3. Comparación de algoritmos de aprendizaje supervisado para la obtención de perfiles de alumnos desertores

    OpenAIRE

    Spositto, Osvaldo Mario

    2016-01-01

    [8 p.] En los últimos años, las técnicas de Minería de Datos han sido progresivamente incorporadas al ámbito universitario, como consecuencia del gran volumen de datos del que se dispone y del notable esfuerzo que se requiere para realizar análisis de los mismos. Este artículo presenta la comparación del rendimiento de dos algoritmos del tipo Aprendizaje Supervisado. Por un lado una arquitectura de Red Neuronal Artificial, del tipo Perceptrón Multicapa y por el otro, una Máquina de Vectore...

  4. Stakes and Solutions for current and up-coming Licensing Challenges in PWR and BWR Reload and Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Curca-Tiving, F.; Opel, S.

    2014-07-01

    Regulatory requirements for reloads and safety analyses are evolving: New safety criteria, requests for enlarged qualification databases, statistical applications, uncertainty propagation... In order to address these challenges and access more predictable licensing processes, AREVA implements a consistent code and methodology suite for PWR and BWR core design and safety analysis, based on a first principles modeling with an extremely broad international verification and validation data base. (Author)

  5. Parametric study of the potential for BWR ECCS strainer blockage due to LOCA generated debris. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Zigler, G.; Brideau, J.; Rao, D.V.; Shaffer, C.; Souto, F.; Thomas, W. [Science and Engineering Associates, Inc., Albuquerque, NM (United States)

    1995-10-01

    This report documents a plant-specific study for a BWR/4 with a Mark I containment that evaluated the potential for LOCA generated debris and the probability of losing long term recirculation capability due ECCS pump suction strainer blockage. The major elements of this study were: (1) acquisition of detailed piping layouts and installed insulation details for a reference BWR; (2) analysis of plant specific piping weld failure probabilities to estimate the LOCA frequency; (3) development of an insulation and other debris generation and drywell transport models for the reference BWR; (4) modeling of debris transport in the suppression pool; (5) development of strainer blockage head loss models for estimating loss of NPSH margin; (6) estimation of core damage frequency attributable to loss of ECCS recirculation capability following a LOCA. Elements 2 through 5 were combined into a computer code, BLOCKAGE 2.3. A point estimate of overall DEGB pipe break frequency (per Rx-year) of 1.59E-04 was calculated for the reference plant, with a corresponding overall ECCS loss of NPSH frequency (per Rx-year) of 1.58E-04. The calculated point estimate of core damage frequency (per Rx-year) due to blockage related accident sequences for the reference BWR ranged from 4.2E-06 to 2.5E-05. The results of this study show that unacceptable strainer blockage and loss of NPSH margin can occur within the first few minutes after ECCS pumps achieve maximum flows when the ECCS strainers are exposed to LOCA generated fibrous debris in the presence of particulates (sludge, paint chips, concrete dust). Generic or unconditional extrapolation of these reference plant calculated results should not be undertaken.

  6. Hydrologic-agronomic-economic model for the optimal operation of the Yaqui river reservoir system using genetic algorithms; Modelo hidrologico-agronomico-economico para la operacion optima del sistema de presas del rio Yaqui, usando algoritmos geneticos

    Energy Technology Data Exchange (ETDEWEB)

    Minjares-Lugo, Jose Luis; Salmon-Castelo, Roberto Fernando; Oroz-Ramos, Lucas Antonio [Comision Nacional del Agua (Mexico); Cruz-Medina, Isidro Roberto [Instituto Tecnologico de Sonora (Mexico)

    2008-07-15

    The objective of this study is to develop an integrated hydrologic-agronomic-economic annual model for the optimal operation of the Yaqui River reservoir system to support irrigation and urban water supply in the watershed. The model solves for each year's water allocations by crop, maximizing annual agricultural income for a specified risk of reservoir shortages and spills. It accounts for adjustments in water supply arising from changes in precipitation and runoff uncertainty and from changes in water demand arising from variations in crop prices and production costs. Model predictions for the agricultural year 2000-2001 are compared with observed results to test the model's predictive ability. Results demonstrate that the model can be used to optimize and analyze reservoir system operation and for water resources management in the Irrigation District No. 041, providing a framework for improving the operation of a reservoir system, selecting an optimal cropping pattern according to its maximum economic benefits, and in the optimal monthly water releases from the reservoir system. The model considers the simultaneous operation of three dams and it is applied to the Irrigation District No. 041, Rio Yaqui. [Spanish] El objetivo de este estudio es desarrollar un modelo integral de optimizacion anual para definir la operacion del sistema de presas del rio Yaqui y la asignacion del volumen mensual de agua para la irrigacion de diferentes cultivos, asi como para satisfacer los requerimientos de uso urbano basado en las condiciones hidrologicas, agronomicas y economicas en la cuenca. El modelo maximiza los beneficios anuales netos del sector agricola, minimizando el riesgo de deficit o derrames en el sistema de presas; incluye cambios en el suministro de agua debido a la incertidumbre de las precipitaciones y del escurrimiento del rio y cambios en la demanda de agua provocados por la incertidumbre de los precios y costos de los cultivos. Se utilizaron datos del ano agricola 2000-2001. Los resultados obtenidos con el modelo se analizan y comparan con los resultados reales obtenidos en este ano en particular para conocer las funciones analiticas del modelo. Los resultados demuestran que este modelo es una herramienta que puede ser utilizada para optimizar y analizar la operacion del sistema de presas del Yaqui, asi como para manejar los recursos hidraulicos en el Distrito de Riego 041, seleccionado el patron de cultivos de acuerdo con sus maximos beneficios economicos y las extracciones optimas mensuales del agua disponible del sistema de presas del rio Yaqui. El modelo considera la operacion simultanea de tres presas y se aplica al Distrito de Riego 041, Rio Yaqui.

  7. Study of AAA Algorithm on the pelvic region with the VMAT technical using a dummy anthropomorphic; Estudio del algoritmo AAA en la region pelvica con la tecnica VMAT usando un maniqui antropomorfico

    Energy Technology Data Exchange (ETDEWEB)

    Puchades Puchades, V.; Serna Berna, A.; Mata Colodro, F.; Ramos Amores, D.; Casal Zamorano, E.

    2013-07-01

    Knowledge of real dosimetry in patients in new techniques of irradiation is very important to know the degree of accuracy of the dose calculations provided by the planners and however it is sometimes difficult to achieve. One way to evaluate this dosimetry without resorting to a patient, is the use of anthropomorphic Dummies. One of the algorithms employed is called AAA (Analytical Anisotropic Algorithm), which is an analytical algorithm of overlap-convolution, which improves the calculation of doses in the heterogeneities that the patient presents in your body (FAT, muscle, bone, lung) in comparison with other ancestor algorithms. (Author)

  8. Detección, identificación y clasificación de defectos usando RNA y un manipulador robótico de 2 G.L (algoritmos Kohonen y MLP

    Directory of Open Access Journals (Sweden)

    Barrera, G.

    2002-06-01

    Full Text Available The ultrasonic inspection technique had a sustained growth since the 80’s. It has several advantages, compared with the contact technique. A flexible and low cost solution is presented based on virtual instrumentation for the servomechanism (manipulator control of the ultrasound inspection transducer in the immersion technique. The developed system uses a personal computer (PC, a Windows Operating System, Virtual Instrumentation Software, DAQ cards and a GPIB card. As a solution to detection, classification and evaluation of defects an Artificial Neuronal Networks technique is proposed. It consists of characterization and interpretation of acoustic signals (echoes acquired by the immersion ultrasonic inspection technique. Two neuronal networks are proposed: Kohonen and Multilayer Perceptron (MLP. With this techniques non-linear complex processes can be modeled with great precision. The 2-degree of freedom manipulator control, the data acquisition and the net training have been carried out in a virtual instrument environment using LabVIEW and DataEngine.

    La técnica de inspección ultrasónica por inmersión ha tenido un desarrollo sostenido desde la década de los 80 y tiene muchas ventajas en comparación con la técnica de contacto. Se presenta una solución flexible y de bajo costo basada en instrumentación virtual para el control de un servomecanismo de exploración ultrasónica (manipulador, por la técnica de inmersión. El sistema desarrollado hace uso de un ordenador personal (PC, del sistema operativo Windows, de software de instrumentación virtual Lab VIEW, de tarjetas de adquisición de datos (DAQ y de una tarjeta GP113. Como solución al problema de la detección, clasificación y evaluación de defectos se propone un sistema experto basado en la técnica de redes neuronales artificiales por medio de la interpretación de las señales acústicas (ecos obtenidas por mediante la técnica de inspección ultrasónica de inmersión. Se proponen dos redes neuronales: Kohonen y Perceptron Multicapas (MLP. Estas técnicas permiten modelar procesos no lineales complejos con una gran exactitud. Tanto las operaciones de control del manipulador de 2 grados libertad, adquisición y tratamiento de los datos y la fase de entrenamiento de las redes se llevó a cabo en un ambiente de instrumentación virtual utilizando Lab VIEW y DataEngine.

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

    OpenAIRE

    Lázaro Janier González-Soler; Airel Pérez-Suárez; Leonardo Chang-Fernández

    2015-01-01

    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 re...

  10. Bosque Azul: Animación de Algoritmos para la enseñanza de estructuras arbóreas1

    OpenAIRE

    Gonzalez, Fernando; Moroni, Norma; Señas, Perla

    2004-01-01

    Bosque Azul es un software específicamente diseñado y desarrollado para la enseñanza y aprendizaje de los temas relacionados con Árboles Binarios de Búsqueda y con árboles AVL que se estudian en los cursos de Estructuras de Datos y Algoritmos Está específicamente basado en la animación de algoritmos y en la visualización de programas. Permite una exploración vertical de los contenidos, asumiendo el aprendizaje de conceptos simples y elementales que se reflejan en las primeras animaciones p...

  11. Diseño e implementación de un algoritmo de tipo recocido simulado para el reconocimiento de rutas en tiempo real

    OpenAIRE

    Yumbulema Rea, Daniela Yohanna; Bustamante Romero, , Johnny

    2009-01-01

    Esta tesis trata de resolver el Problema del Agente viajero, donde el circuito a visitar está constituido por todas las farmacias comprendidas en los sectores, Pedro Carbo, Roca y Rocafuerte. El algoritmo que se va a utilizar es el algoritmo de Recocido simulado, que generalmente es usado en Termodinámica, para controlar el enfriamiento en ciertos procesos complejos ya sea por que utilizan un tiempo no polinomial de resolución o por que no necesitan llagar a un optimo, con un satisfactori...

  12. Diseño e implementación de un algoritmo de tipo recocido simulado para el reconocimiento de rutas en tiempo real

    OpenAIRE

    Yumbulema Rea, Daniela Yohanna

    2005-01-01

    Esta tesis trata de resolver el Problema del Agente viajero, donde el circuito a visitar está constituido por todas las farmacias comprendidas en los sectores, Pedro Carbo, Roca y Rocafuerte. El algoritmo que se va a utilizar es el algoritmo de Recocido simulado, que generalmente es usado en Termodinámica, para controlar el enfriamiento en ciertos procesos complejos ya sea por que utilizan un tiempo no polinomial de resolución o por que no necesitan llagar a un optimo, con un satisfactori...

  13. Identificación de algoritmos de cómputo Intensivo para big data y su implementación en clouds

    OpenAIRE

    Murazzo, María A.; Nelson R. Rodríguez; Guevara, Miguel José; Tinetti, Fernando Gustavo

    2016-01-01

    Almacenar, transferir y procesar grandes volúmenes de datos en el área que se ha denominado Big Data son un factor determinante y un reto para el Cómputo de Alto Rendimiento (sigla en inglés: HPC de High Performance Computing). Los algoritmos usados para procesar esos datos deben sacar provecho de las ventajas ofrecidas por el cómputo en la Nube (Cloud), mediante el uso de algoritmos que permitan agilizar/acelerar el cómputo de o con esos datos. La conjunción de Big Data y HPC se suele enf...

  14. Una contribución al procesamiento del plural en español: un algoritmo de singularización

    OpenAIRE

    Sánchez Ladrón de Guevara, Álvaro; García Jumela, Francisco

    1995-01-01

    Este trabajo presenta una forma original de procesar los plurales en español: la singularización. El algoritmo de singularización recibe como entrada una palabra en plural y devuelve como salida la forma singular. Las reglas del algoritmo, divididas según las terminaciones de las palabras, permiten reconstruir el singular de cualquier plural castellano. La consulta de un diccionario de formas singulares sirve para comprobar el éxito del proceso de singularización. El artículo describe en deta...

  15. Algoritmo para la obtención de parámetros antropométricos en imágenes de rostros frontales

    OpenAIRE

    2011-01-01

    Este trabajo describe un algoritmo desarrollado bajo técnicas de procesamiento de imágenes para la obtención automática de los principales parámetros antropométricos del rostro en posición frontal. El algoritmo emplea un modelo gaussiano de la piel con el fin de detectar el rostro del individuo presente en la escena. Luego, por medio de un conjunto de ecuaciones morfológicas, se segmentan las regiones del rostro de interés (ojos, nariz y labios). Una vez detectadas estas regiones se calculan ...

  16. Impact of modeling Choices on Inventory and In-Cask Criticality Calculations for Forsmark 3 BWR Spent Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Martinez-Gonzalez, Jesus S. [Univ. Politecnica de Madrid (Spain); Ade, Brian J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bowman, Stephen M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gauld, Ian C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ilas, Germina [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Marshall, William BJ J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-01-01

    Simulation of boiling water reactor (BWR) fuel depletion poses a challenge for nuclide inventory validation and nuclear criticality safety analyses. This challenge is due to the complex operating conditions and assembly design heterogeneities that characterize these nuclear systems. Fuel depletion simulations and in-cask criticality calculations are affected by (1) completeness of design information, (2) variability of operating conditions needed for modeling purposes, and (3) possible modeling choices. These effects must be identified, quantified, and ranked according to their significance. This paper presents an investigation of BWR fuel depletion using a complete set of actual design specifications and detailed operational data available for five operating cycles of the Swedish BWR Forsmark 3 reactor. The data includes detailed axial profiles of power, burnup, and void fraction in a very fine temporal mesh for a GE14 (10×10) fuel assembly. The specifications of this case can be used to assess the impacts of different modeling choices on inventory prediction and in-cask criticality, specifically regarding the key parameters that drive inventory and reactivity throughout fuel burnup. This study focused on the effects of the fidelity with which power history and void fraction distributions are modeled. The corresponding sensitivity of the reactivity in storage configurations is assessed, and the impacts of modeling choices on decay heat and inventory are addressed.

  17. Development of a fuzzy logic method to build objective functions in optimization problems: application to BWR fuel lattice design

    Energy Technology Data Exchange (ETDEWEB)

    Martin-del-Campo, C.; Francois, J.L.; Barragan, A.M. [Universidad Nacional Autonoma de Mexico - Facultad de Ingenieria (Mexico); Palomera, M.A. [Universidad Nacional Autonoma de Mexico - Instituto de Investigaciones en Matematicas Aplicadas y Sistema, Mexico, D. F. (Mexico)

    2005-07-01

    In this paper we develop a methodology based on the use of the Fuzzy Logic technique to build multi-objective functions to be used in optimization processes applied to in-core nuclear fuel management. As an example, we selected the problem of determining optimal radial fuel enrichment and gadolinia distributions in a typical 'Boiling Water Reactor (BWR)' fuel lattice. The methodology is based on the use of the mathematical capability of Fuzzy Logic to model nonlinear functions of arbitrary complexity. The utility of Fuzzy Logic is to map an input space into an output space, and the primary mechanism for doing this is a list of if-then statements called rules. The rules refer to variables and adjectives that describe those variables and, the Fuzzy Logic technique interprets the values in the input vectors and, based on the set of rules assigns values to the output vector. The methodology was developed for the radial optimization of a BWR lattice where the optimization algorithm employed is Tabu Search. The global objective is to find the optimal distribution of enrichments and burnable poison concentrations in a 10*10 BWR lattice. In order to do that, a fuzzy control inference system was developed using the Fuzzy Logic Toolbox of Matlab and it has been linked to the Tabu Search optimization process. Results show that Tabu Search combined with Fuzzy Logic performs very well, obtaining lattices with optimal fuel utilization. (authors)

  18. Procesamiento de datos de monitoreo atmosférico usando clasificación no convencional

    OpenAIRE

    Uriarte Arcia, Abril

    2016-01-01

    En el presente trabajo de tesis, se diseña e implementa un método para el procesamiento y predicción de datos atmosféricos emanados a través del escape de vehículos automotores, basado en un algoritmo de clasificación no convencional. El clasificador a emplear es el Gamma, el cual pertenece al enfoque asociativo y utiliza los operadores Alfa y Beta, que son a su vez la base de la memorias asociativas Alfa-Beta. Se realiza el procesamiento y predicción de la concentración de monóxido de ...

  19. DESARROLLO DE UN SISTEMA DE NEURO-MERCADOTECNIA USANDO EL DISPOSITIVO EMOTIV-EPOC

    Directory of Open Access Journals (Sweden)

    Luz Ángela Moreno

    2014-11-01

    Full Text Available Este artículo presenta los avances concebidos en la realización de un sistema de neuro-mercadotecnia. El objetivo del sistema es permitir evaluar las emociones que presentan los televidentes al observar comerciales publicitarios. Se hace uso de la interfaz cerebro-computador Emotiv-EPOC para la adquisición de las neuro-señales. Se describen los algoritmos empleados para el análisis de las pautas publicitarias. Se presentan unas pruebas experimentales donde se comparan los resultados obtenidos por métodos tradicionales con las propuestas.

  20. Incursión en el ámbito de las dos variables: optimización usando argumentos gráficos

    OpenAIRE

    2007-01-01

    Cuando enseñamos a los alumnos a resolver problemas, solemos abusar de la utilización de algoritmos encaminados a encontrar la solución óptima, evitando las dificultades que puede suponer la introducción de reglas más o menos complejas en el diseño de dicho algoritmo. Pero resolver un problema es mucho más que aplicar un algoritmo de forma mecánica, supone encontrar una respuesta coherente a una serie de datos relacionados dentro de un contexto. Es por esto que presentamos esta práctica, dond...

  1. Incursión en el ámbito de las dos variables: optimización usando argumentos gráficos

    OpenAIRE

    Ríos, Jesús; Monserrat, Francisco

    2007-01-01

    Cuando enseñamos a los alumnos a resolver problemas, solemos abusar de la utilización de algoritmos encaminados a encontrar la solución óptima, evitando las dificultades que puede suponer la introducción de reglas más o menos complejas en el diseño de dicho algoritmo. Pero resolver un problema es mucho más que aplicar un algoritmo de forma mecánica, supone encontrar una respuesta coherente a una serie de datos relacionados dentro de un contexto. Es por esto que presentamos esta práctica, dond...

  2. Resultados preliminares de um sistema de topografia de grande-ângulo usando videoceratógrafo com discos de Plácido Preliminary results of a wide-angle corneal topography system for Placido-based videokeratographers

    Directory of Open Access Journals (Sweden)

    Luis Alberto Vieira de Carvalho

    2008-04-01

    Full Text Available OBJETIVO: Desenvolver a instrumentação e o "software" para topografia de córnea de grande-ângulo usando o tradicional disco de Plácido. O objetivo é permitir o mapeamento de uma região maior da córnea para topógrafos de córnea que usem a técnica de Plácido, fazendo-se uma adaptação simples na mira. MÉTODOS: Utilizando o tradicional disco de Plácido de um topógrafo de córnea tradicional, 9 LEDs (Light Emitting Diodes foram adaptados no anteparo cônico para que o paciente voluntário pudesse fixar o olhar em diferentes direções. Para cada direção imagens de Plácido foram digitalizadas e processadas para formar, por meio de algoritmo envolvendo elementos sofisticados de computação gráfica, um mapa tridimensional completo da córnea toda. RESULTADOS: Resultados apresentados neste trabalho mostram que uma região de até 100% maior pode ser mapeada usando esta técnica, permitindo que o clínico mapeie até próximo ao limbo da córnea. São apresentados aqui os resultados para uma superfície esférica de calibração e também para uma córnea in vivo com alto grau de astigmatismo, mostrando a curvatura e elevação. CONCLUSÃO: Acredita-se que esta nova técnica pode propiciar a melhoria de alguns processos, como por exemplo: adaptação de lentes de contato, algoritmos para ablações costumizadas para hipermetropia, entre outros.PURPOSE: To develop the instrumentation and software for wide-angle corneal topography using a Placido-based videokeratographer. The objective is to allow the measurement of a greater area of the cornea using a simple adaptation to the Placido mire. METHODS: Using the traditional Placido disc of a commercial corneal topographer, 9 LEDs (Light Emitting Diodes were installed on the conic mire so that the voluntary patient could gaze in different directions. For each direction Placido images were acquired and processed to form, using a sophisticated computer graphics algorithm, a tridimensional

  3. Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, William BJ J [ORNL; Ade, Brian J [ORNL; Bowman, Stephen M [ORNL; Gauld, Ian C [ORNL; Ilas, Germina [ORNL; Mertyurek, Ugur [ORNL; Radulescu, Georgeta [ORNL

    2015-01-01

    Oak Ridge National Laboratory and the United States Nuclear Regulatory Commission have initiated a multiyear project to investigate application of burnup credit for boiling-water reactor (BWR) fuel in storage and transportation casks. This project includes two phases. The first phase (1) investigates applicability of peak reactivity methods currently used in spent fuel pools (SFPs) to storage and transportation systems and (2) evaluates validation of both reactivity (keff) calculations and burnup credit nuclide concentrations within these methods. The second phase will focus on extending burnup credit beyond peak reactivity. This paper documents the first phase, including an analysis of lattice design parameters and depletion effects, as well as both validation components. Initial efforts related to extended burnup credit are discussed in a companion paper. Peak reactivity analyses have been used in criticality analyses for licensing of BWR fuel in SFPs over the last 20 years. These analyses typically combine credit for the gadolinium burnable absorber present in the fuel with a modest amount of burnup credit. Gadolinium burnable absorbers are used in BWR assemblies to control core reactivity. The burnable absorber significantly reduces assembly reactivity at beginning of life, potentially leading to significant increases in assembly reactivity for burnups less than 15–20 GWd/MTU. The reactivity of each fuel lattice is dependent on gadolinium loading. The number of gadolinium-bearing fuel pins lowers initial lattice reactivity, but it has a small impact on the burnup and reactivity of the peak. The gadolinium concentration in each pin has a small impact on initial lattice reactivity but a significant effect on the reactivity of the peak and the burnup at which the peak occurs. The importance of the lattice parameters and depletion conditions are primarily determined by their impact on the gadolinium depletion. Criticality code validation for BWR burnup

  4. 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.

  5. 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.

  6. La utilización de los algoritmos de sustracción en educación primaria

    Directory of Open Access Journals (Sweden)

    Jorge Segura Beneyto

    2016-03-01

    Full Text Available En este trabajo de fin de grado, el estudio se centrará en investigar el algoritmo de la sustracción. Todo el análisis que se expone, se ha obtenido a partir de varios libros expuestos en la bibliografía y de un instrumento experimental caracterizado por presentar 16 restas con diferentes dificultades. En éste, han participado 201 alumnos y alumnas, que estudian actualmente los cursos de segundo y tercero de Educación Primaria, pertenecientes a cinco centros diferentes. Los resultados demuestran que el método de tomar prestado causa más aciertos, menos errores y la mayoría de los profesores lo prefieren. Además, se constatarán otros aspectos importantes en referencia al algoritmo de la sustracción. The use of subtraction algorithm’s in primary education In this final work degree, the study will focus on researching subtraction algorithm. The whole analysis that is exposed, has been obtained from several books, which are exposed in the bibliography and an experimental instrument characterized by presenting 16 subtraction with different difficulties. 201 students have taken part in this study, who are currently studying the second and third courses of primary education, belonging to five different schools. The results show that the method of borrowing cause more hits, fewer errors and most teachers prefer it. In addition, other important aspects will be recorded in reference to the subtraction algorithm.

  7. 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

  8. Unificar los criterios de sepsis neonatal tardía: propuesta de un algoritmo de vigilancia diagnóstica

    Directory of Open Access Journals (Sweden)

    Alonso Zea-Vera

    Full Text Available 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 sobre todo 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

  9. Especificación del algoritmo para un Test Adaptativo Informatizado de Analogías Verbales

    Directory of Open Access Journals (Sweden)

    Horacio Attorresi

    2012-12-01

    Full Text Available Se presentan los pasos seguidos en el diseño de un Test Adaptativo Informatizado de Analogías Verbales. El algoritmo adaptativo se determinó teniendo en cuenta las características de un Banco de Ítems de Analogías Verbales construido a partir de la Teoría de Respuesta al Ítem, los objetivos de evaluación, la población por evaluar y las características del software. El Banco está compuesto por 64 ítems unidimensionales calibrados según el Modelo Logístico de Tres Parámetros, informativos en todo el rango del rasgo y libres de funcionamiento diferencial entre géneros. Se programó el algoritmo adaptativo con el FastTEST Professional Testing System utilizando las siguientes especificaciones: a inicio aleatorio entre niveles levemente inferiores a la media del rasgo, b estimación del rasgo por Máxima Verosimilitud Condicional, c selección progresiva de los ítems con el Método de Máxima Información de Fisher y d criterio mixto de finalización.

  10. 3D modeling of missing pellet surface defects in BWR fuel

    Energy Technology Data Exchange (ETDEWEB)

    Spencer, B.W., E-mail: Benjamin.Spencer@inl.gov; Williamson, R.L.; Stafford, D.S.; Novascone, S.R.; Hales, J.D.; Pastore, G.

    2016-10-15

    Highlights: • A global/local analysis procedure for missing pellet surface defects is proposed. • This is applied to defective BWR fuel under blade withdrawal and high power ramp conditions. • Sensitivity of the cladding response to key model parameters is studied. - Abstract: One of the important roles of cladding in light water reactor fuel rods is to prevent the release of fission products. To that end, it is essential that the cladding maintain its integrity under a variety of thermal and mechanical loading conditions. Local geometric irregularities in fuel pellets caused by manufacturing defects known as missing pellet surfaces (MPS) can in some circumstances lead to elevated cladding stresses that are sufficiently high to cause cladding failure. Accurate modeling of these defects can help prevent these types of failures. The BISON nuclear fuel performance code developed at Idaho National Laboratory can be used to simulate the global thermo-mechanical fuel rod behavior, as well as the local response of regions of interest, in either 2D or 3D. In either case, a full set of models to represent the thermal and mechanical properties of the fuel, cladding and plenum gas is employed. A procedure for coupling 2D full-length fuel rod models to detailed 3D models of the region of the rod containing a MPS defect is detailed here. The global and local model each contain appropriate physics and behavior models for nuclear fuel. This procedure is demonstrated on a simulation of a boiling water reactor (BWR) fuel rod containing a pellet with an MPS defect, subjected to a variety of transient events, including a control blade withdrawal and a ramp to high power. The importance of modeling the local defect using a 3D model is highlighted by comparing 3D and 2D representations of the defective pellet region. Parametric studies demonstrate the effects of the choice of gaseous swelling model and of the depth and geometry of the MPS defect on the response of the cladding

  11. Experimental investigation of mixing of non-isothermal water streams at BWR operating conditions

    Energy Technology Data Exchange (ETDEWEB)

    Bergagio, Mattia, E-mail: bergagio@kth.se [AlbaNova University Center, Nuclear Reactor Technology Division, Department of Physics, Royal Institute of Technology, 106 91 Stockholm (Sweden); Anglart, Henryk, E-mail: henryk@kth.se [AlbaNova University Center, Nuclear Reactor Technology Division, Department of Physics, Royal Institute of Technology, 106 91 Stockholm (Sweden); Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Street, 00-665 Warsaw (Poland)

    2017-06-15

    Highlights: • Temperatures are measured in the presence of mixing at BWR operating conditions. • The thermocouple support is moved along a pattern to extend the measurement region. • Uncertainty of 1.58 K for temperatures acquired at 1000 Hz. • Momenta of the hot streams and thermal stratification affect the data examined. • Unconventional spectral analysis is required to further study the data collected. - Abstract: In this experimental investigation, wall surface temperatures have been measured during mixing of three water streams in the annular gap between two coaxial stainless-steel tubes. The inner tube, with an outer diameter of 35 mm and a thickness of 5 mm, holds six K-type, ungrounded thermocouples with a diameter of 0.5 mm, which measured surface temperatures with a sampling rate of either 100 Hz or 1000 Hz. The tube was rotated from 0 to 360° and moved in a range of 387 mm in the axial direction to allow measurements of surface temperatures in the whole mixing region. The outer tube has an inner diameter of 80 mm and a thickness of 10 mm to withstand a water pressure of 9 MPa. A water stream at a temperature of either 333 K or 423 K and a Reynolds number between 1657 and 8410 rose vertically in the annular gap and mixed with two water streams at a temperature of 549 K and a Reynolds number between 3.56 × 10{sup 5} and 7.11 × 10{sup 5}. These two water streams entered the annulus radially on the same axial level, 180° apart. Water pressure was kept at 7.2 MPa. Temperature recordings were performed at five axial and eight azimuthal locations, for each set of boundary conditions. Each recording lasted 120 s to provide reliable data on the variance, intermittency and frequency of the surface temperature time series at hand. Thorough calculations indicate that the uncertainty in the measured temperature is of 1.58 K. The mixing region extends up to 0.2 m downward of the hot inlets. In most cases, measurements indicate non-uniform mixing in the

  12. PROPOSICIÓN Y SIMULACIÓN DE UN ALGORITMO ADAPTATIVO PARA SISTEMAS DE ANTENAS INTELIGENTES PROPOSAL AND SIMULATION OF A ADAPTIVE ALGORITHMS FOR SMART ANTENNA SYSTEMS

    Directory of Open Access Journals (Sweden)

    Perla Espinosa Díaz

    2007-12-01

    Full Text Available En este trabajo se describen brevemente los sistemas de antenas inteligentes. Se presentan algunos algoritmos adaptativos que hacen que el sistema sea inteligente. Los algoritmos que se presentan son LMS y el RLS y serán sometidos a un análisis matemático para su posterior simulación vía MatLab. Éstos se escogen por su relación con un algoritmo híbrido desarrollado. Cada algoritmo será evaluado respecto a diferentes parámetros tales como convergencia, rapidez, estabilidad, etcThis paper briefly describes intelligent antenna systems. Some adaptive algorithms that render the system intelligent are presented. LMS and RLS algorithms are introduced and subject to mathematical analysis in order to allow simulation by using MatLab. The algorithms are chosen according to their relationship with the hybrid algorithm developed by the authors. Each algorithm is evaluated with reference to parameters such as convergence, speed, stability, etc

  13. Cracks propagation by stress corrosion cracking in conditions of Boiling Water Reactor (BWR); Propagacion de grietas por corrosion bajo esfuerzo en condiciones de reactor de agua hirviente (BWR)

    Energy Technology Data Exchange (ETDEWEB)

    Fuentes C, P

    2003-07-01

    This work presents the results of the assays carried out in the Laboratory of Hot Cells of the National Institute of Nuclear Research (ININ) to a type test tube Compact Tension (CT), built in steel austenitic stainless type 304L, simulating those conditions those that it operates a Boiling Water Reactor (BWR), at temperature 288 C and pressure of 8 MPa, to determine the speed to which the cracks spread in this material that is of the one that different components of a reactor are made, among those that it highlights the reactor core vessel. The application of the Hydrogen Chemistry of the Water is presented (HWC) that is one alternative to diminish the corrosion effect low stress in the component, this is gets controlling the quantity of oxygen and of hydrogen as well as the conductivity of the water. The rehearsal is made following the principles of the Mechanics of Elastic Lineal Fracture (LEFM) that considers a crack of defined size with little plastic deformation in the tip of this; the measurement of crack advance is continued with the technique of potential drop of direct current of alternating signal, this is contained inside the standard Astm E-647 (Method of Test Standard for the Measurement of Speed of Growth of Crack by fatigue) that is the one that indicates us as carrying out this test. The specifications that should complete the test tubes that are rehearsed as for their dimensions, it forms, finish and determination of mechanical properties (tenacity to the fracture mainly) they are contained inside the norm Astm E-399, the one which it is also based on the principles of the fracture mechanics. The obtained results were part of a database to be compared with those of other rehearsals under different conditions, Normal Chemistry of the Water (NWC) and it dilutes with high content of O{sub 2}; to determine the conditions that slow more the phenomena of stress corrosion cracking, as well as the effectiveness of the used chemistry and of the method of

  14. Genusa Bepu methodologies for the safety analysis of BWRs; Metodologias Bepu de Genusa para el analisis de seguridad de reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Trueba, M.; Garcia, J.; Goodson, C.; Ibarra, L.

    2016-08-01

    This article describes the BEPU methodologies developed by General Electric-Hitachi (GEH) for the evaluation of the BWR reactor safety analysis based on the TRACG best-estimate code. These methodologies are applicable to a wide range of events, operational transients (AOO), anticipated transients without scram (ATWS), loss of coolant accidents (LOCA) and instability events; to different BWR types operating commercially. General Electric (GE( designs and other vendors, including Generation III+ESBWR; to the new operation strategies, and to all types of BWR fuel. Their application achieves, among other benefits, a better understanding of the overall plant response and an improvement in margins to the operating limits; thus, the increase of flexibility in reactor operation and reduction in generation costs. (Author)

  15. Void Reactivity Coefficient Analysis during Void Fraction Changes in Innovative BWR Assemblies

    Directory of Open Access Journals (Sweden)

    Andrius Slavickas

    2015-01-01

    Full Text Available The study of the void reactivity variation in innovative BWR fuel assemblies is presented in this paper. The innovative assemblies are loaded with high enrichment fresh UO2 and MOX fuels. UO2 fuel enrichment is increased above existing design limitations for LWR fuels (>5%. MOX fuel enrichment with fissile Pu content is established to achieve the same burnup level as that of high enrichment UO2 fuel. For the numerical analysis, the TRITON functional module of SCALE 6.1 code with the 238-group ENDF/B-VI cross section data library was applied. The investigation of the void reactivity feedback is performed in the entire 0–100% void fraction range. Higher values of void reactivity coefficient for assembly loaded with MOX fuel are found in comparison with values for assembly loaded with UO2 fuel. Moreover, coefficient values for MOX fuel are positive over 75% void fraction. The variation of the void reactivity coefficient is explained by the results of the decomposition analysis based on four-factor formula and neutron absorption reactions for main isotopes. Additionally, the impact of the moderation enhancement on the void reactivity coefficient was investigated for the innovative assembly with MOX fuel.

  16. Decomposition Analysis of Void Reactivity Coefficient for Innovative and Modified BWR Assemblies

    Directory of Open Access Journals (Sweden)

    Andrius Slavickas

    2014-01-01

    Full Text Available The decomposition analysis of void reactivity coefficient for innovative BWR assemblies is presented in this paper. The innovative assemblies were loaded with high enrichment UO2 and MOX fuels. Additionally the impact of the moderation enhancement on the void reactivity coefficient through a full fuel burnup discharge interval was investigated for the innovative assembly with MOX fuel. For the numerical analysis the TRITON functional module of SCALE code with ENDF/B-VI cross section library was applied. The obtained results indicate the influence of the most important isotopes to the void reactivity behaviour over a fuel burnup interval of 70 GWd/t for both UO2 and MOX fuels. From the neutronic safety concern positive void reactivity coefficient values are observed for MOX fuel at the beginning of the fuel irradiation cycle. For extra-moderated assembly designs, implementing 8 and 12 water holes, the neutron spectrum softening is achieved and consequently the lower void reactivity values. Variations in void reactivity coefficient values are explained by fulfilled decomposition analysis based on neutrons absorption reactions for separate isotopes.

  17. Standard technical specifications General Electric plants, BWR/6. Volume 1, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS.

  18. A conceptual study on large-capacity safety relief valve (SRV) for future BWR plants

    Energy Technology Data Exchange (ETDEWEB)

    Yamada, Katsumi; Tokunaga, Takashi; Iwanaga, Masakazu; Kurosaki, Toshikazu [Toshiba Corporation, Isogo Nuclear Engineering Center, Yokohama (Japan)

    1999-07-01

    This paper presents a conceptual study of Safety Relief Valve (SRV) which has larger flow capacity than that of the conventional one and a new structure. Maintenance work of SRVs is one of the main concerns for next-generation Boiling Water Reactor (BWR) plants whose thermal power is planned to be increased. Because the number of SRVs increases with the thermal power, their maintenance would become critical during periodic inspections. To decrease the maintenance work, reduction of the number by increasing the nominal flow rate per SRV and a new structure suitable for easier treatment have been investigated. From a parameter survey of the initial and maintenance cost, the optimum capacity has been estimated to be between 180 and 200 kg/s. Primarily because the number of SRVs decreases in inversely proportional to the capacity, the total maintenance work decreases. The new structure of SRV, with an internally mounted actuator, decreases the number of the connecting parts and will make the maintenance work easier. A 1/4-scale model of the new SRV has been manufactured and performance tests have been conducted. The test results satisfied the design target, which shows the feasibility of the new structure. (author)

  19. Diffusion bonded matrix of HGMF applied for BWR condensate water purification

    Energy Technology Data Exchange (ETDEWEB)

    Soda, Fumitaka; Yukawa, Takao; Ito, Kazuyuki

    1984-03-01

    A high Gradient Magnetic Filter (HGMF) applied to the purification of power plant primary water has recently attracted much attention. In the application of HGMF to the water treatment of power plants, especially nuclear power plants, reliabillties of matrix (filtering medium) as well as removal performance for cruds (insoluble corrosion products) are considered to be important factors. To satisfy these factors, a new filtering medium named Diffision Bonded Matrix (DBM) has been developed and the test results are reported. Filtering efficiency and mechanical stiffness of DBM were examined using HGMF pilot test units consisting of 160 mm diameters x 240 mm length filter. The filtering velocity and the magnetic flux density used in this test were 800 m/h 5 kG, respectively. The filtering efficiencies and of 85-100% were obtained for artificial cruds for DBM. The DBM indicated slightly better filtering efficiency than for conventional wool matrix under the same filtering and matrix conditions. The DBM kept its original mechanical properties and very few pieces of fibers were broken off while the conventional wool matrix lost its volume elasticities and the considerable amount of fibers was broken off during the test operation. The results described here demonstrated the applicability of DBM for treatment of BWR primary water by High Gradient Magnetic Filter.

  20. In-plant material test experience under hydrogen water chemistry at a Japanese BWR plant

    Energy Technology Data Exchange (ETDEWEB)

    Ando, Masami; Koshiishi, Masato; Kato, Takahiko [Hitachi Ltd., Ibaraki (Japan). Hitachi Works; Abe, Ayumi; Sekiguchi, Masahiko; Takiguchi, Hideki

    1999-07-01

    Hydrogen injection technology has been applied to Japanese domestic aged BWR plants since 1994 to mitigate corrosive environment regarding Intergranular Stress Corrosion Cracking (IGSCC) of Reactor Internals (RINs). The Tsuruga Unit-1 plant has also been operated with this technology since 1997, considering suppression of radiation increase in the main steam piping system besides mitigation of corrosive environment in the reactor; the hydrogen injection rate in the feed water was about 0.5 ppm. In order to confirm the effects of the hydrogen injection on suppression of SCC susceptibility of the RIN materials, several in-plant material tests have been conducted using the reactor water clean up system (RWCU). Cyclic-Slow Strain Rate Tensile (C-SSRT) test, Slow Strain Rate Tensile (SSRT) test and Compact Tension (CT) test were performed in the test facilities which were installed at the sampling line from the RWCU. Evaluation of SCC life by means of the C-SSRT test was the first application as an accelerated SCC test for in-plant material tests. It was confirmed that the hydrogen injection in the feed water has a good mitigation effects on IGSCC performance of the RIN materials. Results will be discussed from a viewpoint of the test condition such as total oxidant, ECP, conductivity and loading/unloading. (author)

  1. Environmentally assisted cracking behavior of dissimilar metal weldments in simulated BWR coolant environments

    Science.gov (United States)

    Huang, J. Y.; Chiang, M. F.; Jeng, S. L.; Huang, J. S.; Kuo, R. C.

    2013-01-01

    The environmentally assisted cracking behavior of dissimilar metal (DM) welds, including Alloy 52-A 508 and Alloy 82-A508, under simulated BWR coolant conditions was studied. Effects of postweld heat treatment and sulfur content of the base metal on the corrosion fatigue and SCC growth rates of DM welds were evaluated. The crack growth rates for the DM weld heat-treated at 621 °C for 24 h were observed to be faster than those for the as-welded. But the DM weld heat-treated at 621 °C for 8 h + 400 °C for 200 h showed better SCC resistance than the as-welded. The longer the heat treatment at 621 °C, the higher the chromium carbides density along the grain boundary was observed. Sulfur could diffuse out of the base metal and segregate along the grain boundaries of the dilution zone, leading to weakening the grain boundary strength and the SCC resistance of the Alloy 52-A508 weld.

  2. Plant analyzer for high-speed interactive simulation of BWR power plant transients

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, H.S.; Lekach, S.V.; Mallen, A.N.; Wulff, W.; Cerbone, R.J.

    1984-04-01

    A combination of advanced modeling techniques and modern, special-purpose peripheral minicomputer technology is presented which affords realistic predictions of plant transient and severe off-normal events in LWR power plants through on-line simulations at a speed ten times faster than actual process speeds. Results are shown for a BWR plant simulation. The mathematical models account for nonequilibrium, nonhomogeneous two-phase flow effects in the coolant, for acoustical effects in the steam line and for the dynamics of the recirculation loop and feedwater train. Point kinetics incorporate reactivity feedback due to void fraction, fuel temperature, coolant temperature, and boron concentration. Control systems and trip logic are simulated for the nuclear steam supply system. The AD10 of Applied Dynamics International is the special-purpose peripheral processor. It is specifically designed for high-speed digital system simulation, accommodates hardware (instrumentation) in the input/output loop, and operates interactively on-line, like an analog computer. Results are shown to demonstrate computing capacity, accuracy, and speed. Simulation speeds have been achieved which are orders of magnitude faster than those of a CDC-7600 mainframe computer or ten times faster than real-time speed.

  3. Generic BWR-4 degraded core in-vessel study. Status report

    Energy Technology Data Exchange (ETDEWEB)

    1984-11-01

    Original intent of this project was to produce a phenomenological study of the in-vessel degradation which occurs during the TQUX and TQUV sequences for a generic BWR-4 from the initiation of the FSAR Chapter 15 operational transient through core debris bed formation to the failure of the primary pressure boundary. Bounding calculations were to be performed for the two high pressure and low pressure non-LOCA scenarios to assess the uncertainties in the current state of knowledge regarding the source terms for containment integrity studies. Source terms as such were defined in terms of hydrogen generation, unreacted metal, and coolant inventroy, and in terms of the form, sequencing and mode of dispersal through the primary vessel boundary. Fission product release was not to be considered as part of this study. Premature termination of the project, however, led to the dicontinuation of work on an as is basis. Work on the in-core phase from the point of scram to core debris bed formation was largely completed. A preliminary scoping calculation on the debris bed phase had been initiated. This report documents the status of the study at termination.

  4. Potential for containment leak paths through electrical penetration assemblies under severe accident conditions. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Sebrell, W.

    1983-07-01

    The leakage behavior of containments beyond design conditions and knowledge of failure modes is required for evaluation of mitigation strategies for severe accidents, risk studies, emergency preparedness planning, and siting. These studies are directed towards assessing the risk and consequences of severe accidents. An accident sequence analysis conducted on a Boiling Water Reactor (BWR), Mark I (MK I), indicated very high temperatures in the dry-well region, which is the location of the majority of electrical penetration assemblies. Because of the high temperatures, it was postulated in the ORNL study that the sealants would fail and all the electrical penetration assemblies would leak before structural failure would occur. Since other containments had similar electrical penetration assemblies, it was concluded that all containments would experience the same type of failure. The results of this study, however, show that this conclusion does not hold for PWRs because in the worst accident sequence, the long time containment gases stabilize to 350/sup 0/F. BWRs, on the other hand, do experience high dry-well temperatures and have a higher potential for leakage.

  5. Thermal utilization opportunities with a small-to-medium sized BWR

    Energy Technology Data Exchange (ETDEWEB)

    Konkin, D.; Simonson, C.J.; Dalai, A.K.; Tanino, K.; Guo, H., E-mail: doug.konkin@usask.ca [Univ. of Saskatchewan, Saskatchewan (Canada); Nishida, K.; Mochida, T. [Hitachi-GE Nuclear Energy, Ltd., Ibaraki (Japan); Ikegawa, T.; Kito, K. [Hitachi, Ltd., Ibaraki (Japan); Knudsen, R. [LeanOptions Consulting, Inc., Regina, Saskatchewan (Canada); Aikman, A. [SNC-Lavalin, Saskatoon, Saskatchewan (Canada); Humphries, R. [AMEC, Toronto, Ontario (Canada)

    2014-07-01

    Hitachi-GE Nuclear Energy Ltd. (Hitachi-GE) has developed a conceptual design for a Double MS: Modular Simplified & Medium Small Reactor (DMS) under the sponsorship of The Japan Atomic Power Company. Recent efforts have yielded enhancements for improved safety and reactor core performance. The DMS is an innovative small-to-medium sized Boiling Water Reactor (BWR), which, based only on electricity generation, has been estimated to almost overcome economy of scale concerns when compared to proven conventional Advanced Boiling Water Reactor (ABWR) technologies. In order to make the DMS more attractive, the University of Saskatchewan (U of S), Hitachi-GE and Hitachi Ltd. (Hitachi) have collaborated on a joint research and development (R&D) initiative to study the utilization of heat and steam from the Balance of Plant (BOP) associated with the DMS for thermal utilization (TU) applications. In this paper, the advanced features of the DMS and the individual projects of the R&D program will be described. (author)

  6. CFD Simulation of rigid venting of the containment of a BWR-5 Mark-II reactor; Simulacion CFD de los venteos rigidos de la contencion de un reactor BWR-5 Mark-II

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-15

    In conditions of prolonged loss of external energy or a severe accident, venting to the atmosphere is an alternative to prevent overpressure and release of fission products from the primary containment of a nuclear reactor. Due to the importance of flow determination through rigid vents, a computational fluid dynamics (CFD) model is proposed to verify the capacity of rigid vents in the primary containment of a boiling water reactor (BWR) under different operating conditions (pressure, temperature and compositions of the fluids). The model predicts and provides detailed information on variables such as mass flow and velocity of the venting gases. In the proposed model the primary containment gas is vented to the atmosphere via rigid vents (pipes) from the dry and wet pit. Is assumed that the container is pressurized because is in a defined scenario, and at one point the venting is open and the gas released into the atmosphere. The objective is to characterize the flow and validate the CFD model for the overpressure conditions that occur in an accident such as a LOCA, Sbo, etc. The model is implemented with Ansys-Fluent general-purpose CFD software based on the geometry of the venting ducts of the containment of a BWR. The model is developed three-dimensional and resolves at steady state for compressible flow and includes the effects of the turbulence represented by the Reynolds stress model. The CFD results are compared with the values of a one-dimensional and isentropic model for compressible flow. The relative similarity of results leads to the conclusion that the proposed CFD model can help to predict the rigid venting capacity of the containment of a BWR, however more information is required for full validation of the proposed model. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  8. Benchmark calculation for radioactivity inventory using MAXS library based on JENDL-4.0 and JEFF-3.0/A for decommissioning BWR plants

    Directory of Open Access Journals (Sweden)

    Tanaka Ken-ichi

    2016-01-01

    Full Text Available We performed benchmark calculation for radioactivity activated in a Primary Containment Vessel (PCV of a Boiling Water Reactor (BWR by using MAXS library, which was developed by collapsing with neutron energy spectra in the PCV of the BWR. Radioactivities due to neutron irradiation were measured by using activation foil detector of Gold (Au and Nickel (Ni at thirty locations in the PCV. We performed activation calculations of the foils with SCALE5.1/ORIGEN-S code with irradiation conditions of each foil location as the benchmark calculation. We compared calculations and measurements to estimate an effectiveness of MAXS library.

  9. 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.

  10. Programación VHDL de algoritmos de codificación para dispositivos de hardware reconfigurable

    OpenAIRE

    Sandoval R., Cecilia E.; Fedón R., Antonio

    2008-01-01

    Esta investigación trata acerca de la implementación sobre hardware reconfigurable de módulos de operación en álgebra de campos finitos de Galois, GF(2m), aplicados al área de codificación. Se ha seleccionado esta área de las matemáticas por ser la base de varios algoritmos en el área de corrección de errores y procesamiento digital de señales para criptografía, los cuales, por razones de desempeño y seguridad, es preferible implementarlos a nivel de hardware sobre dispositivos reconfigura...

  11. Revisando los métodos de agregación de unidades espaciales: MAUP, algoritmos y un breve ejemplo

    Directory of Open Access Journals (Sweden)

    Hada Melissa Sáenz Vela

    2016-01-01

    Full Text Available Los métodos de agregación espacial han generado interés en los últimos años debido a su fácil adecuación a diferentes objetivos. Más allá de eso existen razones estadísticas para aconsejar su aplicación: reducen el sesgo generado por el problema de unidad de área modificable (MAUP. En este artículo se presenta una revisión bibliográfica de este problema y de los diferentes métodos de agregación, así como la aplicación de un algoritmo a datos de la Zona Metropolitana del Valle de México.

  12. Especificación del algoritmo para un Test Adaptativo Informatizado de Analogías Verbales

    OpenAIRE

    Horacio Attorresi; Gabriela Lozzia

    2012-01-01

    Se presentan los pasos seguidos en el diseño de un Test Adaptativo Informatizado de Analogías Verbales. El algoritmo adaptativo se determinó teniendo en cuenta las características de un Banco de Ítems de Analogías Verbales construido a partir de la Teoría de Respuesta al Ítem, los objetivos de evaluación, la población por evaluar y las características del software. El Banco está compuesto por 64 ítems unidimensionales calibrados según el Modelo Logístico de Tres Parámetros, informativos en to...

  13. Modeling and validation of a mechanistic tool (MEFISTO) for the prediction of critical power in BWR fuel assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Adamsson, Carl, E-mail: carl.adamsson@psi.ch [Westinghouse Electric Sweden, SE-721 63, Vaesteras (Sweden); Le Corre, Jean-Marie, E-mail: lecorrjm@westinghouse.com [Westinghouse Electric Sweden, SE-721 63, Vaesteras (Sweden)

    2011-08-15

    Highlights: > The MEFISTO code efficiently and accurately predicts the dryout event in a BWR fuel bundle, using a mechanistic model. > A hybrid approach between a fast and robust sub-channel analysis and a three-field two-phase analysis is adopted. > MEFISTO modeling approach, calibration, CPU usage, sensitivity, trend analysis and performance evaluation are presented. > The calibration parameters and process were carefully selected to preserve the mechanistic nature of the code. > The code dryout prediction performance is near the level of fuel-specific empirical dryout correlations. - Abstract: Westinghouse is currently developing the MEFISTO code with the main goal to achieve fast, robust, practical and reliable prediction of steady-state dryout Critical Power in Boiling Water Reactor (BWR) fuel bundle based on a mechanistic approach. A computationally efficient simulation scheme was used to achieve this goal, where the code resolves all relevant field (drop, steam and multi-film) mass balance equations, within the annular flow region, at the sub-channel level while relying on a fast and robust two-phase (liquid/steam) sub-channel solution to provide the cross-flow information. The MEFISTO code can hence provide highly detailed solution of the multi-film flow in BWR fuel bundle while enhancing flexibility and reducing the computer time by an order of magnitude as compared to a standard three-field sub-channel analysis approach. Models for the numerical computation of the one-dimensional field flowrate distributions in an open channel (e.g. a sub-channel), including the numerical treatment of field cross-flows, part-length rods, spacers grids and post-dryout conditions are presented in this paper. The MEFISTO code is then applied to dryout prediction in BWR fuel bundle using VIPRE-W as a fast and robust two-phase sub-channel driver code. The dryout power is numerically predicted by iterating on the bundle power so that the minimum film flowrate in the bundle

  14. CCF analysis of high redundancy systems safety/relief valve data analysis and reference BWR application. Main report

    Energy Technology Data Exchange (ETDEWEB)

    Mankamo, T. [Avaplan Oy (Finland); Bjoere, S.; Olsson, Lena [ABB Atom AB, Vaesteraas (Sweden)

    1992-12-01

    Dependent failure analysis and modeling were developed for high redundancy systems. The study included a comprehensive data analysis of safety and relief valves at the Finnish and Swedish BWR plants, resulting in improved understanding of Common Cause Failure mechanisms in these components. The reference application on the Forsmark 1/2 reactor relief system, constituting of twelve safety/relief lines and two regulating relief lines, covered different safety criteria cases of reactor depressurization and overpressure protection function, and failure to re close sequences. For the quantification of dependencies, the Alpha Factor Model, the Binomial Probability Model and the Common Load Model were compared for applicability in high redundancy systems.

  15. 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.

  16. Optimización en Paralelo Basada en Poblaciones Usando GPGPU

    Directory of Open Access Journals (Sweden)

    Iliana Castro Liera

    2012-01-01

    Full Text Available En este artículo se muestran dos estrategias para aprovechar el poderío computacional de las unidades de procesamiento gráfico de propósito general GPGPU (General-Purpose computation on Graphics Processing Unit con arquitectura CUDA (Compute Unified Device Architecture para la solución de problemas de optimización utilizando algoritmos genéticos (AG y optimización por enjambre de partículas (PSO, Particle Swarm Optimization. Se muestra que esta implementación en una sola GPU consigue resultados de buena calidad en tiempos menores que los de un cluster de 16 computadoras con 32 núcleos.

  17. Pronósticos para el Rendimiento Del Trigo Usando Redes Neuronales Artificiales

    Directory of Open Access Journals (Sweden)

    Adriana Saldaña-Robles

    2010-01-01

    Full Text Available En el presente trabajo se desarrolló un modelo de predicción de rendimiento, empleando datos de, temperatura del aire, humedad del aire desde 1980 hasta el 2007 para el estado de Guanajuato. Para la predicción de rendimiento se utilizó una red neuronal artificial con una estructura del tipo feed-forward back propagación. Se realizaron pruebas con diferentes arquitecturas en la estructura de la red neuronal, el método de entrenamiento utilizado fue el algoritmo de Levenberg-Marquardt y el error fue evaluado con el MSE. Adicionalmente se alimentó la red neuronal con arreglos diferentes como elementos de entrada. El modelo fue validado con los datos del 2007. Los resultados muestran que los mejores elementos para predecir el rendimiento fueron: los arreglos de temperatura y humedad del aire, los cuales mostraron un MSE de 0.0036.

  18. Detailed investigation of radiolytic gas accumulation in BWR piping with the CMFD-Code helios

    Energy Technology Data Exchange (ETDEWEB)

    Tilman Diesselhorst [Framatome ANP GmbH, NGPS1, P.O.Box 3220, D-91058 Erlangen (Germany); Vladimir Stevanovic [University of Belgrade, 27 Marta 80, 11000 Belgrade (Yugoslavia)

    2005-07-01

    Full text of publication follows: In consequence of the incidents with hydrogen reaction in the Brunsbuettel and Hamaoka NPP's the accumulation of radiolytic gases in piping and components of BWR plants was checked using large scale temperature monitoring. But the more situations in the systems had been looked at, the more questions came up. It had to be realized that not in any concrete situation the possibility of critical gas accumulation can clearly be predicted due to many parameters of influence and conditions, partly acting contradictorily. Therefore the computational multi-fluid dynamic code HELIOS was developed to get a tool for the prediction of radiolytic gas accumulation allowing a detailed insight in the complex thermo-hydraulic and physic-chemical processes. Standard CFD codes generally give no satisfying and reliable results in this field. In the HELIOS code the processes of steam inflow into the modeled piping, convection and diffusion are taken into account, as well as the drainage of condensate film. The conservation equations of mass, energy and momentum are three-dimensionally formulated, separately for steam, gases and condensate. Considered are condensation and heat transfer in the fluid and the pipe wall and isolation, the influence of the gas fraction on the efficiency of condensation included. The effects of absorption and degassing between gas volume and liquid film are also considered. Nearly any piping arrangement can be modeled consisting of vertical, horizontal and inclined sections and bends of different diameter. Various conditions of heat losses can be considered. Results are the time dependent fields of gas/vapor fraction and condensate and the respective temperatures and flow velocities, as well as the accumulation rate of radiolytic gas. The code is verified in its formulations and validated in its applicability for relevant piping systems by comparing the results with analytical solutions, results of quasi one

  19. Reconstrucción filogenética usando geometría algebraica

    Directory of Open Access Journals (Sweden)

    Casanellas, Marta

    2010-12-01

    Full Text Available A new approach to phylogenetic reconstruction has been emerging in the last years. Given an evolutionary model, the joint probability distribution of the nucleotides for these species satisfy some algebraic constraints called invariants. These invariants have theoretical and practical interest, since they can be used to infer phylogenies. In this paper, we explain how to use these invariants to design algorithms for phylogenetic reconstruction and we show how the application of tools and theoretical results coming from commutative algebra and algebraic geometry can improve the performance and the efficiency of these algorithms.

    Una nueva aproximación a la reconstrucción filogenética basada en la geometría algebraica está ganando fuerza en los últimos años. Fijado un modelo evolutivo para un conjunto de especies, las distribuciones teóricas de los nucleótidos de estas especies satisfacen ciertas relaciones algebraicas que llamamos invariantes. Estos invariantes son de interés teórico y práctico dado que se pueden utilizar para inferir filogenias. En este artículo, explicamos cómo usar los invariantes para implementar algoritmos de reconstrucción filogenética y mostramos cómo el uso de técnicas y resultados teóricos procedentes del álgebra conmutativa y la geometría algebraica puede contribuir en la mejora en la eficacia y la eficiencia de estos algoritmos.

  20. Overview of New Tools to Perform Safety Analysis: BWR Station Black Out Test Case

    Energy Technology Data Exchange (ETDEWEB)

    D. Mandelli; C. Smith; T. Riley; J. Nielsen; J. Schroeder; C. Rabiti; A. Alfonsi; Cogliati; R. Kinoshita; V. Pasucci; B. Wang; D. Maljovec

    2014-06-01

    Dynamic Probabilistic Risk Assessment (DPRA) methodologies couple system simulator codes (e.g., RELAP, MELCOR) with simulation controller codes (e.g., RAVEN, ADAPT). While system simulator codes accurately model system dynamics deterministically, simulation controller codes introduce both deterministic (e.g., system control logic, operating procedures) and stochastic (e.g., component failures, parameter uncertainties) elements into the simulation. Typically, a DPRA is performed by: 1) sampling values of a set of parameters from the uncertainty space of interest (using the simulation controller codes), and 2) simulating the system behavior for that specific set of parameter values (using the system simulator codes). For complex systems, one of the major challenges in using DPRA methodologies is to analyze the large amount of information (i.e., large number of scenarios ) generated, where clustering techniques are typically employed to allow users to better organize and interpret the data. In this paper, we focus on the analysis of a nuclear simulation dataset that is part of the Risk Informed Safety Margin Characterization (RISMC) Boiling Water Reactor (BWR) station blackout (SBO) case study. We apply a software tool that provides the domain experts with an interactive analysis and visualization environment for understanding the structures of such high-dimensional nuclear simulation datasets. Our tool encodes traditional and topology-based clustering techniques, where the latter partitions the data points into clusters based on their uniform gradient flow behavior. We demonstrate through our case study that both types of clustering techniques complement each other in bringing enhanced structural understanding of the data.

  1. A safety and regulatory assessment of generic BWR and PWR permanently shutdown nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Travis, R.J.; Davis, R.E.; Grove, E.J.; Azarm, M.A. [Brookhaven National Lab., Upton, NY (United States)

    1997-08-01

    The long-term availability of less expensive power and the increasing plant modification and maintenance costs have caused some utilities to re-examine the economics of nuclear power. As a result, several utilities have opted to permanently shutdown their plants. Each licensee of these permanently shutdown (PSD) plants has submitted plant-specific exemption requests for those regulations that they believe are no longer applicable to their facility. This report presents a regulatory assessment for generic BWR and PWR plants that have permanently ceased operation in support of NRC rulemaking activities in this area. After the reactor vessel is defueled, the traditional accident sequences that dominate the operating plant risk are no longer applicable. The remaining source of public risk is associated with the accidents that involve the spent fuel. Previous studies have indicated that complete spent fuel pool drainage is an accident of potential concern. Certain combinations of spent fuel storage configurations and decay times, could cause freshly discharged fuel assemblies to self heat to a temperature where the self sustained oxidation of the zircaloy fuel cladding may cause cladding failure. This study has defined four spent fuel configurations which encompass all of the anticipated spent fuel characteristics and storage modes following permanent shutdown. A representative accident sequence was chosen for each configuration. Consequence analyses were performed using these sequences to estimate onsite and boundary doses, population doses and economic costs. A list of candidate regulations was identified from a screening of 10 CFR Parts 0 to 199. The continued applicability of each regulation was assessed within the context of each spent fuel storage configuration and the results of the consequence analyses.

  2. BWR: Development and Validation of KERENA reactor; Les REB: Developpement et validation du reacteur KERENA

    Energy Technology Data Exchange (ETDEWEB)

    Diercks, F.; Fuchs, M. [E.ON Kernkraft GmbH (Germany); Erve, M.; Pasler, D. [AREVA (Germany)

    2010-07-01

    KERENA is an advanced boiling water reactor, combining AREVA's and E.ON's expertise. A project was launched to customize the final basic design for this advanced nuclear power plant having a net power output of about 1, 250 MW, a net efficiency of about 37% and a design service life of 60 years. The development takes into account the technical and accumulated operating experience of the project partners. The plant safety concept is based on an optimized combination of a reduced number of proven active safety systems and passive safety systems, utilizing basic laws of physics, such as gravity, enabling them to function without electrical power supplies or activation by powered instrumentation and control systems. Control of a postulated core melt accident is assured with considerable safety margins thanks to passive flooding of the containment for in-vessel melt retention. All passive safety systems are validated in an experimental test program at AREVA, using 1:1 scale test facilities (INKA test facility Karlstein). The KERENA boiling water reactor is compliant with international nuclear codes and standards, and is also designed to withstand the effects of an aircraft crash involving a military aircraft or a large passenger airline. The safety level of the KERENA reactor has been able to be significantly increased compared to existing BWR plants. The advantages of the new safety concept are: -) Reduced susceptibility of safety systems to failures; -) Larger safety margins; -) Good plant behavior in the event of accidents due to the fact that conditions change at a slower rate; -) Grace periods of several days after an accident before operator intervention is required; -) Significantly reduced impact of operator error on reactor safety; -) No need for large-scale emergency response actions such as temporary evacuation or relocation of the neighboring population following a core melt accident. (A.C.)

  3. Development and Assessment of CTF for Pin-resolved BWR Modeling

    Energy Technology Data Exchange (ETDEWEB)

    Salko, Robert K [ORNL; Wysocki, Aaron J [ORNL; Collins, Benjamin S [ORNL; Avramova, Maria [North Carolina State University (NCSU), Raleigh; Gosdin, Chris [Pennsylvania State University

    2017-01-01

    CTF is the modernized and improved version of the subchannel code, COBRA-TF. It has been adopted by the Consortium for Advanced Simulation for Light Water Reactors (CASL) for subchannel analysis applications and thermal hydraulic feedback calculations in the Virtual Environment for Reactor Applications Core Simulator (VERA-CS). CTF is now jointly developed by Oak Ridge National Laboratory and North Carolina State University. Until now, CTF has been used for pressurized water reactor modeling and simulation in CASL, but in the future it will be extended to boiling water reactor designs. This required development activities to integrate the code into the VERA-CS workflow and to make it more ecient for full-core, pin resolved simulations. Additionally, there is a significant emphasis on producing high quality tools that follow a regimented software quality assurance plan in CASL. Part of this plan involves performing validation and verification assessments on the code that are easily repeatable and tied to specific code versions. This work has resulted in the CTF validation and verification matrix being expanded to include several two-phase flow experiments, including the General Electric 3 3 facility and the BWR Full-Size Fine Mesh Bundle Tests (BFBT). Comparisons with both experimental databases is reasonable, but the BFBT analysis reveals a tendency of CTF to overpredict void, especially in the slug flow regime. The execution of these tests is fully automated, analysis is documented in the CTF Validation and Verification manual, and the tests have become part of CASL continuous regression testing system. This paper will summarize these recent developments and some of the two-phase assessments that have been performed on CTF.

  4. Environmental mitigation for SCC initiation of BWR core internals by hydrogen injection during start-up

    Energy Technology Data Exchange (ETDEWEB)

    Dozaki, K.; Abe, A.; Nagata, N.; Takiguchi, H. [The Japan Atomic Power Co. (Japan)

    2004-07-01

    Hydrogen injection into the reactor water has been applied to many BWR power stations. Since hydrogen injected accelerates recombination of oxidant generated by water radiolysis, oxidant concentration, such as dissolved oxygen concentration in reactor water can be reduced. As the result of the reduction of oxidant concentration, Electrochemical Corrosion Potential (ECP) at the surface of structural material can be lowered. Lowered ECP moderates Stress Corrosion Cracking (SCC) sensitivity of structural materials, such as stainless steels. As usual, hydrogen injection system begins to work after the plant start-up is finished, when the condition of normal operation is established. Accordingly, Hydrogen Water Chemistry (HWC) does not cover all the period of plant operation. As far as SCC crack growth is considered, loss of HWC during plant start-up does not result in significant crack growth, because of duration of plant start-up is much shorter than that of plant normal operation, when HWC condition is being satisfied. However, the reactor water environment and load conditions during a plant start-up may contribute to the initiation of SCC. It is estimated that the core internals are subjected to the strain rate that may cause susceptibility to SCC initiation during start-up. Dissolved oxygen (DO) and hydrogen peroxide (H{sub 2}O{sub 2}) has a peak, and ECP is in high levels during start-up. Therefore it is beneficial to perform hydrogen injection during start-up as well in order to suppress SCC initiation. We call it HWC During Start-up (HDS) here. (orig.)

  5. Development of the radiation models of a BWR type reactor and it facility in the SUN-RAH; Desarrollo de modelos de radiacion de un reactor tipo BWR y su instalacion en el SUN-RAH

    Energy Technology Data Exchange (ETDEWEB)

    Barron A, I. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. e-mail: isbarron@yahoo.com.mx

    2005-07-01

    This work about generation models, transport in processes and radioactive contamination of areas of a BWR central, is an amplification to the project developed in the UNAM to have a support tool in subjects or electric generation courses. It is planned about the implementation of models of radiation generation in a BWR type reactor for complement the functions developed in the University Simulator of Nucleo electric- Boiling water reactor (SUN-RAH) which it has been implemented in Simulink of MatLab and it has a model for the dynamics of one nucleo electric central that presents the main characteristics of the reactor vessel, the recirculation system, steam lines, turbines, generator, condensers and feeding water, defined by the main processes that intervene in the generation of energy of these plants. By this way the radiation monitoring systems for area and process, operate simultaneously with the processes of energy generation, with that is possible to observe the changes that present with respect to the operation conditions of the plant, and likewise to appreciate the radiation transport process through the components of the reactor, steam lines and turbines, for different operation conditions and possible faults that they could be presented during the reactor operation. (Author)

  6. Design of a mixed recharge with MOX assemblies of greater relation of moderation for a BWR reactor; Diseno de una recarga mixta con ensambles MOX de mayor relacion de moderacion para un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J.R.; Alonso V, G.; Palacios H, J. [ININ, Carretera Mexico-Toluca Km. 36.5, 52045 Estado de Mexico (Mexico)]. e-mail: jrrs@nuclear.inin.mx

    2004-07-01

    The study of the fuel of mixed oxides of uranium and plutonium (MOX) it has been topic of investigation in many countries of the world and those are even discussed in many places the benefits of reprocessing the spent fuel to extract the plutonium created during the irradiation of the fuel in the nuclear power reactors. At the moment those reactors that have been loaded partially with MOX fuel, are mainly of the type PWR where a mature technology has been achieved in some countries like they are France, Belgium and England, however the experience with reactors of the type BWR is more limited and it is continued studying the best way to introduce this type of fuel in BWRs, one of the main problems to introduce MOX in reactors BWR is the neutronic design of the same one, existing different concepts to introduce the plutonium in the assemblies of fuel and one of them is the one of increasing the relationship of moderation of the assemble. In this work a MOX fuel assemble design is presented and the obtained results so far in the ININ. These results indicate that the investigated concept has some exploitable advantages in the use of the MOX fuel. (Author)

  7. Detección de daño estructural por algoritmos genéticos: una comparación de diferentes tipos de codificación de individuos

    Directory of Open Access Journals (Sweden)

    Jesús Daniel Villalba Morales

    2010-01-01

    Full Text Available En este artículo se aplican los algoritmos genéticos para resolver el problema de detección de daño estructural, y se comparan tres tipos de codificación de individuos: binaria, real y binaria con código redundante. Los algoritmos de código binario y real calculan la extensión del daño para cada elemento en la estructura, por lo tanto, para mejorar su desempeño fue utilizado un proceso de re-inicialización de individuos. Por su parte, el algoritmo de código redundante busca en forma dinámica cuáles son los elementos dañados y cuantifica el daño solo para esos elementos. Para determinar el desempeño de los algoritmos se analiza una armadura sobre diversos escenarios de daño simple y múltiple, y el daño es considerado como una reducción en el módulo de elasticidad de los elementos dañados. Los resultados muestran que el algoritmo que mejor localiza y cuantifica el daño corresponde al algoritmo genético de código redundante

  8. An assessment of BWR (boiling water reactor) Mark-II containment challenges, failure modes, and potential improvements in performance

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, D.L.; Jones, K.R.; Dallman, R.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA)); Wagner, K.C. (Science Applications International Corp., Albuquerque, NM (USA))

    1990-07-01

    This report assesses challenges to BWR Mark II containment integrity that could potentially arise from severe accidents. Also assessed are some potential improvements that could prevent core damage or containment failure, or could mitigate the consequences of such failure by reducing the release of fission products to the environment. These challenges and improvements are analyzed via a limited quantitative risk/benefit analysis of a generic BWR/4 reactor with Mark II containment. Point estimate frequencies of the dominant core damage sequences are obtained and simple containment event trees are constructed to evaluate the response of the containment to these severe accident sequences. The resulting containment release modes are then binned into source term release categories, which provide inputs to the consequence analysis. The output of the consequences analysis is used to construct an overall base case risk profile. Potential improvements and sensitivities are evaluated by modifying the event tree spilt fractions, thus generating a revised risk profile. Several important sensitivity cases are examined to evaluate the impact of phenomenological uncertainties on the final results. 75 refs., 25 figs., 65 tabs.

  9. Data report of BWR post-CHF tests. Transient core thermal-hydraulic test program. Contract research

    Energy Technology Data Exchange (ETDEWEB)

    Iguchi, Tadashi; Itoh, Hideo; Kiuchi, Toshio; Watanabe, Hironori; Kimura, Mamoru; Anoda, Yoshinari [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    JAERI has been performing transient core thermal-hydraulic test program. In the program, authors performed BWR/ABWR DBE simulation tests with a test facility, which can simulate BWR/ABWR transients. The test facility has a 4 x 4 bundle core simulator with 15-rod heaters and one non-heated rod. Through the tests, authors quantified the thermal safety margin for core cooling. In order to quantify the thermal safety margin, authors collected experimental data on post-CHF. The data are essential for the evaluation of clad temperature transient when core heat-up occurs during DBEs. In comparison with previous post-CHF tests, present experiments were performed in much wider experimental condition, covering high clad temperature, low to high pressure and low to high mass flux. Further, data at wider elevation (lower to higher elevation of core) were obtained in the present experiments, which make possible to discuss the effect of axial position on thermal-hydraulics, while previous works usually discuss the thermal-hydraulics at the position where the first heat-up occurs. This data report describes test procedure, test condition and major experimental data of post-CHF tests. (author)

  10. Technical Specification action statements requiring shutdown. A risk perspective with application to the RHR/SSW systems of a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Mankamo, T. [Avaplan Oy, Espoo (Finland); Kim, I.S.; Samanta, P.K. [Brookhaven National Lab., Upton, NY (United States)

    1993-11-01

    When safety systems fail during power operation, the limiting conditions for operation (LCOs) and associated action statements of technical specifications typically require that the plant be shut down within the limits of allowed outage time (AOT). However, when a system needed to remove decay heat, such as the residual heat removal (RHR) system, is inoperable or degraded, shutting down the plant may not necessarily be preferable, from a risk perspective, to continuing power operation over a usual repair time, giving priority to the repairs. The risk impact of the basic operational alternatives, i.e., continued operation or shutdown, was evaluated for failures in the RHR and standby service water (SSW) systems of a boiling-water reactor (BWR) nuclear power plant. A complete or partial failure of the SSW system fails or degrades not only the RHR system but other front-line safety systems supported by the SSW system. This report presents the methodology to evaluate the risk impact of LCOs and associated AOT; the results of risk evaluation from its application to the RHR and SSW systems of a BWR; the findings from the risk-sensitivity analyses to identify alternative operational policies; and the major insights and recommendations to improve the technical specifications action statements.

  11. Aplicación de algoritmos genéticos en la generación automática de horarios docentes en la Facultad Regional Granma

    Directory of Open Access Journals (Sweden)

    Karel Rodríguez Varona

    2012-12-01

    Full Text Available En este trabajo se propone una solución, basada en Algoritmos Genéticos, al problema de la generación de horarios que presenta la Facultad Regional Granma de la Universidad de las Ciencias Informáticas. Se realiza el modelado de la solución y la implementación del algoritmo propuesto en el lenguaje de programación Java. Una de las particularidades de este problema es la presencia de restricciones que deben ser satisfechas. Lo complicado, cuando de generalizar se trata, es que cada centro educacional es diferente en cuanto a recursos disponibles y por lo tanto en cuanto a las restricciones que puede presentar (también se tienen restricciones "generales" que son aplicables a cualquier institución.

  12. 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.

  13. 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.

  14. Processo de ensino e aprendizagem de algoritmos integrando ambientes imersivos e o paradigma de blocos de programação visual

    OpenAIRE

    Érico Marcelo Hoff do Amaral

    2015-01-01

    A dificuldade dos estudantes em relação à aprendizagem de Algoritmos é um assunto que se renova, devido à grande demanda de mercado em relação a profissionais da área de Tecnologia da Informação. A complexidade na construção do raciocínio lógico e do Pensamento Computacional leva a altos índices de evasão e reprovação em disciplinas introdutórias de programação. A concepção tradicional no ensino de Algoritmos possui grandes desafios, da elaboração de materiais interessantes, que estimulem o a...

  15. ALGORITMO PARA A RECONSTRUÇÃO DA IMAGEM DA VAGAROSIDADE A PARTIR DE SINAIS SÍSMICOS CORROMPIDOS COM RUÍDO GROUND ROLL

    Directory of Open Access Journals (Sweden)

    Cláubio Landney Lima Bandeira

    2010-11-01

    Full Text Available Inversão sísmica é uma técnica de imageamento sísmico tomográfico para criar um modelo no espaço da velocidade ou da vagarosidade que pode reconstruir corretamente o conjunto de dados sísmicos medido. Isso geralmente é implementado através da minimização de um algoritmo de inversão dos mínimos quadrados. Este algoritmo reconstrói imagens sísmicas com artefatos produzidos pelo ruído impulsivo coerente ground roll contidos no conjunto de dados de entrada sísmicos brutos. Todavia, este ruído compromete a fidelidade dos dados. Apresentamos resultados superiores aplicando filtros visando remover os efeitos causados por este ruído.

  16. Algoritmo para la atención integral a pacientes con cáncer cutáneo no melanoma

    OpenAIRE

    Victoria Bárzaga , Héctor Oscar

    2012-01-01

    Se presenta un algoritmo para la atención integral a pacientes con cáncer cutáneo no melanoma que incluye: secuencia de acciones, funciones del personal médico y paramédico, métodos preventivos y terapéuticos, medios diagnósticos y el modo de seguimiento clínico. Se estableció un consenso sobre el fundamento teórico y práctico del algoritmo mediante la variante Delphi del método de expertos y se capacitó el personal de la salud involucrado en su implementación. Para la confección del algoritm...

  17. Interação Humano - Computador usando Visão Computacional

    Directory of Open Access Journals (Sweden)

    Bernardo Bucher B. Barbosa

    2015-07-01

    Full Text Available Este trabalho visa estudar maneiras de se explorar a Interação Humano Computador, usando Visão Computacional. A idéia tem como objetivo um esforço para tornar o computador mais interativo com o usuário, sem a necessidade da compra de um hardware ou acessório específico para tal. O produto final deste trabalho em desenvolvimento é um software que contempla esta funcionalidade, tornando o computador mais interativo.

  18. Estudio y construcción de un lazo enganchado en fase usando el programa SPICE

    OpenAIRE

    2005-01-01

    En este artículo presentamos la simulación y construcción de un lazo enganchado en Fase (PLL) usando el programa de simulación de circuitos PSPICE. Los bloques principales del PLL lo forman un oscilador controlado por voltaje (VCO), al que se conecta un limitador de amplitud y un filtro para limpiar los espúreos generados. Para el diseño del VCO se ha utilizado un oscilador básico de Colpitts, al que se incorpora en el circuito de realimentación un diodo varicap controlado por tensión. El ...

  19. Aprendendo fun??es de ranking baseadas em blocos usando programa??o gen?tica

    OpenAIRE

    Sanchez, Pedro Antonio Gonzales

    2013-01-01

    Na atualidade, a Internet ? considerada uma poderosa ferramenta de comunica??o e informa??o. Seu impacto na sociedade est? aumentando cada vez mais, o que significa que est? se tornando indispens?vel. Neste contexto, sistemas de busca por informa??o tornam-se cada vez mais importantes. Neste trabalho, propomos um novo m?todo de busca capaz de aprender fun??es de ranking que exploram a estrutura em bloco das p?ginas Web, usando programa??o gen?tica. Diferentemente de trabalhos anteriores, noss...

  20. Control de los movimientos de un robot usando un acelerómetro y nios ii

    OpenAIRE

    Palacios Játiva, Pablo Geovanny; Bastidas Carrillo, Segundo Jeancarlos; Ponguillo Intriago, Ronald

    2014-01-01

    Este proyecto esta basado en el desarrollo e implementación de un control remoto para manejar los movimientos de un robot LEGO MINDSTORM NXT usando un acelerómetro ADXL345 incorporado en la tarjeta de desarrollo DE0-NANO y el procesador NIOS II. En este trabajo se abordan de forma general conceptos sobre protocolos de comunicación SPI, el protocolo usado por el robot, además de las características principales de la tarjeta DE0 NANO, de la FPGA Cyclone IV, del acelerómetro ADXL345 y del robot ...

  1. LAS PREFERENCIAS DEL CONSUMIDOR USANDO EL MÉTODO DE MÁXIMAS DIFERENCIAS

    OpenAIRE

    Pablo Farías; Bruno Fistrovic

    2016-01-01

    RESUMEN Este estudio tiene como objetivo identificar los atributos más importantes que el consumidor limeño utiliza en el proceso de elección del vino. Adicionalmente, se busca identificar diferencias entre segmentos en estas preferencias. La metodología consiste en una encuesta a consumidores de vino usando el método de máximas diferencias. El estudio es único en América Latina, donde existe una brecha importante en el mercado del vino y donde el método de máximas diferencias es inexplorado ...

  2. Proposta de análise genética de curvas de crescimento de bovinos por meio do algoritmo SAEM

    Directory of Open Access Journals (Sweden)

    N.A.M. Silva

    2012-10-01

    Full Text Available Compararam-se duas diferentes metodologias na avaliação genética de curvas de crescimento de animais Nelore: o algoritmo SAEM e o método Two-step. Para a implementação dessas metodologias, foram utilizados o modelo de crescimento de Brody modificado e o modelo touro. A diferença entre o SAEM e o Two-step é que o algoritmo SAEM estima simultaneamente parâmetros do modelo e efeitos genéticos e ambientais, e o método Two-step faz esse processo de estimação em duas etapas distintas. Mais ainda, o algoritmo SAEM utiliza o método de máxima verossimilhança, e o do Two-step o de máxima verossimilhança restrita. Foram obtidos, com base nas metodologias testadas, além das estimativas de efeitos fixos e parâmetros genéticos, os valores genéticos preditos para os touros avaliados. A partir dos valores genéticos preditos, foram obtidas as curvas genéticas para os touros. O algoritmo SAEM mostrou-se consistente na estimação dos efeitos fixos e na predição dos efeitos aleatórios, apresentando-se como uma alternativa viável para avaliação genética de animais Nelore.

  3. 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.

  4. 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.

  5. Estudio de algoritmos de reducción de imágenes digitales mediante interpolación lineal

    OpenAIRE

    Gómez Uzquiano, Jesús

    2010-01-01

    El principal objetivo de este proyecto se basa en la realización de una investigación detallada de los distintos algoritmos de reducción de imágenes existentes que están basados en el  procedimiento numérico de interpolación lineal, analizando las diferentes técnicas y métodos con los que estos algoritmos abordan el procesamiento escalar de imágenes digitales. Basándonos en los algoritmos más comunmente conocidos dentro de este campo y en diferentesmétodos de representación digital de funcion...

  6. 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.

  7. Algoritmo basado en Nubes de Partículas para la optimización global de funciones en espacios multidimensionales complejos

    Directory of Open Access Journals (Sweden)

    Rafael Bello Pérez

    2012-03-01

    Full Text Available Optimización basada en Nubes de Partículas es una meta-heurística bionspirada que permite encontrar soluciones prometedoras en espacios de búsqueda complejos. En Optimización basada en Nubes de Partículas estándar es frecuente que la nube de  partículas sea atraída por soluciones sub-óptimas, provocando la convergencia prematura del algoritmo y el estancamiento de la bandada. En este artículo se presenta una variante modificada del algoritmo Optimización basada en Nubes de Partículas, que haciendo uso de muestras aleatorias en vecindades variables dispersa la bandada cuando es detectado un estado de estancamiento, ofreciendo de esta manera una alternativa de escape a los óptimos locales. La efectividad y eficiencia del algoritmo propuesto es examinada y resultados experimentales muestran su capacidad para aproximar el mínimo global de nueve funciones benchmark reportadas en la literatura.

  8. Algoritmo para la obtención de parámetros antropométricos en imágenes de rostros frontales

    Directory of Open Access Journals (Sweden)

    Jorge L. Camargo Díaz

    2011-01-01

    Full Text Available Este trabajo describe un algoritmo desarrollado bajo técnicas de procesamiento de imágenes para la obtención automática de los principales parámetros antropométricos del rostro en posición frontal. El algoritmo emplea un modelo gaussiano de la piel con el fin de detectar el rostro del individuo presente en la escena. Luego, por medio de un conjunto de ecuaciones morfológicas, se segmentan las regiones del rostro de interés (ojos, nariz y labios. Una vez detectadas estas regiones se calculan las coordenadas de los puntos de referencia faciales y, finalmente, se relacionan para obtener los parámetros antropométricos. El algoritmo es capaz de detectar automáticamente 14 de los 18 puntos de referencia definidos por Farkas, con un error promedio de ubicación menor a 3 mm. Con este conjunto de puntos se miden 23 parámetros antropométricos faciales en un tiempo promedio de 13 segundos.

  9. Desarrollo de un nuevo algoritmo heurístico para la solución del problema de planificación de rutas con ventanas de tiempo

    Directory of Open Access Journals (Sweden)

    Manuel Martínez Carballo

    2005-01-01

    Full Text Available En este trabajo se presenta un nuevo algoritmo para la resolución del conocido problema de planificación de rutas de transporte sujetas a ventanas de tiempo. Este problema se conoce en la literatura como el VRPTW o Vehicle Routing Problem with Time Windows, y para su solución se han desarrollado multitud de métodos y técnicas exactos y heurísticos. Si bien los primeros requieren una elevada inversión en tiempos de cálculo, los segundos aportan soluciones aproximativas en menores tiempos de cálculo. En este trabajo se presenta un nuevo algoritmo de construcción de rutas de forma aproximativa. Las soluciones arrojadas por el algoritmo mejoran en algunos casos las aportadas por otros autores con métodos similares, aunque nuestro modelo también tiene algunas limitaciones que se comentan en este trabajo.

  10. Proposta de análise de desempenho de algoritmos para otimização de redes de filas M/G/c/K baseada em DOE

    Directory of Open Access Journals (Sweden)

    Helinton André Lopes Barbosa

    2014-03-01

    Full Text Available Neste artigo são apresentados resultados da análise empírica de um algoritmo proposto na literatura para alocação de áreas de espera em redes de filas finitas, abertas e acíclicas, com serviços gerais e servidores múltiplos. Dos resultados computacionais é concluído que o tempo de processamento do algoritmo depende do número de servidores da rede, como era de se esperar, mas independe do quadrado do coeficiente de variação do tempo de serviço. Conclui-se também que as alocações obtidas são robustas e que, em geral, o desempenho global previsto para a rede é acurado, conforme atestado por simulações. Finalmente, chega-se à conclusão de que não é fácil encontrar regras heurísticas para o posicionamento dos servidores múltiplos na rede de filas sem aplicar um algoritmo de alocação de áreas de espera para determinar qual configuração é a melhor.

  11. Mitigation strategies of intergranular corrosion in systems of reactors of water boiling (BWR). Combined action of the chemistry of the hydrogen and the oxygen; Estrategias de mitigacion de la corrosion intergranular en sistemas de reactores de agua en ebullicion (BWR). Accion combinada de la quimica del hidrogeno y del oxigeno

    Energy Technology Data Exchange (ETDEWEB)

    Verdugo, M.

    2015-07-01

    Inter-Granular Stress Corrosion cracking (IGSCC) in austenitic stainless steel and in austenitic nickel-based alloys has been the subject of many studies the aim of which was to resolve one of the main problems faced by BWR nuclear power plants since the 1960s. This corrosion phenomenon is the result of the combined action of three factors: sensitization of the material, high local stresses and an aggressive medium. This paper deals with these factors separately and analyzes the oxidative chemistry of BWR reactors (aggressivity of the medium) as one the main causes if IGSCC. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-10-15

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

  13. Qualification of helium measurement system for detection of fuel failures in a BWR

    Science.gov (United States)

    Larsson, I.; Sihver, L.; Loner, H.; Grundin, A.; Helmersson, J.-O.; Ledergerber, G.

    2014-05-01

    There are several methods for surveillance of fuel integrity during the operation of a boiling water reactor (BWR). The detection of fuel failures is usually performed by analysis of grab samples of off-gas and coolant activities, where a measured increased level of ionizing radiation serves as an indication of new failure or degradation of an already existing one. At some nuclear power plants the detection of fuel failures is performed by on-line nuclide specific measurements of the released fission gases in the off-gas system. However, it can be difficult to distinguish primary fuel failures from degradation of already existing failures. In this paper, a helium measuring system installed in connection to a nuclide specific measuring system to support detection of fuel failures and separate primary fuel failures from secondary ones is presented. Helium measurements provide valuable additional information to measurements of the gamma emitting fission gases for detection of primary fuel failures, since helium is used as a fill gas in the fuel rods during fabrication. The ability to detect fuel failures using helium measurements was studied by injection of helium into the feed water systems at the Forsmark nuclear power plant (NPP) in Sweden and at the nuclear power plant Leibstadt (KKL) in Switzerland. In addition, the influence of an off-gas delay line on the helium measurements was examined at KKL by injecting helium into the off-gas system. By using different injection rates, several types of fuel failures with different helium release rates were simulated. From these measurements, it was confirmed that the helium released by a failed fuel can be detected. It was also shown that the helium measurements for the detection of fuel failures should be performed at a sampling point located before any delay system. Hence, these studies showed that helium measurements can be useful to support detection of fuel failures. However, not all fuel failures which occurred at

  14. BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage

    Energy Technology Data Exchange (ETDEWEB)

    Bevard, Bruce Balkcom [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mertyurek, Ugur [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Scaglione, John M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-10-01

    utilized or referenced, justification has been provided as to why the data can be utilized for BWR fuel.

  15. Direct torus venting analysis for Chinshan BWR-4 plant with MARK-I containment

    Energy Technology Data Exchange (ETDEWEB)

    Yuann, Yng-Ruey, E-mail: ryyuann@iner.gov.tw

    2017-03-15

    Highlights: • Study the effectiveness of Direct Torus Venting System (DTVS) during extended SBO of 24 h for Chinshan MARK-I plant. • Containment response is analyzed by GOTHIC based on boundary conditions from RETRAN calculation. • Analyses are performed with and without DTVS, respectively. • Suppression pool is sub-divided and thermal stratification is observed. - Abstract: The Chinshan plant, owned by Taiwan Power Company, has twin units of BWR-4 reactor and MARK-I containment. Both units have been operating at rated core thermal power of 1840 MWt. The existing Direct Torus Venting System (DTVS) is the main system used for venting the containment during the extended station blackout event. The purpose of this paper is to study the effects of the DTVS venting on the response of the containment pressure and temperature. The reactor is depressurized by manually opening the safety relief valves (SRVs) during the SBO, which causes the mass and energy to be discharged into and heat up the suppression pool. The RETRAN model is used to calculate the Nuclear Steam Supply System (NSSS) response and generate the SRV blowdown conditions, including SRV pressure, enthalpy, and mass flow rate. These conditions are then used as the time-dependent boundary conditions for the GOTHIC code to calculate the containment pressure and temperature response. The DTVS model is established in the GOTHIC model based on the venting size, venting piping loss, venting initiation time, and venting source. The lumped volume model, 1-D coarse-mesh model, and 3-D coarse-mesh model are considered in the torus volume. The calculation is first done without DTVS venting to establish a reference basis. Then a case with DTVS available is performed. Comparison of the two cases shows that the existing DTVS design is effective in mitigating the severity of the containment pressure and temperature transients. The results also show that the 1-D coarse-mesh model may not be appropriate since a

  16. Development of an Input Model to MELCOR 1.8.5 for the Oskarshamn 3 BWR

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, Lars [Lentek, Nykoeping (Sweden)

    2006-05-15

    An input model has been prepared to the code MELCOR 1.8.5 for the Swedish Oskarshamn 3 Boiling Water Reactor (O3). This report describes the modelling work and the various files which comprise the input deck. Input data are mainly based on original drawings and system descriptions made available by courtesy of OKG AB. Comparison and check of some primary system data were made against an O3 input file to the SCDAP/RELAP5 code that was used in the SARA project. Useful information was also obtained from the FSAR (Final Safety Analysis Report) for O3 and the SKI report '2003 Stoerningshandboken BWR'. The input models the O3 reactor at its current state with the operating power of 3300 MW{sub th}. One aim with this work is that the MELCOR input could also be used for power upgrading studies. All fuel assemblies are thus assumed to consist of the new Westinghouse-Atom's SVEA-96 Optima2 fuel. MELCOR is a severe accident code developed by Sandia National Laboratory under contract from the U.S. Nuclear Regulatory Commission (NRC). MELCOR is a successor to STCP (Source Term Code Package) and has thus a long evolutionary history. The input described here is adapted to the latest version 1.8.5 available when the work began. It was released the year 2000, but a new version 1.8.6 was distributed recently. Conversion to the new version is recommended. (During the writing of this report still another code version, MELCOR 2.0, has been announced to be released within short.) In version 1.8.5 there is an option to describe the accident progression in the lower plenum and the melt-through of the reactor vessel bottom in more detail by use of the Bottom Head (BH) package developed by Oak Ridge National Laboratory especially for BWRs. This is in addition to the ordinary MELCOR COR package. Since problems arose running with the BH input two versions of the O3 input deck were produced, a NONBH and a BH deck. The BH package is no longer a separate package in the new 1

  17. CLARIFICACIÓN DE AGUAS USANDO COAGULANTES POLIMERIZADOS: CASO DEL HIDROXICLORURO DE ALUMINIO

    Directory of Open Access Journals (Sweden)

    JUAN MIGUEL COGOLLO FLÓREZ

    2011-01-01

    Full Text Available En este artículo se realiza un estudio del proceso de clarificación en sistemas de tratamiento de aguas industriales usando un coagulante inorgánico polimerizado (hidroxicloruro de aluminio. Inicialmente, se establecen los elementos conceptuales más importantes de las etapas del proceso de clarificación (coagulación, floculación y sedimentación. Luego, se señalan los principales coagulantes convencionales utilizados en el tratamiento de aguas y se abordan los policloruros de aluminio (PAC´s como integrantes de una nueva generación de coagulantes alternativos cuyo uso se ha incrementado en las últimas décadas dado su mejor desempeño respecto a los coagulantes convencionales; se especifican los aspectos técnicos y operativos que se deben considerar al momento de implementar un proceso de clarificación de aguas usando un PAC como coagulante. Finalmente, se presentan datos comparativos de condiciones operacionales reales de un proceso de clarificación de aguas, producto de un trabajo previo, donde se remplazó un coagulante convencional (sulfato de aluminio por hidroxicloruro de aluminio, donde se corrobora el mejor desempeño del proceso luego del remplazo.

  18. ALGORITMOS PARA O PROBLEMA NÃO CAPACITADO DE FLUXOS COM CUSTOS FIXOS NOS ARCOS: UMA COMPARAÇÃO ESTATÍSTICA

    Directory of Open Access Journals (Sweden)

    Frederico R.B. Cruz

    2001-07-01

    Full Text Available Este trabalho tem como propósito a apresentação de resultados de uma comparação empírica entre algoritmos, sendo este um dos assuntos mais recorrentes na área de desenvolvimento de algoritmos. Os algoritmos sob estudo são para resolver um problema de otimização em redes, importante pelas suas aplicações potenciais em sistemas de telefonia e transporte, o problema não capacitado de fluxos com custos fixos nos arcos (NCFCF, uma generalização do clássico problema de Steiner em grafos. Para tal, são utilizadas ferramentas estatísticas conhecidas tais como planejamento de experimentos, análise de variância e intervalos de confiança, mas não comumente empregadas neste tipo de estudo. O problema NCFCF é apresentado em uma modelagem de programação matemática inteira mista, baseada na qual os algoritmos sob consideração são apresentados. Uma descrição do planejamento de experimentos adequado a este tipo de estudo é apresentada e é ilustrado o uso da técnica estatística baseado em cuja análise foi possível classificar os algoritmos sob consideração.This paper is concerned about empirical comparisons of algorithms, one of the most recurrent issues in the field of design of algorithms. The problem under consideration is the uncapacitated fixed-charge network flow (UFCNF problem, a generalization of the classic Steiner problem in graphs. The UFCNF is very important in the practical point of view because of its potential applications for telecommunication and transportation system design. In order to compare the algorithms for the UFCNF problem, we make use of well known and well established statistical tools namely the design of experiments, analysis of variance, and confidence intervals, but rarely applied in such studies. A mixed-integer mathematical programming formulation is presented for the UFCNF problem and the design of experiments suitable for the empirical study is detailed. Finally, the statistical analysis

  19. 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.

  20. Simulations of ex-vessel fuel coolant interactions in a Nordic BWR using MC3D code

    Energy Technology Data Exchange (ETDEWEB)

    Thakre, S.; Ma, W. [Royal Institute of Technology, KTH. Div. of Nuclear Power Safety, Stockholm (Sweden)

    2013-08-15

    Nordic Boiling Water Reactors (BWRs) employ a drywell cavity flooding technique as a nuclear severe accident management strategy. In case of core melt accident where the reactor pressure vessel will fail and the melt will eject from the lower head and fall into a water pool, may be in the form of a continuous jet. It is assumed that the melt jet will fragment, quench and form a coolable debris bed into the water pool. The melt interaction with a water pool may cause an energetic steam explosion which creates a potential risk towards the integrity of containment, leading to fission products release into the atmosphere. The results of the APRI-7 project suggest that the significant damage to containment structures by steam explosion cannot be ruled according to the state-of-the-art knowledge about corresponding accident scenario. In the follow-up project APRI-8 (2012-2016) one of the goals of the KTH research is to resolve the steam explosion energetics (SEE) issue, developing a risk-oriented framework for quantifying conditional threats to containment integrity for a Nordic type BWR. The present study deals with the premixing and explosion phase calculations of a Nordic BWR dry cavity, using MC3D, a multiphase CFD code for fuel coolant interactions. The main goal of the study is the assessment of pressure buildup in the cavity and the impact loading on the side walls. The conditions for the calculations are used from the SERENA-II BWR case exercise. The other objective was to do the sensitivity analysis of the parameters in modeling of fuel coolant interactions, which can help to reduce uncertainty in assessment of steam explosion energetics. The results show that the amount of liquid melt droplets in the water (region of void<0.6) is maximum even before reaching the jet at the bottom. In the explosion phase, maximum pressure is attained at the bottom and the maximum impulse on the wall is at the bottom of the wall. The analysis is carried out using two different

  1. PSI contribution to the CASTOC round robin on EAC of low-alloy RPV steels under BWR conditions

    Energy Technology Data Exchange (ETDEWEB)

    Seifert, H.P.; Ritter, S

    2001-08-01

    Within the CASTOC-project (5th EU FW programme), the environmentally-assisted crack growth (EAC) behaviour of low-alloy reactor pressure vessel (RPV) steels is experimentally investigated under simulated transient and steady-state BWR power operation conditions by 6 European laboratories. The present report contains a summary of the PSI contribution to the Working Package 1 (WP1) of this project. WP1 is an interlaboratory round robin EAC test in simulated BWR/NWC environment under cyclic and static loading conditions. The round robin shall demonstrate the applicability of the used advanced test technique and establishes the technical basis for the decision of test conditions in the other working packages. In the first part of the report, the PSI testing facility/measurement instruments and the applied test and evaluation procedure are discussed in detail. In the second part, the exact test conditions and test results with detailed post-test fractographical evaluation in the SEM are presented. The test results are compared with other PSI results, literature data and nuclear codes. Stable and stationary test conditions within the specified range could be achieved in the PSI test during the whole conditioning and experimental phase. The cyclic crack growth rate results agree well with recent PSI results at a higher dissolved oxygen content of 8 ppm and are slightly below the 'high-sulphur line' of the PLEDGE-model. The crack growth rates are significantly above the ASME XI 'wet' curve. Compared to fatigue crack growth rates in air under otherwise identical test conditions, the effect of the high-temperature water environment resulted in an acceleration of crack growth by a factor of 150-250 under these low-cyclic loading conditions. The test results at constant load confirm the extremely low susceptibility to SCC crack growth under static load at 288 {sup o}C observed in tests at MPA, PSI and in a European Round Robin. They agree well with the RPV

  2. Estimation of the coolant flow through a natural circulation BWR fuel channel applying and equivalent electrical model

    Energy Technology Data Exchange (ETDEWEB)

    Valle H, J.; Morales S, J. B. [UNAM, DEPFI, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, Campus Morelos en IMTA, Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: julfi_ig@yahoo.com.m [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco No. 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)

    2010-10-15

    This work presents the design and implementation of an advanced controller for a reduced order model of a BWR reactor core cooled by natural circulating water, which allows real time estimates of coolant flows through fuel assemblies about standard neutron flux strings. Nuclear power plants with boiling water reactors control individual fuel assembly coolant flows by forced circulation using external or internal water pumps and different core support plate orifices. These two elements reduce flow dependency on local channel pressure drops. In BWR reactors using only natural circulation coolant flows, these two elements are not available and therefore individual channel coolant flows are highly dependent in local conditions, such as power distributions and local pressure drops. Therefore it is expected that grater uncertainties in these variables be used during safety, fuel management and other analysis, which in turns may lead to increased operation penalties, such as tighter operating limits. The objective of this work is to asses by computer simulations means to reduce uncertainties in the measurement of fuel assembly coolant flows and eventually the associated penalties. During coolant phase transitions, pressure drops and local power may alter local natural circulation through fuel assemblies and flow estimates can be helped or not by control rod moves. This work presents the construction of an optimal controller for a core flow estimator based on a reduced order model of the coolant going though the reactor vessel components and nuclear core. This model is to be driven by plant signals from standard BWR instrumentation in order to estimate the coolant flows in selected fuel assemblies about a LPRM string. For this purpose an equivalent electrical model has been mathematically developed and numerically tested. The power-flow maps of typical BRW are used as steady state references for this equivalent model. Once these were fully reproduced for steady state

  3. MCTP, a code for the thermo-mechanical analysis of a fuel rod of BWR type reactors (Neutron part); MCTP, un codigo para el analisis termo-mecanico de una barra combustible de reactores tipo BWR (Parte Neutronica)

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez L, H.; Ortiz V, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: hhl@nuclear.inin.mx

    2003-07-01

    In the National Institute of Nuclear Research of Mexico a code for the thermo-mechanical analysis of the fuel rods of the BWR type reactors of the Nucleo electric Central of Laguna Verde is developed. The code solves the diffusion equation in cylindrical coordinates with several energy groups. The code, likewise, calculates the temperature distribution and power distribution in those fuel rods. The code is denominated Multi groups With Temperatures and Power (MCTP). In the code, the energy with which the fission neutrons are emitted it is divided in six groups. They are also considered the produced perturbations by the changes in the temperatures of the materials that constitute the fuel rods, the content of fission products, the uranium consumption and in its case the gadolinium, as well as the plutonium production. In this work there are present preliminary results obtained with the code, using data of operation of the Nucleo electric Central of Laguna Verde. (Author)

  4. BUTREN-RC an hybrid system for the recharges optimization of nuclear fuels in a BWR; BUTREN-RC un sistema hibrido para la optimizacion de recargas de combustible nuclear en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz S, J.J.; Castillo M, J.A. [ININ, Carretera Mexico-Toluca Km. 36.5, 52045 Estado de Mexico (Mexico); Valle G, E. del [IPN, ESFM, 07738 Mexico D.F. (Mexico)

    2004-07-01

    The obtained results with the hybrid system BUTREN-RC are presented that obtains recharges of nuclear fuel for a BWR type reactor. The system has implemented the methods of optimization heuristic taboo search and neural networks. The optimization it carried out with the technique of taboo search, and the neural networks, previously trained, were used to predict the behavior of the recharges of fuel, in substitution of commercial codes of reactor simulation. The obtained recharges of nuclear fuel correspond to 5 different operation cycles of the Laguna Verde Nuclear Power plant, Veracruz in Mexico. The obtained results were compared with the designs of this cycles. The energy gain with the recharges of fuel proposals is of approximately 4.5% with respect to those of design. The time of compute consumed it was considerably smaller that when a commercial code for reactor simulation is used. (Author)

  5. Recent trends in the mitigation of the IGSCC through modifications in the water chemistry of BWR reactors; Tendencias recientes en la mitigacion del IGSCC mediante modificaciones en la quimica del agua de reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Diaz S, A.; Robles, E.F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    During the last years, the Nuclear Power stations had been that to adequate or to modify the parameters and operational conditions, attempting to maintain and to safeguard the integrity and functionality of its components and systems, as well as the personnel safety involved in its operation. In a Boiling water reactor (BWR), the chemical control of the water, constitutes one of the fundamental aspects to get a sure and reliable operation, having as main objectives: (a) The protection of the reactor vessel, of the structural materials of the same one and of the pipes and components of those recirculation systems against the Intergranular stress corrosion phenomena (IGSCC); (b) To guarantee the integrity of the nuclear fuel minimizing the corrosion phenomena in the fuel elements; and (c) The reduction of the operational dose of the personnel involved directly in the operation and maintenance by means of the control of the activated corrosion products. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

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

  7. BWR simulation in a stationary state for the evaluation of fuel cell design; Simulacion de un reactor BWR en estado estacionario para la evaluacion del diseno de celdas de combustible

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

    In this paper the simulation of a BWR in order to evaluate the performance of a set of fuel assemblies under stationary state in three dimensions (3-D) is presented. 15 cases selected from a database containing a total of 18225 cases are evaluated. The main selection criteria were based on the results of the design phase of the power cells in two dimensions (2-D) and 3-D initial study. In 2-D studies the parameters that were used to qualify and select the designs were basically the local power peaking factor and neutron multiplication factor of each fuel cell. In the initial 3-D study variables that defined the quality of results, and from which the selection was realized, are the margins to thermal limits of reactor operation and the value of the effective multiplication factor at the end of cycle operation. From the 2-D and 3-D results of the studies described a second 3-D study was realized, where the optimizations of the fuel reload pattern was carried out. The results presented in this paper correspond to this second 3-D study. It was found that the designs of the fuel cell they had a similar behavior to those provided by the fuel supplier of reference BWR. Particularly it noted the impact of reload pattern on the cold shut down margin. An estimate of the operation costs of reference cycle analyzed with each one designed reload batch was also performed. As a result a positive difference (gain) up to 10,347 M/US D was found. (Author)

  8. Evaluation of the radial design of fuel cells in an operation cycle of a BWR reactor; Evaluacion del diseno radial de celdas de combustible en un ciclo de operacion de un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez C, J.; Martin del Campo M, C. [Laboratorio de Analisis en Ingenieria de Reactores Nucleares, Facultad de Ingenieria, UNAM, Paseo Cuauhnahuac 8532, Jiutepec, Morelos (Mexico)]. e-mail: jgco@ver.megared.net.mx

    2003-07-01

    This work is continuation of one previous in the one that the application of the optimization technique called Tabu search to the radial design of fuel cells of boiling water reactors (BWR, Boiling Water Reactor) is presented. The objective function used in the optimization process only include neutron parameters (k-infinite and peak of radial power) considering the cell at infinite media. It was obtained to reduce the cell average enrichment completing the characteristics of reactivity of an original cell. The objective of the present work is to validate the objective function that was used for the radial design of the fuel cell (test cell), analyzing the operation of a one cycle of the reactor in which fuels have been fresh recharged that contain an axial area with the nuclear database of the cell designed instead of the original cell. For it is simulated it with Cm-Presto the cycle 10 of the reactor operation of the Unit 1 of the Nuclear Power station of Laguna Verde (U1-CNLV). For the cycle evaluation its were applied so much the simulation with the Haling strategy, as the simulation of the one cycle with control rod patterns and they were evaluated the energy generation and several power limits and reactivity that are used as design parameters in fuel reloads of BWR reactors. The results at level of an operation cycle of the reactor, show that the objective function used in the optimization and radial design of the cell is adequate and that it can induce to one good use of the fuel. (Author)

  9. Calibração do Storm Water Management Model (SWMM utilizando algoritmos evolucionários multiobjetivo

    Directory of Open Access Journals (Sweden)

    Klebber Teodomiro Martins Formiga

    Full Text Available RESUMO O estudo teve por objetivo a realização da calibração do modelo hidrológico Storm Water Management Model (SWMM para a Bacia Hidrográfica do Arroio Cancela, localizada em Santa Maria, Rio Grande do Sul, utilizando o algoritmo evolucionário multiobjetivo R-NSGA. Para tanto, foram realizadas modificações na estrutura do SWMM, de modo que permitisse seu acoplamento como Evolucionary Reference Point Based Non-Dominated Sorting Genetic Algorithm (R-NSGA em ambiente de programação MATLAB. As funções objetivo utilizadas foram o Coeficiente de Eficiência de Nash-Sutcliffe (COE, o Erro da Vazão de Pico (EQP e o Erro do Volume Escoado (EVOL aplicadas simultaneamente na calibração do modelo. Foi proposto um método para determinação da maior compatibilidade de modo a elencar as melhores soluções. Os resultados dos parâmetros calibrados do SWMM foram próximos aos valores físicos da bacia, com exceção dos valores relativos à equação de Horton. As soluções de maior compatibilidade apresentam um melhor comportamento para os eventos de validação, evidenciando a importância da otimização multiobjetivo.

  10. 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.

  11. Connected analysis nuclear-thermo-hydraulic of parallel channels of a BWR reactor using distributed computation; Analisis acoplado nuclear-termohidraulico de canales paralelos de un reactor BWR empleando computacion distribuida

    Energy Technology Data Exchange (ETDEWEB)

    Campos Gonzalez, Rina Margarita

    2007-07-15

    This work consists of the integration of three models previously developed which are described widely in Literature: model of the thermo-hydraulic channel, model of the modal neutronic and the model of the recirculation bows. The tool used for this connection of models is the PVM system, Parallel Virtual Machine that allowed paralleling the model by means of the concept of distributed computation. The purpose of making this connection of models is the one of obtaining a more complete tool than better represents the real configuration and the phenomenology of the nucleus of a BWR reactor, thus obtaining better results. In addition to maintaining the flexibility to improve the resulting model at any time, since the very complex or sophisticated models are difficult to improve being impossible to modify the equations they use and can include variables that are not of primary importance in the tackled problem or that mask relations among variables due to the excess of results. Also maintaining the flexibility for adding component of models or systems of the BWR reactor, all of this following the modeling needs. The Swedish Ringhals power plant was chosen to characterize the resulting connected model for counting on a Stability Benchmark that offers the opportunity to count on real plant data. Besides that in case 9 of cycle 14 of this Benchamark oscillations outside phase appeared, which are from great interest because the detection systems that register the average of the power of the nucleus do not detect them. Additionally in this work the model of the recirculation bows as an independent module is obtained in an individual way, since this model belongs to another work and works connected to the reactor vessel. The model of the recirculation bows is able to model several transients of interest, as it is shown in the Appendix A of this work, among which are found the tripping of recirculation pumps or the transference at low or high velocity of them. The scope of the

  12. Trace Code Validation for BWR Spray Cooling Injection and CCFL Condition Based on GÖTA Facility Experiments

    Directory of Open Access Journals (Sweden)

    Stefano Racca

    2012-01-01

    Full Text Available Best estimate codes have been used in the past thirty years for the design, licensing, and safety of NPP. Nevertheless, large efforts are necessary for the qualification and the assessment of such codes. The aim of this work is to study the main phenomena involved in the emergency spray cooling injection in a Swedish-designed BWR. For this purpose, data from the Swedish separate effect test facility GÖTA have been simulated using TRACE version 5.0 Patch 2. Furthermore, uncertainty calculations have been performed with the propagation of input errors method, and the identification of the input parameters that mostly influence the peak cladding temperature has been performed.

  13. Calculation of releases of radioactive materials in gaseous and liquid effluents from boiling water reactors (BWR-GALE Code)

    Energy Technology Data Exchange (ETDEWEB)

    Bangart, R.L.; Bell, L.G.; Boegli, J.S.; Burke, W.C.; Lee, J.Y.; Minns, J.L.; Stoddart, P.G.; Weller, R.A.; Collins, J.T.

    1978-12-01

    The calculational procedures described in the report reflect current NRC staff practice. The methods described will be used in the evaluation of applications for construction permits and operating licenses docketed after January 1, 1979, until this NUREG is revised as a result of additional staff review. The BWR-GALE (Boiling Water Reactor Gaseous and Liquid Effluents) Code is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from boiling water reactors (BWRs). The calculations are based on data generated from operating reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials that may be released to the environment.

  14. Safety and licensing issues that are being addressed by the Power Burst Facility test programs. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    McCardell, R.K.; MacDonald, P.E.

    1980-01-01

    This paper presents an overview of the results of the experimental program being conducted in the Power Burst Facility and the relationship of these results to certain safety and licensing issues. The safety issues that were addressed by the Power-Cooling-Mismatch, Reactivity Initiated Accident, and Loss of Coolant Accident tests, which comprised the original test program in the Power Burst Facility, are discussed. The resolution of these safety issues based on the results of the thirty-six tests performed to date, is presented. The future resolution of safety issues identified in the new Power Burst Facility test program which consists of tests which simulate BWR and PWR operational transients, anticipated transients without scram, and severe fuel damage accidents, is described.

  15. Fuel radial design using Path Relinking; Diseno radial de combustible usando Path Relinking

    Energy Technology Data Exchange (ETDEWEB)

    Campos S, Y. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)

    2007-07-01

    The present work shows the obtained results when implementing the combinatory optimization technique well-known as Path Re linking (Re-linkage of Trajectories), to the problem of the radial design of nuclear fuel assemblies, for boiling water reactors (BWR Boiling Water Reactor by its initials in English), this type of reactors is those that are used in the Laguna Verde Nucleo electric Central, Veracruz. As in any other electric power generation plant of that make use of some fuel to produce heat and that it needs each certain time (from 12 to 14 months) to make a supply of the same one, because this it wears away or it burns, in the nucleolectric plants to this activity is denominated fuel reload. In this reload different activities intervene, among those which its highlight the radial and axial designs of fuel assemblies, the patterns of control rods and the multi cycles study, each one of these stages with their own complexity. This work was limited to study in independent form the radial design, without considering the other activities. These phases are basic for the fuel reload design and of reactor operation strategies. (Author)

  16. Nueva técnica de monitoreo sobre la dispersión en las señales de radio-sobre-fibra en la banda W usando clustering en histogramas asíncronos

    Directory of Open Access Journals (Sweden)

    Jhon James Granada Torres

    2014-11-01

    Full Text Available Los sistemas de Radio sobre Fibra (RoF, se proponen como una solución prometedora para transmitir señales de radiofrecuencia a altas tasas de transmisión y sobre largas distancias. Algunos estudios proponen el uso de frecuencias portadoras en la banda W (75 - 110 GHz, para lograr transmisiones en el rango de los Gbps. Sin embargo, en este rango de frecuencias la dispersión cromática, se convierte en uno de los principales factores para el incremento de la tasa de error del bit.Este artículo presenta un nuevo método de monitoreo de la dispersión, basado en histogramas asíncronos para sistemas de RoF. El método planteado cuantifica el nivel de distorsión de la señal de radiofrecuencia, mediante un valor adimensional llamado: factor de dispersión. Dicho factor, se calcula mediante una técnica de agrupamiento, la cual se lleva a cabo usando ajustamiento gaus-siano, mediante el algoritmo de máxima esperanza sobre histogramas asíncronos. El monitoreo de la dispersión se realiza sobre una plataforma de simulación, donde se transmiten las señales de radiofrecuencia, empleando modulación No retorno a cero (NRZ y modulación binaria con desplazamiento de fase (BPSK, sobre 80 km de fibra óptica a 60, 75 y 100 GHz. Así, se estima la tasa de error de bit y se compara con el factor de dispersión; dónde se evidencia que los efectos de la dispersión no son proporcionales al incre-mento en la frecuencia de la portadora, la velocidad de transmisión y la distancia. El novedoso método de monitoreo, puede ser usado para estimar la viabilidad de los futuros sistemas de telecomunicaciones híbridos, basados en redes de fibra y bajo ciertos parámetros de transmisión tales como: la distancia, el formato de modulación y la frecuencia de la portadora.

  17. Solución a un problema estático en un área con topografía abrupta usando una velocidad de reemplazamiento variable

    Directory of Open Access Journals (Sweden)

    Castillo López Luis Antonio

    2002-08-01

    información de las áreas con variaciones severas de topografía en Colombia. En el caso del área del piedemonte llanero, usando el paquete interactivo ProMAX, algoritmo Gauss-Seidel.

  18. Distribución de espacios en plantas industriales usando búsqueda tabú

    Directory of Open Access Journals (Sweden)

    CARLOS ANDRÉS DOMÍNGUEZ GUAL

    2005-01-01

    Full Text Available En el problema de la distribución de espacios en plantas industriales se pretende ubicar de forma óptima los departamentos de acuerdo con sus necesidades. Este es un problema complejo de optimización combinatoria debido al gran número de distribuciones posibles, y para cuya solución han sido propuestos varios algoritmos heurísticos; no obstante, dichas técnicas de solución exploran parcialmente y de forma limitada el espacio de posibles combinaciones. Como una alternativa de solución a este problema, se presente una adaptación del método de Búsqueda Tabú, la cual realiza una exploración heurística de mayor amplitud que los métodos tradicionales. Los resultados obtenidos para los casos de aplicación presentados, indican que la metodología propuesta puede encontrar distribuciones de calidad superior, o al menos igual, a los métodos tradicionales.

  19. Analysis of BWR instabilities coupled with 3D code RELAP5 / PARCSv2.7. Application to the event happened in Oskarshamn-2 in 1999; Analisis de inestabilidades en BWR con el codigo acoplado 3D RELAP5/PARCSv2.7. Aplicacion al evento sucedido en Oskarshamn-2 en1999

    Energy Technology Data Exchange (ETDEWEB)

    Garcia-Fenoll, M.; Barrachina, T.; Miro, R.; Verdu, G.

    2014-07-01

    In this work, part of our works in the frame of the OECD/NEA Oskarshamn-2 (O{sub 2}) BWR Stability Benchmark for Coupled Code Calculations and Uncertainty Analysis in Modelling are shown. The objective is to simulate the instability event registered in February 1999 at the Swedish NPP Oskarshamn-2 with the coupled code RELAP5/PARCSv2.7. (Author)

  20. SÍNTESIS DE OXITOCINA EN FASE SÓLIDA USANDO DERIVADOS DE TERBUTOXICARBONILO Y FLUORENILMETOXICARBONILO

    Directory of Open Access Journals (Sweden)

    Julio C Calvo

    2010-08-01

    Full Text Available La oxitocina, péptido cíclico cuya secuencia es CYIQNCPLG, fué el primer péptido de importancia biológica que pudo ser sintetizado. En este trabajo se compara la síntesis de la oxitocina usando resina p metilbenzhidrilamina (MBHA para la síntesis por estrategia t-Boc y resina Rink p-metilbenzhidrilamina (Rink MBHA para la síntesis por estrategia Fmoc, con altos rendimientos. El péptido crudo se ciclizó en una disolución acuosa de dimetilsulfóxido al 10%. La caracterización se llevó a cabo por espectrometría de masas y resonancia magnética nuclear, y se logró detectar la presencia de dos isómeros.

  1. ENSEÑANZA DE ONDAS MECÁNICAS EN CUERDAS USANDO MATHEMATICA

    OpenAIRE

    Guillermo Iván González Pedreros

    2005-01-01

    Se resuelve la ecuación de onda y se efectúa la simulación de la solución obtenida, usando el programa Mathematica, para el caso de una cuerda elástica tensa con un extremo fijo y el otro libre. Esto se propone como ejemplo para la enseñanza de los fenómenos ondulatorios mecánicos en cursos de física general para estudiantes de ciencias e ingeniería. El ejemplo orienta al estudiante en el análisis crítico mientras aprende conceptos fundamentales de física, además puede ser extendido al caso b...

  2. ENSEÑANZA DE ONDAS MECÁNICAS EN CUERDAS USANDO MATHEMATICA

    OpenAIRE

    Guillermo Iván González Pedreros

    2005-01-01

    Se resuelve la ecuación de onda y se efectúa la simulación de la solución obtenida, usando el programa Mathematica, para el caso de una cuerda elástica tensa con un extremo fijo y el otro libre. Esto se propone como ejemplo para la enseñanza de los fenómenos ondulatorios mecánicos en cursos de física general para estudiantes de ciencias e ingeniería. El ejemplo orienta al estudiante en el análisis crítico mientras aprende conceptos fundamentales de física, además puede ser extendido al caso b...

  3. ENSEÑANZA DE ONDAS MECÁNICAS EN CUERDAS USANDO MATHEMATICA

    Directory of Open Access Journals (Sweden)

    Guillermo Iván González Pedreros

    2005-06-01

    Full Text Available Se resuelve la ecuación de onda y se efectúa la simulación de la solución obtenida, usando el programa Mathematica, para el caso de una cuerda elástica tensa con un extremo fijo y el otro libre. Esto se propone como ejemplo para la enseñanza de los fenómenos ondulatorios mecánicos en cursos de física general para estudiantes de ciencias e ingeniería. El ejemplo orienta al estudiante en el análisis crítico mientras aprende conceptos fundamentales de física, además puede ser extendido al caso bidimensional y constituye una base sólida y adecuada para otros temas como las ondas electromagnéticas y la mecánica.

  4. Avaliação de multielementos em amostras de sangue humano usando SR-TXRF

    OpenAIRE

    Nivia Graciele V. Pinto; Carla L. S. Mota; Regina Cely R. Barroso; Silvana Moreira; Delson Braz

    2010-01-01

    A técnica de fluorescência de raios X por reflexão total usando radiação síncrotron (SR-TXRF) é uma poderosa ferramenta utilizada para a determinação das concentrações elementares presentes em amostras biológicas. O objetivo deste estudo é avaliar as possíveis alterações causadas por processos de irradiação na concentração de elementos-traço em amostras de sangue humano. As amostras de sangue foram coletadas no Laboratório de Análises Clínicas Dr. Elilel Figueiredo, Rio de Janeiro, e dividida...

  5. Controle eletroquimico de acido humico e algas usando um reator com eletrodo de filme de diamante

    OpenAIRE

    Andrea Alexandra Junior

    2007-01-01

    Resumo: A presença de ácidos húmico e o crescimento de algas em água de abastecimento e de piscinas geram subprodutos que são prejudiciais à saúde. Para controlar a concentração de ácidos húmico e algas, este trabalho apresenta um processo de eletro-oxidação usando anodos de diamante dopado com boro (DDB). Neste tratamento, a solução aquosa é percolada através de um reator tipo filtro-prensa, com anodo de DDB polarizado a corrente constante. Para caracterizar a eficiência do tratamento, foram...

  6. Verificación de Firmas Usando Transformada de Gabor Signature Verification using the Gabor Transform

    Directory of Open Access Journals (Sweden)

    C Cruz

    2004-01-01

    Full Text Available Este artículo se propone un sistema de verificación estática de firmas con alta capacidad de detección de falsificaciones. En la etapa de extracción de características se obtienen los coeficientes de la transformada de Gabor en cada región de la firma, extrayéndose la posición del coeficiente sobresaliente de cada región. Estas proporcionan información local acerca de la frecuencia y orientación de la textura de una firma. Usando las características extraídas, el sistema entrena una red neuronal de retropropagación con una arquitectura de 9-9-2 para cada firmante. La eficiencia del sistema propuesto se evaluó usando 30 firmas auténticas y 20 firmas falsificadas por expertos para cada firmante. De los resultados obtenidos por simulación, se concluye que el sistema propuesto presenta una verificación global con 90% de acierto, con una menor complejidad computacionalThis paper proposes an off-line signature verification system with fairly good detection capacity against expert forgeries. The feature extraction stage of the proposed system, estimates the coefficients of the Gabor Transform in each local region of the signature image, and extracts the positions of relevant coefficients. These provide local information about frequency and orientation of the signature image texture. Using the extracted features, the proposed system adapts a back-propagation multiplayer neural network with 9-9-2 architecture for each signer. The proposed system was evaluated using 30 genuine signatures and 20 expert forgeries for each signer. The computer simulation results show a 90% overall success, with a lower computational complexity

  7. BWR spent fuel transport and storage system for KKL: TN trademark 52L, TN trademark 97L, TN trademark 24 BHL

    Energy Technology Data Exchange (ETDEWEB)

    Sicard, D.; Verdier, A. [COGEMA Logistics (AREVA Group) (France); Monsigny, P.A. [NOK/KKL (Switzerland)

    2004-07-01

    The LEIBSTADT (KKL) nuclear power plant in Switzerland has opted to ship spent fuel to a central facility called ZWILAG for interim storage. In the mid-nineties, COGEMA LOGISTICS was contracted by KKL for the supply of the TN trademark a52L and TN trademark 97L transport and storage casks for BWR fuel types. In 2003, KKL also ordered from COGEMA LOGISTICS the supply of six TNae24 BHL transport and storage casks. This paper shows how all the three cask designs have responded to the KKL needs to ship and store BWR spent fuel. In addition, it highlights the already significant operational feedback of the TN trademark 52L and TN trademark 97L casks by the KKL and ZWILAG operators.

  8. Development of Sirius facility that simulates void-reactivity feedback, and regional and core-wide stability estimation of natural circulation BWR

    Energy Technology Data Exchange (ETDEWEB)

    Furuya, M.; Inada, F.; Yasuo, A. [Tokyo Electric Power Co., Inc., Central Research Institute (Japan)

    2001-07-01

    The SIRIUS facility was designed and constructed for highly accurate simulation of core-wide and regional instabilities of the BWR. A real-time simulation was performed in the digital controller for modal point kinetics of reactor neutronics and fuel-rod conduction on the basis of measured void fractions in reactor core sections of the thermal-hydraulic loop. Stability experiments were conducted for a wide range of fluid conditions, power distributions, and fuel rod thermal conductivity time constants, including the normal operating conditions of a typical natural circulation BWR. The results showed that there is a sufficiently wide stability margin under normal operating conditions, even when void-reactivity feedback is taken into account. (author)

  9. Effect of sensitization and cold work on stress corrosion susceptibility of austenitic stainless steels in boiling water reactor (BWR) and pressurized water reactor (PWR) conditions

    Energy Technology Data Exchange (ETDEWEB)

    Haenninen, H.; Aho-Mantila, I.

    1981-05-01

    The influence of metallurgical variables on stress corrosion cracking of austenitic stainless steels, in particular AISI 304 and OX18H10T, was examined in O/sub 2/ enriched BWR conditions (8 ppm O/sub 2/) and in typical PWR conditions. Cracking susceptibility in BWR conditions is especially sensitive to alpha martensite content and sensitization. Cracking in alpha martensite compounds is intergranular and transgranular and it can not be related to sensitization. Sensitization induces cracking only in creviced conditions (double U-bend specimens) in AISI 304 steels. In creviced conditions OX18H10T steel exhibits cracking in solution annealed, stabilized and sensitized conditions. The sensitized material is most susceptible. Cracking in solution annealed and stabilized OX18H10T steel is intergranular and transgranular. In PWR conditions (O/sub 2/ content 2 ppb) no cracking is observed. (ESA)

  10. Preliminary results of a high-resolution refractometer using the Hartmann-Shack wave-front sensor: part I Resultados preliminares com refratrômetro de alta resolução, usando sensor de frente de onda de Hartmann-Shack: parte I

    Directory of Open Access Journals (Sweden)

    Luis Alberto Carvalho

    2003-06-01

    Full Text Available In this project we are developing an instrument for measuring the wave-front aberrations of the human eye using the Hartmann-Shack sensor. A laser source is directed towards the eye and its diffuse reflection at the retina generates an approximately spherical wave-front inside the eye. This wave-front travels through the different components of the eye (vitreous humor, lens, aqueous humor, and cornea and then leaves the eye carrying information about the aberrations caused by these components. Outside the eye there is an optical system composed of an array of microlenses and a CCD camera. The wave-front hits the microlens array and forms a pattern of spots at the CCD plane. Image processing algorithms detect the center of mass of each spot and this information is used to calculate the exact wave-front surface using least squares approximation by Zernike polynomials. We describe here the details of the first phase of this project, i. e., the construction of the first generation of prototype instruments and preliminary results for an artificial eye calibrated with different ametropias, i. e., myopia, hyperopia and astigmatism.Neste projeto estamos desenvolvendo instrumento para medidas das aberrações de frente de onda do olho humano usando um sensor Hartmann-Shack. Uma fonte de luz laser é direcionada ao olho e sua reflexão difusa na retina gera frente de onda aproximadamente esférica dentro do olho. Esta frente de onda atravessa os diferentes componentes do olho (humor vítreo, lente, humor aquoso e córnea trazendo informações sobre as aberrações ópticas causadas por estes componentes. No meio externo ao olho existe sistema óptico formado por uma matriz de microlentes e uma câmera CCD. A frente de onda incide nesta matriz e forma um padrão aproximadamente matricial de "spots" no plano do CCD. Algoritmos de processamento de imagens são utilizados para detectar os centróides de cada "spot" e esta informação é utilizada para

  11. Inferência gramatical usando uma técnica evolutiva = Grammatical inference using an evolutionary technical

    Directory of Open Access Journals (Sweden)

    Sandra Mara Guse Scós Venske

    2011-04-01

    Full Text Available Num processo de inferência, busca-se encontrar uma resposta genéricabaseando-se na análise de uma amostra de fatos. A inferência gramatical visa obter uma gramática para uma determinada linguagem baseada em exemplos de cadeias que pertencem ou não à linguagem analisada. Neste trabalho propõe-se um algoritmo para o uso deinferência em gramáticas livres de contexto baseadas em uma cadeia exemplo não pertencente à linguagem. A técnica evolutiva de algoritmos genéticos foi aplicada no processo com o objetivo de auxiliar na criação das regras de produção para as gramáticas,atendendo às restrições impostas pela cadeia exemplo. Uma aplicação do algoritmo de inferência está relacionada a linguagens que possuem padrões específicos pré-definidos, como é o caso de documentos XML no contexto de esquemas. A eficiência do algoritmo proposto é mostrada através de pequenos testes onde são obtidas gramáticas geneticamentegeradas.Inference process try to find a generic answer based on a sample of facts. This process aims to achieve a grammar for a particular language based in string samples that belong or not belong to thespecific language. In this work we propose an algorithm for context-free grammars inference based in only one sample string that not belongs to the language. The genetic algorithm evolutive technical was applied in order to assist the generation of productionrules for grammars. This process must to validate the sample string restrictions. Inference algorithm proposed can be applied in computer languages that have specific pre-defined standards, like schemas for XML documents. Suitability of the proposed algorithm is shown by small experiments where grammars are genetically obtained and generated.

  12. Detección de daño estructural por algoritmos genéticos: una comparación de diferentes tipos de codificación de individuos

    OpenAIRE

    Jesús Daniel Villalba Morales; José Elías Laier

    2010-01-01

    En este artículo se aplican los algoritmos genéticos para resolver el problema de detección de daño estructural, y se comparan tres tipos de codificación de individuos: binaria, real y binaria con código redundante. Los algoritmos de código binario y real calculan la extensión del daño para cada elemento en la estructura, por lo tanto, para mejorar su desempeño fue utilizado un proceso de re-inicialización de individuos. Por su parte, el algoritmo de código redundante busca en forma dinámica ...

  13. 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 ...

  14. 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.

  15. Automatización del Bobinado Industrial de Fleje Plástico Mediante Motores Eléctricos Basados en Algoritmos de Control de Movimiento

    Directory of Open Access Journals (Sweden)

    Marco Freddy Abril Aguilar

    2016-11-01

    Full Text Available En este artículo se describe el diseño e implementación de un Sistema Eléctrico y Electrónico para automatizar el proceso de bobinado de fleje plástico de polipropileno en la empresa CODIEMPAQUES del ECUADOR Cía. Ltda. , mediante el uso de motores eléctricos de inducción y motores a pasos que permitirán enrollar y posicionar el fleje plástico en un carrete para su posterior almacenamiento y distribución.El proceso de bobinado comprende dos etapas que trabajan simultamenamente para obtener un rollo de fleje plástico uniforme y compacto. La etapa de enrrollado realizada por el motor de inducción trifásico bajo el control del algoritmo de fuerza; la etapa de posicionamiento realizada por el motor a pasos a través de algoritmos de control de movimiento de posición, velocidad y cambio de giro.Los algoritmos son procesados por autómatas de gama alta y reciben señales provenientes de sensores inductivos y encoders incrementales; posteriormente las señales son transferidas mediante red de autómatas MODBUS para su procesamiento. La etapa de implementación se realizó bajo la norma ISO/IEC 24702 para la distribución, maniobra y conexión de los dispositivos optimizando el tiempo y recursos

  16. RAMONA-4B a computer code with three-dimensional neutron kinetics for BWR and SBWR system transient - models and correlations

    Energy Technology Data Exchange (ETDEWEB)

    Rohatgi, U.S.; Cheng, H.S.; Khan, H.J.; Mallen, A.N.; Neymotin, L.Y.

    1998-03-01

    This document describes the major modifications and improvements made to the modeling of the RAMONA-3B/MOD0 code since 1981, when the code description and assessment report was completed. The new version of the code is RAMONA-4B. RAMONA-4B is a systems transient code for application to different versions of Boiling Water Reactors (BWR) such as the current BWR, the Advanced Boiling Water Reactor (ABWR), and the Simplified Boiling Water Reactor (SBWR). This code uses a three-dimensional neutron kinetics model coupled with a multichannel, non-equilibrium, drift-flux, two-phase flow formulation of the thermal hydraulics of the reactor vessel. The code is designed to analyze a wide spectrum of BWR core and system transients and instability issues. Chapter 1 is an overview of the code`s capabilities and limitations; Chapter 2 discusses the neutron kinetics modeling and the implementation of reactivity edits. Chapter 3 is an overview of the heat conduction calculations. Chapter 4 presents modifications to the thermal-hydraulics model of the vessel, recirculation loop, steam separators, boron transport, and SBWR specific components. Chapter 5 describes modeling of the plant control and safety systems. Chapter 6 presents and modeling of Balance of Plant (BOP). Chapter 7 describes the mechanistic containment model in the code. The content of this report is complementary to the RAMONA-3B code description and assessment document. 53 refs., 81 figs., 13 tabs.

  17. Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions - CASTOC, Part I: BWR/NWC conditions

    Energy Technology Data Exchange (ETDEWEB)

    Ritter, S.; Seifert, H.P. [Paul Scherrer Institute, PSI, Villigen (Switzerland); Devrient, B.; Roth, A. [Framatome ANP GmbH, Erlangen (Germany); Ehrnsten, U. [VTT Industrial Systems, Espoo (Finland); Ernestova, M.; Zamboch, M. [Nuclear Research Institute, NRI, Rez (Czech Republic); Foehl, J.; Weissenberg, T. [Staatliche Materialpruefungsanstalt, MPA, Stuttgart (Germany); Gomez-Briceno, D.; Lapena, J. [Centro de Investigaciones Energeticas Medioambientales y Tecnologicas, CIEMAT, Madrid (Spain)

    2004-07-01

    One of the ageing phenomena of pressure boundary components of light water reactors (LWR) is environmentally-assisted cracking (EAC). The project CASTOC (5. Framework Programme of the EU) was launched September 2000 with six European partners and terminated August 2003. It was focused in particular on the EAC behaviour of low-alloy steels (LAS) and to some extent to weld metal, heat affected zone and the influence of an austenitic cladding. The main objective was directed to the clarification of EAC crack growth behaviour/mechanism of LAS in high-temperature water under steady-state power operation (constant load) and transient operating conditions (e.g., start-up/shut-down, transients in water chemistry and load). Autoclave tests were performed with Western and Russian type reactor pressure vessel steels under simulated boiling water reactor (BWR)/normal water chemistry (NWC) and pressurised water reactor (VVER) conditions. The investigations were performed with fracture mechanics specimens of different sizes and geometries. The applied loading comprised cyclic loads, static loads and load spectra where the static load was periodically interrupted by partial unloading. With regard to water chemistry, the oxygen content (VVER) and impurities of sulphate and chlorides (BWR) were varied beyond allowable limits for continuous operation. The current paper summarises the most important crack growth results obtained under simulated BWR/NWC conditions. The results are discussed in the context of the current crack growth rate curves in the corresponding nuclear codes. (authors)

  18. RAMONA-4B a computer code with three-dimensional neutron kinetics for BWR and SBWR system transient - models and correlations

    Energy Technology Data Exchange (ETDEWEB)

    Rohatgi, U.S.; Cheng, H.S.; Khan, H.J.; Mallen, A.N.; Neymotin, L.Y.

    1998-03-01

    This document describes the major modifications and improvements made to the modeling of the RAMONA-3B/MOD0 code since 1981, when the code description and assessment report was completed. The new version of the code is RAMONA-4B. RAMONA-4B is a systems transient code for application to different versions of Boiling Water Reactors (BWR) such as the current BWR, the Advanced Boiling Water Reactor (ABWR), and the Simplified Boiling Water Reactor (SBWR). This code uses a three-dimensional neutron kinetics model coupled with a multichannel, non-equilibrium, drift-flux, two-phase flow formulation of the thermal hydraulics of the reactor vessel. The code is designed to analyze a wide spectrum of BWR core and system transients and instability issues. Chapter 1 is an overview of the code`s capabilities and limitations; Chapter 2 discusses the neutron kinetics modeling and the implementation of reactivity edits. Chapter 3 is an overview of the heat conduction calculations. Chapter 4 presents modifications to the thermal-hydraulics model of the vessel, recirculation loop, steam separators, boron transport, and SBWR specific components. Chapter 5 describes modeling of the plant control and safety systems. Chapter 6 presents and modeling of Balance of Plant (BOP). Chapter 7 describes the mechanistic containment model in the code. The content of this report is complementary to the RAMONA-3B code description and assessment document. 53 refs., 81 figs., 13 tabs.

  19. Development and Assessment of CFD Models Including a Supplemental Program Code for Analyzing Buoyancy-Driven Flows Through BWR Fuel Assemblies in SFP Complete LOCA Scenarios

    Science.gov (United States)

    Artnak, Edward Joseph, III

    This work seeks to illustrate the potential benefits afforded by implementing aspects of fluid dynamics, especially the latest computational fluid dynamics (CFD) modeling approach, through numerical experimentation and the traditional discipline of physical experimentation to improve the calibration of the severe reactor accident analysis code, MELCOR, in one of several spent fuel pool (SFP) complete loss-ofcoolant accident (LOCA) scenarios. While the scope of experimental work performed by Sandia National Laboratories (SNL) extends well beyond that which is reasonably addressed by our allotted resources and computational time in accordance with initial project allocations to complete the report, these simulated case trials produced a significant array of supplementary high-fidelity solutions and hydraulic flow-field data in support of SNL research objectives. Results contained herein show FLUENT CFD model representations of a 9x9 BWR fuel assembly in conditions corresponding to a complete loss-of-coolant accident scenario. In addition to the CFD model developments, a MATLAB based controlvolume model was constructed to independently assess the 9x9 BWR fuel assembly under similar accident scenarios. The data produced from this work show that FLUENT CFD models are capable of resolving complex flow fields within a BWR fuel assembly in the realm of buoyancy-induced mass flow rates and that characteristic hydraulic parameters from such CFD simulations (or physical experiments) are reasonably employed in corresponding constitutive correlations for developing simplified numerical models of comparable solution accuracy.

  20. Una combinación de un algoritmo voraz con algoritmos genéticos para optimizar la producción de cartón ondulado || A Combination of a Greedy Algorithm and Genetics Algorithms to Optimize the Production of Corrugated Board

    Directory of Open Access Journals (Sweden)

    Tornadijo Rodríguez, Tomás F.

    2009-01-01

    Full Text Available En este trabajo se propone la utilización de un algoritmo genético para la optimización del corte continuo de planchas de cartón, un problema habitual en la industria cartonera, donde la minimización de mermas de materia prima y el cumplimiento de los plazos de fabricación son dos objetivos prioritarios de la planificación de la producción. Las soluciones aportadas por un algoritmo voraz se utilizan como semillas para el algoritmo genético. Se utiliza el operador de recombinación de cruce en un punto. || In this paper, we suggest a genetic algorithm for optimizing the continuous cutting of cardboard plates, a common problem in the corrugated industry,where minimizing wastage of raw materials and meeting production deadlines are two priority objectives of production planning.The solutions provided by a greedy algorithm are used as seeds for thegenetic algorithm. It uses the one-point crossover operator.

  1. 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.

  2. Algunos algoritmos para filtros digitales en el procesamiento de información electromagnética

    Directory of Open Access Journals (Sweden)

    Díaz C. Ramiro

    2000-08-01

    Full Text Available EI proceso de análisis de señales en prospección electromagnética, ha sido trabajado desde diferentes puntos de vista y varios autores han planteado diferentes metodologías. EI objeto de este artículo es plantear algunos algoritmos para filtros digitales basados en el análisis de Fourier. En el trabajo se muestran las facilidades del uso del dominio de la frecuencia en el análisis de señales en prospeccion electromagnética.

    The signal processing in electromagnetic prospecting have been worked from several points of view and several authors there is expounding several methodologies. The object of this paper is to expound some algorithms for digital filters based on the Analysis of Fourier. In the work the facilities of the use of the

    frequency domain in the signal processing are shown.

  3. 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...

  4. Desarrollo de un algoritmo de aprendizaje de máquina para gravimetría, nivelación geométrica y alturas elipsoidales

    OpenAIRE

    Arias Patiño, Miguel Fernando

    2014-01-01

    Esta investigación tiene por objetivo el modelamiento de la interacción de datos gravimétricos, nivelación geométrica y posicionamiento GPS, a través de un modelo de aprendizaje de máquina, para estimar con cierto grado de precisión alturas niveladas mediante la implementación de algoritmos que relacionan datos de entrada, por medio de un proceso de transformación, donde se obtiene una variable dependiente en función de las relaciones intrínsecas entre las variables explicativa...

  5. Caracterización y reconocimiento de objetos mediante algoritmos de visión computacional para la interacción de un robot con su entorno

    OpenAIRE

    Robles Pizarro, Luis David

    2016-01-01

    En el campo de la robótica, se han desarrollado distintos algoritmos y métodos con el objetivo de mejorar la interacción de los robots con las personas y con su entorno de trabajo en tiempo real; es así, como el sistema reacciona y evoluciona constantemente ante cambios que podrían ocurrir durante su funcionamiento. Para alcanzar los objetivos mencionados, una de las habilidades que se le confiere a la máquina es la capacidad de detectar, registrar y reconocer objetos. La pr...

  6. Algoritmo para la simulación de la visión de un daltónico: presentación del proyecto

    OpenAIRE

    Acevedo Noda, Pablo; Fez Saiz, Dolores de; García Llopis, Celia

    2011-01-01

    Presentación del proyecto: Algoritmo para la simulación de la visión de un daltónico. Despertarse cada día y abrir los ojos produce una avalancha de información que llega hasta nuestro cerebro para ser interpretada. Tras muchos siglos de evolución nuestro sistema visual se ha ido adaptando al entorno que nos rodea. Es fácil imaginar las ventajas que esto nos proporciona. Distinguir el camuflaje de algunos animales y frustrar así sus intentos de pasar inadvertidos o diferenciar un fruto ven...

  7. 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.

  8. 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.

  9. Incorporación de la dinámica grupal en la materia resolución de problemas y algoritmos

    OpenAIRE

    2004-01-01

    Siguiendo nuestra línea de investigación que apunta al desarrollo de plataformas de educación a distancia y teniendo como meta el dictado del Profesorado en Informática para Enseñanza Media a distancia, hemos trabajado en diversas herramientas y propuestas metodológicas que utilizan la Dinámica Grupal y que tienden a mejorar el proceso de enseñanzaaprendizaje de la s materias de dicha carrera. Tomamos como punto de partida la materia Resolución de Problemas y Algoritmos y desarrollamos una...

  10. Inferência gramatical usando uma técnica evolutiva - doi: 10.4025/actascitechnol.v33i2.4799

    Directory of Open Access Journals (Sweden)

    Sandra Mara Guse Scós Venske

    2011-04-01

    Full Text Available Num processo de inferência, busca-se encontrar uma resposta genérica baseando-se na análise de uma amostra de fatos. A inferência gramatical visa obter uma gramática para uma determinada linguagem baseada em exemplos de cadeias que pertencem ou não à linguagem analisada. Neste trabalho propõe-se um algoritmo para o uso de inferência em gramáticas livres de contexto baseadas em uma cadeia exemplo não pertencente à linguagem. A técnica evolutiva de algoritmos genéticos foi aplicada no processo com o objetivo de auxiliar na criação das regras de produção para as gramáticas, atendendo às restrições impostas pela cadeia exemplo. Uma aplicação do algoritmo de inferência está relacionada a linguagens que possuem padrões específicos pré-definidos, como é o caso de documentos XML no contexto de esquemas. A eficiência do algoritmo proposto é mostrada através de pequenos testes onde são obtidas gramáticas geneticamente geradas.

  11. Sistema de razonamiento inductivo basado en algoritmos genéticos para la solución de problemas en condiciones de información imprecisa. Parte I

    OpenAIRE

    Ferrer Rodríguez, Julio Gustavo

    2010-01-01

    El proyecto de investigación “Sistema de razonamiento inductivo basado en algoritmos genéticos para la solución de problemas en condiciones de información imprecisa” permitió obtener los siguientes resultados: la caracterización de los estudiantes de la Facultad de Ingeniería, de la Universidad Cooperativa de Colombia, en relación con el razonamiento inductivo, y la construcción de un prototipo de software utilizando los conceptos de sistemas basados en conocimiento y algoritmos genéticos. Es...

  12. Fusión de algoritmos bayesianos y árboles de clasificación como propuesta para la clasificación supervisada de fallos de equipos en un laboratorio de cómputos

    OpenAIRE

    Corso, Cynthia Lorena; Maldonado, Calixto; Pereyra, Florencia; Martínez, Gimena; Donnet, Matías

    2017-01-01

    Los algoritmos basados en redes bayesianas y árboles de decisión representan métodos que han resultado eficientes para la resolución de problemas de clasificación. Este trabajo pretende combinar estos algoritmos con el objetivo de obtener un modelo híbrido que permita aprovechar y combinar las ventajas de ambos. Con esta estrategia se pretende aumentar la precisión en los resultados de la clasificación supervisada. Este trabajo pretende detallar cual es el grado de precisión en la exactitud, ...

  13. Adaptación del tamaño de la población en los algoritmos genéticos / Adaptation of population size in genetic algorithms

    OpenAIRE

    Cantor Monroy, Giovanni Antonio

    2009-01-01

    Este documento describe un algoritmo genético combinado con un autómata celular que utiliza un esquema de población celular para mantener diversidad en la población y determinar automáticamente el tamaño de la población. Los individuos del algoritmo genético son organizados en un autómata celular de 2 dimensiones, donde los individuos son considerados activos o inactivos en cada iteración del proceso evolutivo de acuerdo con una función de transición de estados configurada en el autómata celu...

  14. Diseño e Implementación de los Algoritmos de Adaptación para Tres Parámetros de Un Controlador de Procesos de Alto Orden

    OpenAIRE

    Calleja Bernal Mendoza, Fernando

    2002-01-01

    En investigaciones anteriores a la presente, Narváez y Ramírez [1] desarrollaron un controlador de tres parámetros basado en modelos de segundo orden diseñado con la estructura IMC (controlador de modelo interno, por sus siglas en inglés). En este trabajo se proponen algoritmos de adaptación para los tres parámetros del controlador propuesto por Narváez y Ramírez, con el objetivo de tener un mejor desempeño del controlador y sustituir la necesidad de una sintonía. Los algoritmos que se propon...

  15. Programación, depuración del algoritmo SSVD en FORTRAN para el cálculo de valores y vectores propios de una matriz simétrica con alta precisión relativa

    OpenAIRE

    Villanueva Baschwitz, Germán

    2009-01-01

    El presente proyecto puede resumirse en tres etapas o tres grupos de actividades en las que el alumno ha desarrollado su trabajo: Implementación y depuración del algoritmo SSVD definitivo en lenguaje FORTRAN. La implementación se ha llevado a cabo en el entorno VISUAL STUDIO 2005 de Microsoft. Se ha utilizado el lenguaje FORTRAN por su extendido uso en Álgebra Lineal Numérica para la programación de algoritmos formales debido a su eficiencia y potencia. Es también el lenguaj...

  16. UTILIDAD Y RENDIMIENTO DE LOS ALGORITMOS DE BRUGADA Y VERECKEI-2 EN EL DIAGNÓSTICO DE LA TAQUICARDIA VENTRICULAR IDIOPÁTICA / Usefulness and performance of the vereckei-2 and brugada algorithms in the diagnosis of idiopathic ventricular tachycardia

    OpenAIRE

    Gustavo Padrón Peña; Fredy J. Rosa Fabián; Ramiro R. Ramos Ramírez; Elibet Chávez González; Raimundo Carmona Puerta; Juan Miguel Cruz Elizundia; Arnaldo Rodríguez León

    2012-01-01

    ResumenIntroducción y objetivos: Existen algoritmos como el de Brugada y Vereckei-2 para el diagnóstico de la taquicardia ventricular, pero no han sido explorados en series específicas de pacientes con taquicardia ventricular idiopática. El propósito de esta investigación no fue otro que identificar en nuestra serie, mediante análisis simple, el esquema de mayor rendimiento diagnóstico de los algoritmos de Brugada y Vereckei-2. Método: Estudio retrospectivo y descriptivo en los 15 pacientes q...

  17. Análisis bayesiano para la diferencia de dos proporciones usando R

    Directory of Open Access Journals (Sweden)

    Zhang, Hanwen

    2009-01-01

    Full Text Available Este artículo presenta una colección de funciones computacionales que son utilizadas en la implementación de un análisis bayesiano exhaustivo para la diferencia de dos proporciones. Con este fin, se discute la estimación puntual, la estimación mediante intervalos de credibilidad y la inferencia predictiva desde dos escenarios: el primero basado en las densidades exactas a priori y a posteriori (construidas mediante la primera función hipergeométrica de Appell y el segundo basado en densidades simuladas (mediante un algoritmo de cadenas de Markov con métodos de Monte Carlo. La implementación de estas funciones se realiza en el programa estadístico R, porque es un software libre, funciona bien en múltiples plataformas y permite enmarcar estas funciones bajo un objeto computacional denominado “paquete”. || In this paper we present a collection of functions that can be used to implement a comprehensive Bayesian analysis of a difference of two proportions. For instance, point estimation, credibility intervals and predictive inference are discussed in both scenarios, the priori and posteriori exact densities(based in the first Appell hypergeometric function and the simulated densities (based in a Markov chain Monte Carlo algorithm. We have chosento implement the suite of functions using the R statistical software because it is freely available, runs on multiple platforms and allows to compress the functions into a single computational object named “package”.

  18. Prediction of the local power factor in BWR fuel cells by means of a multilayer neural network; Prediccion del factor local de potencia en celdas de combustible BWR mediante una red neuronal multicapas

    Energy Technology Data Exchange (ETDEWEB)

    Montes, J.L.; Ortiz, J.J.; Perusquia C, R. [ININ, Carretera Mexico-Toluca s/n, 52750 La Marquesa, Ocoyoacac, Estado de Mexico (Mexico); Francois, J.L.; Martin del Campo M, C. [Departamento de Sistemas Energeticos, Facultad de Ingenieria, Universidad Nacional Autonoma de Mexico, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)]. e-mail: jlmt@nuclear.inin.mx

    2007-07-01

    To the beginning of a new operation cycle in a BWR reactor the reactivity of this it increases by means of the introduction of fresh fuel, the one denominated reload fuel. The problem of the definition of the characteristics of this reload fuel represents a combinatory optimization problem that requires significantly a great quantity of CPU time for their determination. This situation has motivated to study the possibility to substitute the Helios code, the one which is used to generate the new cells of the reload fuel parameters, by an artificial neuronal network, with the purpose of predicting the parameters of the fuel reload cell of a BWR reactor. In this work the results of the one training of a multilayer neuronal net that can predict the local power factor (LPPF) in such fuel cells are presented. The prediction of the LPPF is carried out in those condition of beginning of the life of the cell (0.0 MWD/T, to 40% of holes in the one moderator, temperature of 793 K in the fuel and a moderator temperature of 560 K. The cells considered in the present study consist of an arrangement of 10x10 bars, of those which 92 contains U{sup 235}, some of these bars also contain a concentration of Gd{sub 2}O{sub 3} and 8 of them contain only water. The axial location inside the one assembles of recharge of these cells it is exactly up of the cells that contain natural uranium in the base of the reactor core. The training of the neuronal net is carried out by means of a retro-propagation algorithm that uses a space of training formed starting from previous evaluations of cells by means of the Helios code. They are also presented the results of the application of the neuronal net found for the prediction of the LPPF of some cells used in the real operation of the Unit One of the Laguna Verde Nuclear Power station. (Author)

  19. Design and optimization of a fuel reload of BWR with plutonium and minor actinides; Diseno y optimizacion de una recarga de combustible de BWR con plutonio y actinidos menores

    Energy Technology Data Exchange (ETDEWEB)

    Guzman A, J. R.; Francois L, J. L.; Martin del Campo M, C.; Palomera P, M. A. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, Jiutepec, Morelos 62550 (Mexico)]. e-mail: maestro_juan_rafael@hotmail.com

    2008-07-01

    In this work is designed and optimized a pattern of fuel reload of a boiling water reactor (BWR), whose fuel is compound of uranium coming from the enrichment lines, plutonium and minor actinides (neptunium, americium, curium); obtained of the spent fuel recycling of reactors type BWR. This work is divided in two stages: in the first stage a reload pattern designs with and equilibrium cycle is reached, where the reload lot is invariant cycle to cycle. This reload pattern is gotten adjusting the plutonium content of the assembly for to reach the length of the wished cycle. Furthermore, it is necessary to increase the concentration of boron-10 in the control rods and to introduce gadolinium in some fuel rods of the assembly, in order to satisfy the margin approach of out. Some reactor parameters are presented: the axial profile of power average of the reactor core, and the axial and radial distribution of the fraction of holes, for the one reload pattern in balance. For the design of reload pattern codes HELIOS and CM-PRESTO are used. In the second stage an optimization technique based on genetic algorithms is used, along with certain obtained heuristic rules of the engineer experience, with the intention of optimizing the reload pattern obtained in the first stage. The objective function looks for to maximize the length of the reactor cycle, at the same time as that they are satisfied their limits related to the power and the reactor reactivity. Certain heuristic rules are applied in order to satisfy the recommendations of the fuel management: the strategy of the control cells core, the strategy of reload pattern of low leakage, and the symmetry of a quarter of nucleus. For the evaluation of the parameters that take part in the objective function it simulates the reactor using code CM-PRESTO. Using the technique of optimization of the genetic algorithms an energy of the cycle of 10834.5 MW d/tHM is obtained, which represents 5.5% of extra energy with respect to the

  20. Effect of a Sulphate Transient on the EAC Crack Growth Behaviour of Low-Alloy RPV Steels under Simulated BWR Operating Conditions (CASTOC WP 3, PSI Test 1)

    Energy Technology Data Exchange (ETDEWEB)

    Ritter, S.; Seifert, H. P

    2002-03-01

    Within the CASTOC-project (5th EU FW programme), the environmentally-assisted crack (EAC) growth behaviour of low-alloy reactor pressure vessel (RPV) steels is experimentally investigated under simulated transient and steady-state boiling water reactor (BWR) power operation conditions by six European laboratories. Within WP 3 of this project, the Paul Scherrer Institut (PSI) investigates the effect of water chemistry transients on the EAC crack growth behaviour under periodical partial unloading (PPU) conditions. The present report is a summary of the first PSI test of WP 3 with a Na{sub 2}SO{sub 4} transient. In the first part of the report, the theoretical background on crack growth mechanisms, crack chemistry, mass transport and water chemistry transients as well as a brief literature survey on other water chemistry transient investigations is given. Furthermore, the experimental equipment and test procedure is presented, followed by a summary of the results of PSI test 1 of WP 3. Finally the results are discussed in detail and compared to literature data. In the first part of the experiment, an actively growing EAC crack was generated by PPU in oxygenated high-temperature, high-purity water (T = 288 {sup o}C, DO = 8 ppm, SO{sub 4}{sup 2-} < 0.6 ppb). Then a sulphate transient was applied. The duration ({approx} 300 h) and the amount of sulphate (SO{sub 4}{sup 2-} = 368 ppb) of the applied sulphate transient conservatively covered all sulphate transients, which might occur in BWR/normal water chemistry (NWC) practice. After the transient, outlet conductivity was lowered from ca. 1 {mu}S/cm to less than 0.15 {mu}S/cm within 2.6 h by a 'two-loop technique'. No accelerating effect of the sulphate transient on the EAC crack growth of both tested fracture mechanics specimens under highly oxidising BWR/NWC conditions was observed, making it impossible to deterrnine incubation or delay times. The EAC crack growth rates (CGR) before, during and after the

  1. Algoritmo recursivo funcional para verificación y monitoreo de la densidad de números primos

    Directory of Open Access Journals (Sweden)

    Omar Iván Trejos Buriticá

    2016-12-01

    Full Text Available El presente artículo formula una solución recursiva, usando programación funcional, para la verificación y monitoreo de la densidad de los números primos que corresponde a la cantidad de números primos que se encuentran en un rango determinado. A partir de este planteamiento se hacen algunas reflexiones en torno a la relación entre matemática y programación de computadores así como alrededor de las tendencias que se notan en la estimación progresiva de la densidad de los números primos cuando se hacen algunas modificaciones en los rangos de evaluación. El propósito de este artículo es poner a consideración de los lectores una solución simple y ágil en la solución del problema planteado así como las reflexiones que de allí se derivan.

  2. 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.

  3. Utilizando algoritmos genéticos para exploração do espaço de projeto em sistemas multiprocessados embarcados

    Directory of Open Access Journals (Sweden)

    Alexandre Specian Cardoso

    2012-11-01

    Full Text Available A crescente complexidade no projeto de sistemas embarcados requer que novos tipos de ferramentas sejam desenvolvidas. Um exemplo disso são as plataformas virtuais, que são modelos de simulação visando facilitar a avaliação de arquiteturas quanto ao desempenho, consumo de potência entre outros requisitos de um sistema embarcado. Para diminuir o tempo de exploração do espaço de projeto, métodos heurísticos podem ser utilizados para diminuir o número de simulações necessárias. Este trabalho apresenta o desenvolvimento de um ambiente para modelagem visual e exploração do espaço de projeto de arquiteturas multiprocessadas. O ambiente utiliza um algoritmo genético para permitir uma rápida exploração do espaço de projeto e a otimização da configuração base definida pelo usuário. Um estudo de caso de um decodificador JPEG paralelo foi utilizado e os resultados demonstraram que os algoritmos genéticos permitem minimizar o número de arquiteturas simuladas quando comparado com a simulação exaustiva, além de obter arquiteturas com melhor compromisso entre desempenho e consumo de potência.

  4. Comparación de Algoritmos de Segmentación de Ruido Aplicados a Imágenes de Resonancia Magnética

    Directory of Open Access Journals (Sweden)

    Eduardo Barbará Morales

    2012-12-01

    Full Text Available En el estudio y diagnóstico de pacientes pediátricos que presentan tumores en el sistema nervioso central (SNC, se emplean imágenes de Resonancia Magnética (RM para cuantificar, evaluar y documentar las terapias y tratamientos aplicados. Estas imágenes se ven afectadas por ruidos, principalmente producto del movimiento del paciente en el período de estudio y en el proceso de adquisición de la imagen. En este trabajo se proponen dos algoritmos sencillos y eficientes para realizar la segmentación del ruido presente en las imágenes, analizando su histograma característico. Estas técnicas de segmentación de ruido permiten obtener imágenes a las cuales se les ha segmentado y puesto a cero una cierta cantidad de pixeles, con lo cual es posible disminuir el tiempo de cómputo en procesamientos posteriores. Se realizan además comparaciones entre los algoritmos donde se mide el tiempo de cómputo, el error medio relativo, la cantidad de puntos que son puestos a cero entre otras variables de interés.

  5. Algoritmos de control de calidad para detección de secuencias atípicas de contactos en pluviómetros de balancín

    Directory of Open Access Journals (Sweden)

    José L. Araya

    2009-01-01

    Full Text Available Se prueban diversos Algoritmos de Control de Calidad de Datos (ACCD para precipitación, con el fin de sugerir metodologías alternativas para detección de posibles valores atípicos generados por pluviómetros de balancín en condiciones operativas. Tres diferentes ACCD fueron probados, uno de ellos para la detección de tiempos entre contactos atípicos y otros dos basados en la detección de secuencias de tiempos entre contactos. Las diversas pruebas que fueron llevadas a cabo muestran que estas pruebas pueden ser útiles en la detección de tiempos entre contactos atípicos y obstrucciones parciales, detectando situaciones de obstrucción en el 70% de los casos. Los resultados obtenidos en condiciones controladas señalan que es posible utilizar estos algoritmos en tiempo real en forma conjunta, como una forma de aumentar la posibilidad de detección de valores sospechosos.

  6. Elaboração e Experimento de um Método de Marketing Viral e Database Marketing baseado em Algoritmos Genéticos

    Directory of Open Access Journals (Sweden)

    Fábio Roberto Ferreira Borges

    2012-07-01

    Full Text Available Esse trabalho propõe um método para a otimização dos esforços de comunicação e vendas no meio eletrônico, baseando-se no conceito de Algoritmos Genéticos. Para tal, foi realizada a revisão bibliográfica dos temas Database Marketing, Descoberta de Conhecimento em Bases de Dados, Marketing Viral e Algoritmos Genéticos, permitindo o desenvolvimento do método proposto e esquematização dos passos iterativos. Em seguida, com o propósito de demonstrar a aplicação do método desenvolvido, foi utilizado o método empírico-experimental, a fim de manipular a variável independente e comparar os resultados obtidos na variável dependente com padrões de referência encontrados na literatura. O método foi testado em um grupo experimental de 60 indivíduos. O resultado da Taxa de Clicagem no experimento, em que os indivíduos foram selecionados através da Roleta Viciada que considerava o fit dos mesmos com a mensagem, foi de 13,3%, bem acima das porcentagens apresentadas pela literatura como padrão de referência, apontando para as possibilidades gerenciais de utilização do método desenvolvido.

  7. 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.

  8. 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.

  9. 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.

  10. Optimization of fuel cells for BWR using Path Re linking and flexible strategies of solution;Optimizacion de celdas de combustible para BWR empleando Path Relinking y estrategias flexibles de solucion

    Energy Technology Data Exchange (ETDEWEB)

    Castillo M, J. A.; Ortiz S, J. J.; Torres V, M.; Perusquia del Cueto, R., E-mail: alejandro.castillo@inin.gob.m [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2009-10-15

    In this work are presented the obtained preliminary results to design nuclear fuel cells for boiling water reactors (BWR) using new strategies. To carry out the cells design some of the used rules in the fuel administration were discarded and other were implemented. The above-mentioned with the idea of making a comparative analysis between the used rules and those implemented here, under the hypothesis that it can be possible to design nuclear fuel cells without using all the used rules and executing the security restrictions that are imposed in these cases. To evaluate the quality of the obtained cells it was taken into account the power pick factor and the infinite multiplication factor, in the same sense, to evaluate the proposed configurations and to obtain the mentioned parameters was used the CASMO-4 code. To optimize the design it is uses the combinatorial optimization technique named Path Re linking and the Dispersed Search as local search method. The preliminary results show that it is possible to implement new strategies for the cells design of nuclear fuel following new rules. (Author)

  11. Optimal estimate of the coolant flow in the assemblies of a BWR of natural circulation in real time; Estimacion optima del flujo de refrigerante en los ensambles de un BWR de circulacion natural en tiempo real

    Energy Technology Data Exchange (ETDEWEB)

    Valle H, J.; Morales S, J. B. [UNAM, Facultad de Ingenieria, Division de Estudios de Posgrado, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: julfi_jg@yahoo.com.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)

    2012-10-15

    The present work exposes the design and the implementation of an advanced controller that allows estimating the coolant flow in the fuel assemblies of a BWR reactor of natural circulation in real time. To be able to reduce the penalizations that are established in the calculations of the operation limits due to the magnitude of the uncertainties in the coolant flows of a natural circulation reactor, is the objective of this research. In this work the construction of the optimal controller that allows estimating the coolant flows in a fuel channels group of the reactor is shown, as well as the operation of this applied to a reduced order model that simulates the dynamics of a natural circulation reactor. The controller design required of an estimator of the valuation variables not directly of the plant and of the estimates use of the local distributions of the coolant flow. The controller construction of the estimator was based mathematically in the filter Kalman whose algorithm allows to be carried out an advanced control of the system. To prove the estimator operation was development a simplified model that reproduces the basic dynamics of the flowing coolant in the reactor, which works as observer of the system, this model is coupled by means of the estimator controller to a detail model of the plant. The results are presented by means of graphics of the interest variables and the estimate flow, and they are documented in the chart that is presented at the end of this article. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-10-15

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

  13. Comparison of results for burning with BWR reactors CASMO and SCALE 6.2 (TRITON / NEWT); Comparacion de los resultados de quemado para reactores BWR con CASMO y SCALE 6.2 (TRITON/NEWT)

    Energy Technology Data Exchange (ETDEWEB)

    Mesado, C.; Miro, R.; Barrachina, T.; Verdu, G.

    2014-07-01

    In this paper we compare the results from two codes burned, CASMO and SCALE 6.2 (TRITON). To do this, is simulated all segments corresponding to a boiling water reactor (BWR) using both codes. In addition, to account for different working points, simulations changing the instantaneous variables, these are repeated: void fractions (6 points), fuel temperature (6 points) and control rods (two points), with a total of 72 possible combinations of different instantaneous variables for each segment. After all simulations are completed for each segment, we can reorder the obtained cross sections, as SCALE CASMO both, to create a library of compositions nemtab format. This format is accepted by the neutronic code of nodal diffusion, PARCS v2.7. Finally compares the results obtained with PARCS and with the SIMULATE3 -SIMTAB methodology to level of full reactor. Also, we have made use of the KENO-VI and MCDANCOFF modules belonging to SCALE. The first is a Monte Carlo transport code with which you can validate the value of the multiplier, the second has been used to obtain values of Dancoff factor and increase the accuracy of model SCALE. (Author)

  14. Characterization of welding of AISI 304l stainless steel similar to the core encircling of a BWR reactor; Caracterizacion de soldaduras de acero inoxidable AISI 304L similares a las de la envolvente del nucleo de un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Gachuz M, M.E.; Palacios P, F.; Robles P, E.F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    Plates of austenitic stainless steel AISI 304l of 0.0381 m thickness were welded by means of the SMAW process according to that recommended in the Section 9 of the ASME Code, so that it was reproduced the welding process used to assemble the encircling of the core of a BWR/5 reactor similar to that of the Laguna Verde Nucleo electric plant, there being generated the necessary documentation for the qualification of the one welding procedure and of the welder. They were characterized so much the one base metal, as the welding cord by means of metallographic techniques, scanning electron microscopy, X-ray diffraction, mechanical essays and fracture mechanics. From the obtained results it highlights the presence of an area affected by the heat of up to 1.5 mm of wide and a value of fracture tenacity (J{sub IC}) to ambient temperature for the base metal of 528 KJ/m{sup 2}, which is diminished by the presence of the welding and by the increment in the temperature of the one essay. Also it was carried out an fractographic analysis of the fracture zone generated by the tenacity essays, what evidence a ductile fracture. The experimental values of resistance and tenacity are important for the study of the structural integrity of the encircling one of the core. (Author)

  15. Simulation of the automatic depressurization system (Ads) for a boiling water reactor (BWR) based on RELAP; Simulacion del sistema de despresurizacion automatica (ADS) para un reactor de agua en ebullicion (BWR) basado en RELAP

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez G, C.; Chavez M, C., E-mail: ces.raga@gmail.com [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2012-10-15

    The automatic depressurization system (Ads) of the boiling water reactor (BWR) like part of the emergency cooling systems is designed to liberate the vapor pressure of the reactor vessel, as well as the main vapor lines. At the present time in the Engineering Faculty, UNAM personnel works in the simulation of the Laguna Verde reactor based on the nuclear code RELAP/SCADAP and in the incorporation to the same of the emergency cooling systems. The simulation of the emergency cooling systems began with the inclusion of two hydrodynamic volumes, one source and another drain, and the incorporation of the initiation logic for each emergency system. In this work is defined and designed a simplified model of Ads of the reactor, considering a detail level based on the main elements that compose it. As tool to implement the proposed model, the RELAP code was used. The simulated main functions of Ads are centered in the quick depressurization of the reactor by means of the vapor discharge through the relief/safety valves to the suppression pool, and, in the event of break of the main vapor line, the reduction of the vessel pressure operates for that the cooling systems of the core to low pressure (Lpcs and Lpci) they can begin their operation. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Cardenas V, J.; Filio L, C., E-mail: jaime.cardenas@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose M. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

    2016-09-15

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

  18. Actinides record, power calculations and activity for present isotopes in the spent fuel of a BWR; Historial de actinidos y calculos de potencia y actividad para isotopos presentes en el combustible gastado de un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Enriquez C, P.; Ramirez S, J. R.; Lucatero, M. A., E-mail: pastor.enriquez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2012-10-15

    The administration of spent fuel is one of the more important stages of the nuclear fuel cycle, and this has become a problem of supreme importance in countries that possess nuclear reactors. Due to this in this work, the study on the actinides record and present fission products to the discharge of the irradiated fuel in a light water reactor type BWR is shown, to quantify the power and activity that emit to the discharge and during the cooling time. The analysis was realized on a fuel assembly type 10 x 10 with an enrichment average of 3.69 wt % in U-235 and the assembly simulation assumes four cycles of operation of 18 months each one and presents an exposition of 47 G Wd/Tm to the discharge. The module OrigenArp of the Scale 6 code is the computation tool used for the assembly simulation and to obtain the results on the actinides record presents to the fuel discharge. The study covers the following points: a) Obtaining of the plutonium vector used in the fuel production of mixed oxides, and b) Power calculation and activity for present actinides to the discharge. The results presented in this work, correspond at the same time immediate of discharge (0 years) and to a cooling stage in the irradiated fuel pool (5 years). (Author)

  19. Evaluación de la reducibilidad de un mineral de hierro usando char como reductor

    Directory of Open Access Journals (Sweden)

    Yenny Rubiela Hernández, Carlos Alberto Sandoval Fonseca, Claudia Inés Sánchez Buitrago

    2011-05-01

    Full Text Available Muestra los ensayos de  reduciblidad  realizados en un hornotipo Linder a un mineral de hierro del municipio de Ubalá(departamento de Cundinamarca, Colombia, usando comoreductor un char. Se  indican las características del mineralde  hierro  de Ubalá, de  los  carbones  empleados para  laproducción del char y de la caliza, así como los ensayos dereducibilidad. Para la caracterización de  las materias primasy del char, como producto  final, se aplicaron normas ASTM.En  la producción de  los char se utilizaron  los hornos decoquización  tipo Cerchar  y  tipo  colmena  de  la Uptc  enSamacá  (Boyacá. Los ensayos de reducibilidad se hicieronbajo  los mismos parámetros de operación utilizados concarbón como reductor, y los resultados obtenidos dejan verque el mineral de hierro de Ubalá es reducible en menorporcentaje con char. Sin embargo, por  los grandes beneficiospara el medioambiente que se obtienen trabajando con elchar, no se descarta  la posibilidad de utilizarlo como posiblesustituto del carbón en el proceso de reducción directa.

  20. 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.