Thermal diffusion profile by NRA of Deuterium implanted in solid breeder blanket materials

This paper studies the relationship between aging, physical changes and the results of non-destructive testing of plywood. 176 pieces of plywood were tested to analyze their actual and estimated density using non-destructive methods (screw withdrawal force and ultrasound wave velocity) during a laboratory aging test. From the results of statistical analysis it can be concluded that there is a strong relationship between the non-destructive measurements carried out, and the decline in the physical properties of the panels due to aging. The authors propose several models to estimate board density. The best results are obtained with ultrasound. A reliable prediction of the degree of deterioration (aging) of board is presented. Breeder blanket materials have to produce tritium from lithium while fulfilling several strict conditions. In particular, when dealing with materials to be applied in fusion reactors, one of the key questions is the study of light ions retention, which can be produced by transmutation reactions and/or introduced by interaction with the plasma. In ceramic breeders the understanding of the hydrogen isotopes behaviour and specially the diffusion of tritium to the surface is crucial. Moreover the evolution of the microstructure during irradiation with energetic ions, neutrons and electrons is complex because of the interaction of a high number of processes.

Studies of a Self Cooled Lead Lithium blanket for HiPER Reactor

Within the frame of the HiPER reactor, we propose and study a Self Cooled Lead Lithium blanket with two different cooling arrangements of the system First Wall – Blanket for the HiPER reactor: Integrated First Wall Blanket and Separated First Wall Blanket. We compare the two arrangements in terms of power cycle efficiency, operation flexibility in out-off-normal situations and proper cooling and acceptable corrosion. The Separated First Wall Blanket arrangement is superior in all of them, and it is selected as the advantageous proposal for the HiPER reactor blanket. However, it still has to be improved from the standpoint of proper cooling and corrosion rates

Markov blanket-based approach for learning multi-dimensional Bayesian network classifiers: An application to predict the European Quality of Life-5 Dimensions (EQ-5D) from the 39-item Parkinson's Disease Questionnaire (PDQ-39)

Multi-dimensional Bayesian network classifiers (MBCs) are probabilistic graphical models recently proposed to deal with multi-dimensional classification problems, where each instance in the data set has to be assigned to more than one class variable. In this paper, we propose a Markov blanket-based approach for learning MBCs from data. Basically, it consists of determining the Markov blanket around each class variable using the HITON algorithm, then specifying the directionality over the MBC subgraphs. Our approach is applied to the prediction problem of the European Quality of Life-5 Dimensions (EQ-5D) from the 39-item Parkinson’s Disease Questionnaire (PDQ-39) in order to estimate the health-related quality of life of Parkinson’s patients. Fivefold cross-validation experiments were carried out on randomly generated synthetic data sets, Yeast data set, as well as on a real-world Parkinson’s disease data set containing 488 patients. The experimental study, including comparison with additional Bayesian network-based approaches, back propagation for multi-label learning, multi-label k-nearest neighbor, multinomial logistic regression, ordinary least squares, and censored least absolute deviations, shows encouraging results in terms of predictive accuracy as well as the identification of dependence relationships among class and feature variables.

Self Cooled Lead Lithium blanket and reactor for HiPER

Within the frame of the HiPER reactor, we propose and study a Self Cooled Lead Lithium blanket with two different cooling arrangements of the system First Wall – Blanket for the HiPER reactor: Integrated First Wall Blanket and Separated First Wall Blanket. We compare the two arrangements in terms of power cycle efficiency, operation flexibility in out-off-normal situations and proper cooling and acceptable corrosion. The Separated First Wall Blanket arrangement is superior in all of them, and it is selected as the advantageous proposal for the HiPER reactor blanket. However, it still has to be improved from the standpoint of proper cooling and corrosion rates

Neutronics and activation of the preliminary reacion chamber of HiPER reactor based in a SCLL blanket

Neutronics and activation of the preliminary reacion chamber of HiPER reactor based in a SCLL blanket

D-depth profiling in as-implanted and annealed Li-based breeder blanket ceramics

In future power plants (i.e. DEMO), the nuclear fusion of hydrogen isotopes will be used for energy production. The behaviour of hydrogen isotopes in lithium-enriched ceramics for breeder blankets (BBs) is one of the most important items to be understood. In this paper we present the chemical, microstructural and morphological features of Li4SiO4, Li2TiO3 and a third ceramic candidate with a higher Li:Si proportion (3:1), implanted with D at an energy of 100 keV and at room temperature at a fluence of 1 × 1017 cm−2. The D depth-profile in as-implanted and annealed ceramics (at T ⩽ 200 °C) was characterised by Resonance Nuclear Reaction Analysis (RNRA). The RNRA data indicate that the total amount of D is retained at room temperature, while annealing at 100 °C promotes D release and annealing at T ⩾ 150 °C drives D to completely desorb from all the studied ceramics. D release will be discussed as a function of the microstructurural and morphological features of each material.

Neutronics and activation of the preliminary reaction chamber of HiPER reactor based in a SCLL blanket

The HiPER reactor design is exploring different reaction chambers. In this study, we tackle the neutronicsand activation studies of a preliminary reaction chamber based in the following technologies: unpro-tected dry wall for the First Wall, self-cooled lead lithium blanket, and independent low activation steelVacuum Vessel. The most critical free parameter in this stage is the blanket thickness, as a function ofthe6Li enrichment. After a parametric study, we select for study both a ?thin? and ?thick? blanket, with?high? and ?low?6Li enrichment respectively, to reach a TBR = 1.1. To help to make a choice, we com-pute, for both blanket options, in addition to the TBR, the energy amplification factor, the tritium partialpressure, the203Hg and210Po total activity in the LiPb loop, and the Vacuum Vessel thickness requiredto guarantee the reweldability during its lifetime. The thin blanket shows a superior performance in thesafety related issues and structural viability, but it operates at higher6Li enrichment. It is selected forfurther improvements. The Vacuum Vessel shows to be unviable in both cases, with the thickness varyingbetween 39 and 52 cm. Further chamber modifications, such as the introduction of a neutron reflector,are required to exploit the benefits of the thin blanket with a reasonable Vacuum Vessel.

Simulating the remote handling of the blanket segments in DEMO fusion reactor with thermo-mechanical meshfree multibody dynamics

The present study shows a first approach to the simulation of the remote handling oper- ation which takes into account the thermal and flexible behavior of the blanket segments and its implications on the remote handling equipment, in order to validate and improve its design.

IFMIF suitability for evaluation of fusion functional materials

The International FusionMaterials Irradiation Facility (IFMIF) is a future neutron source based on the D-Li stripping reaction, planned to test candidate fusionmaterials at relevant fusion irradiation conditions. During the design of IFMIF special attention was paid to the structural materials for the blanket and first wall, because they will be exposed to the most severe irradiation conditions in a fusion reactor. Also the irradiation of candidate materials for solid breeder blankets is planned in the IFMIF reference design. This paper focuses on the assessment of the suitability of IFMIF irradiation conditions for testing functionalmaterials to be used in liquid blankets and diagnostics systems, since they are been also considered within IFMIF objectives. The study has been based on the analysis and comparison of the main expected irradiation parameters in IFMIF and DEMO reactor.

Liquid lead and Lithium. A Comprehensive molecular dynamics study

Pb17Li is today a reference breeder material in diverse fusion R&D programs worldwide. One of the main issues in these programs is the problem of liquid metals breeder blanket behavior. Structural material of the blanket should meet high requirements because of extreme operating conditions. Therefore the knowledge of eutectic properties like optimal composition, physical and thermodynamic behavior or diffusion coefficients of Tritium are extremely necessary for current designs. In particular, the knowledge of the function linking the tritium concentration dissolved in liquid materials with the tritium partial pressure at a liquid/gas interface in equilibrium, CT=f(PT), is of basic importance because it directly impacts all functional properties of a blanket determining: tritium inventory, tritium permeation rate and tritium extraction efficiency. Nowadays, understanding the structure and behavior of this compound is a real goal in fusion engineering and materials science. Simulations of liquids can provide much information to the community; not only supplementing experimental data, but providing new tests of theories and ideas, making specific predictions that require experimental tests, and ultimately helping to lead to the deeper understanding and better predictive behavior.

New simulations to qualify eutectic lithium-lead as breeder material

Pb17Li is today a reference breeder material in diverse fusion R&D programs worldwide. One of the main issues is the problem of liquid metals breeder blanket behavior. The knowledge of eutectic properties like optimal composition, physical and thermodynamic behavior or diffusion coefficients of Tritium are extremely necessary for current designs. In particular, the knowledge of the function linking the tritium concentration dissolved in liquid materials with the tritium partial pressure at a liquid/gas interface in equilibrium, CT =f(PT ), is of basic importance because it directly impacts all functional properties of a blanket determining: tritium inventory, tritium permeation rate and tritium extraction efficiency. Nowadays, understanding the structure and behavior of this compound is a real goal in fusion engineering and materials science. Atomistic simulations of liquids can provide much information; not only supplementing experimental data, but providing new tests of theories and ideas, making specific predictions that require experimental tests, and ultimately helping to a deeper understanding

Silica final lenses under HiPER laser fusion reactor operation conditions

We have studied the thermo-mechanical response and atomistic degradation of final lenses in HiPER project. Final silica lenses are squares of 75 × 75 cm2 with a thickness of 5 cm. There are two scenarios where lenses are located at 8 m from the centre: •HiPER 4a, bunches of 100 shots (maximum 5 DT shots <48 MJ at ≈0.1 Hz). No blanket in chamber geometry. •HiPER 4b, continuous mode with shots ≈50 MJ at 10 Hz to generate 0.5 GW. Liquid metal blanket in chamber design.

Ion Beam Analysis of He-implanted fusion solid breedes

Introduction Lithium-based ceramics (silicates, titanates, ?) possess a series of advantages as alternative over liquid lithium and lithium-lead alloys for fusion breeders. They have a sufficient lithium atomic density (up to 540 kg*m-3), high temperature stability (up to 1300 K), and good chemical compatibility with structural materials. Nevertheless, few research is made on the diffusion behavior of He and H isotopes through polycrystalline structures of porous ceramics which is crucial in order to understand the mobility of gas coolants as well as, the release of tritium. Moreover, in the operating conditions of actual breeder blanket concepts, the extraction rate of the helium produced during lithium transmutation can be affected by the composition and the structure of the near surface region modifying the performance of BB materials

Aplicación de un tratamiento biológico a las aguas residuales provenientes de una destilería de alcohol de caña, utilizando un reactor UASB

En este trabajo se llevó a cabo el tratamiento de vinazas mediante dos tecnologías anaerobias. Se dividió en cuatro estudios técnicos. El primero fue el arranque y estabilización del reactor UASB (Upflow Anaerobic Sludge Blanket), en dónde se evaluó la estabilización mediante la eficiencia de remoción de DQO y la granulación del lodo. El segundo estudio evaluó el rendimiento del reactor UASB frente a diferentes Cva. El tercer estudio evaluó el efecto del TRH sobre la eficiencia del reactor UASB, y el cuarto de ellos fue evaluar el rendimiento del RABF (Reactor Anaerobio de Biomasa Fija). El reactor UASB de 2,6 L de capacidad, fue arrancado por lotes, con seis ensayos utilizando vinaza como sustrato. Se obtuvieron eficiencias de remoción en DQO en un rango de 79-91%, en los seis lotes. Se obtuvo formación de gránulos con diámetro (Ø) de 0,85-1,15 mm y un coeficiente de esfericidad (Є) de 0,7-0,77. Se logró la granulación de lodos tras 2 meses de operación. Alcanzada la estabilización del reactor UASB, se siguió una operación en flujo continuo. Las Cva probadas de 1, 2, 4 y 6 gDQO/L.d para el reactor UASB dan una respuesta bastante favorable con respecto al rendimiento del reactor, ya que presento eficiencias de remoción de DQOs del 51 hasta el 76%, eficiencias similares a los reportados por la literatura. En el estudio de TRH se operó con Cva de 6 gDQO/L.d y los TRH fueron de 24, 12 ,5 ,3 y 1 día. El % de eliminación de DQO fue de 51, 60, 57, 60 y 63 % remoción en DQOsoluble, respectivamente. Se alcanzó una producción de biogás máximo de 5.283 ml/d, pero al reducir el TRH se observó una reducción proporcional del volumen total de biogás. El %CH4 contenido en el biogás aumento al disminuir el TRH, reflejando valores de 80 al 92 % de CH4. El RABF con un volumen de 8,2 L, utilizo tubos de plástico corrugado como medio de soporte para las bacterias. Se aplicaron las siguientes Cva; 0,5, 1, 3 y 6 gDQO/L.d. El reactor RABF presento una excelente remoción de la materia orgánica (80% DQOs), una producción de biogás estable, y un contenido en CH4 del biogás muy interesante. Sin embargo, para una Cva superior a 3 gDQO/L.d empezó un comportamiento inesperado de reducción de capacidad. Las condiciones hidrodinámicas del reactor UASB son decisivas para la formación de los gránulos, condición previa para iniciar el flujo continuo. Al operar el reactor UASB en modo continuo, se pudo evaluar las mejores condiciones de operación para este tipo de residuo (vinaza). La Cva de 6 gDQO/L.d para el reactor UASB alimentado con vinaza bruta representa el límite de su capacidad. Sin embargo, al aumentar la Cva se genera una mayor producción de biogás y metano. La eficiencia de remoción de la DQO soluble es independiente del TRH, para una Cva de 6 g DQO/L•d y las condiciones de TRH probadas (24, 12, 5, 3 y 1 días). Los valores de remoción de DQO alcanzados son un poco superior a los valores de biodegradabilidad anaerobia de la vinaza observados de 50 %. De manera general, la reducción del TRH o bien la dilución de la vinaza no presenta un efecto significativo sobre la remoción de la materia orgánica soluble, pero si lo presenta en la remoción de sulfatos reduciendo indirectamente su toxicidad. El soporte termoplástico inoculado en el RABF y alimentado con vinaza bruta, actuó como un filtro, además de obtener buenos resultados en eliminación de DQO, pero dada las dimensiones y la altura del relleno se frena la evacuación del metano. This work was carried out by treatment vinasses with two anaerobic technologies. It was divided into four technical studies. The first was the start up and stabilization Upflow Anaerobic Sludge Blanket (UASB) reactor, where the stability was evaluated by the removal efficiency of COD and sludge granulation. The second study evaluated the performance of the UASB reactor against different OLR. The third study evaluated the effect of HRT on the efficiency of the UASB reactor, and the fourth of which was evaluate the performance Fixed Biomass Anaerobic (FBA) reactor. The UASB reactor of 2,6 L capacity, was started in batch, with six assays using vinasse as substrate. Were obtained removal efficiencies of COD in the range of 79- 91% in the six batches. Forming granules were obtained with a diameter (Ø) of 0,85- 1,15 mm and sphericity coefficient (Є) of 0,7 to 0,77. Sludge granulation was achieved after 2 months of operation. Once stabilization is achieved of the UASB reactor, it was followed by a continuous flow operation. The OLR tested 1, 2, 4 and 6 gCOD/L.d for UASB reactor gives a very favorable response regarding the performance of the reactor, as presented COD5 removal efficiencies of 51 to 76%, similar efficiencies those reported in the literature The HRT study was operated with an OLR of 6 gCOD/L.d and HRT were 24, 12, 5, 3 and 1 day. The removal efficiency was 51, 60, 57, 60 and 63% in soluble COD, respectively. It reached a maximum biogas production of 5.283 ml / d, but by reducing the HRT showed a proportional reduction in the total volume of biogas. The %CH4 content in the biogas increased with decreasing TRH, reflecting values of 80 to 92% of CH4. The FBA reactor with a volume of 8,2 L, used corrugated plastic tubes as carrier for bacteria transportation. The following OLR was applied, 0,5, 1, 3 and 6 gCOD/L.d. The FBA reactor showed an excellent removal of organic matter (80% CODS), a stable biogas production, and CH4 content very interesting. However, for more than 3 gCOD/L.d OLR began with unexpected behavior of capacity reduction. The UASB reactor hydrodynamic conditions are decisive for the formation of the granules, precondition to start the continuous flow. By operating the UASB reactor in continuous mode, it was possible to evaluate the best operating conditions for this type of waste (vinasse). The OLR of 6 gCOD/L.d for the UASB reactor fed with raw vinasse represents the limit of its capacity. However, with increasing OLR creates increased biogas production and methane. The removal efficiency of soluble COD is independent of HRT for OLR of 6 gCOD/L.d and HRT conditions tested (24, 12, 5, 3 and 1 day). COD Removal values achieved are slightly higher than the values of the vinasse anaerobic biodegradability of observed at 50%. Generally, reduction of HRT or vinasse dilution does not present a significant effect on the removal of the soluble organic matter; however if it occurs in the removal of sulfate reducing indirectly its toxicity. The thermoplastic support inoculated in FBA reactor and fed with raw vinasse, acted as a filter, in addition to obtaining good results in COD removal, but given the size and height of the filling slows evacuation of methane.

Simulación atomística de metales líquidos y aleaciones para reactores de fusión nuclear = Atomistic simulation of liquid metals and alloys for nuclear fusion reactors

La presente tesis comprende un estudio de metales líquidos, Li, Pb y eutéctico Li17Pb en el ámbito de la tecnología de fusión nuclear. Uno de los problemas fundamentales en futuros reactores de fusión es la producción y extracción de tritio en la denominada envoltura regeneradora (blanket en inglés). Dicho blanket tendrá dos propósitos, la extracción del calor generado por las reacciones de fusión para su posterior conversión en energía eléctrica así como la producción de tritio para realimentar el proceso. Dicha producción se realizará mediante el “splitting” del Li con los neutrones provenientes de la fusión. Esta reacción produce tritio y helio por lo que la interacción del T y el He con el metal líquido, con los materiales estructurales así como con el He es un problema fundamental aun no bien entendido y de gran importancia para futuros diseños. Los capítulos 1 2 y 3 presentan una introducción a dichos problemas. El capítulo 1 introduce al lector en la tecnología de fusión nuclear. El segundo capítulo explica en mayor detalle el uso de metales líquidos en reactores de fusión, no solo en blankets sino también como primera pared, divertor etc, lo que se denomina en general “plasma facing materials”. Por último se ofrece una breve introducción a las técnicas de dinámica molecular clásica (CMD) y un breve resumen de los potenciales más usados. El estudio se ha llevado a cabo utilizando simulación atomística mediante potenciales semi-empíricos del tipo átomo embebido (EAM). La Tesis consta de 4 partes bien definidas. En primer lugar se verificó la idoneidad de los potenciales tipo EAM para simular las propiedades de los metales Li y Pb en fase líquida. Dicho estudio se detalla en el Capítulo 4 y en su extensión, el Apéndice 1, en el que se estudia los límites de validez de esta aproximación. Los resultados de dicho estudio han sido publicados y presentados en diversos congresos internacionales. Un resumen de la metodología seguida fue publicado como capítulo de libro en Technofusión 2011. Los resultados se presentaron en diversos congresos internacionales, entre ellos ICENES 2011, (Artículo en ICENES Proceedings) ICOPS-SOFE 2011, en una presentación oral etc. El trabajo ha sido aceptado recientemente en Journal of Nuclear Materiales (Fraile et al 2012). La segunda parte y más importante comprende el desarrollo de un potencial para el estudio de la mezcla de ambos metales. Éste es el trabajo más novedoso e importante dado que no existía en la literatura un potencial semejante. Se estudiaron dos aproximaciones distintas al problema, un potencial tipo EAM/cd y un potencial EAM/alloy. Ambos potenciales dan resultados satisfactorios para la simulación del eutéctico (y concentraciones de Li menores que el 17%). Sin embargo el sistema LiPb en todas las concentraciones es un sistema que se aparta enormemente de una solución ideal y dicho potencial no daba buenos resultados para mezclas PbLi con concentraciones de Li grandes. Este problema fue solventado mediante el desarrollo de un segundo potencial, esta vez tipo EAM/alloy (segunda parte del Capítulo 5). Dicho trabajo será enviado a Physical Review Letters o a Phys. Rev. B, y una extensión junto con un estudio detallado de las propiedades del eutéctico de acuerdo con nuestras simulaciones se enviará a continuación a Phys. Rev. B. En tercer lugar se estudió el problema de la difusividad del H en metales líquidos aprovechando distintos potenciales existentes en la literatura. El problema del H en metales líquidos es importante en metalurgia. En dicho capítulo se estudió la difusividad del H en Pd, Ni y Al con potenciales tipo EAM, y también con un potencial más sofisticado que tiene en cuenta la dependencia angular de las interacciones (ADP por sus siglas en inglés). De este modo disponemos de un estudio detallado del problema con diferentes modelos y diferentes metales. La conclusión apunta a que si se compara con los resultados experimentales (muy escasos) los resultados obtenidos mediante CMD dan valores bajos de la difusividad del H. Las razones de dicho desacuerdo entre simulación y experimentos se detallan en el Capítulo 6. Este trabajo ha sido presentado en una presentación oral en el reciente congreso internacional “Trends on Nanothecnology” TNT 2012 celebrado en Madrid. El trabajo será publicado en un futuro próximo. Por último, como se dijo anteriormente, el estudio del He, la formación de burbujas en metales líquidos, su difusión nucleación y cavitación es otro problema deseable de ser estudiado mediante técnicas atomísticas. Para ello es necesario el desarrollo de diversos potenciales, He-Li, He-Pb y un potencial ternario Pb-Li-He. Para ello se han realizado simulación ab initio de los sistemas Pb+He y Li+He. Dicho estudio pretende calcular las fuerzas entre los átomos del metal (Pb o Li) con intersticiales de He. De este modo aplicaremos el “force matching method” (FMM) para el desarrollo de dichos potenciales. En el Capítulo 7 se detallan los resultados obtenidos referidos a las posiciones más favorables de las impurezas de He dentro de redes cristalinas de Pb y Li así como el efecto de tener en cuenta el acoplo spin-orbita (SOC en inglés). El análisis de los resultados en términos de transferencia de carga y análisis de las densidades electrónicas, así como la creación de los potenciales mencionados está en progreso. En conjunto la tesis presenta un estudio de los diversos problemas relacionados con el uso de metales líquidos en reactores de fusión y representa un primer paso en la determinación de parámetros de gran importancia para el diseño de blankets y sistemas de primera pared. Con la simulación MD de dichos problemas mediante, importante, potenciales realistas, valores de difusión, solubilidad etc de especies ligeras, H (o sus isotopos) y He en metales líquidos podrá ser calculada complementando así la base de datos que presenta enormes incertidumbres.