Flow measurement in a 170-MW hydraulic turbine using the Gibson method; Medicion del flujo de una turbina hidraulica de 170 MW utilizando el metodo Gibson

Energy Technology Data Exchange (ETDEWEB)

Urquiza, Gustavo [Universidad Autonoma del Estado de Morelos (Mexico); Adamkowski, Adam [The Szewalski Institute of Fluid-Flow Machinery (Poland); Kubiak, Janusz; Sierra, Fernando [Universidad Autonoma del Estado de Morelos (Mexico); Janicki, Waldemar [The Szewalski Institute of Fluid-Flow Machinery (Poland); Fernandez, J. Manuel [Comision Federal de Electricidad (Mexico)

2007-07-15

This paper describes the methodology applied for measuring water flow through a 170-MW hydraulic turbine. The flow rate was measured using the pressure-time method, also known as the Gibson method. This method uses the well-known water hammer phenomenon in pipelines; in turbine penstocks, for instance. The version of this method used here is based on measuring, during total stop of the water stream, the time-history of pressure change in one section of the turbine penstock and relate it to the pressure in the upper reservoir to which the penstock is connected. The volumetric flow rate is determined from the relevant integration of the measured temporary pressure rise. Flow measurement was possible this way because the influence of the penstock inlet was negligible as far as an error of the measurement is concerned. The length of the penstock was 300 m. Previous experience and a standard IEC-41-1991 were the criteria adopted and applied. A fast and efficient acquisition system, including a 16 bit card, was used. The flow rate was calculated using a computer program developed and tested on several cases. The results obtained with the Gibson method were used for calibration of the on-line flow measuring system based on the Winter-Kennedy method as one of the index methods. This method is very often used for continuous monitoring of the flow rate through hydraulic turbines, when the calibration has been done on site by using the results of measurements obtained by the absolute method. Having measured the flow rate and output power, the efficiency was calculated for any operating conditions. A curve showing the best operating conditions based on the highest efficiency is presented and discussed. The details of the instrumentation, its installation, and the results obtained are discussed in the paper. [Spanish] Este articulo describe la metodologia aplicada para la medicion del flujo en una turbina hidraulica de 170 MW. El flujo se midio utilizando el metodo de presion

Scienza e conoscenza: sul valore del metodo scientifico

Directory of Open Access Journals (Sweden)

Riccardo Luciano Appolloni

2014-05-01

Full Text Available L’antico problema di riconoscere una forma di conoscenza oggettivae fondata è ancora vivo; in questo scritto cercheremo di capire se la scienza moderna possa essere una forma di conoscenza tale e, quindi, privilegiata. A tal fine ci serviremo del pensiero di alcuni epistemologi e scienziati. In particolare, nel trattare il problema del valore epistemologico del metodo scientifico, non potremo esimerci dal fare i conti con l’anarchismo metodologico di Paul K. Feyerabend, verso il quale l’esito del presente articolo sarà fondamentalmente critico. A partire dai fecondi spunti di questo filosofo, tenteremo dapprima di analizzare i caratteri distintivi della scienza e del suo metodo rispetto ad altre forme di sapere; quindi, cercheremo di individuare alcuni limiti della conoscenza razionale.

The Control of Fast Reactors: Current Methods and Future Prospects; Controle des Reacteurs a Neutrons Rapides. Methodes Actuelles et Perspectives d'Avenir; Upravlenie reaktorami na bystrykh nejtronakh. sushchestvuyushchie metody i dal'nejshie perspektivy; Control de Reactores Rapidos: Metodos Actuales y Perspectivas

Energy Technology Data Exchange (ETDEWEB)

Loewenstein, W. B. [Argonne National Laboratory, IL (United States)

1964-06-15

examina los actuales mecanismos de control de los reactores de neutrones rapidos. En la medida de lo posible aprovechan el control por medio de fugas neutronicas. Si este metodo no es aplicable se suele recurrir al control por desplazamiento de los materiales del cuerpo. Igualmente se recurre a un control limitado utilizando un absorbente. Ninguno de estos metodos presenta ventajas considerables cuando se aplica a los'grandes reactores de potencia regeneradores, a menos que la razon interna de regeneracion (del cuerpo) sea muy elevada. Se requerira mucha habilidad para utilizar metodos de control basados en el empleo de un absorbente o en el desplazamiento espectral sin afectar en grado apreciable la economia neutronica deseada y a menudo necesaria. El autor cita algunos resultados preliminares obtenidos con sistemas perfeccionados. La reactividad de control viene determinada por los requisitos relativos a la parada del reactor, al ciclo del combustible (exceso de reactividad) y, en menor medida, por la realimentacion dominante. Pueden especificarse perfectamente los requisitos relativos al exceso de reactividad para un ciclo de combustible determinado, pero esos requisitos varian de modo considerable en otros sistemas similares que funcionen con distintos ciclos de combustible. A partir de ciertos limites, pueden fijarse casi arbitrariamente les requisitos relativos al exceso de reactividad. Sin embargo, existen algunas consideraciones generales que rigen la determinacion de este parametro. Se tienen en cuenta dichas consideraciones al examinar la reactividad de control en los actuales reactores de neutrones rapidos comparandola a la cantidad realmente necesaria para el funcionamiento de reactores de potencia regeneradores y neutrones rapidos. El autor cita parametros tipicos de potencia y de realimentacion en funcion de la temperatura a fin de determinar su influencia en los requisitos relativos a la reactividad de control. Los metodos utilizados para predecir la

Analytic techniques to quantify Tetrachlorohydroquinone and Chloranil; Tecnicas analiticas para cuantificar Tetraclorohidroquinona y Cloranilo

Energy Technology Data Exchange (ETDEWEB)

Castillo Escobedo, Ma. Teresa; Gutierrez de Gonzalez, Luz Ma; Gojon Zorrilla, Gabriel [Universidad Autonoma de Nuevo Leon, Monterrey, Nuevo Leon (Mexico)

1995-02-01

Tetrachlorohydroquinone (TCHQ) was determined by two methods: iodometry and cerimetry. Tritation with aqueous ceric ammonium sulphate using potentiometric end-point detection proved to be the method of choice on account of its coefficient of variation (CV=0.475%) and its excellent accuracy. Chloranil (TCQ) was quantified by titration with aqueous ascorbic acid in acetone-water-hexamethylene tetramine (HMT), the golden-yellow color of the TCQ-HMT complex disappearing at the end point. This method is accurate and has CV=0.396%. [Spanish] Se cuantifico la tetraclorohidroquinona (TCHQ) mediante una tecnica yodometrica y un metodo potenciometrico, basado en el uso de sulfato cerico amoniacal. Se concluyo que el metodo potenciometrico es el mejor, ya que tiene un coeficiente de variacion (CV) de 0.475%, y una exactitud muy aceptable. Se desarrollo un tecnica para cuantificar el Cloranilo (TCQ) por titulacion con Acido Ascorbico en presencia de Hexametilentetramina (HMT) en medio acetona-agua; el punto final se determino por la separacion del color amarillo oro del complejo TCQ-HMT. Esta tecnica presenta un coeficiente de variacion (CV) de 0.396% y una exactitud aceptable. Se realizaron pruebas de hipotesis para verificar la exactitud de los metodos elegidos.

Avaliação dos métodos de amostragem para fauna perifítica em macrófitas na Reserva da Biosfera, Serra do Espinhaço, Estado de Minas Gerais, Brasil - DOI: 10.4025/actascibiolsci.v30i3.377 Evaluation of sampling methods for periphytic fauna in macrophytes at the Espinhaço Mountain Range Biosphere Reserve, Minas Gerais State, Brazil - DOI: 10.4025/actascibiolsci.v30i3.377

Directory of Open Access Journals (Sweden)

Cristiane Machado López

2008-10-01

Full Text Available Os métodos “Jarra”, “Remocao Manual” e “Draga de Eckman modificada” foram avaliados para amostrar a fauna perifitica associada a macrofitas aquaticas. Foram coletadas 63 amostras em cinco ambientes lenticos e tres loticos na reserva da biosfera da Serra do Espinhaco (Estado de Minas Gerais, Brasil. Os testes estatisticos Anova e Tukey foram feitos para riqueza de Protista, Rotifera e Crustacea, enquanto para a abundancia de Protista, Rotifera, Crustacea, Gastrotricha, Tardigrada e Nematoda foram avaliados os percentuais. Os protozoarios e rotiferos representaram 80% da abundancia e riqueza da comunidade. Nos ecossistemas avaliados todos os metodos foram relevantes para Protista, por outro lado, o metodo da Jarra foi o mais adequado para a analise de Crustacea. Entre os metodos, a Draga foi menos indicada para os grupos de microinvertebrados nos ecossistemas aquaticos. Os metodos Remocao Manual e Draga foram apropriados para analisar Rotifera. A abundancia de Gastrotricha e Tardigrada demonstrou melhores resultados pelo metodo da Jarra e Nematoda pelo metodo da Draga. Os tres metodos sao apropriados para amostragem da fauna perifitica em ambos os sistemas aquaticos. Entretanto, e importante estar ciente de que para cada tipo de ecossistema a amostragem da comunidade faunistica requer um metodo especifico para obter a melhor performance.The methods “Jar”, “Manual Removal” and “modified Ekman`s Dredge” were evaluated for sampling periphyton fauna associated to aquatic macrophytes. Sixty three samples were collected from five lentic and three lotic water bodies at Espinhaço Mountain Range Biosphere Reserve (Minas Gerais, Brazil. ANOVA and Tukey statistical tests were performed for Protista, Rotifera and Crustacea richness, whilst Protista, Rotifera, Crustacea, Gastrotricha, Tardigrada and Nematoda, abundance were evaluate by percentage. Amongst the three methods, Dregde is less indicated for different water bodies systems

Methods in nuclear reactors calculations; Metodos de calculo en reactores nucleares

Energy Technology Data Exchange (ETDEWEB)

Velarde, G

1966-07-01

Studies are made of the neutron transport equation corresponding to the the real and virtual reactors, as well as the starting hypotheses. Methods are developed to solve the transport equation in slab geometry, and P{sub l}; B{sub l}; M{sub l}; S{sub n} and discrete ordinates approximations. (Author)

Metodologia de la Administración Federal de Aviación para el Diseño de estructuras de Pavimento flexible para aeropuertos

Directory of Open Access Journals (Sweden)

Julián Rodrigo Quintero González

2013-08-01

Full Text Available Se representan los aspectos técnicos fundamentales y principalesconsideraciones de la metodologia propuesta por la Administracion Federal de Aviación FAA para el diseño de estructuras de pavimento para aeropuertos. Se exponen los aspectos sobre las variables consideradas en el diseño (estructurales tránsito, factores ambientales y factores intrinsecos, se establecen las caracteristicas de las variables consideradas por el metodo (subrasante y materiales para la estructura, geometría del tren de aterrizaje, número de decolajes equivalentes y peso bruto maximo del decolaje y se explica el procedimiento utilizado para el tratamiento de la información requerida en diseño estructural de pavimentos flexibles para aeropuertos.

Preparation of hydrotalcite compounds using ultrasound irradiation to capture CO{sub 2}; Preparacion de compuestos tipo hidrotalcita utilizando irradiacion de ultrasonido para la captura de CO{sub 2}

Energy Technology Data Exchange (ETDEWEB)

Martinez, J.A.J.; Paredes, S.P.; Valenzuela, M.A.; Hernandez, M.L. [Instituto Politecnico Nacional, ESIQIE, Mexico, D.F. (Mexico)]. E-mail: sparedesc@ipn.com.mx

2009-09-15

Al-Mg hydrotalcite compounds (HTC) were prepared using co-precipitation, sol-gel and reconstruction of the structure with ultrasound-assisted irradiation. The interlaminar components for each method were nitrate, acetylacetonate ethoxide and metavanadate, respectively. Optimization of the synthesis was performed using x-ray diffraction. The effect of the different parameters on synthesis was studied, including pH, time and ultrasound irradiation power. In addition, for the reconstruction method, temperature and calcination time were evaluated. For all methods, ultrasound-assisted methods were found to be more efficient and economical than conventional methods reported (autoclave). They also have the advantage of being able to control properties such as crystallinity, porosity and the specific surface, which significantly depends on the preparation method, irradiation time and type of interlaminar component. These methods are intended to synthesize interlaminar anionic materials that are very scarce in nature with better properties than traditional adsorbents used for the capture of CO{sub 2}. [Spanish] Se prepararon compuestos tipo hidrotalcita Al-Mg por los metodos de: coprecipitacion, sol gel y reconstruccion de la estructura asistidos por irradiacion de ultrasonido. Los componentes interlaminares para cada metodo fueron respectivamente: nitrato, etoxido-acetilacetonato y metavanadato. La optimizacion de la sintesis, se efectuo mediante difraccion de rayos-X. Se estudio el efecto de diversos parametros en la sintesis: pH, tiempo y potencia de irradiacion de ultrasonido, ademas, para el metodo de reconstruccion se evaluaron la temperatura y el tiempo de calcinacion. En todos los casos se encontro que el empleo de metodos asistidos por ultrasonido resultan ser mas eficientes y economicos que los metodos convencionales reportados (autoclave), ademas tienen la ventaja, de poder controlar propiedades tales como: la cristalinidad, la porosidad y la superficie

Torque calculation in the induction motor with the finite element method; Calculo del par en el motor de induccion con el metodo del elemento finito

Energy Technology Data Exchange (ETDEWEB)

Castillo Diaz, Ramon

2002-06-15

In this work the method of the finite element is applied to the bi-dimensional analysis of the induction motor in operation in steady state, excited by sine sources of laminar currents and sine sources of voltage. The analysis is focused mainly in the calculation of the electromagnetic torque. The topics of electromagnetic theory are covered and in an idealized model of the induction motor, analytically and numerically with the method of the finite element, in the variant method of Galerkin, the vectorial potential and the torque are calculated. The results obtained with the analytical and numerical methods are compared. Three formulations are developed to calculate the torque with the method of the finite element, using triangular elements of first order, based in the equation of force of Lorentz, the Maxwell tensor and the principle of the virtual work. Finally, a motor of induction of real characteristics is simulated, assuming it is connected to a three-phase voltage source. In this motor it is analyzed the convergence and the evolution in the results obtained of the torque with different discretions, and the torque-velocity performance curve is calculated. [Spanish] En este trabajo se aplica el metodo del elemento finito al analisis bidimensional del motor de induccion en operacion en estado estable, excitado por fuentes de corriente laminar senoidales y fuentes de voltaje senoidales. El analisis se enfoca principalmente en el calculo del par electromagnetico. Se tratan los topicos de teoria electromagnetica involucrados y en un modelo idealizado del motor de induccion, se calculan analitica y numericamente con el metodo del elemento finito, en la variante metodo de Galerkin, el potencial vectorial y el par. Se comparan resultados obtenidos con los metodos analiticos y numericos. Se desarrollan tres formulaciones para calcular el par con el metodo del elemento finito, utilizando elementos triangulares de primer orden, basadas en la ecuacion de fuerza de

Development of an analytic method for arsenic's determination in lime and tortilla; Desarrollo de un metodo analitico para determinacion de arsenico en cal y tortilla

Energy Technology Data Exchange (ETDEWEB)

Huato Soberanis, Julio; Ogura, Tetsuya [Universidad Autonoma de Guadalajara, Guadalajara, Jalisco (Mexico)

1995-02-01

A spectrophotometric method to determine As in tortilla and lime has been optimized, modifying the AsH{sub 3} generator. The reaction between arsin (AsH{sub 3}){sub 4} and diethyldithiocarbamate of Ag (AgDDC); was followed spectrophotometrically. The conditions under which the As remains in the ash during the calcination of the tortillas were studied. It was found that when they were heated in a quartz tube with a careful control of the air flow and oxygen, as well as the heating temperature, the arsenic loss in minimized. [Spanish] Se ha optimizado el metodo para determinar As en la tortilla y cal mediante espectrometria en el visible del color producido en la reaccion entre Arsina (AsH{sub 3}){sub 4} y dietilditiocarbamato de plata (AgDDC); modificando el generador de AsH{sub 3}. Se han buscado las condiciones en las que el arsenico permanece en las cenizas de la calcinacion de las tortillas; encontrandose que las tortillas deben calentarse en un tubo de cuarzo con control del flujo de aire y oxigeno asi como de la temperatura de calentamiento.

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)

The Role of Non-Destructive Testing in Test-Reactor Operation at the National Reactor Testing Station; Role des Essais Non Destructifs dans l'Exploitation des Reacteurs d'Essai au Centre National d'Essais de Reacteurs; Rol' nedestruktivnykh ispytanij pri ehkspluatatsii ispytatel'nykh reaktorov na natsional'noj stantsii po ispytaniyam reaktorov; Papel de los Metodos No Destructivos en la Explotacion de los Reactores de la National Reactor Testing Station

Energy Technology Data Exchange (ETDEWEB)

Francis, W. C.; Brown, E. S.; Burdick, E. E.; Gibson, G. W.; Tingey, F. H. [Phillips Petroleum Company, Atomic Energy Division, Idaho Falls, Idaho (United States)

1965-10-15

'un densimetre, permettent de determiner la distribution du combustible. On a habituellement recours a la radiographie des soudures pour les parties constitutives des reacteurs et des boucles d'essai. Le dispositif perfectionne de mesure de la reactivite (Advanced Reactivity Measurement Facility, ARMF) permet de determiner, pour chaque cycle de reacteur, l'irradiation du combustible et l'empoisonnement dans des specimens. Une application assez peu courante pour un assemblage critique est la mesure de la teneur en bore du combustible dans l'assemblage critique d'essai en genie des reacteurs (Engineering Test Reactor Critical Facility, ETRC). Le controle par courants de Foucault et par des procedes mecaniques de l'espacement des plaques de combustible et la mesure par courants de Foucault de l'epaisseur de l'oxydation (corrosion) sur les plaques irradiees ont donne d'excellents resultats. Des methodes complementaires qui ont fait leurs preuves sont l'inspection par liquide penetrant et les essais a l'azote liquide pour les craquelures superficielles, les essais par recuit thermique pour les souitlures et l'exploration par rayons gamma des plaques irradiees. On a recours a l'essai hydraulique d'un echantillon statistique d'elements combustibles pour verifier l'integrite structurale, notamment la resistance de la liaison entre les plaques de combustible et la gaine. Des efforts constants sont deployes pour ameliorer les methodes actuelles et mettre au point de nouveaux procedes de controle non destructif. (author) [Spanish] Los reactores de ensayo de la National Reactor Testing Station suponen una enorme inversion (superior a 100 millones de dolares) y la necesidad de explotarlos en condiciones de seguridad obliga a proceder a un control de calidad muy estricto de los componentes nucleares y de ensayo, especialmente en lo que respecta a los elementos combustibles y de control. Por tanto, los metodos no. destructivos son fundamentales para determinar la calidad de estos componentes

Survey of Pulsed Neutron Source Methods for Multiplying Media; Methodes des Neutrons Pulses Pour l'Etude des Milieux Multiplicateurs; Obzor metodov s ispol'zovaniem istochnikov impul'snykh nejtronov dlya razmnozhayushchej sredy; Estudio Panoramico de los Metodos de Empleo de Fuentes de Neutrons Pulsados en Medios Multiplicadores

Energy Technology Data Exchange (ETDEWEB)

Garelis, E. [General Electric Company, Vallecitos Atomic Laboratory, Pleasanton, CA (United States)

1965-10-15

-Small-L ). Il discute en outre l'emploi des methodes qui sont fondees sur la reponse a des impulsions pseudoaleatoires et utilisent une correlation entre l'entree et la sortie, pour la determination de la fonction de Green d'un milieu multiplicateur. H montre que les renseignements obtenus par ces methodes sont identiques a ceux fournis par les methodes de la source puisee a repetition, ce qui permet d'appliquer aux premieres les procedes qui ont ete mis au point pour les secondes. (author) [Spanish] En los ultimos afios ha habido dos tendencias principales acerca de la manera mas eficaz de medir la reactividad de parada, empleando fuentes de neutrones pulsados: la primera preconizaba el empleo de metodos tradicionales de medicion con fuentes neutronicas reiteradamente pulsadas, y la segunda propugnaba la aplicacion de metodos basados en una tecnica seudoaleatoria de respuesta a los impulsos, utilizando una correlacion entre los datos de entrada y los de salida. La informacion obtenida con una y otra tecnica es la misma; en teoria, ambos metodos sirven para determinar la funcion de respuesta. Se resefia el desarrollo de las tecnicas de empleo de fuentes de neutrones pulsados aplicadas a sistemas termicos con miras a medir la reactividad, desde los primeros intentos de Sjoestrand hasta el reciente metodo (k{beta}/ Script-Small-L ). Con el metodo usual de empleo de estas fuentes, la propiedad que se procuia determinar es la funcion de Green del conjunto subercritico empleado, es decir, la respuesta del reactor a una fuente de neutrones de funcion delta. El decrecimiento exponencial (e{sup {alpha}t}) de la funcion de Green proporciona una constante de decrecimiento de los neutrones instantaneos que es independiente del espacio. El autor examina los metodos para obtener el valor de la reactividad partiendo de la medida de a, como por ejemplo el metodo de la medicion de la criticidad por neutrones retardados a y el reciente metodo (k{beta}/ Script-Small-L ). Seguidamente examina el

Group cross-sections for fast reactors; Sections efficaces de groupes pour les reacteurs a neutrons rapides; Gruppovye secheniya reaktorov na bystrykh nejtronakh; Secciones eficaces de grupos para reactores rapidos

Energy Technology Data Exchange (ETDEWEB)

Zweifel, P P [University of Michigan, Ann Arbor, MI (United States); Ball, G L [Atomic Power Development Associates, Inc., Detroit, MI (United States)

1962-03-15

, comme c'est souvent le cas, la section efficace de groupe en terme d'integrales de resonance efficace, mais qu'il faut modifier cette definition suivant le type de schema multigroupe utilise. (author) [Spanish] La memoria discute en terminos generales las ecuaciones de difusion de grupos multiples y la forma correcta de las secciones eficaces correspondientes . En particular, demuestra que la seccion eficaz media de transporte puede expresarse con bastante precision en terminos de un promedio de recorridos libres medios. Esta magnitud es dificil de calcular porque no se puede expresar en funcion de promedios elementales ; sin embargo, se demuestran varias desigualdades que simplifican el procedimiento de determinacion de promedios. La memoria discute otros tres aspectos de las secciones eficaces de grupos que con frecuencia se ignoran, pero que pueden ser importantes al estudiar detalladamente un diseno. a) El empleo de los mismos valores medios correspondientes a las secciones eficaces de grupos para todos los reactores rapidos no se justifica si los espectros de los diferentes reactores no son similares y si las secciones eficaces varian rapidamente dentro del grupo, como ocurre a menudo. Los autores describen un metodo de iteracion, que permite obtener valores medios correctos y determinar en que medida los efectos espectrales ejercen influencia sobre los calculos de reactores. b) En los calculos de transporte (metodo S{sub n} por ejemplo), los promedios deben evaluarse en funcion del angulo y de la energia. Como el flujo no es separable en una parte angulo y en una parte energetica, es necesario proceder con sumo cuidado para evitar errores. La ecuacion S{sub n} se estudia sobre la base de un modelo sencillo, y de este estudio se deduce un criterio que puede ser de utilidad al determinar la importancia de la no-separabilida d angular en los calculos de reactores. c) Basandose en los argumentos de conservacion neutronica, se deriva una relacion de compatibilidad

Research reactor fuel bundle design review by means of hydrodynamic testing; Ensayos hidrodinamicos para verificacion de diseno de un elemento combustible para reactores de investigacion

Energy Technology Data Exchange (ETDEWEB)

Pastorini, A; Belinco, C [Comision Nacional de Energia Atomica, San Martin (Argentina). Centro Atomico Constituyentes

1998-12-31

During the design steps of a fuel bundle for a nuclear reactor, some vibration tests are usually necessary to verify the prototype dynamical response characteristics and the structural integrity. To perform these tests, the known hydrodynamic loop facilities are used to evaluate the vibrational response of the bundle under the different flow conditions that may appear in the reactor. This paper describes the tests performed on a 19 plate fuel bundle prototype designed for a low power research reactor. The tests were done in order to know the dynamical characteristics of the plates and also of the whole bundle under different flow rate conditions. The paper includes a description of the test facilities and the results obtained during the dynamical characterization tests and some preliminary comments about the tests under flowing water are also presented. (author) 4 refs., 12 figs., 4 tabs. [Espanol] Durante el diseno de un elemento combustible para un reactor nuclear se requiere de la realizacion de ensayos con el objeto de verificar el comportamiento de ese diseno y permitir, de ser necesario, la introduccion de modificaciones al mismo. Para verificar las caracteristicas de respuesta dinamica e integridad estructural, se realizan ensayos de vibraciones que incluyen someter al prototipo a condiciones de circulacion del fluido similares a las que soportara durante la operacion del reactor. Estos ensayos se realizan en facilidades de ensayos conocidas como circuitos hidrodinamicos, que permiten no solo someter el prototipo al flujo de fluido, sino tambien obtener una adecuada caracterizacion de la respuesta del mismo a traves del luso de sensores de distinto tipo. En este trabajo se describen los ensayos realizados sobre un prototipo de elemento combustible de 19 placas destinado a un reactor de investigacion multiproposito de baja potencia. Los ensayos tuvieron como objetivo conocer la respuesta dinamica de las placas individuales y del elemento combustible en su

Computer program for the calculation of stresses in rotary equipment discs; Programas de computo para el calculo de esfuerzos en discos de equipo rotatorio

Energy Technology Data Exchange (ETDEWEB)

Gutierrez Delgado, Wilson; Kubiak, Janusz; Serrano Romero, Luis Enrique [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1991-12-31

In the preliminary design and diagnosis of rotary machines is very common to utilize simple calculation methods for the mechanical and thermal stresses, dynamic and thermodynamic analysis and flow of fluids in this machines (Gutierrez et al., 1989). The analysis with these methods provides the necessary results for the project initial stage of the machine. Later on, more complex tools are employed to refine the design of some machine components. In the Gutierrez report et al., (1989) 34 programs were developed for the preliminary design and diagnosis of rotating equipment; in this article, one of them is presented in which a method for the analysis of mechanical and thermal stresses is applied in discs of uniform or variable thickness that are normally found in turbomachines and rotary equipment. [Espanol] En el diseno preliminar y diagnostico de maquinas rotatorias es muy comun emplear metodos de calculo sencillos para el analisis de esfuerzos mecanicos y termicos, analisis dinamico y termodinamico y de flujo de fluidos en estas maquinas (Gutierrez et al., 1989). El analisis con estos metodos proporcionan los resultados necesarios para la etapa del proyecto inicial de la maquina. Posteriormente, para refinar el diseno de algunos componentes de la maquina, se aplican las herramientas mas complejas. En el informe de Gutierrez et al., (1989) se desarrollan 34 programas para el diseno preliminar y diagnostico de equipo rotatorio; en este articulo, se presenta uno de ellos, en el que se emplea un metodo para el analisis de esfuerzos mecanicos y termicos en discos de espesor constante o variable que se encuentran comunmente en turbomaquinas y en equipos rotatorios.

Computer program for the calculation of stresses in rotary equipment discs; Programas de computo para el calculo de esfuerzos en discos de equipo rotatorio

Energy Technology Data Exchange (ETDEWEB)

Gutierrez Delgado, Wilson; Kubiak, Janusz; Serrano Romero, Luis Enrique [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1990-12-31

In the preliminary design and diagnosis of rotary machines is very common to utilize simple calculation methods for the mechanical and thermal stresses, dynamic and thermodynamic analysis and flow of fluids in this machines (Gutierrez et al., 1989). The analysis with these methods provides the necessary results for the project initial stage of the machine. Later on, more complex tools are employed to refine the design of some machine components. In the Gutierrez report et al., (1989) 34 programs were developed for the preliminary design and diagnosis of rotating equipment; in this article, one of them is presented in which a method for the analysis of mechanical and thermal stresses is applied in discs of uniform or variable thickness that are normally found in turbomachines and rotary equipment. [Espanol] En el diseno preliminar y diagnostico de maquinas rotatorias es muy comun emplear metodos de calculo sencillos para el analisis de esfuerzos mecanicos y termicos, analisis dinamico y termodinamico y de flujo de fluidos en estas maquinas (Gutierrez et al., 1989). El analisis con estos metodos proporcionan los resultados necesarios para la etapa del proyecto inicial de la maquina. Posteriormente, para refinar el diseno de algunos componentes de la maquina, se aplican las herramientas mas complejas. En el informe de Gutierrez et al., (1989) se desarrollan 34 programas para el diseno preliminar y diagnostico de equipo rotatorio; en este articulo, se presenta uno de ellos, en el que se emplea un metodo para el analisis de esfuerzos mecanicos y termicos en discos de espesor constante o variable que se encuentran comunmente en turbomaquinas y en equipos rotatorios.

Double-Sampling Method for Carrying Out Quality Control of a Fabrication Process; Methode du Double Echantillonnage pour le Controle de la Qualite d'un Procede de Fabrication; Metod dvukh obraztsov dlya osushchestvleniya kontrolya za kachestvom v protsesse izgotovleniya; Metodo de Muestreo Doble para el Control de Calidad de un Proceso de Fabricacion

Energy Technology Data Exchange (ETDEWEB)

Cerrolaza, J. A.; Lago, A.; Montojo, Rosa M. [Junta de Energia Nuclear, Madrid (Spain)

1966-02-15

taille des echantillons et le degre de controle sont determines en fonction des risques inherents a la premiere et a la deuxieme condition. Bien que cette methode soit applicable, elle est fort peu pratique quand il s'agit de controler des pieces de reacteurs, car les echantillons qu'elle exige sont de dimensions excessives. Le memoire expose une methode analogue a celle de Cave mais qui consiste a etablir un double echantillonnage dans lequel la taille moyenne de l'echantillon est beaucoup plus reduite. (author) [Spanish] La fabricacion de componentes que han de ser empleados en reactores nucleares presenta dos caracteristicas fundamentales que condicionan el proceso: la exigencia de una calidad muy elevada que limita a valores muy bajos el porcentaje de piezas defectuosas admisibles, y el coste muy alto de cada uno de los componentes. Estas dos condiciones obligan a que el control durante la fabricacion posea una curva de operacion con potencia muy elevada, y, por otra parte, a que el numero de piezas destruidas en cada inspeccion sea un pequeno como se pueda, siempre que se cumpla la condicion anterior. Los metodos usuales de control, basados en fijar el riesgo de primera especie, no son aplicables, ya que en general su eficacia no es suficiente. Cave ha desarrollado un metodo en que, tanto el tamano de las muestras como los limites de control, se fijan en funcion de los riesgos de primera y segunda especie. Este metodo, si bien es aplicable, resulta poco practico en el control de componentes para reactores, ya que se necesitan muestras de un tamano excesivamente grande. En el presente trabajo se desarrolla un metodo semejante al de Cave, pero en el que se establece un muestreo doble, con lo que el tamano medio de la muestra es mucho mas reducido. (author) [Russian] Pri izgotovlenii komponentov dlja ispol'zovanija v reaktorah reshajushhee znachenie imejut dva osnovnyh faktora, a imenno: neobhodimost' obespechit' ochen' vysokoe kachestvo, dopuskajushhee lish' ochen

Factors application of MW-mile method and participation in the allocation of charges by the drills use in electricity markets; Aplicacion de los factores de participacion y del metodo de MW-milla en la asignacion de cargos por uso de redes de transmision en mercados de electricidad

Energy Technology Data Exchange (ETDEWEB)

Alba-Gomez, L; Tovar-Hernandez, J. H; Gutierrez-Alcaraz, G [Instituto Tecnologico de Morelia, Michoacan (Mexico)]. E-mail: horaciotovar@mexico.com; ggutier@itmorelia.edu.mx

2007-04-15

Use of network allocation costs by shift factors and MW-Mile method is reported in this paper. Conventional shift factors are computed based on DC power flow. DC power flow requires to selecting a slack bus in order to avoid matrix singularity. Therefore, shift factors are slack bus dependent. In order to evade slack bus dependency, two approaches are considered. [Spanish] Este trabajo presenta la asignacion de costos por uso de red mediante la aplicacion de Factores de Participacion (FP) y el metodo de MW-Milla. Los FP clasicos son calculados a partir del modelo lineal de flujos de potencia para lo que se requiere de establecer un nodo de referencia a fin de eliminar la singularidad de la matriz de coeficientes. Por lo tanto, los FP son dependientes de la asignacion del nodo de referencia. Dos metodos alternativos para evitar la dependencia del nodo compensador en la obtencion de los factores de participacion son presentados.

Métodos cromatográficos para determinar aminas biogênicas em alimentos de origem animal

Directory of Open Access Journals (Sweden)

César Aquiles Lázaro de la Torre

2013-12-01

Full Text Available Aminas biogenicas sao formadas como resultado da descarboxilacao de aminoacidos livres especificos. A analise desses metabolitos e de grande importancia na determinacao da qualidade e monitoramento de biogenicas como histamina e tiramina relacionadas com episodios de intoxicacao em humanos. A cromatografia e uma tecnica de separacao química usada para caracterizar aminas biogenicas. Variacoes da tecnica (cromatografia liquida, em camada delgada e gasosa tem sido amplamente usadas, porem a complexidade da matriz alimentar faz com que sejam realizadas mudancas nos processos de extracao, derivatizacao e deteccao em concordancia com cada grupo de alimento. A cromatografia liquida de alta eficiencia (CLAE e o metodo mais utilizado na determinacao de aminas biogenicas em alimentos. Contudo, devido a importancia das aminas biogenicas no controle da qualidade e a seguranca do consumidor, os pesquisadores tentam desenvolver novos metodos com o intuito de uma analise mais rapida e precisa para o controle de alimentos no mercado. O objetivo da revisao e apresentar algumas tecnicas cromatograficas aplicadas no monitoramento de aminas biogenicas em produtos de origem animal.

Módulos interactivos para el aprendizaje de la semántica.

OpenAIRE

Aquino Palacios, Ingrid

2012-01-01

Se proponen modulos interactivos para lograr el aprendizaje de la semantica en alumnos del V semestre de la Carrera de Lenguas, Literatura y Comunicacion de la Facultad de Educacion de la UNCP. Los metodos utilizados fueron el experimental y el bibliografico-documental. Los instrumentos utilizados fueron la prueba objetiva, prueba de ensayo y la prueba pedagogica. Se logró mejorar el aprendizaje de la semántica 

Non-Destructive Methods for Determining Burn-Up in Nuclear Fuel; Methodes Non Destructives d'Evaluation du Taux de Combustion dans le Combustible Nucleaire; Metody opredeleniya vygoraniya v yadernom toplive bez razrusheniya obraztsa; Metodos No Destructivos para Determinai el Grado de Combustion de los Elementos Combustibles Nucleares

Energy Technology Data Exchange (ETDEWEB)

McGonnagle, W. J. [Illinois Institute of Technology, Chicago, IL (United States)

1966-02-15

gamma emis par les matieres radioactives qui se forment au cours du processus de fission, en particulier le spectrometre a cristal courbe, le spectrometre Compton magnetique, le spectrometre Compton a coiencidence et le spectrometre a scintillation. Parmi les autres methodes non destructives, on peut citer l'activation de feuilles, la transmission des neutrons, l'analyse par activation, la mesure des rayonnements gamma de capture et la mesure des neutrons instantanes et differes. Le memoire etudie les principes essentiels des differents appareils et procedes ci-dessus, leur precision et leurs limitations. Le memoire presente des methodes non destructives utilisant les isotopes stables produits au cours du processus de fission. Dans les mesures au moyen de ces isotopes, le schema d'irradiation n'a qu'une importance secondaire et le temps de refroidissement ne joue aucun role. De plus, on dispose de donnees nucleaires plus precises sur les produits stables de la fission. Il semble que les plus utiles de tous les isotopes stables produits au cours du processus de fission soient ceux du zirconium, du molybdene, du ruthenium et du neodyme. Le memoire etudie l'interet de ces methodes d'analyse non destructive. (author) [Spanish] Los metodos no destructivos son de gran utilidad para medir cuantitativamente el grado de combustion. El metodo ideal seria el que no requiriese datos especiales sobre los espectros neutrtfni- cos, las irradiaciones precedentes o el tiempo de enfriamiento. Los elementos combustibles irradiados llevan en cierto modo el registro de su grado de combustion. Este registro consiste en el conjunto de los isotopos radiactivos y estables resultantes del proceso de fision. Desgraciadamente, tanto con los metodos no destructivos como con los destructivos el espectro neutronico, las irradiaciones precedentes y el tiempo de enfriamiento influyen sobre dicho registro. Analogamente, la falta de datos nucleares precisos tales como las secciones eficaces nucleares

Rapid Methods of Determining Internal Radioactive Contamination; Methodes Rapides Permettant d'Evaluer la Contamination Radioactive Interne; 0411 042b 0414 ; Metodos Rapidos para Determinar la Contaminacion Radiactiva Interna

Energy Technology Data Exchange (ETDEWEB)

Sedlet, J.; Fairman, W. D.; Robinson, J. J. [Industrial Hygiene and Safety Division, Argonne National Laboratory, Argonne, IL (United States)

1965-06-15

, il est possible de l'atteindre. Les emetteurs alpha et les emetteurs beta purs de faible energie presentent la plus grande difficulte du fait que les charges corporelles de ces nucleides doivent ordinairement etre evaluees par une analyse radiochimique du sang ou des excreta. Les auteurs decrivent les separations radiochimiques qui ont ete mises au point et appliquees au Laboratoire national d*Argonne pour doser rapidement ces emetteurs. Le memoire examine d'autre part certains problemes que pose l'obtention de charges corporelles a partir des taux d'excretion, peu apres l'absorption. Pendant ce laps de temps, l'excretion se modifie rapidement et, pour beaucoup de nucleides importants en l'occurrence, a un taux inconnu. Pour les taux d'absorption tres eleves ou tres bas, il n'est pas necessaire de connaitre immediatement la mesure precise des charges corporelles. Cependant, il existe pour chaque radionucleide une dose d'absorption intermediaire pour laquelle il faut pouvoir -determiner sans trop tarder la charge corporelle avec une precision relative, ce qui permet de decider ou non le traitement. Les auteurs examinent les proprietes et les facteurs qui rendent le dosage des elements osteotropes particulierement difficile dans les cas d'accident. (author) [Spanish] Los metodos aplicables en casos de accidente o en situaciones excepcionales tienen que ser suficientemente rapidos y sensibles para proporcionar resultados en plazos que faciliten el tratamiento eficaz de las personas sobreexpuestas. Los plazos disponibles dependeran, en parte, del numero de individuos irradiados. Si se logra obtener en pocas horas resultados utiles, se habra cumplido la funcion primaria de las mediciones rapidas de la carga corporal, que es la de contribuir en toda la medida de lo posible a reducir los danos debidos .a radionuclidos depositados internamente. Los metodos que se citan a continuacion pueden servir para evaluar la contaminacion interna en casos de accidente: recuento gamma y

A digital method for period measurements in a nuclear reactor; Um metodo digital para medidas de periodo em um reator nuclear

Energy Technology Data Exchange (ETDEWEB)

Mundim, Sergio Gorretta

1971-02-15

The present paper begins by giving a theoretical treatment for the nuclear reactor period. The conventional method of measuring the period is analysed and some previously developed digital methods are described. The paper criticises the latter, pointing out some deficiencies which the proposed process is able to eliminate. All errors connected with this process are also analysed. The paper presents suitable solutions to reduce them to a minimum. The total error is found to he less than the error presented by the other methods described. A digital period meter is designed with memory resources and an automatic scaler changer. Integrated circuits specifications are used in it. Real time experiments with nuclear reactors were made in order to check te validity of the method. The data acquired were applied to a simulated digital period meter implemented in a general purpose computer. The nuclear part of the work was developed at the 'Comissao Nacional de Energia Nuclear' and the simulation work was dane at the 'Departamento de Calculo Cientifico' of COPPE, which also advised the author in the completion of this thesis. (author)

Industrial Ultrasonic Inspection of Stainless-Steel Claddings for the EL4 Reactor; Controle Industriel par Ultrasons des Gaines en Acier Inoxydable du Reacteur EL4; Promyshlennyj kontrol' obolochechnykh trub iz nerzhaveyushchej stali reaktora dlya EL4 s pomoshch'yu ul'trazvukovogo metoda; Metodos Ultrasonicos para Control Industrial de las Vainas de Acero Inoxidable del Reactor EL4

Energy Technology Data Exchange (ETDEWEB)

Prot, A. C.; Foulquoer, H. E.; Peyrot, J. P. [Centre d' Etudes Nucleaires de Saclay (France)

1965-09-15

del metodo a utilizar representa un proceso delicado, cuyas consideraciones fundamentales se exponen en el presente trabajo. Una vez elegido el metodo y puesto a punto en el laboratorio, surgen dos nuevos problemas: Transposicion a escala industrial. Necesidad de tener siempre presente la calidad que puede alcanzarse en la industria, en relacion con normas de aceptacion definidas de manera mas o menos arbitraria. En la practica, ello obliga a realizar un estudio estadistico sobre partidas de tubos de diversos origenes y clasificarlos teniendo en cuenta umbrales de aceptacion de distintos grados de severidad. Como se ve en el trabajo, el numero de tubos a controlar es muy superior al previsto inicialmente. Este hecho indujo a estudiar una maquina de control automatico, capaz de satisfacer al mismo tiempo las exigencias de la cantidad y las propias del tipo de control seleccionado; estas ultimas son por lo general de orden mecanico y requieren una construccion especialmente esmerada. El conjunto de estas consideraciones llevo a concebir una maquina capaz de satisfacer sin dificultad las necesidades de una cadena de fabricacion'de elementos combustibles. Las posibilidades de esta maquina estan estrechamente ligadas a las caracteristicas del material descontrol escogido, sobre todo al rendimiento de los circuitos electronicos correspondientes a los aparatos de control por metodos ultrasonicos y al de los transductores utilizados. Se deduce del presente estudio, por otra parte, que el material corriente no responde al problema sino de manera muy imperfecta, y que se debe encarar desde ya el proyecto de un aparato especial para este tipo de control. (author) [Russian] Uluchshenie rabochih harakteristik reaktorov trebuet primenenija tshhatel'no razrabotannyh i strogo kontroliruemyh materialov. Odnim iz aspektov jetogo kontrolja javljaetsja kachestvo ispol'zuemyh pokrytij dlja trub, mehanicheskoe sostojanie kotoryh predstavljaet soboj sushhestvennyj faktor rentabel

Design and construction of a live insulator washing system for transformers; Diseno y construccion de un sistema de lavado en vivo para los aisladores de transformadores

Energy Technology Data Exchange (ETDEWEB)

Lizama-Camara, Y.A. [Universidad Veracruzana, Veracruz (Mexico)]. E-mail: yahir_lizama@ieee.org; Mendieta-Antunez, J.A.; Blanco-Brisset, E. [Industrias IEM, Tlalnepantla, Estado de Mexico (Mexico)]. E-mail: unamanu@hotmail.com; Olivares Galvan, J.C.; Escarela-Perez, R. [Universidad Autonoma Metropolitana, Unidad Azcapotzalco, Mexico, D.F. (Mexico)]. E-mails: jolivare_1999@yahoo.com; r.escarela@ieee.org

2012-04-15

Through the electrical industry history there have been developments of different cleaning methods to avoid the insulators flashover s due to pollution. This paper describes the principal cleaning methods applicable to transformers insulators, emphasizing the high pressure fixed-type live insulator washing method, which was applied for cleaning the insulators of 900 MVA transformer bank of the Laguna Verde power plant localized at the state of Veracruz in Mexico. We propose a transformer insulator cleaning methodology, which identifies the main variables to take into account (the voltage level of the transformers, the pollution level of the insulators, determination of the optimal wash time, the amount of water, the optimal pressure of water jet, the maximum conductivity of the water and the wind velocity), reference values are given for these variables. In addition, we present an economic cost analysis when applying a method of this kind in an electric substation. [Spanish] A lo largo de la historia de la industria electrica se han desarrollado diferentes metodos de limpieza para evitar las fallas de los aisladores de los transformadores debido a la contaminacion. Este articulo describe los principales metodos de limpieza aplicables a los aisladores de transformadores, enfatizando el sistema de lavado en vivo tipo fijo con agua a alta presion, metodo que fue aplicado para realizar la limpieza de los aisladores en el banco de transformadores de 900 MVA de la central electrica Laguna Verde, ubicada en el estado de Veracruz, en Mexico. Se propone una metodologia para la limpieza de los aisladores de transformadores, donde se identifican las principales variables a tomar en cuenta (el nivel de tension de los transformadores, nivel de contaminacion de los aisladores, determinacion del tiempo optimo de lavado, cantidad de precipitacion de agua, presion optima del chorro de agua, maxima conductividad del agua y las velocidades de los vientos) y se dan valores de

A digital method for period measurements in a nuclear reactor; Um metodo digital para medidas de periodo em um reator nuclear

Energy Technology Data Exchange (ETDEWEB)

Mundim, Sergio Gorretta

1971-02-15

The present paper begins by giving a theoretical treatment for the nuclear reactor period. The conventional method of measuring the period is analysed and some previously developed digital methods are described. The paper criticises the latter, pointing out some deficiencies which the proposed process is able to eliminate. All errors connected with this process are also analysed. The paper presents suitable solutions to reduce them to a minimum. The total error is found to he less than the error presented by the other methods described. A digital period meter is designed with memory resources and an automatic scaler changer. Integrated circuits specifications are used in it. Real time experiments with nuclear reactors were made in order to check te validity of the method. The data acquired were applied to a simulated digital period meter implemented in a general purpose computer. The nuclear part of the work was developed at the 'Comissao Nacional de Energia Nuclear' and the simulation work was dane at the 'Departamento de Calculo Cientifico' of COPPE, which also advised the author in the completion of this thesis. (author)

Estudio de un reactor catalítico para la obtención de gas de síntesis

OpenAIRE

Romero Sayago, Sara Isabel

2016-01-01

Este trabajo se centra en el estudio del proceso de reformado de gas natural con vapor de agua para producir gas de síntesis. Un compuesto, que como su nombre indica, es de gran importancia en la síntesis de muchos productos. En concreto, se estudia el reactor heterogéneo catalítico donde tiene lugar la reacción de reformado. Mediante un programa de simulación de procesos químicos, se optimiza el proceso de reformado para obtener un rendimiento elevado en el reactor con el mínimo consumo e...

Matriz para ingenieria de tejido oseo: modificacion superficial con zinc Estudio preliminar

OpenAIRE

Martinez, Cristian; Olmedo, Daniel; Ozols, Andres

2013-01-01

El objetivo del presente trabajo es desarrollar un metodo de sintesis de matrices para ingenieria de tejidos, capaces de acelerar los procesos reparativos y disminuir el riesgo de infeccion, destinadas a cirugias reconstructivas que involucren el tejido oseo. A este fin se emplea la fase mineral de hueso bovino, la hidroxiapatita, conservando su estructura tridimensional. Esta se obtiene a partir de un proceso de lavado quimico, seguido de un proceso termico que elimina todos los componentes ...

A microwave technique for electrical conductivity measurements in semiconductors; Un procedimiento en frecuencia de microondas para la medicion de la conductividad electrica en semiconductores

Energy Technology Data Exchange (ETDEWEB)

Ramirez, A; Zehe, A [Benemerita Universidad Autonoma de Puebla, Puebla (Mexico); Starostenko, O [Universidad de las Americas, Puebla, (Mexico); Perez, L [Benemerita Universidad Autonoma de Puebla, Puebla (Mexico)

2003-01-15

In the present paper a theoretical approach is given together with the description of the experimental technique for electrical conductivity measurements of semiconductors in frequency range of 10 GHz, corresponding to a wavelength of {lambda}= 3 cm. It is shown, that the sample conductivity, measured without the need of electrical contacts, Is practically identical with results obtained by direct current methods. The potential use of the method for dielectric measurements in samples of general shape is included in the discussion. Given that the local electrical field is known only in bodies of ellipsoidal shape, one has to apply approximation methods for sample shapes of practical relevance (cylinders, cubes, disks). Finally, the measuring range and corresponding errors are explained on the base of measurements realized with silicon samples. [Spanish] En el presente trabajo se desarrolla la teoria junto con la descripcion del arreglo experimental para la medicion de la conductividad electrica en muestras semiconductoras, utilizando un campo de microondas de {lambda}= 3 cm, correspondiente a una frecuencia n de 10 GHz. Se demuestra que la conductividad electrica medida sin la necesidad de contactos electricos es practicamente identica con resultados obtenidos por el metodo comun utilizando corriente directa (d.c.). Se incorpora en la discusion ademas el potencial del metodo para el estudio de propiedades dielectricas en muestras de geometria general. Dado que solamente en cuerpos con geometria elipsoidal se conoce bien el campo electrico local, y con esto el momento bipolar inducido, para muestras de geometrias mas practicas (cilindros, cubos, discos) se acude a metodos de aproximacion. Finalmente, se discute el rango de mediciones y errores, y se presentan mediciones concretas, utilizando muestras de silicio.

Osservazioni sul principio di legalità come idea e come metodo nell’esperienza giuridica della Chiesa

Directory of Open Access Journals (Sweden)

Beatrice Serra

2012-10-01

SOMMARIO: 1. Introduzione - 2. – La struttura essenziale del concetto di legalità e la sua realizzazione radicale nel diritto della Chiesa. - 3. L’idea di legalità come “regola che sta prima” nel ius commune e la sua coesistenza con un approccio empirico, essenzialmente giurisprudenziale e dottrinale, di costruzione del diritto. Il principio di legalità come metodo di produzione del diritto nel pensiero giuridico moderno- 4. Il legame storico-concettuale fra il principio di legalità e i Codici moderni - 5. Il Codex iuris canonici del 1917 e il principio di legalità come metodo di costruzione del ius ecclesiae in funzione della certezza del diritto - 6. (segueUlteriori riflessi della prima codificazione canonica sul principio di legalità.:

USO DA SISTEMATIZAÇÃO DA ASSISTÊNCIA DE ENFERMAGEM (SAE: UMA FERRAMENTA PARA REALIZAÇÃO DA AUDITORIA DE QUALIDADE

Directory of Open Access Journals (Sweden)

Maria Izelta da Silva Santos

2013-04-01

Full Text Available Realizar uma revisao bibliografica acerca da Sistematização da Assistencia de Enfermagem (SAE como instrumento para auditoria de qualidade. Metodos: Foram revisados 12 artigos cientificos sobre auditoria e 10 artigos sobre SAE, bem como dois livros sobre os assuntos abordados. Esta revisao e de carater descritivo. Resultados: Por meio da pesquisa, tornou-se evidente a correlação da SAE com a auditoria. A SAE bem implementada pode contribuir para uma auditoria de qualidade.

Techniques for contact and contact with friction problems; Tecnicas para problemas de contacto y contacto con friccion

Energy Technology Data Exchange (ETDEWEB)

Velandia Arana, Gonzalo [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1990-12-31

Different numerical techniques are presented based in the finite element method to obtain numerical solutions to contact and contact with friction problems between solid bodies, and compared between each other. [Espanol] Se presentan diferentes tecnicas numericas basadas en el metodo de elementos finitos para la obtencion de soluciones numericas de problemas de contacto y contacto con friccion entre cuerpos solidos, y se comparan entre si.

Techniques for contact and contact with friction problems; Tecnicas para problemas de contacto y contacto con friccion

Energy Technology Data Exchange (ETDEWEB)

Velandia Arana, Gonzalo [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1989-12-31

Different numerical techniques are presented based in the finite element method to obtain numerical solutions to contact and contact with friction problems between solid bodies, and compared between each other. [Espanol] Se presentan diferentes tecnicas numericas basadas en el metodo de elementos finitos para la obtencion de soluciones numericas de problemas de contacto y contacto con friccion entre cuerpos solidos, y se comparan entre si.

A Portable Parallel Implementation of the U.S. Navy Layered Ocean Model

Science.gov (United States)

1995-01-01

Wallcraft, PhD (I.C. 1981) Planning Systems Inc. & P. R. Moore, PhD (Camb. 1971) IC Dept. Math. DR Moore 1° Encontro de Metodos Numericos...Kendall Square, Hypercube, D R Moore 1 ° Encontro de Metodos Numericos para Equacöes de Derivadas Parciais A. J. Wallcraft IC Mathematics...chips: Chips Machine DEC Alpha CrayT3D/E SUN Sparc Fujitsu AP1000 Intel 860 Paragon D R Moore 1° Encontro de Metodos Numericos para Equacöes

Criticality Studies in a Pilot Plant for Processing MTR-Type Irradiated Fuels; Estudios de Criticidad de una Planta Piloto para el Tratamiento de Combustibles Irradiados Tipo ' MTR '

Energy Technology Data Exchange (ETDEWEB)

Pereira Sanchez, G.; Uriarte Hueda, A. [Junta de Energia Nuclear, Division de Materiales Madrid (Spain)

1966-05-15

A number of theoretical studies on nuclear safety have been carried out in a pilot plant being constructed at the Junta de Energia Nuclear in Madrid for processing irradiated fuels from the MTR-type experimental reactor JEN-1. The study was carried out working with aqueous and organic solutions at two levels of {sup 235}U enrichment - 20% and 93%. The paper is divided into two main parts: the first deals with the individual items of equipment, and the interactions between these are studied in the second part. The calculations in this second part have been made using three different methods to make it more certain that the system as a whole can never be critical. The first method employed is based on the solid angle concept and makes it possible to fix the maximum {sup 235}U concentrations within the system. The second method, based on the albedo, supplies the value of the multiplication factor K of the whole assembly as a function of the concentration of {sup 235}U. In the last part, the distribution of the equipment is compared with other similar systems and experimental tests from other sources. Finally, the paper specifies the conditions for working the installation which ensure that a nuclear accident can never occur. (author) [Spanish] Se ha efectuado una serie de estudios teoricos sobre la seguridad nuclear de una planta piloto, que se encuentra en construccion en la Junta de Energfa Nuclear situada en Madrid, para el tratamiento de combustibles irradiados procedentes del reactor experimental JEN-1 del tipo MTR. El estudio se ha realizado utilizando disoluciones, tanto acuosas como organicas, con dos grados de enriquecimiento, 20% y 93% en {sup 235}U. Este trabajo comprende dos partes principales: en la primera se han considerado las distintas unidades del equipo individualmente y en la segunda se han estudiado las interacciones entre ellas. El calculo de esta segunda parte se ha hecho por tres metodos diferentes para tener una mayor seguridad de que el

Data base formation for important components of reactor TRIGA MARK II

Energy Technology Data Exchange (ETDEWEB)

Jordan, R; Mavko, B; Kozuh, M [Inst. Jozef Stefan, Ljubljana (Slovenia)

1992-07-01

The paper represents specific data base formation for reactor TRIGA MARK II in Podgorica. Reactor operation data from year 1985 to 1990 were collected. Two groups of collected data were formed. The first group includes components data and the second group covers data of reactor scrams. Time related and demand related models were used for data evaluation. Parameters were estimated by classical method. Similar data bases are useful everywhere where components unavailabilities may have severe drawback. (author) [Slovenian] V referatu smo prikazali raziskavo, v okviru katere smo za raziskovalni reaktor TRIGA MARK II v Podgorici izoblikovali specificno bazo podatkov. Zbrali smo podatke obratovanja reaktorja od leta 1985 do 1990. Rezultate raziskave dogodkov smo razdelili v dve glavni skupini. V prvo spadajo obratovalni podatki o komponentah, v drugo skupino pa spadajo zagoni oz. zaustavitve reaktorja. Podatke smo ovrednotili z modelom v casovnem prostoru in z modelom na zahtevo. Parametre modelov smo dolocili s klasicno metodo. Opisane baze podatkov so uporabne povsod, kjer so lahko posledice nezanesljivega delovanja sistemov velike. [author].

CONSTRUCCIÓN DE UN REACTOR DISCONTINUO PARA LA OBTENCIÓN DE BIODIESEL A PARTIR DEL ACEITE DE Ricinus communis

Directory of Open Access Journals (Sweden)

Yolimar Fernández

2014-01-01

Full Text Available Se construyó un reactor discontinuo para obtener biodiesel a partir de 5 litros de extracto obtenido de la semilla de Ricinus communis. El reactor es de acero inoxidable, con longitud de 29 cm; diámetro interno de 15,24 cm y fondo cónico de 20cm de largo, espesor de la pared de 0,2cm, resistencia tubular de 1000 W y motor de 110 volt. Se extrajo y se comparó con las normas respectivas las propiedades físicas y químicas del aceite crudo. Se realizaron pruebas preliminares de transesterificación del aceite catalizadas con NaOH para constatar la viabilidad de la reacción y definir las condiciones operacionales. El biodiesel obtenido fue caracterizado y comparado con referencias presentes en la literatura. Los resultaron mostraron que es posible obtener el biocombustible en el reactor discontinuo con un grado de conversión 88%; confirmando su aplicación en reacciones de transesterificación en medio básico.

METODO OPTICO PARA MEDIR EL COMPORTAMIENTO DE UNA LINEA DE TRANSMISION.

OpenAIRE

ASAHI KODAMA, TAKESHI EDUARDO; ASAHI KODAMA, TAKESHI EDUARDO

1998-01-01

El objetivo de esta tesis es el de establecer un método de manera de poder medir en forma óptica la corriente y el voltaje que circulan en una línea de transmisión. Para ello, se utilizan los fenómenos de Faraday y Kerr en líneas de transmisión que tienen 57p.

DOLOČITEV POVRŠINSKE NAPETOSTI Z METODO KAPILARNEGA DVIGA DVOFAZNIH SISTEMOV

OpenAIRE

Kravanja, Gregor

2014-01-01

Namen magistrske naloge je bil postavitev merilne naprave in razvoj nove metode merjenja površinske napetosti s kapilarnim dvigom dvofaznih sistemov v okolici kritične točke. Za pridobitev natančnih in primerljivih meritev je bilo potrebno poznati natančni notranji premer tankih kapilar. Določili smo ga z metodo laserskega tipanja na nemški koordinatni merilni napravi ZEISS tipa UMC-850 s pomočjo merilne programske opreme CALYPSO 5.1.4. Za merjenje ravnotežne višine smo uporabili računalniški...

Evaluación de una prueba rápida para el diagnostico de Malaria en áreas endémicas del Perú

Directory of Open Access Journals (Sweden)

Nancy Arrospide V

2006-04-01

Full Text Available Objetivos: Evaluar la sensibilidad, especificidad y valores predictivos de la prueba rapida basada en la deteccion de la pLDH (OptiMALR kit individual para el diagnostico de malaria en areas endemicas del Peru. Materiales y metodos: Estudio transversal realizado con pacientes febriles atendidos en centros de salud de la selva norte del Peru (San Martin y Loreto, de abril a diciembre de 2001. A cada paciente se le realizo la gota gruesa, la prueba OptiMALR y densidad parasitaria en forma ciega, por personal local capacitado y luego en el Laboratorio Nacional de Referencia de Malaria. Se calculo la sensibilidad (S, especificidad (E, valor predictivo positivo (VPP y valor predictivo negativo(VPN de la prueba OptiMALR en relacion a la gota gruesa para el diagnostico de malaria global y segun especie (P.falciparum y P.vivax. Resultados: Se incluyeron 346 muestras, 170 positivas. La prueba OptiMALR tuvo niveles de S=95,7%, E=97,1%, VPP=97,7%, VPN=95,3% independientemente de la especie. Para P.falciparum tuvo S=90,5%, E=97,3%, VPP=67,9 y VPN=99.4%; en tanto que para P.vivax S=92,0%, E=99,0%, VPP=98,7% y VPN=93,5%. Las sensibilidades estratificadas por parasitemia fueron 97,0% (5000 parasitos/¥ìL, 99% (100-5000 p/¥ìL y 50% (<100p/¥ìL. Conclusiones: La prueba rapida OptiMALR es un metodo con buena sensibilidad y especificidad para el diagnostico de malaria y puede ser usado en lugares donde no se dispone de laboratorios o microscopistas.

New Methods and Facilities for the Measurement of Physical Properties of Reactor Components and Irradiated Materials; Nouveaux Procedes et Instruments de Mesure des Proprietes Physiques des Elements de Reacteur et des Matieres Irradiees; Novye metody i sredstva izmereniya fizicheskikh s vojstv komponentov reaktora i obluchennykh materialov; Nuevos Metodos y Equipos para Medir Propiedades Fisicas de Componentes de Reactor y de Materiales Irradiados

Energy Technology Data Exchange (ETDEWEB)

Foerster, F.; Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

1965-09-15

radiactivas a temperaturas comprendidas entre 20 y 1 000 Degree-Sign C. Los autores discuten el control de calidad de metales no ferrosos por medida de la conductividad electrica aplicando corrientes de Foucault. Se describe un instrumento para medir la conductividad electrica de metales no ferrosos sin utilizar elementos en contacto. Se explica la correlacion entre la conductividad electrica y las caracteristicas de esfuerzo-deformacion de metales y aleaciones no ferrosos. Se presta especial atencion a la determinacion de estas propiedades en muestras pequenas. Se describe un dispositivo para medicion directa a distancia en la zona radiactiva del reactor. Se examina la relacion existente entre conductividad electrica y la dosis de radiacion. Se describe un instrumento para medir la permeabilidad, la remanencia y la fuerza coercitiva en funcion de la-solicitacion mecanica y la deformacion elastica y plastica, como tambien de la dosis de radiacion. Se expone un metodo para medir la variacion de las propiedades magneticas en funcion de la solicitacion elastica y la deformacion plastica. Se discuten los efectos de la irradiacion sobre la permeabilidad y la fuerza coercitiva. Se describe un instrumento para medicion rapida e indicacion directa de la permeabilidad de componentes de acero inoxidable. Se explica la correlacion entre permeabilidad y contenido de {Delta} - ferrita. Se exponen las mediciones del porcentaje de {Delta} - ferrita en soldaduras practicadas en tubos de acero inoxidable, y de las precipitaciones de {Delta}-ferrita en funcion de la deformacion plastica (forjado de los elementos combustibles). (author) [Russian] Opisan pribor dlja avtomaticheskogo izmerenija i registracii modulja Junga, modulja sdviga i kojefficienta zatuhanija kak funkcii temperatury i vremeni. Izmerenie modulja Junga proizvoditsja s pomoshh'ju vozbuzhdennyh obrazcov razlichnyh razmerov pri ih estestvennoj chastote. Izmerenie kojefficienta zatuhanija proizvoditsja po svobodnomu zatuhaniju

Non-Destructive Testing Methods Applied to Multi-Finned SAP Tubing for Nuclear-Fuel Elements; Essais Non Destructifs de Gaines a Ailettes, en Poudre d'Aluminium Frittee, pour Elements Combustibles; Nedestruktivnye metody ispytaniya rebristykh trub iz spechennogo alyuminikiog'o poroshka dlya yadernykh toplivnykh ehlementov; Metodos de Ensayo No Destructivo Aplicados a Tubos de SAP con Aletas Multiples Destinados a Elementos Combustibles

Energy Technology Data Exchange (ETDEWEB)

Lund, S. A. [Danish Central Welding Institution, Copenhagen (Denmark); Knudsen, P. [Danish Atomic Energy Commission, Research Establishment, Risoe (Denmark)

1965-09-15

Energia Atomica de Dinamarca ha emprendido el estudio de un reactor de potencia con refrigerante organico y moderador de agua pesada. Los correspondientes elementos combustibles consisten en haces de 19 barras formadas por pastillas de dioxido de uranio sinterizado, encerradas en tubos de producto de aluminio sinterizado (SAP), de 2 m de longitud, provistos de aletas helicoidales. Para obtener condiciones optimas de transmision de calor y mantener la integridad del elemento combustible durante el funcionamiento del reactor, es necesario contar con tubos de muy alta calidad. Se citan dos ejemplos que ponen de manifiesto las estrechas tolerancias dimensionales adoptadas. Para asegurar una calidad adecuada de los tubos, se establecio un control de calidad muy estricto, basado en gran medida en la aplicacion de metodos no destructivos. Se describen en esta memoria las tecnicas desarrolladas para medir el espesor de pared y los diametros, y para descubrir defectos. La compleja seccion transversal, con 24 aletas, impide aplicar metodos ultrasonicos o de comentes de Foucault para medir el espesor de la pared. Por consiguiente, se desarrollo un calibre registrador de rayos beta, cuyo funcionamiento se basa en la atenuacion sufrida por la radiacion beta proveniente de una fuente de {sup 90}Sr colocada en el interior del tubo. Para el registro continuo del espesor de la pared del tubo con seccion transversal mas simple, de 12 aletas, se utiliza un metodo ultrasonico de resonancia por inmersion. Los diametros interno y externo (entre puntos de aletas) se registran de manera continua mediante calibres neumaticos rapidos. Las fallas se detectan mediante la tecnica de eco de impulsos ultrasonicos, y examinando los tubos con corrientes de Foucault. El metodo ultrasonico permite descubrir facilmente las fisuras transversales, pero hasta ahora ha sido imposible utilizarlo para la deteccion de defectos longitudinales. Por consiguiente, ademas del ensayo ultrasonico, se aplica el examen con

RA-0 reactor. New neutronic calculations; Reactor RA-0. Nuevos calculos neutronicos

Energy Technology Data Exchange (ETDEWEB)

Rumis, D; Leszczynski, F

1991-12-31

An updating of the neutronic calculations performed at the RA-0 reactor, located at the Natural, Physical and Exact Sciences Faculty of Cordoba National University, are herein described. The techniques used for the calculation of a reactor like the RA-0 allows prediction in detail of the flux behaviour in the core`s interior and in the reflector, which will be helpful for experiments design. In particular, the use of WIMSD4 code to make calculations on the reactor implies a novelty in the possible applications of this code to solve the problems that arise in practice. (Author). [Espanol] En este trabajo se actualizan los calculos neutronicos realizados para el reactor RA-0, instalado en la Facultad de Ciencias Exactas, Fisicas y Naturales de la Universidad Nacional de Cordoba. Se describen los calculos realizados hasta la fecha y los resultados obtenidos. Las tecnicas incorporadas al calculo de un reactor como el RA-0 permiten predecir en detalle el comportamiento del flujo en el interior del nucleo y en el reflector, lo que sera una importante ayuda en el diseno de experimentos. En particular, el empleo del codigo WIMSD4 para calculos del reactor completo constituye una novedad en las posibles aplicaciones de ese codigo para resolver problemas que se presentan en la practica. (Autor).

Methodology for the integral comparison of nuclear reactors: selecting a reactor for Mexico; Metodologia para la comparacion integral de reactores nucleares: seleccion de un reactor para Mexico

Energy Technology Data Exchange (ETDEWEB)

Reyes R, R.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)]. e-mail: ricarera@yahoo.com.mx

2006-07-01

In this work it was built a methodology to compare nuclear reactors of third generation that can be contemplated for future electric planning in Mexico. This methodology understands the selection of the reactors to evaluate eliminating the reactors that still are not sufficiently mature at this time of the study. A general description of each reactor together with their main ones characteristic is made. It was carried out a study for to select the group of parameters that can serve as evaluation indicators, which are the characteristics of the reactors with specific values for each considered technology, and it was elaborated an evaluation matrix indicators including the reactors in the columns and those indicators in the lines. Since that none reactor is the best in all the indicators were necessary to use a methodology for multi criteria taking decisions that we are presented. It was used the 'Fuzzy Logic' technique, the which is based in those denominated diffuse groups and in a system of diffuse inference based on heuristic rules in the way 'If Then consequence> ', where the linguistic values of the condition and of the consequence is defined by diffuse groups, it is as well as the rules always they transform a diffuse group into another. Later on they combine all the diffuse outputs to create a single output and an inverse transformation is made that it transfers the output from the diffuse domain to the real one. They were carried out two studies one with the entirety of the indicators and another in which the indicators were classified in three approaches: the first one refers to indicators related with the planning of the plants inside the context of the general electric sector, the second approach includes indicators related with the characteristics of the fuel and the third it considers indicators related with the acting of the plant in safety and environmental impact. This second study allowed us to know the qualities of

Commissioning of research reactors. Safety guide

International Nuclear Information System (INIS)

2006-01-01

The objective of this Safety Guide is to provide recommendations on meeting the requirements for the commissioning of research reactors on the basis of international best practices. Specifically, it provides recommendations on fulfilling the requirements established in paras 6.44 and 7.42-7.50 of International Atomic Energy Agency, Safety of Research Reactors, IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005) and guidance and specific and consequential recommendations relating to the recommendations presented in paras 615-621 of International Atomic Energy Agency, Safety in the Utilization and Modification of Research Reactors, Safety Series No. 35-G2, IAEA, Vienna (1994) and paras 228-229 of International Atomic Energy Agency, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, Safety Series No. 35-G1, IAEA, Vienna (1994). This Safety Guide is intended for use by all organizations involved in commissioning for a research reactor, including the operating organization, the regulatory body and other organizations involved in the research reactor project

Bioreduction of para-chloronitrobenzene in drinking water using a continuous stirred hydrogen-based hollow fiber membrane biofilm reactor

Energy Technology Data Exchange (ETDEWEB)

Xia Siqing, E-mail: siqingxia@gmail.com [State Key Laboratory of Pollution Control and Resource Reuse, College of Environmental Science and Engineering, Tongji University, Shanghai 200092 (China); Li Haixiang; Zhang Zhiqiang [State Key Laboratory of Pollution Control and Resource Reuse, College of Environmental Science and Engineering, Tongji University, Shanghai 200092 (China); Zhang Yanhao [College of Municipal and Environmental Engineering, Shandong Jianzhu University, Jinan 250101 (China); Yang Xin; Jia Renyong; Xie Kang; Xu Xiaotian [State Key Laboratory of Pollution Control and Resource Reuse, College of Environmental Science and Engineering, Tongji University, Shanghai 200092 (China)

2011-08-30

Highlights: {yields} We designed a novel hollow fiber membrane biofilm reactor for p-CNB removal. {yields} Biotransformation pathway of p-CNB in the reactor was investigated in this study. {yields} Nitrate and sulfate competed more strongly for hydrogen than p-CNB. {yields} This reactor achieved high removal efficiency and hydrogen utilization efficiency. - Abstract: para-Chloronitrobenzene (p-CNB) is particularly harmful and persistent in the environment and is one of the priority pollutants. A feasible degradation pathway for p-CNB is bioreduction under anaerobic conditions. Bioreduction of p-CNB using a hydrogen-based hollow fiber membrane biofilm reactor (HFMBfR) was investigated in the present study. The experiment results revealed that p-CNB was firstly reduced to para-chloraniline (p-CAN) as an intermediate and then reduced to aniline that involves nitro reduction and reductive dechlorination with H{sub 2} as the electron donor. The HFMBfR had reduced p-CNB to a major extent with a maximum removal percentage of 99.3% at an influent p-CNB concentration of 2 mg/L and a hydraulic residence time of 4.8 h, which corresponded to a p-CNB flux of 0.058 g/m{sup 2} d. The H{sub 2} availability, p-CNB loading, and the presence of competing electron acceptors affected the p-CNB reduction. Flux analysis indicated that the reduction of p-CNB and p-CAN could consume fewer electrons than that of nitrate and sulfate. The HFMBfR had high average hydrogen utilization efficiencies at different steady states in this experiment, with a maximum efficiency at 98.2%.

Análisis de estabilidad del reactor PFTR para una reacción con cinética de primer orden utilizando la funcional de Lyapunov

Directory of Open Access Journals (Sweden)

Héctor Armando Durán Peralta

2007-01-01

Full Text Available Abunda la literatura referente al análisis de estabilidad de reactores con parámetros globalizados de concentración y temperatura (por ejemplo el CSTR, en cambio es escasa la literatura sobre la estabilidad de reactores con parámetros distribuidos donde existe distribución espacial de concentración y temperatura, como es el caso del reactor tubular PFTR. Este documento analiza la estabilidad del reactor PFTR isotérmico y no isotérmico para una reacción con cinética de primer orden utilizando la funcional de Lyapunov. Se trabaja con una cinética de primer orden pues un objetivo de este artículo es mostrar cómo se aplica la funcional de Lyapunov al análisis de un reactor de parámetros distribuidos, dado que es casi inexistente la literatura sobre el método de la funcional de Lyapunov aplicada a la estabilidad de reactores (técnica usada en el análisis de estabilidad de sistemas en ingeniería eléctrica. El análisis de estabilidad dio como resultado perfiles de temperatura y concentración asintóticamente estables para los casos PFTR isotérmico, no isotérmico con constante cinética independiente de la temperatura y PFTR no isotérmico adiabático. Para el PFTR con retiro de calor el análisis condujo a una región de estabilidad asintótica y a una región incierta donde puede o no haber oscilaciones.

Dispositivo de posicionamiento de muestras biológicas para su irradiación en un canal radial de un reactor nuclear // Biological samples positioning device for irradiations on a radial channel at the nuclear research reactor

Directory of Open Access Journals (Sweden)

Maritza Rodríguez - Gual

2010-05-01

Full Text Available ResumenPor la demanda de un dispositivo experimental para el posicionamiento de las muestras biológicaspara su irradiación en un canal radial de un reactor nuclear de investigaciones en funcionamiento, seconstruyó y se puso en marcha un dispositivo para la colocación y retirada de las muestras en laposición de irradiación de dicho canal. Se efectuaron las valoraciones económicas comparando conotro tipo de dispositivo con las mismas funciones. Este trabajo formó parte de un proyectointernacional entre Cuba y Brasil que abarcó el estudio de los daños inducidos por diferentes tipos deradiación ionizante en moléculas de ADN. La solución propuesta es comprobada experimentalmente,lo que demuestra la validez práctica del dispositivo. Como resultado del trabajo, el dispositivoexperimental para la irradiación de las muestras biológicas se encuentra instalado y funcionando yapor 5 años en el canal radial # 3(BH#3 Palabras claves: reactor nuclear de investigaciones, dispositivo para posicionamiento de muestras,___________________________________________________________________________AbstractFor the demand of an experimental device for biological samples positioning system for irradiationson a radial channel at the nuclear research reactor in operation was constructed and started up adevice for the place and remove of the biological samples from the irradiation channels withoutinterrupting the operation of the reactor. The economical valuations are effected comparing withanother type of device with the same functions. This work formed part of an international projectbetween Cuba and Brazil that undertook the study of the induced damages by various types ofionizing radiation in DNA molecules. Was experimentally tested the proposed solution, whichdemonstrates the practical validity of the device. As a result of the work, the experimental device forbiological samples irradiations are installed and operating in the radial beam hole #3(BH#3

Determination of the neutron spectrum at different locations in the Argentine RA-1 Reactor; Determinacion del espectro neutronico en distintas posiciones del reactor RA-1

Energy Technology Data Exchange (ETDEWEB)

Lerner, A M; Madariaga, M R [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)

1999-12-31

Radiodosimetria de la Autoridad Regulatoria Nuclear (ARN) utiliza la columna rapida del reactor para el disenio, calibracion y puesta a punto de dosimetros de criticidad asi como de los metodos de evaluacion rapida de las dosis absorbida por el personal en el caso de accidentes. Con este objeto se irradiaron hojuelas de Au(1), Au bajo Cd e In(2), para estimar los flujos neutronicos absolutos termico, epitermico y rapido respectivamente en la posicion de irradiacion. Esta estimacion es tanto mas precisa cuanto mejor se conocen las respuestas de los distintos materiales de los detectores al espectro de neutrones presente. Esto a su vez requiere el conocimiento previo de dicho espectro (dependencia detallada del flujo neutronico con la energia) en la posicion que se analiza. En este trabajo se presenta el calculo neutronico que fue oportunamente requerido al Grupo de Reactores de Investigacion y Conjuntos Criticos de la ARN, con el objeto de determinar el espectro neutronico en la posicion de irradiacion rapida del RA-1. Se ha evaluado el espectro neutronico en diferentes posiciones del reactor, utilizando dos lineas de calculo diferentes y considerando, a los fines de este analisis, una potencia de 40 kW. Se ha representado al reactor y al recinto que lo aloja con un modelo simplificado, unidimensional, como un conjunto de regiones circulares concentricas. Se muestran los graficos de los flujos rapido y termico (con corte en 0,4 eV) en funcion de la distancia al centro del reactor. Se muestra asimismo el grafico del flujo neutronico (en n/cm{sup 2}.seg.eV) en funcion de la energia en la posicion de irradiacion rapida. Se consignan tambien los valores del flujo (en n/cm{sup 2}.seg.eV) en funcion de la energia en otras posiciones tipicas, asi como los valores equivalentes de los flujos integrados (en n/cm{sup 2}.seg). ((1) De acuerdo con la reaccion Au{sup 197}(n, {gamma})Au{sup 198}, con una seccion eficaz de {sigma}{sub 0}=98.8b para neutrones termicos. (2) De acuerdo con la

Reactor network synthesis for isothermal conditions = Síntese de redes de reatores para condições isotérmicas

Directory of Open Access Journals (Sweden)

Lincoln Kotsuka da Silva

2008-07-01

Full Text Available In the present paper, a computational systematic procedure for isothermal Reactor Network Synthesis (RNS is presented. A superstructure of ideal CSTR and PFR reactors is proposed and the model is formulated as a constrained Nonlinear Programming (NLP problem. Complex reactions (series/parallel reactions are considered. The objective function is based on yield or selectivity, depending on the desired product, subject to different operational conditions. The problem constraints are mass balances in the reactorsand in the considered reactor network superstructure. A systematic computational procedure is proposed and a Genetic Algorithm (GA is developed to obtain the optimal reactor arrangement with the maximum yield or selectivity and minimum reactor volume. Results are as good as or better than those reported in the literature.No presentetrabalho apresenta-se um procedimento computacional para síntese de redes de reatores (SRR operando em condições isotérmicas. Uma superestrutura de rede de reatores formada por reatores ideais CSTR e PFR é proposta e o problema apresenta uma formulação de programação não linear (PNL. São consideradas reações complexas (série/paralelas. A função objetivo é baseada no rendimento ou na seletividade em relação ao produto desejado, sujeito a diferentes condições de operação. As restrições ao problema são provenientes dos balanços de massa e da configuração da superestrutura considerada.No procedimento computacional é proposto um Algoritmo Genético (AG para obtenção do arranjo ótimo de reatores com máximo rendimento ou seletividade com menor volume reacional. Os resultados obtidos são condizentes com os obtidos na literatura.

Análisis de estabilidad del reactor PFTR para una reacción con cinética de primer orden utilizando la funcional de Lyapunov

OpenAIRE

Héctor Armando Durán Peralta; Luis Fernando Córdoba C

2007-01-01

Abunda la literatura referente al análisis de estabilidad de reactores con parámetros globalizados de concentración y temperatura (por ejemplo el CSTR), en cambio es escasa la literatura sobre la estabilidad de reactores con parámetros distribuidos donde existe distribución espacial de concentración y temperatura, como es el caso del reactor tubular PFTR. Este documento analiza la estabilidad del reactor PFTR isotérmico y no isotérmico para una reacción con cinética de primer orden utilizando...

Análisis de estabilidad del reactor pftr para una reacción con cinética de primer orden utilizando la funcional de lyapunov

OpenAIRE

Durán Peralta, Héctor Armando; Córdoba C, Luis Fernando

2010-01-01

Abunda la literatura referente al análisis de estabilidad de reactores con parámetros globalizados de concentración y temperatura (por ejemplo el CSTR), en cambio es escasa la literatura sobre la estabilidad de reactores con parámetros distribuidos donde existe distribución espacial de concentración y temperatura, como es el caso del reactor tubular PFTR. Este documento analiza la estabilidad del reactor PFTR isotérmico y no isotérmico para una reacción con cinética de primer orden utilizand...

Comparative Study of the Methods Used for the Computer Resolution of Composite Gamma-Ray Spectra; Etude Comparative des Methodes Utilisees pour la Resolution de Spectres Gamma Complexes au Moyen d'un Ordinateur; Sravnitel'noe izuchenie metodov razresheniya sostavnykh gamma-spektrov pri pomoshchi schetno-reshayushchego ustrojstva; Estudio Comparativo de los Metodos Aplicados para Resolver Espectros Gamma Complejos Mediante Calculadoras

Energy Technology Data Exchange (ETDEWEB)

DeHaan, A. Jr.; Leventhal, L.; Benson, P. [Tracerlab, Richmond, CA (United States)

1965-10-15

'a resolution; 2. Resolution du pic sans elimination; 3. Etablissement d'un ensemble d'equ'ations lineaires simultanees du meme ordre que le nombre de radionucleides presents dans le melange et solution de ces equations; 4. Evaluation des concentrations non connues par la methode des moindres carres, classique ou ponderee; 5. Combinaison des methodes statistiques et des methodes des moindres carres utilisant la regression lineaire multiple progressive, en s'efforcant d'integrer des processus decisifs dans l'analyse. Pour chaque methode d'analyse appliquee a des melanges de radionucleides, les auteurs fournissent une estimation statistique des erreurs de mesure de la concentration des radionucleides. (author) [Spanish] La resolucion de mezclas complejas de emisores gamma se ha simplificado gracias al empleo de espectrometros gamma muy perfeccionados en asociacion con calculadoras numericas. En la actualidad, los laboratorios pueden en general disponer de estos instrumentos o tener facilmente acceso a ellos. En la memoria se examinan los metodos seguidos en el laboratorio de los autores para determinar la concentracion de cada radionuclido emisor gamma contenido en muestras de precipitaciones radiactivas, y se comparan los resultados obtenidos por los diferentes metodos matematicos aplicables a las muestras compuestas. Los datos proporcionados por las calculadoras se comparan con los resultados obtenidos por analisis radioquimico de la muestra. Se han analizado muestras binarias por los metodos mencionados, operacion que se extendio despues a las mezclas integradas por muchos componentes. Se ha elaborado un metodo de computo que normaliza los espectros gamma para reducir al mfnimo el efecto de la deriva del espectrometro a largo plazo, y representa el espectro segun un sistema de coordenadas, una de las cuales es la energia. Se han investigado los efectos de un 'fotopico imprevisto', de una componente de intensidad cero y de picos superpuestos en la resolucion segun los

Soluciones analiticas AL problema de jets con velocidad de eyeccion variable EN EL tiempo.

Science.gov (United States)

Canto, J.; Raga, A. C.; D'Alessio, P.

1998-11-01

Se presenta un nuevo metodo que permite resolver de manera exacta y analitica las ecuaciones que describen un jet hipersonico con velocidad de eyeccion variable en el tiempo. El metodo se basa en consideraciones sencillas de conservacion de momento para las superficies de trabajo que se forman en el interior del jet. Como ejemplo, se presentan soluciones para jets con variacion sinusoidal en la velocidad de eyeccion, y tambien para el caso de un incremento lineal en el tiempo. Estas soluciones analiticas tienen una clara aplicacion en la interpretacion de las observaciones de jets asociados a objetos Herbig-Haro.

Analysis of the indices of thermal comfort for the conditions of the Mexican Republic; Analisis de los indices de confort termico para las condiciones de la republica mexicana

Energy Technology Data Exchange (ETDEWEB)

Fuentes Freixanet, Victor; Rodriguez Viqueira, Manuel [Universidad Autonoma Metropolitana - Unidad Azcapotzalco (Mexico)

2009-07-15

The objective of this article is to analyze different indices of thermal comfort for the Mexican Republic. Among them the Fanger (PMV and PPD) physiological methods of comfort and the new effective temperature index are included. The standard effective temperature (SET), as well as the adaptive methods of Humphreys and Nicol, Auliciems, De Dear and Brager. A comparative analysis is done of the different indices through thematic maps determined by interpolation, using a climatic data base of 700 cities obtained from the observatories and stations of the National Meteorological Service. This article pretends to establish general criteria of the thermal comfort to later define design strategies for each one of the climatic regions of the Mexican Republic. [Spanish] El objetivo de este articulo es analizar distintos indices de confort termico para la Republica Mexicana. Entre ellos se incluyen los metodos fisiologicos de confort de Fanger (PMV y PPD), el indice de nueva temperatura efectiva. La temperatura efectiva estandar (SET), asi como los metodos adaptativos de Humphreys y Nicol, Auliciems, De Dear y Brager. Se hace un analisis comparativo de los distintos indices a traves de mapas tematicos determinados por interpolacion, usando una base de datos climaticos de 700 ciudades obtenidos de los observatorios y estaciones del Servicio Meteorologico Nacional. Este articulo presenta establecer criterios generales del confort termico para posteriormente definir estrategias de diseno para cada una de las regiones climaticas de la Republica Mexicana.

Clique aqui para Decidir: As Recomendacoes Online Na Decisao de Compra dos Servicos Hoteleiros

Directory of Open Access Journals (Sweden)

Raissa Karen Leitinho Sales

2015-01-01

Full Text Available Este estudo investigou como as opinioes publicadas em sites de recomendacoes influenciam o processo de decisao de compra de servicos hoteleiros. Na coleta de dados, pelo metodo qualitativo, utilizou‑se entrevistas com internautas e consumidores que ja se sentiram influenciados pelas opinioes de outros usuarios. Os resultados indicam que as opinioes postadas atuam de forma relevante na decisao de compra de servicos hoteleiros. Os principais fatores para tornar os comentarios dos internautas referencias sao a credibilidade e a confianca que os buscadores de informacoes lhes atribuem. Identificaram‑se, ainda, os processo de compartilhamento e de busca de informacoes online dos servicos turisticos.

Non-Destructive Testing in Reactor Pressure-Vessel Fabrication; Essais non Destructifs dans la Fabrication des Caissons Etanches de Reacteurs; Nedestruktivnoe ispytanie pri izgotovlenii reaktornykh bakov vysokogo davleniya; Ensayo no Destructivo Durante la Fabricacion de Recipientes de Presion para Reactores

Energy Technology Data Exchange (ETDEWEB)

McGonnagle, W. J. [Fluids Dynamics Research, Iit Research Institute, Chicago, IL (United States)

1965-09-15

applicables. Il suggere des criteres, a la fois realistes et satisfaisants, d'acceptation et de rejet. Il expose les grandes lignes d'une procedure qui permettra au personnel charge des essais non destructifs d'accomplir sa tache de maniere appropriee au stade opportun du cycle de fabrication. Il etudie les rapports entre le groupe charge des essais non destructifs et les autres groupes de personnel intervenant dans la fabrication du caisson. (author) [Spanish] El presente trabajo tiene como finalidad esbozar brevemente un programa de control de calidad aplicado en el proyecto y construccion de un recipiente de presion para reactor, capaz de satisfacer todas las exigencias nucleares y de seguridad; asimismo se propone poner de manifiesto el papel y la importancia de los ensayos no destructivos en el logro de ese objetivo. Las fallas observadas en materiales, componentes y conjuntos de elementos, ponen de manifiesto que las actuales tecnicas de fabricacion no bastan por sf solas para garantizar en todos los casos la seguridad de servicio de los componentes criticos. Aun empleando los mejores procesos, asf como tambien metodos y tecnicas sometidas a controles apropiados, aparecen fallas y heterogeneidades. Por lo tanto, se requiere un programa adecuado y correctamente integrado de ensayos no destructivos, a fin de lograr el nivel de calidad imprescindible para el recipiente de presion de todo reactor nuclear. Los principales metodos no destructivos aplicados por los fabricantes de recipientes de presion para reactores son: inspeccion visual, radiografia y gammagraffa, ensayo ultrasonico, y empleo de particulas magneticas y de Ifquidos penetrantes. El programa de ensayos no destructivos incluye la inspeccion del material en forma de chapas, piezas forjadas, piezas coladas, revestimientos y soldaduras. Se analizan en este trabajo los problemas particulares con que tropieza el ensayo no destructivo aplicado a recipientes de presion para reactores nucleares. Se exponen y discuten

Sonochemical synthesis of a PdAg/C electrocatalyst for oxygen reduction reaction; Sintesis sonoquimica de un electrocatalizador de PdAg/C para la reaccion de reduccion de oxigeno

Energy Technology Data Exchange (ETDEWEB)

Godinez-Garcia, A.; Perez-Robles, J.F. [Centro de Investigacion y de Estudios Avanzados del IPN. Santiago de Queretaro, Queretaro (Mexico)]. E-mail: jperez@qro.cinvestav.mx; Solorza-Feria, O. [CINVESTAV-IPN, Mexico, D.F. (Mexico)

2009-09-15

The synthesis and characterization of nanocatalysts for fuel cells has been a primary line of research for the purpose of obtaining less expensive electrocatalysts with better activity. A large variety of methods exist to synthesize useful nanoparticles as electrocatalysts. Each method generates particles with a different surface morphology and, therefore, the catalytic activity usually varies depending on which is used in the synthesis. In this work, PdAg/C electrocatalysts are synthesized with high-intensity ultrasonic irradiation and compared to those obtained using a conventional method such as reduction by NaBH{sub 4}. The study of this technique is of interest because it produces highly dispersed carbon-supported nanoparticles with very clean surfaces. Each electrocatalyst was evaluated for its oxygen reduction reaction (ORR) in acid medium with cyclic voltamperometry (CV) and rotating disc electrode (RDE). The electrocatalyst was characterized with x-ray diffraction and transmission electron microscopy (TEM). The physical characterization reveals that the electrocatalyst is composed of nanometric bimetallic aggregates. An important characteristic of the PdAg/C alloy obtained using ultrasound is better activity than that obtained by reduction with NaBH{sub 4}. [Spanish] La sintesis y caracterizacion de nanocatalizadores para celdas de combustible ha sido una de las principales lineas de investigacion, con el objetivo de obtener electrocatalizadores mas baratos y con una mejor actividad. Existen una gran variedad de metodos para sintetizar nanoparticulas utiles como electrocatalizadores, cada metodo genera particulas con una morfologia superficial diferente por lo que la actividad catalitica suele variar dependiendo de cual se utilice en la sintesis. En este trabajo se sintetizan electrocatalizadores de PdAg/C con irradiacion ultrasonica de alta intensidad y se comparan con las obtenidas con un metodo convencional como es la reduccion por NaBH{sub 4}. Esta

Metodo para montaje permanente de huevos de helmintos enteroparasitos Definitive preservation of helminthic eggs

Directory of Open Access Journals (Sweden)

Victor Muñoz

1990-04-01

Full Text Available Se comunican resultados obtenidos empleando Medio de Hoyer para el montaje de huevos de helmintos enteroparásitos, destinado a preparaciones para colecciones docentes y/o de investigación. La utilización de esta técnica en muestras fecales conteniendo huevos de A. lumbricoides, T. trichiura, Uncinaria sp., Taenia sp., Diphyllobothrium sp., H. nana, H. diminuta y F. hepática, permitió la correcta observación de ellos en lecturas iniciadas a las 24 horas y mantenidas hasta 180 días después.The results using the Hoyer method for examining eggs of helminths enteroparasites are presented. This method is particularly swited for teaching and on research purposes. Using this technique in fecal sample containing eggs of A.lumbricoides, T. trichiura, Uncinaria sp., Taenia sp., Diphyllobothrium sp., H. nana, H. diminuta and F. hepática allowed the correct identification of then after 24 hours up to 180 days after the samples were obtained.

Estudio de la distribución de los tiempos de residencia en un reactor tubular para la hidrólisis de lecitina de soja con fosfolipasa A2 inmovilizada

Directory of Open Access Journals (Sweden)

Zaritzky, N.

2001-10-01

efectuada mediante el uso de enzima fosfolipasa A2 inmovilizada, liberando un ácido graso de la posición C-2 de los fosfolípidos para obtener un producto enriquecido en lisolecitinas. La reacción enzimática sigue una cinética de primer orden cuando las concentraciones de sustrato están dentro del rango: 6,34 10-3 y 19,0 10-3M. El valor de la constante de velocidad es: k= 9,88 10-2 min-1 cuando la enzima está inmovilizada sobre alúmina. Se construyó un reactor que permite la circulación del fluido a través del soporte. El soporte seleccionado fue alúmina en consideración a sus buenas propiedades mecánicas y a su bajo costo. Fue analizado el comportamiento del flujo en el reactor, y cuanto este se aparta del modelo ideal de flujo en pistón, inyectando una solución de 1 % NaCl (trazador en forma de inyección por impulso. La medición de la conductividad de la solución efluente resultó adecuada para la determinación de los tiempos de residencia. El sistema mostró comportamiento lineal. Se analizaron los tiempos de residencia en el reactor utilizando tres diferentes volúmenes de flujo para diferentes arreglos de soporte y material inerte. Se calcularon las fracciones no convertidas en el reactor y se observaron las diferencias a la salida en comparación a las de un reactor de flujo en pistón, precisamente porque se generan canalizaciones y cortocircuitos en la columna. La conversión máxima resultó para las más altas concentraciones de sustrato y para el menor flujo de alimentación. El módulo de dispersión resultó bastante mayor que el límite que introduce una curva gaussiana para el caso en el cual el grado de suposición de alta dispersión fue corregido. El reactor alcanzó un comportamiento similar al de un reactor de mezcla completa y se concluyó que son importantes el grado de retromezcla, la formación de remolinos y zonas de redistribución de material.

Simulation of molecular transitions using classical trajectories

Energy Technology Data Exchange (ETDEWEB)

Donoso, A.; Martens, C. C. [University of California, California (United States)

2001-03-01

In the present work, we describe the implementation of a semiclassical method to study physical-chemical processes in molecular systems where electronic state transitions and quantum coherence play a dominant role. The method is based on classical trajectory propagation on the underlying coupled electronic surfaces and is derived from the semiclassical limit of the quantum Liouville equation. Unlike previous classical trajectory-based methods, quantum electronic coherence are treated naturally within this approach as complex weighted trajectory ensembles propagating on the average electronic surfaces. The method is tested on a model problem consisting of one-dimensional motion on two crossing electronic surfaces. Excellent agreement is obtained when compared to the exact results obtained by wave packet propagation. The method is applied to model quantum wave packet interferometry, where two wave packets, differing only in a relative phase, collide in the region where the two electronic surfaces cross. The dependence of the resulting population transfer on the initial relative phase of the wave packets is perfectly captured by our classical trajectory method. Comparison with an alternative method, surface hopping, shows that our approach is appropriate for modelling quantum interference phenomena. [Spanish] En este trabajo se describe la implementacion de un metodo semiclasico para estudiar procesos fisicos-quimicos en sistemas moleculares donde las transiciones entre estados electronicos y las coherencias cuanticas juegan un papel predominante. El metodo se basa en la propagacion de trayectorias clasicas sobre las correspondientes superficies electronicas acopladas y se deriva a partir del limite semiclasico de la ecuacion cuantica de Liouville. A diferencia de metodos previos basados en trayectoria clasica, dentro de este esquema, las coherencias electronicas cuanticas son tratadas de manera natural como ensamble de trayectorias con pesos complejos, moviendose en

Development of a chromatographic method for the study of the stability and compatibility of Mexican fuel oils; Desarrollo de un metodo cromatografico para el estudio de estabilidad y compatibilidad de combustoleos mexicanos

Energy Technology Data Exchange (ETDEWEB)

Blass Amador, Georgina; Panama Tirado, Luz Angelica [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1992-11-01

compatibility of fuel oil mixes. [Espanol] En Mexico, la mayoria de la energia electrica producida proviene del uso de combustibles residuales pesados conocidos como combustoleos los cuales han sufrido disminuciones en la calidad debido a una combinacion de factores, entre los que destaca el de los cambios en el proceso de refinacion. Es necesario desarrollar metodos que sean capaces de indicar la inestabilidad (formacion de sedimento o incremento en viscosidad durante el almacenamiento o calentamiento) o incompatibilidad (formacion de sedimento al mezclar dos o mas) de los combustoleos utilizados en las centrales termoelectricas. El objetivo de este trabajo fue el desarrollar una prueba alternativa para el estudio de la compatibilidad y/o estabilidad de combustoleos mexicanos empleando cromatografia de liquidos de alta resolucion (CLAR) y asi poder determinar aspectos estructurales del combustoleo que determinan su estabilidad. Dado que la formacion de sedimentos ocurre cuando el poder disolvente del combustible es inadecuado para mantener los asfaltenos en solucion, es importante conocer la medida del poder disolvente o aromaticidad del diluyente; asi pues, la primera parte de este trabajo se centro en la determinacion del perfil de compuestos aromaticos de los diluyentes de los combustoleos, la otra parte se dedico a la determinacion del perfil de distribucion de los pesos moleculares de los asfaltenos presentes en los combustoleos. Los perfiles de la fraccion aromatica, asi como los de distribucion de pesos moleculares se determinaron empleando cromatografia de liquidos, en la que se empleo una variedad de columnas y de disolventes. Se efectuo una combinacion de pruebas de rutina tales como contenido de asfaltenos, equivalencia de tolueno, viscosidad, etcetera con el fin de obtener correlaciones con el metodo cromatografico desarrollado. En este articulo se discute solo la seccion correspondiente a la obtencion del perfil de contenidos de aromaticos de los combustoleos. Se

Actualización del sistema SCADA y de control para los reactores MQ5 y MQ6 de la planta de Pinturas Condor, Sherwin Williams Ecuador

Directory of Open Access Journals (Sweden)

Jonathan Reinoso

2013-12-01

Full Text Available El presente documento describe la actualización del sistema SCADA para los reactores MQ5 y MQ6 de la planta de Pinturas Condor mediante el software Intouch y la actualización del sistema de control del reactor MQ5 implementado en un controlador lógico programable (PLC de marca SCHNEIDER, además de la arquitectura de control realizada en el proyecto. El sistema SCADA y de control de los reactores permiten la visualización y control de los datos y variables más relevantes durante las diferentes fases de producción de resinas en los reactores MQ5 y MQ6.

Metodología para resolver la ecuación del transporte con el código de ordenadas discretas TORT en el reactor IPEN/MB-01

OpenAIRE

Bernal, A.; Abarca Giménez, Agustín; Barrachina Celda, Teresa María; Miró Herrero, Rafael; Verdú Martín, Gumersindo Jesús

2013-01-01

La resolución de la Ecuación del Transporte Neutrónico en estado estacionario en reactores nucleares de tipo piscina, se consigue normalmente por medio de 2 métodos numéricos diferentes: Monte Carlo (estocástico) y Ordenadas Discretas (determinista). El método de las Ordenadas Discretas resuelve la Ecuación del Transporte Neutrónico para un conjunto de determinadas direcciones, obteniendo un conjunto de ecuaciones y soluciones para cada dirección, donde la solución para cada dirección es el f...

Um metodo para modelagem de exceções em desenvolvimento baseado em componentes

OpenAIRE

Patrick Henrique da Silva Brito

2005-01-01

Resumo: Devido a grande popularização do Desenvolvimento Baseado em Componentes (DBC), ele vem sendo empregado inclusive no desenvolvimento de sistemas computacionais críticos. O emprego do DBC na construção de sistemas confiáveis evidencia a necessidade de se desenvolver componentes de software que sejam robustos e que possuam uma garantia maior do seu funcionamento correto. Tratamento de exceções é uma técnica bastante conhecida para a verificação e tratamento de erros em sistemas de softwa...

METODO PROPUESTO PARA LA PREDICCION DE TENSIONES ADMISIBLES EN ZAPATAS CIMENTALDAS EN ARENAS

OpenAIRE

DIAZ SEGURA; EDGAR GIOVANNY; DIAZ SEGURA; EDGAR GIOVANNY

2010-01-01

La evidencia experimental ha demostrado que la mayoría de las metodologías actuales no son capaces de predecir las cargas de diseño de zapatas en suelos no cohesivos con un grado aceptable de precisión. En el presente estudio se propone un método sencillo y realista para estimar la carga de diseño de zapatas rígidas cimentadas en arenas sometidas a una carga estática vertical. Se adoptó como criterio de diseño el propuesto por Terzaghi et al. (1996), basado en limitar a 16 mm e...

METODO PROPUESTO PARA LA PREDICCION DE TENSIONES ADMISIBLES EN ZAPATAS CIMENTADAS EN ARENAS

OpenAIRE

DIAZ SEGURA, EDGAR GIOVANNY; DIAZ SEGURA, EDGAR GIOVANNY

2010-01-01

La evidencia experimental ha demostrado que la mayoría de las metodologías actuales no son capaces de predecir las cargas de diseño de zapatas en suelos no cohesivos con un grado aceptable de precisión. En el presente estudio se propone un método sencillo y realista para estimar la carga de diseño de zapatas rígidas cimentadas en arenas sometidas a una carga estática vertical. Se adoptó como criterio de diseño el propuesto por Terzaghi et al. (1996), basado en limitar a 16 mm el asentamiento ...

Modeling and identification for the adjustable control of generation processes; Modelado e identificacion para el control autoajustable de procesos de generacion

Energy Technology Data Exchange (ETDEWEB)

Ricano Castillo, Juan Manuel; Palomares Gonzalez, Daniel [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1990-12-31

The recursive technique of the method of minimum squares is employed to obtain a multivariable model of the self regressive mobile mean type, needed for the design of a multivariable, self-adjustable controller self adjustable multivariable. In this article the employed technique and the results obtained are described with the characterization of the model structure and the parametric estimation. The convergency velocity curves are observed towards the parameters` numerical values. [Espanol] La tecnica recursiva del metodo de los minimos cuadrados se emplea para obtener un modelo multivariable de tipo autorregresivo de promedio movil, necesario para el diseno de un controlador autoajustable muitivariable. En el articulo, se describe la tecnica empleada y los resultados obtenidos con la caracterizacion de la estructura del modelo y la estimacion parametrica. Se observan las curvas de la velocidad de convergencia hacia los valores numericos de los parametros.

Modeling and identification for the adjustable control of generation processes; Modelado e identificacion para el control autoajustable de procesos de generacion

Energy Technology Data Exchange (ETDEWEB)

Ricano Castillo, Juan Manuel; Palomares Gonzalez, Daniel [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1989-12-31

The recursive technique of the method of minimum squares is employed to obtain a multivariable model of the self regressive mobile mean type, needed for the design of a multivariable, self-adjustable controller self adjustable multivariable. In this article the employed technique and the results obtained are described with the characterization of the model structure and the parametric estimation. The convergency velocity curves are observed towards the parameters` numerical values. [Espanol] La tecnica recursiva del metodo de los minimos cuadrados se emplea para obtener un modelo multivariable de tipo autorregresivo de promedio movil, necesario para el diseno de un controlador autoajustable muitivariable. En el articulo, se describe la tecnica empleada y los resultados obtenidos con la caracterizacion de la estructura del modelo y la estimacion parametrica. Se observan las curvas de la velocidad de convergencia hacia los valores numericos de los parametros.

Uses and updating of the Benders method in the integer-mixed programming in the planning of the electric power systems expansion; Usos y actualizacion del metodo de Benders en la programacion entera-mixta y en la planeacion de la expansion de los sistemas electricos de potencia

Energy Technology Data Exchange (ETDEWEB)

De la Torre Vega, Eli

1997-04-01

of some potential improvements that the proposed method has. [Espanol] En el primer capitulo se presenta la deduccion de los cortes de Benders partiendo de las propiedades de la dualidad. Tambien se presentan las propiedades de los cortes de Benders asi como el algoritmo inicial de Benders para resolver cualquier problema de programacion lineal entera-mixta. En el segundo capitulo, se presenta el problema de la planeacion de la expansion de los medios de generacion y transmision en un sistema electrico de potencia, las distintas estructuras de la programacion matematica a que da lugar y como se puede adaptar el metodo de Benders a estas. En el tercer capitulo se presentan las aportaciones teoricas de este trabajo: a) Como inicializar el problema maestro para aprovechar la experiencia adquirida despues de haber resuelto un problema similar, de modo que se pueda resolver mas eficientemente, la sucesion de problemas de programacion lineal entero-mixtos que surgen al resolver el problema de la planeacion de la expansion de los medios de generacion y transmision en un sistema electrico de potencia. b) Como generar un problema maestro cuya solucion optima continua corresponda al optimo continuo del problema entero-mixto, de modo que la busqueda de soluciones enteras se realice en la vecindad del optimo continuo. c) Como generar una solucion entera, cercana al optimo continuo del problema entero-mixto, que tenga mucha probabilidad de ser factible, y que quizas sea la solucion optima entera, en un tiempo menor al que se requiere para resolverlo en forma exacta. Ademas, se presentan otras ideas que se le pueden incorporar al metodo de Benders. A fin de mostrar la efectividad de las ideas propuestas, en el capitulo 4 se presentan los resultados obtenidos al resolver varios problemas usando: 1. El metodo de Benders in actualizacion, 2. El metodo de Ramificacion y Acotamiento, 3. La actualizacion de Benders al agregar restricciones y 4. La actualizacion de Benders al considerar

A GENERAL ANALYTICAL APPROACH FOR PRESTRESSED AND NON-PRESTRESSED CONCRETE BEAM-COLUMNS REINFORCED WITH BONDED AND UNBONDED COMPOSITES: (I THEORY

Directory of Open Access Journals (Sweden)

J. A. RODRIGUEZ-GUTIÉRREZ

2011-01-01

Full Text Available Se propone un metodo de analisis que determina la respuesta a corto y largo plazo de vigas columnas de hormigon pretensado y no pretensado reforzado con cualquier combinacion de barras de FRP y/o placas, barras de acero, torones pretensados adheridos o no adheridos. El metodo de analisis propuesto incluye vigas y columnas revestidas con telas FRP y tubos de FRP rellenos de hormigon. Tambien se incluyen los efectos de la rigidez a traccion, fluencia y retraccion del hormigon y la relajacion de la armadura de acero pretensado. Se adoptan los modelos de Vecchio y Collins [1] y de Popovics [2, 3] en las relaciones esfuerzo-deformacion del hormigon a traccion y a compresion, respectivamente. Las relaciones esfuerzo-deformacion de los refuerzos de acero y de FRP se modelan mediante lineas rectas multiples (esto es, lineas poligonales. El metodo de las fibras (modificado es utilizado para calcular los diagramas momento-curvatura a diferentes niveles de la carga axial aplicada (es decir, las curvas M-P-¿Ö y el metodo de Gauss de integracion (para la suma de las contribuciones de los fibras paralelas al eje neutro para calcular las rotaciones laterales y deflexiones a lo largo de la luz de la viga-columna. La validez del modelo propuesto y las ecuaciones correspondientes se pusieron a prueba con datos experimentales disponibles en la literatura tecnica (vease la parte II de esta publicacion.

Determination of the Effectiveness of Control Rods in the VVER Reactor Fuel Assemblies; Determination de l'Efficacite des Barres de Reglage dans les Ensembles Combustibles du reacteur VVER; Opredelenie ehffektivnosti reguliruyushchikh sterzhnej v sborkakh reaktora VVEHR; Determinacion de la Eficacia de las Barras de Control en los Conjuntos de Elementos Combustibles del Reactor VVER

Energy Technology Data Exchange (ETDEWEB)

Semenov, V. N.; Lunin, G. L.; Komissarov, L. V.; Kamyshan, A. N.; Halizev, V. I.; Andrianov, G. Ja.; Voznesenskij, V. A.; Kuz' micheva, V. A.; Lebedev, V. I. [Ordena Lenina Institut Atomnoj Energii Im. I.V. Kurchatova, Moskva, SSSR (Russian Federation)

1964-06-15

The paper describes experiments done in homogeneous mock-ups of the fuel assemblies from the VVER Reactor (at one level of enrichment) to determine the effectiveness of absorbing systems comprising shim fuel assemblies or water cavities and of absorbing rods clad in jackets made of differing materials. The paper also gives data on some experiments that have been done in mock-ups of assemblies with differing levels of enrichment. These experiments make it possible to verify the methods used in calculation and to evaluate the prospects of using them for heterogeneous reactors. (author) [French] Le memoire decrit les experiences qui ont ete faites pour determiner l 'efficacite des absorbants contenus dans les barres de compensation, l'effet cavitaire et l 'efficacite des absorbants gaines de materiaux divers, au moyen d'assemblages homogenes de cartouches de combustible du reacteur VVER (reacteur de puissance ralenti et refroidi a l 'eau ayant le meme taux d'enrichissement. On y trouve en outre des donnees sur certaines experiences executees a l 'aide d'assemblages de cartouches de combustible taux d'enrichissement differents. Ces travaux permettent de verifier la methode de calcul et d'evaluer ses possibilites d'application aux reacteurs non homogenes. (author) [Spanish] Se describen en la memoria experimentos para determinar la eficacia de los materiales absorbentes contenidos en las barras de compensacion, el efecto de cavitacion y la eficacia de los materiales absorbentes revestidos de diversos materiales, realizados con ayuda de los conjuntos homogeneos de elementos combustibles del reactor VVER (reactor de potencia moderado y refrigerado por agua) con un solo grado de enriquecimiento. Ademas, se exponen datos sobre los experimentos efectuados con ayuda de conjuntos de grados de enriquecimientos; variados. Tales experimentos permiten verificar el metodo de calculo teorico, utilizad o y evaluar la posibilidad de aplicarlo a los reactores no homogeneos. (author

Diseño de un reactor de transesterificación para la obtención de biodiesel a partir de aceites vegetales

OpenAIRE

MARSET GIMENO, DAVID

2016-01-01

[ES] En este proyecto se pretende que el alumno realice el diseño, montaje y puesta a punto un reactor de transesterificación de laboratorio para la obtención de biodiesel a partir de aceites vegetales, utilizando catálisis básica homogénea. Paralelamente se definirán las técnicas analíticas a emplear para el control de la calidad de los aceites de partida y el seguimiento de los productos de reacción. A partir de los resultados experimentales se realizará el diseño y estimación económica...

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

Energy Technology Data Exchange (ETDEWEB)

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

2006-07-01

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

Research reactors: a tool for science and medicine; Reactores de investigacion: herramientas para la ciencia y la medicina

Energy Technology Data Exchange (ETDEWEB)

Ordonez, Juan [Investigacion Aplicada SE (INVAP), San Carlos de Bariloche (Argentina)

2001-07-01

The types and uses of research reactors are reviewed. After an analysis of the world situation, the demand of new research reactors of about 20 MW is foreseen. The experience and competitiveness of INVAP S.E. as designer and constructor of research reactors is outlined and the general specifications of the reactors designed by INVAP for Egypt and Australia are given.

A Comparison of Radioisotope Methods for River Flow Measurement; Comparaison de methodes radioisotopiques de mesure du debit des cours d'eau; Sravnenie radioizotopnykh metodov izmereniya rechnykh stokov; Comparacion de los metodos radioisotopicos para medir el caudal de los rios

Energy Technology Data Exchange (ETDEWEB)

Clayton, C. G.; Smith, D. B. [Wantage Research Laboratory Atomic Energy Research Establishment Wantage, Berks (United Kingdom)

1963-08-15

consequent d'aucune utilite comme indicateur dans la mesure du debit d'un cours d'eau s'il n'est pas employe avec un entraineur; mais avec un entraineur, on observe une amelioration marquee de l'exactitude des resultats. {sup 24}Na et {sup 82}Br n'ont accuse aucune adsorption a des distances bien superieures a celles qui sont necessaires pour assurer une brassage lateral; dans la riviere la plus lente, toutefois, on a note, a plus de 660 m du point d'injection, une certaine diminution de {sup 24}Na. Le memoire contient quelques observations sur la dispersion laterale et longitudinale qui, a une certain degre, influe sur l'application generale des methodes radioisotopiques a la mesure du debit des cours d'eau. Les auteurs parviennent a la conclusion que les trois methodes donnent des resultats satisfaisants. Ils preferent, en fin'de compte, la methode d'echantillonnage continue, car elle donne les resultats les plus exacts pour, la quantite minimum d'indicateur. (author) [Spanish] Los autores han empleado los procedimientos de dilucion, muestreo continuo y recuento total en un estudio comparativo de los metodos radioisotopicos de medicion de caudales fluviales en el arroyo Aylburton, en Gloucestershire, y en los rios Usway Burn y Alwin, en Northumberland. Se trata de tres tios de caracteristicas geologicas diferentes, cuyos caudales oscilan entre 2,5 1/s y 3 m{sup 3}/s. En todos los metodos de medicion de caudales que emplean indicadores, la distancia entre el punto en que se efectua la medicion y el punto en que se anade el indicador tiene que ser suficientemente grande para que se produzca una mezcla lateral completa. Por otra parte, no debe ser excesiva para evitar que la dipersion longitudinal supere cierto valor o que se pierda parte del indicador por adsorcion en el lecho fluvial. La dispersion depende de las caracteristicas hidraulicad de la corriente y es inherente al metodo. Por su parte, la adsorcion depende del indicador elegido y de las caracteristicas geologicas

Subsurface microbial ecology. Epi fluorescence direct counts; Ecologia microbica del sottosuolo: metodo di conta diretta in epifluorescenza

Energy Technology Data Exchange (ETDEWEB)

Barra Caracciolo, A.; Silvestri, C.; Creo, C.; Izzo, G. [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dipt. Ambiente

1998-07-01

To the aim of recognize the importance of microorganisms in affecting or even determining the fate of xenobiotics in the subsurface environment evaluating bacteria concentration in a subsurface ecosystem, the report discusses a soil sample treatment method which has been developed for epi fluorescence direct counting with DAPI. [Italian] Lo studio discute un metodo di trattamento del campione per la conta diretta in epifluorescenza con un marcatore selettivo per il DNA, il DAPI, al fine di quantificare la concentrazione batterica del sottosuolo e studiare il ruolo dei microrganismi nella biodegradazione delle molecole esogene, ancora poco indagato.

Measurements with a Pulsed and Modulated Source in a Reactor; Mesures au Moyen d'une Source Pulsee et Modulee dans un Reacteur; Izmereniya v reaktore s pomoshch'yu impul'snogo i moduliruemogo is tochnika; Mediciones Efectuadas en Reactor con una Fuente Pulsada y Modulada

Energy Technology Data Exchange (ETDEWEB)

Rotter, W. [Centre d' Etude de l' Energie Nucleaire, Mol (Belgium)

1965-10-15

generateur: le temps de mesure est donc minimum. Les observations enregistrees sur bande perforee sont depouillees par une calculatrice numerique. (author) [Spanish] Los laboratorios de investigacion Philips han construido un generador neutronico de flujo variable en funcion del tiempo. Con una serie de mediciones efectuadas en el reactor BRO2 en estado subcrftico, se ha demostrado su utililidad practica en la esfera de la fisica de los reactores. El funcionamiento del generador es muy flexible debido a su alta estabilidad, a la posibilidad de variar bruscamente la intensidad neutronica, y de pulsar el flujo o modularlo de manera sinusoidal. El generador permite determinar la reactividad ({rho} = {Delta}k/{beta}) y la vida media de los neutrones ( Script-Small-L /{beta}) segun varios metodos independientes. Es posible proceder a una comparacion exacta de esos metodos, dado que pueden aplicarse sin modificar las condiciones de medicion. El autor ha calculado los siguientes valores: a) p, sobre la base de los neutrones retardados, por reduccion instantanea del flujo neutronico; b) p, sobre la base de los neutrones inmediatos, por impulsos neutronicos; c) Script-Small-L /{beta}, combinando 1) y 2), cuando 0, 5 dolares < {rho} < 2 dolares, y d) Script-Small-L /{beta}, sobre la base de la funcion de transferencia del reactor para una fuente modulada. En la memoria se examinan las funciones de transferencia correspondientes a un oscilador de reactividad y a una fuente de modulacion sinusoidal. Se demuestra que es posible medir Script-Small-L /{beta}, cuando 0,1 dolar < {rho} < 10 dolares utilizando una fuente modulada. Por el mismo metodo se obtiene tambien la reactividad partiendo de la razon neutrones inmediatos/neutrones retardados para una frecuencia optima que es practicamente independiente de los datos relativos a los neutrones retardados y del cociente Script-Small-L /{beta}. La precision estadistica de cada metodo puede aumentarse acumulando un gran numero de ciclos en el

Some Non-Destructive Testing Methods Applicable to Sintered Materials; Quelques Methodes d'Essais Non Destructifs Applicables aux Materiaux Frittes; Nekotorye metody nedestruktivnykh ispytanii, primenimye k spechennym materialam; Algunos Metodos de Ensayo No Destructivo Aplicables a los Materiales Sinterizados

Energy Technology Data Exchange (ETDEWEB)

Labusca, Elena; Mirion, I.; Andreescu, N.; Alecu, M.; Biscoveanu, I. [Institut de Physique Atomique, Bucarest (Romania)

1965-10-15

solides frittes, a l'aide de la metallographie et de la microscopie electronique. Ces methodes mettent en evidence l'homogeneite de la structure, les dimensions et l'orientation des grains, la presence de defauts divers (inclusions, pores) et revolution meme du processus de frittage, y compris la formation des cristaux, la croissance granulaire, etc. Dans quelques cas, on peut combiner l'examen microscopique a des essais de microdurete. Cet examen de la structure microcristalline represente l'une des methodes principales de controle qualitatif des materiaux frittes, et ne peut etre remplace par aucun autre moyen d'investigation. 2. Controle du degre de consolidation, qui determine essentiellement la qualite des materiaux frittes. Ce controle est effectue par la mesure de quelques proprietes, telles que la conductibilite electrique et thermique, en correlation avec la densite, etant donne que la conductibilite des materiaux frittes est directement porportionnelle au degre de frittage. On a essaye aussi une methode adequate de controle de la porosite; on a obtenu des donnees experimentales interessantes, surtout au point de vue de la porosite libre, laquelle est susceptible aux inclusions gazeuses. Le memoire contient des donnees experimentales concernant l'application de ces methodes de controle a quelques materiaux frittes interessants pour la technologie nucleaire. (author) [Spanish] Teniendo en cuenta la estructura granular especifica de los materiales sinterizados, elaborados a partir de polvos, cuyo proceso de consolidacion se desarrolla en funcion del tratamiento de sinterizacion, los autores han estudiado algunos metodos para verificar el grado de sinterizacion y controlar ciertas propiedades. Entre los metodos no destructivos utilizados, se mencionan en la presente memoria: 1. Examen de la estructura cristalina de los solidos sinterizados por metalografia y microscopfa electronica. Estos metodos ponen de manifiesto el giado de homogeneidad estructural, la dimension

Modificação do metodo "kindling" para obtenção de status epilepticus experimental em ratos

Directory of Open Access Journals (Sweden)

Carlos J. Reis de Campos

1980-03-01

Full Text Available Foi utilizada em nova espécie animal (ratos, uma modificação do método "kindling", introduzida por Taber e col. (1977 para obtenção de status epilepticus experimental. Para isso foram implantados mediante cirurgia estereotáxica, eletrodos duplos, torcidos no hipocampo dorsal de 12 ratos machos albinos. Esses animais foram submetidos, após uma semana de pós-operatório, a 1 segundo de estimulação elétrica de baixa intensidade em forma intermitente, um estímulo por minuto durante 2 horas, desenvolvendo-se em prazo de 30 minutos um estado de epilepsia eletrográfica e comportamental duradoura. Vários padrões de descargas epilépticas eletrográficas foram observados bem como manifestações convulsivas tônico-clônicas. Os animais que foram submetidos a novas sessões de estimulação após 7 e 14 dias mostraram aumento de atividade epiléptica demonstrando uma modificação plástica do hipocampo do rato submetido a estimulação elétrica a qual perdura no tempo. O método permite a obtenção de "kindling" em tempo bem mais curto (horas, comparativamente às técnicas anteriormente descritas (dias, tornando-se um promissor modelo de epilepsia para testes de drogas anticonvulsivantes e para o estudo dos mecanismos fisiopatológicos e bioquímicos envolvidos na descarga epiléptica.

Development of PARA-ID Code to Simulate Inelastic Constitutive Equations and Their Parameter Identifications for the Next Generation Reactor Designs

International Nuclear Information System (INIS)

Koo, Gyeong Hoi; Lee, J. H.

2006-03-01

The establishment of the inelastic analysis technology is essential issue for a development of the next generation reactors subjected to elevated temperature operations. In this report, the peer investigation of constitutive equations in points of a ratcheting and creep-fatigue analysis is carried out and the methods extracting the constitutive parameters from experimental data are established. To perform simulations for each constitutive model, the PARA-ID (PARAmeter-IDentification) computer program is developed. By using this code, various simulations related with the parameter identification of the constitutive models are carried out

Development of technologies for nuclear reactors of small and medium sized; Desarrollo de Tecnologias para Reactores Nucleares de pequeno y medio tamano

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-08-15

This meeting include: countries presentations, themes and objectives of the training course, reactor types, design, EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, ATMEA 1, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR, React ores enfriados con metales liquidos, Hs, Prism,Terra Power, Hyper ion, appliance's no electric as de energia, Generation IV Reactors,VHTR, Gas Fast Reactor, Sodium Fast Reactor, Molten salt Reactor, Lfr, Water Cooled Reactor, Technology Assessment Process, Fukushima accident.

Aplicação de metodos de otimização para o calculo do equilibrio quimico e de fases combinados para processos com gas de sintese

OpenAIRE

Consuelo Cristina Gomes Silva

2008-01-01

Resumo: Essa pesquisa consiste em aplicar métodos de otimização global para o cálculo do equilíbrio químico e de fases combinados para misturas com gás de síntese. O gás de síntese tem grande interesse industrial, pelas inúmeras possibilidades de produção de diversos compostos químicos. Dessa forma, é fundamental conhecer as condições termodinâmicas que favoreçam a obtenção de determinado produto. A aplicação de métodos de otimização global é de grande interesse para a determinação do equilíb...

Metaheurística MOAMP para un problema de recogida de basuras en áreas rurales

Directory of Open Access Journals (Sweden)

Caballero Fernández, Rafael

2009-01-01

Full Text Available RESUMEN Se propone un modelo bi-objetivo para la recogida de basuras en áreas rurales.. Los objetivos son la reducción de los costes de transporte de los vehículos de recogida y la mejora del nivel de servicio. Concretamente la calidad va a estar relacionada con la frecuencia de recogida en los diferentes puntos. Se propone un algoritmo para obtener un conjunto de soluciones no dominadas a este problema. Este metodo está basado en la estrategia denominada MOAMP y consigue obtener conjuntos numerosos y densos de soluciones no-dominadas.ABSTRACT In this work a biobjective model for recollecting dusty bins in rural areas is proposed in a period. The two objectives considered are: minimizing costs (that is transport costs and improving level service. Specifically the level of service or quality depends on frequency of recollecting in every point over different points. Also an algorithm is proposed in order to obtain a set of not dominated solutions close to efficiency curve. This algorithm is based in MOAMP strategy. It shows to obtain a dense set of not-dominated solutions.

Modelo estadístico para la simulación de reactores de lixiviación ácida

Directory of Open Access Journals (Sweden)

Mónica Hernández-Rodríguez

2015-05-01

Full Text Available Se desarrolló un modelo estadístico que permite simular el comportamiento de la batería de reactores en el proceso de lixiviación ácida y determinar a partir de parámetros operacionales la eficiencia de extracción de níquel y de cobalto. Al realizar las pruebas de validación se obtuvo que más del 95% de los valores determinados por el modelo están dentro de los límites de confianza estimados, sin embargo se observa una tendencia a que el valor calculado se encuentre por debajo del reportado, lo cual se cumple para el 65,79 % y el 61,84 %, de los datos, con relación a la eficiencia de extracción de níquel y cobalto, respectivamente. Se realizó un análisis de sensibilidad paramétrica para establecer la influencia de las variables de operación en el sistema. Se concluye que la sensibilidad depende del nivel de operación del sistema y que las variables más significativas en todos los niveles son: la concentración de magnesio y la de níquel así como la relación ácido - mineral

Colorectal cancer: before and after PET-CT; Cancer colorrectal: antes y despues de PET-TC

Energy Technology Data Exchange (ETDEWEB)

San Roman, Jose [Hospital Italiano, Buenos Aires (Argentina). Servicio de Diagnostico por Imagenes

2008-07-01

The author makes reference to the fundamental and growing role of images in the detection, localization, staging and control in colorectal cancer therapy. He points out the main reasons why the combined method PET-CT has meant to a great progress in diagnostic imaging and compares its diagnostic capacity and cost-benefit with other methods. Also, he makes a brief review of some technical aspects. [Spanish] El autor senala el rol central y creciente de las imagenes para la deteccion, localizacion, estadificacion y control del tratamiento del CCR. Menciona las razones principales por las que el metodo combinado PET-TC ha significado un progreso mayor para el diagnostico por imagenes y compara su capacidad diagnostica y costo-beneficio con los metodos establecidos. Tambien hace un repaso breve de algunos aspectos tecnicos.

Análisis de la sensibilidad paramétrica en reactores de lecho fijo

Directory of Open Access Journals (Sweden)

Hermes A. Rangel Jara

1992-05-01

Full Text Available En la búsqueda de los reactores de lecho fijo que ofrezcan una seguridad y permitanmaximizar la conversión -para una determinada longitud del reactor- se analizan los tres arreglos más comunes (paralelo, contracorriente y temperatura constante, con respecto al medio de enfriamiento. Como casos de aplicación se estudiaron la oxidación parcial de O-xileno para producir anhidrido ftálico como producto único en el primer caso y teniendo en cuenta reacciones paralelas y consecutivas para el segundo caso. El sistema de ecuaciones variacionales originado a partir del sistema de ecuaciones diferenciales del modelo del reactor sirve para solucionar el problema de valores de frontera y adicionalmente la sensibilidad paramétrica de las diferentes variables. Mediante un análisis de la sensibilidad paramétrica y de otras ventajas resultantes el arreglo en paralelo puede considerarse como la alternativa más atractiva.

Analytic computation of the quantum levels of a two-dimensional hydrogenic donor in the presence of a constant magnetic field of arbitrary strength

Energy Technology Data Exchange (ETDEWEB)

Villalba, Victor M.; Pino, Ramiro [Instituto Venezolano de Investigaciones Cientificas, Caracas (Venezuela)

2001-03-01

In this article we review different techniques for computing the energy spectrum of 2 D hydrogenic donors and two-electron quantum dots in the presence of a constant, magnetic field perpendicular to the plane of the electron. We compute the 1S, 2P- and 3D- energy levels via a scaled variational mixed-bases method. We compare our results with those obtained with the shifted 1/N method. [Spanish] En el presente articulo se exhiben distintos metodos para calcular el espectro de energia de donores hidrogenicos y puntos cuanticos con dos electrones en presencia de un campo magnetico constante perpendicular al plano del electron. Se calculan los niveles de energia 1S, 2P- y 3D- con ayuda del metodo variacional de bases mixtas con escalamiento. Comparamos nuestro resultados con los obtenidos con ayuda del metodo 1/N con corrimiento.

Evaluación del comportamiento hidrodinámico como herramienta para optimización de reactores anaerobios de crecimiento en medio fijo

Directory of Open Access Journals (Sweden)

Andrea Pérez

2008-01-01

Full Text Available Las condiciones de flujo no ideal en los reactores afectan su desempeño; las causas comunes son cortos circuitos, zonas muertas y recirculación interna por corrientes cinéticas y/o de densidad. En este estudio se optimizó el diseño de un filtro anaerobio a escala real que trata las aguas residuales del proceso de extracción de almidón de yuca, el cual presentaba problemas de represamiento y bajas eficiencias de remoción. La evaluación del comportamiento hidrodinámico inicial mostró la presencia de flujo dual (32% flujo pistón - FP y 37% mezcla completa - CM, zonas muertas (20% y ausencia de cortos circuitos; adicionalmente, la modelación del reactor indicó un grado de dispersión elevado y un comportamiento tendiente a un reactor CM en serie de dos unidades. Con base en estos resultados, se implementaron dos modificaciones en el diseño del reactor: falso fondo y tubería perforada para evacuación de biogás, las cuales permitieron incrementar la fracción de FP (44%, reducir la fracción de zonas muertas (15%, disminuir el Índice de Dispersión (ID e incrementar la tendencia del reactor a un CM en serie de tres unidades, lo que aumentó el tiempo de retención hidráulico (TRH real de 9,6 a 10,2 horas (TRH teórico 12 horas y las eficiencias teóricas de remoción de 73 a 78%.

Nuclear instrumentation for research reactors; Instrumentacion nuclear para reactores nucleares de investigacion

Energy Technology Data Exchange (ETDEWEB)

Hofer, Carlos G.; Pita, Antonio; Verrastro, Claudio A.; Maino, Eduardo J. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Unidad de Actividades de Reactores y Centrales Nucleares. Sector Instrumentacion y Control

1997-10-01

The nuclear instrumentation for research reactors in Argentina was developed in 70`. A gradual modernization of all the nuclear instrumentation is planned. It includes start-up and power range instrumentation, as well as field monitors, clamp, scram and rod movement control logic. The new instrumentation is linked to a computer network, based on real time operating system for data acquisition, display and logging. This paper describes the modules and whole system aspects. (author). 2 refs.

Simulação numérica aplicada para avaliar o efeito da pré-polimerização no comportamento de reatores tubulares Numerical simulation to evaluate the effect from pre-polymerization on the behavior of tubular reactors

Directory of Open Access Journals (Sweden)

André L. Nogueira

2007-09-01

Full Text Available O presente estudo utiliza um modelo matemático fenomenológico para simular um sistema de polimerização contínuo em dois estágios. Este sistema é composto por um reator contínuo tipo tanque agitado (CSTR, para pré-polimerização do monômero (primeiro estágio, associado em série a um reator tubular para conduzir a reação até elevados valores de conversão (segundo estágio. Um modelo detalhado, considerando variações axiais e radiais, assim como operação não-isotérmica, foi utilizado para simular o comportamento do reator tubular em diferentes situações. Um modelo de caracterização também foi desenvolvido para fornecer estimativas do peso molecular médio e do índice de polidispersão do polímero. Os resultados mostram que reações de polimerização conduzidas em sistemas contínuos de dois estágios fornecem um polímero com propriedades menos heterogêneas do que um polímero obtido em um sistema reacional composto por apenas um reator tubular. Além disso, quanto maior a viscosidade da mistura reacional alimentada ao reator tubular, mais homogêneo é o polímero obtido.The present study uses a phenomenological model to simulate a continuous, two-stage polymerization process. This system is composed by a continuous stirred tank reactor (CSTR for monomer pre-polymerization (first stage, connected to a tubular reactor (second stage to carry out the reaction up to high conversion values. A comprehensive non-isothermal 2-D model (axial and radial variations was used to predict the tubular reactor behavior. A polymer characterization model was also developed to provide estimates of the polymer average molecular weight and polydispersity. According to the results, polymerization reactions carried out in a continuous two-stage system provide a polymer with less heterogeneous properties than the one obtained in a single tubular reactor. Besides, it is possible to produce a more homogeneous polymer increasing the viscosity

Estudio hidrodinámico de reactores empacados de flujo ascendente(REFA)

OpenAIRE

Díaz Marrero, Miguel Ángel; Dueñas Moreno, Jaime; Cabrera Díaz, Ania

2014-01-01

En el presente trabajo se emplean las técnicas de estímulo respuesta para estudiar los modelos de flujos de dos reactores tipo REFA, con volúmenes de 3,4 y 6 litros respectivamente, usando tiempos de retención hidráulicos y trazadores diferentes en ambos. Se determinaron las curvas de concentración contra tiempo para ambos reactores y se realizó el análisis comparativo de un grupo de relaciones entre los diferentes tiempos que se obtuvieron en los gráficos. Se aplica con los mismos experiment...

Estudio de criticidad del reactor MSBR con SCALE

OpenAIRE

Criado Martín, Alejandro Fernando

2011-01-01

El presente proyecto final de carrera se enmarca en el convenio de colaboración entre el Consejo de Seguridad Nuclear (CSN) y la Universitat Politècnica de Catalunya (UPC) para la realización de proyectos en el ámbito de la seguridad nuclear y la protección radiológica. El proyecto estudia la criticidad del reactor Molten Salt Breeder Reactor (MSBR) mediante el código de simulación SCALE. El MSBR es un reactor de sales fundidas concebido y diseñado por ORNL, con una composic...

The Economical Application of Non-Destructive Testing to Reactor Components, Especially Jacket Tubing; Avantages Economiques du Controle Non Destructif des Pieces de Reacteurs, Notamment des Tubes de Gainage; Ehkonomicheskoe primenenie nedestruktivnykh ispytanij dlya reaktornykh komponentov, v chastnosti obolochechnykh trub; Aplicacion en Condiciones Economicas de Ensayos No Destructivos a las Piezas de los Reactores, en Especial a los Tubos de Revestimiento

Energy Technology Data Exchange (ETDEWEB)

Renken, C. J. [Metallurgy Division Argonne National Laboratory Argonne, IL (United States)

1965-10-15

. Des indications erronees de defauts contribuent directement a l'accroissement du prix de revient des pieces; c'est pourquoi le memoire contient une evaluation de ces effets pour les methodes ultrasonores et electromagnetiques en ce qui concerne plusieurs sources frequentes d'indications erronees. L'auteur expose l'experience acquise au Laboratoire national d'Argonne dans l'application de ces methodes a des quantites relativement importantes de tubes d'origines diverses, du point de vue du prix minimum du controle parunite de longueur de tube. Cette partie du memoire resume egalement l'experience acquise au Laboratoire d'Argonne avec les methodes electromagnetiques et impulsions les plus recentes. L'auteur discute l'influence primordiale, mais generalement trop negligee, du diametre et de l'epaisseur du tube sur le prix de revient du controle. Comme la question de l'economie du controle est etroitement liee et celle des defauts admissibles, l'auteur expose les normes appliquees a cet egard au Laboratoire d'Argonne. Enfin, il enumere les obstacles pratiques et theoriques qui empechent de reduire le prix de revient du controle des pieces et il s'efforce de faire une prevision des reductions possibles de c e prix grace aux methodes ultiasonores et electromagnetiques. (author) [Spanish] Ademas de las caracteristicas que debe reunir el modelo ideal de reactor, hay que aplicarle metodos de ensayo que no tengan caracter destructivo. Como otros ideales, es probable que este no se alcance nunca. Para cualquier modelo en el que el costo sea un factor importante, la cuestion de la posibilidad de ensayar las piezas en condiciones economicas debe plantearse al mismo tiempo que la de la posibilidad de fabricacion. En la presente memoria se resellan algunas observaciones al respecto y se examina la importancia que ha de atribuirse a los metodos de ensayo no destructivo al establecer las especificaciones correspondientes. El fabricante ademas es responsable de la utilizacion de

Diseño de un modelo para la optimización de los procesos en el mantenimiento programado aplicado al equipo Casa 212 de la Fuerza Aérea Colombiana

Directory of Open Access Journals (Sweden)

José Enrique Sarmiento

2006-01-01

Full Text Available Este proyecto es el resultado de Ia busqueda constante de un mejoramiento continuo de los procesos que garantizan la calidad total en el mantenimiento aeronautico, concebdo y desarrollado para ser aplicado en el mantenimiento basico de 100 horas o 1A del equipo C-212-300 asignado al grupo técnico del Comando Aéreo de Combate No.2. Es así como se hace un recuento acerca de Ia historia y Ia evolución del mantenimiento aeronautico, Ia normatividad y los metodos de trabajo, el estudio de tiempos y movimientos empleados actualmente, para garantizar Ia eficiencia y seguridad en Ia aviación comercial y militar. De ahí, que se visitó la Base Aerea del Ejercito del Aire Español, SATENA y la Base Aerea de Apiay de Ia Fuerza Aerea Colombiana, quienes t ienen dentro de sus flotas el equipo C-212.

Estudio de ecotoxicidad y biodegradabilidad de ibuprofeno en un reactor aerobio de lodos activos de mezcla completa

OpenAIRE

Zambrano Flores, Johanna Vanessa

2013-01-01

Es importante conocer qué efectos de toxicidad aguda y crónica presenta el Ibuprofeno, así como los posibles efectos tóxicos que a largo plazo puedan producirse sobre la biomasa activa presente en las plantas depuradoras de aguas residuales contaminadas con este compuesto. Para ello, se realizó el montaje de un reactor aerobio de fangos activos de mezcla completa. Primero, se alimentó al reactor únicamente con agua residual sintética para el arranque y operación estacionaria del reactor. Desp...

Protocolo Nacional para la Evaluacion de Disturbios en Suelos Forestales; Volumen II: Metodos complementarios, estadística y recoleccion de datos

Science.gov (United States)

Deborah S. Page-Dumroese; Ann M. Abbott; Thomas M. Rice

2013-01-01

Este documento-El Volumen II: Métodos complementarios, estadística y recolección de datos- define las bases, los métodos estadísticos y de almacenamiento de datos de un Protocolo Nacional para la Evaluación de Disturbios en Suelos Forestales. Esta guía técnica proporciona las bases de un método consistente, con definiciones comunes, para generar datos de alta calidad,...

New tools for subsurface imaging of 3D seismic Node data in hydrocarbon exploration =

Science.gov (United States)

Benazzouz, Omar

A aquisicao de dados sismicos de reflexao multicanal 3D/4D usando Ocean Bottom NODES de 4 componentes constitui atualmente um sector de importancia crescente no mercado da aquisicao de dados reflexao sismica marinha na industria petrolifera. Este tipo de dados permite obter imagens de sub-superficie de alta qualidade, com baixos niveis de ruido, banda larga, boa iluminacao azimutal, offsets longos, elevada resolucao e aquisicao de tanto ondas P como S. A aquisicao de dados e altamente repetitiva e portanto ideal para campanhas 4D. No entanto, existem diferencas significativas na geometria de aquisicao e amostragem do campo de ondas relativamente aos metodos convencionais com streamers rebocados a superficie, pelo que e necessario desenvolver de novas ferramentas para o processamento deste tipo de dados. Esta tese investiga tres aspectos do processamento de dados de OBSs/NODES ainda nao totalmente resolvidos de forma satisfatoria: a deriva aleatoria dos relogios internos, o posicionamento de precisao dos OBSs e a implementacao de algoritmos de migracao prestack 3D em profundidade eficientes para obtencao de imagens precisas de subsuperficie. Foram desenvolvidos novos procedimentos para resolver estas situacoes, que foram aplicados a dados sinteticos e a dados reais. Foi desenvolvido um novo metodo para deteccao e correccao de deriva aleatoria dos relogios internos, usando derivadas de ordem elevada. Foi ainda desenvolvido um novo metodo de posicionamento de precisao de OBSs usando multilateracao e foram criadas ferramentas de interpolacao/extrapolacao dos modelos de velocidades 3D de forma a cobrirem a extensao total area de aquisicao. Foram implementados algoritmos robustos de filtragem para preparar o campo de velocidades para o tracado de raios e minimizar os artefactos na migracao Krichhoff pre-stack 3D em profundidade. Os resultados obtidos mostram um melhoramento significativo em todas as situacoes analisadas. Foi desenvolvido o software necessario para o

Efecto neutralizador del extracto acuoso de Dracontium loretense (JERGÓN SACHA sobre la actividad letal del veneno de Bothrops atrox

Directory of Open Access Journals (Sweden)

Amanda Lovera

2006-07-01

Full Text Available Objetivo: Determinar la capacidad del extracto acuoso D. loretense (jergon sacha para neutralizar la actividad letal del veneno de la serpiente B. atrox. Materiales y metodos: Se realizo el screening fitoquimico del extracto acuoso del bulbo desecado de D. loretense, se calculo la dosis letal 50(DL50 para el extracto y el veneno de B. atrox. Luego se realizaron enfrentamientos de diferentes dosis de extracto y veneno inyectadas intraperitonealmente en ratones, previa incubacion, para calcular la dosis eficaz 50% (DE50 del extracto para neutralizar el efecto letal del veneno por el metodo de Probits. Resultados: El analisis fitoquimico del extracto permitio identificar compuestos fenolicos, taninos, saponinas, proteinas, terpenoides y esteroides. No sobrevivio ningun raton que recibio el veneno sin D. loretense, y no fallecio ninguno al que se le dio solo el extracto acuoso de D. loretense. Se determino la DE50 en 91,15 µg/raton del extracto para neutralizar 2DL50 del veneno. Se encontro que a mayor dosis del veneno de B.atrox se necesito menores dosis del extracto acuoso de D. loretense. Conclusiones: el extracto acuoso de D. loretense neutraliza la actividad letal de veneno de B. atrox. Es necesario realizar estudios que permitan identificar los metabolitos del extracto que tienen esta accion.

Application of heating in dex in Los Humeros geothermal reservoir; Comportamiento de los indices de calentamiento en el yacimiento geotermico de los Humeros

Energy Technology Data Exchange (ETDEWEB)

Aragon, Alfonso; Arellano, Victor M; Izquierdo, Georgina; Garcia, Alfonso; Barragan, Rosa Maria; Verma, Mahendra P [Instituto de Investigaciones Electricas, Temixco, Morelos (Mexico); Pizano, Arturo [Comision Federal de Electricidad, Los Humeros (Mexico)

2000-12-01

Reservoir engineering uses several methodologies to evaluate reservoir information characteristics, which in one well vary with time during its production life. One of the methods widely used is the pressure analysis by stimulating the reservoir through cold water injection. For this case, the temperature is used as stimulating parameter and the resultant perturbation is analyzed for the formation intervals in order to determine reservoir permeability and thickness. This method requires a set of temperature logs taking a different stability time. The heating index is calculated from the temperature gradient with time. The index correlated with drilling parameters such as the circulation lost volume, lithology, drilling speed, et cetera. It is used identify interesting reservoir characteristics for production and injections purposes. The method is applied on wells: Br-2 from Broadlands, New Zealand; and H-11, H-31 and H-33 from Los Humeros, Mexico. The results indicate the usefulness of this method in evaluating geothermal reservoirs. [Spanish] La ingenieria de yacimientos dispone de diversas tecnicas para la evaluacion de las caracteristicas de los espesores de la formacion en un pozo, cuyo comportamiento cambia a largo de las diferentes etapas de su vida productiva. Uno de los metodos ampliamente utilizados es el comportamiento de la presion a traves de estimulos suministrados al yacimiento. Haciendo una analogia de la presion, para el caso de inyeccion de agua fria, se utiliza la temperatura como estimulo y se analizan los disturbios que esta provoca en algunas secciones de la formacion, a partir de lo cual es factible determinar intervalos permeables en el yacimiento. El metodo requiere de un par de perfiles de temperatura registrados a diferente tiempo de reposo del pozo. Con las diferencias de temperatura respecto al tiempo, se calcula el indice de calentamiento el cual se correlaciona con los parametros disponibles, contenidos durante la perforacion, como son

Computational package for the dynamic analysis of synchronous generators and their controls; Paquete computacional para el analisis de generadores sincronos y sus controles

Energy Technology Data Exchange (ETDEWEB)

Perez Guillen, Jesus Artemio

1997-12-31

conjunto de simuladores de los elementos que integran el subsistema de generacion. El desarrollo de la interfaz grafica se realizo con programacion orientada a objetos utilizando la libreria de clases para aplicaciones en medio ambiente Windows, proporcionada por el compilador de Borland C++, generando un conjunto de menus y ventanas de dialogos que integran un medio ambiente de simulacion interactivo y versatil. El paquete contiene modelos matermaticos de tercero, cuarto, quinto y sexto orden para generadores sincronos de polos lisos y polos salientes; incluye los modelos matematicos de los sistemas de excitacion DC1A, AC1A y ST1A de la clasificacion del IEEE; modelos de turbinas termica e hidraulica con gobernador de velocidad; se incluye un modelo matematico para el estabilizador de sistema de potencia y los efectos de la saturacion magnetica en los generadores sincronos. La solucion de las ecuaciones diferenciales puede realizarse por cuatro metodos de integracion numerica. Euler, Euler mejorado y Runge Kutta de segundo y cuarto orden. Tambien se incluyen algoritmos para la generacion grafica del diagrama fasorial, curva de capacidad y curva de saturacion de la maquina sincrona. Se presentan resultados de simulaciones para verificar la influencia en la respuesta dinamica del sistema de los metodos numericos de integracion, del modelado de la maquina sincrona, de los sistemas de excitacion, del estabilizador del sistema de potencia y de la saturacion magnetica del generador sincrono. Con la integracion de la interfaz grafica, el conjunto de simuladores para los distintos elementos del sistema de generacion de potencia indicados y el conjunto de herramientas de analisis grafico se obtiene un paquete de computo que puede ser util para la ensenanza e investigacion de la dinamica de los generadores sincronos y sus controles.

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

Energy Technology Data Exchange (ETDEWEB)

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

1992-12-31

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

Valoracion economica ambiental de la calidad del aire por emisiones industriales en la ciudad de quevedo,ecuador

OpenAIRE

Espol; Cabrera Casillas, Elvis Antonio; Lozano Mendoza, Pedro Harrys

2017-01-01

El objetivo principal del estudio es realizar una valoracion economico ambiental por la mejora de la calidad del aire en quevedo, para esto se elaboro un escenario hipotètico utilizando el metodo de valoracion contingente en su formato dicotomico doble. Guayaquil CAMBIO CLIMATICO

Conhecimentos de adolescentes sobre Doenças Sexualmente Transmissíveis: subsídios para prevenção Conocimientos de adolescentes sobre Enfermedades Sexualmente Transmisibles: subsidios para la prevención Teenagers' knowledge of Sexually Transmitted Diseases: strategies for prevention

Directory of Open Access Journals (Sweden)

José Roberto da Silva Brêtas

2009-12-01

Full Text Available Objetivo: Identificar o conhecimento de adolescentes sobre as formas de transmissão e prevenção das Doenças Sexualmente Transmissíveis. Metodos: envolveu 920 adolescentes entre 10 e 19 anos de idade eos dados foram obtidos por meio de um questionário estruturado. Resultado: os resultados demonstraram que a principal fonte para obtenção de informações sobre o assunto foi o professor; as Doenças Sexualmente Transmissíveis não são totalmente desconhecidas para os adolescentes do estudo, sendo a AIDS a mais conhecida.Objetivo: Identificar el nivel de conocimiento de adolescentes sobre las formas de transmisión y prevención de las EST. Métodos: Envolvió 920 adolescentes entre 10 y 19 años de edad, los datos fueron obtenidos por medio de un cuestionario estructurado. Resultados: Los resultados demostraron que la principal fuente para obtención de informaciones sobre el asunto fue el profesor; las Enfermedades Sexualmente Transmisibles no son totalmente desconocidas para los adolescentes del estudio, siendo el SIDA la más conocida.Objective: To identify teenager's knowledge of transmission and prevention of sexually transmitted diseases (STD. Methods: A sample of children and teenagers aged between 10 and 19 years participated in the study. Data were collected through a structured questionnaire developed for the study. Results: The findings suggested that the main source of information on Sexually Transmitted Diseases was the participants' school teacher. Sexually transmitted diseases are not entirely unknown by the participants in the study, with AIDS the most notorious.

DINÁMICA DE UN REACTOR DE BIOPELÍCULA ANAEROBIA TIPO INTERCAMBIADOR DE CALOR (RBAIC

Directory of Open Access Journals (Sweden)

Carlos Ramiro Escalera Vásquez

2005-01-01

Full Text Available Las características dinámicas de un reactor de biopelícula anaerobio tipo intercambiador de calor (RBAIC, usado para el tratamiento de aguas residuales de melazas, fueron estudiadas experimentalmente. Se realizaron experimentos para estudiar la respuesta del reactor a las sobrecargas orgánicas. También se estudiaron los efectos de los cambios de temperatura de las paredes calientes y las temperaturas ambientales, sobre la eficiencia del reactor, bajo condiciones de estado estacionario. Se demostró que el RBAIC es estable ante la ocurrencia de sobrecarga orgánica. Se concluyó que existe una separación de fases microbianas dentro del reactor, en condiciones normales de operación. Es decir, las bacterias acidogénicas predominan en la masa líquida recirculante y las heteroacetogénicas y metanogénicas lo hacen en la biopelícula adherida a las paredes calientes de transferencia de calor, lo cual implica que los cambios de la temperatura de la pared afectan de mayor manera a la eficiencia de remoción, que los cambios de temperatura del entorno. El RBAIC es una configuración  novedosa, con características energéticas favorables para el tratamiento de aguas residuales de la industria alimenticia.

Application of the identification methods from Hilbert and Prony to the study of oscillatory phenomena in electrical power systems; Aplicacion de los metodos de identificacion de Hilbert y Prony al estudio de fenomenos oscilatorios en sistemas electricos de potencia

Energy Technology Data Exchange (ETDEWEB)

Andrade Soto, Manuel Antonio

2002-10-15

In the present thesis work the application of identification techniques is investigated based on methods of spectral analysis to the study of the instantaneous characteristics of signals obtained by means of digital simulation of the dynamic behavior of the power system. The study focuses on the perspectives developed from two different approaches of analysis: the use of lineal methods of spectral analysis and the use of methods of non-lineal analysis, based on the concept of an analytical signal. The developed tools are applied to the study of two phenomena of electromechanical origin of different characteristics in complex power systems. A comparison between the results obtained is performed for these techniques and the possibility of its application is discussed for the problem of on-line identification in power systems. [Spanish] En el presente trabajo de tesis se investiga la aplicacion de tecnicas de identificacion basadas en metodos de analisis espectral al estudio de las caracteristicas instantaneas de senales obtenidas mediante simulacion digital del comportamiento dinamico del sistema de potencia. El estudio se centra en las aproximaciones desarrolladas desde dos enfoques distintos de analisis: la utilizacion de metodos lineales de analisis espectral y la utilizacion de metodos de analisis no lineal, basados en el concepto de una senal analitica. Las herramientas desarrolladas se aplican al estudio de dos fenomenos de origen electromecanico de caracteristicas distintas en sistemas complejos de potencia. Se hace una comparacion entre los resultados obtenidos por estas tecnicas y se discute la posibilidad de su aplicacion al problema de identificacion en linea en sistemas de potencia.

Proposta de metodo de gerenciamento de processos administrativos para organizações prestadoras de serviços

OpenAIRE

Benigno Roberto Zaki

2009-01-01

Resumo: Desde a metade do século XX e neste início do século XXI, as empresas buscam aumentar a produtividade e melhorar a qualidade de seus produtos e serviços. Para uma organização, muito mais do que a liderança no seu mercado de atuação é a sua capacidade de se manter competitiva. A busca da vantagem competitiva perante o mercado está em satisfazer as expectativas do cliente e implementar com êxito uma série de exigências em termos de eficiência no processo produtivo. O desenvolvimento des...

Tele-asistencia y tele-alarma para adultos mayores: experiencias preliminares en Mexico

Directory of Open Access Journals (Sweden)

Liliana Giraldo-Rodriguez

2013-08-01

Full Text Available OBJETIVO Analizar el efecto de un programa piloto de tele-asistencia y tele-alarma en la autopercepción del estado de salud de los adultos mayores y conocer la satisfacción y aceptación del programa. METODOS Estudio transversal que incluyó entrevistas a 378 adultos mayores, 294 cuidadores/familiares y 53 profesionales de la salud, realizado en la Ciudad de México en 2010. Variables sociodemográficas, de autopercepción del estado de salud, satisfacción y aceptación del programa se obtuvieron por medio de cuestionario estandarizado. Se realizó análisis descriptivo y se utilizaron pruebas no paramétricas. RESULTADOS Se observaron efectos significativos en la autopercepción del estado de salud, 6,17 (DE 17,9 p < 0,05 puntos por encima de la media. El programa tuvo una buena aceptación por parte de los adultos mayores, de sus cuidadores familiares y de los profesionales de la salud. CONCLUSIONES El programa contribuye a mantener o mejorar la calidad de vida, permite la atención preventiva y es un medio ideal para dar apoyo psicosocial a los adultos mayores.

Tratamiento de aguas industriales mediante reactor biológico de membranas

OpenAIRE

Aznar Jiménez, Antonio

2008-01-01

El Laboratorio de Ingeniería para el Tratamiento de Aguas de la Universidad Carlos III de Madrid, de investigación y servicios en el tratamiento de aguas residuales, optimiza el diseño y puesta a punto de reactores biológicos de membranas (MBR), indicados para obtener agua depurada de alta calidad y/o aumentar la capacidad de tratamiento.

Effect of temperature on two-phase anaerobic reactors treating slaughterhouse wastewater

Directory of Open Access Journals (Sweden)

Simone Beux

2007-11-01

Full Text Available The effectiveness of the anaerobic treatment of effluent from a swine and bovine slaughterhouse was assessed in two sets of two-phase anaerobic digesters, operated with or without temperature control. Set A, consisting of an acidogenic reactor with recirculation and an upflow biological filter as the methanogenic phase, was operated at room temperature, while set B, consisting of an acidogenic reactor without recirculation and an upflow biological filter as the methanogenic phase, was maintained at 32°C. The methanogenic reactors showed COD (Chemical Demand of Oxygen removal above 60% for HRT (Hydraulic Retention Time values of 20, 15, 10, 8, 6, 4, and 2 days. When the HRT value in those reactors was changed to 1 day, the COD percentage removal decreased to 50%. The temperature variations did not have harmful effects on the performance of reactors in set A.Avaliou-se a eficiência do tratamento anaeróbio de efluente de matadouro de suínos e bovinos em dois conjuntos de biodigestores anaeróbios de duas fases, operados com e sem controle de temperatura. O conjunto A, formado por um reator acidogênico com recirculação e um filtro biológico de fluxo ascendente, foi operado a temperatura ambiente e o conjunto B, formado por um reator de fluxo ascendente e um filtro biológico de fluxo ascendente, foi mantido a 32°C. Os reatores metanogênicos apresentaram remoção de DQO acima de 60 % para os TRHs de 20, 15, 10, oito, seis, quatro e dois dias. Quando o TRH destes reatores foi mudado para um dia observou-se uma queda da porcentagem de remoção de DQO para 50 %. As variações de temperatura parecem não ter prejudicado o desempenho dos reatores do conjunto A.

Características dieléctricas de diversos polímeros (PVC, EVA, HDPE, y PP) reforzados con neumáticos fuera de uso (GTR)

OpenAIRE

Mujal-Rosas, R.; Orrit-Prat, J.; Ramis-Juan, X.; Marin-Genesca, M.; Rahhali, Ahmed

2011-01-01

La masiva fabricación de neumáticos y la dificultad para su almacenamiento o eliminación constituye un grave problema medioambiental. En la actualidad, se utilizan diversos metodos para el reciclaje de los neumáticos, como por ejemplo la trituración mecánica, que separa el caucho vulcanizado del acero y las fibras, utilizandose este caucho en numerosas aplicaciones industriales como pavimentos, aislantes, calzados, etc. El presente artículo se centra en buscar una nueva aplicación para estos ...

Optimum geometry for boiler soot blowers nozzles; Geometria optima de toberas para deshollinadores de caldera

Energy Technology Data Exchange (ETDEWEB)

Espinoza Garza, Jesus; Garcia Tinoco, Guillermo J; Martinez Flores, Jose Oscar [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1990-12-31

For boiler soot blowing converging-diverging nozzles are employed, whose function is to convert thermal energy of a gas into kinetic energy to remove the deposits that adhere to the heat exchanger surfaces. In this paper are described the experimental equipment and the methods for flow, dynamic pressure, discharge velocity and air expansion factor calculation in each nozzle, as a function of its design geometry, utilizing air from a five stage centrifugal compressor. The graphic analysis of the results, concludes that the most efficient nozzles are not the ones than develop the greatest velocity, but the ones of highest dynamic pressure at the outlet. The nozzle geometry that allows obtaining the maximum dynamic air pressure at the discharge is A{sub 2}/A{sub g}=1.3676 [Espanol] Para el deshollinado de calderas se utilizan las toberas convergentes-divergentes, cuya funcion es convertir la energia termica de un gas en energia cinetica para remover los depositos que se adhieren a las superficies de intercambio de calor. En este trabajo se describen el equipo experimental y los metodos de calculo para flujo, presion dinamica, velocidad a la descarga y factor de expansion del aire en cada tobera, como funcion de su geometria de diseno. Durante la experimentacion se evaluaron siete disenos diferentes de toberas, empleando aire de un compresor centrifugo de cinco etapas. Del analisis grafico de los resultados, se concluye que las toberas mas eficientes no son las que desarrollan mayor velocidad sino las de mayor presion dinamica de la salida. La geometria de tobera que permite obtener la maxima presion dinamica del aire a la descarga es A{sub 2}/A{sub g} = 1.3676.

Optimum geometry for boiler soot blowers nozzles; Geometria optima de toberas para deshollinadores de caldera

Energy Technology Data Exchange (ETDEWEB)

Espinoza Garza, Jesus; Garcia Tinoco, Guillermo J.; Martinez Flores, Jose Oscar [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1989-12-31

For boiler soot blowing converging-diverging nozzles are employed, whose function is to convert thermal energy of a gas into kinetic energy to remove the deposits that adhere to the heat exchanger surfaces. In this paper are described the experimental equipment and the methods for flow, dynamic pressure, discharge velocity and air expansion factor calculation in each nozzle, as a function of its design geometry, utilizing air from a five stage centrifugal compressor. The graphic analysis of the results, concludes that the most efficient nozzles are not the ones than develop the greatest velocity, but the ones of highest dynamic pressure at the outlet. The nozzle geometry that allows obtaining the maximum dynamic air pressure at the discharge is A{sub 2}/A{sub g}=1.3676 [Espanol] Para el deshollinado de calderas se utilizan las toberas convergentes-divergentes, cuya funcion es convertir la energia termica de un gas en energia cinetica para remover los depositos que se adhieren a las superficies de intercambio de calor. En este trabajo se describen el equipo experimental y los metodos de calculo para flujo, presion dinamica, velocidad a la descarga y factor de expansion del aire en cada tobera, como funcion de su geometria de diseno. Durante la experimentacion se evaluaron siete disenos diferentes de toberas, empleando aire de un compresor centrifugo de cinco etapas. Del analisis grafico de los resultados, se concluye que las toberas mas eficientes no son las que desarrollan mayor velocidad sino las de mayor presion dinamica de la salida. La geometria de tobera que permite obtener la maxima presion dinamica del aire a la descarga es A{sub 2}/A{sub g} = 1.3676.

Comparison Of The Worth Of Critical And Exponential Measurements For Heavy-Water-Moderated Reactors; Valeur Relative des Mesures Critiques et Exponentielles pour l'Etude des Reacteurs Ralentis a l'Eau Lourde; Sravnenie tsennosti kriticheskikh i ehksponentsial'nykh izmerenij dlya reaktorov s tyazhelovodnym zamedlitelem; Valor Relativo de las Mediciones Criticas y Exponenciales para los Reactores Moderados por Agua Pesada

Energy Technology Data Exchange (ETDEWEB)

Graves, W. E.; Hennelly, E. J. [Savannah River Laboratory, E.I. Du Pont De Nemours and Co., Aiken, SC (United States)

1964-02-15

ultimos diez afios, en el Laboratorio de Savannah River (SRL) se ha venido trabajando con un conjunto critico de agua pesada el PDP, y con un conjunto exponencial, el SE, en forma paralela. Los autores presentan una resefla de a experiencia asi adquirida en dicho laboratorio, exponiendo los resultados y formulando recomendaciones sobre cual de los dos tipos de conjuntos resulta mas adecuado para determinados experimentos. A continuacion se exponen seis tipos de experimentos: 1. Determinacion del laplaciano en reticulados isotropicos uniformes En el SRL se han llevado a cabo extensas comparaciones entre mediciones efectuadas con ayuda de conjuntos criticos de region unica, conjuntos exponenciales, conjuntos criticos de sustitucion y del reactor PCTR (prompt critical test reactor). En el caso de los conjuntos exponenciales, aparentemente solo se tropieza con dificultades en las determinaciones del laplaciano radial. Si se llegase a salvarlas, los experimentos exponenciales podrian rivalizar sin desmedro con los criticos. Los conjuntos criticos de region unica son los que exigen mas material; les sigilen los conjuntos criticos de sustitucion y los exponenciales, cuyas necesidades son, en terminos generales, comparables; en ultimo termino figura el PCTR, cuyas exigencias son minimas. 2. Efectos anisotropicos y de cavitacion Se examinan brevemente loe experimentos realizados en el SRL con conjuntos criticos y se establecen comparaciones entre estos y los conjuntos exponenciales; en otra memoria se trata el mismo tema con mas detalle. ' 3. Evaluacion de los sistemas de control Los experimentos exponenciales se prestan para efectuar mediciones de la eficacia global, siempre que sus resultados se analicen adecuadamente. No obstante, para un estudio cabal de la distribucion general del flujo, de los gradientes de flujo, etc., se requiere un conjunto critico de gran tamano, como el PDP. 4. Coeficientes de temperatura Los experimentos exponenciales constituyen un excelente metodo

Integral physics data for fast-reactor design; Donnees de physique integrale intervenant dans les etudes de reacteur a neutrons rapides; Integral'nye fizicheskie dannye dlya raschetov reaktorov na bystrykh nejtronakh; Datos fisicos integrales para el diseno de reactores rapidos

Energy Technology Data Exchange (ETDEWEB)

Loewenstein, W B; Meneghetti, D [Argonne National Laboratory, Argonne, IL (United States)

1962-03-15

examinent ces donnees et decrivent leurs domaines d'application. Ils montrent que dans certaines analyses de spectre et d'etat critique, les resultats experimentaux et analytiques sont limites. Ils font des suggestions sur l'orientation des recherches experimentales et analytiques a venir. Elles combleraient le fosse entre la theorie et l'experience qui existe dans les systemes 'connus'. Ces propositions comprennent egalement des suggestions en vue de 'consolider' la physique de modeles theoriques de grands reacteurs surgenerateurs a neutrons rapides. (author) [Spanish] La preparacion del capitulo dedicado a la fisica de los reactores rapidos, en la segunda edicion de la publicacion 'Reactor Physics Constants' que aparecera en breve, exigio la recopilacion de los datos disponibles sobre experimentos integrales. La eleccion de los datos integrales de fisica de los reactores rapidos que se ha de incluir en esa seccion se baso en los dos criterios siguientes: a) que los datos provengan de sistemas relativamente simples que se presten para un analisis teorico sencillo; y b) que se trate de sistemas complejos que representan prototipos o maquetas que ofrecen interes general para el estudio de los reactores de potencia rapidos. Se fijo el primer criterio con la intencion de registrar los datos integrales de aquellos sistemas que tienen una utilidad mas general en la verificacion de los parametros y los procedimientos de calculo de las secciones eficaces. El segundo criterio se basa en la presentacion de los datos corrientes sobre sistemas reales de reactores de potencia reproductores rapidos. Estos son demasiado complicados para permitir un analisis teorico sencillo. Constituyen una demostracion de la complejidad del reactor real si se compara con la instalacion critica de experimentacio n mas esquematica y mas facil de analizar. Los datos fisicos integrales que intrevienen en el diseno de reactores constituyen el resultado de mediciones efectuadas en conjuntos criticos o

EFICIENCIA DE CONSORCIOS MICROBIANOS PARA TRATAMIENTO DE AGUAS RESIDUALES EN UN SISTEMA DE RECIRCULACIÓN ACUÍCOLA

Directory of Open Access Journals (Sweden)

IVÁN ANDRÉS SÁNCHEZ O

Full Text Available Los filtros biológicos viabilizan el reuso de aguas residuales (AR en sistemas de recirculación acuícola (SRA, su desempeño depende entre otros factores, del tipo de filtro, medio soporte e inóculo utilizado. Se evaluaron las eficiencias de diferentes inóculos para el tratamiento de AR provenientes del cultivo de trucha arcoiris mediante biofiltros de flujo ascendente en un SRA. Se utilizó un tanque para cultivo con control de nivel, un filtro con bolsas de lienzo para retención de sólidos y seis biofiltros de diámetro 3” con arena como medio soporte y tiempo de retención hidráulica (TRH de 11 min. Los inóculos utilizados fueron: R1-control: aguas del SRA; R2-lodos estación piscícola; R3-agua laguna aereada relleno sanitario Antanas (RSA; R4-sedimentos de acuarios; R5-lodos laguna aereada RSA; R6-lodos reactor sulfidogénico RSA. No hubo diferencias estadísticamente significativas entre los reactores para remoción de DQO, fósforo, amoniaco y nitritos, cuyas remociones medias fueron de 45,3; 15,1; 4,7 y 27,2% respectivamente. Hubo diferencias estadísticas entre reactores para remoción de color y nitratos, las mejores eficiencias fueron para: color R6:38,8% y R1:37,3%; para nitratos R5:47,3% y R6:42,8%; demostrándose la influencia de consorcios microbianos en los SRA

Seismic pressure effect on retaining walls; Presiones generadas por sismo en muros de retencion

Energy Technology Data Exchange (ETDEWEB)

Bonola, Isaac; Aviles, Javier [Instituto Mexicano de Tecnologia del Agua, Jiutepec, Morelos (Mexico)

2006-04-15

Retaining walls are auxiliary works used in different hydraulic structures. In seismically active areas, the dynamic pressures generated by the backfill must be appropriately evaluated at the design stage. Currently, a number of methods for estimating the seismic response of this type of works are available; however, most of them are simplified and not all the parameters involved have been examined. In this paper, a hybrid boundary and finite element method is presented for gravity walls in which the backfill can be represented by a horizontally layered medium. The effect of lateral extension of the backfill can be included in the model by introducing a vertical boundary coupling the movement of the backfill with that of the surrounding soil. The wave propagation analysis in the layered medium is carried out for both horizontal and vertical harmonic excitation; the latter excitation may cause important responses under certain situations. To illustrate the applicability of the proposed method, results for two numerical examples are presented: one for dry backfill and other for saturated backfill, considering in both cases the variations of dynamic properties of the soil with the depth. [Spanish] Los muros de retencion son estructuras auxiliares utilizadas en distintas obras hidraulicas. En zonas sismicas, las presiones dinamicas generadas por el relleno deben evaluarse adecuadamente en la etapa de diseno. Actualmente existen numerosos metodos para estimar la respuesta sismica de este tipo de estructuras; sin embargo, la mayoria de ellos son simplificados y no todos los parametros involucrados han sido examinados. En este trabajo se presenta un metodo hibrido de frontera y elemento finito para muros de gravedad en el que el relleno puede representarse por un medio estratificado horizontalmente. En el modelo puede incluirse el efecto de la extension lateral del relleno, introduciendo una frontera vertical que acopla el movimiento del relleno con el del suelo

Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal

OpenAIRE

Pedro, Miguel António de Morais

2012-01-01

O presente trabalho tem como objectivo avaliar economicamente e determinar a viabilidade da implementação de um reactor nuclear para produção de energia eléctrica. Faz-se uma abordagem a aspectos da energia nuclear no mundo e em particular a energia nuclear na união europeia, faz-se uma análise sobre a estrutura do sector nuclear em Espanha e o futuro da energia no mundo. É realizada uma análise sobre a energia nuclear em Portugal, são abordados aspectos como o planeamento energético, a local...

Reactor Radiation Loops as Large Gamma Sources; Boucles d'irradiation des reacteurs nucleaires utilisees comme sources gamma intenses; Radiatsionnye kontury yadernykh reaktorov kak moshchnye gamma-istochniki; Empleo de circuitos de irradiacion de los reactores como fuentes gamma de gran intensidad

Energy Technology Data Exchange (ETDEWEB)

Ryabukhina, Yu. S.

1963-11-15

primer lugar, se eligieron para la realizacion de esos circuitos las aleaciones de indio, metal liquido a temperatura ambiente. Se estudio el comportamiento de dos eutecticos de indio frente a algunos materiales de construccion y a principios de 1960 se construyo el primer circuito de prueba de indio-galio. Como iesultado de estudios ulteriores, se instalaron modelos de circuitos de indio-galio, con una actividad en el irradiador equivalente a unos 100 g de Ra, en el reactor IRT de la Academia de Ciencias de la Republica Socialista Sovietica de Georgia, asi'como un circuito de prueba de indio-galio-estafio in el canal del reactor IRT del Instituto de Energia Atomica de la Academia de Ciencias de la Union Sovietica. Por ultimo, en 1962, se instalo un circuito de trabajo de indio-galio-estano en el reactor IRT de la Academia de Ciencias de la Republica Socialista Sovietica de Latvia para efectuar irradiaciones en escala semiindustrial. La actividad maxima en el irradiador equivale a 30 000 g de Ra. La memoria consta de las siguientes partes: 1. ''Calculo de los circuitos de irradiacion''; en esta parte se resena la labor realizada en materia de metodos de calculo de los circuitos de irradiacion. 2. ''Modelo de un circuito de irradiacion deindio-galiodelreactor IRT de Tbilisi''; se describe el funcionamiento de este circuito. 3. ''Circuito de irradiacion de indio-galio-estano del reactor IRT de la Academia de Ciencias de la Republica Socialista Sovietica de Latvia'' ; se describe el funcionamiento de este circuito. 4. ''Perspectivas de desarrollo de los circuitos de irradiacion''; se describen los experimentos y circuitos y se presentan calculos que sugieren la posibilidad de construir circuitos de manganeso solido y circuitos con aleaciones liquidas de indio. (author) [Russian] Nachinaya s 1957 g. v SSSR provodilis' raboty po izucheniyu radiatsionnykh konturov. Byli razrabotany metody rascheta takikh sistem, izucheny vozmozhnosti razlichnykh gamma-nositelej. Vnachale byli

ESTUDIO COMPARATIVO DEL EFECTO DE ZHONGJI (RM3) MOXADO MAS PUNTOS REGULARES VS PUNTOS REGULARES EN PACIENTES CON NEUROPATIA DIABETICA -NO TIENE CARATULA-

OpenAIRE

LERMA GARCIA, HECTOR ALFONSO

2010-01-01

ANTECEDENTES: DESDE LA ANTIGUEDAD SE HA COMPROBADO LA EFECTIVIDAD DE LA ACUPUNTURA PARA EL TRATAMIENTO DEL DOLOR Y PARA LA DIABETES EN EL SER HUMANO. OBJETIVO: EL PRESENTE ESTUDIO TIENE COMO OBJETIVO ANALIZAR EL EFECTO DEL TRATAMIENTO DEL DOLOR Y ALTERACIONES SENSITIVAS EN PACIENTES CON NEUROPATIA DIABETICA. METODO: SE ESTUDIARON TREINTA PACIENTES CON UN DIAGNOSTICO DE NEUROPATIA DIABETICA LOS CUALES SE DIVIDIERON EN TRES GRUPOS A LOS CUALES SE LES APLICO EN EL GRUPO 1 ZHONG...

Ultra-high-speed oscillographic techniques; Techniques d'oscillographie ultra-rapide; Metody sverkhskorostnoj ostsillografii; Metodos oscilograficos ultrarrapidos

Energy Technology Data Exchange (ETDEWEB)

Abercrombie, S; Elphick, B; Foster, H [Atomic Weapons Research Establishment, Aldermaston (United Kingdom)

1962-04-15

100 {Omega}; e) Des resistances de complement a large bande, destinees a l'extraction des signaux de declenchement de la base de temps; / ) Des bases de temps fournissant des signaux de l'ordre de quelques nanosecondes et comportant des dispositifs de declenchement et de suppression du faisceau; g) Un appareil de prise de vues a grande ouverture. En conclusion, le memoire examine certaines applications de l'electronique nucleaire. (author) [Spanish] Despues de un resumen historico de los metodos de utilizacion de oscilografos para senales transitorias de alta velocidad, los autores examinan sus limites de aplicacion practica. En la memoria se pasa revista a los tubos de rayos catodicos apropiados para estos oscilografos, tomando en cuenta especialmente los tipos de deflexion por onda progresiva. En la memoria se estudian los siguientes componentes de un oscilografo completo para senales transitorias: a) Un tubo de rayos catodicos con deflexion por onda progresiva con conexion coaxial balanceada y una anchura de banda de 2 GHz; b) Un transformador inversor de fase con una impedancia caracteristica de 100 y 50 {Omega} y una anchura de banda de 1,5 kHz a 1,5 GHz; c) Resistencias de terminacion coaxial para frecuencias del orden de los GHz; d) Condensadores de acoplamiento compensados para usarlos en lineas coaxiales con frecuencias comprendidas entre 5 kHz y 3 GHz y 100 {Omega} de impedancia caracteristica; e) Atenuadores resistivos de banda ancha, para la extraccion de senales de disparo de base de tiempos; f) Bases de tiempo del orden de los nanosegundos, con dispositivos disparadores y supresores ; g) Una camara de gran apertura. Finalmente, los autores examinan las aplicaciones de estos oscilografos en la electronica nuclear. (author) [Russian] Posle kratkogo opisaniya ostsillograficheskogo metoda izucheniya sverkhskorostnykh perekhodnykh izluchenij obsuzhdayutsya prakticheskie vozmozhnosti ehtogo apparata. Daetsya obzor podkhodyashchikh katodnykh ehlektronnykh lamp

SIMULACION DE LA PUESTA EN MARCHA DE UN REACTOR DE BIOPELÍCULA ANAEROBIA TIPO INTERCAMBIADOR DE CALOR

Directory of Open Access Journals (Sweden)

Ramiro Escalera Vásquez

2009-01-01

Full Text Available Se ha desarrollado un  modelo de reactor que considera la separación de fases microbianas dentro de un reactor anaerobio tipo intercambiador de calor, donde las bacterias acidogénicas predominan en la masa líquida recirculante y las heteroacetogénicas y metanogénicas lo hacen en la biopelícula adherida a las paredes. El modelo considera también las resistencias difusionales a la transferencia de masa ocasionadas por la capa laminar y la biopelícula. También se consideran las reacciones paralelas y consecutivas propias de la degradación anaerobia de compuestos orgánicos fácilmente biodegradables, por ejemplo, residuos industriales de altas concentraciones de carbohidratos. El modelo de reactor y las ecuaciones pseudo-analíticas para la estimación de los factores de efectividad, desarrolladas para otro tipo de bioreactores anaerobios tales como lechos empacados y fluidizados, pueden utilizarse para estimar la eficacia y evaluar el funcionamiento de un Reactor de Biopelícula Anaerobia tipo Intercambiador de Calor (RBAIC . En este trabajo se ha verificado que los resultados del modelo concuerdan con los resultados experimentales de la eficacia y funcionamiento del RBAIC, dentro del periodo de puesta en marcha.

Glucose isomerization in simulated moving bed reactor by Glucose isomerase

Directory of Open Access Journals (Sweden)

Eduardo Alberto Borges da Silva

2006-05-01

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

Diseño de un microreactor para la producción de hidrógeno a partir de alcoholes

OpenAIRE

Griffon, Fabien

2006-01-01

El objetivo de este trabajo ha sido diseñar un reactor químico para producir hidrógeno a partir de etanol. El reactor funciona gracias a dos reacciones catalizadas que tienen lugar paralelamente: • el reformado: CH3-CH=O + 3 H2O → 2 CO2 + 5 H2 • la oxidación: CH3-CH2-OH + 2 O2 → 2 CO2 + 3 H2O La reacción de reformado transforma el alcohol en hidrógeno, y la de oxidación, que es muy exotermica, suministra energía para la reacción de reformado. El reactor es de paredes catalít...

The Non-Destructive Testing of Fuel Elements and Their Components for the United Kingdom Power-Reactor Development Programme; Controle Non Destructif des Elements Combustibles et de Leurs Parties Constitutives dans le Cadre du Programme de Developpement des Reacteurs de Puissance au Royaume-Uni; Nedestruktivnoe ispytanie teplovydelyayushchikh ehlementov i ikh komponentov dlya osushchestvleniya programmy soedinennogo korolevstva po razrabotke ehnergeticheskikh reaktorov; Ensayo No Destructivo de Elementos Combustibles y sus Componentes, en el Marco del Programa de Reactores de Potencia del Reino Unido

Energy Technology Data Exchange (ETDEWEB)

Mann, C. A.; Campsie, I. C. [U.K.A.E.A., Reactor Fuel Element Laboratories, Springfields, Salwick, Preston, Lancs. (United Kingdom)

1965-10-15

procede simple et peu couteux qui consiste a plonger la piece dans un liquide et a observer la formation de bulles. Enfin, les auteurs discutent l'emploi du krypton-85 comme radioindicateur. (author) [Spanish] Los procedimientos de ensayo que se exponen han sido establecidos en el Laboratorio de combustibles nucleares, como parte del programa del Grupo correspondiente, relativo a varillas de combustible para reactores de distintos tipos. La vainas de esas varillas consisten en tubos de acero inoxidable o aleaciones de circonio de 5 a 15 mm de diametro. a) Se describe la localizacion de fallas o grietas en los tubos. Inspeccion ultrasonica con dos sondas sumergidas. Los tubos se someten a un barrido helicoidal a gran velocidad en un tanque estacionario, con lo cual se observan y registran las senales que denotan la existencia de fallas. Para calibrar el sistema y comprobar su estabilidad, se usan como referencias unas ranuras practicadas por chisporroteo. En ciertos casos se recurre tambien a la inspeccion mediante corrientes de Foucault. Los dos metodos que se describen emplean un sistema de bobina anular de pasaje rapido y una bobina superficial con exploracion helicoidal. Para la seleccion de fases y filtrado de la senal de salida se una un circuito de puente, con frecuencias comprendidas entre 30 y 60 kHz. b) Se discute ademas la inspeccion de las dimensiones de tubos y pastillas. Se hace un estudio comparativo de diversos metodos mecanicos, neumaticos, nucleares y electronicos de medicion de las dimensiones de los tubos, y se explican las precauciones que han de adoptarse para impedir que estos se rayen. Se describen tecnicas para medir el diametro y la longitud de la circunferencia de las pastillas y se recomienda la comparacion de las circunferencias, en el caso de tubos delgados, como metodo mas ajustado a la realidad para el estudio de los problemas que plantea la existencia de huecos entre las paredes del tubo y las pastillas. El perfeccionamiento de equipo para

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

Energy Technology Data Exchange (ETDEWEB)

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

1966-02-15

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

L’utilizzo della ricostruzione nella comunicazione del patrimonio archeologico. L’approccio, il metodo, le finalità e alcuni spunti di discussione.

Directory of Open Access Journals (Sweden)

Elena Bacci

2010-05-01

In questo contributo si focalizza l’attenzione sulla ricostruzione grafica e virtuale del patrimonio e sulle sensazioni che la ricostruzione evoca nel fruitore del messaggio culturale. La ricostruzione si attua mediante la collaborazione tra archeologo e illustratore e costituisce un momento di verifica visiva dell’interpretazione archeologica e uno strumento di comunicazione del dato archeologico fruibile a più livelli. Ciò avviene grazie allo scambio costante di informazioni (dati scientifici e proposte di ricostruzione e il confronto che ne deriva determina i metodi e le fasi di avanzamento del progetto. Il metodo si basa sull’integrazione delle immagini 3D con il disegno tradizionale ed è finalizzato alla trasposizione del dato archeologico, in modo tale da garantire alla ricostruzione il duplice requisito di soddisfazione estetica e credibilità scientifica.

Preparation of Impervious Pyrolytic Carbon Coatings and Application to Dispersed Fuels; Preparation de revetements de carbone pyrolytique etanches - applications aux combustibles disperses; Prigotovlenie nepronitsaemogo uglerodnogo piroliticheskogo pokrytiya dlya dispergirovannogo topliva; Preparacion de revestimientos estancos de carbono piroutico: aplicacion a los combustibles nucleares dispersos

Energy Technology Data Exchange (ETDEWEB)

Auriol, A.; David, C. [Battelle Memorial Institute, Geneve (Switzerland); Fillatre, A.; Kurka, G.; Le Boulbin, E.; Rappeneau, J. [Commissariat a l' Energie Atomique (France)

1963-11-15

A method of depositing pyrolytic carbon, which adheres well to a graphite support and is gas-tight, was developed and the physical properties of the deposit were evaluated. The fluidized bed technique was used in applying this method of coating to fissile granules of uranium oxide and uranium carbide. After explaining the conditions for coating the granules, the authors examined their macrostructure, microstructure and permeability. Their behaviour at high temperature was investigated with a view to using them in a reactor. (author) [French] Une methode de deposition de carbone pyrolydque adherant bien au graphite support et etanche aux gaz a ete mise au point. Les proprietes physiques du depot ont ete evaluees. Cette methode de revetement a ete transposee a des granules fissiles d'oxyde et de carbure d'uranium en utilisant la technique du lit fluidise. Apres avoir precise les conditions de revetement de ces granules, on etudie leur macrostructure, leur microstructure, ainsi que leur permeabilite. Le comportement de ces granules a haute temperature a ete examine en vue de leur utilisation eventuelle dans un reacteur. (author) [Spanish] Los autores han elaborado un metodo para depositar carbono pirolitico que se adhiere fuertemente al soporte de grafito y es estanco a los gases. Han determinado las propiedades de dicho deposito. Este metodo de revestimiento fue aplicado a granulos fisionables de oxido y de carburo de uranio, utilizando la tecnica del lecho fluidificado. Despues de determinar las condiciones en que se efectua el revestimiento de esos granulos, los autores estudiaron su macroestructura y su microestructura, asi como su permeabilidad. Examinaron tambien su comportamiento a temperatura elevada, con miras a utilizarlos oportunamente en los reactores. (author) [Russian] Razrabotan metod osazhdeniya piroliticheskogo ugleroda, khorosho pokryvayushchego grafitovuyu osnovu s polucheniem nepronitsaemogo dlya gazov pokrytiya. Otseneny fizicheskie svojstva

Reactor de película líquida descendente para la sulfonación de ésteres metílicos con trióxido de azufre

Directory of Open Access Journals (Sweden)

Jesús Alfonso Torres Ortega

2009-09-01

Full Text Available Se realizó un conjunto de experimentos de sulfonación de dodecilbenceno (DDB y ésteres metílicos (ME derivados de la esteari- na hidrogenada de palma, con SO3 gaseoso desorbido del óleum, en un reactor de sulfonación en película líquida descendente a escala banco de 40 cm de longitud y ½ pulgada de diámetro interno. Mediante titulaciones volumétricas se determinaron los porcentajes de materia sulfonada y contenido de ácido sulfúrico, así como el porcentaje de aceite libre mediante extracciones con éter de petróleo. La funcionalidad del reactor se verificó efectuando ensayos a condiciones reportadas por Gutiérrez y cola- boradores para dodecilbenceno sulfonado (DDBS, para lo cual fueron determinadas las técnicas de análisis en el Laboratorio de Ingeniería Química (LIQ de la Universidad Nacional de Colombia, sede Bogotá, con el acompañamiento de la empresa Química Básica Colombiana (Caloto, Cauca. Finalmente, se procedió a evaluar la influencia de diferentes variables de proce- so sobre la sulfonación de la mezcla de ésteres metílicos. Los resultados obtenidos en el sulfonador se ajustaron por regresión li- neal múltiple a ecuaciones empíricas, obteniendo expresiones que muestran de forma directa el efecto de variables como la re- lación molar SO3/ME, concentración de SO3 en la corriente gaseosa y flujo másico de ME.

Guía para la certificación de servicios diagnósticos de trastornos del sueño en Colombia. (Incluye estándares para Servicios Pediátricos.

Directory of Open Access Journals (Sweden)

Natalia Londono Palacio

2014-07-01

Full Text Available RESUMEN: INTRODUCCIÓN: La Asociación Colombiana de Sociedades Científicas (ACSC; convocó al Grupo de Investigación Transdisciplinario en Trastornos del Sueño (GITTS, conformado por la Asociación Colombiana de Medicina del Sueño (ACMES, la Asociación Colombiana de Medicina Interna (ACMI® - Médicos para adultos, la Asociación Colombiana de Neumología y Cirugía de Tórax (Asoneumocito, la Asociación Colombiana de Neurología (ACN, la Asociación Colombiana de Otorrinolaringología y Cirugía Plástica Facial (ACORL y la Asociación Colombiana de Psiquiatría (ACP para que elaboraran un documento con el cual se estableciera una normatividad para la certificación voluntaria de los servicios que estudian los trastornos del sueño en Colombia. Se busca que este proceso fomente la excelencia en el diagnóstico de los trastornos del sueño. OBJETIVOS: El proceso busca definir los estándares mínimos para los servicios diagnósticos de medicina del sueño en Colombia. Aunque riguroso, el proceso ha de ser “amigable para el usuario”. Se propone a la ACMES como ente evaluador. MATERIALES Y METODOS: El proceso evalúa la organización y administración de los servicios; los empleados y la dirección; las políticas y los procedimientos; la educación y el desarrollo del personal; las instalaciones y los equipos; y el aseguramiento de la calidad. El enfoque general estuvo influenciado por programas establecidos y adoptados en otros países. Se espera que la consistencia con las guías internacionales disminuya la cantidad de trabajo necesaria para preparar la aplicación para los servicios que ya estén involucrados en los procedimientos de certificación (ej. certificación de hospitales y esto ayude a preparar el camino para la certificación en sueño. La primera fase del proceso incluye contestar un cuestionario detallado designado para evaluar qué tan preparado está el servicio para ser certificado. La autoevaluación es una

Proposed method for the hydraulic design of ski-jump energy dissipators in dam spillways considering the occurrence of scour holes downstream of the structure; Metodo propuesto para el diseno hidraulico de trampolines empleados como disipadores de energia en aliviaderos para presas, considerando la ocurrencia del cono de socavacion al pie del mismo

Energy Technology Data Exchange (ETDEWEB)

Pardo-Gomez, Rafael [Centro de Investigaciones Hidraulicas (Cuba)

2008-04-15

Ski-jump energy dissipators are widely used in hydraulic engineering because of their well-known effectiveness. Nevertheless, some uncertainty exits associated with the dimensions of the scour hole appearing downstream of the structure. This paper presents a new method for solving this problem. This method includes spillway stability checking as part of the design process and also stability checking of any other construction near the energy dissipation zone. [Spanish] Los disipadores de energia tipo trampolin tienen amplia utilizacion en la practica de la ingenieria hidraulica por su probada eficacia; sin embargo, su diseno esta sujeto a cierto grado de incertidumbre en cuanto a la prediccion de las dimensiones del cono de socavacion que habra de producirse aguas abajo de la estructura. En el presente trabajo se muestra un metodo novedoso, mediante el cual el autor soluciona el aspecto antes referido, toda vez que se incluye como parte del proceso de diseno la comprobacion de la estabilidad del propio aliviadero o de cualquier otra obra cercana a la zona de disipacion de energia.

Optimal restoration strategies based on heuristic techniques for electrical distribution networks; Estrategias de restablecimiento optimas basadas en tecnicas heuristicas para redes de distribucion electrica

Energy Technology Data Exchange (ETDEWEB)

Cruz Castrejon, J. A; Islas Perez, E; Espinosa Reza, A; Garcia Mendoza, R [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)]. E-mails: adrian.cruz@iie.org.mx; eislas@iie.org.mx; aer@iie.org.mx; rgarcia@iie.org.mx

2013-03-15

In this paper we present a proposed solution to the problem of finding alternatives to reset faults in radial distribution networks power systems. This solution uses a deterministic method based on the definition of heuristics and whose main objectives are to improve execution time and solution quality. This search is based on the alternate repetition of two stages: a stage that attempts to reset the unconnected areas and other areas trying ballasting overloaded. [Spanish] En este articulo se presenta una propuesta de solucion al problema de busqueda de alternativas de restablecimiento para fallas en redes de distribucion radiales en sistemas electricos de potencia. Esta solucion utiliza un metodo deterministico basado en la definicion de heuristicas y cuyos objetivos principales son: mejorar el tiempo de ejecucion y calidad de la solucion. Esta busqueda se basa en la repeticion alternada de dos etapas: una etapa que intenta restablecer las areas desconectadas y otra que intenta deslastrar las areas sobrecargadas.

Comparative analysis of power conversion cycles optimized for fast reactors of generation IV; Analisis comparativo de ciclos de conversion de potencia optimizados para reactores rapidos de generacion IV

Energy Technology Data Exchange (ETDEWEB)

Perez Pichel, G. D.

2011-07-01

For the study, which is presented here, has been chosen as the specific parameters of each reactor, which are today the three largest projects within generation IV technology development: ESFR for the reactor's sodium, LEADER for the lead reactor's and finally, GoFastR in the case of reactor gas-cooled.

Diseño del sistema de control de un fermentador para elaboración doméstica de cerveza

OpenAIRE

MARTÍNEZ TOMÁS, MIGUEL

2015-01-01

[ES] En el presente trabajo se pretende integrar la tecnología de controladores PIC de bajo costo conocidos como Arduino con el proceso tradicional de fabricación de cerveza de fermentación alta, de cara a la fabricación de reactores domésticos de fermentación que simplifiquen la entrada al mundo del homebrewing al público. Para ello se ha diseñado un código en el lenguaje nativo de la plataforma capaz de controlar un reactor piloto fabricado a efecto de pruebas para este proye...

Biblioteca pública y acceso a la información: retos para la sociedad de la información en Brasil y España

Directory of Open Access Journals (Sweden)

Maria Cleide Rodrigues Bernardino

2015-05-01

Full Text Available Objetivo. Presenta una discusión teórica sobre la concepción de la biblioteca como una institución democrática que se relaciona directamente con el derecho a la información, la cual garantiza el acceso al conocimiento, la cultura, la educación y el ocio de acuerdo con sus funciones y al Manifiesto de la UNESCO. Método. Este es un estudio exploratorio con análisis cualitativo, cuantitativo y metodo dialéctico. Fue realizado en bibliotecas públicas de Brasil y España, observando los aspectos de la interactividad y conectividad, como supuestos necesarios para la sociedad de la información. Resultados. El fundamento teórico se basa en estudios de Suaiden (2012; Felicia Soto (2006; Jaramillo, et al (2008 los cuales introducen cuestiones sobre la misión de la biblioteca pública y los retos para la sociedad de la información; además Cuevas-Cerveró (2009 y Cuevas-Cerveró y Simeão (2011, quien señalan la participación de la biblioteca pública como lugar de formación para el aprendizaje informacional. Conclusiones. La sociedad de la información requiere el libre acceso a la información a todos aquellos que lo necesitan en cualquier soporte o formato, incluyendo el electrónico. Sin embargo, aun tenemos desigualdades sociales responsables de la brecha digital.

Estudio preliminar para el tratamiento de lixiviados en un reactor de biodiscos

OpenAIRE

Ordóñez Losada, Paola Jimena; Betancur Pérez, Alonso

2003-01-01

El presente trabajo hace parte de un proyecto de investigación de la Universidad Nacional de Colombia Sede Manizales y EMAS (Empresa Metropolitana de Aseo S.A. E.S.P) para encontrar la mejor alternativa para el tratamiento de los lixiviados del relleno sanitario “La Esmeralda” de la ciudad de Manizales, con el fin de cumplir la legislación ambiental vigente sobre vertimientos líquidos industriales a las aguas superficiales. Se analizó en forma preliminar la aplicación de la tecnología biodisc...

Solitary pulmonary nodule: radiologic features and diagnostic approach; Nodulo pulmonar solitario: caracteristicas radiologicas y abordaje diagnostico

Energy Technology Data Exchange (ETDEWEB)

Rodriguez Cambronero, Luis Enrique

2012-07-01

A literature review is conducted on the solitary pulmonary nodule, to determine the diagnostic methods and specific characteristics. The diagnostic methods used have been: chest radiography, computed tomography, positron emission tomography and magnetic resonance imaging. The radiological features are defined: location, size, definition of contours or edges (margins), densitometric and attenuation characteristics, cavitation, air bronchogram, growth, doubling time, satellite nodules, nutrient vessels [Spanish] Una revision bibliografica es realizada sobre el nodulo pulmonar solitario, para determinar los metodos de diagnostico y caracteristicas especificas. Los metodos de diagnostico utilizados han sido: la radiografia de torax, tomografia computarizada, tomografia por emision de positrones y resonancia magnetica. Las caracteristicas radiologicas son definidas: localizacion, tamano, definicion de los bordes o contornos (margenes), caracteristicas densitometricas y de atenuacion, cavitacion, broncograma aereo, crecimiento, tiempo de duplicacion, nodulos satelite, vasos nutrientes.

Planning the expansion of electrical transmission networks with evolutionary programming; Planeacion de la expansion de redes de transmision electrica con programacion evolucionaria

Energy Technology Data Exchange (ETDEWEB)

Ceciliano Meza, Jose Luis

1997-12-31

utilizados para resolver el problema de planeacion PERTE. El funcionamiento del algoritmo de programacion evolucionaria propuesto se probo en dos redes de transmision electrica. El primer caso de prueba es un sistema el cual se conoce en la literatura. El segundo caso es un sistema representativo de la red de transmision electrica de centroamerica. Los resultados obtenidos mejoran todos los resultados mostrados al aplicar diferentes metodos heuristicos de optimizacion (algoritmos geneticos, recocido simulado y busqueda tabu) para resolver el mismo problema.

MINIMUM BRACING STIFFNESS FOR MULTI-COLUMN SYSTEMS: THEORY

Directory of Open Access Journals (Sweden)

J. DARÍO ARISTIZÁBAL-OCHOA

2011-01-01

Full Text Available Se propone un metodo que determina la rigidez minima de arrostramiento requeridos por un sistema elastico de varias columnas para lograr condiciones de pandeo sin deriva entre pisos. Las ecuaciones que evaluan la rigidez minima requerida de los arrostramientos laterales y de torsion y la carga critica de pandeo ¡§arriostrada¡¨ correspondiente para cada columna del nivel de piso se obtienen utilizando las funciones de estabilidad modificadas. Se incluyen los siguientes efectos: 1 tipos de conexiones (rigidas, semirrigidas y simples, 2 la distribucion en planta de las columnas (es decir, la orientacion de la seccion transversal y la ubicacion del centro de gravedad de cada columna, 3 deformaciones por cortante a lo largo de cada columna mediante el metodo modificado propuesto por Haringx en 1948, y 4 distribucion de la carga axial entre las columnas (es decir, el patron de carga. Los efectos de las deformaciones axial y de torsion no estan incluidos. El metodo propuesto es aplicable a estructuras 2D y 3D con conexiones rigidas, semirigidas y simple. La formulacion se presenta en este documento se basa en un trabajo previo presentado por Aristizabal-Ochoa en 2007. Se demuestra que la rigidez minima de los arrostramientos laterales y de torsion requeridos por un sistema de varias columnas depende de: 1 la distribucion en planta las columnas; 2 la variacion en altura y propiedades de la seccion transversal de las columnas; 3las rigideces a flexion y a cortante de cada columna; 4 el patron de cargas en el sistema de columnas; 5 la falta de simetria (en el patron de carga, en la disposicion de las columnas, tamanos de las columnas, y sus alturas que hacen que el pandeo combinado de torsion y flexion lateral pueden reducir la capacidad de pandeo critico de la estructura en su conjunto; y 6 las condiciones de apoyo y restricciones en el extremo superior de las columnas. El metodo propuesto se limita a sistemas multi-columna con columnas elasticas y

Study of indicators aggregation techniques for the selection of a new nuclear reactor for Mexico; Estudio de tecnicas de agregacion de indicadores para la seleccion de un nuevo reactor nuclear para Mexico

Energy Technology Data Exchange (ETDEWEB)

Barragan M, A.M.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, 04510 Mexico D.F. (Mexico)]. e-mail: ale_bar_m@yahoo.com.mx

2007-07-01

A study on several aggregation techniques that can be used as multi criteria analysis methods, like important part of the methodology developed for the selection of a nuclear reactor for Mexico is described. In an arbitrary way three reactors were selected to be compared, these they are the AP1000 (Advance Passive from 1000 MWe), the PBMR (Pebble Bed Modular Reactor) and the GT-MHR (Gas Turbine Modular Helium). The evaluation approaches were classified in three categories: Economic, Socio-political and of safety and environment. In each category they were defined the more important evaluation indicators and then it was built a matrix with those values of each reactor. The four studied aggregation methods are described: Normalization, Linear deliberation, Fuzzy Logic and AHP (Analytic Hierarchy Process). The well-known aggregation mechanisms are those that are obtained of the lineal deliberation and of the normalization, which have demonstrated to give good results before the simplicity of their use. The fuzzy logic has the advantage that it allows to manage qualitative and quantitative information simultaneously without the aggregation problems that are presented since in a conventional system the semantic pattern on that is based, it is provided by the theory of the diffuse groups that has demonstrated in other areas of the knowledge a better approach to the reality, when admitting that the nature has shades and that the decisions take in function of a wide range of possibilities and of approaches in contradictory occasions or in conflict, all equally worth. The Analytic Hierarchical Process (AHP) that consists in formalizing the intuitive understanding of a multi criteria complex problem, by means of the construction of a hierarchical model that allows the decision agent to structure the problem in visual form, giving him the form of a hierarchy of attributes (global objective of the problem, approaches and alternative). Finally, using the matrix of initiators

Analysis and evaluation of the main factors that influence the growing of the electrical power consumption in the national electrical sector, period 2000-2005; Analisis y evaluacion de los principales factores que influyen en el crecimiento del consumo de energia electrica en el sector electrico nacional, periodo 2000-2005

Energy Technology Data Exchange (ETDEWEB)

Aguilar Luna, Luis Miguel

2008-06-15

de potencia (CUFP). Ademas, se desarrolla en esta tesis las ecuaciones utilizadas en el Jacobiano del metodo Newton-Raphson, para resolver flujos de potencia incluyendo los dispositivos SIFLETCA. Se muestra diferentes aplicaciones que se tienen al instalar un dispositivo, tales como prevencion de flujos en anillo, barrera electronica, incremento en la capacidad de transmision y especificacion del flujo de potencia en lineas de transmision. Por otra parte, se desarrolla en la tesis un analisis de sensibilidades de un sistema de potencia en estado estacionario. Tambien se proponen en la tesis los parametros de control para los cuales se calcula las sensibilidades. Asimismo, se utiliza un indice de desempeno para medir el grado de congestion de un sistema electrico. Al calcular las sensibilidades se utiliza los resultados obtenidos de los flujos de potencia. Se usa 4 redes electricas para encontrar donde se debe situar cada dispositivo SIFLETCA para reducir la congestion en el sistema. Tambien, se compara el metodo desarrollado en la tesis con un metodo de sensibilidades que emplea flujos de CD para validacion y mostrar las ventajas de usar el metodo Newton en flujos de potencia.

Calculation of sensitivities in electrical systems with SIFLETCA devices; Calculo de sensibilidades en sistemas electricos con dispositivos SIFLETCA

Energy Technology Data Exchange (ETDEWEB)

Rubio Marroquin, Gabriel Omar

2004-03-15

de potencia (CUFP). Ademas, se desarrolla en esta tesis las ecuaciones utilizadas en el Jacobiano del metodo Newton-Raphson, para resolver flujos de potencia incluyendo los dispositivos SIFLETCA. Se muestra diferentes aplicaciones que se tienen al instalar un dispositivo, tales como prevencion de flujos en anillo, barrera electronica, incremento en la capacidad de transmision y especificacion del flujo de potencia en lineas de transmision. Por otra parte, se desarrolla en la tesis un analisis de sensibilidades de un sistema de potencia en estado estacionario. Tambien se proponen en la tesis los parametros de control para los cuales se calcula las sensibilidades. Asimismo, se utiliza un indice de desempeno para medir el grado de congestion de un sistema electrico. Al calcular las sensibilidades se utiliza los resultados obtenidos de los flujos de potencia. Se usa 4 redes electricas para encontrar donde se debe situar cada dispositivo SIFLETCA para reducir la congestion en el sistema. Tambien, se compara el metodo desarrollado en la tesis con un metodo de sensibilidades que emplea flujos de CD para validacion y mostrar las ventajas de usar el metodo Newton en flujos de potencia.

Study of thermophysical and thermohydraulic properties of sodium for fast sodium cooled reactors; Estudio de las propiedades termofisicas y termohidraulicas del sodio para reactores rapidos enfriados por sodio

Energy Technology Data Exchange (ETDEWEB)

Vega R, A. K.; Espinosa P, G. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, San Rafael Atlixco No. 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico); Gomez T, A. M., E-mail: a.karen.vr@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2016-09-15

The importance of liquid sodium lies in its use as a coolant for fast reactors, but why should liquid metal be used as a coolant instead of water? Water is difficult to use as a coolant for a fast nuclear reactor because its acts as a neutron moderator, that is, stop the fast neutrons and converts them to thermal neutrons. Nuclear reactors such as the Pressurized Water Reactor or the Boiling Water Reactor are thermal reactors, which mean they need thermal neutrons for their operation. However, is necessary for fast reactors to conserve as much fast neutrons, so that the liquid metal coolants that do have this capability are implemented. Sodium does not need to be pressurized, its low melting point and its high boiling point, higher than the operating temperature of the reactor, make it an adequate coolant, also has a high thermal conductivity, which is necessary to transfer thermal energy and its viscosity is close to that of the water, which indicates that is an easily transportable liquid and does not corrode the steel parts of the reactor. This paper presents a brief state of the art of the rapid nuclear reactors that operated and currently operate, as well as projects in the door in some countries; types of nuclear reactors which are cooled by liquid sodium and their operation; the mathematical models for obtaining the properties of liquid sodium in a range of 393 to 1673 Kelvin degrees and a pressure atmosphere. Finally a program is presented in FORTRAN named Thermo-Sodium for the calculation of the properties, which requires as input data the Kelvin temperature in which the liquid sodium is found and provides at the user the thermo-physical and thermo-hydraulic properties for that data temperature. Additional to this the user is asked the Reynolds number and the hydraulic diameter in case of knowing them, and in this way the program will provide the value of the convective coefficient and that of the dimensionless numbers: Nusselt, Prandtl and Peclet. (Author)

Análisis de señales de medidas mecánicas para el mantenimiento predictivo avanzado

OpenAIRE

Montalvo Martín, Cristina

2012-01-01

Para contribuir al diseño de un mantenimiento mecánico avanzado, se utilizan en esta tesis las técnicas de análisis de ruido para monitorizar las vibraciones de los internos de un reactor PWR y para vigilar la respuesta dinámica de los sensores de presión capacitivos tipo Rosemount ampliamente utilizados en la industria, sobre todo en las plantas nucleares. Para el primer caso, se han ajustado mediante un método no lineal de Breit- Wigner los espectros de resonancias obtenidos por medio de la...

Análisis de señales de medidas mecánicas para el mantenimiento predictivo avanzado

OpenAIRE

Montalvo Martín, Cristina

2010-01-01

Para contribuir al diseño de un mantenimiento mecánico avanzado, se utilizan en esta tesis las técnicas de análisis de ruido para monitorizar las vibraciones de los internos de un reactor PWR y para vigilar la respuesta dinámica de los sensores de presión capacitivos tipo Rosemount ampliamente utilizados en la industria, sobre todo en las plantas nucleares. Para el primer caso, se han ajustado mediante un método no lineal de Breit- Wigner los espectros de resonancias obtenidos por medio de la...

Analysis of the nonlinear dynamic behavior of power systems using normal forms of superior order; Analisis del comportamiento dinamico no lineal de sistemas de potencia usando formas normales de orden superior

Energy Technology Data Exchange (ETDEWEB)

Marinez Carrillo, Irma

2003-08-01

of the generator and criteria and procedures are proposed to interpret the phenomenon of modal interaction. [Spanish] Esta tesis investiga la aplicacion de metodos de analisis de perturbacion de parametros en la teoria de sistemas dinamicos no lineales, al estudio de la estabilidad de pequena senal de sistemas electricos de potencia. El trabajo se centra en la determinacion de dos aspectos fundamentales de interes en el estudio del comportamiento dinamico no lineal del sistema: la caracterizacion y cuantificacion del grado de la interaccion no lineal entre los modos fundamentales de oscilacion del sistema y el estudio de los modos con mayor influencia en la respuesta del sistema ante perturbaciones pequenas. Con estos objetivos, se propone un modelo matematico general, basado en la aplicacion de la expansion en series de potencia del modelo no lineal del sistema de potencia y la teoria de formas normales de capos vectoriales para el estudio del comportamiento dinamico del sistema de potencia. La herramienta propuesta generalizada los metodos existentes en la literatura para considerar efectos de orden superior en el modelo dinamico del sistema de potencia. Partiendo de esta representacion, se propone una metodologia para obtener soluciones analiticas de lazo cerrado y se investiga la extension de los metodos existentes para identificar y cuantificar el grado de interaccion entre los modos fundamentales de oscilacion del sistema. La herramienta desarrollada permite, a partir de expresiones analiticas de lazos cerrado, el desarrollo de medidas analiticas para evaluar el grado de estres en el sistema, la interaccion entre los modos fundamentales de oscilacion y la determinacion de fronteras de estabilidad. El desarrollo conceptual del metodo propuesto en esta tesis ofrece, por otra parte, una gran flexibilidad para incorporar modelos detallados del sistema de potencia y la evaluacion de diversas medidas de la interaccion modal no lineal. Por ultimo, se presenta los

A pulsed fast reactor; Un reacteur pulse a neutrons rapides; Impul'snyj reaktor na bystrykh nejtronakh; Reactor rapido pulsado

Energy Technology Data Exchange (ETDEWEB)

Blokhin, G. E.; Blokhintsev, D. I.; Blyumkina, Yu. A.; Bondarenko, I. I.; Deryagin, B. N.; Zajmovskij, A. S.; Zinov' ev, V. P.; Kazachkovskij, O. D.; Krasnoyarov, N. V.; Lejpunskij, A. I.; Malykh, V. A.; Nazarov, P. M.; Nikolaev, S. K.; Stavisskij, Yu. Ya.; Ukraintsev, F. I.; Frank, I. M.; Shapiro, F. Ji.; Yazvitskij, Yu. S. [Akademiya Nauk, Moscow, SSSR (Russian Federation)

1962-03-15

temperature de la reactivite. (author) [Spanish] Desde diciembre de 1960, el reactor de impulsos de neutrones rapidos IBR viene funcionando a su potencia nominal en el Instituto Central de Investigaciones Nucleares. Dicho reactor se utiliza como fuente pulsante de neutrones para realizar experimentos de fisica por el metodo del tiempo de vuelo. Se llevan a cabo determinacione s de las secciones eficaces totales, de las secciones eficaces de captura de neutrones intermedios, estudios de las interacciones de los neutrones lentos con los solidos y los liquidos y mediciones de los espectros neutronicos en distintos medios. Los autores describen las principales caracteristicas constructivas del reactor y los resultados de los estudios realizados mediante el mismo. Este reactor trabaja con arreglo a un regimen de impulsos periodicos. Los impulsos de potencia se originan cuando la parte movil del cuerpo, fijada a un disco giratorio, atraviesa la parte estacionaria con una velocidad del orden de los 230 m/s. Gracias a la presencia de una zona movible auxiliar, es posible variar la frecuencia de los impulsos de potencia entre 2,3 y 88 impulsos por segundo. La potencia media del reactor es de 1 kW y la duracion media de los impulsos, de 36 {mu}s. El reactor esta provisto de un sistema de mando y de seguridad que vela por el mantenimiento automatico de la potencia del reactor en su valor medio, asi como por su rapida detencion en caso de perturbacion del funcionamiento. Tambien posee el reactor conductores neutronicos de vacio, que se utilizan en los experimentos de tiempo de vuelo. El conducto principal tiene 1000 m de longitud. En el proceso de puesta en marcha y durante las investigaciones fisicas realizadas con el reactor, se estudio el efecto del desplazamiento de los organos de regulacion y de las partes moviles del cuerpo sobre la reactividad, se determino la duracion de los impulsos a distintos regimenes de trabajo del reactor y se estudiaron las fluctuaciones de la amplitud de

Fundamentos del metodo cientifico

Directory of Open Access Journals (Sweden)

Badii, M. H.

2004-01-01

Full Text Available El objetivo de esta obra no radica en realizar una búsqueda exhaustiva de la literatura en el tema, sino, sentar las bases del método científico, notando los aspectos filosóficos e éticos de la ciencia. Se presentan los conceptos y definiciones fundamentales relacionados con la metodología de la investigación científica. Se maneja el concepto de la toma de los datos válidos como un requisito básico en cualquier trabajo científico. Se pone a disposición del lector un modelo denominado el ECOEE que es una herramienta poderosa para establecer puntos de comparación e discusión entre los resultados de diferentes trabajos científicos. Finalmente, ofrece unas sugerencias de que hacer o no hacer en cuanto a realizar un trabajo de investigación.

A method for optimization of patient dose estimation in conventional radiology; Un metodo per l'ottimizzazione della stima della dose al paziente nella radiologia tradizionale

Energy Technology Data Exchange (ETDEWEB)

Tofani, A.; Del Corona, A. [Azienda Unita' Sanitaria Locale 6, Livorno (Italy). Unita' Ospedaliera di Fisica Sanitaria; Niespolo, A. [Azienda Ospedaliera Pisana, Pisa (Italy). Unita' Ospedaliera di Fisica Sanitaria

2000-05-01

found to depend on the average body surface, a parameter which takes into account both patient height and mass. Thus, determining the normalization factor for each projection and each view allows to estimate the absorbed dose under different geometrical conditions. The method has been verified by considering four of the most common X-ray procedures (chest AP, cervical spine LAT, lumbar spine AP and head LAT). The average error on dose estimation is about 13 %. In the very next future the method will be extended to all the projections and views of ICRP Report no. 34, and we plant to integrate the described algorithm in a computer program devoted to the automatic computation of patient dose. [Italian] Il metodo raccomandato dalla International Commission on Radiological Protection (ICRP) nel suo Report n. 34(1982) per il calcolo della dose al paziente negli esami di radiodiagnostica e' basato su dati dosimetrici tabulati ottenuti mediante simulazioni Monte Carlo su fantocci antropomorfi descritti da semplici funzioni matematiche. Nel caso del calcolo della dose per un paziente adulto, le limitazioni principali di questo metodo sono due: in primo luogo i parametri geometrici dell'esame - e in particolare la distanza fuoco-pellicola e il formato della pellicola- sono fissi, e questo rende problematico l'utilizzo dei dati dosimetrici nelle condizioni effettive in cui si e' svolto l'esame, che in genere non coincideranno con quelle standard ICRP. Inoltre quando le dimensioni e la massa del paziente differiscono sensibilmente da quelle del fantoccio utilizzato nelle simulazioni (il cosidetto uomo di riferimento, di altezza pari a 174 cm e massa di 70,9 Kg) il metodo ICRP puo' portare a errori considerevoli nella stima della dose. Lo scopo del presente lavoro e' quello di indicare una possibile via di uscita per superare queste limitazioni. L'algoritmo proposto in questo lavoro si basa sull'applicazione del metodo suggerito da Huda e

La digestión anaerobia y los reactores UASB. Generalidades

OpenAIRE

Yaniris Lorenzo; Ma. Cristina Obaya

2006-01-01

Se muestran las generalidades de los reactores, se da a conocer su concepto, se enumeran las aguas residuales que pueden ser tratadas en los mismos, se comentan los parámetros a tener en cuenta para que funcione adecuadamente y se enumeran las ventajas y desventajas de este proceso, así como su aplicabilidad.

Evaluation of the reliability of electric power transmission systems; Evaluacion de confiabilidad de sistemas de transmision de energia electrica

Energy Technology Data Exchange (ETDEWEB)

Vega Ortiz, Miguel

1989-07-01

algorithm in a digital program, this was proved in a personal computer applying it to IEEE transmission systems evaluated with other methods, among them one of 140 buses and 199 transmission lines. The results as far as reliability indexes compared with the other methods were very satisfactory and promising as far as required CPU time and memory for larger systems. [Spanish] En esta tesis se ataca el problema de la Evaluacion de la Confiabilidad de los Sistemas de Transmision de Energia Electrica para fines de su planeacion integral. Una vez descrito el problema se presentan los indices que miden la confiabilidad de los sistemas electricos de potencia. Despues se describen los metodos para evaluar las redes de transmision, como el de Enumeracion de Contingencias, el Monte Carlo, el de Markov y los metodos para sistemas complejos como el de Cortes Minimos. Este ultimo se desarrolla ampliamente por las ventajas que presenta su aplicacion en la planeacion de redes grandes y complejas. El metodo de cortes minimos consta de dos grandes pasos: Determinar los cortes minimos para los puntos de carga y calcular los indices de confiabilidad en base a los cortes minimos. Los algoritmos convencionales para la determinacion de cortes minimos consideran un problema por cada punto de carga en forma independiente pasando por una determinacion de caminos minimos. En este tipo de algoritmos el tiempo de CPU y el espacio en memoria requeridos crecen exponencialmente para el caso de sistemas de transmision grandes, lo que representa una fuerte restriccion para su aplicacion. Para resolver este problema se establecio una metodologia en la que se modela el sistema por medio de un grafo y se determinan los cortes minimos con un algoritmo basado en la construccion de ciclos en el grafo dual. Con estos cortes se evalua la conexidad y capacidad de la red, obteniendose los indices de confiabilidad para cada bus y para el sistema. Estos indices se calculan con la representacion equivalente para

Body composition using deuterated water, index of insulin resistance and cortisol levels in Costa Rican school in the metropolitan area; Composicion corporal utilizando agua deuterada, indice de resistencia a la insulina y niveles de cortisol en escolares costarricenses del area metropolitana

Energy Technology Data Exchange (ETDEWEB)

Valverde Vindas, Allan Ignacio

2014-07-01

Body composition in the Costa Rican child population is evaluated and analyzed to determine the relationship with the index of insulin resistance and serum cortisol levels. 113 children in the metropolitan area were studied using deuterium isotope techniques as reference method for overweight and obesity. Morning cortisol levels were determined by immunoassay techniques (ELISA). The insulin resistance index of 113 Costa Rican boys and girls is obtained by the homeostatic method and the relationship between body composition with index of insulin resistance or levels of cortisol [Spanish] La composicion corporal en la poblacion infantil costarricense es evaluada y analizada para determinar la relacion con el indice de resistencia a la insulina y niveles de cortisol serico. 113 ninos y ninas del area metropolitana fueron estudiados utilizando tecnicas isotopicas de deuterio como metodo de referencia para sobrepeso y obesidad. Los niveles de cortisol matutino se han determinado mediante tecnicas inmunoensayo (ELISA). El indice resistencia a la insulina de 113 ninos y ninas costarricenses es obtenido mediante el metodo homeostatico asi como la relacion entre composicion corporal con indice de resistencia a la insulina o niveles de cortisol.

A CONTRIBUIÇÃO DE IMRE LAKATOS PARA A ANÁLISE EPISTEMOLÓGICA DO PROGRAMA BRASILEIRO DE PÓS-GRADUAÇÃO EM ENFERMAGEM

Directory of Open Access Journals (Sweden)

Gilberto de Lima Guimarães

2017-01-01

Full Text Available Objetivo : presentar la perspectiva teórica de Imre Lakatos apartir de su Metodología de Programas de Investigación Científica y su uso de evaluación epistemiológica del Programa de Post-Grado en Enfermería Brasileño. Metodo : se trata de un análisis reflexivo, organizado en tres secciones, guiados por la siguiente pregunta: ¿la proposición teórico-filosofica de Imre Lakatos puede contribuir para evaluación del Programa brasilero de Post Grado en Enfermería? Discussión : se asume el cuidado de enfermería como hipótesis teórica; se presentan los elementos básicos del programa lakatosiano: núcleo duro, cinturón protector, heurística negativa y heurística positiva; y su aplicabilidad para evaluar el Programa de Post-Grado en Enfermería de Brasil, definir y establecer los elementos básicos lakatosianos. Después de 43 años de la creación del post grado stricto sensu en Brasil, se hace necesario criticar el fundamento epistemiológico. Conclusión : defiendese la ampliación del proceso de evaluación a partir del enlace entre el cuantitativo y lo filosófico a fin de juzgar la ciencia de enfermería.

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

Energy Technology Data Exchange (ETDEWEB)

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

2009-07-01

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

ELABORACIÓN DE CRITERIOS E INDICADORES PARA DESARROLLAR Y EVALUAR PROGRAMAS DE ENVEJECIMIENTO SALUDABLE EN LOS LUGARES DE TRABAJO

Directory of Open Access Journals (Sweden)

Inmaculada Mateo Rodríguez

2015-01-01

Full Text Available Fundamentos:En el actual contexto poblacional de envejecimiento dela población y prolongación de la vida laboral, los programas de promociónde salud en el trabajo son una herramienta clave y necesaria para promoverun envejecimiento activo y saludable. El objetivo fue elaborar una herra-mienta tipo lista de verificación para orientar la planificación, implemen-tación y evaluación de buenas prácticas en intervenciones en este ámbito,aplicables a una variedad de programas, países y centros de trabajo.Métodos:Se utilizó una técnica Delphi en tres rondas en la que parti-ciparon expertos/as de cinco países europeos. Se elaboró un cuestionario enlínea a partir de una lista de criterios e indicadores y, empleando el correoelectrónico, se trabajó durante las sucesivas rondas en su adaptación a laevaluación de intervenciones. Mediante procesos de valoración y consenso,se priorizaron los criterios e indicadores más relevantes.Resultados:Partiendo de nueve criterios basales se priorizaron cuatrocriterios clave cuyas puntuaciones medias fueron: relevancia: 62, adecua-ción al objetivo: 57, innovación: 50 y garantía de calidad: 41. Utilizandoesta matriz de criterios e indicadores se diseñó una lista de verificación conla información clave que debe recogerse a la hora de planificar, implementary evaluar buenas prácticas en las intervenciones.Conclusiones:La lista de verificación ayuda a sistematizar la metodo-logía global de implantación de intervenciones que puede ser utilizada porresponsables de los programas para promover el envejecimiento activo ysaludable en los centros de trabajo.

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

Energy Technology Data Exchange (ETDEWEB)

Sacco, Wagner Figueiredo

2000-03-01

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

FOTOBIORREACTOR: HERRAMIENTA PARA CULTIVO DE CIANOBACTERIAS

Directory of Open Access Journals (Sweden)

Luis Guillermo Ramírez Mérida

2014-05-01

Full Text Available Las cianobactérias son organismos eficientes en la conversión de energía solar y producen una gran variedad de metabolitos. En la actualidad son el centro de atención para la producción de biocombustible, son usadas como biofertilizantes, control de contaminación ambiental y como fuente de nutrientes en alimentación humana y animal. Con el fin de proporcionar crecimiento y aprovechar el potencial de las cianobacterias, se requieren fotobiorreactores eficientes. Aunque se han propuesto muchos tipos de fotobiorreactores, no existe un reactor ideal, solo unos pocos pueden utilizarse para la producción de biomasa de cianobacterias. De hecho, la elección del fotobiorreactor más adecuado depende de la situación, ya que tanto las especies de algas disponibles y el destino final jugarán un papel importante. Uno de los principales factores que limita su aplicación práctica en cultivos de biomasa es la transferencia de masa. Por esto, entender el coeficiente de transferencia de masa en los fotobiorreactores es necesario para una operación eficiente del cultivo de biomasa en cianobacterias. En esta revisión, se discuten varios tipos de fotobiorreactores muy promisorios para la producción de biomasa de cianobacterias.

Reactor inventory monitoring system for Angra-1 reactor; Sistema de monitoracao de inventario do reator para usina nuclear Angra I

Energy Technology Data Exchange (ETDEWEB)

S Neto, Joaquim A.; Silva, Marcos C.; Pinheiro, Ronaldo F.M. [Furnas Centrais Eletricas S.A., Rio de Janeiro, RJ (Brazil); Soares, Milton [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Martinez, Aquilino; Comerlato, Cesar A.; Oliveira, Eugenio A. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Lab. de Monitoracao de Processos

1996-07-01

This work describes the project of Reactor Inventory Monitoring System, which will be installed in Angra I Nuclear Power Plant. The inventory information is important to the operators take corrective actions in case of an incident that may cause a failure in the core cooling. (author)

The Role of Exponential and PCTR Experiments at Hanford in the Design of Large Power Reactors; Roles Respectifs des Experiences Exponentielles et du Reacteur d'Etude des Constantes Physiques de Hanford dans les Etudes de Grands Reacteurs de Puissance; Znachenie ehksponentsial'nykh opytov i opytov na reaktore PCTR pri proektirovanii bol'shikh ehnergeticheskikh reaktorov v khehnforde; Papel de los Experimentos Exponenciales y del Reactor PCTR de Hanford en el Proyecto de Grandes Reactores de Potencia

Energy Technology Data Exchange (ETDEWEB)

Heineman, R. E. [General Electric Company, Richland, WA (United States)

1964-02-15

que ces installations permettent d'utiliser, en vue de faire face aux besoins de donnees experimentales de plus en plus diverses. Il faut avoir tous ces renseignements presents a l'esprit si l'on veut prevoir comment evolueront les besoins et les tendances dans l'emploi de ces installations pour les etudes de reacteurs de puissance. Le memoire decrit brievement le Reacteur d'etude des reseaux a haute temperature et indique comment on se propose de l'utiliser dans le cadre de cette evolution. (author) [Spanish] Desde hace casi 15 anos se vienen realizando en los laboratorios de Hanford mediciones exponenciales en reticulados de grafito* uranio. Aunque los resultados de dichos experimentos se emplearon para establecer los laplacianos de reactores de produccion, contribuyeron tambien a ampliar los conocimientos sobre la fisica de estos sistemas. Muy pronto se reconocio que la utilidad del experimento exponencial quedaba limitada por sus grandes dimensiones y por su escasa sensibilidad a pequenas perturbaciones localizadas del sistema. Por ello se comenzo a idear un experimento integral en un reactor que reduciria al minimo la cantidad de materiales necesarios para obtener datos significativos. A tal efecto, se construyo una instalacion critica perfeccionada de varias regiones, que se denomino PCTR (reactor para estudio de constantes fisicas). Este reactor se ha empleado para determinar las constantes fisicas de varios reactores de potencia. Ademas, ha servido como instalacion de uso general para medir secciones eficaces y para determinar los parametros diferenciales e integrales de fisica de los reactores correspondientes a diversos tipos de medios multiplicadores. Los reactores exponenciales se emplearon despues de construir el PCTR, a pesar de que este cumplio ampliamente sus promesas. El autor proporciona diversos datos tipicos obtenidos con estas dos instalaciones y compara sus papeles respectivos para el estudio de nuevos reactores de potencia, para justificar la

Power Reactor Design at Zero Power; Etudes de Reacteurs de Puissance, au Moyen de Machines de Puissance Zero; Konstruktsiya ehnergeticheskogo reaktora nulevoj moshchnosti; Diseno de Reactores Generadores con Ayuda de Reactores de Potencia Nula

Energy Technology Data Exchange (ETDEWEB)

Redman, W. C.; Plumlee, K. E.; Baird, Q. L. [Argonne National Laboratory, Argonne, IL (United States)

1964-02-15

de los elementos combustibles de oxido de uranio-oxido de torio en agua pesada, destacando principalmente los datos necesarios para el diseAo de un segundo cuerpo para el reactor experimental de agua hirviente de Argonne; 2. Preparacien de una maqueta de reactor de investigacion de flujo elevado que permitira veriflcar los calculos efectuados durante el estudio, determinar la geometrra optima y evaluar el efecto de la combustion; 3. Determinacion de las distribuciones energeticas y del efecto de inmersion de los elementos combustibles sobre la reactividad en el caso de un reactor de agua hirviente con sobrecalentador incorporado; 4. Diseflo de un cuerpo de reactor reproductor plutonfgeno de neutrones ripidos, refrigerado por sodio y alimentado con {sup 235}U, que constituiri la carga inicial del segundo reactor reproductor experimental (EBR-II) de Argonne; 5. Estudio de las caracterfcticas de un reactor de dos zonas (termica y rapida) que sufren interaccidn. Al discutir estos programas, los autores explican tambien en que factores se basd la eleccion de los experimentos en conjuntos exponenciales y criticos sin envenenamiento en maquetas de potencia nula, asi como de los experimentos in situ, que sirvieron para obtener los datos necesarios. Tambien describen la importancia de los trabajos analiticos complementarios. La memoria presenta ejemplos especfficos para demostrar en que medida se pueden obtener datos sobre el diseno del reactor antes de explotarlo en regimen normal. Entre estos datos se cuenta el margen de paro, el exceso de reactividad necesario para el funcionamiento, los coeficientes de temperatura, la eficacia de las barras de control y de seguridad, la cinetica del reactor, los esquemas de produccion de energia, los requisitos que ha de cumplir la fuente neutronica de puesta en marcha, y la sensibilidad de los instrumentos, los blindajes y la economfa neutronica. El estudio de los experimentos realizados recientemente con reactores de potencia nula

Continuous hyperpolarization with parahydrogen in a membrane reactor

Science.gov (United States)

Lehmkuhl, Sören; Wiese, Martin; Schubert, Lukas; Held, Mathias; Küppers, Markus; Wessling, Matthias; Blümich, Bernhard

2018-06-01

Hyperpolarization methods entail a high potential to boost the sensitivity of NMR. Even though the "Signal Amplification by Reversible Exchange" (SABRE) approach uses para-enriched hydrogen, p-H2, to repeatedly achieve high polarization levels on target molecules without altering their chemical structure, such studies are often limited to batch experiments in NMR tubes. Alternatively, this work introduces a continuous flow setup including a membrane reactor for the p-H2, supply and consecutive detection in a 1 T NMR spectrometer. Two SABRE substrates pyridine and nicotinamide were hyperpolarized, and more than 1000-fold signal enhancement was found. Our strategy combines low-field NMR spectrometry and a membrane flow reactor. This enables precise control of the experimental conditions such as liquid and gas pressures, and volume flow for ensuring repeatable maximum polarization.

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

International Nuclear Information System (INIS)

Henry, A.F.

1980-01-01

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

Development of sialons colloidally processed in aqueous medium

Science.gov (United States)

Pereira, Catarina Alexandra Goncalves

Desenvolveu-se um novo metodo de processamento coloidal em meio aquoso para consolidar cerâmicos de ?-Y-SiAlON, os quais foram sinterizados por prensagem isostatica a quente (HIP) e por spark plasma sintering (SPS). Preparou-se com sucesso uma suspensao aquosa de pos precursores de YSiAlON (Si3N4, Al2O3, Y2O3 e AlN), temporariamente estavel, usando Dolapix PC21 como dispersante, permitindo a fabricacao de pos granulados pela tecnica de aspersao-congelamento-liofilizacao e a consolidacao de corpos em verde por enchimento por barbotina. Avaliou-se o efeito do excesso de oxigenio introduzido pelo processamento aquoso no desenvolvimento microestrutural e nas propriedades mecânicas. Os corpos de Y-SiAlON consolidados por enchimento por barbotina e sinterizados por HIP a 1800ºC apresentaram microestruturas e propriedades mecânicas similares a corpos consolidados por prensagem a seco. Estes materiais exibiram densificacao completa, dureza Vickers maxima de 2003 e tenacidade a fractura (metodo SEVNB) maxima de 5.20 MPam1/2. Foi ainda possivel estabelecer uma relacao estreita entre o aumento do conteudo em oxigenio das amostras sinterizadas e a diminuicao da tenacidade a fractura. Na tentativa de melhorar a tenacidade a fractura dos materiais, procedeu-se a incorporacao nas suspensoes de sementes de Ca-?-SiAlON de geometria alongada produzidas por sintese por combustao, adicionadas como agentes de reforco. A sintese por combustao realizada em larga escala (cargas ate 1 kg) nao produziu efeitos negativos obvios nos produtos da reaccao. Investigara-se os efeitos da adicao de 5 % em peso de sementes nas propriedades mecânicas e no desenvolvimento microestrutural de amostras densificadas por HIP. Em comparacao com os materiais sem sementes, a tenacidade a fractura (metodo SEVNB) aumentou 13%, mas a dureza Vickers resultou 14,5% inferior. A sinterizacao por SPS permitiu obter densificacao completa a temperaturas tao baixas como 1600ºC a partir dos pos granulados de Y

Reactor core in FBR type reactor

International Nuclear Information System (INIS)

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

1989-01-01

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

Software for the nuclear reactor dynamics study using time series processing; Software para el estudio de la dinamica de reactores nucleares mediante el procesamiento de series temporales

Energy Technology Data Exchange (ETDEWEB)

Valero, Esbel T.; Montesino, Maria E. [Instituto Superior de Ciencia y Tecnologia Nuclear (ISCTN), La Habana (Cuba)

1997-12-01

The parametric monitoring in Nuclear Power Plant (NPP) permits the operational surveillance of nuclear reactor. The methods employed in order to process this information such as FFT, autoregressive models and other, have some limitations when those regimens in which appear strongly non-linear behaviors are analyzed. In last years the chaos theory has offered new ways in order to explain complex dynamic behaviors. This paper describes a software (ECASET) that allow, by time series processing from NPP`s acquisition system, to characterize the nuclear reactor dynamic as a complex dynamical system. Here we show using ECASET`s results the possibility of classifying the different regimens appearing in nuclear reactors. The results of several temporal series processing from real systems are introduced. This type of analysis complements the results obtained with traditional methods and can constitute a new tool for monitoring nuclear reactors. (author). 13 refs., 3 figs.

Sedimentación, solubilización, y prefermentación de aguas residuales en un reactor biopelícula

OpenAIRE

Cuevas-Rodríguez, Germán; Tejero Monzón, Iñaki

2003-01-01

Esta investigación fue realizada con el objetivo de desarrollar un nuevo reactor prefermentador de aguas residuales para incrementar los porcentajes de sedimentación, hidrólisis y prefermentación de la materia orgánica contenida en el agua residual bruta, empleando una sola unidad de pretratamiento y, de esta manera, poder remplazar el decantador primario por este nuevo reactor. El estudio fue realizado en un reactor biopelícula de lecho sumergido fijo, empacado con un medio de soporte BLASF‚...

Biohydrogen production from diary processing wastewater by anaerobic biofilm reactors

Energy Technology Data Exchange (ETDEWEB)

Rios-Gonzalez, L.J.; Moreno-Davila, I.M.; Rodriguez-Martinez, J.; Garza-Garcia, Y. [Universidad Autonoma de Coahuila, Saltillo, Coahuila (Mexico)]. E-mail: leopoldo.rios@mail.uadec.mx

2009-09-15

to be employed for hydrogen production. [Spanish] Este articulo describe la produccion biologica de hidrogeno a partir de agua residual diaria via fermentacion anaerobica utilizando choque termico pretratado (100 grados centigrados, 30 min.) y procedimientos de tratamiento acido para enriquecer selectivamente el hidrogeno produciendo consorcios mezclados antes de la inoculacion de reactores por lote. El biorreactor empleado para el consorcio de inmovilizacion se opero a temperatura mesofilica (ambiente) (20{+-}3 grados centigrados), bajo condiciones acidofilicas (pH 4.0-4.5), HRT (2h), y un soporte natural para generar hidrogeno produciendo biopelicula de consorcios mezclados: Opuntia imbricata. El reactor se opero inicialmente con sorbitol (5g/L) durante 60 dias de operacion. Las pruebas de lote se llevaron a cabo empleando 20{+-}0.02g de soporte natural con biopelicula. Los experimentos de lote se realizaron para investigar el efecto de la DQO ((2.9-21.1 g-DQO/L), a pH inicial de 7.0, 32{+-}1 grados centigrados. La produccion maxima de hidrogeno se obtuvo a 21.1 g-COD/L. Se efectuaron experimentos del efecto del pH empleando una concentracion de sustrato optima (21.2 g-COD/L), a pH de 4 a 7 y 11.32 (pH de agua residual diaria) y 32{+-}1 grados centigrados. Los resultados de los experimentos indican que el cultivo inicial optimo fue de pH 4.0, pero podemos considerar tambien una produccion estable de hidrogeno a pH 11.32 (pH de agua residual diaria), por lo que se pudo evitar ajustar el pH, y usar agua residual diaria como queda en el proceso de produccion de queso. El pH operacional de 4.0 esta 1.5 unidades por debajo del reportado antes correspondiente al hidrogeno que producen los organismos. La influencia del efecto de la temperatura se realizo usando la concentracion de sustrato optima (21.2 g-COD/L), dos niveles de pH: 4.0 y 11.32, y cuatro diferentes temperaturas: 16{+-}3 grados centigrados (temperatura ambiente), 32{+-}1 grados centigrados, 45{+-}1 grados

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

Energy Technology Data Exchange (ETDEWEB)

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

1991-12-31

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1992-12-31

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

A new method for the coefficients of the characteristic polynomial; Un metodo nuevo para los coeficientes del polinomio caracteristico

Energy Technology Data Exchange (ETDEWEB)

Gonzalez, H.E. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2006-07-01

In linear algebra, one can associate an equation to each square matrix: its characteristic equation or secular equation. Starting from this equation, the one characteristic polynomial that codes several important properties of the matrix is obtained: its own values, it determinant and it appearance. The first method to calculate those coefficients of this polynomial were proposed by the french astronomer Urbain Jean Joseph Le Verrier (1811-1877), from then on, many methods have intended to calculate these coefficients. In this work the author proposes a new one method and a bibliographical citation is given where the calculations with others methods that know each other for it, taking like reference the matrix used by Le Verrier are explained. It was concluded that it here proposed, besides being the only mexican method that is knew, has the advantage of being very easy of understanding and of calculating well, in the operations that it carries out, it doesn't use the division and it avoids fractions in matrices whose entrances are whole. This has a great importance for their use in the classroom for their great didactic value and in nuclear reactors and Genetic Engineering. (Author)

A new method for the coefficients of the characteristic polynomial; Un metodo nuevo para los coeficientes del polinomio caracteristico

Energy Technology Data Exchange (ETDEWEB)

Gonzalez, H E [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2006-07-01

In linear algebra, one can associate an equation to each square matrix: its characteristic equation or secular equation. Starting from this equation, the one characteristic polynomial that codes several important properties of the matrix is obtained: its own values, it determinant and it appearance. The first method to calculate those coefficients of this polynomial were proposed by the french astronomer Urbain Jean Joseph Le Verrier (1811-1877), from then on, many methods have intended to calculate these coefficients. In this work the author proposes a new one method and a bibliographical citation is given where the calculations with others methods that know each other for it, taking like reference the matrix used by Le Verrier are explained. It was concluded that it here proposed, besides being the only mexican method that is knew, has the advantage of being very easy of understanding and of calculating well, in the operations that it carries out, it doesn't use the division and it avoids fractions in matrices whose entrances are whole. This has a great importance for their use in the classroom for their great didactic value and in nuclear reactors and Genetic Engineering. (Author)

Integrated scheme of long-term for spent fuel management of power nuclear reactors; Esquema integrado de largo plazo para la administracion de combustible gastado de reactores nucleares de potencia

Energy Technology Data Exchange (ETDEWEB)

Ramirez S, J. R.; Palacios H, J. C.; Martinez C, E., E-mail: ramon-ramirez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2015-09-15

After of irradiation of the nuclear fuel in the reactor core, is necessary to store it for their cooling in the fuel pools of the reactor. This is the first step in a processes series before the fuel can reach its final destination. Until now there are two options that are most commonly accepted for the end of the nuclear fuel cycle, one is the open nuclear fuel cycle, requiring a deep geological repository for the fuel final disposal. The other option is the fuel reprocessing to extract the plutonium and uranium as valuable materials that remaining in the spent fuel. In this study the alternatives for the final part of the fuel cycle, which involves the recycling of plutonium and the minor actinides in the same reactor that generated them are shown. The results shown that this is possible in a thermal reactor and that there are significant reductions in actinides if they are recycled into reactor fuel. (Author)

Technology and Power

Science.gov (United States)

2003-04-07

disappear and opponents will fight throughout the battlefield destroying critical points of command and control systems, logistical support and...with these problems. However, growth slumped to 3 percent in 2000. The Pakistani education sector is in a critical state of disarray. While substantial...Accessed 15 March 2003. Briones, Guillermo. Metodos y Técnicas de Investigación para las Ciencias Sociales, 3rd ed. Ciudad de México, México: Editorial

Autonomía escolar en la Educación Básica (1982-2014): Estado de la cuestión desde la perspectiva supranacional

OpenAIRE

Sáenz Melo, José Antonio; Molina García, Amelia

2017-01-01

En este artículo presentamos un panorama general sobre los principales enfoques epistémicos en la investigación sobre política educativa en el mundo, centrado de modo específico en las contribuciones hacia la producción de conocimiento de la autonomía de gestión y su relación con la Agenda Globalmente Estructurada para la Educación (AGEE), con la intención de describir el posicionamiento de una política pública en su dimensión supranacional y nacional, para lo cual se adopta el enfoque metodo...

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.

Solar system design to heating water for a biodigester; Diseno de un sistema solar de calentamiento de agua para un biodigestor

Energy Technology Data Exchange (ETDEWEB)

Gutierrez Castro, Lucia Monica; Quinto Diez, Pedro [Escuela Superior de Ingenieria Mecanica y Electrica, Instituto Politecnico Nacional, Mexico, D.F. (Mexico)]. E-mail: moni-80-lgc@hotmail.com; pqd510@hotmail.com; Tovar Galvez, Luis Raul [Centro Interdisciplinario de Investigaciones de Estudios sobre Medio Ambiente y Desarrollo, Instituto Politecnico Nacional, Mexico, D.F. (Mexico)]. E-mail: ltovarg@ipn.mx

2010-11-15

In this paper a Solar System of Heating Water (SSHW) to provide energy to a biodigester which produces biogas located in the Interdisciplinary Center of Investigation of Studies About Environment and Development (CIIEMAD) is assessed. This evaluation is made by means of the f Method considerating the extraterrestrial radiation, the earth radiation in the zone and the necessary energy to maintain at 55 degrees Celsius the mixture inside the biodigester. The data were introduced in the SOLAR program to calculate both the harnessing area m{sup 2} and the storage capacity in L/m{sup 2}. To guarantee the good performance of the SSHW, a control and monitoring system for the temperature of the mix inside the biodigester is proposed. It also controls the input and output temperature to the solar collectors, as well as the cost analysis which shows the savings of fuel of the SSHW with a conventional system to heating water. [Spanish] En este articulo se evalua un sistema solar de calentamiento de agua (SSCA) para proveer energia a un biodigestor que forma parte del sistema de generacion de biogas (SGB) ubicado en el Centro Interdisciplinario de Investigaciones de Estudios sobre Medio Ambiente y Desarrollo (CIIEMAD). Dicha evaluacion se realiza por medio del Metodo f de diseno que considera datos de radiacion terrestre, radiacion extraterrestre sobre la zona y la energia necesaria para mantener la temperatura de la mezcla dentro del biodigestor a 55 grados centigrados. Los datos fueron introducidos en el programa SOLAR para el calculo del area de captacion en m{sup 2} y la capacidad de almacenamiento en L/m{sup 2}. Para garantizar el buen funcionamiento del SSCA se propone un sistema de control y monitoreo de la temperatura de la mezcla dentro del biodigestor. Tambien se controla la temperatura de entrada y salida a los colectores solares, asi como el analisis de costos que muestra el ahorro de combustible del SSCA con un sistema convencional de calentamiento de agua.

Reactor core and initially loaded reactor core of nuclear reactor

International Nuclear Information System (INIS)

Koyama, Jun-ichi; Aoyama, Motoo.

1989-01-01

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

A {beta} - {gamma} coincidence; Metodo de coincidencias {beta} - {gamma}

Energy Technology Data Exchange (ETDEWEB)

Agullo, F

1960-07-01

A {beta} - {gamma} coincidence method for absolute counting is given. The fundamental principles are revised and the experimental part is detailed. The results from {sup 1}98 Au irradiated in the JEN 1 Swimming pool reactor are given. The maximal accuracy is 1 per cent. (Author) 11 refs.

Nuclear reactor physics course for reactor operators

International Nuclear Information System (INIS)

Baeten, P.

2006-01-01

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

Reactor core of FBR type reactor

International Nuclear Information System (INIS)

Hayashi, Hideyuki; Ichimiya, Masakazu.

1994-01-01

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

Nuclear reactors

International Nuclear Information System (INIS)

Barre, Bertrand

2015-10-01

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

Data Evaluation Problems in the Pulsed Neutron Source Method; Problemes d'Evaluation des Donnees dans les Applications de la Methode de la Source Pulsee; Problemy otsenki dannykh pri primenenii metoda istochnika impul'snykh nejtronov; Problemas de Evaluacion de Datos en el Metodo de la Fuente de Neutrones Pulsados

Energy Technology Data Exchange (ETDEWEB)

Pal, L.; Bod, L.; Szatmary, Z. [Central Research Institute for Physics, Hungarian Academy of Sciences, Budapest (Hungary)

1965-08-15

moyen de transport dans de nombreuses matieres hydrogenees. (author) [Spanish] Desde hace mas de diez anos se viene empleando el metodo de los neutrones pulsados para determinar los parametros de difusion de los neutrones termicos. Este metodo ha resultado especialmente idoneo para el estudio de los moderadores hidrogenados. Los autores dan los resultados de las mediciones hechas en agua, benceno, tolueno, xileno, ciclohexano, n-hexano y difenilo, y examinan los metodos para evaluar con el minimo error los parametros de difusion de interes partiendo de los datos obtenidos en las mediciones. Se examina detenidamente, tanto en el plano teorico como en el experimental, el efecto de tiempo de vuelo que se manifiesta por razones tecnicas cuando se investigan moderadores a elevadas temperaturas, y que influye en el valor de la constante de desintegracion, y se exponen las condiciones geometricas en que se ha de operar para obtener resultados satisfactorios. Los autores determinan tambien el efecto que sobre la constante de desintegracion ejerce el tiempo muerto del detector neutronico y del amplificador, y demuestran que es despreciable cuando [i(t) {tau}]{sup 2} << 1, siendo i/t/dt el numero de neutrones detectados en el intervalo de tiempo/t, t + dt/, y {tau} el tiempo muerto. Se evaluo la constante de desintegracion empleando el metodo de la maxima probabilidad. Para determinar inequivocamente la funcion de probabilidad, se eligio un analizador multicanal que acumulaba como maximo una sola senal por ciclo de analisis y por canal. Se comprobo que la incorporacion del parametro caracteristico del fondo a la funcion de probabilidad tiene primordial importancia. Los parametros de la funcion de maxima probabilidad se evaluaron en una calculadora aplicando el metodo de iteracion de Newton. Cuando no se tiene debidamente en cuenta el fondo, este puede causar una mayor contaminacion aparente de armonicos, la cual, a su vez, puede interpretarse como un fondo aparente. Por ello es

Reactor core for LMFBR type reactors

International Nuclear Information System (INIS)

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

1987-01-01

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

CONSERVACION DE MANZANAS GRANNY SMITH MINIMAMENTE PROCESADAS POR METODOS COMBINADOS

OpenAIRE

GALLEGUILLOS CANALES, PAMELA CRISTINA; GALLEGUILLOS CANALES, PAMELA CRISTINA

2011-01-01

Se ha demostrado que el consumo de frutas y hortalizas tiene un efecto beneficioso para la salud. Debido a su alto contenido de antioxidantes, constituye una de las maneras más efectivas para reducir el riesgo de enfermedades crónicas no transmisibles (Speisky, 2006; Block et al., 1992; Knekt et al., 1997; Ness y Powles, 1997; Doll, 1990; Wang et al., 1996; Del Caro et al., 2004). El aumento de muertes por enfermedades como cáncer, diabetes y enfermedades cardiovasculares, ha llevado a ent...

Plant Measurement, Sampling and Analysis for Accountancy Purposes with Particular Reference to Separation Plants at Windscale; Mesures, Echantillonnages et Analyses en Usine a des Fins Comptables, Notamment dans les Installations de Separation de Windscale; Izmereniya, vzyatie obraztsov i analizy v tselyakh ucheta na opyte ustanovki razdeleniya radioizotopov v uindskejle; Medicion, Muestreo y Analisis para Fines Contables, Especialmente en las Plantas de Separacion de Windscale

Energy Technology Data Exchange (ETDEWEB)

Davidson, A. S.; Elliott, F.; Powell, R.; Swinburn, K. A. [United Kingdom Atomic Energy Authority, Windscale and Calder Works, Cumberland (United Kingdom)

1966-02-15

) titrimetrie, e) dilution isotopique suivie de spectrometrie de masse, et f) spectrometrie differentielle. Ils soulignent egalement les methodes de dosage de l'uranium, notamment les suivantes: a) gravimetrie de U{sub 3}O{sub 8}. b) extraction a l ' ether suivie de gravimetrie ou de colorimetrie, c) titrimetrie, d) dilution isotopique suivie de spectrometrie de masse, et e) determination de l'enrichissement par spectrometrie de masse ou spectrographie des emissions accompagnees d'un deplacement des raies. Pour toutes les methodes comptables, on utilise des etalons pour assurer le controle de la qualite et faire ressortir toute inexactitude qu'il est necessaire de corriger. Les auteurs indiquent la precision de chaque methode et enumerent les methodes effectivement utilisees dans la nouvelle usine de separation. (author) [Spanish] Todas las cifras destinadas a la contabilidad de materiales especiales corresponden por lo menos a uno de los tres parametros siguientes: medicion en la planta, muestreo y analisis. Para las mediciones en la planta conviene emplear la pesada siempre que sea posible; por ejemplo, la cantidad de plutonio que entra en la nueva planta de separacion de Windscale se calcula a base del peso de las barras de uranio. Los autores exponen los metodos de medicion de volumenes: a) 'pneumercator', y b) empleo de cesio radiactivo como indicador, y evaluan la exactitud y precision de cada uno de esos metodos. El muestreo de soluciones en un proceso intermitente se efectua con tubos evacuados despues de homogeneizar la solucion. Para las corrientes 'continuas' , que requieren mucha exactitud, se ha ideado un dispositivo de muestreo continuo que se emplea a la entrada de la nueva planta de separacion. En Windscale, el metodo normal de muestreo consiste en taladrar lingotes metalicos; para otros solidos se sigue la practica de homogeneizar todo lo posible el material antes de tomar la muestra (para el oxido de plutonio, por ejemplo, se emplea una mezcladora conica en Y

Ageing Management for Research Reactors. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-10-15

This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

Ageing Management for Research Reactors. Specific Safety Guide

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

Efecto de dos metales pesados, cadmio y níquel, sobre la eficiencia de remoción de carga orgánica de un reactor UASB a escala de laboratorio

Directory of Open Access Journals (Sweden)

Luis Eduardo Forero

2004-01-01

Full Text Available Se realizaron ensayos en tres reactores UASB de tres litros cada uno, a un tiempo de retención hidráulico (TRH de cuatro horas y carga orgánica volumétrica de 4,8 g/L/d. Después de la fase inicial de arranque, tiempo de 4.000 horas para los tres reactores, se procedió a afectarlos de la siguiente forma: el primer reactor fue alimentado con 5 mg/L de cloruro de cadmio en forma continua, el segundo reactor fue alimentado con 10 mg/L de cloruro de níquel en forma continua también, mientras que el tercer reactor no se afectó con sustancia alguna y sirvió como control. La eficiencia de remoción de demanda química de oxígeno (DQO del primer reactor cambió del 60% de la fase de arranque (fase 1 al 18% en la fase afectada con cadmio (fase dos; la eficiencia de remoción de DQO en el reactor dos pasó del 60 al 24% y a su vez para el reactor tres control no hubo cambio significativo en dicha eficiencia. A su vez el reactor uno acumuló el cadmio en el lodo, mientras que el reactor dos no hizo lo propio con el níquel.

Nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

This patent describes an improved liquid metal nuclear reactor construction comprising: (a) a nuclear reactor core having a bottom platform support structure; (b) a reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core; (c) a containment structure surrounding the reactor vessel and having a sidewall spaced outwardly from the reactor vessel side wall and having a base mat spaced below the reactor vessel bottom end wall; (d) a central small diameter post anchored to the containment structure base mat and extending upwardly to the reactor vessel to axially fix the bottom end wall of the reactor vessel and provide a center column support for the lower end of the reactor core; (e) annular support structure disposed in the reactor vessel on the bottom end wall and extending about the lower end of the core; (f) structural support means disposed between the containment structure base mat and bottom end of the reactor vessel wall and cooperating for supporting the reactor vessel at its bottom end wall on the containment structure base mat to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event; (g) a bed of insulating material disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall; freely expand radially from the central post as it heats up while providing continuous support thereof; (h) a deck supported upon the wall of the containment vessel above the top open end of the reactor vessel; and (i) extendible and retractable coupling means extending between the deck and the top open end of the reactor vessel and flexibly and sealably interconnecting the reactor vessel at its top end to the deck

Mathematical and numerical modeling of the turbulent dispersion of reactive pollutant plumes; Modelacion matematica y numerica de la dispersion turbulenta de plumas de contaminantes reactivos

Energy Technology Data Exchange (ETDEWEB)

Rodas Grapain, Arturo

1999-07-01

One of the main problems involved in air quality models to calculate the pollutant concentration in a single point in the space and time, is the complexity of the numerical method. Even though the numerical methods are based on sophisticated and elaborated mathematics. They present two important and inevitable drawbacks: the stability of the numerical method. This means that its capacity to obtain reliable convergency in relation to the calculated values and real values is limited. The time and memory consumption. The high machine memory used to perform the numerical procedures and the time needed to prepare such procedures. Another problem is the mathematical basis of the structure of the air quality model. Commonly, simple models can perform quick estimations; however they are not exact contrary to the complex and elaborated models. In order to employ these complex models a high speed computer (workstations or Cray computer) is required. For this reason, this work presents a model approach with a relatively simple theoretical structure. The structure of this model named MOTTQUIP (modelo de transporte turbulento y quimica de plumas) can provide good results in point concentration operations. These results are compared with those obtained by two moderately complex mathematical models (Georgopoulos-Seinfeld and Lipphardt reactive plume models). The model developed in this work, shows a special feature where the solution of the differential equations are not involved explicitly. Therefore, it does not present the typical difficult in solving this kind of equations with the traditional numerical methods. [Spanish] Uno de los principales problemas que se presentan en los modelos de calidad del aire para el calculo de la concentracion de un cierto contaminante, para un punto dado en el espacio y en el tiempo, es la complejidad del metodo numerico involucrado para este fin, debido a que dichos metodos de calculo estan basados en matematicas sofisticadas y muy

A structure-preserving approach to normal form analysis of power systems; Una propuesta de preservacion de estructura al analisis de su forma normal en sistemas de potencia

Energy Technology Data Exchange (ETDEWEB)

Martinez Carrillo, Irma

2008-01-15

. [Spanish] El comportamiento dinamico de los sistemas de potencia es no lineal y es comprendido por diversos procesos en diferentes escalas de tiempo. El tamano y la complejidad de estos mecanismos han estimulado a la propuesta de metodos que reducen la dimension original preservando caracteristicas esenciales de la naturaleza del sistema. En esta investigacion, se propone un metodo analitico no lineal basado en la teoria de formas normales y tecnicas de perturbacion singular para el analisis de oscilaciones de gran amplitud. Este enfoque permite que el metodo de formas normales alcance su maxima capacidad proporcionando una metodologia general para su aplicacion en una amplia variedad de sistemas no lineales en los diversos campos de la investigacion. Basados en la teoria de formas normales de los sistemas dinamicos, se propone un modelo que preserva la estructura del sistema, las caracteristicas de la red y la carga. Aprovechando la separacion que existe entre la dinamica lenta y rapida, originada por las diferentes escalas de tiempo; una eficiente tecnica basada en perturbaciones singulares, es usada para obtener el comportamiento no lineal de los sistemas de potencia preservando exactamente la estructura de la red. Este metodo no requiere reduccion de ecuaciones por lo que se puede obtener informacion adicional de interes directamente de la red y de la dinamica de la carga del sistema de potencia. En este trabajo son desarrolladas expresiones analiticas que proporcionan una buena aproximacion al comportamiento real del sistema, y ademas se proponen tecnicas para interpretar estas soluciones en terminos de funciones modales para designar areas de control y ubicar dispositivos FACTS; asi tambien se desarrollan criterios para caracterizar los efectos de la red sobre el comportamiento no lineal del sistema. Los procedimientos desarrollados son probados en dos sistemas reales de potencia.

New digital control system for the operation of the Colombian research reactor IAN-R1; Nuevo sistema de control digital para la operacion del reactor de investigacion Colombiano IAN-R1

Energy Technology Data Exchange (ETDEWEB)

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

2015-09-15

En 2011, Mexico won the Colombian international tender for the renewal of instrumentation and control of the IAN-R1 Reactor, to Argentina and the United States. This paper presents the design criteria and the development made for the new digital control system installed in the Colombian nuclear reactor IAN-R1, which is based on a redundant and diverse architecture, which provides increased availability, reliability and safety in the reactor operation. This control system and associated instrumentation met all national export requirements, with the safety requirements established by the IAEA as well as the requirements demanded by the Colombian Regulatory Body in nuclear matter. On August 20, 2012, the Colombian IAN-R1 reactor reached its first criticality controlled with the new system developed at Instituto Nacional de Investigaciones Nucleares (ININ). On September 14, 2012, the new control system of the Colombian IAN-R1 reactor was officially handed over to the Colombian authorities, this being the first time that Mexico exported nuclear technology through the ININ. Currently the reactor is operating successfully with the new control system, and has an operating license for 5 years. (Author)

Simulación CFD de la transferencia de calor en un reactor de hidrotratamiento de aceites vegetales de segunda generación

OpenAIRE

Mendoza Sépulveda, César Camilo

2013-01-01

Resumen: Se desarrolló un modelo CFD que permite representar la transferencia de calor en un reactor de hidrotratamiento de aceites vegetales. Este modelo permitió evaluar la transferencia de calor para distintas configuraciones del reactor. En el proceso de hidrotratamiento de aceites vegetales se transforma el aceite en un líquido con cero contenido de azufre y excelentes propiedades como combustible diesel. El proceso se basa en la adición de hidrógeno a alta presión en un reactor de lecho...

Disposal of Low-Activity Waste and Accumulation in Cultivated Soils; Rejets d'Effluents Faiblement Radioactifs et Accumulation dans les Sols Cultives; 0416 0418 0414 ; Desechos y Efluentes de Baja Actividad: Su Acumulacion en los Terrenos Cultivados

Energy Technology Data Exchange (ETDEWEB)

Barbier, G. [Station Centrale d' Agronomie, Versailles (France); Michon, G. [Service d' Hygiene Atomique et de Radiopathologie, Centre d' Etudes Nucleaires, Saclay (France)

1960-07-01

The paper describes a method of accumulating long-lived radioisotopes in soils and calculating the maximum contamination they would cause in vegetables grown on these soils. The authors suggest a way of expressing this contamination and a formula by which the maximum contamination of one kilogramme of the harvested produce in relation to the tolerated contamination per litre of irrigation water could be calculated. (author) [French] L'article decrit une methode destinee a prevoir l'accumulation des radioelements de longue periode dans les sols et a chiffrer la contamination limite qui en resultera pour des legumes cultives sur ces sols. Les auteurs proposent un mode d'expression de cette contamination et une formule qui permettrait de calculer la contamination limite d'un kg de produit recolte par rapport a la contamination toleree d'un litre d'eau d'irrigation. (author) [Spanish] En la memoria se describe un metodo para evaluar la acumulacion de los radioelementos de periodo largo en los terrenos y para calcular la contaminacion limite resultante para las hortalizas cultivadas en dichos terrenos. Los autores proponen un metodo para expresar dicha contaminacion y una formula que permita determinar la contaminacion limite de un kilogramo de producto cosechado en funcion de la contaminacion admisible por litre de agua de riego. (author) [Russian] V stat'e opisyvaetsja metod, pozvoljajushhij predvidet' nakoplenie dolgozhivushhih radioaktivnyh izotopov v pochve i opredeljat' predel'nyj uroven' vytekajushhego iz jetogo zarazhenija dlja ovoshhej, vyrashhivaemyh na jetih zemljah. Avtory stat'i predlagajut metod vyrazhenija jetogo zarazhenija i formulu, pozvoljajushhuju vychislit' predel'nyj uroven' zarazhenija odnogo kilogramma ovoshhej po otnosheniju k dopustimomu urovnju zarazhenija odnogo litra oroshajushhej vody. (author)

Effect of the empty fraction in a solar reactor of fluidized bed; Efecto de la fraccion vacia en un reactor solar de lecho fluidizado

Energy Technology Data Exchange (ETDEWEB)

Torres, Alejandro; Romero-Paredes, Hernando; Vazquez, Alejandro; Torijano, Eugenio; Ambriz, Juan J [Universidad Autonoma Metropilitana-Iztapalapa, Mexico, D.F. (Mexico)

2000-07-01

de lecho fluidizado que a la vez sirve como receptor solar de un sistema de almacenamiento termoquimico de la energia solar. Los complejos fenomenos que se tienen en estos reactores hacen dificil su dimensionamiento para su aplicacion solar. Por ello, modelar y simular su comportamiento sin y con reaccion quimica ayuda a paliar este inconveniente. Uno de los fenomenos presentes es el cambio de la fraccion vacia en la cual concentramos nuestra atencion. En este trabajo se propone una alternativa en el modelado de estos sistemas considerando las fluctuaciones locales de la fraccion vacia o porosidad {epsilon}(x, y) en el lecho. Para esto se propone una distribucion probabilistica uniforme para todos los nodos de la malla (x, y) del lecho donde se asocian valores de porosidad locales para cada nodo de la malla mediante un generador aleatorio donde {epsilon}(x, y){epsilon} [0.1]. La fraccion nueva juega un papel muy importante debido a que la penetracion de la radiacion solar en estos sistemas de cuerpos opacos depende directamente de la distribucion de espacios vacios en la trayectoria de la radiacion incidente que afecta su comportamiento termico y cinetico. De los resultados se puede comprobar la caracteristica de no isotermicidad del reactor lo que conlleva, una vez alcanzada la temperatura de reaccion, a un perfil de concentraciones disperso. La fraccion vacia es un parametro que influye grandemente en estos perfiles y que incrementando el numero de fluidizacion es como se logra disminuir ese tiempo. En conclusion, se resalta la importancia que juega la fraccion vacia en la evolucion tanto de los perfiles de temperatura como de concentracion. El comportamiento del lecho en la simulacion se hace mas precisa de acuerdo con los resultados experimentales previamente obtenidos.

Remoción de fósforo de diferentes aguas residuales en reactores aeróbios de lecho fluidizado trifásico con circulación interna

Directory of Open Access Journals (Sweden)

Gleyce Teixeira Correia

2013-01-01

Full Text Available El vertimiento de aguas residuales (AR produce impactos sobre los cuerpos de agua receptores. Nutrientes como P generan implicaciones en los sistemas lénticos pues aceleran los procesos de eutrofización. Se han utilizado diversas tecnologías para la remoción de P de las AR: sistemas de tratamiento físico químico con importantes efectos por adición de productos coagulantes; procesos biológicos basados en alternancia de condiciones anaerobias y aerobias con importantes implicaciones de volumen necesario; sistemas como lagunas de estabilización e irrigación requieren de áreas muy considerables y procesos de postratamiento. Los reactores aerobios de lecho fluidizado con circulación interna (RALFCI son opciones compactas que utilizan gran concentración de biomasa activa que han demostrado su capacidad para remover materia orgánica y N. Para AR domésticas provenientes de la estación de bombeo de Ilha Solteira y para los efluentes de un sistema de recirculación acuícola (SRA de cultivo semi-intensivo de tilapia se evaluó la eficiencia de remoción de P reactivo y P total en tres tipos de RALFCI con diámetro externo de 250 mm y diferentes diámetros de tubo interno (DTI, con dos medios de soporte y diferentes concentraciones en dos de los reactores. Las eficiencias medias de remoción de P reactivo en AR domésticas para un tiempo de retención hidráulica (TRH de 3 horas en el reactor con DTI 125 mm variaron entre 25,6 y 38,4% y en el reactor con DTI 150 mm entre 27,5 y 32,5%; la remoción de P total en el SRA para un TRH de 0,19 h y DTI 100 mm fue de 32,7%.

Generation IV reactors: reactor concepts

International Nuclear Information System (INIS)

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

2003-01-01

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

Calibration of the hydraulic model of a full-scale activated sludge plant; Calibracion hidraulica a escala real de un reactor de lodos activados

Energy Technology Data Exchange (ETDEWEB)

Fall, Cheikh [Universidad Autonoma del Estado de Mexico (Mexico); Loaiza-Navia, Jimmy [Servicios de Agua y Drenaje de Monterrey (Mexico)

2008-04-15

When planning to simulate a wastewater treatment plant (WWTP) with the activated sludge model number 1 (ASM1), one of the first requirements is to determine the hydraulic model of the reactor. The aim of this study was to evaluate the hydrodynamic regime of the aeration tank of a municipal WWTP by using a rhodamine tracer test and the Aquasim simulation software. A pre-simulation was performed in order to quantify the appropriate colorant mass, set up a sampling plan and evaluate the anticipated visual impact of the tracer test in the river receiving the treated effluents. A tracer test and dynamic flow measurements were carried out, the results of which served to establish and calibrate the hydraulic model. The evaluated tank was physically built as a plug-flow reactor subdivided in 7 compartments, but the study revealed that it is best represented by a model with 5 virtual mixed reactors in series. Through the study, the approach of using a WWTP simulator for hydraulics calibration was shown to be a powerful and flexible tool for designing a tracer test and for identifying adequate tank-in-series models of full-scale activated sludge aeration tanks. [Spanish] Cuando se planea simular una planta de tratamiento con base en el modelo numero 1 de lodos activados (ASM1), uno de los primeros requisitos es determinar el modelo hidraulico del reactor. En este trabajo se estudio el regimen hidrodinamico del tanque de accion de una planta de tratamiento de aguas residuales municipales (PTAR), utilizando una prueba de trazador con rodamina y un programa de simulacion (Aquasim). Se realizo una prueba de trazador con el experimento, lo que permitio determinar la cantidad requerida de trazador, fijar los intervalos de muestreo y limitar el impacto visual anticipado del colorante sobre el rio que recibe el efluente tratado. Se llevaron a cabo la prueba de trazador y la medicion de los perfiles dinamicos de caudales, cuyos resultados sirvieron para establecer y calibrar el

High temperature fast reactor for hydrogen production in Brazil; Reator nuclear rapido de altissima temperatura para producao de hidrogenio no Brasil

Energy Technology Data Exchange (ETDEWEB)

Nascimento, Jamil A. do; Ono, Shizuca; Guimaraes, Lamartine N.F. [Centro Tecnico Aeroespacial (CTA-IEAv), Sao Jose dos Campos, SP (Brazil). Inst. de Estudos Avancados]. E-mail: jamil@ieav.cta.br

2008-07-01

The main nuclear reactors technology for the Generation IV, on development phase for utilization after 2030, is the fast reactor type with high temperature output to improve the efficiency of the thermo-electric conversion process and to enable applications of the generated heat in industrial process. Currently, water electrolysis and thermo chemical cycles using very high temperature are studied for large scale and long-term hydrogen production, in the future. With the possible oil scarcity and price rise, and the global warming, this application can play an important role in the changes of the world energy matrix. In this context, it is proposed a fast reactor with very high output temperature, {approx} 1000 deg C. This reactor will have a closed fuel cycle; it will be cooled by lead and loaded with nitride fuel. This reactor may be used for hydrogen, heat and electricity production in Brazil. It is discussed a development strategy of the necessary technologies and some important problems are commented. The proposed concept presents characteristics that meet the requirements of the Generation IV reactor class. (author)

Tratamiento de las excretas de cerdo mediante un reactor anaeróbico SCFBR a nivel de banco Treatment of pig excreta using an SCFBR anaerobic reactor

Directory of Open Access Journals (Sweden)

Caicedo Luis A.

1999-06-01

Full Text Available Un nuevo reactor anaeróbico denominado Sludge Central Fixed Bed Reactor (SCFBR fue construido y evaluado para tratar los residuos líquidos de las granjas porcícolas. El SCFBR está constituido por tres zonas principales. Una zona inferior de lodos, seguida por un módulo empacado ubicado en forma concéntrica y, en la parte superior, una zona de separación sólido, líquido y gas. El reactor de 28,5 1 de volumen de reacción fue evaluado durante 210 días para tres cargas orgánicas de 0,548, 0,421 y 1,239 g DQO/ 1 día. El SCFBR fue alimentado inicialmente en forma discontinua con tiempos de retención hidráulicos (TRH de 10 y 10,7 días. Posteriormente el TRH fue disminuido a 3,87 días con una alimentación en continuo. Para las tres cargas orgánicas de 0,548, 0,421 y 1,239 g DQO/1 día se obtuvieron remociones en la demanda química de oxígeno (DQO de 68%, 81% y 73% y en los sólidos volátiles (SV, de 53,5%, 55,8% y 50,1%, respectivamente. El SCFBR presentó un buen desempeño, re-presentado en las eficiencias de remoción y en la estabilidad observada. Se presenta una microfotografía tomada de una muestra de lodo de la zona inferior del SCFBR, observándose una gran presencia de microorganismos del género Methanosaeta (Methanothrix.

A new anaerobic reactor called the Sludge Central Fixed Bed Reactor (SCFBR was built and evaluated for the treatment of liquid residue from the pig farms. The SCFBR has three main parts. The lower area is for sludge, the middle part consists of a concentrically

Nuclear reactor

International Nuclear Information System (INIS)

Hattori, Sadao; Sato, Morihiko.

1994-01-01

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

The CAREM reactor and present currents in reactor design

International Nuclear Information System (INIS)

Ordonez, J.P.

1990-01-01

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

Methods for the control of NOx and particles in the combustion; Metodos para el control de NOx y particulas en la combustion

Energy Technology Data Exchange (ETDEWEB)

Romo Millares, Cesar A [Instituto de Investigaciones Electrica, Cuernavaca (Mexico)

1997-12-31

This present the techniques and equipment of control of transmissions for thermoelectric power stations appear that have mayor possibilities of being considered in the future immediate within the national energetic panorama and the frame established by the environmental normative. The subject polluting compounds to overhaul are oxides of nonburned nitrogen and particles [Espanol] Se presentan las tecnicas y equipos de control de emisiones para centrales termoelectricas que tienen mayores posibilidades de ser consideradas en el futuro inmediato dentro del panorama energetico nacional y el marco establecido por la normatividad ambiental. Los compuestos contaminantes sujetos a revision son los oxidos de nitrogeno y las particulas inquemadas

Methods for the control of NOx and particles in the combustion; Metodos para el control de NOx y particulas en la combustion

Energy Technology Data Exchange (ETDEWEB)

Romo Millares, Cesar A. [Instituto de Investigaciones Electrica, Cuernavaca (Mexico)

1996-12-31

This present the techniques and equipment of control of transmissions for thermoelectric power stations appear that have mayor possibilities of being considered in the future immediate within the national energetic panorama and the frame established by the environmental normative. The subject polluting compounds to overhaul are oxides of nonburned nitrogen and particles [Espanol] Se presentan las tecnicas y equipos de control de emisiones para centrales termoelectricas que tienen mayores posibilidades de ser consideradas en el futuro inmediato dentro del panorama energetico nacional y el marco establecido por la normatividad ambiental. Los compuestos contaminantes sujetos a revision son los oxidos de nitrogeno y las particulas inquemadas

Calculation of the electromagnetic fields in electric machines through the use of the finite element. Algorithms for the solution of induction problems. Pt. 3; Calculo de campos electromagneticos en maquinas electricas mediante elemento finito. Algoritmos para la solucion de problemas de induccion. Pt. 3

Energy Technology Data Exchange (ETDEWEB)

Rosales, Mario F [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1988-12-31

This article is based in the electromagnetic modeling presented in the first part of the series for the indirect solution of partial differential equations. Magnetic systems in closed regions with moving or axial symmetry, whose total current density is partially known (induction problems) are considered. Includes the ability to deal with means in movement and a sinusoidal behavior for the source density current is assumed. Some algorithms are developed that are implanted in the software CALIIE-2D of the Instituto de Investigaciones Electricas (IIE) to obtain the numerical solutions of these problems. The basic systems of algebraic equations are obtained through the application of the Galerkin method in the discreteness of the finite element with first order triangular elements. [Espanol] Este articulo se basa en la modelacion electromagnetica presentada en la primera parte de la serie y en el planteamiento proporcionado en la segunda parte para la solucion indirecta de ecuaciones diferenciales parciales. Se consideran sistemas magneticos en regiones cerradas con simetria traslacional o axial, cuya densidad de corriente total es parcialmente conocida (problemas de induccion). Incluye la capacidad para tratar medios con movimiento y se supone un comportamiento senoidal para la densidad de corriente fuente. Se desarrollan los algoritmos que se implantan en el programa de computo CALIIE-2D del Instituto de Investigaciones Electricas (IIE) para obtener las soluciones numericas de estos problemas. Los sistemas basicos de ecuaciones algebraicas se obtienen mediante la aplicacion del metodo de Galerkin en la discretizacion de elemento finito con elementos triangulares de primer orden.

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

International Nuclear Information System (INIS)

Anon.

1986-01-01

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

Validación de la limpieza del reactor empleado en la preparación de medicamentos

Directory of Open Access Journals (Sweden)

Lisseux Castilla Valentín

2001-04-01

Full Text Available En la actualidad, la validación de los procesos se ha convertido en una imperiosa necesidad de la Industria Médico-Farmacéutica, para garantizar la calidad de sus productos y lograr la comercialización de estos. En esta dirección se comenzaron los trabajos de validación de la limpieza de los equipos y se realizó la validación de la limpieza del reactor SEN, que se utiliza para la preparación de los inyectables. Para lograr este objetivo, se elaboró una metodología de trabajo, se seleccionaron los métodos analíticos más apropiados, se establecieron los criterios de aceptación y se escribió un protocolo de validación, que constituyó la herramienta fundamental de trabajo. Posteriormente se realizó la validación de la limpieza del reactor, y se concluyó que el procedimiento de limpieza, aunque no garantiza total eliminación de los residuos del producto, sí cumple con los criterios de aceptación establecidos.At present, the validation of the processes is an imperative necessity of the Medicopharmaceutical Industry to guarantee the quality of its products and to commercialize them. To this end, the cleaning of the equipment began to be validated and the validation of the cleaning of the SEN reactor that is used for the preparation of injections was carried out. To attain this goal, a working methodology was designed, the most appropiate analytical methods were selected, the acceptance criteria were established and a validation protocol was written that was the fundamental working tool. Later on, the validation of the cleaning of the reactor was made and it was concluded that although the cleaning procedure does not guarantee the total elimination of the residuals of the product, it fulfills the established acceptance criteria.

Reactor science and technology: operation and control of reactors

International Nuclear Information System (INIS)

Qiu Junlong

1994-01-01

This article is a collection of short reports on reactor operation and research in China in 1991. The operation of and research activities linked with the Heavy Water Research Reactor, Swimming Pool Reactor and Miniature Neutron Source Reactor are briefly surveyed. A number of papers then follow on the developing strategies in Chinese fast breeder reactor technology including the conceptual design of an experimental fast reactor (FFR), theoretical studies of FFR thermo-hydraulics and a design for an immersed sodium flowmeter. Reactor physics studies cover a range of topics including several related to work on zero power reactors. The section on reactor safety analysis is concerned largely with the assessment of established, and the presentation of new, computer codes for use in PWR safety calculations. Experimental and theoretical studies of fuels and reactor materials for FBRs, PWRs, BWRs and fusion reactors are described. A final miscellaneous section covers Mo-Tc isotope production in the swimming pool reactor, convective heat transfer in tubes and diffusion of tritium through plastic/aluminium composite films and Li 2 SiO 3 . (UK)

Nuclear power reactors

International Nuclear Information System (INIS)

1982-11-01

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

Design and construction of the SIPPING for fuels of the TRIGA Mark III reactor; Diseno y construccion del SIPPING para combustibles del reactor TRIGA Mark III

Energy Technology Data Exchange (ETDEWEB)

Castaneda J, G.; Delfin L, A.; Alvarado P, R.; Mazon R, R.; Ortega V, B. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: adl@nuclear.inin.mx

2003-07-01

The sipping technique, it has been used by several possessors of nuclear research reactors in its irradiated nuclear fuels, likewise in some fuel storage sites, with the objective of to determine the quantity of radioactivity that the fuel liberates in the means in that it is. The irradiated fuel in storage of some nuclear research reactors, its can have cracks that cross the cladding of the same one, generating the liberation of fission products that its need to determine to maintain safety measures appropriate as much as the fuel as of the facilities where they are. It doesn't exist until now, some method published for the non destructive sipping test technique. Based on that described, the Reactor Department of the National Institute of Nuclear Research, it has designed and built an inspection system of irradiated fuel that it will allow the detection of gassy fission products in site, and solids by means of the measurement of the activity of the Cs-137 contained in water samples. (Author)

Metodo integrado para la gestion de Universidades basado en el Balanced Scorecard (bsc y el modelo europeo de calidad (efqm: caso U.C.S.M.

Directory of Open Access Journals (Sweden)

Horacio Vicente Barreda Tamayo

2010-12-01

Full Text Available El presente Trabajo realiza la propuesta de un Método Integrado que permite mejorar la competitividad en la Gestión de las Universidades, este método se basa: En una herramienta de Gestión Estratégica: el Balanced Scorecard (BSC, que fue creada por Kaplan y Norton en 1992; y En el Modelo Europeo de Calidad (EFQM, que fue desarrollado como un Modelo de Excelencia en 1991. La metodología utilizada consiste en analizar las características, ventajas y limitaciones del BSC y el EFQM para aplicarlos simultáneamente en la gestión de Tomando como base los 9 criterios del EFQM, se desarrolla un Mapa Estratégico del BSC, para que se alineen todas las perspectivas hacia el logro de los Objetivos Estratégicos de la Organización. El método integrado planteado se aplica en el caso de la Universidad Católica de Santa María (Arequipa- Perú, donde se analiza las ventajas que implicaría la implementación del mismo.

Research reactors

International Nuclear Information System (INIS)

Merchie, Francois

2015-10-01

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

Roles of plasma neutron source reactor in development of fusion reactor engineering: Comparison with fission reactor engineering

International Nuclear Information System (INIS)

Hirayama, Shoichi; Kawabe, Takaya

1995-01-01

The history of development of fusion power reactor has come to a turning point, where the main research target is now shifting from the plasma heating and confinement physics toward the burning plasma physics and reactor engineering. Although the development of fusion reactor system is the first time for human beings, engineers have experience of development of fission power reactor. The common feature between them is that both are plants used for the generation of nuclear reactions for the production of energy, nucleon, and radiation on an industrial scale. By studying the history of the development of the fission reactor, one can find the existence of experimental neutron reactors including irradiation facilities for fission reactor materials. These research neutron reactors played very important roles in the development of fission power reactors. When one considers the strategy of development of fusion power reactors from the points of fusion reactor engineering, one finds that the fusion neutron source corresponds to the neutron reactor in fission reactor development. In this paper, the authors discuss the roles of the plasma-based neutron source reactors in the development of fusion reactor engineering, by comparing it with the neutron reactors in the history of fission power development, and make proposals for the strategy of the fusion reactor development. 21 refs., 6 figs

Impacto orcamentario da utilizacao do Metodo Canguru no cuidado neonatal

Directory of Open Access Journals (Sweden)

Aline Piovezan Entringer

2013-10-01

Full Text Available OBJETIVO Estimar o impacto orçamentário da utilização do Método Canguru na rede municipal de saúde. MÉTODOS Um modelo de decisão analítico foi desenvolvido para simular os custos do Método Canguru e Unidade Intermediária Neonatal no Rio de Janeiro, RJ, em 2011. A população de referência foi constituída pelos recém-nascidos estáveis clinicamente, que podem receber assistência nas duas modalidades de cuidado. O impacto orçamentário foi estimado para uma coorte hipotética de 1.000 recém-nascidos elegíveis em um ano. A proporção de recém-nascidos elegíveis que recebem assistência nas duas modalidades foi obtida por coleta de dados nas maternidades incluídas no estudo. As probabilidades dos eventos e o consumo de recursos de saúde, no período da assistência, foram incorporados ao modelo. Cenários foram desenvolvidos para refletir a adoção do método Canguru em maior ou menor escala. RESULTADOS A utilização do Método Canguru significou redução de gastos equivalente a 16% em um ano, se todos os recém-nascidos elegíveis fossem assistidos por esse método. CONCLUSÕES A opção Método Canguru é de menor custo comparado com a da Unidade Intermediária Neonatal. A análise de impacto orçamentário da utilização desse método no Sistema Único de Saúde indicou economia importante para o período de um ano.

Choice and the cost and benefit analysis of one solar system of renewable energy for the Tepozan Park; Seleccion y analisis costo-beneficio de un sistema de energia renovable para el parque Tepozan

Energy Technology Data Exchange (ETDEWEB)

Lopez P, J. Manuel A; Sheinbaum P, Claudia [Instituto de Ingenieria de la UNAM, Mexico, D. F. (Mexico)

2000-07-01

This article is about the choice process and the cost and benefit analysis of one solar photovoltaic system for the Tepozan Park, which is a space of ecoturism and ecological education, it is at the Tlalpan District in Mexico, D.F. According to this objective, we start with an introduction related to general conditions in the Park and we talk about the energy requirement. Next, the method for the better option choice is shown, this is based on decision analysis of Kepner and Tregoe. The choice option is evaluated according to the main financial tools of the Cost and Benefit Analysis private evaluation. This shows the decision analysis including issued about ecology. Finally, we add a point for the result synthesis, so we can have a complete approach in order to choice a renewable energy. As conclusion is shown the most important costs and benefits, thinking on future decisions about operation and maintenance of the system. [Spanish] En este articulo se presenta el proceso de seleccion y analisis Costo-Beneficio de un sistema de energia solar fotovoltaica para las instalaciones del Parque Tepozan, un espacio de ecoturismo y educacion ambiental, ubicado en la delegacion Tlalpan de Mexico, D.F. Para ello, se da una introduccion de las condiciones generales del parque y de los requerimientos de energia. Posteriormente se presenta un apartado del metodo para la seleccion de la alternativa mas adecuada, sustentado en un analisis de decisiones. La alternativa seleccionada, se somete a una evaluacion de los principales criterios de la evaluacion privada derivada del Analisis Costo Beneficio, con lo que se ilustra el proceso de toma de decision, incluyendo los factores de impacto ambiental. Finalmente, se incorpora un apartado de sintesis de resultados, para aportar un panorama completo en cuanto a la operacion y mantenimiento del sistema dentro del parque.

Reactor physics aspects of CANDU reactors

International Nuclear Information System (INIS)

Critoph, E.

1980-01-01

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

Research reactors

International Nuclear Information System (INIS)

Kowarski, L.

1955-01-01

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

Comparison between TRU burning reactors and commercial fast reactor

International Nuclear Information System (INIS)

Fujimura, Koji; Sanda, Toshio; Ogawa, Takashi

2001-03-01

Research and development for stabilizing or shortening the radioactive wastes including in spent nuclear fuel are widely conducted in view point of reducing the environmental impact. Especially it is effective way to irradiate and transmute long-lived TRU by fast reactors. Two types of loading way were previously proposed. The former is loading relatively small amount of TRU in all commercial fast reactors and the latter is loading large amount of TRU in a few TRU burning reactors. This study has been intended to contribute to the feasibility studies on commercialized fast reactor cycle system. The transmutation and nuclear characteristics of TRU burning reactors were evaluated and compared with those of conventional transmutation system using commercial type fast reactor based upon the investigation of technical information about TRU burning reactors. Major results are summarized as follows. (1) Investigation of technical information about TRU burning reactors. Based on published reports and papers, technical information about TRU burning reactor concepts transmutation system using convectional commercial type fast reactors were investigated. Transmutation and nuclear characteristics or R and D issue were investigated based on these results. Homogeneously loading of about 5 wt% MAs on core fuels in the conventional commercial type fast reactor may not cause significant impact on the nuclear core characteristics. Transmutation of MAs being produced in about five fast reactors generating the same output is feasible. The helium cooled MA burning fast reactor core concept propose by JAERI attains criticality using particle type nitride fuels which contain more than 60 wt% MA. This reactor could transmute MAs being produced in more than ten 1000 MWe-LWRs. Ultra-long life core concepts attaining more than 30 years operation without refueling by utilizing MA's nuclear characteristics as burnable absorber and fertile nuclides were proposed. Those were pointed out that

Análisis de la dispersión axial de masa y calor en reactores de lecho fijo

Directory of Open Access Journals (Sweden)

Rangel Jara Hermes Augusto

1997-01-01

Full Text Available Dentro del espíritu investigativo a nivel teórico del estudio de los reactores químicos, el presente trabajo desarrolla e implementa un análisis conceptual y numérico de los fenómenos de dispersión axial de calor y masa en reactores de lecho fijo. Se pretende disponer de una alternativa numérica que permita en una forma rápida y precisa la solución de las ecuaciones diferenciales junto con las respectivas condiciones de frontera del modelo matemático. Para la simulación del reactor de lecho fijo se empleó un modelo unidimensional pseudohomogeneo con parámetros aglomerados.

Nuclear reactor types

International Nuclear Information System (INIS)

Jones, P.M.S.

1987-01-01

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

Intervención breve para adolescentes que inician el consumo abusivo de alcohol y otras drogas: su eficacia en un escenario clínico

Directory of Open Access Journals (Sweden)

Carlos Augusto Rodríguez Durán

2017-06-01

Full Text Available Introducción: en las últimas décadas, se ha observado en los adolescentes mexicanos un incremento en la cantidad y frecuencia del consumo de alcohol y drogas ilícitas; los programas de intervención breve han demostrado ser eficaces para reducir el consumo y abuso de sustancias en diversas poblaciones. Objetivo: determinar la eficacia del Programa de Intervención Breve para Adolescentes que Inician el Consumo Abusivo de Alcohol y otras Drogas (PIBA, así como el mantenimiento del cambio en los jóvenes que asistieron. Metodo: se utilizó un diseño de medidas repetidas, no probabilístico y sin grupo control. En el seguimiento participaron 60 usuarios consumidores de sustancias de entre 16 y 20 años de edad, de ambos sexos, habitantes de la Ciudad de México. Resultados: al comparar la preintervención vs. el seguimiento, se encontró que los adolescentes que participaron en el PIBA mantuvieron una reducción en su patrón de consumo (cantidad, frecuencia y tiempo de abstinencia de alcohol, mariguana e inhalables; disminuyeron los problemas asociados con el consumo; e incrementaron su nivel de autoeficacia percibida. La mejoría fue mayor en quienes concluyeron la intervención breve que en quienes no terminaron todas las sesiones. Conclusiones: el PIBA fue coadyuvante en la consecución de las metas propuestas por la mayoría de los adolescentes que asistieron a este tratamiento psicológico.

UNA TECNICA ESTADISTICA PARA MEDIR LA CONFLICTIVIDAD SOCIAL A TRAVES DEL REGISTRO ARQUEOLOGICO (A Statistical Technique to Measure Social Conflict through the Archaeological Record

Directory of Open Access Journals (Sweden)

Pascual Izquierdo-Egea

2015-03-01

Full Text Available Se presenta aqui una tecnica estadistica para medir la conflictividad social a traves del registro mortuorio. Nace al amparo del metodo de valoracion contextual empleado en el analisis de los ajuares funerarios desde 1993. Se trata de una herramienta fundamental para el desarrollo de la arqueologia de los fenomenos sociales, cuyos relevantes resultados empiricos avalan su trascendencia teorica. Tras proceder a su conceptualizacion en funcion de la desigualdad social y la riqueza relativa, se explican las dos clases de conflictividad social definidas: estructural o estatica y coyuntural o dinamica. Finalmente, se incluyen sus conexiones con la ley demografica de Malthus a traves de sus dos parametros: poblacion y recursos. Todo este entramado teorico se ilustra con algunas aplicaciones referidas a las civilizaciones antiguas, abarcando la protohistoria iberica, la Mesoamerica prehispanica o la Roma altoimperial. ENGLISH: A statistical technique to measure social conflict through the mortuary record is presented here. It is born under the contextual valuation method used in the analysis of grave goods since 1993. This is a fundamental tool for the development of the archaeology of social phenomena, whose relevant empirical results support its theoretical significance. After conveying its conceptualization in terms of social inequality and relative wealth, the two classes of social conflict are explained: static or structural and dynamic or conjunctural. Finally, connections with the Malthusian demographic law through its two parameters—population and resources—are included. The synthesis of these theoretical frameworks is illustrated with applications to ancient civilizations, including Iberian protohistory, prehispanic Mesoamerica, and early imperial Rome.

Reactor containment and reactor safety in the United States

International Nuclear Information System (INIS)

Kouts, H.

1986-01-01

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

Reactor Physics

International Nuclear Information System (INIS)

Ait Abderrahim, A.

2002-01-01

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

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2001-04-01

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

Reactor Physics

International Nuclear Information System (INIS)

Ait Abderrahim, A.

2001-01-01

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

Modelamiento matemático para la pirolisis del cuesco de palma aceitera- Mathematical Modelingfor the Pyrolysis of the Oil Palm Kernel Shell

Directory of Open Access Journals (Sweden)

Manuel Alejandro Mayorga Betancourt

2017-06-01

Full Text Available En Colombia hay diferentes procesos en los cuales se desperdician los residuos, uno de ellos es la obtención de aceite para producir biodiesel a partir de palma aceitera, proceso en el cual se generan importantes cantidades de cuesco de palma, siendo los procesos termoquímicos una de las formas de aprovechamiento energético. El resultado del presente trabajo, es proponer un modelo matemático para el comportamiento del cuesco de palma africana en el proceso de pirolisis y en un estudio posterior para la gasificación. Este trabajo fue desarrollado haciendo una descripción del proceso en un reactor de lecho fijo tubular, el cual se utiliza para ambos procesos, tanto pirolisis como gasificación, con calentamiento directo, siendo muy exotérmico el proceso, identificando la fenomenología en la cual se aplican los conceptos de transferencia de energía, masa. Para el proceso de pirolisis se plantearon los balances de transferencia de energía y masa, despreciando el balance de momento debido a que los gases de síntesis se retiran para que no se generen reacciones heterogéneas, eliminando la fase gaseosa para no tener caídas de presión, por lo cual solo se tuvo en cuenta la fase sólida, lo que permitió que se tratara como una reacción homogénea. Como resultados se generaron dos modelos que describen el comportamiento del reactor en el proceso de pirolisis como un paso inicial para contribuir a la estandarización del proceso a nivel industrial.

Reactor

International Nuclear Information System (INIS)

Toyama, Masahiro; Kasai, Shigeo.

1978-01-01

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

Evaluation of climatic forecasts of rainfall for the Tlaxcala State (Mexico): 1998-2002

Energy Technology Data Exchange (ETDEWEB)

Gay Garcia, C. [Centro de Ciencias de la Atmosfera, Universidad Nacional Autonoma de Mexico (UNAM), Mexico, D.F. (Mexico); Hernandez Vazquez, M.; Jimenez Lopez, J. [Centro de Investigaciones en Ciencias Biologicas, Universidad Autonoma de Tlaxcala, Tlaxcala (Mexico); Lezama Gutierrez, J. [Departamento de Agrobiologia, Universidad Autonoma de Tlaxcala, Tlaxcala (Mexico); Magana Rueda, V.O.; Morales Acoltzi, T. [Centro de Ciencias de la Atmosfera, Universidad Nacional Autonoma de Mexico, UNAM, Mexico, D.F. (Mexico); Orozco Flores, S. [Centro de Investigaciones en Ciencias Biologicas, Universidad Autonoma de Tlaxcala, Tlaxcala (Mexico)

2004-07-01

During the second semester of 1997 the Project Utilizacion de pronosticos climaticos para actividades agricolas de Tlaxcala was instrumented with the purpose of aiding decision making in agricultural activities in the estate of Tlaxcala, Mexico. The main objective of the project was to characterize extreme values of precipitation associated with El Nino/La Nina events, to produce useful forecasts for decision making. This was achieved through close contacts with the farmers whose specific needs were taken into account to the extent possible. In a sense such forecasts became forecasts watched over by producers. The method of ensemble of analogs was applied to historical data. The evaluation of annual and monthly forecasts is presented here. The results show that knowledge about the regional climate has been gained as it is reflected by the skill of the method to forecast. The forecast for the region, for the year 2003 is analyzed in terms of the precipitation anomalies. [Spanish] En el segundo semestre de 1997, se implemento el proyecto de investigacion Utilizacion de pronosticos climaticos para actividades agricolas en el estado de Tlaxcala. El objetivo principal del proyecto original fue el de caracterizar valores extremos de precipitacion asociados a los eventos El Nino/La Nina, producir pronosticos mensuales de precipitacion que fueran practicos en la toma de decisiones para los cultivos de temporal. Esto ultimo fue discutido con los productores cuyas necesidades y sugerencias fueron tomadas en cuenta, considerando un pronostico lo mas extendido posible. De esta manera los pronosticos se tornaron Pronosticos vigilados por los productores. El metodo de ensamble de analogos observados fue aplicado para generar los pronosticos de 1998-2002. La evaluacion de los pronosticos anuales y mensuales se presenta aqui. Los resultados muestran que se ha ganado conocimiento acerca del clima regional, como se refleja en la habilidad del metodo para pronosticar. Por ultimo, se

Fiber-optic components for optical communicatios and sensing =

Science.gov (United States)

Marques, Carlos Alberto Ferreira

Nos ultimos anos, a Optoelectronica tem sido estabelecida como um campo de investigacao capaz de conduzir a novas solucoes tecnologicas. As conquistas abundantes no campo da optica e lasers, bem como em comunicacoes opticas tem sido de grande importancia e desencadearam uma serie de inovacoes. Entre o grande numero de componentes opticos existentes, os componentes baseados em fibra optica sao principalmente relevantes devido a sua simplicidade e a elevada de transporte de dados da fibra optica. Neste trabalho foi focado um destes componentes opticos: as redes de difraccao em fibra optica, as quais tem propriedades opticas de processamento unicas. Esta classe de componentes opticos e extremamente atraente para o desenvolvimento de dispositivos de comunicacoes opticas e sensores. O trabalho comecou com uma analise teorica aplicada a redes em fibra e foram focados os metodos de fabricacao de redes em fibra mais utilizados. A inscricao de redes em fibra tambem foi abordado neste trabalho, onde um sistema de inscricao automatizada foi implementada para a fibra optica de silica, e os resultados experimentais mostraram uma boa aproximacao ao estudo de simulacao. Tambem foi desenvolvido um sistema de inscricao de redes de Bragg em fibra optica de plastico. Foi apresentado um estudo detalhado da modulacao acustico-optica em redes em fibra optica de silica e de plastico. Por meio de uma analise detalhada dos modos de excitacao mecanica aplicadas ao modulador acustico-optico, destacou-se que dois modos predominantes de excitacao acustica pode ser estabelecidos na fibra optica, dependendo da frequencia acustica aplicada. Atraves dessa caracterizacao, foi possivel desenvolver novas aplicacoes para comunicacoes opticas. Estudos e implementacao de diferentes dispositivos baseados em redes em fibra foram realizados, usando o efeito acustico-optico e o processo de regeneracao em fibra optica para varias aplicacoes tais como rapido multiplexador optico add-drop, atraso de grupo

Allocation of thermoelectric units in short term in large scale electric power systems; Asignacion de unidades termoelectricas a corto plazo en sistemas electricos de potencia de gran escala

Energy Technology Data Exchange (ETDEWEB)

Guillen Moya, Isaias

1987-08-01

mathematics with dynamic programming to accelerate the search of a solution and (2) the development of an alternating method to solve the economic dispatch problem without restrictions. This method does not have to form the curve of incremental equivalent cost, with which a great deal of memory storage and execution time are saved. [Spanish] Se presenta un metodo para resolver el problema de asignacion de unidades termoelectricas en sistemas electricos de potencia de gran escala. El problema consiste en determinar cuales unidades generadoras deberan ser programadas para entrar o salir de operacion durante los intervalos de horizonte de planeacion, de tal forma que se satisfagan a minimo costo, y en forma confiable la demanda pronosticada de potencia electrica y las restricciones fisicas y operativas de los componentes del sistema de potencia. El metodo esta compuesto por dos etapas: la primera etapa encuentra una solucion inicial factible de unidades termo por medio de metodos heuristicos. La segunda etapa produce una solucion a partir de un estado de asignacion inicial factible. El costo de operacion se reduce aplicando programacion dinamica en aproximaciones sucesivas, de tal forma que el producto de cada interaccion constituye el estado de asignacion de menor costo encontrado hasta esa etapa. El rango de busqueda para la solucion optima es reducido aplicando tecnicas de relajacion lagrangeana para seleccionar unicamente las unidades que tienen el mayor potencial de reducir el costo de operacion. El algoritmo es validado utilizando un sistema representativo del sistema interconectado nacional que consta de 108 unidades termoelectricas agrupadas en 7 grupos de generacion, para un horizonte de planeacion de una semana dividido en intervalos horarios, conteniendo 18,144 variables discretas, 18,144 variables continuas y 39,024 restricciones. En una computadora VAX 11/780 el problema es resuelto en 55 minutos de CPU con una estimacion del 1.02% de suboptimalidad que indica que

Study of a fuel assembly for the nuclear reactor of IV generation cooled with supercritical water; Estudio de un ensamble de combustible para el reactor nuclear de generacion IV enfriado con agua supercritica

Energy Technology Data Exchange (ETDEWEB)

Barragan M, A.; Martin del Campo M, C.; Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Espinosa P, G., E-mail: albrm29@yahoo.com [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Area de Ingenieria en Recursos Energeticos, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (MX)

2011-11-15

In this work a neutron study is presented about a square assembly design of double line of fuel rods, with moderator box to the center of the arrangement, for a nuclear reactor cooled with supercritical water (SCWR). The SCWR reactor was chosen by the characteristics of its design, mainly because is based in light water reactors (PWR and BWR), and the operational experience that has of them allow to use models and similar programs to simulate the fuel and the nucleus of this type of reactors. To develop the necessary models and to carry out the design and analysis of the SCWR reactor, the neutron codes MCNPX and Helios were used. The reason of using both codes, is because the code MCNPX used thoroughly in the neutron simulation of these reactors, it has been our reference code to analyze the results obtained with the Helios code which results are more efficient because its calculation times are minors. In the nucleus design the same parameters for both codes were considered. The results show that the design with Helios is a viable option to simulate these reactors since their values of the neutrons multiplication factor are very similar to those obtained with MCNPX. On the other hand, it could be corroborated that the CASMO-4 code is inadequate to simulate the fuel to the temperature conditions and water pressure in the SCWR. (Author)

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2002-04-01

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

Research reactor standards and their impact on the TRIGA reactor community

International Nuclear Information System (INIS)

Richards, W.J.

1980-01-01

The American Nuclear Society has established a standards committee devoted to writing standards for research reactors. This committee was formed in 1971 and has since that time written over 15 standards that cover all aspects of research reactor operation. The committee has representation from virtually every group concerned with research reactors and their operation. This organization includes University reactors, National laboratory reactors, Nuclear Regulatory commission, Department of Energy and private nuclear companies and insurers. Since its beginning the committee has developed standards in the following areas: Standard for the development of technical specifications for research reactors; Quality control for plate-type uranium-aluminium fuel elements; Records and reports for research reactors; Selection and training of personnel for research reactors; Review of experiments for research reactors; Research reactor site evaluation; Quality assurance program requirements for research reactors; Decommissioning of research reactors; Radiological control at research reactor facilities; Design objectives for and monitoring of systems controlling research reactor effluents; Physical security for research reactor facilities; Criteria for the reactor safety systems of research reactors; Emergency planning for research reactors; Fire protection program requirements for research reactors; Standard for administrative controls for research reactors. Besides writing the above standards, the committee is very active in using communications with the nuclear regulatory commission on proposed rules or positions which will affect the research reactor community

Pós-tratamento de efluente nitrificado da parboilização de arroz utilizando desnitrificação em reator UASB Post-treatment a nitrified parboilized rice wastewater using denitrification in UASB reactor

Directory of Open Access Journals (Sweden)

Loraine Andre Isoldi

2005-12-01

Full Text Available Um sistema combinado reator UASB-reator aeróbio foi utilizado para a remoção de nitrogênio total e DQO de efluente de parboilização de arroz. O experimento foi realizado em reatores de bancada, com volumes de 4 L (UASB e 3,6 L (reator aeróbio. Os parâmetros de operação pH, temperatura, alcalinidade e concentração de ácidos voláteis foram monitorados durante o período experimental. Para o reator aeróbio de mistura completa, foi determinada, também, a concentração de oxigênio dissolvido. O sistema combinado reator UASB-reator aeróbio apresentou uma eficiência de remoção de carbono de 84% e uma eficiência de remoção de nitrogênio total Kjeldahl de 83%. O sistema proposto, nas condições experimentais, demonstrou ser adequado para remoção, simultânea, de DQO e de compostos oxidados de nitrogênio, em reator UASB.An UASB-aerobic reactor system was used for the removal of total nitrogen and COD of effluent from industries of parboilized rice. The experiment was performed in reactors with volumes of 4 L (UASB reactor and 3,6 L (aerobic reactor, respectevely. Temperature, pH, alkalinity and volatile acids concentration were monitored during the experiment. Dissolved oxygen concentration was determined for the aerobic reactor. The UASB-aerobic reactor system showed 84% carbon removal efficiency and 83% total Kjeldahl nitrogen removal efficiency. This system was able to remove, efficiently, COD and nitrogen in an UASB reactor.

Reactor operation

CERN Document Server

Shaw, J

2013-01-01

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

Improved nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding liquid metal coolant and housing the core within the pool. A generally cylindrical concrete containment structure surrounds the reactor vessel and a central support pedestal is anchored to the containment structure base mat and supports the bottom wall of the reactor vessel and the reactor core. The periphery of the reactor vessel bore is supported by an annular structure which allows thermal expansion but not seismic motion of the vessel, and a bed of thermally insulating material uniformly supports the vessel base whilst allowing expansion thereof. A guard ring prevents lateral seismic motion of the upper end of the reactor vessel. The periphery of the core is supported by an annular structure supported by the vessel base and keyed to the vessel wall so as to be able to expand but not undergo seismic motion. A deck is supported on the containment structure above the reactor vessel open top by annular bellows, the deck carrying the reactor control rods such that heating of the reactor vessel results in upward expansion against the control rods. (author)

Reactor as furnace and reactor as lamp

International Nuclear Information System (INIS)

Goldanskii, V.I.

1992-01-01

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

Development of Reactor Console Simulator for PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Mohd Idris Taib; Izhar Abu Hussin; Mohd Khairulezwan Abdul Manan; Nufarhana Ayuni Joha; Mohd Sabri Minhat

2012-01-01

The Reactor Console Simulator will be an interactive tool for operator training and teaching of PUSPATI TRIGA Reactor. Behaviour and characteristic for reactor console and reactor itself can be evaluated and understand. This Simulator will be used as complement for actual present reactor console. Implementation of man-machine interface is using computer screens, keyboard and mouse. Multiple screens are used to match the physical of present reactor console. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate the estimated reactor console parameters. (author)

Mechanism design for the control rods conduction of TRIGA Mark III reactor in the NINR; Diseno del mecanismo para la conduccion de las barras de control del reactor Triga Mark III del ININ.

Energy Technology Data Exchange (ETDEWEB)

Franco C, A

1997-12-01

This work presents in the first chapter a general studio about the reactor and the importance of control rods in the reactor , the mechaniucal design attending to requisitions that are imposed for conditions of operation of the reactor are present in the second chapter, the narrow relation that exists with the new control console and the mechanism is developed in the thired chapter, this relation from a point of view of an assembly of components is presents in fourth chapter, finally reaches and perspectives of mechanism forming part of project of the automation of reactor TRIGA MARK III, are present in the fifth chapter. (Author).

Reactor safeguards

CERN Document Server

Russell, Charles R

1962-01-01

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

Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

International Nuclear Information System (INIS)

Greneche, D.

2014-01-01

This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

Control of reactor coolant flow path during reactor decay heat removal

International Nuclear Information System (INIS)

Hunsbedt, A.N.

1988-01-01

This patent describes a sodium cooled reactor of the type having a reactor hot pool, a slightly lower pressure reactor cold pool and a reactor vessel liner defining a reactor vessel liner flow gap separating the hot pool and the cold pool along the reactor vessel sidewalls and wherein the normal sodium circuit in the reactor includes main sodium reactor coolant pumps having a suction on the lower pressure sodium cold pool and an outlet to a reactor core; the reactor core for heating the sodium and discharging the sodium to the reactor hot pool; a heat exchanger for receiving sodium from the hot pool, and removing heat from the sodium and discharging the sodium to the lower pressure cold pool; the improvement across the reactor vessel liner comprising: a jet pump having a venturi installed across the reactor vessel liner, the jet pump having a lower inlet from the reactor vessel cold pool across the reactor vessel liner and an upper outlet to the reactor vessel hot pool

The research reactors their contribution to the reactors physics

International Nuclear Information System (INIS)

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

2000-01-01

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

Reactor noise analysis of experimental fast reactor 'JOYO'

International Nuclear Information System (INIS)

Ohtani, Hideji; Yamamoto, Hisashi

1980-01-01

As a part of dynamics tests in experimental fast reactor ''JOYO'', reactor noise tests were carried out. The reactor noise analysis techniques are effective for study of plant characteristics by determining fluctuations of process signals (neutron signal, reactor inlet temperature signals, etc.), which are able to be measured without disturbances for reactor operations. The aims of reactor noise tests were to confirm that no unstable phenomenon exists in ''JOYO'' and to gain initial data of the plant for reference of the future data. Data for the reactor noise tests treated in this paper were obtained at 50 MW power level. Fluctuations of process signals were amplified and recorded on analogue tapes. The analysis was performed using noise code (NOISA) of digital computer, with which statistical values of ASPD (auto power spectral density), CPSD (cross power spectral density), and CF (coherence function) were calculated. The primary points of the results are as follows. 1. RMS value of neutron signal at 50 MW power level is about 0.03 MW. This neutron fluctuation is not disturbing reactor operations. 2. The fluctuations of A loop reactor inlet temperatures (T sub(AI)) are larger than the fluctuations of B loop reactor inlet temperature (T sub(BI)). For this reason, the major driving force of neutron fluctuations seems to be the fluctuations of T sub(AI). 3. Core and blanket subassemblies can be divided into two halves (A and B region), with respect to the spacial motion of temperature in the reactor core. A or B region means the region in which sodium temperature fluctuations in subassembly are significantly affected by T sub(AI) or T sub(BI), respectively. This phenomenon seems to be due to the lack of mixing of A and B loop sodium in lower plenum of reactor vessel. (author)

A study of digital hardware architectures for nuclear reactors protection systems applications - reliability and safety analysis methods; Um estudo de arquiteturas de hardware para aplicacao em sistemas digitais de protecao de reatores nucleares - metodos de analise de confiabilidade e seguranca

Energy Technology Data Exchange (ETDEWEB)

Benko, Pedro Luiz

1997-07-01

A study of digital hardware architectures, including experience in many countries, topologies and solutions to interface circuits for protection systems of nuclear reactors is presented. Methods for developing digital systems architectures based on fault tolerant and safety requirements is proposed. Directives for assessing such conditions are suggested. Techniques and the most common tools employed in reliability, safety evaluation and modeling of hardware architectures is also presented. Markov chain modeling is used to evaluate the reliability of redundant architectures. In order to estimate software quality, several mechanisms to be used in design, specification, and validation and verification (V and V) procedures are suggested. A digital protection system architecture has been analyzed as a case study. (author)

Reactor physics and reactor computations

International Nuclear Information System (INIS)

Ronen, Y.; Elias, E.

1994-01-01

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

Cold neutron source conceptual designing for Tehran Research Reactor

International Nuclear Information System (INIS)

Khajvand, N.; Mirvakili, S.M.; Faghihi, F.

2016-01-01

Highlights: • Cold neutron source conceptual designing for Tehran research reactor is carried out. • Type and geometry of moderator and dimensions of cold neutron source are analyzed. • Liquid hydrogen with more ortho-concentration can be better option as moderator. - Abstract: A cold neutron source (CNS) conceptual designing for the Tehran Research Reactor (TRR) were carried out using MCNPX code. In this study, a horizontal beam tube of the core which has appropriate the highest thermal flux is selected and parametric analysis to choose the type and geometry of the moderator, and the required CNS dimensions for maximizing the cold neutron production was performed. In this design the moderator cell has a spherical annulus structure, and the cold neutron flux and its brightness are calculated together with the nuclear heat load of the CNS for a variety of materials including liquid hydrogen, liquid deuterium, and solid methane. Based on our study, liquid hydrogen with more ortho-concentration than para and solid methane are the best options.

Caracterización de la infección de las vías urinarias en mujeres embarazadas atendidas en una entidad de primer nivel de atención (Manizales, Colombia) 2006-2010

OpenAIRE

Arroyave, Valentina; Cardona, Andrés Felipe; Castaño Castrillón, José Jaime; Giraldo, Viviana; Jaramillo, Mariana; Moncada, Norma Cecilia; Aicardo Ortiz, Ernesto; Villegas Arenas, Oscar Alberto

2010-01-01

ANTECEDENTES: Las infecciones del tracto urinario son las complicaciones más frecuentes del embarazo. Ocasionan una seria morbilidad materna y perinatal (parto pretérmino, peso bajo al nacer y ruptura prematura de membranas).MATERIALES Y METODOS: Estudio de corte transversal, con muestra de 1429 historias de gestantes que asistieron a controles prenatales y al parto en ASSBASALUD E. S. E. Manizales, Colombia. Para realizar este estu-dio se diseñó un instrumento, con las variables escogidas, p...

Theory of the Sagnac's interferometer of low birefringence and twist fiber; Teoria del interferometro de Sagnac de fibra de baja birrefrigencia y torcida

Energy Technology Data Exchange (ETDEWEB)

Estudillo-Ayala, J. M.; Kuzin, E. A.; Ibarra-Escamilla, B. [Instituto Nacional de Astrofisica, Optica y Electronica, Puebla (Mexico); Rojas-Laguna, R. [Universidad de Guanajuato, Guanajuato (Mexico)

2001-06-01

The fibre Sagnac interferometer of low birefringence and twist in the lineal region is examined numerically, a method is shown to measure the birefringence in the fibers and rotation of the axes inside of the interferometer fibre loop. [Spanish] El interferometro de Sagnac de fibra de baja birrefrigencia y torcida en la region lineal es numericamente examinado, se muestra un metodo para medir la birrefrigencia en las fibras y rotacion de los ejes dentro de la fibra del lazo del interferometro.

Reactor water spontaneous circulation structure in reactor pressure vessel

International Nuclear Information System (INIS)

Takahashi, Kazumi

1998-01-01

The gap between the inner wall of a reactor pressure vessel of a BWR type reactor and a reactor core shroud forms a down comer in which reactor water flows downwardly. A feedwater jacket to which feedwater at low temperature is supplied is disposed at the outer circumference of the pressure vessel just below a gas/water separator. The reactor water at the outer circumferential portion just below the air/water separator is cooled by the feedwater jacket, and the feedwater after cooling is supplied to the feedwater entrance disposed below the feedwater jacket by way of a feedwater introduction line to supply the feedwater to the lower portion of the down comer. This can cool the reactor water in the down comer to increase the reactor water density in the down comer thereby forming strong downward flows and promote the recycling of the reactor water as a whole. With such procedures, the reactor water can be recycled stably only by the difference of the specific gravity of the reactor water without using an internal pump. In addition, the increase of the height of the pressure vessel can be suppressed. (I.N.)

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-09-15

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

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

Energy Technology Data Exchange (ETDEWEB)

Cuevas Vivas, Gabriel Francisco

1999-12-01

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

Activación del topacio natural irradiado por neutrones en el núcleo del reactor RP-10

OpenAIRE

Gómez, J.; Parreño, Fernando; Lázaro, Gerardo; Vela, Mariano

2003-01-01

Se obtuvieron cristales de topacio activados al ser irradiados con neutrones dentro del núcleo del reactor RP-10. La activación depende del flujo de neutrones, por ello se desarrolló portamuestras (canes de irradiación) para absorber que son los causantes de la activación

REMOCIÓN DE ARSÉNICO (V ASISTIDA POR OXIDACIÓN UV SOLAR EN UN FOTO-REACTOR TUBULAR DE SECCIÓN CIRCULAR

Directory of Open Access Journals (Sweden)

Ramiro Escalera Vásquez

2010-01-01

Full Text Available Se ha construido y caracterizado un foto-reactor tubular de sección circular para su aplicación al tratamiento de aguas subterráneas contaminadas con Arsénico, As(V, utilizando las técnica de la Remoción de Arsénico por Oxidación Solar (RAOS. El concentrador solar que posee una capacidad de radiación equivalente a 2,8 soles, fue construido reciclando materiales desechados: tubos de vidrio proveniente de lámparas de Ne y tubos de desagüe sanitario de 6” (PVC, recubiertos por láminas de aluminio. Pruebas simultáneas sin agitación,realizadas aplicando la radiación UV solar a aguas sintéticas, demostraron que la remoción de As(V en el foto-reactor es más rápida queen un tubo de vidrio sólo y en una botella PET de 2 litros, logrando remociones mayores al 98% en todos los casos. Los tiempos para la aparición de los flóculos de complejo Fe-citrato fueron de 40, 50 y 90 min respectivamente, para intensidades de radiación UVA integral (290-390 nm entre 50 y 70 Wm-2. Pruebas de irradiación seguidas de agitación controlada a 30-33 s-1 de gradiente de velocidad, demostraron que el foto-reactor acelera el proceso de formación de flóculos fácilmente sedimentables al cabo de 20-30 min de agitación. Los tiempos de irradiación óptimos para el foto-reactor, el tubo y la botella son de 15, 25 y 60 min, respectivamente. Pruebas en régimen de flujo continuo en un foto-reactor de aproximadamente 1 m2 de área, con un tiempo de residencia hidráulica (igual al tiempo de irradiación de 15 min, mostraron la formación inmediata de flóculos fácilmente sedimentables cuando se agitan a 33 s-1 durante 20-30 min, lográndose una remoción del 98,36% una concentración remanente de 16,5 mgL-1 de As(V en aguas decantadas. Esto significa que se pueden tratar aproximadamente 130 Lm-2 en una jornada de 6 horas de radiación UVA de 50-70 Wm-2 de intensidad.

Reactor

International Nuclear Information System (INIS)

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

1979-01-01

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

Diseño de biorreactores para producir bioetanol a partir de residuos de piel de patata

OpenAIRE

Pérez Madroñal, Rafael Ángel

2018-01-01

El objetivo principal de este proyecto es el dimensionamiento de los reactores de hidrólisis y fermentación de una planta de bioetanol para poder producir 27 millones de litros al año de bioetanol, teniendo como materia prima residuos de piel de patata. Para obtener el bioetanol, se recoge el almidón presente en los residuos de la piel de patata y se hacen pasar por dos reacciones, un proceso de hidrólisis enzimática y un proceso de fermentación. En ambos se usarán enzimas de l...

Reactor Physics Training

International Nuclear Information System (INIS)

Baeten, P.

2007-01-01

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

FBR type reactor

International Nuclear Information System (INIS)

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

1994-01-01

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

RB Research nuclear reactor RB reactor, Annual report for 2000

International Nuclear Information System (INIS)

Milosevic, M.

2000-12-01

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

Reactor container

International Nuclear Information System (INIS)

Kato, Masami; Nishio, Masahide.

1987-01-01

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

Aprendizaje organizativo y generación de competencias

Directory of Open Access Journals (Sweden)

FLORENTINA MORENO PELÁEZ

1997-01-01

Full Text Available el aprendizaje organizativo es algo mas que la generacion de competencias en los miembros que actuan en la organizacion. el ao se materializa, como tal, en innovaciones organizativas (metodos, tecnologias, cultura, productos. con ello se consigue mejorar resultados y potenciar la relacion dialectica con el entorno, aumentando sus expectativas de superviviencia y desarrollo en el tiempo. para conseguir estos incrementos se debe dar un tipo de aprendizaje que llamamos organizativo-institucional, cuyo resultado es un "espacio cooperativo" superador de las barreras organizativas y de la logica competitiva interna que parcela saberes y los convierte en base de poderes particulares. son precisos, por tanto, dos enfoques metodologicos para abordar el problema: el pensamiento sistemico y el dialectico.

Reactor Physics Programme

Energy Technology Data Exchange (ETDEWEB)

De Raedt, C

2000-07-01

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

Reactor Physics Programme

International Nuclear Information System (INIS)

De Raedt, C.

2000-01-01

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

Construction of the Tangent to a Cycloid Proposed by Wallis and Fermat

Directory of Open Access Journals (Sweden)

Loredana Biacino

2017-02-01

Full Text Available In this paper some methods used in the XVII century for the construction of the tangents to a cycloid in a point are exposed: the kinematical method employed by Roberval, the classical geometrical  method used by Wallis and the Fermat’s construction as a consequence of his tangents method. Le Costruzioni della Tangente alla Cicloide Proposte da Wallis e da Fermat In questo lavoro sono esposti vari metodi in uso nel ‘600 per la costruzione della tangente ad una cicloide in un suo punto: il metodo cinematico impiegato da Roberval, il metodo geometrico classico usato dal Wallis e la costruzione di Fermat come conseguenza del suo metodo delle tangenti. Parole Chiave: Cicloide, Tangente ad una curva, Metodo cinematico delle tangenti, Metodo delle tangenti di Fermat.

Para-Hermitian and para-quaternionic manifolds

International Nuclear Information System (INIS)

Ivanov, S.; Zamkovoy, S.

2003-10-01

A set of canonical para-Hermitian connections on an almost para-Hermitian manifold is defined. A Para-hermitian version of the Apostolov-Gauduchon generalization of the Goldberg-Sachs theorem in General Relativity is given. It is proved that the Nijenhuis tensor of a Nearly para-Kaehler manifolds is parallel with respect to the canonical connection. Salamon's twistor construction on quaternionic manifold is adapted to the para-quaternionic case. A locally conformally hyper-para-Kaehler (hypersymplectic) flat structure with parallel Lee form on the Kodaira-Thurston complex surfaces modeled on S 1 x SL (2, R)-tilde is constructed. Anti-self-dual locally conformally hyper-para-Kaehler (hypersymplectic) neutral metrics with non vanishing Weyl tensor are obtained on the Inoe surfaces. An example of anti-self-dual neutral metric which is not locally conformally hyper-para-Kaehler (hypersymplectic) is constructed. (author)

Para-Hermitian and para-quaternionic manifolds

Energy Technology Data Exchange (ETDEWEB)

Ivanov, S [University of Sofia ' St. Kl. Ohridski' , Faculty of Mathematics and Informatics, Sofia (Bulgaria) and Abdus Salam International Centre for Theoretical Physics, Trieste (Italy); Zamkovoy, S [University of Sofia ' St. Kl. Ohridski' , Faculty of Mathematics and Informatics, Sofia (Bulgaria)

2003-10-01

A set of canonical para-Hermitian connections on an almost para-Hermitian manifold is defined. A Para-hermitian version of the Apostolov-Gauduchon generalization of the Goldberg-Sachs theorem in General Relativity is given. It is proved that the Nijenhuis tensor of a Nearly para-Kaehler manifolds is parallel with respect to the canonical connection. Salamon's twistor construction on quaternionic manifold is adapted to the para-quaternionic case. A locally conformally hyper-para-Kaehler (hypersymplectic) flat structure with parallel Lee form on the Kodaira-Thurston complex surfaces modeled on S{sup 1} x SL (2, R)-tilde is constructed. Anti-self-dual locally conformally hyper-para-Kaehler (hypersymplectic) neutral metrics with non vanishing Weyl tensor are obtained on the Inoe surfaces. An example of anti-self-dual neutral metric which is not locally conformally hyper-para-Kaehler (hypersymplectic) is constructed. (author)

Metodo integrado para la gestion de Universidades basado en el Balanced Scorecard (bsc y el modelo europeo de calidad (efqm: caso U.C.S.M.

Directory of Open Access Journals (Sweden)

Edwing Jesús Ticse Villanueva

2010-06-01

Full Text Available http://dx.doi.org/10.5007/1983-4535.2010v3n1p01   El presente Trabajo realiza la propuesta de un Método Integrado  que permite mejorar la competitividad en la Gestión de las Universidades, este método se basa: En una herramienta de Gestión Estratégica: el Balanced Scorecard (BSC, que fue creada por Kaplan y Norton en 1992; y En el Modelo  Europeo de Calidad (EFQM, que fue desarrollado como un Modelo de Excelencia en 1991. La metodología utilizada consiste en analizar las características, ventajas y limitaciones del BSC y el EFQM para aplicarlos simultáneamente en la gestión de Tomando como base los 9 criterios del EFQM, se desarrolla un Mapa Estratégico del BSC, para que se alineen todas las perspectivas hacia el logro de los Objetivos Estratégicos de la Organización. El método integrado planteado se aplica en el caso de la Universidad Católica de Santa María (Arequipa- Perú, donde se analiza las ventajas que implicaría la implementación del mismo

Evaluación del potencial acidogénico para producción de AGV de melaza de la industria azucarera como valorización de este subproducto

Directory of Open Access Journals (Sweden)

María Angélica Palomino

2016-06-01

Full Text Available Se evaluó el potencial acidogénico de la melaza de la industria azucarera en 4 diferentes OLR (6,02±4,33; 13,96±7,11; 15,81±4,83; 26,94±13,27kgDQO/m3.d en un reactor de fl ujo ascendente, con lodo granular. El sistema no contó con control de pH e inhibición de la fase metanogénica. El reactor operó en continuo durante 148 días. Para evaluar el potencial acidogénico se utilizó el grado de acidifi cación neto (GAn. Los resultados mostraron que durante las tres primeras OLR el %GAn (29,46 ± 13,01; 20,23 ± 13,67; 24,63 ± 19,49 se mantuvo sin diferencias signifi cativas, pero para la mayor OLR el %GAn disminuyó a la tercera parte (10,21 ± 7,14, mientras la concentración de AGV fue la mayor para esta fase (2644,89mgDQO/L, además se avaluó el balance de DQO para cada una de las fases, donde el % de AGV en el efl uente representó el porcentaje orgánico fermentable rápidamente en el efl uente, estos valores indican que con una recirculación interna se podría mejorar el %GAn u obtener otra serie de productos de base biológica para el aprovechamiento de este residuo. En este artículo se utilizó un reactor de fl ujo ascendente como alternativa a los estudiados (CSRT y batch presentando diferentes resultados

Nuclear reactors. Introduction

International Nuclear Information System (INIS)

Boiron, P.

1997-01-01

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

Ultrasonic Water-Gap Measurements in MTR Fuel Elements; Mesure par Ultrasons des Espaces Intercalaires dans les Elements Combustibles des Reacteurs d'Essai de Materiaux; Izmereniya vodyanogo zazora v teplovydelyayushchikh ehlementakh dlya materialovedcheskogo reaktora s pomoshch'yu ul'trazvuka; Medicion Ultrasonica de la Capa de Agua en Elementos Combustibles para Reactores de Ensayo de Materiales

Energy Technology Data Exchange (ETDEWEB)

Deknock, R. [Metallurgy Department, S.C.K./C.E.N., Mol (Belgium)

1965-10-15

distance intercalaire fournit a un enregistreur une tension stable de sortie de 1 V. Il est facile de mesurer les variations des distances intercalaires avec une precision de 5 {mu}m. Les mesures ont ete faites pour plusieurs elements combustibles. Les resultats et la reproductibilite sont tres satisfaisants. (author) [Spanish] Los elevados flujos termicos que suelen alcanzarse en los recientes reactores de ensayo de materiales, exigen recorridos adecuados para lograr una transmisiun uniforme de calor y una disipacion segura del mismo, evitando asf la formacion de vapor en la masa. Ademas, a fin de controlar el hinchamiento y el comportamiento del combustible en el reactor, tambien debe medirse la capa de agua en experimentos realizados despues de la irradiacion, con elementos combustibles agotados. A tal efecto se ha disenado una sonda ultrasonica destinada a medir, en una longitud de 1 m el espesor de 3 mm de agua correspondiente al elemento combustible BR-2. En el caso de los experimentos posteriores a la irradiacion, es necesario trabajar con el elemento combustible sumergido en un tanque de agua, a profundidad no menor de 6 m. La sonda puede resistir una prolongada inmersion en agua, y no le afectan las dosis normales de radiacion gamma. Aunque proyectado conforme al metodo usual de reflexion de impulsos, el sistema permite separar pulsos emitidos y reflejados, usando un cristal ferro-electrico de 10 MHz, con elevada disipacion inherente de energia. Puede usarse un osciioscopio para la lectura, en cuyo caso el tiempo se representa en el eje horizontal, regulandose la velocidad de barrido de manera que sea directamente proporcional a la velocidad de propagacion de la onda, es decir, al espesor de la capa de agua. Este tipo de representacion da resultados satisfactorios cuando setrata de un numero limitado de mediciones, pero sin duda resulta mas conveniente el registro grafico. En este caso, se da a los impulsos emitidos y reflejados la forma deseada y se les inyecta

Improved Techniques for Low-Flux Measurement of Prompt Neutron Lifetime, Conversion Ratio and Fast Spectra; Methodes Perfectionnees de Mesure de la Duree de Vie des Neutrons Instantanes, du Rapport de Conversion et des Spectres de Neutrons Rapides, dans un Reacteur a Bas Flux; Usovershenstvovannye metody izmereniya vremeni zhizni mgnovennykh nejtronov, koehffitsienta konversii i spektra bystrykh nejtronov pri slabykh potokakh nejtronov; Tecnicas Perfeccionadas para la Determinacion del Periodo de los Neutrones Inmediatos, la Razon de Conversion y los Espectros de Neutrones Rapidos, con Flujos Reducidos

Energy Technology Data Exchange (ETDEWEB)

Armani, R. J.; Bennett, E. F.; Brenner, M. W.; Bretscher, M. M.; Cohn, C. E.; Huber, R. J.; Kaufmann, S. G.; Redman, W. C. [Argonne National Laboratory, Argonne, IL (United States)

1964-02-15

a mi- hauteur 1,5%), pour la somme des impulsions dans l'irradiation par les neutrons thermiques. (author) [Spanish] En el programa del reactor ZPR, se han aplicado varios metodos estadfsticos para determinar la razon perfodo de los neutrones inmediatos/perfodo de la fraccion de neutrones retardados. Los autores idearon uno de los metodos, consistente en el analisis del ruido del reactor con un filtro de paso de banda, y perfeccionaron otros, taies como la medicion de la frecuencia de coincidencias retardadas entre los impulsos del contador en funcion del retardo, y la determinacion de la variancia relativa de las integrales de tiempo del flu jo neutronico en funcion del tiempo de integracion. Han estudiado en que terrenos se aplican mas ventajosamente los distintos metodos. Tambien han procurado interpretar los resultados de las mediciones precitadas y han comprobado que la interpretacion basada en un modelo cinetico simple puede aplicarse a numerosos casos practicos. Los autores describen varios perfeccionamientos introducidos en su metodo original de activacion para la determinacion de la razon produccion/destruccion de material fisionable, con flujos reducidos. Entre ellos figuran la aplicacion de tecnicas radioqufmicas de alta sensibilidad como procedimiento de confirmacion; la correccion de impulsos parasitos, mediante laminas de diferente grado de enriquecimiento, para determinar la contribucion de la fision del material fertii a la actividad de los productos de fision, asi como Iaminas expuestas a los diferentes espectros para medir los impulsos relacionados con los sucesos de fision en la determinacion de la captura; y en el empleo del recuento por coincidencias para la deteccion de la desintegracion del {sup 239}Np. Para deducir la razon de conversion partiendo de los datos relativos a la activacion, es preciso conocer el coeficiente {alpha}, es decir, la razon capturas/fisiones en el combustible. Por ahora no existe ninguen metodo experimental que permita

Nuclear reactor, reactor core thereof, and device for constituting the reactor

International Nuclear Information System (INIS)

Takiyama, Masashi.

1994-01-01

A reactor core is constituted by charging coolants (light water) in a reactor pressure vessel and distributing fuel assemblies, reflecting material sealing pipes, moderator (heavy water and helium gas) sealing pipes, and gas sealing pipes therein. A fuel guide tube is surrounded by a cap and the gap therebetween is made hollow and filled with coolant steams. The cap is supported by a baffle plate. The moderator sealing pipe is disposed in a flow channel of coolants in adjacent with the cap. The position of the moderator sealing tube in the reactor core is controlled by water stream from a hydraulic pump with a guide tube extending below the baffle plate being as a guide. Then, the position of the moderator sealing tube is varied to conduct power control, burnup degree compensation, and reactor shut down. With such procedures, moderator cooling facility is no more necessary to simplify the structure. Further, heat generated from the moderator is transferred to the coolants thereby improving heat efficiency of the reactor. (I.N.)

Slurry reactors

Energy Technology Data Exchange (ETDEWEB)

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

1979-08-01

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

Optimal reactor strategy for commercializing fast breeder reactors

International Nuclear Information System (INIS)

Yamaji, Kenji; Nagano, Koji

1988-01-01

In this paper, a fuel cycle optimization model developed for analyzing the condition of selecting fast breeder reactors in the optimal reactor strategy is described. By dividing the period of planning, 1966-2055, into nine ten-year periods, the model was formulated as a compact linear programming model. With the model, the best mix of reactor types as well as the optimal timing of reprocessing spent fuel from LWRs to minimize the total cost were found. The results of the analysis are summarized as follows. Fast breeder reactors could be introduced in the optimal strategy when they can economically compete with LWRs with 30 year storage of spent fuel. In order that fast breeder reactors monopolize the new reactor market after the achievement of their technical availability, their capital cost should be less than 0.9 times as much as that of LWRs. When a certain amount of reprocessing commitment is assumed, the condition of employing fast breeder reactors in the optimal strategy is mitigated. In the optimal strategy, reprocessing is done just to meet plutonium demand, and the storage of spent fuel is selected to adjust the mismatch of plutonium production and utilization. The price hike of uranium ore facilitates the commercial adoption of fast breeder reactors. (Kako, I.)

Methodology for the accelerated simulation of the deterioration that by atmospheric corrosion appears in electronic equipment; Metodologia para la simulacion acelerada del deterioro que por corrosion atmosferica se presenta en equipo electronico

Energy Technology Data Exchange (ETDEWEB)

Ortiz Prado, A.; Schouwenaars, R.; Cerrud Sanchez, S.M. [Facultad de Ingenieria, UNAM, Mexico, D.F. (Mexico)

2002-12-01

The corrosion resistance of systems and electronic parts which are designed to work in atmospheric conditions have been tested for decades; some of these methods were the Cyclic Humidity Test, Field Tests and Salt Spray (Fog) Testing, the latter was one of the most popular methods. However, the salt spray test and most of the other existing methods do not show strong relationships with the real conditions of service. For this reason, it is necessary to develop appropriated methods and equipment for the accelerated simulation of real atmospheric corrosion phenomena. This article seeks to demonstrate the need to develop a test and the necessary equipment to reproduce the damage in electronic systems and equipment by atmospheric corrosion. [Spanish] Para la evaluacion de la resistencia a la corrosion de sistemas y equipo electronico que trabajaran bajo condiciones de deterioro generadas por el medio ambiente, se han aplicado una serie de ensayos, donde el mas popular es el de camara de niebla salina. Sin embargo, este y otros que se han elaborado para tal efecto no tienen ninguna relacion con las condiciones reales de servicio, por lo que es necesario un metodo de evaluacion que permita simular de forma acelerada los fenomenos de deterioro por efectos ambientales. Este articulo pretende demostrar la necesidad de desarrollar una prueba, que en forma acelerada, reproduzca el dano que sufre el material por efecto de la atmosfera; el cual se orienta a la evaluacion de equipo electrico y electronico.

The Application of Various Nondestructive Testing Methods to Fuel Elements of the Orgel Type; Application des Differentes Methodes d'Essais Non Destructifs aux Elements Combustibles du Type Orgel; Primenenie razlichnykh nedestruktivnykh metodov ispytanij k toplivnym ehlementam tipa ''orgel''; Aplicacion de Distintos Metodos de Ensayo No Destructivo a los Elementos Combustibles de Tipo Orgel

Energy Technology Data Exchange (ETDEWEB)

Bonnet, P.; Jansen, J. [EURATOM, C.C.R., Ispra (Italy)

1965-09-15

methode a un capteur montre quelles sont les limites d'utilisation de ces deux methodes. Defauts transversaux; La methode a un capteur appliquee a cette recherche fait l'objet d'une breve description. Entrainement mecanique: Le memoire fait etat d'un banc mecanique, type laboratoire, pour la recherche des criteres d'essais et d'un banc de passage des tubes, de type semi-industriel, pour l'examen en continu avec enregistrement des defauts. Les difficultes rencontrees et les moyens misenceuvrepoury remediersont evoques. c) Tests par radiographie. Cette methode fera l'objet d'un memoire special; seuls sont indiques les resultats obtenus sur tubes de force ou sur tubes de gaines. d) Test divers Les test finaux sur elements combustibles complets peuvent se resumer en deux parties. Tests d'etancheite au moyen du test a l'helium developpe par la SOGEV. Un dispositif permet d'examiner simultanement 4 ou 6 elements combustibles ou separement 2 ou 3. Tests classiques de radiographie; l'accent est mis plus particulierement sur l'etude des soudures; on donne la marge des conditions experimentales pour obtenir une bonne definition. En conclusion, les auteurs presentent un projet de chaine de controle semi-industrielle avec les differentes possibilites de traitements et essaient de degager une certaine philosophie des tests non destructifs appliques aux elements combustibles. (author) [Spanish] La memoria presenta los distintos metodos empleados para deteccion de fallas (de tipo dimensional o estructural) en vainas de elementos combustibles. Los autores describen, asimismo, los ensayos finales con elementos combustibles completos, en particular radiografia de las soldaduras y pruebas de estanqueidad. Este tema se ha tratado ya en forma parcial. El estudio de las caracteristicas dimensionales de las vainas lisas de SAP (producto de aluminio sinterizado) ha sido objeto de trabajos bastante avanzados. La memoria examina en particular los siguientes temas: 1. Medicion de diametros internos

Computerized reactor monitor and control for nuclear reactors

International Nuclear Information System (INIS)

Buerger, L.

1982-01-01

The analysis of a computerized process control system developed by Transelektro-KFKI-Videoton (Hangary) for a twenty-year-old research reactor in Budapest and or a new one in Tajura (Libya) is given. The paper describes the computer hardware (R-10) and the implemented software (PROCESS-24K) as well as their applications at nuclear reactors. The computer program provides for man-machine communication, data acquisition and processing, trend and alarm analysis, the control of the reactor power, reactor physical calculations and additional operational functions. The reliability and the possible further development of the computerized systems which are suitable for application at reactors of different design are also discussed. (Sz.J.)

Síntesis de membranas cerámicas para la regeneración de baños de cromado agotados

Directory of Open Access Journals (Sweden)

Sánchez, E.

2005-12-01

Full Text Available Ceramic membranes intended for use as compartment separators in electrochemical reactors used for recycling spent chromium plating baths have been synthesised. Two variables of the membrane synthesis process have been studied (pressing pressure and organic matter addition, to enable designing prototypes with the appropriate characteristics to act as separators, at a low manufacturing cost.

Se han sintetizado membranas cerámicas destinadas a la función de separadores entre los compartimentos de un reactor electroquímico, cuya aplicación es el reciclado de baños de cromado usados. Se han estudiado dos variables del proceso de síntesis de las membranas (presión de prensado y adición de materia orgánica, para conseguir prototipos con las características adecuadas para realizar la función de separador, y a la vez conseguir un coste de fabricación reducido.

Safeguarding research reactors

International Nuclear Information System (INIS)

Powers, J.A.

1983-03-01

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

Control of reactor coolant flow path during reactor decay heat removal

Science.gov (United States)

Hunsbedt, Anstein N.

1988-01-01

An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

Reactor operations Brookhaven medical research reactor, Brookhaven high flux beam reactor informal monthly report

International Nuclear Information System (INIS)

Hauptman, H.M.; Petro, J.N.; Jacobi, O.

1995-04-01

This document is the April 1995 summary report on reactor operations at the Brookhaven Medical Research Reactor and the Brookhaven High Flux Beam Reactor. Ongoing experiments/irradiations in each are listed, and other significant operations functions are also noted. The HFBR surveillance testing schedule is also listed

Reactor core for FBR type reactor

International Nuclear Information System (INIS)

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

1996-01-01

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

Space-time reactor kinetics for heterogeneous reactor structure

Energy Technology Data Exchange (ETDEWEB)

Raisic, N [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

1969-11-15

An attempt is made to formulate time dependent diffusion equation based on Feinberg-Galanin theory in the from analogue to the classical reactor kinetic equation. Parameters of these equations could be calculated using the existing codes for static reactor calculation based on the heterogeneous reactor theory. The obtained kinetic equation could be analogues in form to the nodal kinetic equation. Space-time distribution of neutron flux in the reactor can be obtained by solving these equations using standard methods.

Determination of hydrazine in third loops of China experimental fast reactor by spectrophotometry

International Nuclear Information System (INIS)

Huang Wenjie; Wang Mi; Gao Yaopeng; Xie Chun; Yu Xiaochen

2013-01-01

The method for the determination of hydrazine by Uv-vis spectrophotometer was proposed. The coloration conditions and instrument parameters were also optimized. In HCl, hydrazine formed a yellow azine with para-dimethyl aminobenzaldehyde ((CH 3 ) 2 NC 6 H 4 CHO), and then determined by spectrophotometer. The complex's maximum absorption was exhibited at 458 nm. The coloration effect was excellent in conditions of 1% HCl, 10 mL para-dimethyl aminobenzaldehyde and 10 minutes' developing time. A good liner relationship was obtained in the range of 5∼200 μg/L, and the recovery was (101.1±1.9)%. This method was used in the third loop of China experimental fast reactor with satisfactory results. (authors)

Nuclear Reactor RA Safety Report, Vol. 4, Reactor

International Nuclear Information System (INIS)

1986-11-01

RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices [sr

Implementacion de modulos constructivistas que atiendan "misconceptions" y lagunas conceptuales en temas de la fisica en estudiantes universitarios

Science.gov (United States)

Santacruz Sarmiento, Neida M.

Este estudio se enfoco en los "misconception" y lagunas conceptuales en temas fundamentales de Fisica como son Equilibrio Termodinamico y Estatica de fluidos. En primer lugar se trabajo con la identificacion de "misconceptions" y lagunas conceptuales y se analizo en detalle la forma en que los estudiantes construyen sus propias teorias de fenomenos relacionados con los temas. Debido a la complejidad en la que los estudiantes asimilan los conceptos fisicos, se utilizo el metodo de investigacion mixto de tipo secuencial explicativo en dos etapas, una cuantitativa y otra cualitativa. La primera etapa comprendio cuatro fases: (1) Aplicacion de una prueba diagnostica para identificar el conocimiento previo y lagunas conceptuales. (2) Identificacion de "misconceptions" y lagunas del concepto a partir del conocimiento previo. (3) Implementacion de la intervencion por medio de modulos en el topico de Equilibrio Termodinamico y Estatica de Fluidos. (4) Y la realizacion de la pos prueba para analizar el impacto y la efectividad de la intervencion constructivista. En la segunda etapa se utilizo el metodo de investigacion cualitativo, por medio de una entrevista semiestructurada que partio de la elaboracion de un mapa conceptual y se finalizo con un analisis de datos conjuntamente. El desarrollo de este estudio permitio encontrar "misconceptions" y lagunas conceptuales a partir del conocimiento previo de los estudiantes participantes en los temas trabajados, que fueron atendidos en el desarrollo de las distintas actividades inquisitivas que se presentaron en el modulo constructivista. Se encontro marcadas diferencias entre la pre y pos prueba en los temas, esto se debio al requerimiento de habilidades abstractas para el tema de Estatica de Fluidos y al desarrollo intuitivo para el tema de Equilibrio Termodinamico, teniendo mejores respuestas en el segundo. Los participantes demostraron una marcada evolucion y/o cambio en sus estructuras de pensamiento, las pruebas estadisticas

Feasible reactor power cutback logic development for an integral reactor

International Nuclear Information System (INIS)

Han, Soon-Kyoo; Lee, Chung-Chan; Choi, Suhn; Kang, Han-Ok

2013-01-01

Major features of integral reactors that have been developed around the world recently are simplified operating systems and passive safety systems. Even though highly simplified control system and very reliable components are utilized in the integral reactor, the possibility of major component malfunction cannot be ruled out. So, feasible reactor power cutback logic is required to cope with the malfunction of components without inducing reactor trip. Simplified reactor power cutback logic has been developed on the basis of the real component data and operational parameters of plant in this study. Due to the relatively high rod worth of the integral reactor the control rod assembly drop method which had been adapted for large nuclear power plants was not desirable for reactor power cutback of the integral reactor. Instead another method, the control rod assembly control logic of reactor regulating system controls the control rod assembly movements, was chosen as an alternative. Sensitivity analyses and feasibility evaluations were performed for the selected method by varying the control rod assembly driving speed. In the results, sensitivity study showed that the performance goal of reactor power cutback system could be achieved with the limited range of control rod assembly driving speed. (orig.)

Verificación de la contaminación del maíz por flatoxina B1

Directory of Open Access Journals (Sweden)

Lisa Vallone

2010-10-01

Full Text Available “Aflaflesh” es un instrumento computarizado, diseñado para combinar un metodo de adquisición de datos visuales, con sofisticados sistemas operativosde software y análisis de imágenes. Esto, mediante la exposicion de la fluorescencia de maíz sometido a la radiación UV, ya que si hay contaminación con aflatoxinas B1, es posible transformar directamente el número de pixeles de la fluorescencia, en la concentración de AFB1 correspondiente.

Cineantropometría: composición corporal y somatotipo de futbolistas que desarrollan su actividad física en equipos de la Comunidad Autónoma de Madrid

OpenAIRE

Herrero de Lucas, Ángel

2004-01-01

Definimos Cineantropometría como el estudio del tamaño, forma, proporcionalidad, composición, maduración biológica y función corporal; con objeto de entender el proceso del crecimiento, el ejercicio, el rendimiento deportivo y la nutrición. OBJETIVOS: Estudio controlado, transversal, no randomizado, de tipo observacional y analítico cineantropométrico. MATERIAL Y METODO: Utilizamos el protocolo de medidas establecido por la Sociedad Internacional para el Avance de la Cineantropometría (I.S.A....

RA Reactor

International Nuclear Information System (INIS)

1978-02-01

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

H Reactor

Data.gov (United States)

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

Desenvolvimento e validação de metodos para a determinação de antimicrobianos em leite e farmacos usando a cromatografia liquida de alta eficiencia e eletroforese capilar

OpenAIRE

Monica Cecilia Vargas Mamani

2007-01-01

Resumo: Antimicrobianos são largamente empregados na medicina veterinária e resíduos destes podem permanecer nos alimentos de origem animal, acima de valores considerados seguros, quando não são respeitadas as boas práticas veterinárias. O objetivo deste trabalho foi o desenvolvimento e validação de métodos para a determinação de tetraciclinas, sulfonamidas, cloranfenicol e fluoroquinolonas em fármacos usando a eletroforese capilar (CE), assim como método multiresíduos para a determinação de ...

Reactor container

International Nuclear Information System (INIS)

Naruse, Yoshihiro.

1990-01-01

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

Hybrid reactors

International Nuclear Information System (INIS)

Moir, R.W.

1980-01-01

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

Copolymers of new generation for the dehydrated crude oil (petroleum); Copolimeros de nueva generacion para el deshidratado de aceite crudo (petroleo)

Energy Technology Data Exchange (ETDEWEB)

Castro Sotelo, Laura Veronica [Instituto Politecnico Nacional ESIQIE, Mexico, D.F. (Mexico)]. E-mail: lcastros@ipn.mx; Flores Oropeza, Eugenio Alejandro; Hernandez Cortez, Jose Gonzalo; Lopez Ortega, Alfonso; Arreguin Valencia, Felipe [Instituto Mexicano del Petroleo, Mexico, D.F. (Mexico)]. E-mail: eaflores@imp.mx; jhcortez@imp.mx; alopezo@imp.mx; flos2099@yahoo.com.mx; Hernandez Garcia, Arnulfo [Universidad Nacional Autonoma de Mexico, Facultad de Quimica, Mexico, D.F. (Mexico)]. E-mail: arte8080@hotmail.com; Hernandez Xilohua, Arturo Eutiquio [Instituto Mexicano del Petroleo Mexico, D.F. (Mexico)]. E-mail: art_eut@hotmail.com; Ramirez Gutierrez, David; Hernandez Carbajal, Edgar Ivan [Instituto Politecnico Nacional, ESIQIE, Mexico, D.F. (Mexico)]. Email: theprettiestthingever@hotmail.com; hcei11@hotmail.com; Vazquez Moreno, Flavio Salvador [Instituto Mexicano del Petroleo, Mexico, D.F. (Mexico)]. E-mail: flaviusmx@yahoo.com.mx

2010-11-15

Crude oil is a mixture of hydrocarbons, salts and water as impurities. When crude oil has high water content, their commercial value is reduced in the market, so the separation of these impurities is important for a better quality product. The content of these impurities in the crude oil reduction is a concern across the world. There are several methods for crude oil dehydration and breaking emulsions; this work presents the results of tests demulsifiers, agents which are different molecular mass polyethers. Using several test bottles compared performance agents demulsifiers which were assessed at different concentrations in a heavy crude oil from wells in the southeast of Mexico. The evaluation results showed the range of molecular mass of polymers that provide better performance for the abatement of the water content in the crude oil. [Spanish] El aceite crudo es una mezcla de hidrocarburos, sales y agua como impurezas. Cuando el aceite crudo presenta alto contenido de agua, su valor a nivel comercial se reduce en el mercado, por lo que es importante la separacion de estas impurezas para obtener un producto de mejor calidad. La reduccion del contenido de estas impurezas en el aceite crudo es una preocupacion a nivel mundial. Existen varios metodos para la deshidratacion del aceite crudo y romper las emulsiones; en este trabajo se presentan los resultados de pruebas con agentes desemulsificantes, los cuales son polieteres de diferente masa molecular. Mediante varias pruebas de botellas se comparo el desempeno de los agentes desemulsificantes los cuales fueron evaluados a diferentes concentraciones en un aceite crudo pesado procedente de pozos del Sureste de Mexico. Los resultados de la evaluacion mostraron el intervalo de masa molecular de los polimeros que proporcionan un mejor desempeno en el abatimiento del contenido de agua en el aceite crudo.

Nuclear research reactors

International Nuclear Information System (INIS)

1985-01-01

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

Strategic planning for research reactors. Guidance for reactor managers

International Nuclear Information System (INIS)

2001-04-01

The purpose of this publication is to provide guidance on how to develop a strategic plan for a research reactor. The IAEA is convinced of the need for research reactors to have strategic plans and is issuing a series of publications to help owners and operators in this regard. One of these covers the applications of research reactors. That report brings together all of the current uses of research reactors and enables a reactor owner or operator to evaluate which applications might be possible with a particular facility. An analysis of research reactor capabilities is an early phase in the strategic planning process. The current document provides the rationale for a strategic plan, outlines the methodology of developing such a plan and then gives a model that may be followed. While there are many purposes for research reactor strategic plans, this report emphasizes the use of strategic planning in order to increase utilization. A number of examples are given in order to clearly illustrate this function

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1991-04-01

The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

Spectrographic determination of metallic impurities in organic coolants for nuclear reactors; Determinacion espectrografica de impurezas metalicas en refrigerantes organicos para reactores nucleares

Energy Technology Data Exchange (ETDEWEB)

Martin Munoz, M; Alvarez Gonzalez, F

1969-07-01

A spectrochemical method for determining metallic impurities in organic coolants for nuclear reactors is given. The organic matter in solid samples is eliminated by controlled distillation and dry ashing in the presence of magnesium oxide as carrier. Liquid, samples are vacuum distillated. The residue is analyzed by carrier distillation and by total burning techniques. The analytical results are discussed and compared with those obtained destroying the organic matter without carrier and using the copper spark technique. (Author) 12 refs.

Research reactors - an overview

International Nuclear Information System (INIS)

West, C.D.

1997-01-01

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

Multiregion reactors

International Nuclear Information System (INIS)

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

1979-08-01

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

REMOVAL OF ORGANIC MATTER AND TOXICITY IN AN UPFLOW IMMOBILIZED BIOMASS ANAEROBIC REACTOR TREATING HOSPITAL WASTEWATER: PRELIMINARY EVALUATION

Directory of Open Access Journals (Sweden)

MÓNICA PORRAS TORRES

2013-01-01

Full Text Available El objetivo de esta investigación consistió en evaluar el desempeño de un reactor anaerobio de flujo ascendente de biomasa inmovilizada (RAFABI tratando un efluente hospitalario real. Se estudió la remoción de materia orgánica y toxicidad, por medio de análisis como UV254, DQOfiltrada y determinación del porcentaje de inhibición en el crecimiento de la raíz de la cebolla. Los resultados mostraron que el proceso biológico estuvo estable durante los 287 días de operación continua, el valor medio de la relación AI/AP fue de 1.21±0.08, indicando que no hubo acumulación de ácidos en el sistema. Sin embargo, los valores de la eficiencia de remoción de DQOfiltrada, 56±15% y UV254, 21±36%, no fueron representativos. La toxicidad se redujo en 50%. Con base en lo anterior, es necesario utilizar el reactor anaerobio en combinación con otros procesos como por ejemplo los procesos de oxidación avanzada, para continuar reduciendo la materia orgánica recalcitrante al proceso anaerobio. Se comprobó la capacidad que tienen los reactores anaerobios de biomasa inmovilizada para remover la toxicidad.

Reactor building

International Nuclear Information System (INIS)

Maruyama, Toru; Murata, Ritsuko.

1996-01-01

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

Nuclear reactor

International Nuclear Information System (INIS)

Garabedian, G.

1988-01-01

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

Reactor physics challenges in GEN-IV reactor design

Energy Technology Data Exchange (ETDEWEB)

Driscoll, Michael K.; Hejzlar, Pavel [Massachusetts Institute of Technology, MA (United States)

2005-02-15

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources.

Reactor physics challenges in GEN-IV reactor design

International Nuclear Information System (INIS)

Driscoll, Michael K.; Hejzlar, Pavel

2005-01-01

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources

Reactor Vessel Surveillance Program for Advanced Reactor

Energy Technology Data Exchange (ETDEWEB)

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

2008-10-15

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

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

Energy Technology Data Exchange (ETDEWEB)

Merced D, J. E.

2016-07-01

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

Análisis teórico de la influencia del régimen de mezclado para la producción de acetato de etilo

Directory of Open Access Journals (Sweden)

Hugo Alexander Martínez C.

1999-01-01

Full Text Available Se efectúa un análisis teórico a la reacción de esteriticación entre ácido acético y etanol tendiente a conocer la conveniencia de operar en modo de CSTR (reactor de mezcla total ideal o PFTR (reactor de flujo pistón, para un conjunto dado de parámetros fisicoquímicos y cinética de esterificación de seudoprlmer orden.

Soil Moisture Measurement through Time Domain Reflectometry (TDR). Irrigation Application; Medicion de la humedad del suelo por reflectometria en el dominio temporal (TDR). Aplicacion en irrigacion

Energy Technology Data Exchange (ETDEWEB)

Quinonez Pedroza, Hector E.; Ruelle, Pierre; Nemeth Ildiko [Cemagre, (France)

2002-03-01

Knowledge of how moisture varies in the soil is essential to determine the actual rate of evapotranspiration in crops and, thus, the amount of water necessary for irrigation. Lisimeters, tensiometers and the neutron probe have been widely used for precise measurement of soil moisture in order to calibrate models of irrigation scheduling or to calculate volumes of irrigation water. Despite the usefulness of such measurements, these methods have limited use because of problems like high cost of lisimeters and neutron probes as well as their strict regulation, limited range of validity of tensiometers. Moreover, the measurements obtained from these methods generally describe noncontinuous points in time. Time Domain Reflectometry (TDR) is a viable to such methods because of its precision and the continuity of its measurements. This study evaluates soil moisture, using the neutron and TDR methods in maize crop irrigated by gravity in closed furrows. The results show that even though the absolute determinations of moisture are different in the 30-90 cm profiles, moisture variations were similar in all cases and respond consequently to the additions of water and to evapotranspiration. Neutron probe drawback become evident on its no-continuous measurements contrasting with the continuous measurements of TDR, which allows a detailed analysis of the infiltration and evapotranspiration phenomenal at instantaneous time scales. [Spanish] El conocimiento de la variacion de la humedad del suelo es esencial para determinar la evapotranspiracion real de los cultivos. Esta ultima, a su vez, permite conocer las cantidades necesarias de agua de riego. Los lisimetros, los tensiometros y el aspersor de nuestro s han sido ampliamente usados para la medicion precisa de la humedad del suelo con propositos de calibracion de modelos de programacion del riego o para su utilizacion directa en el calculo de volumenes de riego. A pesar de la importancia de tales mediciones, su uso es muy

The nuclear reactor strategy between fast breeder reactors and advanced pressurized water reactors

International Nuclear Information System (INIS)

Seifritz, W.

1983-01-01

A nuclear reactor strategy between fast breeder reactors (FBRs) and advanced pressurized water reactors (APWRs) is being studied. The principal idea of this strategy is that the discharged plutonium from light water reactors (LWRs) provides the inventories of the FBRs and the high-converter APWRs, whereby the LWRs are installed according to the derivative of a logistical S curve. Special emphasis is given to the dynamics of reaching an asymptotic symbiosis between FBRs and APWRs. The main conclusion is that if a symbiotic APWR-FBR family with an asymptotic total power level in the terawatt range is to exist in about half a century from now, we need a large number of FBRs already in an early phase

Inventory Methods in a Conversion Plant; Methodes d'Inventaire dans un Etablissement de Transformation; Metody inventarizatsij na predpriyatii po pererabotke yadernykh materialov; Metodos de Inventario en una Planta de Transformacion

Energy Technology Data Exchange (ETDEWEB)

Billy, G. [Commissariat a l' Energie Atomique, Paris (France)

1966-02-15

inventarios es la de salvaguardar los intereses de la Comision, evaluar la cuantia de las perdidas y controlar las medidas adoptadas para el almacenaje de los desechos. Para el recuento de las existencias el inspector puede efectuar materialmente el inventario, participar en el o comprobarlo. Este ultimo procedimiento es el que da mejores resultados. Las operaciones de recuento, precedidas de una reunion preparatoria para fijar las modalidades, se efectuan en dos tiempos: la comprobacion del inventario ponderal y la comprobacion de la contabilidad fisica. Las cuestiones que pueden plantearse durante el inventario se refieren a las discrepancias en el peso y el contenido, la eleccion del equipo de pesada, los residuos y la evaluacion de las perdidas. Los metodos de inventario no deben diferir de un pais a otro. Parece preferible subrayar las dificultades que se presentan durante las operaciones y estudiar en comun los medios para evitarlas. (author) [Russian] Osnovnymi zadachami inventarizacii javljajutsja: sobljudenie interesov Komissariata; opredelenie razmerov poter'; kontrol' mer, prinimaemyh dlja hranenija othodov. Inspektirujushhee lico mozhet provodit' fakticheskuju inventarizaciju, uchastvovat' v nej ili proverjat' ee. Jetot poslednij metod daet nailuchshie rezul'taty. Operacii po uchetu, kotorym predshestvuet podgotovitel'noe soveshhanie dlja opredelenija sposobov ucheta, provodjatsjav dva jetapa: snachala proverjaetsja nalichie po vesu, azatemdoku mentacija. Voprosy, voznikajushhie v svjazi s inventarizaciej i kasajushhiesja vesa, soderzhanija poko- vok, vybora vesov dlja vzveshivanija, normy othodov i ocenki poter', razreshajutsja otpravite- lem i poluchatelem. Metody inventarizacii v odnom gosudarstve ne dolzhny sil'no otlichat'sja ot takovyh v drugom gosudarstve. Neobhodimo podcherknut' trudnosti, voznikajushhie v processe inven- tarizacii, i zhelatel'nost' otyskanija sovmestnyh putej ih preodolenija. (author)

Increased SRP reactor power

International Nuclear Information System (INIS)

MacAfee, I.M.

1983-01-01

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

Diseño y simulación de un reactor prototipo que soporte condiciones de hidrogenación para crudo pesado con una capacidad de 1 galón por segundo para Petroecuador

OpenAIRE

Checa Ramírez, Pablo Andrés; Andy Cerda, Amilkar Patricio

2010-01-01

El presente proyecto se plantea en cinco capítulos estrictamente relacionados: Procesos teóricos, Tipos de reactores, Diseño y cálculo del reactor prototipo, Método del cálculo de prueba y error, y, costos que genera el diseño

Manufacture of amorphous and poly-crystalline materials with the sol-gel process; Fabricacion de materiales amorfos y policristalinos con la ruta sol-gel

Energy Technology Data Exchange (ETDEWEB)

Castaneda-Contreras, J. [Centro Universitario de Los Lagos, Universidad de Guadalajara, Guadalajara, Jalisco (Mexico)

2006-01-15

The sun-gel process is a chemical route that allows the manufacture of amorphous and poly-crystalline materials in a relatively simple way. New materials can be obtained, materials that through the traditional manufacture methods, are very difficult to obtain, such as oxide combinations (SiO{sub 2}, TiO{sub 2}, ZrO{sub 2}, etc.), and that, when being produced by traditional methods, they run the risk of being contaminated with rare earth ions or organic dyes. The unique structures, micro- structures and compounds that can be made with the sun-gel process open many possibilities for practical applications, to name a few: the manufacture of optical components, preforms for optical fibers, dielectric coatings, superconductors, waveguides, nanoparticles, solar cells, etc. [Spanish] El proceso sol-gel es una ruta quimica que permite fabricar materiales amorfos y policristalinos de forma relativamente sencilla. Se pueden obtener nuevos materiales que a traves de los metodos tradicionales de fabricacion son muy dificiles de obtener, tales como combinaciones de oxidos (SiO{sub 2}, TiO{sub 2}, ZrO{sub 2}, etc.), y que, de ser producidos por metodos tradicionales corren el riesgo de contaminarse con iones de tierras raras o colorantes organicos. Las estructuras unicas, micro estructuras y compuestos que pueden hacerse con el proceso sol-gel abren muchas posibilidades para aplicaciones practicas, por nombrar algunas, la fabricacion de componentes opticos, preformas para fibras opticas, recubrimientos dielectricos, superconductores, guias de onda, nanoparticulas, celdas solares, etc.

Arranque y operación a escala real de un sistema de tratamiento de lodos activos para aguas residuales de matadero

OpenAIRE

Pabón, Sandra Liliana; Suárez Gélvez, John Hermógenes

2010-01-01

La investigación se desarrolló en la planta de tratamiento de aguas residuales de la empresa Frigorífico Frigofrontera Ltda., la cual está constituida por un sistema de tratamiento primario que incluye cribado, desarenado, trampa de grasas y sedimenta- ción, un reactor de lodo activo con recirculación para el tratamiento secundario y un filtro descendente como tratamiento ter- ciario. El caudal tratado en promedio es de 1,38 L/s; el reactor de lodo activo tiene un volumen de 144 m3, un ...

Calculation of reactivity for safety in nuclear reactors; Calculo de la reactividad para seguridad en reactores nucleares

Energy Technology Data Exchange (ETDEWEB)

Suescun D, D. [Universidad Surcolombiana, Av. Pastrana Borrero - Carrera 1, Neiva, Huila (Colombia); Rojas A, O., E-mail: daniel.suescun@usco.edu.co [Universidad Popular Autonoma del Estado de Puebla, Av. 9 Pte 1908, Barrio de Santiago, 72410 Puebla (Mexico)

2017-09-15

The measurement of reactivity is a function of time and its calculation results from the variation in nuclear power from the inverse equation of punctual kinetics. This equation is a differential integral, where the term of the integral conserves the historical power and the differential part is directly related to the period of the reactor. In practice, in a nuclear plant, sensors are required to record the signals. For example, the movements of the control rods that cause the fluctuations of nuclear power over time commonly generate signals with noise, an event that makes difficult to estimate the reactivity. Thus is necessary and very useful to build digital reactivity meters in real time, since allows a reactor to be operated with greater security. The calculation of the reactivity is carried out using punctual kinetics, especially the concentration of delayed neutron precursors. In this work we present a new way to reduce the fluctuations in the calculation of the reactivity, for the high precision we propose the generalization of the predictor and corrector of the Adams-Bashforth-Moulton (ABM) method of order 4 to solve numerically the equations of the point kinetics for the calculation of the reactivity, without using the power history, due to the nature of the equations of the punctual kinetics, the modifiers of the different predictors are used to increase the accuracy in the approximation obtained accompanied by the filter known as Savitzky-Golay (Sg), allow to reduce the fluctuations of reactivity. It is known that the Sg filter softens and does not attenuate the nuclear power regardless of its shape, guarantees to reduce noise levels up to σ = 0.01, with a calculation time step of σ = 0.01, s. This formulation uses a polynomial approximation of Gram, with a degree d = 2, to calculate the convolution coefficients by means of an analytical formula that is implemented computationally and avoids problems of bad conditioning, caused by the inversion of a

Tokamak reactor studies

International Nuclear Information System (INIS)

Baker, C.C.

1981-01-01

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

Computerized reactor monitor and control for research reactors

International Nuclear Information System (INIS)

Buerger, L.; Vegh, E.

1981-09-01

The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

Simulacion borrosa de un reactor con reaccion exotermica no lineal

Directory of Open Access Journals (Sweden)

MIGUEL ANGEL RODRIGUEZ BORROTO

2007-01-01

Full Text Available En el presente trabajo se desarrolla un modelo difuso basado en la estructura Takagi-Sugeno-Kang dinámica para un reactor continuo de tanque con agitador (RCTA con reacción química de primer orden exotérmico. A partir de datos experimentales obtenidos mediante simulación del proceso real, se obtiene la base de datos de las variables de entrada y salida del proceso y a partir de la misma se elaboran los archivos de datos de entrenamiento y de verificación del modelo borroso el cual es obtenido mediante la herramienta anfis de MATLAB. El modelo obtenido permite predecir la salida del sistema con errores de predicción muy bajos, por lo que el mismo sienta las bases para el diseño de un controlador predictivo no lineal del mismo en próximas etapas de la investigación

Radioisotope tracer study in a pilot-scale trickle bed reactor

Energy Technology Data Exchange (ETDEWEB)

Pant, H.J.; Pendharkar, A.S. [Bhabha Atomic Research Centre, Isotope Applications Div, Bombay (India); Prasad, J.S.; Maiti, R.N.; Chawla, R.; Lahri, R.N.; Ram Babu, D. [Engineers India Limited, Gurgaon, Haryana (India); Berne, Ph. [CEA Grenoble, DTEN/SAT, 38 (France)

2001-07-01

Trickle bed reactor (TBR) is a reactor in which a liquid and a gas phase flow concurrently downwards through a fixed bed of catalyst particles while the reaction takes place. The trickle bed reactors find a number of applications in petroleum refining, chemical. petro-chemical and bio-chemical processes due to their suitability for hydro-processing operations.The knowledge of radial distribution, mean residence time (MRT). liquid holdup and degree of axial mixing is a basic requirement to evaluate the reactor performance of a TBR, its optimal size, the physical and chemical interactions and the pumping requirements. Measurement and analysis of residence time distribution (RTD) of liquid phase facilitate the determination of these parameters. This paper describes the measurement of RTD of liquid phase in a pilot-scale trickle bed reactor operating at high pressure. Kerosene and nitrogen were used as liquid and gas phase, respectively. Porous alumina catalyst particles were used as packing. Bromine-82 as para-di-bromo benzene was used as a tracer to measure RTD of organic liquid phase. The RTD of kerosene was measured as a function of liquid and gas flow rates and pressure. The axial dispersion model with exchange between active and dead zones was proposed and used to simulate the measured RTD data and model parameters i.e mean residence time ({tau}), Peclet Number (Pe), dynamic fraction of the liquid ({phi}) and the number of transfer units (N) were obtained. The results of the simulations indicated intermediate degree of axial mixing of liquid phase. The RTD predicted by the axial dispersion model with exchange between active and dead zones fits well to the experimentally measured RTD data and thus is a suitable model to describe the dynamics of the liquid phase in TBRs filled with porous catalyst particles. (authors)

EVALUACIÓN DE LA SENSIBILIDAD PARAMÉTRICA DEL PROCESO DE SÍNTESIS DE LA CICLONITA EN UN REACTOR POR LOTES

Directory of Open Access Journals (Sweden)

Juan Carlos Ojeda Toro

Full Text Available En este trabajo se evaluó la sensibilidad paramétrica del proceso de síntesis de la ciclonita en un reactor por lotes. Esto con el fin de definir condiciones seguras de operación para esta reacción altamente exotérmica. La ley de velocidad de la reacción se ajustó a partir de datos experimentales disponibles en la literatura. Reparametrizando los balances de materia y energía del reactor, se estableció la sensibilidad de la temperatura de reacción con respecto a la variación de la temperatura inicial del sistema reactivo y la temperatura del medio refrigerante. Para determinar las condiciones críticas de operación del reactor, se usó como criterio el cálculo de los coeficientes de sensibilidad y los perfiles de temperatura-conversión así como el lugar geométrico de los máximos de estas curvas. Se definió para el sistema reactivo un potencial crítico de generación de calor (M igual a 34 y que las condiciones críticas de Runaway corresponden a un número de Semenov (ψ igual a 0,684, un parámetro de calor de reacción (B igual a 15 y un número del tipo Arrhenius (γ con un valor de 20. Así mismo, los perfiles de temperatura-conversión precisan una relación crítica entre el potencial de enfriamiento y generación de calor de 2,5786 (N/M.

Calculation of low-energy reactor neutrino spectra reactor for reactor neutrino experiments

Energy Technology Data Exchange (ETDEWEB)

Riyana, Eka Sapta; Suda, Shoya; Ishibashi, Kenji; Matsuura, Hideaki [Dept. of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Kyushu (Japan); Katakura, Junichi [Dept. of Nuclear System Safety Engineering, Nagaoka University of Technology, Nagaoka (Japan)

2016-06-15

Nuclear reactors produce a great number of antielectron neutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may take part in special weak interactions. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectrum from a typical pressurized water reactor (PWR) reactor core. To calculate neutrino spectra, we need information about all generated nuclides that emit neutrinos. They are mainly fission fragments, reaction products and trans-uranium nuclides that undergo negative beta decay. Information in relation to trans-uranium nuclide compositions and its evolution in time (burn-up process) were provided by a reactor code MVP-BURN. We used typical PWR parameter input for MVP-BURN code and assumed the reactor to be operated continuously for 1 year (12 months) in a steady thermal power (3.4 GWth). The PWR has three fuel compositions of 2.0, 3.5 and 4.1 wt% {sup 235}U contents. For preliminary calculation we adopted a standard burn-up chain model provided by MVP-BURN. The chain model treated 21 heavy nuclides and 50 fission products. The MVB-BURN code utilized JENDL 3.3 as nuclear data library. We confirm that the antielectron neutrino flux in the low energy region increases with burn-up of nuclear fuel. The antielectron-neutrino spectrum in low energy region is influenced by beta emitter nuclides with low Q value in beta decay (e.g. {sup 241}Pu) which is influenced by burp-up level: Low energy antielectron-neutrino spectra or emission rates increase when beta emitters with low Q value in beta decay accumulate. Our result shows the flux of low energy reactor neutrinos increases with burn-up of nuclear fuel.

Nuclear Reactor Physics

Science.gov (United States)

Stacey, Weston M.

2001-02-01

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

Reactor. Mind picture of the future Jules-Horowitz Reactor (RHJ)

International Nuclear Information System (INIS)

Eustache, S.

1999-01-01

This paper gives information about the future research reactor, named Reactor Jules-Horowitz (RJH). This irradiation reactor will be placed at industrialists disposal, for research concerning the competitiveness and the safety french electro-nuclear park. Principles and innovations are detailed. This reactor will respect the ALARA principle (as low as reasonably achievable). (A.L.B.)

Advanced epithermal thorium reactor (AETR) physics; Physique d'un reacteur au thorium, a neutrons epithermiques, de type perfectionne (AETR); Fizika usovershenstvovannog o nadteplovogo torievogo reaktora; Fisica del reactor epitermico de tipo avanzado, alimentado con torio (AETR)

Energy Technology Data Exchange (ETDEWEB)

Campise, A. V. [Atomics International, Canoga Park, CA (United States)

1962-03-15

'etude de cet ensemble a mis en relief l'importance des donnees relatives aux sections efficaces et de l'interpretation theorique des resultats experimentaux pour l'etude d'un reacteur au thorium de type perfectionne. La precision des methodes analytiques employees a ete demontree lors de l'analyse des resultats experimentaux obtenus avec le ZPR-III. L'auteur compare trois configurations pour le transfert de chaleur, en utilisant le temps de doublement comme parametre d'optimisation. Les effets de la production de {sup 233}Pa et d'isotopes de l'uranium sur le bilan neutronique, les taux possibles de surgeneration et les caracteristiques de la combustion sont evalues en tenant compte de l'imprecision des sections efficaces nucleaires. (author) [Spanish] El autor estudia la concepcion del reactor AETR desde el punto de vista de la teoria actual de los parametros nucleares y del balance neutronico. En los sistemas moderados por grafito examina el efecto de la captura por resonancia en el torio para energias medias de absorcion del orden de 0,10 a 100 keV. Aplica formulas de resonancia angosta y de resonancia ancha para obtener la integral de resonancia efectiva en funcion de la temperatura, correspondiente a las barras de torio, y dicho parametro se expresa como secciones eficaces equivalentes de varios grupos. Se ha disenado y construido un conjunto critico para obtener datos nucleares indispensables en la gama de energias intermedias. En el diseno nuclear de dicho conjunto, se ha tenido particularmente en cuenta la importancia de los datos relativos a secciones eficaces y la interpretacion teorica de estos resultados experimentales, cosas ambas relacionadas con el diseno del reactor AETR. La precision de los metodos analiticos ha quedado demostrada por el estudio de los resultados experimentales obtenidos con el reactor ZPR-III. Se comparan tres sistemas de transmision de calor utilizando el tiempo de duplicacion como parametro optimo. Se estudia el efecto de la formacion

The analysis for inventory of experimental reactor high temperature gas reactor type

International Nuclear Information System (INIS)

Sri Kuntjoro; Pande Made Udiyani

2016-01-01

Relating to the plan of the National Nuclear Energy Agency (BATAN) to operate an experimental reactor of High Temperature Gas Reactors type (RGTT), it is necessary to reactor safety analysis, especially with regard to environmental issues. Analysis of the distribution of radionuclides from the reactor into the environment in normal or abnormal operating conditions starting with the estimated reactor inventory based on the type, power, and operation of the reactor. The purpose of research is to analyze inventory terrace for Experimental Power Reactor design (RDE) high temperature gas reactor type power 10 MWt, 20 MWt and 30 MWt. Analyses were performed using ORIGEN2 computer code with high temperatures cross-section library. Calculation begins with making modifications to some parameter of cross-section library based on the core average temperature of 570 °C and continued with calculations of reactor inventory due to RDE 10 MWt reactor power. The main parameters of the reactor 10 MWt RDE used in the calculation of the main parameters of the reactor similar to the HTR-10 reactor. After the reactor inventory 10 MWt RDE obtained, a comparison with the results of previous researchers. Based upon the suitability of the results, it make the design for the reactor RDE 20MWEt and 30 MWt to obtain the main parameters of the reactor in the form of the amount of fuel in the pebble bed reactor core, height and diameter of the terrace. Based on the main parameter or reactor obtained perform of calculation to get reactor inventory for RDE 20 MWT and 30 MWT with the same methods as the method of the RDE 10 MWt calculation. The results obtained are the largest inventory of reactor RDE 10 MWt, 20 MWt and 30 MWt sequentially are to Kr group are about 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq, for group I are 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq and for groups Cs are 2,20E+16 Bq, 2,40E+16 Bq, 2,60E+16 Bq. Reactor inventory will then be used to calculate the reactor source term and it

FBR type reactors

International Nuclear Information System (INIS)

Suzuoki, Akira; Yamakawa, Masanori.

1985-01-01

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

FBR type reactor

International Nuclear Information System (INIS)

Hayase, Tamotsu.

1991-01-01

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

Evaluation of plate type fuel options for small power reactors; Avaliacao de alternativas de combustivel tipo placa para reatores de pequeno porte

Energy Technology Data Exchange (ETDEWEB)

Andrzejewski, Claudio de Sa

2005-07-01

Plate type fuels are generally used in research reactor. The utilization of this kind of configuration improves significantly the overall performance fuel. The conception of new fuels for small power reactors based in plate-type configuration needs a complete review of the safety criteria originally used to conduce power and research reactor projects. In this work, a group of safety criteria is established for the utilization of plate-type fuels in small power reactors taking into consideration the characteristics of power and research reactors. The performance characteristics of fuel elements are strongly supported by its materials properties and the adopted configuration for its fissile particles. The present work makes an orientated bibliographic investigation searching the best material properties (structural materials and fuel compounds) related to the performance fuel. Looking for good parafermionic characteristics and manufacturing exequibility associated to existing facilities in national research centres, this work proposes several alternatives of plate type fuels, considering its utilization in small power reactors: dispersions of UO{sub 2} in stainless steel, of UO{sub 2} in zircaloy, and of U-Mo alloy in zircaloy, and monolithic plates of U-Mo cladded with zircaloy. Given the strong dependency of radiation damage with temperature increase, the safety criteria related to heat transfer were verified for all the alternatives, namely the DNBR; coolant temperature lower than saturation temperature; peak meat temperature to avoid swelling; peak fuel temperature to avoid meat-matrix reaction. It was found that all alternatives meet the safety criteria including the 0.5 mm monolithic U-Mo plate cladded with zircaloy. (author)

Modelling of pressurized water reactor fuel, rod time dependent radial heat flow with boundary element method; Modeliranje spremenljivega radijalnega toplotnega toka tlacnovodne gorivne palice z metodo robnih elementov

Energy Technology Data Exchange (ETDEWEB)

Sarler, B [Institut Jozef Stefan, Ljubljana (Yugoslavia)

1987-07-01

The basic principles of the boundary element method numerical treatment of the radial flow heat diffusion equation are presented. The algorithm copes the time dependent Dirichlet and Neumann boundary conditions, temperature dependent material properties and regions from different materials in thermal contact. It is verified on the several analytically obtained test cases. The developed method is used for the modelling of unsteady radial heat flow in pressurized water reactor fuel rod. (author)

Nuclear reactor

International Nuclear Information System (INIS)

Tilliette, Z.

1975-01-01

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

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-07-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

International Nuclear Information System (INIS)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

Thai research reactor

International Nuclear Information System (INIS)

Aramrattana, M.

1987-01-01

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

Computerized procedure for protection coordination in distribution primary circuits; Procedimiento computarizado para coordinacion de protecciones en circuitos primarios de distribucion

Energy Technology Data Exchange (ETDEWEB)

Carrillo, Victor M; Velazquez Sanchez, Raul [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1987-12-31

Nowadays, the method employed to study the protection coordination are based in the hand outlining of curves time- current and in the visual comparison in log sheets. Due to the large amount of distribution circuits, the engineer makes a considerable effort to perform this type of studies, which besides are routinist and time consuming. In this article a program for the computer aided design for the protection coordination in primary distribution circuits is presented. Such a program -carried out in the Transmission and Distribution Department of the Power Systems Division of the Instituto de Investigaciones Electricas (IIE)- substitutes in an efficient manner, the manual procedures that are performed in the protection coordination studies. The coordination principles, suggested by the equipment manufacturers, were respected, trying, at the same time, to keep the procedures of the Comision Federal de Electricidad personnel (CFE) emerged from the field experience. The algorithm basically consists of an iterative process in the selection of the adjustments taking as a reference the of three-phase short- circuit and of phase to ground, values, as well as the operating times. [Espanol] Actualmente, los metodos que se emplean para estudiar la coordinacion de protecciones se basan en el trazado manual de curvas de tiempo-corriente y en la comparacion visual sobre hojas logaritmicas. Debido a la gran cantidad de circuitos de distribucion, el ingeniero hace un esfuerzo considerable para realizar este tipo de estudios, los que ademas, son rutinarios y tardados. En este articulo, se presenta un programa para el diseno asistido por computadora del proceso de coordinacion de protecciones en circuitos primarios de distribucion. Dicho programa -realizado en el Departamento de Transmision y Distribucion, de la Division de Sistemas de Potencia, del Instituto de Investigaciones Electricas (IIE)- sustituye de manera eficaz los procedimientos manuales que se efectuan en los estudios

Computerized procedure for protection coordination in distribution primary circuits; Procedimiento computarizado para coordinacion de protecciones en circuitos primarios de distribucion

Energy Technology Data Exchange (ETDEWEB)

Carrillo, Victor M.; Velazquez Sanchez, Raul [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1986-12-31

Nowadays, the method employed to study the protection coordination are based in the hand outlining of curves time- current and in the visual comparison in log sheets. Due to the large amount of distribution circuits, the engineer makes a considerable effort to perform this type of studies, which besides are routinist and time consuming. In this article a program for the computer aided design for the protection coordination in primary distribution circuits is presented. Such a program -carried out in the Transmission and Distribution Department of the Power Systems Division of the Instituto de Investigaciones Electricas (IIE)- substitutes in an efficient manner, the manual procedures that are performed in the protection coordination studies. The coordination principles, suggested by the equipment manufacturers, were respected, trying, at the same time, to keep the procedures of the Comision Federal de Electricidad personnel (CFE) emerged from the field experience. The algorithm basically consists of an iterative process in the selection of the adjustments taking as a reference the of three-phase short- circuit and of phase to ground, values, as well as the operating times. [Espanol] Actualmente, los metodos que se emplean para estudiar la coordinacion de protecciones se basan en el trazado manual de curvas de tiempo-corriente y en la comparacion visual sobre hojas logaritmicas. Debido a la gran cantidad de circuitos de distribucion, el ingeniero hace un esfuerzo considerable para realizar este tipo de estudios, los que ademas, son rutinarios y tardados. En este articulo, se presenta un programa para el diseno asistido por computadora del proceso de coordinacion de protecciones en circuitos primarios de distribucion. Dicho programa -realizado en el Departamento de Transmision y Distribucion, de la Division de Sistemas de Potencia, del Instituto de Investigaciones Electricas (IIE)- sustituye de manera eficaz los procedimientos manuales que se efectuan en los estudios

Determinación de aminas aromaticas por cromatografia liquida de alta resolución.

OpenAIRE

Gutiérrez Bouzán, Mª Carmen; Crespi Rosell, Martí

1989-01-01

Este trabajo consiste en la puesta a punto del metodo analítico para la determinación por cromatografia liquida de alta resolución (HPLC) de las aminas aromáticas empleadas más frecuentemente en la fabricación de colorantes sulfurosos: m-tolilendiamina, p-fenilendiamina, o-toluidina, p-toluidina, anilina, p-aminofenol, difenilamina, y p-hidroxidifenilamina. La longitud de onda de detección es de 260 nm. El principal objetivo del presente estudio es la consecución de un método de análisis p...

Qualidade de vida e saúde bucal em crianças e adolescentes: aspectos conceituais e metodológicos

OpenAIRE

Barbosa,Taís de Souza; Mialhe,Fábio Luiz; Castilho,Aline Rogéria Freire de; Gavião,Maria Beatriz Duarte

2010-01-01

O interesse pela qualidade de vida e saúde bucal em crianças e adolescentes vem aumentando, já que as desordens orais provavelmente apresentam efeito negativo na qualidade de vida das mesmas. Neste sentido, questionários que visam a avaliar o impacto da saúde bucal no bem-estar têm sido desenvolvidos e adaptados para este grupo específico. O objetivo deste trabalho é descrever a relação entre qualidade de vida e saúde bucal em crianças e adolescentes, focalizando aspectos conceituais e metodo...

Relación familia-escuela: La implicación programada de los padres en el aula infantil y su repercusión en los alumnos

OpenAIRE

Martínez-Canales, Emma

2016-01-01

En este TFG se propone desde una base teórica-práctica, que la tarea compartida, programada y reflexiva entre padres y educadores repercute favorablemente en el buen desarrollo cognitivo, social y afectivo del niño. El trabajo se centra en una Propuesta de Intervención para una escuela en concreto, cuyo tema central es la influencia de la implicación programada de la familia en el desarrollo cognitivo, social y afectivo del niño en el ambiente familiar y en el ambiente áulico. La metodo...

Planeamiento estratégico de la Región Lima Provincias

OpenAIRE

Centeno Díaz, Teobaldo Josué; Enríquez Pocomo, Wilder Ever; Rios Marín, Francisco Julio; Villalva Quispe, Carlos Cazeli

2016-01-01

xvi, 213 p. : il. ; 30 cm. La presente tesis desarrolla el Plan Estratégico de la Región Lima Provincias, región con un gran potencial por explotar que podría convertirse en eje de desarrollo de la zona centro occidental peruana, los grandes recursos naturales con los que cuenta, su cercanía a la Ciudad de Lima y los Tratados de Libre Comercio (TLC) suscritos por el Perú con otras naciones son grandes oportunidades para insertarla en la economía nacional y mundial. La metodo...

Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

Energy Technology Data Exchange (ETDEWEB)

Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Poore, III, Willis P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Moe, Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-03-01

This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

Nuclear reactor instrumentation at research reactor renewal

International Nuclear Information System (INIS)

Baers, B.; Pellionisz, P.

1981-10-01

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

Reactor System Design

International Nuclear Information System (INIS)

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

2006-08-01

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

BWR type reactor

International Nuclear Information System (INIS)

Watanabe, Shoichi

1983-01-01

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

Prevention device for rapid reactor core shutdown in BWR type reactors

International Nuclear Information System (INIS)

Koshi, Yuji; Karatsu, Hiroyuki.

1986-01-01

Purpose: To surely prevent rapid shutdown of a nuclear reactor upon partial load interruption due to rapid increase in the system frequency. Constitution: If a partial load interruption greater than the sum of the turbine by-pass valve capacity and the load setting bias portion is applied in a BWR type power plant, the amount of main steams issued from the reactor is decreased, the thermal input/output balance of the reactor is lost, the reactor pressure is increased, the void is collapsed, the neutron fluxes are increased and the reactor power rises to generate rapid reactor shutdown. In view of the above, the turbine speed signal is compared with a speed setting value in a recycling flowrate control device and the recycling pump is controlled to decrease the recycling flowrate in order to compensate the increase in the neutron fluxes accompanying the reactor power up. In this way, transient changes in the reactor core pressure and the neutron fluxes are kept within a setting point for the rapid reactor shutdown operation thereby enabling to continue the plant operation. (Horiuchi, T.)

Reactor core of nuclear reactor

International Nuclear Information System (INIS)

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

1994-01-01

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

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

Directory of Open Access Journals (Sweden)

Lopez, F.

2004-07-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-12-31

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

High-temperature and breeder reactors - economic nuclear reactors of the future

International Nuclear Information System (INIS)

Djalilzadeh, A.M.

1977-01-01

The thesis begins with a review of the theory of nuclear fission and sections on the basic technology of nuclear reactors and the development of the first generation of gas-cooled reactors applied to electricity generation. It then deals in some detail with currently available and suggested types of high temperature reactor and with some related subsidiary issues such as the coupling of different reactor systems and various schemes for combining nuclear reactors with chemical processes (hydrogenation, hydrogen production, etc.), going on to discuss breeder reactors and their application. Further sections deal with questions of cost, comparison of nuclear with coal- and oil-fired stations, system analysis of reactor systems and the effect of nuclear generation on electricity supply. (C.J.O.G.)

Development of neutronic models with KANEXT for a reactor of traveling wave; Desarrollo de modelos neutronicos con KANEXT para un reactor de onda viajera

Energy Technology Data Exchange (ETDEWEB)

Lopez S, R. C.; Francois L, J. L. [UNAM, Facultad de Ingeniera, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac No. 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico); Becker, M., E-mail: rcarlosls@yahoo.com.mx [Institut fur Neutronenphysik und Reaktortechnik (KIT), Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany)

2012-10-15

Problems with the computation time in a based code on the Monte Carlo method, they conduct to explore the option of the deterministic codes to be able to develop a model of robust reactor of traveling wave, and where short term results are obtained to carry out experimentation work to the moment to study an assemblies exchange scheme as method of fuel administration. KANEXT is a versatile and reliable code, developed in Germany that has satisfied our development necessities until the moment. In this article is described the KANEXT operation, and like it was implemented to develop a preliminary model of reactor core of traveling wave with operation way of stationary wave. The results obtained until the moment, as for the neutrons multiplication factor and the isotopic balance, are encouraging and they lead to refine the model removing completely the axial covering. The adoption of deterministic codes has allowed carrying out tests of complete core in a conventional computer in question of only hours; this will be valuable in the next stage of the research, where developing a re situate scheme of fuel assemblies will involve a great quantity of sprints. (Author)

Heterogeneous reactors

International Nuclear Information System (INIS)

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

1979-08-01

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

Nuclear reactor neutron shielding

Science.gov (United States)

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

2017-09-12

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

Fast breeder reactors

International Nuclear Information System (INIS)

Heinzel, V.

1975-01-01

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

Reactor container

International Nuclear Information System (INIS)

Shibata, Satoru; Kawashima, Hiroaki

1984-01-01

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

Reactor technology: power conversion systems and reactor operation and maintenance

International Nuclear Information System (INIS)

Powell, J.R.

1977-01-01

The use of advanced fuels permits the use of coolants (organic, high pressure helium) that result in power conversion systems with good thermal efficiency and relatively low cost. Water coolant would significantly reduce thermal efficiency, while lithium and salt coolants, which have been proposed for DT reactors, will have comparable power conversion efficiencies, but will probably be significantly more expensive. Helium cooled blankets with direct gas turbine power conversion cycles can also be used with DT reactors, but activation problems will be more severe, and the portion of blanket power in the metallic structure will probably not be available for the direct cycle, because of temperature limitations. A very important potential advantage of advanced fuel reactors over DT fusion reactors is the possibility of easier blanket maintenance and reduced down time for replacement. If unexpected leaks occur, in most cases the leaking circuit can be shut off and a redundant cooling curcuit will take over the thermal load. With the D-He 3 reactor, it appears practical to do this while the reactor is operating, as long as the leak is small enough not to shut down the reactor. Redundancy for Cat-D reactors has not been explored in detail, but appears feasible in principle. The idea of mobile units operating in the reactor chamber for service and maintenance of radioactive elements is explored

Fusion-fission hybrid reactors

International Nuclear Information System (INIS)

Greenspan, E.

1984-01-01

This chapter discusses the range of characteristics attainable from hybrid reactor blankets; blanket design considerations; hybrid reactor designs; alternative fuel hybrid reactors; multi-purpose hybrid reactors; and hybrid reactors and the energy economy. Hybrid reactors are driven by a fusion neutron source and include fertile and/or fissile material. The fusion component provides a copious source of fusion neutrons which interact with a subcritical fission component located adjacent to the plasma or pellet chamber. Fissile fuel and/or energy are the main products of hybrid reactors. Topics include high F/M blankets, the fissile (and tritium) breeding ratio, effects of composition on blanket properties, geometrical considerations, power density and first wall loading, variations of blanket properties with irradiation, thermal-hydraulic and mechanical design considerations, safety considerations, tokamak hybrid reactors, tandem-mirror hybrid reactors, inertial confinement hybrid reactors, fusion neutron sources, fissile-fuel and energy production ability, simultaneous production of combustible and fissile fuels, fusion reactors for waste transmutation and fissile breeding, nuclear pumped laser hybrid reactors, Hybrid Fuel Factories (HFFs), and scenarios for hybrid contribution. The appendix offers hybrid reactor fundamentals. Numerous references are provided

Reactor protection systems for the Replacement Research Reactor, ANSTO

International Nuclear Information System (INIS)

Morris, C.R.

2003-01-01

The 20-MW Replacement Research Reactor Project which is currently under construction at ANSTO will have a combination of a state of the art triplicated computer based reactor protection system, and a fully independent, and diverse, triplicated analogue reactor protection system, that has been in use in the nuclear industry, for many decades. The First Reactor Protection System (FRPS) consists of a Triconex triplicated modular redundant system that has recently been approved by the USNRC for use in the USA?s power reactor program. The Second Reactor Protection System is a hardwired analogue system supplied by Foxboro, the Spec 200 system, which is also Class1E qualified. The FRPS is used to drop the control rods when its safety parameter setpoints have been reached. The SRPS is used to drain the reflector tank and since this operation would result in a reactor poison out due to the time it would take to refill the tank the FRPS trip setpoints are more limiting. The FRPS and SRPS have limited hardwired indications on the control panels in the main control room (MCR) and emergency control centre (ECC), however all FRPS and SRPS parameters are capable of being displayed on the reactor control and monitoring system (RCMS) video display units. The RCMS is a Foxboro Series I/A control system which is used for plant control and monitoring and as a protection system for the cold neutron source. This paper will provide technical information on both systems, their trip logics, their interconnections with each other, and their integration into the reactor control and monitoring system and control panels. (author)

Reactor container

International Nuclear Information System (INIS)

Fukazawa, Masanori.

1991-01-01

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

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)

A multi-purpose reactor

International Nuclear Information System (INIS)

Changwen Ma

2000-01-01

An integrated natural circulation self pressurized reactor can be used for sea water desalination, electrogeneration, ship propulsion and district or process heating. The reactor can be used for ship propulsion because it has following advantages: it is a integrated reactor. Whole primary loop is included in a size limited pressure vessel. For a 200 MW reactor the diameter of the pressure vessel is about 5 m. It is convenient to arranged on a ship. Hydraulic driving facility of control rods is used on the reactor. It notably decreases the height of the reactor. For ship propulsion, smaller diameter and smaller height are important. Besides these, the operation reliability of the reactor is high enough, because there is no rotational machine (for example, circulating pump) in safety systems. Reactor systems are simple. There are no emergency water injection system and boron concentration regulating system. These features for ship propulsion reactor are valuable. Design of the reactor is based on existing demonstration district heating reactor design. The mechanic design principles are the same. But boiling is introduced in the reactor core. Several variants to use the reactor as a movable seawater desalination plant are presented in the paper. When the sea water desalination plant is working to produce fresh water, the reactor can supply electricity at the same time to the local electricity network. Some analyses for comprehensive application of the reactor have been done. Main features and parameters of the small (Thermopower 200 MW) reactor are given in the paper. (author)

TU Electric reactor physics model verification: Power reactor benchmark

International Nuclear Information System (INIS)

Willingham, C.E.; Killgore, M.R.

1988-01-01

Power reactor benchmark calculations using the advanced code package CASMO-3/SIMULATE-3 have been performed for six cycles of Prairie Island Unit 1. The reload fuel designs for the selected cycles included gadolinia as a burnable absorber, natural uranium axial blankets and increased water-to-fuel ratio. The calculated results for both startup reactor physics tests (boron endpoints, control rod worths, and isothermal temperature coefficients) and full power depletion results were compared to measured plant data. These comparisons show that the TU Electric reactor physics models accurately predict important measured parameters for power reactors

Control Rods in high-Flux Swimming-Pool Reactors; Les Barres de Controle dans les Piles Piscines a Haut Flux; Reguliruyushchie sterzhni dlya reaktorov bassejnovogo tipa s vysokoj plotnost'yu nejtronnogo potoka; Las Barras de Control en los Reactores Tipo Piscina de Flujo Elevado

Energy Technology Data Exchange (ETDEWEB)

Ageroni, P.; Blum, P.; Denielou, G.; Denis, P.; Meunier, C. [Centre d' Etudes Nucleaires de Grenoble (France)

1964-06-15

etudes en cours sur les barres de controle des piles piscine a coeur ouvert fonctionnant dans la bande de 10 a 30 MW. (author) [Spanish] La memoria examina los problemas planteados por las barras de control en los reactores de investigacion de tipo piscina abierta, de alta potencia especifica y elevado flujo, basandose en calculos y experimentos efectuados durante la construccion del reactor SILOE. Expone asimismo la experiencia adquirida con las barras de control mientras el reactor funcionaba a 13 MW. Examina sucesivamente: a) Los balances de reactividad y los valores de esta para los diversos tipos de barras de control que se han ensayado (cadmio, B4C, tierras raras, y combinaciones de estas sustancias); b) los picos de flujo que la presencia de barras de control crea en el cuerpo del reactor, su influencia sobre la potencia especifica, los flujos rapidos que se pueden obtener y los medios para incrementarlos; c) los problemas tecnologicos planteados por la construccion de las barras; d) los problemas de refrigeracion, vibracion, deformacion y tiempo necesario para introducirlos en el reactor. Para terminar, describe someramente loe estudios que se estan realizando con las barras de control de reactores de tipo piscina de cuerpo abierto cuando funcionan en el intervalo de potencias comprendido entre 10 y 30 MW. (author) [Russian] 1. V svete raschetov i jeksperimentov, provedennyh pri postrojke reaktora STLOE , rassmatrivajutsja problemy, voznikajushhie v svjazi s regulirujushhimi sterzhnjami dlja issledovatel'skih reaktorov otkrytogo bassejnovogo tipa s bol'shoj udel'noj moshhnost'ju i s vysokoj plotnost'ju nejtronnogo potoka. Privodjatsja takzhe rezul'taty ispytanija jetogo reaktora pri .moshhnosti 13 mgvt v svjazi s razlichnymi regulirujushhimi sterzhnjami. 2. Posledov atel'no rassmatrivajutsja sledujushhie problemy: a) balans reaktivnosti i reaktivnaja sposobnost' podvergnutyh ispytanijam regulirujushhih sterzhnej razlichnyh tipov (kadmij, B{sub 4}C , redkie zemli

Empleo de metodos numericos para el ajuste de los coeficientes de difusividad (D) y convectivo de transferencia de masa (hm) en el secado de alimentos

OpenAIRE

Arranz Saiz, Francisco Javier; Correa Hernando, Eva Cristina; Jiménez Ariza, Heidi Tatiana; Diezma Iglesias, Belen; Garcia-Herrero, Javier; Robla Villalba, José Ignacio; Barreiro Elorza, Pilar

2011-01-01

Los modelos matemáticos de transferencia de humedad desde el alimento al medio circundante durante el proceso de secado dependen de dos parámetros: coeficiente de difusividad efectiva D y coeficiente convectivo de transferencia de masa hm, cuya determinación experimental se basa en la consideración de un sistema difusivo sencillo de solución analítica bien conocida. Para el caso, que aquí nos ocupa, de difusión monodimensional en una lámina infinita de grosor 2l, la solución analítica de ...

HYDROGEN KINETICS LIMITATION OF AN AUTOTROPHIC SULPHATE REDUCTION REACTOR

Directory of Open Access Journals (Sweden)

CÉSAR SÁEZ-NAVARRETE

2012-01-01

Full Text Available El uso de sustratos inorgánicos podría reducir los costos y simplificar la operación de sistemas de tratamiento de aguas que utilizan bacterias reductoras de sulfato. Sin embargo, el uso de H2 como sustrato energético y la bioproducción de H2S podrían provocar limitaciones cinéticas. El objetivo de este estudio fue evaluar las condiciones en las que la capacidad de transferencia de masa de un bioreactor de reducción de sulfato, limita su cinética de reducción. La cinética del reactor fue obtenida monitoreando la presión del sistema en condiciones de no limitación por sulfato. Se concluyó que el diseño del bioreactor debería basarse en sus propiedades de transferencia. La tasa de consumo de H2 alcanzó un máximo de 10-4 M/min, para una tasa de reducción de sulfato de 3.4 g·L-1·d-1. Para evitar limitación por H2 se requirió un kLa de 1.48 min-1 a 1.2·109 cells/L (1.23·10-9 L·min-1·cell-1, valor relevante para propósitos de escalamiento.

Supercritical Water Reactors

International Nuclear Information System (INIS)

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

2014-01-01

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

Tank type reactor

International Nuclear Information System (INIS)

Otsuka, Fumio.

1989-01-01

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

New about research reactors

International Nuclear Information System (INIS)

Egorenkov, P.M.

2001-01-01

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

Desempeño de tanques decantadores de sólidos en un sistema de recirculación para producción de tilapia

Directory of Open Access Journals (Sweden)

Yemall Maigual E.

2013-08-01

Full Text Available Objetivo. Comparar la eficiencia de remoción de sólidos, turbidez y color aparente en un decantador convencional y uno de columna en un sistema de recirculación acuícola (SRA para cultivo de tilapia. Materiales y métodos. Se cultivaron tilapias con densidad entre 30 y 33 kg/m3 en un SRA, el cual constó de: caja de nivel constante, tubería en PVC, tres tanques de cultivo, decantador convencional de flujo horizontal (D.Con, decantador de columna de flujo ascendente (D.Col, reactor de lecho fluidizado trifásico, reactor para transferencia de oxígeno, compresor, blower, electrobomba. El D.Con operó con volumen útil (VU de 1.4 m3 y tiempo de retención hidráulica (TRH de 2.94 h, fue vaciado una vez por semana para lavado y colecta del lodo, representando sustitución del 55% del volumen del sistema. El D.Col operó con 0.30 m3 de VU y TRH de 0.553 h. Se realizaron 3 sangrados diarios, representando sustitución semanal de 50% del volumen. Resultados. Las eficiencias promedio de remoción fueron: para sólidos totales de 34.01 y 44.44%; sólidos suspendidos 64.45% y 71.71%; sólidos volátiles 21.10 y 45.65%; para turbidez 65.51 y 62.79%; para color aparente 56.37 y 50.91%, respectivamente en el D.Con y el D.Col. Conclusiones. Ambos decantadores son útiles en la remoción de los parámetros estudiados y presentaron comportamientos semejantes en remoción de turbidez y color aparente. Sin embargo, el D.Col es más eficiente que el convencional para remoción de los sólidos, ocupa menor espacio, menor volumen y requiere menor porcentaje de renovación, mostrando viabilidad para su utilización en SRA.

Evaluation of Pressure Changes in HANARO Reactor Hall after a Reactor Shutdown

International Nuclear Information System (INIS)

Han, Geeyang; Han, Jaesam; Ahn, Gukhoon; Jung, Hoansung

2013-01-01

The major objective of this work is intended to evaluate the characteristics of the thermal behavior regarding how the decay heat will be affected by the reactor hall pressure change and the increase of pool water temperature induced in the primary coolant after a reactor shutdown. The particular reactor pool water temperature at the surface where it is evaporated owing to the decay heat resulting in the local heat transfer rate is related to the pressure change response in the reactor hall associated with the primary cooling system because of the reduction of the heat exchanger to remove the heat. The increase in the pool water temperature is proportional to the heat transfer rate in the reactor pool. Consequently, any limit on the reactor pool water temperature imposes a corresponding limit on the reactor hall pressure. At HANARO, the decay heat after a reactor shutdown is mainly removed by the natural circulation cooling in the reactor pool. This paper is written for the safety feature of the pressure change related leakage rate from the reactor hall. The calculation results show that the increase of pressure in the reactor hall will not cause any serious problems to the safety limits although the reactor hall pressure is slightly increased. Therefore, it was concluded that the pool water temperature increase is not so rapid as to cause the pressure to vary significantly in the reactor hall. Furthermore, the mathematical model developed in this work can be a useful analytical tool for scoping and parametric studies in the area of thermal transient analysis, with its proper representation of the interaction between the temperature and pressure in the reactor hall

Performance Characteristics of the Experimental Boiling Water Reactor from 0 to 100 MW(t); Performances de l'EBWR de 0 a 100 MW; Rabochaya kharakteristika ehksperimental'nogo kipyashchego reaktora EBWR pri moshchnosti 0 - 100 mgvt.; Rendimiento del reactor experimental de agua hirviente (EBWR) entre 0 y 100 MW

Energy Technology Data Exchange (ETDEWEB)

Iskenderian, A.; Lipinski, W. C.; Petrick, M.; Wimunc, E. A. [Argonne National Laboratory, Argonne, IL (United States)

1963-10-15

controle; emploi d'elements enrichis; fonctions de transfert; analyse des bruits; certaines mesures de flux; stabilite, etc. En outre, on a pu savoir comment se comportaient certaines pieces et parties constitutives du reacteur et si elles restaient intactes, notamment le systeme de controle de l'acide borique, le niveau des rayonnements, la distribution des produits de la corrosion, les vices de fonctionnement du materiel; les barreaux de combustible et les barres de commande, etc. Les performances de l'EBWR dependent presque exclusivement de l'entrainement de la vapeur dans le tube d'eau, de Tentraftiement du liquide par la vapeur qui se degage, et, indirectement, de remplacement de l'interface vraie dans le caisson. C'est l'entrafhement de la vapeur dans le tube d'eau qui domine pour les puissances inferieures. Au-dessus de 65 MW les performances du reacteur sont radicalement modifiees. La vitesse de degagement de la vapeur atteint 33 cm/s et la hauteur du dome de vapeur descend a 1m. Dans ces conditions, il se produit un entrainement de liquide par la vapeur qui augmente rapidement lorsqu'on augmente la puissance. Le reacteur cesse alors de se comporter comme un reacteur a eau bouillante a cycle direct; en un sens, il fonctionne comme un reacteur a deux cycles, en circulation naturelle. (author) [Spanish] El 25 de mayo de 1962, el Laboratorio Nacional de Argonne fue autorizado por la USAEC a poner en funcionamiento el EBWR con una potencia de 100 MW. En el marco de la administracion de su sistema de salvaguardias el Organismo Internacional de Energia Atomica dio su aprobacion el 11 de julio de 1962. El 15 de noviembre del mismo ano, el reactor alcanzo la potencia de 100 MW. El programa experimental ejecutado con el reactor EBWR de 100 MW quedo completado el 6 de diciembre de 1962. Uno de los principales propositos del mismo consistia en dotar al reactor de los instrumentos necesarios para obtener datos e informaciones sobre el rendimiento de este tipo de reactor

Design guide for Category III reactors: pool type reactors

International Nuclear Information System (INIS)

Brynda, W.J.; Lobner, P.R.; Powell, R.W.; Straker, E.A.

1978-11-01

The Department of Energy (DOE) in the ERDA Manual requires that all DOE-owned reactors be sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate consideration to health and safety factors. Specific guidance pertinent to the safety of DOE-owned reactors is found in Chapter 0540 of the ERDA Manual. The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC). This Design Guide deals principally with the design and functional requirement of Category III reactor structures, components, and systems

The computerized reactor period measurement system for China fast burst reactor-II

International Nuclear Information System (INIS)

Zhao Wuwen; Jiang Zhiguo

1996-01-01

The article simply introduces the hardware, principle, and software of the computerized reactor period measurement system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between fission yield and pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computerized measurement system makes the reactor period measurement into automatical and intelligent and also improves the speed and precision of period data on-line process

Computer measurement system of reactor period for China fast burst reactor-II

International Nuclear Information System (INIS)

Zhao Wuwen; Jiang Zhiguo

1997-01-01

The author simply introduces the hardware, principle, and software of the reactor period computer measure system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between Fission yield and Pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computer measure system makes the reactor period measurement into automation and intellectualization and also improves the speed and precision of period data process on-line

Reactor safety method

International Nuclear Information System (INIS)

Vachon, L.J.

1980-01-01

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

Small propulsion reactor design based on particle bed reactor concept

International Nuclear Information System (INIS)

Ludewig, H.; Lazareth, O.; Mughabghab, S.; Perkins, K.; Powell, J.R.

1989-01-01

In this paper Particle Bed Reactor (PBR) designs are discussed which use 233 U and /sup 242m/Am as fissile materials. A constant total power of 100MW is assumed for all reactors in this study. Three broad aspects of these reactors is discussed. First, possible reactor designs are developed, second physics calculations are outlined and discussed and third mass estimates of the various candidates reactors are made. It is concluded that reactors with a specific mass of 1 kg/MW can be envisioned of 233 U is used and approximately a quarter of this value can be achieved if /sup 242m/Am is used. If this power level is increased by increasing the power density lower specific mass values are achievable. The limit will be determined by uncertainties in the thermal-hydraulic analysis. 5 refs., 5 figs., 6 tabs

Physics of nuclear reactors

International Nuclear Information System (INIS)

Baeten, Peter

2006-01-01

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

New Frontiers for Non-Destructive Testing in the Nuclear Age; Perspectives des Essais Non Destructifs a l'Ere Nucleaire; ''Novye rubezhi'' nedestruktivnykh ispytanij v yadernyj vek; Nuevas Posibilidades de los Ensayos No Destructivos en la Era Nuclear

Energy Technology Data Exchange (ETDEWEB)

Ballard, D. W. [Sandia Laboratory Albuquerque, NM (United States)

1965-10-15

electromagneticos, se establecen otros nuevos para comprobar si el equipo retine los requisitos necesarios tanto en e l aspecto estatico como en el dinamico. Esos metodos ultrarrapidos y de elevado poder de resolucion constituyen en realidad las nuevas fronteras del ensayo no destructivo, y a ellos se refiere fundamentalmente la presente memoria. Entre los modernos metodos de ensayo que se estudian se cuenta el uso de rayos infrarrojos para verificar el estado de las soldaduras y la inspeccion cinematorradiografica de las estructuras durante los ensayos de vibracion para verificar su comportamiento dinamico. Hay que tener tambien muy en cuenta la importancia de una localizacion eficaz de los escapes para que el combustible de los reactores pueda utilizarse en condiciones de seguridad. Se examina un metodo de inspeccion de piezas revestidas, basado en el empleo de gas radiactivo, con el que se pueden medir fugas de incluso 10{sup -12} cm{sup 3}/s, esto es, de 1 cm{sup 3} cada 500 anos. Otro medio eficaz que puede utilizarse actualmente es la radiografia dinamica con gran ampliacion, basada en el uso de tubos vidicon sensibles a los rayos X. Se estudia asimismo un nuevo metodo analogo al indicado, (cinesonograffa); con este metodo, la obtencion de imagenes se realiza por medios ultrasonicos y no radiograficos. Para terminar, se procura estudiar el equipo totalmente automatico y ultrarrapido que habra de prepararse para exploracion a gran velocidad. Ese equipo supone la aplicacion simultanea de varios metodos de ensayo no destructivo. Los metodos basados en el empleo de rayos infrarrojos, los electromagneticos y los de microondas combinados con la exploracion gobernada por cinta magnetica se utilizan para obtener imagenes de la produccion; esas imagenes pueden ser televisadas o registradas a distancia. Se examinan los parametros de ensayo, las posibilidades de indicacion y los sistemas de comprobacion continua. Esas posibilidades se han estudiado ya en laboratorio y ahora hay que

Generation III+ Reactor Portfolio

International Nuclear Information System (INIS)

2010-03-01

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

Desempenho de reatores anaeróbios de fluxo ascendente com manta de lodo em dois estágios tratando águas residuárias de suinocultura Performance of two-stage up flow anaerobic sludge blanket reactors treating swine wastewater

Directory of Open Access Journals (Sweden)

Adriana M. de Santana

2005-12-01

Full Text Available Avaliou-se o desempenho de dois reatores anaeróbios de fluxo ascendente com manta de lodo (UASB em escala-piloto com volumes de 908 L e 188 L, instalados em série, alimentados com águas residuárias de suinocultura com concentrações médias de sólidos suspensos totais (SST variando de 2.216 mg L-1 a 7.131 mg L-1 e submetidos a tempos de detenção hidráulica (TDH de 62,3 e 31,1 h, no primeiro reator, e de 12,9 e 6,5 h, no segundo reator. As eficiências médias de remoção de DQOtotal variaram de 74,0% a 89,6% no Reator 1 e de 34,3% a 45,1% no Reator 2, resultando em valores médios de 86,6% a 93,1% para o sistema de tratamento em dois estágios com carga orgânica volumétrica (COV na faixa de 3,40 a 14,44 kg DQOtotal m-3 reator d-1 no Reator 1. As concentrações de metano no biogás foram acima de 75% para o Reator 1 e de 80% para o Reator 2. Os valores médios de pH variaram na faixa de 6,9 a 8,2 para o efluente do Reator 1 e de 7,0 a 8,3 para o efluente do Reator 2. Os ácidos voláteis totais mantiveram-se estáveis com concentrações médias abaixo de 200 mg L-1. Esses resultados indicaram que as condições de carga orgânica, em termos de DQO e SSV, impostas ao sistema de tratamento anaeróbio em dois estágios, não foram limitantes para que houvesse o desenvolvimento de lodo com microbiota adaptada e com alta atividade, propiciando altas eficiências médias de remoção de matéria orgânica (86,6 a 93,1% para DQOtotal e 85,6 a 88,2% para SSV e taxas de produção de metano de 0,156 a 0,289 m³ CH4 kg-1 de DQO removida.The objective of this work was monitoring the performance of two up flow anaerobic sludge blanket reactors (UASB in a pilot-scale testing with volumes of 908 L and 188 L, installed in series, loaded with swine wastewater with total suspended solids (TSS ranging from 2216 to 7131 mg L-1, submitted to an hydraulic detention time (HDT of 62.3 and 31.1 h, in the first reactor, and 12.9 and 6.5 h, in the second

Guide to power reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-07-15

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

Analysis of dynamic stability and safety of reactor system by reactor simulator

International Nuclear Information System (INIS)

Raisic, N.

1963-11-01

In order to enable qualitative analysis of dynamic properties of reactors RA and RB, mathematical models of these reactors were formulated and adapted for solution on analog computer. This report contains basic assessments for creating the model and complete equations for each reactor. Model was used to analyse three possible accidents at the RA reactor and possible hypothetical accidents at the RB reactor

Nuclear reactor physics

CERN Document Server

Stacey, Weston M

2010-01-01

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

Sodium-cooled nuclear reactor

International Nuclear Information System (INIS)

Hammers, H.W.

1982-01-01

The invention concerns a sodium-cooled nuclear reactor, whose reactor tank contains the primary circuit, shielding surrounding the reactor core and a primary/secondary heat exchanger, particularly a fast breeder reactor on the module principle. In order to achieve this module principle it is proposed to have electromagnetic circulating pumps outside the reactor tank, where the heat exchanger is accomodated in an annular case above the pumps. This case has several openings at the top end to the space above the reactor core, some smaller openings in the middle to the same space and is connected at the bottom to an annular space between the tank wall and the reactor core. As a favoured variant, it is proposed that the annular electromagnetic pumps should be arranged concentrically to the reactor tank, where there is an annual duct on the inside of the reactor tank. In this way the sodium-cooled nuclear reactor is made suitable as a module with a large number of such elements. (orig.) [de

Some Possibilities of the Eddy-Current Method for Multi-Parameter Testing of Structural Components; Quelques Possibilites Offertes par la Methode des Courants de Foucault pour le Controle de Nombreux Parametres des Elements de Construction; Nekotorye vozmozhnosti metoda vikhrevykh tokov dlya mnogoparametrovogo kontrolya ehlementov konstruktsij; Algunas Posibilidades que Brinda el Metodo de las Corrientes de Foucault para Controlar Numerosos Parametros de los Elementos de Construccion

Energy Technology Data Exchange (ETDEWEB)

Vjahorev, V. G.; Gerasimov, V. G.; Deniskin, V. P.; Trahtenberg, L. I.; Shkarlet, Ju. M. [Gosudarstvennyj Komitet po Ispol' zovaniju Atomnoj Jenergii SSSR, Moskva, SSSR (Russian Federation)

1965-09-15

donnees calculees et experimentales, les auteurs indiquent diverses possibilites de realisation de detecteurs a courants de Foucault de frequence unique permettant le controle avec modification simultanee de plusieurs parametres. (author) [Spanish] Los autores demuestran que los problemas del control no destructivo de diversos parametros se plantean en la tecnologia nuclear segun ciertas leyes y que el metodo de las corrientes de Foucault se adapta particularmente a la solucion de varios de esos problemas. Los autores justifican la utilizacion de modelos electricos para resolver problemas de control con ayuda de una larga bobina hueca. Presentan formulas y exponen un metodo para el calculo de detectores a base de corrientes parasitas. Describen un dispositivo que permite verificar el espesor de las paredes de tubos; en este dispositivo, el desplazamiento del tubo a controlar no ejerce influencia alguna sobre los resultados de las mediciones, gracias al empleo de un monitor accionado por una senal dependiente de la fase de tension del detector. En calidad de detector se ha empleado un dispositivo destinado al control de los tubos de un autogenerador despues de haber incluido en su circuito una bobina de ensayo. Partiendo de datos calculados y experimentales, los autores senalan diversas posibilidades de realizacion de detectores a base de corrientes de Foucault de frecuencia unica, que permiten efectuar el control con modificacion simultanea de varios parametros. (author) [Russian] Pokazana zakonomernost' voznikno- venija zadach o nerazrushajushhem mnogoparametrovom kontrole v jadernoj tehnologii i celeso- obraznost' reshenija nekotoryh iz nih metodom vihrevyh tokov. Obosnovano primenenie jelektricheskih modelej dlja reshenija zadach kontrolja s ispol'zovaniem dlinnoj prohodnoj katushki. Privodjatsja raschetnye formuly i izlagaetsja metodika rascheta nakladnyh toko- vihrevyh datchikov. Opisana shema pribora dlja kontrolja tolshhiny stenki trub, v kotorom vlijanie pereme

Atomic reactor thermal engineering

International Nuclear Information System (INIS)

Kim, Gwang Ryong

1983-02-01

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

Experimental petrology for the thermobarometric determination of mineral paragenesis: the fluid inclusions; Petrologia experimental para la determinacion termobarometrica de paragenesis minerales: las inclusiones fluidas

Energy Technology Data Exchange (ETDEWEB)

Gonzalez Partida, Eduardo; Torres Rodriguez, Vicente; Birkle, Peter [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1994-05-01

There is a great number of phenomena in nature in which some fluid participates as the main component. Such is the case of oil deposits formation, of metallic minerals, geothermal systems, metamorphic and diagenetic deposits. The common denominator of all of them is that in some part of their stages important physico-chemical processes occurred in the related fluids, leaving evidence of such phenomena in the fluid inclusions. The Geothermal Department has petrologic vanguard tools for reservoir problems resolution, since it has laboratories for the study on fluid inclusions by means of the technique called cryoscopic-microthermometry that permits the definition of physico-chemical conditions of the brine that participated or participates in the hydrothermal systems formation. The method simultaneously permits to know the characteristics of the initial brine that participated in the interaction water-rock phenomenon, observe the boiling phenomena, and determine conditions of initial pressure in the reservoirs. [Espanol] Existe un gran numero de fenomenos en la naturaleza en los que participa algun fluido como componente principal. Tal es el caso de la formacion de yacimientos de petroleo, de minerales metalicos, de sistemas geotermicos, yacimientos metamorficos y diageneticos. El comun denominador de todos ellos es que en alguna de sus etapas ocurrieron procesos fisicoquimicos importantes en los fluidos relacionados, quedando evidencia de tales fenomenos en las inclusiones fluidas. El Departamento de Geotermia cuenta con herramientas petrologicas de vanguardia para la resolucion de problemas en yacimientos, ya que tiene laboratorios para el estudio de las inclusiones fluidas por medio de la tecnica denominada microtermometria-crioscopica que permite definir condiciones fisicoquimicas de la salmuera que participo o participa en la formacion de sistemas hidrotermales. El metodo permite simultaneamente conocer las caracteristicas de la salmuera inicial que participo en

Argentinean integrated small reactor design and scale economy analysis of integrated reactor

International Nuclear Information System (INIS)

Florido, P. C.; Bergallo, J. E.; Ishida, M. V.

2000-01-01

This paper describes the design of CAREM, which is Argentinean integrated small reactor project and the scale economy analysis results of integrated reactor. CAREM project consists on the development, design and construction of a small nuclear power plant. CAREM is an advanced reactor conceived with new generation design solutions and standing on the large experience accumulated in the safe operation of Light Water Reactors. The CAREM is an indirect cycle reactor with some distinctive and characteristic features that greatly simplify the reactor and also contribute to a highly level of safety: integrated primary cooling system, self pressurized, primary cooling by natural circulation and safety system relying on passive features. For a fully doupled economic evaluation of integrated reactors done by IREP (Integrated Reactor Evaluation Program) code transferred to IAEA, CAREM have been used as a reference point. The results shows that integrated reactors become competitive with power larger than 200MWe with Argentinean cheapest electricity option. Due to reactor pressure vessel construction limit, low pressure drop steam generator are used to reach power output of 200MWe for natural circulation. For forced circulation, 300MWe can be achieved. (author)

Estudio de distribución de tiempos de residencia en un reactor biológico de lecho empacado cerámico

Directory of Open Access Journals (Sweden)

Tatiana Rodríguez Chaparro

2004-01-01

Full Text Available La distribución de tiempos de residencia de un reactor es una característica del mezclado que ocurre dentro de él [ ] 1 [ ] 2 ; su determinación es básica para el diseño de cualquier tipo de reactor en escala real. El objetivo de esta investigación consistió en determinar la distribución de tiempos de residencia en un reactor biológico de lecho empacado cerámico (anillos a partir de pruebas con trazadores. Los resultados obtenidos utilizando las técnicas de inyección por paso y pulso fueron 34.577 seg., y 17.745 seg., respectivamente, y la dispersión calculada infinita. Lo anterior permite concluir que en reactores de lecho empacado cerámico (anillos las moléculas del trazador se distribuyen uniformemente en todo el sistema. Los ensayos se realizaron en un modelo a escala laboratorio.

Fractal analysis of the electrical discharges' surface paths in polymeric insulation considering different pollution levels; Analisis fractal de las trayectorias de descargas electricas superficiales en aislamiento polimerico considerando diferentes niveles de contaminacion

Energy Technology Data Exchange (ETDEWEB)

Palacios Lopez, Arturo

2002-07-01

In this thesis tree patterns of superficial breakdown in polymeric insulator of Silicon Rubber are generated. Experimental arrangement rod-rod was used on the basis of norm ASTM D 2303-85. Pollution levels on the basis of norm IEC 507 were also used. The experimental values of Fractal Dimension for each case of pollution were reported. A self similar method called Box Counting for the fractal dimension calculus and for the self affine methods an R/S and Variogram were used. According to the results, it was concluded that the tree patterns of superficial electric breakdown in Silicon Rubber is self similar and its value does not depend on the degree of pollution, that is equivalent to the concentration of salt for liter of water or to the Equivalent Salt Deposition (ESDD), in the surface of an insulator. [Spanish] En el presente trabajo se inducen descargas electricas superficiales en un aislamiento polimerico de Hule Silicon, el arreglo experimental que se utilice es punta-punta con base en la norma ASTM D 2303-85 y los niveles de contaminacion con base en la norma IEC 507. Se reportan los valores experimentales de la Dimension Fractal para cada caso de contaminacion, se utilice el metodo auto similar de conteo de cuadros, para el calculo de la Dimension Fractal y para metodos auto afines se utilice analisis R/S y variograma. Con los resultados obtenidos se concluye que la trayectoria de la descarga electrica superficial en un polimero de Hule Silicon es auto similar y su valor no depende del grado de contaminacion, el cual es equivalente a la concentracion de gramos de sal por litro de agua o a la densidad de sal depositada (DESD), en la superficie de un aislador.

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

OpenAIRE

Lázaro, Gerardo; Parreño, Fernando

2001-01-01

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

Fast reactors

International Nuclear Information System (INIS)

Vasile, A.

2001-01-01

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

Comparative analysis between P1 and B1 equations for neutron moderation; Analise comparativa entre os metodos de obtencao e das solucoes das equacoes P1 e B1 para moderacao de neutrons

Energy Technology Data Exchange (ETDEWEB)

Martinez, Aquilino Senra; Silva, Fernando Carvalho da; Cardoso, Carlos Eduardo Santos [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear

2000-07-01

In order to calculate the neutron flux in nuclear reactors, B1 or P1 equations are solved by numerical methods for several groups of energy. The neutron fluxes obtained from the solutions of the B1 and P1 equations are similar when they are applied to large nuclear power reactors. However, an important difference between the two fluxes is that the system of P1 equations uses one more approximation than the B1 system and then, its flux is less precise. The present work shows the relations between both equations and analyzes for what conditions the two equations systems are equivalent. Furthermore, this equations are numerically solved in 54 groups of energy for a quadrangular arrange. (author)

Consideraciones de diseño para la eliminación biológica de fósforo empleando procesos biopelícula

OpenAIRE

Castillo de Castro, Pedro; Tejero Monzón, Iñaki

1999-01-01

El siguiente artículo es un resumen del estado del arte de la Eliminación Biológica de Fósforo (EBF) empleando procesos de biopelícula. En él se describen minuciosamente los mecanismos que intervienen en la eliminación biológica de este elemento, así como las teorías actualmente aceptadas. Se presentan los procesos biopelícula actualmente desarrollados, así como los consideraciones de diseño para reactores biopelícula, y la forma de trabajo necesaria para conseguir la EBF.

Reactor power measuring device

International Nuclear Information System (INIS)

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

1993-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

Reactor container

International Nuclear Information System (INIS)

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

1997-01-01

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

Study on Reactor Performance of Online Power Monitoring in PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

2014-01-01

The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on reactor performance of online power monitoring based on various parameter of reactor such as log power, linear power, period, Fuel and coolant temperature and reactivity parameter with using neutronic and other instrumentation system of reactor. Methodology of online power estimation and monitoring is to evaluate and analysis of reactor power which is important of reactor safety and control. Neutronic instrumentation system will use to estimate power measurement, differential of log and linear power and period during reactor operation .This study also focus on noise fluctuation from fission chamber during reactor operation .This work will present result of online power monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that optimization of online power monitoring will improved the reactor control and safety parameter of reactor during operation. (author)

Efecto de la concentración de SO2 en las reacciones de calcinación y sulfatación de calcáreos en reactores de lecho fluidizado. // Effect of the SO2 concentration in the calcinations and sulfatation reactions in a fluidized bed reactor.

Directory of Open Access Journals (Sweden)

J. E. Lindo Samaniego

2008-01-01

Full Text Available Fue realizado un estudio sobre el efecto de las concentraciones de SO2 en la absorción por calcáreo en hornos de LechoFluidizado. Para observar la influencia del SO2 en los parámetros de diferentes procesos físicos y químicos fueron creadosambientes para cuatro concentraciones diferentes de SO2 : 500, 1000, 2000 y 4000 ppm. Se utilizaron dos tipos decalcáreos: Dolimitico-DP y el Calcítico-CI. El Lecho Fluidizado Burbujeante utilizado tiene 160 mm de diámetro interno yfue fluidizado con aire a la temperatura de 850 °C, con una concentración de SO2 deseada. Como material del lecho fueutilizada la arena de cuarzo (99,9% con diámetro de 385 μm y de masa aproximadamente 3,0 kg. El calcáreo fueadicionado en dosificación de 50 g con el reactor ya pre-calentado. Las variaciones de las concentraciones de SO2, CO2,CO, O2 y las descargas, fueron monitoreadas continuamente a la salida del ciclón que fue utilizado para la retención de lapartícula fina. Para esos dados se desarrolló un programa en LabView. El modelo matemático escogido posibilitó ladeterminación de la conversión.Palabras claves: Lecho fluidizado, dióxido de azufre, absorción de azufre, calcáreo , reactor de lechofluidizado.___________________________________________________________________________Abstract.A Study of the effect of the concentrations of SO2 in its absorption by limestones in fluidized bed furnaces wasconducted. For the determination of the SO2 influence on the different physical and chemical parameters of process,such as calcinations and sulfatation four different atmospheres were used in the reator with concentrations of SO2 of500, 1000, 2000 and 4000 ppm. Two types of limestones were used: Dolomite-DP and Calcitic-CI. The bench scalebubbling fluidized bed reactor had a 160 mm internal diameter and was fluidized with air at 850 °C containing therequired concentration of SO2. Bed material was quartz sand (99,9% , with 385 μm diameter and approximately

A punched-card library of neutron cross-sections and its use in the mechanized preparation of group cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations on high-speed computers

Energy Technology Data Exchange (ETDEWEB)

Parker, K [Atomic Weapons Research Establishment, Aldermaston (United Kingdom)

1962-03-15

constantes de groupes pour reproduire des mesures integrales et la simplification d'une serie de constantes pour un grand nombre de groupes en vue d'obtenir une serie de constantes pour un petit nombre de groupes. (author) [Spanish] La memoria describe el fichero de tarjetas perforadas sobre las que se registran en el Atomic Weapons Research Establishment (AWRE) las secciones eficaces neutronicas, asi como los programas correspondientes de la calculadora IBM-7090 que se emplean para la elaboracion de estos datos con miras a obtener promedios por grupo de secciones eficaces apropiadas para calculos neutronicos de grupos multiples por los metodos de Montecarlo, de S{sub n} de Carlson y otros procedimientos. El autor expone seguidamente los metodos desarrollados para estudiar la dispersion elastica isotropica y anisotropica. Comprenden la aproximacion de transporte de grupos multiples y el tratamiento completo de la dispersion anisotropica empleando los momentos polinomicos de Legendre de la matriz de transferencia por dispersion. El trabajo expone los principios de la formacion de constantes de grupo y, a titulo ilustrativo, describe sistemas de constantes de grupo que sirven para calculos de reactores rapidos. Analiza algunos problemas practicos como la adaptacion empirica de las constantes de grupo para reproducir resultados de mediciones integrales, y la reduccion de un sistema de constantes de muchos grupos a otro de pocos grupos. (author) [Russian] V doklade daetsya opisanie nakho-dyashchejsya v Nauchno-issledovatel'sko m tsentre po razrabotke atomnogo oruzhiya biblioteki perforirovannykh kartochek sechenij nejtronov sovmestno s programmami IBM 7090, kotorye obrabatyvayut ehti dannye dlya polucheniya usrednennykh po gruppam sechenij, kotorye ispol'zuyutsya v nejtronnykh vychisleniyakh po metodam Monte Karlo, Karlsona S{sub n} i v drugikh mnogogruppovykh vychisleniyakh. Opisyvayutsya metody, kasayushchiesya kak izotropnogo, tak i anizotropnogo uprugogo rasseyaniya. Oni

Nuclear power reactors: reactor safety and military and civil defence

International Nuclear Information System (INIS)

Hvinden, T.

1976-01-01

The formation of fission products and plutonium in reactors is briefly described, followed by a short general discussion of reactor safety. The interaction of reactor safety and radioactive release considerations with military and civil defence is thereafter discussed. Reactors and other nuclear plants are factors which must be taken into account in the defence of the district around the site, and as potential targets of both conventional and guerilla attacks and sabotage, requiring special defence. The radiological hazards arising from serious damage to a power reactor by conventional weapons are briefly discussed, and the benefits of underground siting evaluated. Finally the author discusses the significance of the IAEA safeguards work as a preventive factor. (JIW)

Research reactors in Argentina

International Nuclear Information System (INIS)

Carlos Ruben Calabrese

1999-01-01

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

To the analysis of reactor noise in boiling water reactors

International Nuclear Information System (INIS)

Seifritz, W.

1972-01-01

The paper contains some basic thoughts on the problem of neutron flux oscillations in power reactors. The advantages of self-powered detectors and their function are explained. In addition, noise measurements of the boiling water reactors at Lingen and Holden are described, and the possibilities of an employment of vanadium detectors for the analysis of reactor noise are discussed. The final pages of the paper contain a complete list of the author's publications in the field of reactor noise analysis. (RW/AK) [de

Computerized supervision and control system for movement at the RP-10 reactor control rods bank; Sistema de supervicion y mando computarizado para el movimiento en banco de las barras de control del Reactor RP-10

Energy Technology Data Exchange (ETDEWEB)

Padilla M, C E

1998-07-01

The project involves the use of a compatible microcomputer, Labwindows/CVI software, as well as National Instruments data acquisition cards AT-MIO16-E10 and PC-DIO96 to modify the sequence of movement of the reactor's rods and control them from a graphic interface in a computer's monitor. This graphic presentation is set as console of virtual instruments from where rod movement can be conducted. Normal rod movement, bank rod movement, and rod calibration have been considered. These experiences involve different logic of rod movements, which will determine movement sequence. Control of the automatic range of a current amplifier module was also considered. This module is know as 'automatic pilot amplifier' and given the strategic location of its detector (compensated ionizing camera) at the reactor's core, it delivers neutron flux current considered as reference to superficial neutron flux distribution at the reactor's core. Lecture and monitoring of this signal allows taking the reactor to a certain power, current of this signal is proportional to the power we want the reactor to reach. Advantages obtained with this system include the update of the control console, more uniform distribution of neutron flux, with lower and uniform burnup of nuclear fuel. (author)