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En el presente Trabajo Fin de Máster se desarrolla el concepto de una nueva cadena de valor de las redes eléctricas inteligentes en el País Vasco para la Asociación Cluster de Energía. Dentro de este proyecto, se tiene en cuenta la integración de las Smart Grids en el sistema hasta la fecha, analizando tanto la arquitectura de dicha tecnología como el avance del sector en Euskadi. Además, se proponen medidas para actualizar el catálogo de Smart Grids de ACE. Estas actuaciones tienen como finalidad la actualización de la información existente en este segmento de mercado, con el objetivo de poder ofrecer un mejor servicio por parte del Cluster de Energía del País Vasco hacia las compañías y organismos asociados. De esta manera, se pretende impulsar al sector de bienes y equipos eléctricos del País Vasco en el ámbito de las nuevas actividades digitales. El presente Trabajo Fin de Máster contribuye a los Objetivos de Desarrollo Sostenible de Agenda 2030 promulgada por la Organización de las Naciones Unidas (ONU). Concretamente, el TFM pretende realizar una aportación a los ODS 7: “Energía asequible y no contaminante”, ODS 8: “Trabajo decente, y crecimiento económico”, ODS 9: “Industria, innovación e infraestructura”, ODS 11: “Ciudades y comunidades sostenibles”, ODS 12: “Producción y consumo responsable” y ODS 17: “Alianzas para los objetivos”.

Whether a nuclear installation has radiological impact and, in that case, its extension, are the questions behind any environmental analysis of the installation along its operational life. This analysis is based on the detailed establishment of the radiological background of the area. Accordingly, the dismantling and decommissioning process (D&D) of a nuclear power plant starts with a radiological monitoring plan, which includes the radiological characterization of the area and of its surroundings. At the completion of the D&D, unrestricted use for the site will be permitted strictly in accordance with results of the radiological survey within the limits established by the local authorities. Groundwater quality is typically included in any radiological analysis since, among other reasons, a significant part of it is highly likely to end up being extracted for domestic use and hence, human consumption. While there is no regulation containing maximum activity concentration or radionuclide guidance values for water that may be destined for uses other than public consumption, if groundwater is considered a “part” of the land, dose criteria for site release can be applied. Therefore, together with the guidance levels to be established for the different radionuclides expected in the groundwater, the detection limits to be employed when performing routine radio analytical characterization procedures in the laboratory should also be provided. In this paper, we first propose a relation of the potential radionuclides to be analyzed in groundwater, together with their detection limits to be achieved when the determinations are performed in a laboratory, and subsequently, we discuss the most suitable analytical methodologies and resources that would be necessary to undertake radiological characterization plans from a practical point of view.

El objeto del proyecto que se desarrolla a continuación es el diseño y dimensionamiento de una instalación fotovoltaica para una instalación industrial situada en la provincia de Álava. El objetivo principal será encontrar el diseño óptimo de los paneles fotovoltaicos, consiguiendo la mejor relación precio-producción para obtener un autoconsumo real. Previamente al comienzo del dimensionamiento de la instalación, se estudia la historia de la energía fotovoltaica y la actualidad de producción energética, tanto a nivel mundial como a nivel nacional. A su vez, se detallan los diferentes tipos de sistemas fotovoltaicos según sus propiedades y componentes y la normativa a seguir en cada uno de ellos. El proceso de diseño comienza con el estudio de la potencia solar recibida en la zona de la instalación. A continuación, se seleccionan los paneles y se estudia la energía que se puede generar con ellos. Seguidamente, se estudia el número de paneles necesarios y su posición en la cubierta de la instalación. Por último, se calcula el presupuesto de la instalación y la amortización de esta.

Today, the measurement of 14C in environmental samples is of particular interest, as it enables the assessment of the impact caused by nuclear activities and the fossil fuel industry on the environment. In order to assure the quality of 14C measurement results, the strategy to enlarge the validation of three radioanalytical methods in environmental samples using liquid scintillation spectrometry—the direct counting of water, bubbling of water and combustion of solids—is presented. Due certain difficulties, such as the lack of quality control materials and the scarcity of proficiency test and intercomparison exercises, especially in solid samples, a set of water and soil samples were prepared for the purpose by tracing them with known quantities of a 14C standard solution at two activity levels. Aliquots were subjected to the corresponding method and their activity concentration was calculated. Finally, uncertainty, detection limit, accuracy, precision, repeatability and linearity were analysed. The acceptance criteria for the quality parameters were previously established according to ISO 13528:2015 standard and Eurachem Laboratory Guide to Method Validation. In all the methods, the studied parameters fall within the acceptance range, so they are validated. The quality of the results in real samples is controlled through field validation.

Desde los años 40, el estudio de la radiactividad ha cobrado una mayor importancia en el mundo, debido a las distintas sucesiones que han ocurrido desde las bombas atómicas y los accidentes ocurridos en Chernóbil y en Fukushima. Estos acontecimientos han revelado la gran importancia del estudio y del control de la radiactividad ambiental, por ello se han creado programas de vigilancia ambiental donde se han determinado las técnicas y la cuantificación de los valores radiológicos. Ante esta situación y debido a la inminente preocupación por la sociedad ante el peligro de los valores radiológicos, surge el presente proyecto que consiste en el análisis temporal de los valores radiológicos ambientales del agua y de la dieta, datos procedentes de los Programas de Vigilancia Radiológica Ambiental (PVRA), de la Red de estaciones de muestreo (REM), que forma parte de la vigilancia nacional, desarrollada por el Consejo de Seguridad Nuclear. En estos programas se recogen muestras ambientales en campo, que son transportadas a laboratorios de universidades u otros organismos públicos o privados, especializados en medidas ambientales de baja actividad radiológica, donde se lleva a cabo su preparación y medida obteniéndose, después de un periodo de tiempo variable, los resultados de su actividad radiológica. El análisis muestra los resultados obtenidos por las distintas zonas de muestreo en España del número y la concentración de actividad de radioisótopos de origen natural y artificial en dichas zonas, así como su relación con las distintas cadenas de desintegración. El análisis permite observar la consecución de las exigencias en la normativa correspondiente y los valores de la dosis indicativa. Se analizan su evolución temporal y dependencias con el medio ambiente. Asimismo, se realiza una comparación con los valores obtenidos de la Radioactivity Environmental Monitoring data base (REMdb) en Europa.

Este proyecto se ha desarrollado con el fin de simular la transición hacia el modelo de transporte eléctrico de cero emisiones previsto para el año 2050. Una vez contextualizado el trabajo, se ha procedido a diseñar la infraestructura necesaria para la recarga del VE. Para ello se han tenido en cuenta varios parámetros propios del barrio, por lo que se ha diseñado teniendo en cuenta las necesidades para cada una de las etapas. Para finalizar, se ha analizado el presupuesto que implicaría este proyecto y el impacto que tendría en cuanto a la calidad del aire y los GEI.

In this work, two Tc radiochemical isolation methods—a conventional method by Triskem TEVA ® resin and a rapid method by Empore™ Tc Rad Disk—are compared in the field of nuclear decommissioning and 99Tc assessment. The conventional method results more selective than the rapid one, being able to remove almost 100% of the main radiological interferers with the exception of the 90Y; however, the rapid method obtains higher chemical yields (97% vs. 80%) and slightly lower detection limits (0.025 Bq vs. 0.030 Bq) than the conventional. Both methods are similar with regards to equipment and reagent costs.

The aim of this paper is to statistically characterize gross beta activity concentrations in ground-level air in Bilbao (northern Spain) by analysing five years (2014–2018) worth of weekly measurements in aerosols collected in filters to analyse the impact of local meteorological parameters on concentrations. In addition, synoptic meteorological scenarios associated with anomalous beta surface activity concentrations were identified. Over this five-year period, beta activity concentrations ranged from 35.45 µBq/m3 to 1778 µBq/m3 with a mean of 520.12 ± 281.77 µBq/m3. A positive correlation was found with the alpha concentrations (0.67), with an average of 0.138 for the alpha/beta ratio, and a low correlation was found with 7Be (0.16). Statistical analysis identified a seasonal component in the time series, increasing, on average, beta activity concentrations from winter to autumn. The highest beta activity concentrations were measured under the arrival of southerly land winds with low wind speeds, while the wind analysis (surface winds and air masses) of two different seasonal periods (autumn 2015 and winter 2017) have highlighted how small variations in synoptic and local winds highly influence beta activity concentrations. These results are relevant to understand the meteorological factors affecting beta activity concentrations in this area and hence to define meteorological scenarios that are in favour to high/anomalous surface activity concentrations that are harmful to the environmental and public health.

[EN] The investigation of radioactivity in samples is an application of gamma-ray spectrometry dealing with low and very low level gamma-ray activities of different isotopes. Gamma-ray spectrometry performed in the framework of radiological environmental monitoring may be done after selective sampling processes or after a chemical purification of a sample. Both cases imply that only some specific radionuclides should contribute to the obtained spectrum. Gamma-ray spectrometry performed with medium energy resolution detectors may allow the possible distinction of their photopeaks. Therefore, a cerium bromide (CeBr3) detector can be particularly attractive for routine tasks in radiological environmental monitoring as it has a high efficiency, medium energy resolution and it can work at room temperature. This study describes the conditions under which a CeBr3 detector can serve for some routine analysis in radiological analysis of samples collected in the environment or collected by air-samplers in environmental radiological monitoring programmes.

[EN]Determination of Pu-241 is an essential issue for radiation protection, as it is the precursor of some nuclides with high radiotoxicity. Pu-241 is a low energy beta emitter, which makes its measurement more challenging than that of Pu alpha emitters. The most widely used method for the measurement of Pu-241 is liquid scintillation counting (LSC). In this method, the assessment of Pu radiochemical yield is done by measuring the sample by alpha spectrometry before being lixiviated and measured by LSC. This double measurement affects uncertainty analysis, as well as decision threshold and detection limit, considering that both components of the total yield (radiochemical and lixiviation) should be contemplated. In this paper, and for quality assurance (QA) purposes, in-depth uncertainty and detection limit formulae for the proposed method, controlling correlations and considering all the parameters involved including chemical and lixiviation yields, have been developed. A sensitivity analysis of the uncertainty budget together with an assessment of Pu-242 tracer quantity to be used, ensuring a total yield of at least 50% and a relative uncertainty of the leaching yield of at most 5%, have been carried out. In addition, an analysis of the impact of the real lixiviation yield value and its uncertainty on the results has been done. As a general conclusion, and considering the values of the parameters chosen for this work (samples of 1 g measured for 24 h by LSC), the Pu-241 uncertainties range from 5% to 30% depending on the activity concentration values and the detection limits range from 14 to 30 Bq kg(-1), depending on yield values. The main components of the uncertainty budget are the net Pu-241 and background counts obtained in the LSC measurement for low contaminated samples while this is the case for the alpha gross count rate in LSC measurement of the alpha calibration source for highly contaminated samples. In addition, an analysis of possible interference by

191 p., En esta Tesis se desarrolla e implementa un procedimiento para la determinación conjunta de Fe-55 y Ni-63 en muestras medioambientales.También se desarrolla y propone un procedimiento general de validación para procedimientos radioanalíticos que posteriormente se aplicarán al procedimiento desarrollado permitiendo así su perceptiva validación previa a considerar como un método de rutina en el laboratorio.

[EN] In this paper, in-situ radiological characterisation by means of non-destructive techniques is studied and analysed in the context of the different constrained environments (identified as radioactivity, materials, accessibility and other hazards) that may be encountered in the nuclear facilities undergoing decommissioning and dismantling. As a complement to a previous paper (Aspe et al., 2020), the present one gives a global guidance to assist with the decision making process regarding the selection of in-situ measurement techniques that could be applied in such constrained environments. In addition, from the definition of the investigation objectives, and for each one of the most common in-situ measurement techniques, a brief description is given about the impact of the above constraints and how to integrate them onto the system definition, including the experimental design, the mechanical integration and the data management, to properly define the best radiological characterization methodology. Moreover, complementing this general view, all the phases – from initial to final – of a D&D programme were taken into account to provide basic recommendations, together with some particular dispositions, for the appropriate implementation of the chosen instruments. Strengths and weaknesses of the common detectors used for the different in-situ measurement techniques, as well as their recommended applications in nuclear facilities are also outlined.

[EN] Nearly all decommissioning and dismantling (D&D) projects are steered by the characterisation of the plant being dismantled. This radiological characterisation is a complex process that is updated and modified during the course of the D&D. One of the tools for carrying out this characterisation is the performance of in-situ measurements. There is a wide variety of equipment and methodologies used to carry out on-site measurements, depending on the environment in which they are to be carried out and also on the specific objectives of the measurements and the financial and personnel resources available. The extent to which measurements carried out with different types of equipment or methodologies providing comparable results can be crucial in view of the D&D strategy development and the decision-making process. This paper concerns an on-site benchmarking exercise carried out at the activated biological shield of Belgian Reactor 3 (BR3). This activity allows comparison and validation of characterisation methodologies and different equipment used as well as future interpretation of final results in terms of uncertainties and sensitivities. This paper describes the measurements and results from the analysis of this exercise. Other aspects of this exercise will be reported in separate papers. This paper provides an overview of the on-site benchmarking exercise, outlines the participating organisations and the measurement equipment used for total gamma, dose rate and gamma spectrometry measurements and finally, results obtained and their interpretations are discussed for each type of measurement as a function of detector type. Regarding the dose measurements, results obtained by using a large variety of equipment are very consistent. In view of mapping the inner surface of the biological shield the most appropriate equipment tested might be the organic scintillator, the BGO or even the ionisation chamber. In addition, for mapping this surface, the most appropriate to

In the context of the INSIDER european project, an analysis of the suitability of existing methodologies for in-situ measurements under constraint environments in nuclear facilities following a D&D process was carried out. A list of the constrained environments that could appear was made, along with their expected level of impact on the methodologies (see references: K. Amgarou, M. Herranz (2021): State-of-the-art and challenges of non-destructive techniques for in-situ radiological characterization of nuclear facilities to be dismantled, Nuclear Engineering and Technology 53 (2021), pp. 3491–3504 and F. Aspe, R. Idoeta, G. Auge, M. Herranz: Classification and categorization of the constrained environments in nuclear/radiological installations under decommissioning and dismantling processes, Progress in Nuclear Energy 124 (2020) 102247). As a complement to these papers, the last paper (see K. Amgarou, F. Aspe, R.l Idoeta, M. Herranz: Recommendations for the selection of in situ measurement techniques for radiological characterization in nuclear/radiological installations under decommissioning and dismantling processes, Progress in Nuclear Energy 137 (2021) 103761), gives a global guidance to assist with the decision making process regarding the selection of the best in-situ measurement techniques that could be applied in the different constrained environments. Using the information collected through these analysis, this software is decision-helping tool for the selection of the suitable in-situ equipment/detector to be used in a nuclear facility for the different D&D phases depending on the constrained environment.

INSIDER is an EU Horizon 2020 research project, within the topic NFRP-7 of the EURATOM programme, that aims to develop and validate a new and improved integrated characterization methodology and strategy for the nuclear decommissioning and dismantling operations (D&D) of nuclear power plants, and post-accidental land remediation of nuclear facilities under constrained environments. In line with this general objective, the definition and implementation of the practical considerations surrounding the radiological characterization of nuclear/radioactive facilities subject to a D&D programme is under development. In-situ measurements are key for this radiological characterization. However, in some cases these measurements have to be carried out under constrained conditions, which poses some challenges to their realization. A constrained environment is a general term that includes all types of environment that hinder the choice of a nondestructive in-situ measurement method. In the context of this paper, it is applied to different situations: radioactive levels of the area to be characterised, difficult accessibility of this area, type and properties of the materials contained in it, as well as the possible presence of other environmental hazards, such as asbestos, chemical and/or organic/biological ones. In this context, an analysis of the suitability of existing methodologies for in-situ measurements in constrained environment is being carried out. The first step to accomplish this task is to describe the constrained environments that could appear in the different nuclear/radioactive facilities and their respective challenges. This paper includes a description of the different constrained environments, showing their corresponding challenges and a classification of the constraints, and it provides a series of tables linking the installations and areas inside them with the different constraints that appear. In the case of the radioactive constraints, a description of the

This work presents the analysis of weekly 7Be activity concentrations in the air measured in Bilbao (northern Spain) by collecting aerosols in filters over a ten years period (2009–2018). 7Be level is in the 0.35–7.3 mBq/m3 range, with a mean of 3.20 ± 1.12 mBq/m3. The trend, cycle, seasonal and monthly variability are evaluated using time series analysis techniques. The results indicate the impact of sunspots (24th solar cycle) on interannual 7Be activity concentrations, and a significant seasonal and monthly variation, with maximum concentrations occurring in spring-summer and minimum in the winter. The correlation of different 7Be ranges with local meteorological parameters, such as precipitation, temperature, relative humidity, and pressure, is also addressed, with precipitation having the greatest impact on 7Be activity values. The analysis of synoptic airflows, by calculating the back-trajectory clusters, and local winds at surface level reveals the important influence of the arrival of slow northwest Atlantic flows and the development of breezes on reaching high 7Be activity concentrations in this area.

A co-precipitation method followed by a liquid–liquid extraction and liquid scintillation counting is validated by applying it to five different types of matrices. In order to test the applicability of the method, complex matrices are selected. This paper shows the implementation and the results of the validation of the method.

[EN]Analysis of an X-ray equipment with such a low power (30 kV of acceleration potential) that it allows not to declare itself as a radioactive installation, in order to determine its maximum capacity in the hole-type and wire-type imperfection detection field in alumina by means of a wolfram focus as generating element, intended to be used it formerly in industrial applications., [ES]Análisis de un equipo de RX, cuya baja potencia (30 kV de potencial de aceleración) permita la no declaración del mismo como instalación radiactiva, para determinar su máxima capacidad de detección de defectos tipo taladro y tipo hilo en aluminio utilizando un foco de Wolframio como elemento generador para su posterior uso en el ámbito industrial., [EU]X-izpi ekipo baten analisia, zeinen potentzia baxua (30KV azkartze potentzialkoa) instalazioaren aitorpen erradioaktiboa egiteari uko egiten dio, bere ahalmen maximoa zulo eta hari sortako akats aurkitzearen sailean mugatzeko aluminioan, wolframio foku batekin elementu sortzailetzat, egingo da geroko erabilerako industria mailan.

[ES]El presente estudio consiste en realizar una espectrometría gamma a 12 resinas de intercambio iónico obtenidas de un generador de vapor en una central nuclear. Los resultados de actividad obtenidos serán estudiados para conocer si la actividad de las resinas concuerda con la actividad habitual en una instalación de ese tipo. A continuación, con la información obtenida y resultados de espectrometrías beta y alfa realizadas a las muestras, se determinará si las correlaciones entre radionucleidos clave y radionucleidos de difícil medida, establecidos por el instituto Sueco SKB (Sweden Nuclear Fuel and Waste Management Company), son adecuadas para este caso concreto., [EN]This project consists in developing a gamma spectrometry to 12 different ionic exchange resins from a steam generator belonging of a nuclear power plant. The activities obtained will be checked in order to know which its main component are, also to see if the results shown respect or correlate to those expected in this type of power plant. At last, with the results obtained and information from a beta and alfa spectrometry, determine whether the scaling factors between key radionuclides and difficult to measure ones in nuclear plants, stablished by Swedish SKB (Sweden Nuclear Fuel and Waste Management Company), are accurate for this specific situation., [EU]Ikerlan honetan ikasiko dira zentral nuklearreko 12 erretxinak espektrometria gammarekin. Jardueran lortutako emaitzak aztertuko dira ea lortutako erretxinaren jarduera, mota honetako instalazio bateko jarduera normala den. Ondoren, espektrometria beta eta alphari buruzko informazio eta emaitzekin konparatuko da espektrometria gamma hau. Helburua hau da: Swedish SKB (Sweden Nuclear Fuel and Waste Management Company) ezarritako radionukleido klabe eta zailak neurtzeko radionukleidoen arteko korrelazioak kasu honetan egokiak diren ala ez jakitea.

EN]This is a document done to try to see the effect of a nuclear power plant accident. In particular, it studies what would be the radiation doses delivered to the people in the close areas around the power plant of Garoña, if it had suffered from a loss of coolant accident during its normal functioning., [ES]Este es un documento realizado con la intención de analizar el efecto de un accidente nuclear en una central tipo. Más concretamente, qué nivel de dosis afectaría a la población en torno a una central nuclear seleccionada, Garoña, si durante su actividad hubiese sufrido de una pérdida de refrigerante., [EU]Agiri hau istripu nuklear baten ondorioak analizatzeko intentzioarekin dago egina. Garoña eta inguruko poblazioak zein dosi jasoko luketeen nuklear zentralak martxan ziharduen bitartean, zentralak hozgarri jario bat sufrituko balu.

[ES]El proceso de soldadura más común es la soldadura por arco metálico con electrodos revestidos. A veces ese revestimiento contiene materiales radiactivos de origen natural (NORMs). En España los electrodos más utilizados son los recubiertos de rutilo mezclado con otros materiales. El rutilo contiene algunos radionúclidos naturales detectables, por lo que puede ser considerado como un NORM. Este trabajo principalmente se centra en la aplicación de la metodología expuesta en la Guía de Seguridad 11.3 del Consejo de Seguridad Nuclear (Metodología para la evaluación del impacto radiológico en las industrias NORM), como una herramienta para obtener las dosis en una fábrica que produce este tipo de electrodo y evaluar el impacto radiológico en una instalación específica. Para ello, se aplicaron en dicha instalación los pasos requeridos por la metodología para su cumplimiento. Se analizaron los beneficios inherentes al estudio y se identificaron las zonas de radiación más altas así como la posición de los trabajadores. Habiendo hecho uso de evaluaciones de dosis llevadas a cabo con anterioridad por otros procedimientos, métodos de simulación, se establecieron las pautas de protección radiológica a seguir para el cumplimiento de dicha guía, mediante la colocación de dosímetros personales y monitores de radiación., [EU]Soldadura-prozesurik ohikoena estalitako elektrodoak dituen arku metaliko bidezko soldadura da. Batzuetan estaldura horrek jatorri naturala daukaten material erradiaktiboak (NORM-ak) izaten ditu. Espainian gehien erabiltzen diren elektrodoak errutiloz eta beste materialen nahasketaz estalitakoak dira. Errutiloak zenbait erradionukleido natural detektagarriak ditu, beraz NORM bat bezala har daiteke. Lan honek batez ere Segurtasun Nuklearrerako Kontseiluaren 11.3. Segurtasun Gidan azaldutako metodologiaren aplikazioan jartzen du arreta, elektrodo mota hau ekoizten duen lantegi batean dosiak lortzeko eta instalazio espezifiko batean inpaktu erradiologikoa ebaluatzeko tresna bat bezala. Horretarako, metodologiak eskatutako pausuak aplikatu ziren aipatutako instalazioan. Ikerketari datxekizkion abantailak aztertu egin ziren eta erradiazio-gunerik altuenak identifikatu ziren eta baita langileen posizioa ere. Aurretik beste prozedura batzuen bidez, simulazio-metodoak, burututako dosi-ebaluazioak erabiliz, aipatutako gida betetzeko behar diren babespen erradiologikoko jarraibideak ezarri ziren, dosimetro pertsonalak eta erradiazio-monitoreak kokatuz., [EN]Metallic arc welding using covered electrodes is the most common welding process. Sometimes the covering contains naturally occurring radioactive materials (NORMs). In Spain the most frequently used electrodes are covered with rutile mixed with other materials. Rutile contains some detectable natural radionuclides, so it can be considered a NORM. This paper mainly focuses on the application of the methodology set out in the Safety Guide 11.3 of the Nuclear Safety Council (methodology for evaluation of the radiological impact on the NORM industries), as a tool to get the dose at a factory which produces this type of electrode and evaluate the radiological impact on a specific installation. To do this, the required steps were systematically applied to ensure compliance. The benefits inherent in the study were analyzed and areas of higher radiation and the position of workers were identified. Having previously assessed radiation doses by other methods, simulation methods, new radiation protection guidelines, such as the need for personal dosimeters and radiation monitors, were introduced.

[ES]El objetivo de este trabajo es analizar el montaje de un contador proporcional de radiación para su uso en una red de vigilancia radiológica ambiental desde su diseño básico hasta su puesta en marcha. Se realizará un análisis de las razones que nos han llevado a elegir este tipo de contadores de ionización gaseosa (frente a otros tipos), para llegar a la conclusión de que son los más adecuados para la vigilancia radiológica ambiental. Este análisis describirá la solución a la que se ha llegado para construir un contador con los medios al alcance y el porqué de su diseño concreto, así como la metodología de trabajo que se ha seguido para la obtención del mismo. Basándonos en suposiciones teóricas derivadas del análisis geométrico de la instrumentación para la obtención de resultados previsibles, se realizará una verificación mediante ensayos técnicos en el laboratorio. Se presupuestará el material utilizado y las horas requeridas, para llevar una cuenta de lo que le ha costado al departamento y lo que le habría costado en caso de no poseer la instrumentación utilizada. Después de realizar diversos test relacionados con la instrumentación electrónica, se procederá a obtener unas conclusiones derivadas de los ensayos en el laboratorio para su posterior comparación con las estimaciones teóricas. En el anexo I se encuentran los planos de diseño que se han realizado y en el anexo II los resultados finales obtenidos de los ensayos.