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.

Evaluation of a Change Detection Methodology by Means of Binary Thresholding Algorithms and Informational Fusion Processes

Landcover is subject to continuous changes on a wide variety of temporal and spatial scales. Those changes produce significant effects in human and natural activities. Maintaining an updated spatial database with the occurred changes allows a better monitoring of the Earth?s resources and management of the environment. Change detection (CD) techniques using images from different sensors, such as satellite imagery, aerial photographs, etc., have proven to be suitable and secure data sources from which updated information can be extracted efficiently, so that changes can also be inventoried and monitored. In this paper, a multisource CD methodology for multiresolution datasets is applied. First, different change indices are processed, then different thresholding algorithms for change/no_change are applied to these indices in order to better estimate the statistical parameters of these categories, finally the indices are integrated into a change detection multisource fusion process, which allows generating a single CD result from several combination of indices. This methodology has been applied to datasets with different spectral and spatial resolution properties. Then, the obtained results are evaluated by means of a quality control analysis, as well as with complementary graphical representations. The suggested methodology has also been proved efficiently for identifying the change detection index with the higher contribution.

Plasma–wall interaction in laser inertial fusion reactors: novel proposals for radiation tests of first wall materials

Dry-wall laser inertial fusion (LIF) chambers will have to withstand strong bursts of fast charged particles which will deposit tens of kJ m−2 and implant more than 1018 particles m−2 in a few microseconds at a repetition rate of some Hz. Large chamber dimensions and resistant plasma-facing materials must be combined to guarantee the chamber performance as long as possible under the expected threats: heating, fatigue, cracking, formation of defects, retention of light species, swelling and erosion. Current and novel radiation resistant materials for the first wall need to be validated under realistic conditions. However, at present there is a lack of facilities which can reproduce such ion environments. This contribution proposes the use of ultra-intense lasers and high-intense pulsed ion beams (HIPIB) to recreate the plasma conditions in LIF reactors. By target normal sheath acceleration, ultra-intense lasers can generate very short and energetic ion pulses with a spectral distribution similar to that of the inertial fusion ion bursts, suitable to validate fusion materials and to investigate the barely known propagation of those bursts through background plasmas/gases present in the reactor chamber. HIPIB technologies, initially developed for inertial fusion driver systems, provide huge intensity pulses which meet the irradiation conditions expected in the first wall of LIF chambers and thus can be used for the validation of materials too.

Wavelet-based image fusion in multi-view three-dimensional microscopy

Multi-view microscopy techniques such as Light-Sheet Fluorescence Microscopy (LSFM) are powerful tools for 3D + time studies of live embryos in developmental biology. The sample is imaged from several points of view, acquiring a set of 3D views that are then combined or fused in order to overcome their individual limitations. Views fusion is still an open problem despite recent contributions in the field. We developed a wavelet-based multi-view fusion method that, due to wavelet decomposition properties, is able to combine the complementary directional information from all available views into a single volume. Our method is demonstrated on LSFM acquisitions from live sea urchin and zebrafish embryos. The fusion results show improved overall contrast and details when compared with any of the acquired volumes. The proposed method does not need knowledge of the system's point spread function (PSF) and performs better than other existing PSF independent fusion methods.

Ion beam analysis of as-received, H-implanted and post implanted annealed fusion steels

The elemental distribution for as-received (AR), H implanted (AI) and post-implanted annealed (A) Eurofer and ODS-Eurofer steels has been characterized by means of micro Particle Induced X-ray Emission (μ-PIXE), micro Elastic Recoil Detection (μ-ERD) and Secondary Ion Mass Spectrometry (SIMS). The temperature and time-induced H diffusion has been analyzed by Resonance Nuclear Reaction Analysis (RNRA), Thermal Desorption Spectroscopy (TDS), ERDA and SIMS techniques. μ-PIXE measurements point out the presence of inhomogeneities in the Y distribution for ODS-Eurofer samples. RNRA and SIMS experiments evidence that hydrogen easily outdiffuses in these steels even at room temperature. ERD data show that annealing at temperatures as low as 300 °C strongly accelerates the hydrogen diffusion process, driving out up to the 90% of the initial hydrogen.

Ignition conditions for inertial confinement fusion targets with a nuclear spin-polarized DT fuel

The nuclear fusion cross-section is modified when the spins of the interacting nuclei are polarized. In the case of deuterium?tritium it has been theoretically predicted that the nuclear fusion cross-section could be increased by a factor d = 1.5 if all the nuclei were polarized. In inertial confinement fusion this would result in a modification of the required ignition conditions. Using numerical simulations it is found that the required hot-spot temperature and areal density can both be reduced by about 15% for a fully polarized nuclear fuel. Moreover, numerical simulations of a directly driven capsule show that the required laser power and energy to achieve a high gain scale as d-0.6 and d-0.4 respectively, while the maximum achievable energy gain scales as d0.9.

Self-consistent numerical dispersion relation of the ablative Rayleigh-Taylor instability of double ablation fronts in inertial confinement fusion

The linear stability analysis of accelerated double ablation fronts is carried out numerically with a self-consistent approach. Accurate hydrodynamic profiles are taken into account in the theoretical model by means of a fitting parameters method using 1D simulation results. Numerical dispersión relation is compared to an analytical sharp boundary model [Yan˜ez et al., Phys. Plasmas 18, 052701 (2011)] showing an excellent agreement for the radiation dominated regime of very steep ablation fronts, and the stabilization due to smooth profiles. 2D simulations are presented to validate the numerical self-consistent theory.

Experimental results on advanced inertial fusion schemes obtained within the HiPER project

This paper presents de results of experiments conducted within the Work Package 10 (fusion experimental programme) of the HiPER project. The aim of these experiments was to study the physics relevant for advanced ignition schemes for inertial confinement fusion, i.e. the fast ignition and the shock ignition. Such schemes allow to achieve a higher fusion gain compared to the indirect drive approach adopted in the National Ignition Facility in United States, which is important for the future inertial fusion energy reactors and for realising the inertial fusion with smaller facilities

Plasma–wall interaction in laser inertial fusion reactors: novel proposals for radiation tests of first wall materials

Dry-wall laser inertial fusion (LIF) chambers will have to withstand strong bursts of fast charged particles which will deposit tens of kJ m−2 and implant more than 1018 particles m−2 in a few microseconds at a repetition rate of some Hz. Large chamber dimensions and resistant plasma-facing materials must be combined to guarantee the chamber performance as long as possible under the expected threats: heating, fatigue, cracking, formation of defects, retention of light species, swelling and erosion. Current and novel radiation resistant materials for the first wall need to be validated under realistic conditions. However, at present there is a lack of facilities which can reproduce such ion environments. This contribution proposes the use of ultra-intense lasers and high-intense pulsed ion beams (HIPIB) to recreate the plasma conditions in LIF reactors. By target normal sheath acceleration, ultra-intense lasers can generate very short and energetic ion pulses with a spectral distribution similar to that of the inertial fusion ion bursts, suitable to validate fusion materials and to investigate the barely known propagation of those bursts through background plasmas/gases present in the reactor chamber. HIPIB technologies, initially developed for inertial fusion driver systems, provide huge intensity pulses which meet the irradiation conditions expected in the first wall of LIF chambers and thus can be used for the validation of materials too.

The seminar of nuclear safety in advanced reactors and the seminar of nuclear fusion: two formative initiatives from Universidad Politécnica de Madrid and spanish young Generation in Nuclear (Jóvenes Nucleares)

panish Young Generation in Nuclear (Jóvenes Nucleares) is a commission of the Spanish Nuclear Society (SNE), whose main goals are to spread knowledge about nuclear energy among the society. Following this motivation, two Seminars have been carried out with the collaboration of the Technical University of Madrid: The Seminar of Nuclear Safety in Advanced Reactors (SRA) and the Seminar of Nuclear Fusion (SFN). The first one, which has been celebrated every year since 2010, aims to show clearly the advances that have been obtained in the section of safety with the new reactors, from a technical but simple point of view and without needing great previous nuclear engineering knowledge. The second one, which first edition was held in 2011, aims to give a general overview of the past, present and future situation of nuclear fusion technology, and was born as a result of the increasing interest of our Spanish Young Generation members in this technology.

Ultraintense lasers applied to laser fusion material testing: production of ions, X rays and neutrons

Due to the particular characteristics of the fusion products, i.e. very short pulses (less than a few μs long for ions when arriving to the walls; less than 1 ns long for X-rays), very high fluences ( 10 13 particles/cm 2 for both ions and X rays photons) and broad particle energy spectra (up to 10 MeV ions and 100 keV photons), the laser fusion community lacks of facilities to accurately test plasma facing materials under those conditions. In the present work, the ability of ultraintese lasers to create short pulses of energetic particles and high fluences is addressed as a solution to reproduce those ion and X-ray bursts. Based on those parameters, a comparison between fusion ion and laser driven ion beams is presented and discussed, describing a possible experimental set-up to generate with lasers the appropriate ion pulses. At the same time, the possibility of generating X-ray or neutron beams which simulate those of laser fusion environments is also indicated and assessed under current laser intensities. It is concluded that ultraintense lasers should play a relevant role in the validation of materials for laser fusion facilities.

Ultraintense Lasers Applied to Laser Fusion Material Testing: Production of Ions, X rays and Neutrons

The ability of ultraintese lasers to create short pulses of energetic particles and high fluences is addressed as a solution to reproduce ion and X-ray ICF bursts for the characterization and validation of plasma facing components. The possibility of using a laser neutron source for material testing will also be discussed.

The technofusion project for fusion technology development: opportunities for the inertial community

The new Spanish installation for fusion research (Technofusion) has been approved by both the national and regional governments. Funding up to 80-100 M€ will be invested in the construction of seven laboratories to cover many aspects relevant to fusion technology development. This work discusses their utility for inertial fusion research.

Atmospheric modelling of tritium forms transport: review of capabilities and R&D needs for the assessment of fusion facilities environmental impact

One of the key scrutiny issues of new coming energy era would be the environmental impact of fusion facilities managing one kg of tritium. The potential change of committed dose regulatory limits together with the implementation of nuclear design principles (As Low as Reasonably achievable - ALARA -, Defense in Depth -D-i-D-) for fusion facilities could strongly impact on the cost of deployment of coming fusion technology. Accurate modeling of environmental tritium transport forms (HT, HTO) for the assessment of fusion facility dosimetric impact in Accidental case appears as of major interest. This paper considers different short-term releases of tritium forms (HT and HTO) to the atmosphere from a potential fusion reactor located in the Mediterranean Basin. This work models in detail the dispersion of tritium forms and dosimetric impact of selected environmental patterns both inland and in-sea using real topography and forecast meteorological data-fields (ECMWF/FLEXPART). We explore specific values of this ratio in different levels and we examine the influence of meteorological conditions in the HTO behavior for 24 hours. For this purpose we have used a tool which consists on a coupled Lagrangian ECMWF/FLEXPART model useful to follow real time releases of tritium at 10, 30 and 60 meters together with hourly observations of wind (and in some cases precipitations) to provide a short-range approximation of tritium cloud behavior. We have assessed inhalation doses. And also HTO/HT ratios in a representative set of cases during winter 2010 and spring 2011 for the 3 air levels.

The technofusion project for fusion technology development: opportunities for the inertial community

Technofusion will be the new Spanish singular scientific-technical installation for fusion research. The research activities will be focused on seven areas of materials research considered the most relevant ones for further technological developments of fusion energy. In principle, most of the infrastructure in Technofusion will be useful for both, magnetic (MC) and inertial (IC) confinement fusion communities and most of the research and developments carried out for one of the fusion concepts will be valid and transferable to the other. However, some aspects related to first wall materials strongly differ in MC and IC approaches. This is due to the very different typical ion energy and deposited powers in both cases.