Impact radiologique liés au transport de matières radioactives par route en Espagne / Radiological impact associated with the transport by road of radioactive material in Spain

Questions relating to the transport of radioactive materials are very much an issue of current interest due to the increasing mobility of the materials involved in the nuclear fuel cycle, commitment to the environment, the safety and protection of persons and the corresponding regulatory legal framework. The radiological impact associated with this type of transport was assessed by means of a new data-processing tool that may be of use and serve as complementary documentation to that included in transport regulations. Thus, by determining the level of radiation at a distance of one metre from the transport vehicle and by selecting a route, the associated impacts will be obtained, such as the affected populations, the dose received by the most highly exposed individual, the overall radiological impact, the doses received by the population along the route and the possible detriment to their health. The most important conclusion is that the emissions of ionising radiation from the transport of radioactive material by road in Spain are not significant as regards the generation of adverse effects on human health, and that their radiological impact may be considered negligible.

Calculation Methodology and Fabrication Procedures for Particle Accelerator Strip-Line Kickers: Application to the CTF3 Combiner Ring Extraction Kicker and TL2 Tail Clippers

A particle accelerator is any device that, using electromagnetic fields, is able to communicate energy to charged particles (typically electrons or ionized atoms), accelerating and/or energizing them up to the required level for its purpose. The applications of particle accelerators are countless, beginning in a common TV CRT, passing through medical X-ray devices, and ending in large ion colliders utilized to find the smallest details of the matter. Among the other engineering applications, the ion implantation devices to obtain better semiconductors and materials of amazing properties are included. Materials supporting irradiation for future nuclear fusion plants are also benefited from particle accelerators. There are many devices in a particle accelerator required for its correct operation. The most important are the particle sources, the guiding, focalizing and correcting magnets, the radiofrequency accelerating cavities, the fast deflection devices, the beam diagnostic mechanisms and the particle detectors. Most of the fast particle deflection devices have been built historically by using copper coils and ferrite cores which could effectuate a relatively fast magnetic deflection, but needed large voltages and currents to counteract the high coil inductance in a response in the microseconds range. Various beam stability considerations and the new range of energies and sizes of present time accelerators and their rings require new devices featuring an improved wakefield behaviour and faster response (in the nanoseconds range). This can only be achieved by an electromagnetic deflection device based on a transmission line. The electromagnetic deflection device (strip-line kicker) produces a transverse displacement on the particle beam travelling close to the speed of light, in order to extract the particles to another experiment or to inject them into a different accelerator. The deflection is carried out by the means of two short, opposite phase pulses. The diversion of the particles is exerted by the integrated Lorentz force of the electromagnetic field travelling along the kicker. This Thesis deals with a detailed calculation, manufacturing and test methodology for strip-line kicker devices. The methodology is then applied to two real cases which are fully designed, built, tested and finally installed in the CTF3 accelerator facility at CERN (Geneva). Analytical and numerical calculations, both in 2D and 3D, are detailed starting from the basic specifications in order to obtain a conceptual design. Time domain and frequency domain calculations are developed in the process using different FDM and FEM codes. The following concepts among others are analyzed: scattering parameters, resonating high order modes, the wakefields, etc. Several contributions are presented in the calculation process dealing specifically with strip-line kicker devices fed by electromagnetic pulses. Materials and components typically used for the fabrication of these devices are analyzed in the manufacturing section. Mechanical supports and connexions of electrodes are also detailed, presenting some interesting contributions on these concepts. The electromagnetic and vacuum tests are then analyzed. These tests are required to ensure that the manufactured devices fulfil the specifications. Finally, and only from the analytical point of view, the strip-line kickers are studied together with a pulsed power supply based on solid state power switches (MOSFETs). The solid state technology applied to pulsed power supplies is introduced and several circuit topologies are modelled and simulated to obtain fast and good flat-top pulses.

Obtaining carbonation depth of concrete used two different procedures standard EHE-08

In the Standard EHE 08, for the first time, durability acquires the status of Limit State. Article 8 provides that the term Durability limit state, produced by physical and chemical actions, different loads and actions of structural analysis, which can degrade the concrete and reinforcement to unacceptable limits. The verification of this limit state can be done through a procedure set out in the provisions of the Standard. This procedure is based on the use of tables that, depending on the aggressiveness of the environment in which the structure is the concrete strength and the life of the project, setting the quality of the concrete cover (minimum thickness and maximum water cement ratio of concrete used) and the maximum crack width. This procedure, simple in its application, provides highly secure solutions. In addition, on Annex 9, the Standard EHE 08 offers models for testing the durability limit state in cases of corrosion of reinforcement due to carbonation of concrete or entry of chloride ions. The results obtained with these models are tighter than those obtained with the procedure of the articles. In this paper we use both methods in the study of reinforced concrete structures with potential problems of corrosion of reinforcement due to carbonation of concrete. Later checking the results obtained by both procedures. Results demonstrate that the use of the models listed in Annex 9 of Standard EHE 08 offer cheaper solutions than those obtained using the procedure of the articles

Monitoring maximum peak power density values as a more reliable marker for measurement procedures to elucidate RF EMF health effects: Leganes project

Considering the measurement procedures recommended by the ICNIRP, this communication is a proposal for a measurement procedure based in the maximum peak values of equivalent plane wave power density. This procedure has been included in a project being developed in Leganés, Spain. The project plans to deploy a real time monitoring system for RF to provide the city with a useful tool to adapt the environmental EM conditions to the new regulations approved. A first stage consisting of 105 measurement points has been finished and all the values are under the threshold of the regulation.

Microarray analysis of autoimmune diseases by machine learning procedures

—Microarray-based global gene expression profiling, with the use of sophisticated statistical algorithms is providing new insights into the pathogenesis of autoimmune diseases. We have applied a novel statistical technique for gene selection based on machine learning approaches to analyze microarray expression data gathered from patients with systemic lupus erythematosus (SLE) and primary antiphospholipid syndrome (PAPS), two autoimmune diseases of unknown genetic origin that share many common features. The methodology included a combination of three data discretization policies, a consensus gene selection method, and a multivariate correlation measurement. A set of 150 genes was found to discriminate SLE and PAPS patients from healthy individuals. Statistical validations demonstrate the relevance of this gene set from an univariate and multivariate perspective. Moreover, functional characterization of these genes identified an interferon-regulated gene signature, consistent with previous reports. It also revealed the existence of other regulatory pathways, including those regulated by PTEN, TNF, and BCL-2, which are altered in SLE and PAPS. Remarkably, a significant number of these genes carry E2F binding motifs in their promoters, projecting a role for E2F in the regulation of autoimmunity.

Conditional parallelization of nonStrict independence. Procedures and assessmen

This paper presents a conditional parallelization process for and-parallelism based on the notion of non-strict independence, a more relaxed notion than the traditional of strict independence. By using this notion, a parallelism annotator can extract more parallelism from programs. On the other hand, the intrinsic complexity of non-strict independence poses new challenges to this task. We report here on the implementation we have accomplished of an annotator for non-strict independence, capable of producing both static and dynamic execution graphs. This implementation, along with the also implemented independence checker and their integration in our system, have resulted what is, to the best of our knowledge, the first parallelizing compiler based on nonstrict independence which produces dynamic execution graphs. The paper also presents a preliminary assessment of the implemented tools, comparing them with the existing ones for strict independence, which shows encouraging results.

Neutronics design and radiological aspects of HiPER facilities

En este trabajo se han cubierto diferentes asuntos del diseño neutrónico de los aspectos radiológicos de las dos instalaciones del proyecto HiPER. El proyecto HiPER es un proyecto europeo concebido en el marco del programa ESFRI (European Scientific Facilities Research Infrastructure). Está destinado al desarrollo de la energía de fusión nuclear inercial mediante el uso de láseres y el esquema iluminación directa. Consecuentemente, se trata de una instalación con fines exclusivamente civiles. Se divide en dos fases, correspondientes con dos instalaciones: HiPER Engineering y HiPER Reactor. La instalación HiPER Engineering desarrollará las tecnologías implicadas en la ignición de alta repetición de cápsulas de DT por iluminación directa. El HiPER Reactor será una planta demostradora que produzca electricidad haciendo uso de las tecnologías desarrolladas durante la fase HiPER Engineering. El HiPER Engineering se centrará en las tecnologías relevantes para las igniciones a alta repetición de cápsulas de DT usando la iluminación directa. El principal esfuerzo de desarrollo tecnológico se hará en todos los asuntos directamente relacionados con la ignición: láseres, óptica, inyector, y fabricación masiva de cápsulas entre otros. Se espera una producción de entre 5200 MJ/año y 120000 MJ/año dependiendo del éxito de la instalación. Comparado con la energía esperada en NIF, 1200 MJ/año, se trata de un reto y un paso más allá en la protección radiológica. En este trabajo se ha concebido una instalación preliminar. Se ha evaluado desde el punto de vista de la protección radiológica, siendo las personas y la óptica el objeto de protección de este estudio. Se ha establecido una zonificación durante la operación y durante el mantenimiento de la instalación. Además, se ha llevado a cabo una evaluación de la selección de materiales para la cámara de reacción desde el punto de vista de gestión de residuos radiactivos. El acero T91 se ha seleccionado por, siendo un acero comercial, presentar el mismo comportamiento que el acero de baja activación EUROFER97 al evaluarse como residuo con el nivel de irradiación de HiPER Engineering. Teniendo en cuenta los resultados obtenidos para la instalación preliminar y las modificaciones de la instalación motivadas en otros campos, se ha propuesto una instalación avanzada también en este trabajo. Un análisis más profundo de los aspectos radiológicos, así como una evaluación completa de la gestión de todos los residuos radiactivos generados en la instalación se ha llevado a cabo. La protección radiológica se ha incrementado respecto de la instalación preliminar, y todos los residuos pueden gestionarse en un plazo de 30 sin recurrir al enterramiento de residuos. El HiPER Reactor sera una planta demostradora que produzca electricidad basada en las tecnologías de ignición desarrolladas durante la fase HiPER Engineering. El esfuerzo de desarrollo tecnológico se llevará a cabo en los sistemas relacionados con la generación de electricidad en condiciones económicas: manto reproductor de tritio, ciclos de potencia, vida y mantenimiento de componentes, o sistemas de recuperación de tritio entre otros. En este trabajo la principal contribución a HiPER Reactor está relacionada con el diseño de la cámara de reacción y sus extensiones en la planta. La cámara de reacción es la isla nuclear más importante de la planta, donde la mayoría de las reacciones nucleares tienen lugar. Alberga la primera pared, el manto reproductor de tritio y la vasija de vacío. Todo el trabajo realizado aquí ha pivotado en torno al manto reproductor de tritio y sus interacciones con el resto de componentes de la planta. Tras una revisión profunda de la bibliografía de los diseños recientes de cámaras de reacción con características similares a HiPER Reactor, se ha propuesto y justificado un esquema tecnológico innovador para el manto reproductor de tritio. El material fértil selecconado es el eutéctico 15.7 at.% Litio – 84.3 at.% Plomo, LiPb, evitando el uso de berilio como multiplicador neutrónico mientras se garantiza el ajuste online de la tasa de reproducción de tritio mediante el ajuste en el enriquecimiento en 6Li. Aunque se podría haber elegido Litio purom el LiPb evita problemas relacionados con la reactividad química. El precio a pagar es un reto materializado como inventario radiactivo de Z alto en el lazo de LiPb que debe controlarse. El material estructural seleccionado es el acero de baja activación EUROFER97, que estará en contacto directo con le LiPb fluyendo a alta velocidad. En este esquema tecnológico, el LiPb asegurará la autosuficiente de tritio de la planta mientras el propio LiPb extrae del manto el calor sobre él depositado por los neutrones. Este esquema recibe el nombre de manto de Litio-Plomo auto-refrigerado (SCLL por sus siglas en inglés). Respecto de los conceptos SCLL previos, es destacable que nos e requieren componentes del SiC, puesto que no hay campos magnéticos en la cámara de reacción. Consecuentemente, el manto SCLL propuesto para HiPER presenta riesgo tecnológicos moderados, similares a otros dispositivos de fusión magnética, como el HCLL, e incluso inferiores a los del DCLL, puesto que no se require SiC. Los retos que se deben afrontar son el control del inventario de Z alto así como las tasas de corrosión derivadas de la interacción del LiPb con el EUROFE97. En este trabajo se abordan ambos aspectos, y se presentan los respectivos análisis, junto con otros aspectos neutrónicos y de activación, tales como la protección de la vasija de vacío por parte del material fértil para garantizar la resoldabilidad de por vida en la cara externa de la vasija. También se propone y se estudio un ciclo de potencia de Brayton de Helio para dos configuraciones diferentes de refrigeración del sistema primera pared-manto reproductor. Las principales conclusiones de estos estudios son: i) el inventario de Z alto puede controlarse y es comparable al que se encuentra en dispositivos de fusión similares, ii)la vasija de vacío requiere una mayor protección frente a la radiación neutrónica y iii) las tasas de corrosión son demasiado altas y la temperatura media de salida del LiPb es demasiado baja. Tiendo en cuenta estos resultados juntos con otras consideraciones relacionadas con el mantenimiento de componentes y la viabilidad constructiva, se ha propuesto una evolución de la cámara de reacción. Las evoluciones más destacables son la introducción de un reflector neutrónico de grafito, la modificación de la configuración de la óptica final, la forma y el tamaño de la cámara de vacío y una nueva subdivisión modular del manto. Se ha evaluado desde el punto de vista neutrónico, y su análisis y posterior evolución queda fuera del objeto de este trabajo. Los códigos utilizados en este trabajo son: CATIA para la generación de geometrías 3D complejas MCAM para la traducción de archivos de CATIA a formato de input de MCNP MCNP para el transporte de la radiación (neutrones y gammas) y sus respuestas asociadas ACAB para la evolución del inventario isotópico y sus respuestas asociadas MC2ACAB para acoplar MCNP y ACAB para el cómputo de dosis en parada usando la metodología R2S basada en celda. Moritz para visualizar los reultados de MCNP FLUENT para llevar a cabo cálculos de fluido-dinámica Para llevar a cabo este trabajo, han sido necesarias unas destrezas computacionales. Las más relevantes utilizadas son: generación de geometrás 3D complejas y transmisión a MCNP, diferentes tñecnica de reducción de varianza como importancia por celdas y weight windows basado en malla, metodología Rigorous-two-Steps basada en celdas para el cálculo de dosis en parada y la modificación del código ACAB para el cálculos con múltiples espectros en la misma simulación. Como resumen, la contribución de este trabajo al proyecto HiPER son dos diseños conceptuales de instalación: una para HiPER Engineering y otra para HiPER Reactor. La primera se ha estudio en profundidad desde el punto de vista de protección radiológica y gestión de residuos, mientras que la segunda se ha estudiado desde el punto de vista de operación: seguridad, comportamiento, vida y mantenimiento de componentes y eficiencia del ciclo de potencia.

Advances in neutronics and radiological protection of HiPER 4a

The HiPER project, phase 4a, is evolving. In this study we present the progress made in the field of neutronics and radiological protection for an integrated design of the facility. In the current model, we take into account the optical systems inside the target bay, as well as the remote handling requirements and related infrastructure, together with different shields. The last reference irradiation scenario, consisting of 20 MJ of neutron yields, 5 yields per burst, one burst every week and 30 years of expected lifetime is considered for this study. We have performed a characterization of the dose rates behavior in the facility, both during operation and between bursts. The dose rates are computed for workers, regarding to maintenance and handling, and also for optical systems, regarding to damage. Furthermore, we have performed a waste management assessment of all the components inside the target bay. Results indicate that remote maintenance is mandatory in some areas. The small beam penetrations in the shields are responsible for some high doses in some specific locations. With regards to optics, the residual doses are as high as prompt doses. It is found that the whole target bay may be fully managed as a waste in 30 years by recycling and/or clearance, with no need for burial.

A comparison between PML, infinite elements and an iterative BEM as mesh truncation methods for HP self-adaptive procedures in electromagnetics

Finite element hp-adaptivity is a technology that allows for very accurate numerical solutions. When applied to open region problems such as radar cross section prediction or antenna analysis, a mesh truncation method needs to be used. This paper compares the following mesh truncation methods in the context of hp-adaptive methods: Infinite Elements, Perfectly Matched Layers and an iterative boundary element based methodology. These methods have been selected because they are exact at the continuous level (a desirable feature required by the extreme accuracy delivered by the hp-adaptive strategy) and they are easy to integrate with the logic of hp-adaptivity. The comparison is mainly based on the number of degrees of freedom needed for each method to achieve a given level of accuracy. Computational times are also included. Two-dimensional examples are used, but the conclusions directly extrapolated to the three dimensional case.

Woolliness assessment in peaches. Comparison between human and instrumental procedures and results

Woolliness, a negative attribute of sensory texture, is characterised by the lack of juiciness without variation of the tissue water content an incapacity of ripening although there is external ripe appearance. In this study, peaches cv Springcrest (early and soft flesh peaches) and Miraflores (late and hard flesh peaches) corresponding to three different maturity stages at harvest, stored 0, 1, 2, 3 and 4 weeks at 1 and 5°C have been tested by instrumental and sensory means. A Instrumental classification of woolliness has been compared to the sensory assessment. For Springcrest peaches the sensory results match with those found for the instrumental procedure. In this case , Woolliness appears after 2 weeks of storage at 5°C, changing abruptly from crispy to woolly. Miraflores peaches did not develop woolliness during storage. After comparing with sensory results, it is shown that a common instrumental scale may be appropriate to classify for woolliness all peach varieties.

An approach to stakeholders involvement in the preparedness for nuclear and radiological emergency response & recovery in Spain

The elaboration of a generic decision-making strategy to address the evolution of an emergency situation, from the stages of response to recovery, and including a planning stage, can facilitate timely, effective and consistent decision making by the response organisations at every level within the emergency management structure and between countries, helping to ensure optimal protection of health, environment, and society. The degree of involvement of stakeholders in this process is a key strategic element for strengthening the local preparedness and response and can help a successful countermeasures strategy. A significant progress was made with the multi-national European project EURANOS (2004-2009) which brought together best practice, knowledge and technology to enhance the preparedness for Europe's response to any radiation emergency and long term contamination. The subsequent establishment of a European Technology Platform and the recent launch of the research project NERIS-TP ("Towards a self sustaining European Technology Platform (NERIS-TP) on Preparedness for Nuclear and Radiological Emergency Response and Recovery") are aimed to continue with the remaining tasks for gaining appropriate levels of emergency preparedness at local level in most European countries. One of the objectives of the NERIS-TP project is: Strengthen the preparedness at the local/national level by setting up dedicated fora and developing new tools or adapting the tools developed within the EURANOS projects (such as the governance framework for preparedness, the handbooks on countermeasures, the RODOS system, and the MOIRA DSS for long term contamination in catchments) to meet the needs of local communities. CIEMAT and UPM in close interaction with the Nuclear Safety Council will explore, within this project, the use and application in Spain of such technical tools, including other national tools and information and communication strategies to foster cooperation between local, national and international stakeholders. The aim is identify and involve relevant stakeholders in emergency preparedness to improve the development and implementation of appropriate protection strategies as part of the consequence management and the transition to recovery. In this paper, an overview of the "state of the art" on this area in Spain and the methodology and work Plan proposed by the Spanish group within the project NERIS to grow the stakeholder involvement in the preparedness to emergency response and recovery is presented.

Storabelity of melon for different ripeness stages at harvest. Selection of instrumental procedures for quality assessment.

The consumption of melon (Cucumis melo L.) has been, until several years ago, regional, seasonal and without commercial interest. Recent commercial changes and world wide transportation have changed this situation. Melons from 3 different ripeness stages at harvest and 7 cold storage periods have been analysed by destructive and non destructive tests. Chemical, physical, mechanical (non destructive impact, compression, skin puncture and Magness- Taylor) and sensory tests were carried out in order to select the best test to assess quality and to determine the optimal ripeness stage at harvest. Analysis of variance and Principal Component Analysis were performed to study the data. The mechanical properties based on non-destructive Impact and Compression can be used to monitor cold storage evolution. They can also be used at harvest to segregate the highest ripeness stage (41 days after anthesis DAA) in relation to less ripe stages (34 and 28 DAA).Only 34 and 41 DAA reach a sensory evaluation above 50 in a scale from 0-100.

Analysis of the operator action and the single failure criteria in a SGTR sequence using best estimate assumptions with TRACE 5.0

Steam Generator Tube Rupture (SGTR) sequences in Pressurized Water Reactors are known to be one of the most demanding transients for the operating crew. SGTR are a special kind of transient as they could lead to radiological releases without core damage or containment failure, as they can constitute a direct path from the reactor coolant system to the environment. The first methodology used to perform the Deterministic Safety Analysis (DSA) of a SGTR did not credit the operator action for the first 30 min of the transient, assuming that the operating crew was able to stop the primary to secondary leakage within that period of time. However, the different real SGTR accident cases happened in the USA and over the world demonstrated that the operators usually take more than 30 min to stop the leakage in actual sequences. Some methodologies were raised to overcome that fact, considering operator actions from the beginning of the transient, as it is done in Probabilistic Safety Analysis. This paper presents the results of comparing different assumptions regarding the single failure criteria and the operator action taken from the most common methodologies included in the different Deterministic Safety Analysis. One single failure criteria that has not been analysed previously in the literature is proposed and analysed in this paper too. The comparison is done with a PWR Westinghouse three loop model in TRACE code (Almaraz NPP) with best estimate assumptions but including deterministic hypothesis such as single failure criteria or loss of offsite power. The behaviour of the reactor is quite diverse depending on the different assumptions made regarding the operator actions. On the other hand, although there are high conservatisms included in the hypothesis, as the single failure criteria, all the results are quite far from the regulatory limits. In addition, some improvements to the Emergency Operating Procedures to minimize the offsite release from the damaged SG in case of a SGTR are outlined taking into account the offsite dose sensitivity results.

Bankable procedures for the technical quality assurance of large scale PV plants

Strict technical quality assurance procedures are essential for PV plant bankability. When large-scale PV plants are concerned, this is typically accomplished in three consecutive phases: an energy yield forecast, that is performed at the beginning of the project and is typically accomplished by means of a simulation exercise performed with dedicated software; a reception test campaign, that is performed at the end of the commissioning and consists of a set of tests for determining the efficiency and the reliability of the PV plant devices; and a performance analysis of the first years of operation, that consists in comparing the real energy production with the one calculated from the recorded operating conditions and taking into account the maintenance records. In the last six years, IES-UPM has offered both indoor and on-site quality control campaigns for more than 60 PV plants, with an accumulated power of more than 300 MW, in close contact with Engineering, Procurement and Construction Contractors and financial entities. This paper presents the lessons learned from such experience.

Diseño y ensayos en tierra de paneles solares para un satélite de órbita baja = Design and testing procedures of a Low Earth Orbit (LEO) satellite solar panels

Debido al reciente incremento de conflictos en el mundo árabe y dado el interés nacional de España en dicha zona, se propone en este proyecto un estudio inicial para el diseño y desarrollo de un microsatélite que ayude al gobierno de España a mantener esa zona bajo observación constante. En el presente trabajo se abarcan todos los subsistemas del satélite, haciéndose un estudio más detallado del subsistema de potencia