Desmantelamiento del experimento EB

Este proyecto consiste en la fase de desmantelamiento de un experimento que se ha ido desarrollando por la empresa AITEMIN en colaboración con multitud de empresas internacionales del ámbito de la eliminación de residuos radioactivos de alta actividad y se desarrolla en el laboratorio subterráneo de Mont Terri en Suiza. En el proyecto se describirán todas las partes del experimento y se procederá a establecer el procedimiento a utilizar para su desmantelamiento, explicando exhaustivamente los pasos a realizar por las personas responsables de la desmantelamiento. ABSTRACT This project involves the dismantling phase of an experiment that has been developed by the company AITEMIN in collaboration with many international companies in the field of radioactive waste disposal and develops high activity in the Mont Terri underground laboratory in Switzerland. The project will describe all parts of the experiment and proceed to establish the procedure to be used for dismantling, thoroughly explaining the steps to be performed by the persons responsible for the dismantling

Motivating Young Students to Start a Career in Nuclear: The Basic Course of Science and Nuclear Technology, An Educational Activity of Spanish Young Generation in Nuclear (JÓVENES NUCLEARES)

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

Introducing Nuclear Energy to High-School Students: The Spanish Young Generation in Nuclear (Jóvenes Nucleares) Lectures

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

Análisis del comportamiento a corrosión de armaduras embebidas en probetas de mortero, con sustitución parcial de áridos y cemento por escorias blancas de horno cuchara

El hormigón armado es el material estructural más empleado en construcción, lo que exige un exhaustivo control tanto de los materiales que lo componen como de su ejecución, con el fin de garantizar la vida útil para la que ha sido proyectado. Uno de los principales problemas de la durabilidad del hormigón armado, es la corrosión de sus armaduras. Existen en la actualidad diferentes métodos que intentan detener el proceso de corrosión, entre ellos, los inhibidores superficiales de corrosión. El continuo incremento en la producción de acero desde el siglo XIX, ha producido un desequilibrio entre los productos fabricados en las industrias siderúrgicas y los residuos generados. Como consecuencia, toneladas de residuos son depositados en vertederos, provocando graves daños medioambientales con el paso del tiempo. El volumen de escorias producidas en la industria siderúrgica en España asciende a 2,55Mt al año, de ahí la importancia del reciclaje de estos productos y de su integración como materia prima en el proceso de fabricación de otros materiales. Partiendo de estas premisas, en el presente trabajo de investigación se ha estudiado el comportamiento a corrosión, de barras de acero de armar embebidas en probetas de mortero, en las que se ha sustituido parcialmente el árido y el cemento por escorias blancas de horno cuchara (LFS), mediante técnicas electroquímicas y gravimétricas. Para ello, se han fabricado probetas prismáticas de 6 x 8 x 2 cm3 con diferentes porcentajes de ión cloruro, introducidos en el momento del amasado, tanto en probetas patrón como en probetas con escorias LFS. El análisis de los resultados obtenidos permite concluir que las probetas patrón y las probetas con escorias LFS tienen comportamientos similares en presencia de cloruros por encima del 0,4% en peso de cemento y por tanto que la sustitución de escorias LFS por arena (25%) y cemento (30%) no afecta negativamente a la corrosión de las armaduras. Por tanto, el uso de escorias LFS en el proceso de fabricación de hormigón armado es una práctica que presenta ventajas competitivas respecto a las técnicas de construcción tradicionales, desde el punto de vista económico y medioambiental. En cuanto a los inhibidores superficiales de corrosión, no han resultado eficaces en probetas con escorias LFS, independientemente del porcentaje de ión cloruro, mientras que en probetas patrón han sido eficaces para porcentajes de ión cloruro igual o inferior al 0,8% en peso de cemento. ABSTRACT Reinforced concrete is the most widely used structural material. This implies that rigorous control must be applied in order to guarantee the life-span and performance of structures made using this composite material. One of the main problems regarding concrete durability is bar corrosion. At present, there are different methods adopted to stop the corrosion process, among them, surface corrosion inhibitors. The continuous growth in steel production since the 19th century has led to an imbalance between waste products generated in steel production processes and their subsequent use. As a consequence, mass dumping at waste disposal sites has been causing a significant environmental problem over the years. The amount of slag produced by the steel industry each year in Spain amounts to 2.55Mt, hence the importance of recycling by-products from steel production so they can be used as primary material in the manufacturing process of other materials. Starting from this working hypothesis, and using electrochemical and gravimetric techniques, this research work aims to analyse and study the corrosion behaviour of steel rebars embedded in mortar specimens, containing ladle furnace slag in partial substitution for aggregate and cement. Prisms were manufactured from 6 x 8 x 2 cm3 with different percentages of chloride ion introduced at the time of mixing, in standard specimens and specimens with LFS slag. Results from the analysis show that the standard specimens and those containing LFS slag display a similar behaviour in the presence of chlorides. Furthermore, when LFS slag is replaced by sand (25%) and cement (30%) corrosion of rebars is not negatively affected. Additionally, the use of LFS slag in the manufacture of reinforced structures is a practice that represents a competitive advantage over traditional construction techniques, from both an economic and environmental point of view Finally, as for surface corrosion inhibitors, they have not proved effective in specimens containing LFS slag, regardless of the percentage of the chloride ion, whereas in standard specimens they have been effective in chloride ion percentages not exceeding 0.8% (as to the cement amount).

Limiting properties in the characterisation of mixed recycled aggregates for use in the manufacture of concrete

El objetivo principal de este trabajo de investigación es estudiar las propiedades del árido reciclado mixto para la fabricación de hormigón reciclado en aplicaciones no estructurales. Se ha realizado la caracterización completa de 35 muestras de áridos reciclados mixtos gruesos de distinta calidad, procedentes de 13 plantas de tratamiento diferentes de la geografía española. Se han estudiado las correlaciones que existen entre las diferentes propiedades, en particular, con la absorción de agua, el contenido de sulfatos y la composición. Se propone una clasificación de los áridos reciclados y se limita de forma indicativa el contenido de yeso para que una muestra de árido reciclado mixto cumpla con la limitación del 0,8% de los sulfatos solubles en ácido de la Instrucción EHE-08. Recycling of construction and demolition waste (CDW) has become a widespread concern in Spain for the last years, as a way to preserve natural resources and achieve a better control of waste disposal sites.Specific applications which make use of mixed recycled aggregates are of great importance, as this types of aggregates constitute the majority of the total production. Structural and non-structural concrete is one of the possible applications, being this the main goal of our study. This paper presents a study on the physical and chemical characteristics of mixed recycled aggregates which have been obtained from different CDW treatment plants of Spain. Correlations between the different properties were investigated in order to find criterions of acceptance for recycled aggregates to be used in concrete. The comparison between the properties offers the possibility of pre-selecting a great quantity of mixed recycled aggregates, these being suitable for either structural and non-structural concrete. The determination of water absorption and the gypsum content are good indicators in order to evaluate the quality of the mixed recycled aggregates for its application in the production of concrete.

Analysis of a Spanish energy scenario with Generation IV nuclear reactors

The advantages of fast-spectrum reactors consist not only of an efficient use of fuel through the breeding of fissile material and the use of natural or depleted uranium, but also of the potential reduction of the amount of actinides such as americium and neptunium contained in the irradiated fuel. The first aspect means a guaranteed future nuclear fuel supply. The second fact is key for high-level radioactive waste management, because these elements are the main responsible for the radioactivity of the irradiated fuel in the long term. The present study aims to analyze the hypothetical deployment of a Gen-IV Sodium Fast Reactor (SFR) fleet in Spain. A nuclear fleet of fast reactors would enable a fuel cycle strategy different than the open cycle, currently adopted by most of the countries with nuclear power. A transition from the current Gen-II to Gen-IV fleet is envisaged through an intermediate deployment of Gen-III reactors. Fuel reprocessing from the Gen-II and Gen-III Light Water Reactors (LWR) has been considered. In the so-called advanced fuel cycle, the reprocessed fuel used to produce energy will breed new fissile fuel and transmute minor actinides at the same time. A reference case scenario has been postulated and further sensitivity studies have been performed to analyze the impact of the different parameters on the required reactor fleet. The potential capability of Spain to supply the required fleet for the reference scenario using national resources has been verified. Finally, some consequences on irradiated final fuel inventory are assessed. Calculations are performed with the Monte Carlo transport-coupled depletion code SERPENT together with post-processing tools.

Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking

The new reactor concepts proposed in the Generation IV International Forum (GIF) are conceived to improve the use of natural resources, reduce the amount of high-level radioactive waste and excel in their reliability and safe operation. Among these novel designs sodium fast reactors (SFRs) stand out due to their technological feasibility as demonstrated in several countries during the last decades. As part of the contribution of EURATOM to GIF the CP-ESFR is a collaborative project with the objective, among others, to perform extensive analysis on safety issues involving renewed SFR demonstrator designs. The verification of computational tools able to simulate the plant behaviour under postulated accidental conditions by code-to-code comparison was identified as a key point to ensure reactor safety. In this line, several organizations employed coupled neutronic and thermal-hydraulic system codes able to simulate complex and specific phenomena involving multi-physics studies adapted to this particular fast reactor technology. In the “Introduction” of this paper the framework of this study is discussed, the second section describes the envisaged plant design and the commonly agreed upon modelling guidelines. The third section presents a comparative analysis of the calculations performed by each organisation applying their models and codes to a common agreed transient with the objective to harmonize the models as well as validating the implementation of all relevant physical phenomena in the different system codes.