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Juanico, L.E.
Universidad Nacional de Cuyo, Mendoza (Argentina). Inst. Balseiro1997
Universidad Nacional de Cuyo, Mendoza (Argentina). Inst. Balseiro1997
AbstractAbstract
[en] A theoretical and experimental study of the dynamic behavior of a boiling channel is presented. In particular, the existence of different basins of attraction during instabilities was established. A fully analytical treatment of boiling channel dynamics were performed using a algebraic delay model. Subcritical and supercritical Hopf bifurcations could be identified and analyzed using perturbation methods. The derivation of a fully analytical criterion for Hopf bifurcation transcription was applied to determine the amplitude of the limit cycles and the maximum allowed perturbations necessary to break the system stability. A lumped parameters model which allows the representation of flow reversal is presented. The dynamic of very large amplitude oscillations, out of the Hopf bifurcation domain, was studied. The analysis revealed the existence of new dynamical basins of attraction, where the system may evolve to and return from with hysteresis. Finally, an experimental study was conducted, in a water loop at atmospheric pressure, designed to reproduce the operating conditions analyzed in the theory. Different dynamic phase previously predicted in the theory were found and their nonlinear characteristics were studied. In particular, subcritical and supercritical Hopf bifurcations and very large amplitude oscillations with flow reversal were identified. (author). 53 refs., figs
Original Title
Identificacion de cuencas dinamicas en flujos con ebullicion
Primary Subject
Source
1997; 189 p; Tesis (Dr. en Ingenieria Nuclear)
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Ventura, M.A.
Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)1998
Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)1998
AbstractAbstract
[en] Two radial conduction models, one for steady state and another for unsteady state, in a nuclear power reactor fuel element are developed. The objective is to obtain the temperatures in the fuel pellet and the cladding. The lumped-parameter hypothesis are adopted to represent the system. Both models are verified and their results are compared with similar ones. A method to calculate the conductance in the gap between the UO2 pellet and the clad and its associated uncertainty is included in the steady state model. (author)
[es]
Se desarrollan dos modelos (uno estacionario y otro transitorio) para simular la conduccion radial en un elemento combustible y vaina del elemento. Se adopta la hipotesis de representacion de parametros concentrados. Dichos modelos son verificados y comparados con otros similares. Se incluye en el modelo estacionario un metodo para calcular la conductancia del huelgo existente entre la pastilla de UO2 y la vaina del elemento combustible y la incerteza asociada a su valor. (autor)Original Title
Conduccion de calor radial en un elemento combustible de un reactor de potencia
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1998; 32 p; 9 refs., 6 figs., 3 tabs.
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Marengo, J.A.; Ruch, M.; Spinosa, C.
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation1997
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation1997
AbstractAbstract
[en] Electromagnetic nondestructive techniques are usually applied to solve many inspection problems in industry. In particular, eddy currents are used for the detection of defects and the characterization of physical properties of metallic materials and components. One such application is the measurement of thickness of non conductive layers on a conducting substrate. A laboratory device for the quantitative determination of those thicknesses was developed at our laboratory. It works in the range from 0 to 100 μm and was calibrated with a micro metre screw. This task involved the design and construction of the sensors their characterization (working frequency, resolution, sensitivity, etc.) and the setup of the mechanical system and the electronic signal generation and measurement circuit. (author)
[es]
Las tecnicas electromagneticas se aplican para resolver diversos problemas en la industria. En metalurgia, la utilizacion de corrientes inducidas permite detectar defectos y caracterizar propiedades fisicas en materiales y componentes. En particular, una de las aplicaciones es la medicion de espesores de capas de recubrimientos aislantes sobre sustrato conductor. Se desarrollo en laboratorio un dispositivo para efectuar un analisis cuantitativo de estos espesores. En la calibracion del mismo se utilizo un tornillo micrometrico. Los espesores a medir estaban en un rango entre 0 y 100 μm. La implementacion de tal sistema involucro el diseno de los sensores de medicion, la construccion de los mismos, el estudio de sus caracteristicas (frecuencia de trabajo, resolucion, sensibilidad, etc.) y la puesta a punto del sistema mecanico y del circuito electronico de generacion de senal y medidas, usados para la realizacion de la tarea. (autor)Original Title
Caracterizacion no destructiva de recubrimientos superficiales sobre materiales no ferromagneticos
Primary Subject
Source
Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Universidad Tecnologica Nacional, Mendoza (Argentina). Facultad Regional; 424 p; 1997; p. 277-281; CORENDE: Regional congress on nondestructive and structural evaluation; CORENDE: Congreso regional de ensayos no destructivos y estructurales; Mendoza (Argentina); 27-30 Oct 1997; 5 refs., 11 figs.
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Kulichevsky, R.
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation1997
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation1997
AbstractAbstract
[en] The nuclear power plants steam generators have different types of structural supports. One of these types are the antiseismic supports, which are intended to be under stress only if a seismic event takes place. Nevertheless, the antiseismic supports lugs, that are welded to the steam generator vessel, are subjected to thermal fatigue because of the temperature cycles related with the shut down and start up operations performed during the life of the nuclear power plant. In order to evaluate the stresses that the lugs are subjected to, several strain gages were welded on two supports lugs, positioned at two heights of one of the Embalse nuclear power plant steam generators. In this paper, the instrumentation used and the strain measurements obtained during two start up operations are presented. The influence of the plant start up operation parameters on the lugs strain evolution is also analyzed. (author)
[es]
Los generadores de vapor de las centrales nucleares poseen distintos tipos de soportes estructurales. Uno de esos tipos son los soportes antisismicos, los que deberian soportar cargas solo en el caso en que tenga lugar un evento sismico. A pesar de ello, se encuentran sometidos a un proceso de fatiga termica originado en los ciclos termicos que se producen durante las paradas y puesta en marcha de la central a lo largo de la vida util de la misma. Con el objeto de evaluar estas cargas durante la puesta en marcha de la central, se instrumentaron con extensometros dos soportes antisismicos de uno de los generadores de vapor de la central nuclear Embalse, uno en la zona superior y otro en la zona inferior del mismo. En este trabajo se presenta el tipo de instrumentacion utilizada y los resultados obtenidos durante dos operaciones de puesta en marcha. Se analiza ademas la influencia de los parametros de operacion de la puesta en marcha de la central sobre la evolucion de las deformaciones. (autor)Original Title
Mediciones de deformacion en soportes antisismicos de un generador de vapor en una central nuclear
Primary Subject
Source
Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Universidad Tecnologica Nacional, Mendoza (Argentina). Facultad Regional; 424 p; 1997; p. 333-337; CORENDE: Regional congress on nondestructive and structural evaluation; CORENDE: Congreso regional de ensayos no destructivos y estructurales; Mendoza (Argentina); 27-30 Oct 1997; 1 ref., 7 figs., 1 tab.
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Pastorini, A.; Belinco, C.
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation1997
Proceedings CORENDE: Regional congress on nondestructive and structural evaluation1997
AbstractAbstract
[en] 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)
[es]
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 conjunto ante distintas condiciones de caudal de fluido. En el trabajo se incluye una descripcion de las facilidades de ensayo utilizadas y una presentacion de los resultados obtenidos durante la caracterizacion dinamica del prototipo y durante los ensayos con circulacion de fluido. (autor)Original Title
Ensayos hidrodinamicos para verificacion de diseno de un elemento combustible para reactores de investigacion
Primary Subject
Source
Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Universidad Tecnologica Nacional, Mendoza (Argentina). Facultad Regional; 424 p; 1997; p. 407-413; CORENDE: Regional congress on nondestructive and structural evaluation; CORENDE: Congreso regional de ensayos no destructivos y estructurales; Mendoza (Argentina); 27-30 Oct 1997; 4 refs., 12 figs., 4 tabs.
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Lopez, F.O.; Bruno, H.A.
Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)1998
Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)1998
AbstractAbstract
[en] In natural uranium and heavy water reactors, tritium is produced mainly as the activation product of the deuterium in the moderator and cooling medium. About 75% of the liquid effluents discharged by nuclear power plants in Argentina correspond to tritium. In the case of the Embalse nuclear power plant, the liquid effluents are discharged into the Rio Tercero reservoir. As its water is used for drinking, 98% of the dose received by the critical group is due to these discharges. A simple mathematical model was developed which predicts the variation in the tritium concentration in the reservoir. It is a complete mixture type model and the entry parameters are the lake volume, entrance volume and discharge volume. The model was solved by means of a Runge-Kutta method of second order. The chosen method is a modified Euler. A good correlation is observed when the values obtained by means of the numeric resolution of the developed model are compared with the values obtained by the tritium measurement made during the 1996 and 1997 environmental monitoring program. (author)
[es]
Se desarrollo un modelo fisico sencillo que predice la variacion de la concentracion de tritio en el lago de Embalse Rio Tercero. Este es un modelo del tipo mezcla completa (o total) basado en los siguientes parametros de entrada: el volumen del lago, el caudal del mismo, la descarga de la central y la constante de desintegracion radiactiva. El modelo fue resuelto numericamente mediante un metodo de Runge-Kutta de segundo orden. El metodo elegido es el de Euler modificado. Se presenta la comparacion de los valores obtenidos mediante la resolucion numerica del modelo desarrollado y los valores de concentracion de tritio en aguas del embalse, medidos durante el monitoreo ambiental que realiza en forma rutinaria la Autoridad Regulatoria Nuclear. En esta comparacion se observa una buena correlacion. (autor)Original Title
Analisis del comportamiento temporal de la concentracion de tritio en el lago Embalse Rio Tercero
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1998; 6 p; 4 refs., 1 fig.
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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CANDU TYPE REACTORS, DEVELOPING COUNTRIES, EQUATIONS, HEAVY WATER MODERATED REACTORS, HYDROGEN COMPOUNDS, HYDROGEN ISOTOPES, ISOTOPES, LATIN AMERICA, LIGHT NUCLEI, NUCLEAR FACILITIES, NUCLEI, ODD-EVEN NUCLEI, OXYGEN COMPOUNDS, POWER PLANTS, POWER REACTORS, PRESSURE TUBE REACTORS, RADIOISOTOPES, REACTORS, SOUTH AMERICA, SURFACE WATERS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER, YEARS LIVING RADIOISOTOPES
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Santa Cruz, G.A.
Proceedings of the 6. Argentine congress on radiation protection and nuclear safety1998
Proceedings of the 6. Argentine congress on radiation protection and nuclear safety1998
AbstractAbstract
[en] Full text: A charged particles transport Monte Carlo code, specially designed for the boron neutron capture therapy microdosimetry study was developed. The code allows the use of real tri dimensional problem geometry, using serial microscopy slides from a biological substrate where the 10B(n, Alpha)7Li, 14N(n,p)14C reactions and events can occur. The spatial distribution of sources (10B, 14N concentrations), regions of interest (where the energy deposition, linear energy transfer and other parameters will be calculated) and other zones (without boron) are obtained from the images. The code is in the benchmarking stage, using geometrically simple cases and experimental data obtained from microdosimetric spectra from TEPC (Tissue Equivalent Proportional Counters) doped with 10B. It allows to obtain LET spectra discriminated by event classes, chord-length distributions, dose and frequency mean values and visualizations of the spatial energy deposition. A similar version of the code uses bidimensional images from a tissue sample containing a great number of cellular structures. An equivalence between the microdosimetry of a bidimensional case and a tri dimensional one can be done. If the real distribution of 10B is known, for example by high resolution alpha-track autoradiography, the code can use this information explicitly. (author)
[es]
Texto completo: Se ha desarrollado un codigo de calculo por Monte Carlo de transporte de particulas cargadas especialmente disenado para el estudio de la microdisometria en Boron Neutron Capture Therapy (BNCT). Este permite utilizar la geometria tridimensional real del problema y para ello se utilizan imagenes que describen, mediante cortes seriados, las distintas regiones de interes de un sustrato biologico donde se desarrollan los posibles enventos correspondientes a las reacciones 10B(n,alfa)7Li y 14N(n,p)14C. Estas proveen al programa la ubicacion espacial de regiones de fuentes (concentraciones de 10B y 14N), regiones sensibles (donde se desea calcular la energia depositada, el LET y su districubiicion espacial) y regiones pasivas. Este codigo se encuentra actualmente en la etapa de validacion, para la cual se utilizan casos sencillos geometricamente y casos experimentales tales como la reproduccion de espectros microdosimetricos obtenidos con contadores proporcionales equivalentes a tejido (TEPC) dopados con 10B. Permite obtener espectros de LET con la contribucion de los distintos eventos, distribuciones de cuerdas, valores medios de LET para las distribuciones de frecuencia y dosis y visualizaciones de la distribucion espacial de la energia depositada. Una extension del codigo permite trabajar con imagenes bidimensionales de un tejido altamente poblado de celulas. Puede realizarse una equivalencia entre las mediciones microdosimetricas para un conjunto grande de cortes de celulas y las que se obtendrian para una celula representativa de la poblacion. Ademas esta preparado para el caso en que se cuente con informacion directa de la distribucion de boro 10, por ejemplo por autorradiografia sobre un detector de trazas. (autor)Original Title
Desarrollo de un codigo Monte Carlo tridimensional para el estudio de la microdosimetria aplicada a la terapia por captura neutronica de boro
Primary Subject
Secondary Subject
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Sociedad Argentina de Radioproteccion, Buenos Aires (Argentina); 75 p; 1998; p. 26; 6. Argentine congress on radiation protection and nuclear safety; 6. Congreso argentino de proteccion radiologica y seguridad nuclear; Buenos Aires (Argentina); 22-24 Sep 1998
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Cardenas, H.; Perez, A.
Proceedings of the 6. Argentine congress on radiation protection and nuclear safety1998
Proceedings of the 6. Argentine congress on radiation protection and nuclear safety1998
AbstractAbstract
[en] Transport of 1,8% U235 enriched fuel rods needs both the evaluation of the radiological risk and considerations about criticality aspects. Issues as diverse production characteristics, storage facilities in the source of origin an economical aspects have to be added to the radiological and nuclear considerations. Transport of those rods through national territory must comply with the Argentine Regulatory authority's regulations, based on the Safety Series No. 6, (ed. 1985) -as amended 1990- IAEA. Safety criteria are exposed, taking into account the amount of material to be transported, container characteristics, packaging type and expedition conditions. (author)
Original Title
Estudio preliminar para el transporte de barras combustibles de UO2 enriquecido al 1,8%
Primary Subject
Source
Sociedad Argentina de Radioproteccion, Buenos Aires (Argentina); 75 p; 1998; p. 64; 6. Argentine congress on radiation protection and nuclear safety; 6. Congreso argentino de proteccion radiologica y seguridad nuclear; Buenos Aires (Argentina); 22-24 Sep 1998; Abstract prepared for a document that is itself an abstract
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ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, DOCUMENT TYPES, EVEN-ODD NUCLEI, FUEL ELEMENTS, HEAVY NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LAWS, MINUTES LIVING RADIOISOTOPES, NUCLEI, RADIOISOTOPES, REACTOR COMPONENTS, SPONTANEOUS FISSION RADIOISOTOPES, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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Lopez Vietri, J.R.; Novo, R.G.; Bianchi, A.J.
Proceedings of the 6. Argentine congress on radiation protection and nuclear safety1998
Proceedings of the 6. Argentine congress on radiation protection and nuclear safety1998
AbstractAbstract
[en] Full text: This paper points out a comparative analysis between the requirements of the 1985 edition (as Amended 1990), in-force in almost all countries included Argentina, and the 1996 edition, that is foresee to put in-force 1st January 2001, of the Regulations for the safe transport of radioactive material, published by the International Atomic Energy Agency (IAEA). The English version of the 1996 edition was published in December 1996 and the Spanish one in September 1997. Such edition was the culmination of a difficult consensus and harmonisation reached after an analysis process of the-years cycle between the IAEA Member Sates and related international organisations (United Nations, International Civil Aviation Organisation, International Air Transport Association, International Federation of Air Lines Pilots Associations, International Maritime Organisation) as well as regional organisations (Economic Commission for Europe, Commission of the European Communities). Both editions of the Regulations include a set of design, operational and administrative requirements that substantially do not differ as for their safety basic philosophy. However, the 1996 edition introduces numerous modifications of different magnitude, which will derive in technological, economic and operative consequences. Of such modifications the paper only analysed the relevant ones which update the state of art in the subject and allow the Regulations continue maintaining an acceptable level of control of the radiation, criticality and thermal hazards to persons, property and the environment during the transport of radioactive material. In addition, the paper briefly describes the possible impact that the main modifications induced in the 1996 edition of the Regulations should have, depending on the type of user considered either in Argentina or in other Latin America countries. However, it is desirable that the personal of competent authorities of each country involved in transport regulatory activities know in detail all the modifications introduced in the 1996 edition and notify them to the corresponding users. It is advantageous because of changes in structural or thermal requirements should be interesting for designers instead of changes in operative or administrative requirements should be for consignors or carriers concern. (author)
[es]
Texto completo: El presente trabajo contiene un analisis comparativo entre las disposiciones de la edicion de 1986 (enmendada en 1990), vigente en casi todos los paises incluyendo la Argentina, y la edicion de 1996, que se preve entrara en vigencia en enero del 2001, del 'Reglamento para el transporte seguro de materiales radiactivos' del Organismo Internacional de Energia Atomica (OIEA). La edicion de 1996, publicada en idioma ingles en diciembre de 1996 y en castellano en septiembre de 1997, fue el corolario de un dificultoso consenso y armonizacion alcanzado despues de un ciclo de 10 anios de analisis entre los Estados Miembros del OIEA y los organismos internacionales (Naciones Unidas, Organizacion de Aviacion Civil Internacional, Asociacion de Transporte Aereo Internacional, Federacion Internacional de las Asociaciones de Pilotos de Lineas Aereas, Organizacion Maritima Internacional) y regionales (Comision Economica para Europa, Comision de las Comunidades Europeas). Ambas ediciones del Reglamento contienen un conjunto de requisitos de disenio, operativos y administrativos que en sustancia no difieren en cuanto a la filosofia basica de seguridad. Sin embargo, la ultima edicion introduce numerosas modificaciones de diversa magnitud que derivaran en consecuencias de indole tecnologica, economica y opoerativa. Tales mofidicaciones, de las cuales se analizan solo las mas relevantes, actualizan el estado del arte en el tema permitiendo que la norma continue manteniendo un grado razonable de control sobre los riesgos radiologicos, de criticidad y termicos que pueden correr las personas, los bienes y el medio ambiente durante el transporte de materiales radiactivos. Ademas, el trabajo describe sucintamente el posible impacto que las principales modificaciones introducidas en la edicion de 1996 del Reglamento podrian tener, segun el tipo de usuario que se trate, en Argentina o en otros paises de America Latina. Sin embargo, es aconsejable que los integrantes de las autoridades competentes de cada pais que ejerzan funciones regulatorias del transporte conozcan en detalle todas las modificaciones introducidas en dicha edicion y las informen a los correspondientes usuarios, ya que por ejemplo, los cambios en los requisitos estructurales o termicos serian de interes a los diseniadores y los de indole operativa o administrativa a los remitentes o transportistas. (autor)Original Title
El reglamento de transporte del OIEA: principales modificaciones incorporadas en la edicion de 1996 y el posible impacto de su adopcion en Argentina
Primary Subject
Source
Sociedad Argentina de Radioproteccion, Buenos Aires (Argentina); 75 p; 1998; p. 66; 6. Argentine congress on radiation protection and nuclear safety; 6. Congreso argentino de proteccion radiologica y seguridad nuclear; Buenos Aires (Argentina); 22-24 Sep 1998
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Segado, R.C.; Menossi, C.A.
Proceedings of the 6. Argentine congress on radiation protection and nuclear safety1998
Proceedings of the 6. Argentine congress on radiation protection and nuclear safety1998
AbstractAbstract
[en] Full text: The first Radiation Protection and Nuclear Safety Postgraduate Course was held in 1977, when the former Radioprotection and Nuclear Safety Branch of the National Atomic Energy Commission decided implement that course for the qualification of its professionals. After then, in 1980, by agreement between the CNEA, the National University of Buenos Aires and the Ministry of Health and Social Welfare got its present academic qualification as a Post-Graduate Course. Since then, it was sponsored by the IAEA. This Organization annually grants fellowships to fifteen students from different countries. Up to now, twenty consecutive courses have been delivered and more than five hundredth graduated, more than half of them coming from abroad. The aim of the course is the qualification and training in Radiological Protection and Nuclear Safety of those professionals involved in the design, construction, operation and decommissioning of Nuclear and Radioactive Installation and their related regulatory issues. (author)
[es]
Texto completo: En el anio 1977, la entonces Gerencia de Proteccion Radiologica y Seguridad Nuclear de la Comision Nacional de Energia Atomica implemento un Curso de Proteccion Radiologica y Seguridad Nuclear. En 1980, por convenio con la Facultad de Ingenieria de la Universidad de Buenos Aires y el Ministerio de Salud y Accion Social se transformo en Curso de Postgrado, y a partir de ese anio recibio el auspicio de la OIEA. Desde entonces se ha venido dictando ininterrumpidamente, y de el han egresado hasta el presente 516 profesionales, de los cuales aproximadamente la midad fueron argentinos, y el resto extranjeros (mayoritariamente latinoamericanos) becados por el OIEA. Actualmente el Curso continua siendo desarrollado por la Autoridad Regulatoria Nuclear Argentina, con los mismos colaboradores y auspicio. El objetivo del mismo radica en la capacitacion de profesionales que participaran en el diseno, construccion, operacion y cierre de instalaciones nucleares y radiactivas (comprendiendo estas, las aplicaciones medicas e industriales), y los aspectos regulatorios concernientes. El cuerpo docente esta integrado por especialistas, provenientes fundamentalmente de las instituciones que lo organizan, del OIEA (que posibilita la participacion de especialistas internacionales) y profesionales de otras instituciones nacionales (oficiales o privadas). Durante el desarrollo del curso se realizan trabajos practicos en laboratorios e instalaciones dedicados especificamente a las tecnicas, determinaciones y/o experimentacion, en las que se capacita al participante. El nivel de excelencia de la capacitacion que se brinda puede apreciarse al observar que en muchos paises de America Latina y el Caribe, cargos de relevancia en instituciones especializadas en temas radiactivos y nucleares son desempenados por ex-alumnos del curso. En el presente trabajo se describen las caracteristicas fundamentales del curso, de su desarrollo, organizacion y contenido programatico. (autor)Original Title
Curso de postgrado en proteccion radiologica y seguridad nuclear
Primary Subject
Source
Sociedad Argentina de Radioproteccion, Buenos Aires (Argentina); 75 p; 1998; p. 18; 6. Argentine congress on radiation protection and nuclear safety; 6. Congreso argentino de proteccion radiologica y seguridad nuclear; Buenos Aires (Argentina); 22-24 Sep 1998
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