979 resultados para Radioactive decontamination.


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The assessment of the accuracy of parameters related to the reactor core performance (e.g., ke) and f el cycle (e.g., isotopic evolution/transmutation) due to the uncertainties in the basic nuclear data (ND) is a critical issue. Different error propagation techniques (adjoint/forward sensitivity analysis procedures and/or Monte Carlo technique) can be used to address by computational simulation the systematic propagation of uncertainties on the final parameters. To perform this uncertainty assessment, the ENDF covariance les (variance/correlation in energy and cross- reactions-isotopes correlations) are required. In this paper, we assess the impact of ND uncertainties on the isotopic prediction for a conceptual design of a modular European Facility for Industrial Transmutation (EFIT) for a discharge burnup of 150 GWd/tHM. The complete set of uncertainty data for cross sections (EAF2007/UN, SCALE6.0/COVA-44G), radioactive decay and fission yield data (JEFF-3.1.1) are processed and used in ACAB code.

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For a number of important nuclides, complete activation data libraries with covariance data will be produced, so that uncertainty propagation in fuel cycle codes (in this case ACAB,FISPIN, ...) can be developed and tested. Eventually, fuel inventory codes should be able to handle the complete set of uncertainty data, i.e. those of nuclear reactions (cross sections, etc.), radioactive decay and fission yield data. For this, capabilities will be developed both to produce covariance data and to propagate the uncertainties through the inventory calculations.

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The accurate computation of radioactive opacities is needed in several research fields such as astrophysics, magnetic fusion or ICF target physics analysis, in which the radiation transport is an important feature to determine in detail. Radiation transport plays an important role in the transport of energy in dense plasma and it is strongly influenced by the variation of plasma opacity with density and temperature, as well as, photon energy. In this work we present some new features of the opacity code ATMED [1]. This code has been designed to compute the spectral radioactive opacity as well as the Rosseland and Planck means for single element and mixture plasmas. The model presented is fast, stable and reasonably accurate into its range of application and it can be a useful tool to simulate ICF experiments in plasma laboratory.

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The main objective of this course, conducted by Jóvenes Nucleares (Spanish Young Generation in Nuclear, JJNN), a non-profit organization that depends on the Spanish Nuclear Society (SNE) is to pass on basic knowledge about Science and Nuclear Technology to the general public, mostly students and introduce them to its most relevant points. The purposes of this course are to provide general information, to answer the most common questions about Nuclear Energy and to motivate the young students to start a career in nuclear. Therefore, it is directed mainly to high school and university students, but also to general people that wants to learn about the key issues of such an important matter in our society. Anybody could attend the course, as no specific scientific education is required. The course is done at least once a year, during the Annual Meeting of the Spanish Nuclear Society, which takes place in a different Spanish city each time. The course is done also to whichever university or institution that asks for it to JJNN, with the only limit of the presenter´s availability. The course is divided into the following chapters: Physical nuclear and radiation principles, Nuclear power plants, Nuclear safety, Nuclear fuel, Radioactive waste, Decommission of nuclear facilities, Future nuclear power plants, Other uses of nuclear technology, Nuclear energy, climate change and sustainable development. The course is divided into 15 minutes lessons on the above topics, imparted by young professionals, experts in the field that belongs either to the Spanish Young Generation in Nuclear, either to companies and institutions related with nuclear energy. At the end of the course, a 200 pages book with the contents of the course is handed to every member of the audience. This book is also distributed in other course editions at high schools and universities in order to promote the scientific dissemination of the Nuclear Technology. As an extra motivation, JJNN delivers a course certificate to the assistants. At the end of the last edition course, in Santiago de Compostela, the assistants were asked to provide a feedback about it. Some really interesting lessons were learned, that will be very useful to improve next editions of the course. As a general conclusion of the courses it can be said that many of the students that have assisted to the course have increased their motivation in the nuclear field, and hopefully it will help the young talents to choose the nuclear field to develop their careers

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One of the main goals of Spanish Young Generation (JJNN) is to spread knowledge about nuclear energy, not only pointing out its advantages and its role in our society, but also trying to correct some of the ideas that are due to the biased information and to the lack of knowledge. With this goal in mind, lectures were given in several high schools, aimed at students ranging from 14 to 18 years old. This paper explains the experience accumulated during those talks and the conclusions that can be drawn, so as to better focus the communication about nuclear energy, especially the one aimed at a young public. In order to evaluate the degree of knowledge and information on a specific topic of a given group of individuals, statistical methods must be used. At the beginning of each lecture (and sometimes at the end, in order to evaluate the impact of the talk) the students were submitted to a short survey conducted by Spanish Young Generation. It consisted in eight questions, dealing with the relation between the main environmental issues (global warming, acid rain, radioactive waste…) and nuclear energy. The answers can be surprising, especially for professionals of the nuclear field who, since they are so familiar with this topic, often forget that this is just the case of a minority of people. A better knowledge of the degree of information of a given group enables to focus and personalize the communication. Another communication tool is the direct contact with students: it starts with their questions, which can then lead to a small debate. If the surveys inform about the topics they are unaware of, the direct exchange with them enables to find the most effective way to provide them the information. Of course, it depends a lot on the public attending the talk (age, background…) and on the debate following the talk: a good communication, adapted to the public, is necessary. Therefore, the outcome of the performed exercise is that Spanish teenagers have still a lack of knowledge about nuclear energy. We can learn that items that are evident for nuclear young professionals are unknown for high school teenagers

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El microclima urbano juega un rol importante en el consumo energético de los edificios y en las sensaciones de confort en los espacios exteriores. La urgente necesidad de aumentar la eficiencia energética, reducir las emisiones de los contaminantes y paliar la evidente falta de sostenibilidad que afecta a las ciudades, ha puesto la atención en el urbanismo bioclimático como referente para una propuesta de cambio en la forma de diseñar y vivir la ciudad. Hasta ahora las investigaciones en temas de microclima y eficiencia energética se han concentrado principalmente en como orientar el diseño de nuevos desarrollo. Sin embargo los principales problemas de la insostenibilidad de las actuales conurbaciones son el resultado del modelo de crecimiento especulativo y altamente agotador de recursos que han caracterizado el boom inmobiliario de las últimas décadas. Vemos entonces, tanto en España como en el resto de los Países Europeos, la necesidad de reorientar el sector de la construcción hacía la rehabilitación del espacio construido, como una alternativa capaz de dar una solución más sostenible para el mercado inmobiliario. En este propósito de mejorar la calidad de las ciudades actuales, el espacio público juega un papel fundamental, sobre todo como lugar para el encuentro y la socialización entre los ciudadanos. La sensación térmica condiciona la percepción de un ambiente, así que el microclima puede ser determinante para el éxito o el fracaso de un espacio urbano. Se plantea entonces cómo principal objetivo de la investigación, la definición de estrategias para el diseño bioclimático de los entornos urbanos construidos, fundamentados en las componentes morfotipológica, climática y de los requerimientos de confort para los ciudadanos. Como ulterior elemento de novedad se decide estudiar la rehabilitación de los barrios de construcción de mediado del siglo XX, que en muchos casos constituyen bolsas de degrado en la extendida periferia de las ciudades modernas. La metodología empleada para la investigación se basa en la evaluación de las condiciones climáticas y de confort térmico de diferentes escenarios de proyecto, aplicados a tres casos de estudio situados en un barrio periurbano de la ciudad de Madrid. Para la determinación de los parámetros climáticos se han empleado valores obtenidos con un proceso de simulación computarizada, basados en los principios de fluidodinámica, termodinámica y del intercambio radioactivo en el espacio construido. A través de uso de programas de simulación podemos hacer una previsión de las condiciones microclimáticas de las situaciones actuales y de los efectos de la aplicación de medidas. La gran ventaja en el uso de sistemas de cálculo es que se pueden evaluar diferentes escenarios de proyecto y elegir entre ellos el que asegura mejores prestaciones ambientales. Los resultados obtenidos en los diferentes escenarios han sido comparados con los valores de confort del estado actual, utilizando como indicador de la sensación térmica el índice UTCI. El análisis comparativo ha permitido la realización de una tabla de resumen donde se muestra la evaluación de las diferentes soluciones de rehabilitación. Se ha podido así demostrar que no existe una solución constructiva eficaz para todas las aplicaciones, sino que cada situación debe ser estudiada individualmente, aplicando caso por caso las medidas más oportunas. Si bien los sistemas de simulación computarizada pueden suponer un importante apoyo para la fase de diseño, es responsabilidad del proyectista emplear las herramientas más adecuadas en cada fase y elegir las soluciones más oportunas para cumplir con los objetivos del proyecto. The urban microclimate plays an important role on buildings energy consumption and comfort sensation in exterior spaces. Nowadays, cities need to increase energy efficiency, reduce the pollutants emissions and mitigate the evident lack of sustainability. In reason of this, attention has focused on the bioclimatic urbanism as a reference of change proposal of the way to design and live the city. Hitherto, the researches on microclimate and energy efficiency have mainly concentrated on guiding the design of new constructions. However the main problems of unsustainability of existing conurbations are the result of the growth model highly speculative and responsible of resources depletion that have characterized the real estate boom of recent decades. In Spain and other European countries, become define the need to redirect the construction sector towards urban refurbishment. This alternative is a more sustainable development model and is able to provide a solution for the real estate sector. In order to improve the quality of today's cities, the public space plays a key role, especially in order to provide to citizens places for meeting and socializing. The thermal sensation affects the environment perception, so microclimate conditions can be decisive for the success or failure of urban space. For this reasons, the main objective of this work is focused on the definition of bioclimatic strategies for existing urban spaces, based on the morpho-typological components, climate and comfort requirements for citizens. As novelty element, the regeneration of neighborhoods built in middle of the twentieth century has been studied, because are the major extended in periphery of modern cities and, in many cases, they represent deprived areas. The research methodology is based on the evaluation of climatic conditions and thermal comfort of different project scenarios, applied to three case studies located in a suburban neighborhood of Madrid. The climatic parameters have been obtained by computer simulation process, based on fluid dynamics, thermodynamics and radioactive exchange in urban environment using numerical approach. The great advantage in the use of computing systems is the capacity for evaluate different project scenarios. The results in the different scenarios were compared with the comfort value obtained in the current state, using the UTCI index as indicator of thermal sensation. Finally, an abacus of the thermal comfort improvement obtained by different countermeasures has been performed. One of the major achievement of doctoral work is the demonstration of there are not any design solution suitable for different cases. Each situation should be analyzed and specific design measures should be proposed. Computer simulation systems can be a significant support and help the designer in the decision making phase. However, the election of the most suitable tools and the appropriate solutions for each case is designer responsibility.

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Las cuestiones relacionadas con el transporte de residuos radiactivos de alta actividad (RAA) al previsto almacén temporal centralizado (ATC) en Villar de Cañas (Cuenca) están de actualidad, debido a la movilidad que se espera en un futuro próximo, el compromiso con el medio ambiente, la protección de las personas, así, como la normativa legal reguladora. En esta tesis se ha evaluado el impacto radiológico asociado a este tipo de transportes mediante una nueva herramienta de procesamiento de datos, que puede ser de utilidad y servir como documentación complementaria a la recogida en el marco legal del transporte. Además puede facilitar el análisis desde una perspectiva más científica, para investigadores, responsables públicos y técnicos en general, que pueden utilizar dicha herramienta para simular distintos escenarios de transportes radiactivos basados únicamente en datos de los materiales de entrada y las rutas elegidas. Así, conociendo el nivel de radiación a un metro del transporte y eligiendo una ruta, obtendremos los impactos asociados, tales como las poblaciones afectadas, la dosis recibida por la persona más expuesta, el impacto radiológico global, las dosis a la población en el trayecto y el posible detrimento de su salud. En España se prevé una larga “ruta radiactiva” de más de 2.000 kilómetros, por la que el combustible nuclear gastado se transportará presumiblemente por carretera desde las centrales nucleares hasta el ATC, así como los residuos vitrificados procedentes del reprocesado del combustible de la central nuclear Vandellos I, que en la actualidad están en Francia. Como conclusión más importante, se observa que la emisión de radiaciones ionizantes procedentes del transporte de residuos radiactivos de alta actividad en España, en operación normal, no es significativa a la hora de generar efectos adversos en la salud humana y su impacto radiológico puede considerarse despreciable. En caso de accidente, aunque la posibilidad del suceso es remota, las emisiones, no serán determinantes a la hora de generar efectos adversos en la salud humana. Issues related to the transport of high level radioactive wastes (HLW) to the new centralised temporary storage facility to be built in Villar de Cañas (Cuenca) are attracting renewed attention due to the mobility expected in the near future for these materials, the commitment to the environment, the protection of persons and the legal regulatory standards. This study assesses the radiological impacts associated with this type of transport by means of a new dataprocessing tool, which may be of use and serve as documentation complementary to that included in the legal framework covering transport. Furthermore, it may facilitate analysis from a more scientific perspective for researchers, public servants and technicians in general, who may use the tool to simulate different radioactive transport scenarios based only on input materials data and the routes selected. Thus, by knowing the radiation level at a distance of one metre from the transport and selecting a route, it is possible to obtain the associated impacts, such as the affected populations, the dose received by the most exposed individual, the overall radiological impact and the doses to the public en route and the possible detriment to their health. In Spain a long “radioactive route” of more than 2,000 kilometres is expected, along which spent nuclear fuels will be transported – foreseeably by road – from the nuclear power plants to the CTS facility. The route will also be used for the vitrified wastes from fuel reprocessing of the fuel from Vandellós I nuclear power plant, which are currently in France. In conclusion, it may be observed that the emission of ionising radiations from transport of high level radioactive wastes in Spain is insignificant, in normal operations, as regards the generation of adverse effects for human health, and that the radiological impact may be considered negligible. In the event of an accident, the possibility of which is remote, the emissions will not be also a very determining factor as regards adverse effects for human health.

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We are investigating the performances of a data acquisition system for Time of Flight PET, based on LYSO crystal slabs and 64 channels Silicon Photomultipliers matrices (1.2 cm2 of active area each). Measurements have been performed to test the timing capability of the detection system (SiPM matices coupled to a LYSO slab and the read-out electronics) with both test signal and radioactive source.

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To provide public and private actors at local, regional, national and European levels with methodologies to: – Create the conditions for them to gradually appropriate the problematic of long term rehabilitation following a situation of long‐lasting radioactive contamination; – Develop in their context appropriate means and tools for rehabilitation strategies; – Foster innovation and experimentation at territorial and national levels.

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A Steam Generator Tube Rupture (SGTR) in a Pressurized Water Reactor (PWR) can lead to an atmospheric release bypassing the containment via the secondary system and exiting though the Pressurized Operating Relief Valves of the affected Steam Generator. That is why SGTR historically have been treated in a special way in the different Deterministic Safety Analysis (DSA), focusing on the radioactive release more than the possibility of core damage, as it is done in the other Loss of Coolant Accidents(LOCAs).