956 resultados para Exelon Braidwood Nuclear Facility (Will County, Ill.)


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El futuro de la energía nuclear de fisión dependerá, entre otros factores, de la capacidad que las nuevas tecnologías demuestren para solventar los principales retos a largo plazo que se plantean. Los principales retos se pueden resumir en los siguientes aspectos: la capacidad de proporcionar una solución final, segura y fiable a los residuos radiactivos; así como dar solución a la limitación de recursos naturales necesarios para alimentar los reactores nucleares; y por último, una mejora robusta en la seguridad de las centrales que en definitiva evite cualquier daño potencial tanto en la población como en el medio ambiente como consecuencia de cualquier escenario imaginable o más allá de lo imaginable. Siguiendo estas motivaciones, la Generación IV de reactores nucleares surge con el compromiso de proporcionar electricidad de forma sostenible, segura, económica y evitando la proliferación de material fisible. Entre los sistemas conceptuales que se consideran para la Gen IV, los reactores rápidos destacan por su capacidad potencial de transmutar actínidos a la vez que permiten una utilización óptima de los recursos naturales. Entre los refrigerantes que se plantean, el sodio parece una de las soluciones más prometedoras. Como consecuencia, esta tesis surgió dentro del marco del proyecto europeo CP-ESFR con el principal objetivo de evaluar la física de núcleo y seguridad de los reactores rápidos refrigerados por sodio, al tiempo que se desarrollaron herramientas apropiadas para dichos análisis. Efectivamente, en una primera parte de la tesis, se abarca el estudio de la física del núcleo de un reactor rápido representativo, incluyendo el análisis detallado de la capacidad de transmutar actínidos minoritarios. Como resultado de dichos análisis, se publicó un artículo en la revista Annals of Nuclear Energy [96]. Por otra parte, a través de un análisis de un hipotético escenario nuclear español, se evalúo la disponibilidad de recursos naturales necesarios en el caso particular de España para alimentar una flota específica de reactores rápidos, siguiendo varios escenarios de demanda, y teniendo en cuenta la capacidad de reproducción de plutonio que tienen estos sistemas. Como resultado de este trabajo también surgió una publicación en otra revista científica de prestigio internacional como es Energy Conversion and Management [97]. Con objeto de realizar esos y otros análisis, se desarrollaron diversos modelos del núcleo del ESFR siguiendo varias configuraciones, y para diferentes códigos. Por otro lado, con objeto de poder realizar análisis de seguridad de reactores rápidos, son necesarias herramientas multidimensionales de alta fidelidad específicas para reactores rápidos. Dichas herramientas deben integrar fenómenos relacionados con la neutrónica y con la termo-hidráulica, entre otros, mediante una aproximación multi-física. Siguiendo este objetivo, se evalúo el código de difusión neutrónica ANDES para su aplicación a reactores rápidos. ANDES es un código de resolución nodal que se encuentra implementado dentro del sistema COBAYA3 y está basado en el método ACMFD. Por lo tanto, el método ACMFD fue sometido a una revisión en profundidad para evaluar su aptitud para la aplicación a reactores rápidos. Durante ese proceso, se identificaron determinadas limitaciones que se discutirán a lo largo de este trabajo, junto con los desarrollos que se han elaborado e implementado para la resolución de dichas dificultades. Por otra parte, se desarrolló satisfactoriamente el acomplamiento del código neutrónico ANDES con un código termo-hidráulico de subcanales llamado SUBCHANFLOW, desarrollado recientemente en el KIT. Como conclusión de esta parte, todos los desarrollos implementados son evaluados y verificados. En paralelo con esos desarrollos, se calcularon para el núcleo del ESFR las secciones eficaces en multigrupos homogeneizadas a nivel nodal, así como otros parámetros neutrónicos, mediante los códigos ERANOS, primero, y SERPENT, después. Dichos parámetros se utilizaron más adelante para realizar cálculos estacionarios con ANDES. Además, como consecuencia de la contribución de la UPM al paquete de seguridad del proyecto CP-ESFR, se calcularon mediante el código SERPENT los parámetros de cinética puntual que se necesitan introducir en los típicos códigos termo-hidráulicos de planta, para estudios de seguridad. En concreto, dichos parámetros sirvieron para el análisis del impacto que tienen los actínidos minoritarios en el comportamiento de transitorios. Concluyendo, la tesis presenta una aproximación sistemática y multidisciplinar aplicada al análisis de seguridad y comportamiento neutrónico de los reactores rápidos de sodio de la Gen-IV, usando herramientas de cálculo existentes y recién desarrolladas ad' hoc para tal aplicación. Se ha empleado una cantidad importante de tiempo en identificar limitaciones de los métodos nodales analíticos en su aplicación en multigrupos a reactores rápidos, y se proponen interesantes soluciones para abordarlas. ABSTRACT The future of nuclear reactors will depend, among other aspects, on the capability to solve the long-term challenges linked to this technology. These are the capability to provide a definite, safe and reliable solution to the nuclear wastes; the limitation of natural resources, needed to fuel the reactors; and last but not least, the improved safety, which would avoid any potential damage on the public and or environment as a consequence of any imaginable and beyond imaginable circumstance. Following these motivations, the IV Generation of nuclear reactors arises, with the aim to provide sustainable, safe, economic and proliferationresistant electricity. Among the systems considered for the Gen IV, fast reactors have a representative role thanks to their potential capacity to transmute actinides together with the optimal usage of natural resources, being the sodium fast reactors the most promising concept. As a consequence, this thesis was born in the framework of the CP-ESFR project with the generic aim of evaluating the core physics and safety of sodium fast reactors, as well as the development of the approppriated tools to perform such analyses. Indeed, in a first part of this thesis work, the main core physics of the representative sodium fast reactor are assessed, including a detailed analysis of the capability to transmute minor actinides. A part of the results obtained have been published in Annals of Nuclear Energy [96]. Moreover, by means of the analysis of a hypothetical Spanish nuclear scenario, the availability of natural resources required to deploy an specific fleet of fast reactor is assessed, taking into account the breeding properties of such systems. This work also led to a publication in Energy Conversion and Management [97]. In order to perform those and other analyses, several models of the ESFR core were created for different codes. On the other hand, in order to perform safety studies of sodium fast reactors, high fidelity multidimensional analysis tools for sodium fast reactors are required. Such tools should integrate neutronic and thermal-hydraulic phenomena in a multi-physics approach. Following this motivation, the neutron diffusion code ANDES is assessed for sodium fast reactor applications. ANDES is the nodal solver implemented inside the multigroup pin-by-pin diffusion COBAYA3 code, and is based on the analytical method ACMFD. Thus, the ACMFD was verified for SFR applications and while doing so, some limitations were encountered, which are discussed through this work. In order to solve those, some new developments are proposed and implemented in ANDES. Moreover, the code was satisfactorily coupled with the thermal-hydraulic code SUBCHANFLOW, recently developed at KIT. Finally, the different implementations are verified. In addition to those developments, the node homogenized multigroup cross sections and other neutron parameters were obtained for the ESFR core using ERANOS and SERPENT codes, and employed afterwards by ANDES to perform steady state calculations. Moreover, as a result of the UPM contribution to the safety package of the CP-ESFR project, the point kinetic parameters required by the typical plant thermal-hydraulic codes were computed for the ESFR core using SERPENT, which final aim was the assessment of the impact of minor actinides in transient behaviour. All in all, the thesis provides a systematic and multi-purpose approach applied to the assessment of safety and performance parameters of Generation-IV SFR, using existing and newly developed analytical tools. An important amount of time was employed in identifying the limitations that the analytical nodal diffusion methods present when applied to fast reactors following a multigroup approach, and interesting solutions are proposed in order to overcome them.

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This paper focuses on the possible instruments for ‘ex-ante’/’preventive’/’precautionary’ interventions which can be deployed by the ESM and the ECB in order to prevent a debt crisis in a eurozone country. The potential of Eurobonds will also be discussed in this crisis management perspective. The first part of this paper traces the underlying trends of the evolution of interest rates in eurozone countries over the last decades. The second part discusses the principles of a preventive intervention in sovereign bond markets for the purpose of lowering borrowing costs of countries facing refinancing constraints; the limits and main issues of an ex-ante intervention will be underlined. In the third part, the properties of the ESM’s precautionary financial assistance and secondary market support facility will be discussed in details. The ECB preemptive intervention policies and, in particular, the OMT will be analyzed in the fourth part of the paper. The most likely course of action – a combined intervention by the ESM and the ECB – will be discussed in the fifth part. Finally, I will point out the core challenges of introducing Eurobonds as additional instruments to mitigate the rise of borrowing costs in the short term.

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Germany’s decision to give up the use of nuclear energy will force it to find a conventional low-carbon energy source as a replacement; in the short term, in addition to coal, this is likely to be gas. Due to their continued high debt and the losses associated with the end of atomic power, German companies will not be able to spend large funds on investing in conventional energy. First of all, they will aim to raise capital and repay their debts. The money for this will come from selling off their less profitable assets; this will include sales on the gas market. This will create opportunities for natural gas exporters and extraction companies such as Gazprom to buy back some of the German companies’ assets (electricity companies, for example). The German companies will probably continue to seek to recover the costs incurred in the investment projects already underway, such as Nord Stream, the importance of which will grow after Russian gas imports increase. At the same time, because of their debts, the German companies will seek to minimise their investment costs by selling some shares on the conventional energy market, to Russian corporations among others; the latter would thus be able to increase their stake in the gas market in both Western (Germany, Great Britain, the Benelux countries) and Central Europe (Poland, the Czech Republic). It is possible that while establishing the details of cooperation between the Russian and German companies, Russia will try to put pressure on Germany to give up competing projects such as Nabucco. However, a well-diversified German energy market should be able to defend itself against attempts to increase German dependence on Russian gas supplies and the dictates of high prices.

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This paper analyses empirically how increasingly close trade relations between China and Russia might affect the European Union (EU). We show that EU countries are complementary to Russia on the Chinese market. However, Chinese exports are increasingly relevant substitutes for EU exports on the Russian market. This means that an increase in China-Russia economic cooperation should have a negative impact on European exports. We simulate a scenario in which trade tariffs between Russia and China are eliminated, which is found to reduce EU exports to Russia. Finally, a more granular approach to the question analyses which sectors in Europe will be more affected by the increasing economic links between China and Russia, and finds that electronic machinery, equipment and machinery, and nuclear reactors will be particularly affected. Such findings obviously show quickly China is moving up the ladder in terms of export structure and how strategically important it is for Europe to continue upgrading its industry to compete at the highest level of that ladder.

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Cover-title: Illinois canal scrip fraud.

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None published 1872/73-1873/74.

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House Resolution (HR) 1010 adopted June 2004, encourages the Illinois EPA to establish a Right-to-Know Committee and to obtain citizens' input on the most effective and efficient means of providing notice to residents exposed to or potentially exposed to contamination from air, land or water. In keeping with the spirit of the resolution, Illinois EPA is conducting this pilot notification project with the assistance of the Illinois Department of Public Health and the Cook County Department of Public Health. This notice is precautionary, because of the potential for one or more sites to affect the groundwater quality in the area. There are many sites in the area that may have a potential for contaminating groundwater. The current notification has to do with information Illinois EPA has gathered in the course of investigating, monitoring and performing work on the landfill sites discussed below. These are located in the Chicago Heights/South Chicago Heights area, south of 26th Street and west of State Street (see attached map): Chicago Heights Refuse Depot, Triem Landfill and Fitzmar Landfill. A fourth landfill, Lobue, is adjacent to these, although Illinois EPA currently has very little information about that landfill. In 1987, vinyl chloride was detected in South Chicago Heights Well #3 at a level that was more than the Class I Groundwater Standard, which is 2 parts per billion. Investigation and sampling of monitoring wells at the landfill site near Well #3 showed higher concentrations of vinyl chloride (140-240 parts per million) in 1988. South Chicago Heights discontinued the use of Well #3 after this event and later stopped using all its wells and began purchasing water from Chicago Heights in 2000.

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Areas of concern: This notification is based on information Illinois EPA has found while investigating, monitoring and working on two landfill sites in the Chicago Heights/South Chicago Heights area. Tests from groundwater and surface water at one landfill site showed levels of vinyl chloride greater than state Class I groundwater standards - the state standards that are designed to protect groundwater for use as drinking water. Vinyl chloride is from a family of chemicals known as volatile organic compounds (VOCs), which are common man-made chemicals found in cleaning solvents, gasoline and oil. These chemicals can travel in groundwater long distances from where they were spilled or dumped.

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Since 1974, several reports have recommended modification to Busse Woods Reservoir's principal spillway to provide additional flood protection downstream. Consequently, DuPage County (Ill.) constructed several flood control structures as part of its Lower Salt Creek Watershed Plan, making modification of the Busse Woods Dam the last component of the plan to be implemented.

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Includes an annoucement that the Illinois Dept. of Transportation, in cooperation with the Illinois State Toll Highway Authority, will be performing additional studies in support of the extension of I-355 through Will County, Illinois.

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Photocopy of: Chicago : Cook County Department of Corrections Commission, 1965.