Performance of a transmutation advanced device for sustainable energy application

Preliminary studies have been performed to design a device for nuclear waste transmutation and hydrogen generation based on a gas-cooled pebble bed accelerator driven system, TADSEA (Transmutation Advanced Device for Sustainable Energy Application). In previous studies we have addressed the viability of an ADS Transmutation device that uses as fuel wastes from the existing LWR power plants, encapsulated in graphite in the form of pebble beds, cooled by helium which enables high temperatures (in the order of 1200 K), to generate hydrogen from water either by high temperature electrolysis or by thermochemical cycles. For designing this device several configurations were studied, including several reflectors thickness, to achieve the desired parameters, the transmutation of nuclear waste and the production of 100 MW of thermal power. In this paper new studies performed on deep burn in-core fuel management strategy for LWR waste are presented. The fuel cycle on TADSEA device has been analyzed based on both: driven and transmutation fuel that had been proposed by the General Atomic design of a gas turbine-modular helium reactor. The transmutation results of the three fuel management strategies, using driven, transmutation and standard LWR spent fuel were compared, and several parameters describing the neutron performance of TADSEA nuclear core as the fuel and moderator temperature reactivity coefficients and transmutation chain, are also presented

Neutron spectrometry using artificial neural networks for a bonner sphere spectrometer with 3He detector

Neutron spectra unfolding and dose equivalent calculation are complicated tasks in radiation protection, are highly dependent of the neutron energy, and a precise knowledge on neutron spectrometry is essential for all dosimetry-related studies as well as many nuclear physics experiments. In previous works have been reported neutron spectrometry and dosimetry results, by using the ANN technology as alternative solution, starting from the count rates of a Bonner spheres system with a LiI(Eu) thermal neutrons detector, 7 polyethylene spheres and the UTA4 response matrix with 31 energy bins. In this work, an ANN was designed and optimized by using the RDANN methodology for the Bonner spheres system used at CIEMAT Spain, which is composed of a He neutron detector, 12 moderator spheres and a response matrix for 72 energy bins. For the ANN design process a neutrons spectra catalogue compiled by the IAEA was used. From this compilation, the neutrons spectra were converted from lethargy to energy spectra. Then, the resulting energy ?uence spectra were re-binned by using the MCNP code to the corresponding energy bins of the He response matrix before mentioned. With the response matrix and the re-binned spectra the counts rate of the Bonner spheres system were calculated and the resulting re-binned neutrons spectra and calculated counts rate were used as the ANN training data set.

Preliminary approach to neutron instrument selecction at ESSB-Bilbao based on experience at ISIS molecular spectroscopy group

Collaborative efforts between the Neutronics and Target Design Group at the Instituto de Fusión Nuclear and the Molecular Spectroscopy Group at the ISIS Pulsed Neutron and Muon Source date back to 2012 in the context of the ESS-Bilbao project. The rationale for these joint activities was twofold, namely: to assess the realm of applicability of the low-energy neutron source proposed by ESS-Bilbao - for details; and to explore instrument capabilities for pulsed-neutron techniques in the range 0.05-3 ms, a time range where ESS-Bilbao and ISIS could offer a significant degree of synergy and complementarity. As part of this collaboration, J.P. de Vicente has spent a three-month period within the ISIS Molecular Spectroscopy Group, to gain hands-on experience on the practical aspects of neutron-instrument design and the requisite neutron-transport simulations. To date, these activities have resulted in a joint MEng thesis as well as a number of publications and contributions to national and international conferences. Building upon these previous works, the primary aim of this report is to provide a self-contained discussion of general criteria for instrument selection at ESS-Bilbao, the first accelerator-driven, low-energy neutron source designed in Spain. To this end, Chapter 1 provides a brief overview of the current design parameters of the accelerator and target station. Neutron moderation is covered in Chapter 2, where we take a closer look at two possible target-moderator-reflector configurations and pay special attention to the spectral and temporal characteristics of the resulting neutron pulses. This discussion provides a necessary starting point to assess the operation of ESSB in short- and long-pulse modes. These considerations are further explored in Chapter 3, dealing with the primary characteristics of ESS-Bilbao as a short- or long-pulse facility in terms of accessible dynamic range and spectral resolution. Other practical aspects including background suppression and the use of fast choppers are also discussed. The guiding principles introduced in the first three chapters are put to use in Chapter 4 where we analyse in some detail the capabilities of a small-angle scattering instrument, as well as how specific scientific requirements can be mapped onto the optimal use of ESS-Bilbao for condensed-matter research. Part 2 of the report contains additional supporting documentation, including a description of the ESSB McStas component, a detailed characterisation of moderator response and neutron pulses, and estimates ofparameters associated with the design and operation of neutron choppers. In closing this brief foreword, we wish to thank both ESS-Bilbao and ISIS for their continuing encouragement and support along the way.

Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1

A review of the experimental data for natC(n,c) and 12C(n,c) was made to identify the origin of the natC capture cross sections included in evaluated data libraries and to clarify differences observed in neutronic calculations for graphite moderated reactors using different libraries. The performance of the JEFF-3.1.2 and ENDF/B-VII.1 libraries was verified by comparing results of criticality calculations with experimental results obtained for the BR1 reactor. This reactor is an air-cooled reactor with graphite as moderator and is located at the Belgian Nuclear Research Centre SCK-CEN in Mol (Belgium). The results of this study confirm conclusions drawn from neutronic calculations of the High Temperature Engineering Test Reactor (HTTR) in Japan. Furthermore, both BR1 and HTTR calculations support the capture cross section of 12C at thermal energy which is recommended by Firestone and Révay. Additional criticality calculations were carried out in order to illustrate that the natC thermal capture cross section is important for systems with a large amount of graphite. The present study shows that only the evaluation carried out for JENDL-4.0 reflects the current status of the experimental data.

Neutronic design for ESS-Bilbao neutron source

The European Spallation Source-Bilbao (ESS-Bilbao) project plans to build an accelerator facility compliant with the ESS-AB requirements which will be able to drive several experimental stations for research purposes involving intense proton beams with currents up to 75 mA, 50 MeV of final energy, 1.5 ms of pulse length and up to 50 Hz repetition rate. The accelerator will also drive a compact neutron source which will provide useful neutron beams to carry out experiments on moderator optimization, neutron optics devices and general neutron instrumentation as well as preparation work for experiments to be carried out by neutron beam users at the large facilities.

Diseño de un módulo de IFMIF para irradiación de envolturas regeneradoras basadas en metales líquidos para reactores de fusión

La fusión nuclear es, hoy en día, una alternativa energética a la que la comunidad internacional dedica mucho esfuerzo. El objetivo es el de generar entre diez y cincuenta veces más energía que la que consume mediante reacciones de fusión que se producirán en una mezcla de deuterio (D) y tritio (T) en forma de plasma a doscientos millones de grados centígrados. En los futuros reactores nucleares de fusión será necesario producir el tritio utilizado como combustible en el propio reactor termonuclear. Este hecho supone dar un paso más que las actuales máquinas experimentales dedicadas fundamentalmente al estudio de la física del plasma. Así pues, el tritio, en un reactor de fusión, se produce en sus envolturas regeneradoras cuya misión fundamental es la de blindaje neutrónico, producir y recuperar tritio (fuel para la reacción DT del plasma) y por último convertir la energía de los neutrones en calor. Existen diferentes conceptos de envolturas que pueden ser sólidas o líquidas. Las primeras se basan en cerámicas de litio (Li2O, Li4SiO4, Li2TiO3, Li2ZrO3) y multiplicadores neutrónicos de Be, necesarios para conseguir la cantidad adecuada de tritio. Los segundos se basan en el uso de metales líquidos o sales fundidas (Li, LiPb, FLIBE, FLINABE) con multiplicadores neutrónicos de Be o el propio Pb en el caso de LiPb. Los materiales estructurales pasan por aceros ferrítico-martensíticos de baja activación, aleaciones de vanadio o incluso SiCf/SiC. Cada uno de los diferentes conceptos de envoltura tendrá una problemática asociada que se estudiará en el reactor experimental ITER (del inglés, “International Thermonuclear Experimental Reactor”). Sin embargo, ITER no puede responder las cuestiones asociadas al daño de materiales y el efecto de la radiación neutrónica en las diferentes funciones de las envolturas regeneradoras. Como referencia, la primera pared de un reactor de fusión de 4000MW recibiría 30 dpa/año (valores para Fe-56) mientras que en ITER se conseguirían <10 dpa en toda su vida útil. Esta tesis se encuadra en el acuerdo bilateral entre Europa y Japón denominado “Broader Approach Agreement “(BA) (2007-2017) en el cual España juega un papel destacable. Estos proyectos, complementarios con ITER, son el acelerador para pruebas de materiales IFMIF (del inglés, “International Fusion Materials Irradiation Facility”) y el dispositivo de fusión JT-60SA. Así, los efectos de la irradiación de materiales en materiales candidatos para reactores de fusión se estudiarán en IFMIF. El objetivo de esta tesis es el diseño de un módulo de IFMIF para irradiación de envolturas regeneradoras basadas en metales líquidos para reactores de fusión. El módulo se llamará LBVM (del inglés, “Liquid Breeder Validation Module”). La propuesta surge de la necesidad de irradiar materiales funcionales para envolturas regeneradoras líquidas para reactores de fusión debido a que el diseño conceptual de IFMIF no contaba con esta utilidad. Con objeto de analizar la viabilidad de la presente propuesta, se han realizado cálculos neutrónicos para evaluar la idoneidad de llevar a cabo experimentos relacionados con envolturas líquidas en IFMIF. Así, se han considerado diferentes candidatos a materiales funcionales de envolturas regeneradoras: Fe (base de los materiales estructurales), SiC (material candidato para los FCI´s (del inglés, “Flow Channel Inserts”) en una envoltura regeneradora líquida, SiO2 (candidato para recubrimientos antipermeación), CaO (candidato para recubrimientos aislantes), Al2O3 (candidato para recubrimientos antipermeación y aislantes) y AlN (material candidato para recubrimientos aislantes). En cada uno de estos materiales se han calculado los parámetros de irradiación más significativos (dpa, H/dpa y He/dpa) en diferentes posiciones de IFMIF. Estos valores se han comparado con los esperados en la primera pared y en la zona regeneradora de tritio de un reactor de fusión. Para ello se ha elegido un reactor tipo HCLL (del inglés, “Helium Cooled Lithium Lead”) por tratarse de uno de los más prometedores. Además, los valores también se han comparado con los que se obtendrían en un reactor rápido de fisión puesto que la mayoría de las irradiaciones actuales se hacen en reactores de este tipo. Como conclusión al análisis de viabilidad, se puede decir que los materiales funcionales para mantos regeneradores líquidos podrían probarse en la zona de medio flujo de IFMIF donde se obtendrían ratios de H/dpa y He/dpa muy parecidos a los esperados en las zonas más irradiadas de un reactor de fusión. Además, con el objetivo de ajustar todavía más los valores, se propone el uso de un moderador de W (a considerar en algunas campañas de irradiación solamente debido a que su uso hace que los valores de dpa totales disminuyan). Los valores obtenidos para un reactor de fisión refuerzan la idea de la necesidad del LBVM, ya que los valores obtenidos de H/dpa y He/dpa son muy inferiores a los esperados en fusión y, por lo tanto, no representativos. Una vez demostrada la idoneidad de IFMIF para irradiar envolturas regeneradoras líquidas, y del estudio de la problemática asociada a las envolturas líquidas, también incluida en esta tesis, se proponen tres tipos de experimentos diferentes como base de diseño del LBVM. Éstos se orientan en las necesidades de un reactor tipo HCLL aunque a lo largo de la tesis se discute la aplicabilidad para otros reactores e incluso se proponen experimentos adicionales. Así, la capacidad experimental del módulo estaría centrada en el estudio del comportamiento de litio plomo, permeación de tritio, corrosión y compatibilidad de materiales. Para cada uno de los experimentos se propone un esquema experimental, se definen las condiciones necesarias en el módulo y la instrumentación requerida para controlar y diagnosticar las cápsulas experimentales. Para llevar a cabo los experimentos propuestos se propone el LBVM, ubicado en la zona de medio flujo de IFMIF, en su celda caliente, y con capacidad para 16 cápsulas experimentales. Cada cápsula (24-22 mm de diámetro y 80 mm de altura) contendrá la aleación eutéctica LiPb (hasta 50 mm de la altura de la cápsula) en contacto con diferentes muestras de materiales. Ésta irá soportada en el interior de tubos de acero por los que circulará un gas de purga (He), necesario para arrastrar el tritio generado en el eutéctico y permeado a través de las paredes de las cápsulas (continuamente, durante irradiación). Estos tubos, a su vez, se instalarán en una carcasa también de acero que proporcionará soporte y refrigeración tanto a los tubos como a sus cápsulas experimentales interiores. El módulo, en su conjunto, permitirá la extracción de las señales experimentales y el gas de purga. Así, a través de la estación de medida de tritio y el sistema de control, se obtendrán los datos experimentales para su análisis y extracción de conclusiones experimentales. Además del análisis de datos experimentales, algunas de estas señales tendrán una función de seguridad y por tanto jugarán un papel primordial en la operación del módulo. Para el correcto funcionamiento de las cápsulas y poder controlar su temperatura, cada cápsula se equipará con un calentador eléctrico y por tanto el módulo requerirá también ser conectado a la alimentación eléctrica. El diseño del módulo y su lógica de operación se describe en detalle en esta tesis. La justificación técnica de cada una de las partes que componen el módulo se ha realizado con soporte de cálculos de transporte de tritio, termohidráulicos y mecánicos. Una de las principales conclusiones de los cálculos de transporte de tritio es que es perfectamente viable medir el tritio permeado en las cápsulas mediante cámaras de ionización y contadores proporcionales comerciales, con sensibilidades en el orden de 10-9 Bq/m3. Los resultados son aplicables a todos los experimentos, incluso si son cápsulas a bajas temperaturas o si llevan recubrimientos antipermeación. Desde un punto de vista de seguridad, el conocimiento de la cantidad de tritio que está siendo transportada con el gas de purga puede ser usado para detectar de ciertos problemas que puedan estar sucediendo en el módulo como por ejemplo, la rotura de una cápsula. Además, es necesario conocer el balance de tritio de la instalación. Las pérdidas esperadas el refrigerante y la celda caliente de IFMIF se pueden considerar despreciables para condiciones normales de funcionamiento. Los cálculos termohidráulicos se han realizado con el objetivo de optimizar el diseño de las cápsulas experimentales y el LBVM de manera que se pueda cumplir el principal requisito del módulo que es llevar a cabo los experimentos a temperaturas comprendidas entre 300-550ºC. Para ello, se ha dimensionado la refrigeración necesaria del módulo y evaluado la geometría de las cápsulas, tubos experimentales y la zona experimental del contenedor. Como consecuencia de los análisis realizados, se han elegido cápsulas y tubos cilíndricos instalados en compartimentos cilíndricos debido a su buen comportamiento mecánico (las tensiones debidas a la presión de los fluidos se ven reducidas significativamente con una geometría cilíndrica en lugar de prismática) y térmico (uniformidad de temperatura en las paredes de los tubos y cápsulas). Se han obtenido campos de presión, temperatura y velocidad en diferentes zonas críticas del módulo concluyendo que la presente propuesta es factible. Cabe destacar que el uso de códigos fluidodinámicos (e.g. ANSYS-CFX, utilizado en esta tesis) para el diseño de cápsulas experimentales de IFMIF no es directo. La razón de ello es que los modelos de turbulencia tienden a subestimar la temperatura de pared en mini canales de helio sometidos a altos flujos de calor debido al cambio de las propiedades del fluido cerca de la pared. Los diferentes modelos de turbulencia presentes en dicho código han tenido que ser estudiados con detalle y validados con resultados experimentales. El modelo SST (del inglés, “Shear Stress Transport Model”) para turbulencia en transición ha sido identificado como adecuado para simular el comportamiento del helio de refrigeración y la temperatura en las paredes de las cápsulas experimentales. Con la geometría propuesta y los valores principales de refrigeración y purga definidos, se ha analizado el comportamiento mecánico de cada uno de los tubos experimentales que contendrá el módulo. Los resultados de tensiones obtenidos, han sido comparados con los valores máximos recomendados en códigos de diseño estructural como el SDC-IC (del inglés, “Structural Design Criteria for ITER Components”) para así evaluar el grado de protección contra el colapso plástico. La conclusión del estudio muestra que la propuesta es mecánicamente robusta. El LBVM implica el uso de metales líquidos y la generación de tritio además del riesgo asociado a la activación neutrónica. Por ello, se han estudiado los riesgos asociados al uso de metales líquidos y el tritio. Además, se ha incluido una evaluación preliminar de los riesgos radiológicos asociados a la activación de materiales y el calor residual en el módulo después de la irradiación así como un escenario de pérdida de refrigerante. Los riesgos asociados al módulo de naturaleza convencional están asociados al manejo de metales líquidos cuyas reacciones con aire o agua se asocian con emisión de aerosoles y probabilidad de fuego. De entre los riesgos nucleares destacan la generación de gases radiactivos como el tritio u otros radioisótopos volátiles como el Po-210. No se espera que el módulo suponga un impacto medioambiental asociado a posibles escapes. Sin embargo, es necesario un manejo adecuado tanto de las cápsulas experimentales como del módulo contenedor así como de las líneas de purga durante operación. Después de un día de después de la parada, tras un año de irradiación, tendremos una dosis de contacto de 7000 Sv/h en la zona experimental del contenedor, 2300 Sv/h en la cápsula y 25 Sv/h en el LiPb. El uso por lo tanto de manipulación remota está previsto para el manejo del módulo irradiado. Por último, en esta tesis se ha estudiado también las posibilidades existentes para la fabricación del módulo. De entre las técnicas propuestas, destacan la electroerosión, soldaduras por haz de electrones o por soldadura láser. Las bases para el diseño final del LBVM han sido pues establecidas en el marco de este trabajo y han sido incluidas en el diseño intermedio de IFMIF, que será desarrollado en el futuro, como parte del diseño final de la instalación IFMIF. ABSTRACT Nuclear fusion is, today, an alternative energy source to which the international community devotes a great effort. The goal is to generate 10 to 50 times more energy than the input power by means of fusion reactions that occur in deuterium (D) and tritium (T) plasma at two hundred million degrees Celsius. In the future commercial reactors it will be necessary to breed the tritium used as fuel in situ, by the reactor itself. This constitutes a step further from current experimental machines dedicated mainly to the study of the plasma physics. Therefore, tritium, in fusion reactors, will be produced in the so-called breeder blankets whose primary mission is to provide neutron shielding, produce and recover tritium and convert the neutron energy into heat. There are different concepts of breeding blankets that can be separated into two main categories: solids or liquids. The former are based on ceramics containing lithium as Li2O , Li4SiO4 , Li2TiO3 , Li2ZrO3 and Be, used as a neutron multiplier, required to achieve the required amount of tritium. The liquid concepts are based on molten salts or liquid metals as pure Li, LiPb, FLIBE or FLINABE. These blankets use, as neutron multipliers, Be or Pb (in the case of the concepts based on LiPb). Proposed structural materials comprise various options, always with low activation characteristics, as low activation ferritic-martensitic steels, vanadium alloys or even SiCf/SiC. Each concept of breeding blanket has specific challenges that will be studied in the experimental reactor ITER (International Thermonuclear Experimental Reactor). However, ITER cannot answer questions associated to material damage and the effect of neutron radiation in the different breeding blankets functions and performance. As a reference, the first wall of a fusion reactor of 4000 MW will receive about 30 dpa / year (values for Fe-56) , while values expected in ITER would be <10 dpa in its entire lifetime. Consequently, the irradiation effects on candidate materials for fusion reactors will be studied in IFMIF (International Fusion Material Irradiation Facility). This thesis fits in the framework of the bilateral agreement among Europe and Japan which is called “Broader Approach Agreement “(BA) (2007-2017) where Spain plays a key role. These projects, complementary to ITER, are mainly IFMIF and the fusion facility JT-60SA. The purpose of this thesis is the design of an irradiation module to test candidate materials for breeding blankets in IFMIF, the so-called Liquid Breeder Validation Module (LBVM). This proposal is born from the fact that this option was not considered in the conceptual design of the facility. As a first step, in order to study the feasibility of this proposal, neutronic calculations have been performed to estimate irradiation parameters in different materials foreseen for liquid breeding blankets. Various functional materials were considered: Fe (base of structural materials), SiC (candidate material for flow channel inserts, SiO2 (candidate for antipermeation coatings), CaO (candidate for insulating coatings), Al2O3 (candidate for antipermeation and insulating coatings) and AlN (candidate for insulation coating material). For each material, the most significant irradiation parameters have been calculated (dpa, H/dpa and He/dpa) in different positions of IFMIF. These values were compared to those expected in the first wall and breeding zone of a fusion reactor. For this exercise, a HCLL (Helium Cooled Lithium Lead) type was selected as it is one of the most promising options. In addition, estimated values were also compared with those obtained in a fast fission reactor since most of existing irradiations have been made in these installations. The main conclusion of this study is that the medium flux area of IFMIF offers a good irradiation environment to irradiate functional materials for liquid breeding blankets. The obtained ratios of H/dpa and He/dpa are very similar to those expected in the most irradiated areas of a fusion reactor. Moreover, with the aim of bringing the values further close, the use of a W moderator is proposed to be used only in some experimental campaigns (as obviously, the total amount of dpa decreases). The values of ratios obtained for a fission reactor, much lower than in a fusion reactor, reinforce the need of LBVM for IFMIF. Having demonstrated the suitability of IFMIF to irradiate functional materials for liquid breeding blankets, and an analysis of the main problems associated to each type of liquid breeding blanket, also presented in this thesis, three different experiments are proposed as basis for the design of the LBVM. These experiments are dedicated to the needs of a blanket HCLL type although the applicability of the module for other blankets is also discussed. Therefore, the experimental capability of the module is focused on the study of the behavior of the eutectic alloy LiPb, tritium permeation, corrosion and material compatibility. For each of the experiments proposed an experimental scheme is given explaining the different module conditions and defining the required instrumentation to control and monitor the experimental capsules. In order to carry out the proposed experiments, the LBVM is proposed, located in the medium flux area of the IFMIF hot cell, with capability of up to 16 experimental capsules. Each capsule (24-22 mm of diameter, 80 mm high) will contain the eutectic allow LiPb (up to 50 mm of capsule high) in contact with different material specimens. They will be supported inside rigs or steel pipes. Helium will be used as purge gas, to sweep the tritium generated in the eutectic and permeated through the capsule walls (continuously, during irradiation). These tubes, will be installed in a steel container providing support and cooling for the tubes and hence the inner experimental capsules. The experimental data will consist of on line monitoring signals and the analysis of purge gas by the tritium measurement station. In addition to the experimental signals, the module will produce signals having a safety function and therefore playing a major role in the operation of the module. For an adequate operation of the capsules and to control its temperature, each capsule will be equipped with an electrical heater so the module will to be connected to an electrical power supply. The technical justification behind the dimensioning of each of these parts forming the module is presented supported by tritium transport calculations, thermalhydraulic and structural analysis. One of the main conclusions of the tritium transport calculations is that the measure of the permeated tritium is perfectly achievable by commercial ionization chambers and proportional counters with sensitivity of 10-9 Bq/m3. The results are applicable to all experiments, even to low temperature capsules or to the ones using antipermeation coatings. From a safety point of view, the knowledge of the amount of tritium being swept by the purge gas is a clear indicator of certain problems that may be occurring in the module such a capsule rupture. In addition, the tritium balance in the installation should be known. Losses of purge gas permeated into the refrigerant and the hot cell itself through the container have been assessed concluding that they are negligible for normal operation. Thermal hydraulic calculations were performed in order to optimize the design of experimental capsules and LBVM to fulfill one of the main requirements of the module: to perform experiments at uniform temperatures between 300-550ºC. The necessary cooling of the module and the geometry of the capsules, rigs and testing area of the container were dimensioned. As a result of the analyses, cylindrical capsules and rigs in cylindrical compartments were selected because of their good mechanical behavior (stresses due to fluid pressure are reduced significantly with a cylindrical shape rather than prismatic) and thermal (temperature uniformity in the walls of the tubes and capsules). Fields of pressure, temperature and velocity in different critical areas of the module were obtained concluding that the proposal is feasible. It is important to mention that the use of fluid dynamic codes as ANSYS-CFX (used in this thesis) for designing experimental capsules for IFMIF is not direct. The reason for this is that, under strongly heated helium mini channels, turbulence models tend to underestimate the wall temperature because of the change of helium properties near the wall. Therefore, the different code turbulence models had to be studied in detail and validated against experimental results. ANSYS-CFX SST (Shear Stress Transport Model) for transitional turbulence model has been identified among many others as the suitable one for modeling the cooling helium and the temperature on the walls of experimental capsules. Once the geometry and the main purge and cooling parameters have been defined, the mechanical behavior of each experimental tube or rig including capsules is analyzed. Resulting stresses are compared with the maximum values recommended by applicable structural design codes such as the SDC- IC (Structural Design Criteria for ITER Components) in order to assess the degree of protection against plastic collapse. The conclusion shows that the proposal is mechanically robust. The LBVM involves the use of liquid metals, tritium and the risk associated with neutron activation. The risks related with the handling of liquid metals and tritium are studied in this thesis. In addition, the radiological risks associated with the activation of materials in the module and the residual heat after irradiation are evaluated, including a scenario of loss of coolant. Among the identified conventional risks associated with the module highlights the handling of liquid metals which reactions with water or air are accompanied by the emission of aerosols and fire probability. Regarding the nuclear risks, the generation of radioactive gases such as tritium or volatile radioisotopes such as Po-210 is the main hazard to be considered. An environmental impact associated to possible releases is not expected. Nevertheless, an appropriate handling of capsules, experimental tubes, and container including purge lines is required. After one day after shutdown and one year of irradiation, the experimental area of the module will present a contact dose rate of about 7000 Sv/h, 2300 Sv/h in the experimental capsules and 25 Sv/h in the LiPb. Therefore, the use of remote handling is envisaged for the irradiated module. Finally, the different possibilities for the module manufacturing have been studied. Among the proposed techniques highlights the electro discharge machining, brazing, electron beam welding or laser welding. The bases for the final design of the LBVM have been included in the framework of the this work and included in the intermediate design report of IFMIF which will be developed in future, as part of the IFMIF facility final design.

Estudio empírico de la influencia de la experiencia y del conocimiento del dominio del analista en la efectividad de la educción de requisitos

Contexto: La presente tesis doctoral se enmarca en la actividad de educción de los requisitos. La educción de requisitos es generalmente aceptada como una de las actividades más importantes dentro del proceso de Ingeniería de Requisitos, y tiene un impacto directo en la calidad del software. Es una actividad donde la comunicación entre los involucrados (analistas, clientes, usuarios) es primordial. La efectividad y eficacia del analista en la compresión de las necesidades de clientes y usuarios es un factor crítico para el éxito del desarrollo de software. La literatura se ha centrado principalmente en estudiar y comprender un conjunto específico de capacidades o habilidades personales que debe poseer el analista para realizar de forma efectiva la actividad de educción. Sin embargo, existen muy pocos trabajos que han estudiado dichas capacidades o habilidades empíricamente. Objetivo: La presente investigación tiene por objetivo estudiar el efecto de la experiencia, el conocimiento acerca del dominio y la titulación académica que poseen los analistas en la efectividad del proceso de educción de los requisitos, durante los primeros contactos del analista con el cliente. Método de Investigación: Hemos ejecutado 8 estudios empíricos entre cuasi-experimentos (4) y experimentos controlados (4). Un total de 110 sujetos experimentales han participado en los estudios, entre estudiantes de post-grado de la Escuela Técnica Superior de Ingenieros Informáticos de la Universidad Politécnica de Madrid y profesionales. La tarea experimental consistió en realizar sesiones de educción de requisitos sobre uno o más dominios de problemas (de carácter conocido y desconocido para los sujetos). Las sesiones de educción se realizaron empleando la entrevista abierta. Finalizada la entrevista, los sujetos reportaron por escrito toda la información adquirida. Resultados: Para dominios desconocidos, la experiencia (entrevistas, requisitos, desarrollo y profesional) del analista no influye en su efectividad. En dominios conocidos, la experiencia en entrevistas (r = 0.34, p-valor = 0.080) y la experiencia en requisitos (r = 0.22, p-valor = 0.279), ejercen un efecto positivo. Esto es, los analistas con más años de experiencia en entrevistas y/o requisitos tienden a alcanzar mejores efectividades. Por el contrario, la experiencia en desarrollo (r = -0.06, p-valor = 0.765) y la experiencia profesional (r = -0.35, p-valor = 0.077), tienden a ejercer un efecto nulo y negativo, respectivamente. En lo que respecta al conocimiento acerca del dominio del problema que poseen los analistas, ejerce un moderado efecto positivo (r=0.31), estadísticamente significativo (p-valor = 0.029) en la efectividad de la actividad de educción. Esto es, los analistas con conocimiento tienden a ser más efectivos en los dominios de problema conocidos. En lo que respecta a la titulación académica, por falta de diversidad en las titulaciones académicas de los sujetos experimentales no es posible alcanzar una conclusión. Hemos podido explorar el efecto de la titulación académica en sólo dos cuasi-experimentos, sin embargo, nuestros resultados arrojan efectos contradictorios (r = 0.694, p-valor = 0.51 y r = -0.266, p-valor = 0.383). Además de las variables estudiadas indicadas anteriormente, hemos confirmado la existencia de variables moderadoras que afectan a la actividad de educción, tales como el entrevistado o la formación. Nuestros datos experimentales confirman que el entrevistado es un factor clave en la actividad de educción. Estadísticamente ejerce una influencia significativa en la efectividad de los analistas (p-valor= 0.000). La diferencia entre entrevistar a uno u otro entrevistado, en unidades naturales, varía entre un 18% - 23% en efectividad. Por otro lado, la formación en requisitos aumenta considerablemente la efectividad de los analistas. Los sujetos que realizaron la educción de requisitos después de recibir una formación específica en requisitos tienden a ser entre un 12% y 20% más efectivos que aquellos que no la recibieron. El efecto es significativo (p-valor = 0.000). Finalmente, hemos observado tres hechos que podrían influir en los resultados de esta investigación. En primer lugar, la efectividad de los analistas es diferencial dependiendo del tipo de elemento del dominio. En dominios conocidos, los analistas con experiencia tienden a adquirir más conceptos que los analistas noveles. En los dominios desconocidos, son los procesos los que se adquieren de forma prominente. En segundo lugar, los analistas llegan a una especie de “techo de cristal” que no les permite adquirir más información. Es decir, el analista sólo reconoce (parte de) los elementos del dominio del problema mencionado. Este hecho se observa tanto en el dominio de problema desconocido como en el conocido, y parece estar relacionado con el modo en que los analistas exploran el dominio del problema. En tercer lugar, aunque los años de experiencia no parecen predecir cuán efectivo será un analista, sí parecen asegurar que un analista con cierta experiencia, en general, tendrá una efectividad mínima que será superior a la efectividad mínima de los analistas con menos experiencia. Conclusiones: Los resultados obtenidos muestran que en dominios desconocidos, la experiencia por sí misma no determina la efectividad de los analistas de requisitos. En dominios conocidos, la efectividad de los analistas se ve influenciada por su experiencia en entrevistas y requisitos, aunque sólo parcialmente. Otras variables influyen en la efectividad de los analistas, como podrían ser las habilidades débiles. El conocimiento del dominio del problema por parte del analista ejerce un efecto positivo en la efectividad de los analistas, e interacciona positivamente con la experiencia incrementando aún más la efectividad de los analistas. Si bien no fue posible obtener conclusiones sólidas respecto al efecto de la titulación académica, si parece claro que la formación específica en requisitos ejerce una importante influencia positiva en la efectividad de los analistas. Finalmente, el analista no es el único factor relevante en la actividad de educción. Los clientes/usuarios (entrevistados) también juegan un rol importante en el proceso de generación de información. ABSTRACT Context: This PhD dissertation addresses requirements elicitation activity. Requirements elicitation is generally acknowledged as one of the most important activities of the requirements process, having a direct impact in the software quality. It is an activity where the communication among stakeholders (analysts, customers, users) is paramount. The analyst’s ability to effectively understand customers/users’ needs represents a critical factor for the success of software development. The literature has focused on studying and comprehending a specific set of personal skills that the analyst must have to perform requirements elicitation effectively. However, few studies have explored those skills from an empirical viewpoint. Goal: This research aims to study the effects of experience, domain knowledge and academic qualifications on the analysts’ effectiveness when performing requirements elicitation, during the first stages of analyst-customer interaction. Research method: We have conducted eight empirical studies, quasi-experiments (four) and controlled experiments (four). 110 experimental subjects participated, including: graduate students with the Escuela Técnica Superior de Ingenieros Informáticos of the Universidad Politécnica de Madrid, as well as researchers and professionals. The experimental tasks consisted in elicitation sessions about one or several problem domains (ignorant and/or aware for the subjects). Elicitation sessions were conducted using unstructured interviews. After each interview, the subjects reported in written all collected information. Results: In ignorant domains, the analyst’s experience (interviews, requirements, development and professional) does not influence her effectiveness. In aware domains, interviewing experience (r = 0.34, p-value = 0.080) and requirements experience (r = 0.22, p-value = 0.279), make a positive effect, i.e.: the analysts with more years of interviewing/requirements experience tend to achieve higher effectiveness. On the other hand, development experience (r = -0.06, p-value = 0.765) and professional experience (r = -0.35, p-value = 0.077) tend to make a null and negative effect, respectively. On what regards the analyst’s problem domain knowledge, it makes a modest positive effect (r=0.31), statistically significant (p-value = 0.029) on the effectiveness of the elicitation activity, i.e.: the analysts with tend to be more effective in problem domains they are aware of. On what regards academic qualification, due to the lack of diversity in the subjects’ academic degrees, we cannot come to a conclusion. We have been able to explore the effect of academic qualifications in two experiments; however, our results show opposed effects (r = 0.694, p-value = 0.51 y r = -0.266, p-value = 0.383). Besides the variables mentioned above, we have confirmed the existence of moderator variables influencing the elicitation activity, such as the interviewee and the training. Our data confirm that the interviewee is a key factor in the elicitation activity; it makes statistically significant effect on analysts’ effectiveness (p-value = 0.000). Interviewing one or another interviewee represents a difference in effectiveness of 18% - 23%, in natural units. On the other hand, requirements training increases to a large extent the analysts’ effectiveness. Those subjects who performed requirements elicitation after specific training tend to be 12% - 20% more effective than those who did not receive training. The effect is statistically significant (p-value = 0.000). Finally, we have observed three phenomena that could have an influence on the results of this research. First, the analysts’ effectiveness differs depending on domain element types. In aware domains, experienced analysts tend to capture more concepts than novices. In ignorant domains, processes are identified more frequently. Second, analysts get to a “glass ceiling” that prevents them to acquire more information, i.e.: analysts only identify (part of) the elements of the problem domain. This fact can be observed in both the ignorant and aware domains. Third, experience years do not look like a good predictor of how effective an analyst will be; however, they seem to guarantee that an analyst with some experience years will have a higher minimum effectiveness than the minimum effectiveness of analysts with fewer experience years. Conclusions: Our results point out that experience alone does not explain analysts’ effectiveness in ignorant domains. In aware domains, analysts’ effectiveness is influenced the experience in interviews and requirements, albeit partially. Other variables influence analysts’ effectiveness, e.g.: soft skills. The analysts’ problem domain knowledge makes a positive effect in analysts’ effectiveness; it positively interacts with the experience, increasing even further analysts’ effectiveness. Although we could not obtain solid conclusions on the effect of the academic qualifications, it is plain clear that specific requirements training makes a rather positive effect on analysts’ effectiveness. Finally, the analyst is not the only relevant factor in the elicitation activity. The customers/users (interviewees) play also an important role in the information generation process.

Volunteer Engagement: Does Engagement Predict the Degree of Satisfaction among New Volunteers and the Commitment of Those who have been Active Longer?

This study examines the concept of engagement in samples of volunteers from different non-profit organisations. Study 1 analyzes the psychometric properties of the abbreviated version of the Utrecht Work Engagement Scale (UWES) (Schaufeli, Bakker, & Salanova, 2006a). Two factorial structures are examined: one-dimensional and three-dimensional structures. Based on the Three-Stage Model of Volunteers’ Duration of Service (Chacón, Vecina, & Dávila, 2007), Study 2 investigates the relationship between engagement, volunteer satisfaction, and intention to remain in a sample of new volunteers and the relationship between engagement, organisational commitment, and intention to remain in a sample of veteran volunteers. Moderated mediation analysis is provided using duration of service as a moderator in order to set a splitting point between new and veteran volunteers. The results of the confirmatory factor analysis suggest that the three-factor model fits better to the data. Regarding the structural models, the first one shows that engagement is crucial to volunteer satisfaction during the first stage, while volunteer satisfaction is the key variable in explaining intention to continue. The second structural model shows that engagement reinforces the participant’s commitment to the organisation, while organizational commitment predicts intention to continue. Both models demonstrate a notable decline when samples are changed.

Estudo das relações entre maus tratos na infância, prejuízo em funções executivas e transtornos do comportamento disruptivo em uma amostra comunitária de crianças

Evidências apontam para forte relação independente entre maus tratos na infância, comportamentos disruptivos e prejuízos em funções executivas. No entanto, ainda não é completamente compreendido como estes três fatores se relacionam entre si. Esta pesquisa avaliou a relação entre maus-tratos na infância e transtornos do comportamento disruptivo, testando desempenho em funções executivas como possível mediador e moderador desta relação. A presente pesquisa está inserida no estudo \"Coorte de escolares de alto risco para o desenvolvimento de psicopatologia e resiliência na infância e adolescência - projeto Prevenção\", projeto integrante do Instituto Nacional de Ciência e Tecnologia de Psiquiatria do Desenvolvimento para Infância e Adolescência (INCT-INPD), o qual incluiu 2500 crianças em idade escolar de São Paulo e Porto Alegre (Brasil). As crianças foram extensamente avaliadas com entrevistas diagnósticas, relatos de pais e da própria criança sobre maus tratos e com testes neuropsicológicos. Resultados indicam associação de maus tratos na infância e transtornos do comportamento disruptivo, porém não foi encontrada associação entre maus tratos e funções executivas. Crianças com transtornos do comportamento disruptivo apresentaram pior desempenho em teste específico para avaliação de flexibilidade cognitiva. Desempenho em funções executivas não agiu como mediador ou moderador da associação entre maus tratos e transtornos do comportamento disruptivo. Desta forma, os resultados indicam que a associação entre experiências de maus tratos e transtornos do comportamento disruptivo ocorre independentemente do desempenho em funções executivas. Futuros estudos longitudinais são fundamentais para confirmar estes resultados e elucidar os mecanismos cognitivos envolvidos nesta associação causal

Evolução das doses no ambiente do Reator IEA-R1 e tendências com base nos resultados atuais

O Ipen/Cnen-SP possui um Reator de Pesquisa(IEA-R1) em operação desde 1957. Ele utiliza água leve como blindagem, moderador e como fluido refrigerante, o volume desta piscina é de 273m3. Até 1995 a operação do Reator era descontinua, ou seja, operava diariamente sendo desligado no final do dia, a uma potência de 2,0 MW. A partir daquele ano, após algumas modificações de segurança, o Reator passou a operar de forma continua, ou seja, de segunda-feira a quarta-feira sem ser desligado, totalizando 64 horas semanais. A potência também foi aumentando até 4,5 MW em 2012. Em virtude dessas alterações, a saber, operação contínua e do aumento da potência, as doses dos trabalhadores aumentaram e por isso foram realizados vários estudos para diminui-las. Estudos demonstraram que uma das principais limitações para operação de um reator em potência elevada, provém das radiações gama emitidas pelo sódio-24. Outros elementos como magnésio-27, Alumínio-28, Argônio-51, contribuem de forma considerável para a atividade da água da piscina. A introdução de uma camada de água quente em sua superfície, estável e isenta de elementos radioativos com 1,5m a 2m de espessura constituiria uma blindagem às radiações provenientes dos elementos radioativos dissolvidos na água. Estudos de otimização provaram que a instalação da camada quente não era necessária para o regime e potência atual de operação do Reator, pois outros procedimentos adotados eram mais eficazes. A partir desta decisão o serviço de Proteção Radiológica do Reator IEA-R1, montou um programa de avaliação das doses para certificar-se de que elas se mantinham em valores razoáveis baseados em princípios estabelecidos em normas nacionais e internacionais. O intuito deste trabalho é realizar uma análise das doses individuais dos IOE (Individuo Ocupacionalmente Expostos), considerando as mudanças no regime de operação do Reator e sugerir opções de proteção e segurança, viáveis em primeira instância, para reduzir as doses analisadas, visando se chegar aos níveis de referencia de 3 mSv/ano adotados pela instalação em apreço.

The Effects of Father Absence Due to Divorce: A Systems Interpretation.

In American society, the incidence of divorce continues to rise. In 1974, the estimate was that 40% of all new marriages would end in divorce. When children are involved, the mother usually regains custody. Although the number of children of divorce living with their fathers is increasing, it is still a small percent. In addition, the rate of remarriages is lower when children are involved (Hetherington.et al.,1977). Consequently, a large number of children are being raised in father-absent homes, and indications are that the numbers are increasing. A recent Denver Post article predicted that 50% of all children now being born will spend some of their childhood in a single-parent home. In terms of frequency, the father-absent family is becoming quite common, even "normal," yet it often continues to be considered a "broken" home and, when compared to the two-parent family, an inadequate structure in which to raise healthy children. Since father-absent families are so common these days, this opinion is in need of review.This paper will present a review of the father absence research in three areas: sex role development, cognitive development and personality development. The role of moderator variables will be discussed. And, finally,an open systems model will be proposed as a vehicle to better understand the effects of father absence and as a guide for future research.

Examining the impact of pre-k and kindergarten classroom alignment on school readiness outcomes

This study explored children’s experiences of instructional alignment from prekindergarten to kindergarten and analyzed the impact of those alignment experiences on children’s school readiness outcomes. The study answered the following overarching research question: Does the alignment of children’s learning experiences between prekindergarten and kindergarten impact school readiness outcomes? Three sub-questions drove the research design: (1) How do children’s prekindergarten and kindergarten learning experiences align; (2) To what extent does the alignment of early learning experiences predict children’s school readiness outcomes; and (3) Does the quality of prekindergarten classroom teacher interactions moderate the impact of any PK-K alignment effects? Using cluster analysis and hierarchical linear modeling (HLM) to analyze data from over 1,300 children in the 2009 Head Start Family and Child Experiences Survey (FACES), the study found that children have distinct and definable experiences of PK-K alignment. Results also indicated a disparity in children’s PK-K alignment experiences, with Hispanic/Latino children more likely to attend Head Start programs with poor systems transition practices followed by kindergartens with poor classroom structures. The study found that growth in the use of instructional activity centers from prekindergarten to kindergarten is predictive of better literacy and math outcomes. Findings further suggested that boys, minority students, and children from lower income households are predicted to score lower than girls, white classmates, and higher-income peers across school readiness measures. Findings support the need for equitable transition and alignment practices for children from all racial and ethnic groups. They also argue for an increase in child-directed activity centers in kindergarten. With one exception, the current findings did not support the hypothesis that prekindergarten teacher quality is a moderator of alignment effects on children’s school readiness outcomes. The study presents suggestions for further research.

Examining the relationship among genes, attention bias to emotion, and depression in youth

The investigation of biologically initiated pathways to psychological disorder is critical to advance our understanding of mental illness. Research has suggested that attention bias to emotion may be an intermediate trait for depression associated with biologically plausible candidate genes, such as the serotonin transporter (5-HTTLPR) and catechol-o-methyl-transferase (COMT) genes, yet there have been mixed findings in regards to the precise direction of effects. The experience of recent stressful life events (SLEs) may be an important, yet currently unstudied, moderator of the relationship between genes and attention bias as SLEs have been associated with both gene expression and attention to emotion. Additionally, although attention biases to emotion have been studied as a possible intermediate trait associated with depression, no study has examined whether attention biases within the context of measured genetic risk lead to increased risk for clinical depressive episodes over time. Therefore, this research investigated both whether SLEs moderate the link between genetic risk (5-HTTLPR and COMT) and attention bias to emotion and whether 5-HTTLPR and COMT moderated the relationship between attention biases to emotional faces and clinical depression onset prospectively across 18 months within a large community sample of youth (n= 467). Analyses revealed a differential effect of gene. Youth who were homozygous for the low expressing allele of 5-HTTLPR (S/S) and had experienced more recent SLEs within the last three months demonstrated preferential attention toward negative emotional faces (angry and sad). However, youth who were homozygous for the high expressing COMT genotype (Val/Val) and had experienced more recent SLEs showed attentional avoidance of positive facial expressions (happy). Additionally, youth who avoided negative emotion (i.e., anger) and were homozygous for the S allele of the 5-HTTLPR gene were at greater risk for prospective depressive episode onset. Increased risk for depression onset was specific to the 5-HTTLPR gene and was not found when examining moderation by COMT. These findings highlight the importance of examining risk for depression across multiple levels of analysis, such as combined genetic, environmental, and cognitive risk, and is the first study to demonstrate clear evidence of attention biases to emotion functioning as an intermediate trait predicting depression.

The Impact of Prefrontal Cortex "Warm Up" on Immediate Cognitive Reappraisal Ability in Older Adolescents with Elevated Symptoms of Depression

Cognitive Reappraisal (CR) is a central component of Cognitive Behavioral Therapy for adolescent depression. Yet, previous research indicates that a brain region highly associated with successful CR in adults, the Prefrontal Cortex (PFC), is not fully developed until early adulthood. Thus, there is growing concern that CBT interventions directed at building CR abilities in depressed teens might be constrained by PFC immaturity. However, CR is an effective strategy for regulating affect. The current study evaluated an intervention aimed at enhancing CR performance through PFC “warm up” with a working memory task. Additionally, the study examined moderators of intervention response, as well as cognitive correlates of self-reported CR use. Participants included 48 older adolescents (mean age=19.1, 89% female) with elevated symptoms of depression who were randomly assigned to a lab-based WM or control activity followed by a CR task. Overall, results failed to support the effectiveness of “warm up” to augment CR performance. However, current level of depression predicted negative bias and sadness ratings after CR instructions, and this effect was qualified by an interaction with condition. The moderator analysis showed that depressive symptoms interacted with condition such that in the control condition, participants with higher depressive symptoms had significantly lower negative bias scores than individuals with lower depressive symptoms, but this pattern was not found in the experimental condition. Contrary to hypotheses, history of depression did not moderate treatment response. Additional analyses explored alternative explanations for the lack of intervention effects. There was some evidence to suggest that the WM task was frustrating and cognitively taxing. However, irritation scores and overall WM task accuracy did not predict subsequent CR performance. Lastly, multiple cognitive variables emerged as correlates of self-reported CR use, with cognitive flexibility contributing unique variance to self-reported CR use. Results pointed to new directions for improving CR performance among youth with elevated symptoms of depression.

Recommendation of Elisha Parmele as a candidate for ministry, July 3, 1781

This document describes Parmele's examination before an association of ministers in Berkshire County and records their subsequent decision to recommend him as a candidate for "the gospel ministry." Stephen West was the moderator of this meeting, and Daniel Collens was its scribe.