Prácticas en Asturias Manuscrito : grupos hulleros de las minas Mariana, Baltasara, Zurón : fábrica de luz eléctrica en Gijón : transporte de energía eléctrica en el puerto del Musel (Gijón)

Asturias es una del as regiones mineras más importante de nuestra Península.Además de figurar en primer término como proveedora de hulla, contiene también otras minas de sustancias metalíferas, entre las que pueden citarse las del Naranco (Oviedo)....

Education and Training of Future Nuclear Engineers Through the use of an Interactive Plant Simulator

The successful experience of the Jose Cabrera Nuclear Power Plant Interactive Graphical Simulator implementation in the Nuclear Engineering Department in the Universidad Polite´cnica de Madrid, for the Education and Training of nuclear engineers is shown in this paper. The paper starts with the objectives and the description of the Simulator Aula, and the methodology of work following the recommendations of the IAEA for the use of nuclear reactor simulators for education. The practices and material prepared for the students, as well as the operational and accident situations simulated are provided.

Desarrollo de códigos neutrónicos propios para la simulación del núcleo de reactores PWR

La simulación de la física del núcleo de los reactores nucleares por su complejidad requiere del uso de computadores y del software adecuado, y su evolución es ir hacía métodos y modelos de los llamados best-estimate, con el objeto de aumentar la disponibilidad de la central manteniendo los márgenes de seguridad. Para ello el Departamento de Ingeniería Nuclear (UPM), ha desarrollado el Sistema SEANAP en uso en varias centrales nucleares españolas, que realiza la simulación en 3D y con detalle de barrita combustible del quemado nominal y real del núcleo del reactor, hace el seguimiento en línea de la operación, y ayuda a la planificación óptima de las maniobras operacionales

Interface discontinuity factors in the modal eigenspace of the multigroup diffusion matrix

Interface discontinuity factors based on the Generalized Equivalence Theory are commonly used in nodal homogenized diffusion calculations so that diffusion average values approximate heterogeneous higher order solutions. In this paper, an additional form of interface correction factors is presented in the frame of the Analytic Coarse Mesh Finite Difference Method (ACMFD), based on a correction of the modal fluxes instead of the physical fluxes. In the ACMFD formulation, implemented in COBAYA3 code, the coupled multigroup diffusion equations inside a homogenized region are reduced to a set of uncoupled modal equations through diagonalization of the multigroup diffusion matrix. Then, physical fluxes are transformed into modal fluxes in the eigenspace of the diffusion matrix. It is possible to introduce interface flux discontinuity jumps as the difference of heterogeneous and homogeneous modal fluxes instead of introducing interface discontinuity factors as the ratio of heterogeneous and homogeneous physical fluxes. The formulation in the modal space has been implemented in COBAYA3 code and assessed by comparison with solutions using classical interface discontinuity factors in the physical space

Interactive Graphic Simulation: An Advanced Methodology to Improve the Teaching-Learning Process in Nuclear Engineering Education and Training

Nowadays, computer simulators are becoming basic tools for education and training in many engineering fields. In the nuclear industry, the role of simulation for training of operators of nuclear power plants is also recognized of the utmost relevance. As an example, the International Atomic Energy Agency sponsors the development of nuclear reactor simulators for education, and arranges the supply of such simulation programs. Aware of this, in 2008 Gas Natural Fenosa, a Spanish gas and electric utility that owns and operate nuclear power plants and promotes university education in the nuclear technology field, provided the Department of Nuclear Engineering of Universidad Politécnica de Madrid with the Interactive Graphic Simulator (IGS) of “José Cabrera” (Zorita) nuclear power plant, an industrial facility whose commercial operation ceased definitively in April 2006. It is a state-of-the-art full-scope real-time simulator that was used for training and qualification of the operators of the plant control room, as well as to understand and analyses the plant dynamics, and to develop, qualify and validate its emergency operating procedures.

Formación y entrenamiento de ingenieros nucleares mediante el máster de Ciencia y Tecnología nuclear de la UPM

El Departamento de Ingeniería Nuclear imparte los Programas oficiales de Máster y Doctorado en Ciencia y Tecnología Nuclear, que cuentan desde el año 2006 con la Mención de Calidad del Ministerio de Educación y desde este curso 2010-2011con la Mención a la Excelencia. El contenido del Máster abarca desde la tecnología nuclear de los reactores de fisión hasta el estudio de los combustibles y materiales para los futuros reactores de fusión tanto inercial como magnética.

Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmark databases

The need to refine models for best-estimate calculations, based on good-quality experimental data, has been expressed in many recent meetings in the field of nuclear applications. The modeling needs arising in this respect should not be limited to the currently available macroscopic methods but should be extended to next-generation analysis techniques that focus on more microscopic processes. One of the most valuable databases identified for the thermalhydraulics modeling was developed by the Nuclear Power Engineering Corporation (NUPEC), Japan. From 1987 to 1995, NUPEC performed steady-state and transient critical power and departure from nucleate boiling (DNB) test series based on the equivalent full-size mock-ups. Considering the reliability not only of the measured data, but also other relevant parameters such as the system pressure, inlet sub-cooling and rod surface temperature, these test series supplied the first substantial database for the development of truly mechanistic and consistent models for boiling transition and critical heat flux. Over the last few years the Pennsylvania State University (PSU) under the sponsorship of the U.S. Nuclear Regulatory Commission (NRC) has prepared, organized, conducted and summarized the OECD/NRC Full-size Fine-mesh Bundle Tests (BFBT) Benchmark. The international benchmark activities have been conducted in cooperation with the Nuclear Energy Agency/Organization for Economic Co-operation and Development (NEA/OECD) and Japan Nuclear Energy Safety (JNES) organization, Japan. Consequently, the JNES has made available the Boiling Water Reactor (BWR) NUPEC database for the purposes of the benchmark. Based on the success of the OECD/NRC BFBT benchmark the JNES has decided to release also the data based on the NUPEC Pressurized Water Reactor (PWR) subchannel and bundle tests for another follow-up international benchmark entitled OECD/NRC PWR Subchannel and Bundle Tests (PSBT) benchmark. This paper presents an application of the joint Penn State University/Technical University of Madrid (UPM) version of the well-known subchannel code COBRA-TF, namely CTF, to the critical power and departure from nucleate boiling (DNB) exercises of the OECD/NRC BFBT and PSBT benchmarks

The Key Role Transferring Knowledge of Nuclear España, The Spanish Nuclear Society Magazine

The magazine of the Spanish Nuclear Society (SNE), “Nuclear España” is a scientific-technical publication with almost thirty years of uninterrupted edition and more than 300 numbers published. Their pages approach technical subjects related to the nuclear energy, as well as the activities developed by the SNE, especially in national and international meetings. The main part of the magazine is composed by articles written by known specialist of the energy industry. One of the top goals of the magazine is to help on transferring the knowledge from the generation that built the nuclear power plants in Spain and the new generation of professionals that have started its nuclear career in the last years. Each number is monographic, trying to cover as many aspects on an issue as it is possible, with collaborations from the companies, the research centers and universities that helps to have complementary points of view. On the other hand the articles help to deep in the issue´s topic, broadening the view of the readers about the nuclear field and helping to share knowledge across the industry. The news section of the Magazine picks up the actuality of the sector as a whole. The editorial section reflects the opinion of the SNE Governing Board and the Magazine Committee on the subjects of interest in this field. On the other hand, the monthly interview sets out the professional outstanding opinions. With a total of eleven numbers per year, three of them have a noticeable international character: the one dedicated to the operative experiences on the Spanish and European nuclear power plants, the monographic issue devoted tothe Annual Meeting of the SNE and the international issue, which covers the last activities of the Spanish industry in international projects. Both first are bilingual issues (Spanish-English), whereas the international edition is published completely in English. Besides its diffusion through all the members of the SNE, the Magazine is distributed, in the national scope, to companies and organisms related to the nuclear power, universities, research centers, representatives of the Central, Autonomic and Local Administrations, mass media and communication professionals. It is also sent to the utilities and research centers in Europe, United States, South America and Asia.

Red GNSS de InlandGEO en la Comunidad de Madrid: Aplicaciones en Tiempo Real

Se exponen aquí los desarrollos llevados a cabo para instalar y hacer operativa una red de Estaciones Permanentes GNSS, en la Comunidad de Madrid, con el fin de generalizar la disponibilidad pública, en todo el ámbito geográfico de la CAM, de las correcciones diferenciales de GNSS, contribuir a la densificación del Marco de Referencia ETRS89, y disponer de una Red GPS de altas prestaciones (GPS, GLONASS y la paulatina entrada GALILEO) con una idónea geometría, para proyectos de investigación en el marco de la CAM, tanto en Postproceso como en Tiempo Real. Se comentan aquí los pasos realizados para su instalación y entrada en operación, el cálculo preciso de sus coordenadas con el software BERNESE, análisis de precisiones y el desarrollo de un test de calidad a fin de comprobación las soluciones que da la red en tiempo real, comprobación de las soluciones en postproceso y comprobación del alcance de precisión del sistema. Crear un entorno de precisión sobre nuevas aplicaciones de Redes GPS de TOPCON en Agricultura de Precisión, Control de Maquinaria y posicionamiento de equipos topográficos para empresas, organismos y particulares de la CAM.

Desarrollos para la explotación de datos integrados mediante fotogrametría y láser escáner en proyectos de patrimonio arquitectónico

La presente tesis doctoral describe los desarrollos realizados, y finalmente materializados en patentes con registro de la propiedad intelectual, para la integración de las nuevas tecnologías de documentación fotogramétrica y las bases de datos de los barredores láser terrestres, en los procesos de elaboración, redacción y ejecución de proyectos de restauración y rehabilitación arquitectónicos. Los avances tecnológicos aparecidos en control métrico, junto con las técnicas de imagen digital y los desarrollos fotogramétricos, pueden aportar mejoras significativas en el proceso proyectual y permiten aplicar nuevos procedimientos de extracción de datos para generar de forma sencilla, bajo el control directo y supervisión de los responsables del proyecto, la información métrica y documental más adecuada. Se establecen como principios, y por tanto como base para el diseño de dicha herramienta, que los desarrollos aparecidos sí han producido el uso extendido del sistema CAD (como instrumento de dibujo) así como el uso de la imagen digital como herramienta de documentación. La herramienta a diseñar se fundamenta por tanto en la imagen digital (imágenes digitales, imágenes rectificadas, ortofotografías, estéreo- modelos, estereo- ortofotografías) así como su integración en autocad para un tratamiento interactivo. En la aplicación de la fotogrametría a la disciplina arquitectónica, se considera de interés estructurar aplicaciones con carácter integrador que, con mayores capacidades de interactuación y a partir de información veraz y rigurosa, permitan completar o elaborar documentos de interés proyectual, ABSTRACT This doctoral thesis explains the developments carried out, and finally patented with intellectual property rights, for the integration of the new photogrammetric technology documentation and terrestrial scanner databases in the preparation, documentation and implementation processes of restoration projects and architectural renovation. The technological advances in metric control, as well as the digital image techniques and photogrammetric developments, can together bring a significant improvement to the projecting process, and, under the direct control and supervision of those in charge of the project, can allow new data extraction processes to be applied in order to easily generate the most appropriate metric information and documentation. The principles and, therefore, the basis for the design of this tool are that the developments have indeed produced the widespread use of the CAD system (as a drawing instrument) and the use of digital images as a documentation tool. The tool to be designed is therefore based on digital images (rectify images, orthophotos, stereomodels, stereo-orthophotos) as well as its integration in Autocad for interactive processing. In the application of photogrammetry to the architectural discipline, what interests us is to structure applications of an integrative nature which, with a greater capacity for interaction and from accurate and thorough information, enable the completion or elaboration of documents that are of interest to the project.

Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR

Performing three-dimensional pin-by-pin full core calculations based on an improved solution of the multi-group diffusion equation is an affordable option nowadays to compute accurate local safety parameters for light water reactors. Since a transport approximation is solved, appropriate correction factors, such as interface discontinuity factors, are required to nearly reproduce the fully heterogeneous transport solution. Calculating exact pin-by-pin discontinuity factors requires the knowledge of the heterogeneous neutron flux distribution, which depends on the boundary conditions of the pin-cell as well as the local variables along the nuclear reactor operation. As a consequence, it is impractical to compute them for each possible configuration; however, inaccurate correction factors are one major source of error in core analysis when using multi-group diffusion theory. An alternative to generate accurate pin-by-pin interface discontinuity factors is to build a functional-fitting that allows incorporating the environment dependence in the computed values. This paper suggests a methodology to consider the neighborhood effect based on the Analytic Coarse-Mesh Finite Difference method for the multi-group diffusion equation. It has been applied to both definitions of interface discontinuity factors, the one based on the Generalized Equivalence Theory and the one based on Black-Box Homogenization, and for different few energy groups structures. Conclusions are drawn over the optimal functional-fitting and demonstrative results are obtained with the multi-group pin-by-pin diffusion code COBAYA3 for representative PWR configurations.

Detection and Isolation of Simultaneous Additive and Parametric Faults in Nonlinear Stochastic Dynamical Systems

This paper presents a new fault detection and isolation scheme for dealing with simultaneous additive and parametric faults. The new design integrates a system for additive fault detection based on Castillo and Zufiria, 2009 and a new parametric fault detection and isolation scheme inspired in Munz and Zufiria, 2008 . It is shown that the so far existing schemes do not behave correctly when both additive and parametric faults occur simultaneously; to solve the problem a new integrated scheme is proposed. Computer simulation results are presented to confirm the theoretical studies.

Boron dilution benchmark using COBAYA3/FLICA4 coupled codes within the NURISP European Project

Within the subproject 3 of the NURISP project three neutron kinetic codes have been implemented into the NURESIM platform. For all three codes (CRONOS2, COBAYA3 and DYN3D) the coupling with the thermal hydraulic code FLICA4 was accomplished using the features of the NURESIM platform. This paper contains the results obtained with COBAYA3/FLICA4 coupled codes for the PWR boron dilution benchmark defined within the sub project 3 of the NURISP project. Results are provided for all the scenarios.

Initiatives and facilities for E&T in the nuclear science and technology master at UPM

The present Master/Doctorate in Nuclear Science and Technology programme implemented in the Department of Nuclear Engineering of the Universidad Politécnica de Madrid (NED-UPM) has the excellence qualification by the Spanish Ministry of Education. One of the main of this programme is the training for the development of methodologies of simulation, design and advanced analysis, including experimental tools, necessary in research and in professional work in the nuclear field.

Análisis de un accidente de rotura de tubos de GV mediante la utilización del SGI de Zorita

En el año 2008 la Universidad Politécnica de Madrid y la empresa Gas Natural Fenosa firmaron un acuerdo por el que se creaba el Aula José Cabrera en el Departamento de Ingeniería Nuclear de la UPM. Dicho aula cuenta con el simulador gráfico interactivo de la central nuclear José Cabrera, que es un simulador de alcance total de una central nuclear PWR de un lazo. El objetivo de la ponencia es demostrar la gran aplicación didáctica que tiene dicho aula. El simulador es una herramienta de uso interactivo para trabajo individual o en grupo con los alumnos. Dentro de la asignatura de “Fiabilidad y Análisis del Riesgo” del Máster Ciencia y Tecnología Nuclear de la ETSII-UPM, se propuso la realización de un árbol de eventos para un accidente propuesto por los alumnos. El trabajo que se presenta en esta ponencia ha consistido en el análisis del accidente de rotura de tubos en el generador de vapor usando el simulador gráfico interactivo.