73 resultados para INERTIAL CONFINEMENT FUSION

em Universidad Politécnica de Madrid


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This work aims at identifying commonpotentialproblems that futurefusiondevices will encounter for both magnetic and inertialconfinement approaches in order to promote joint efforts and to avoid duplication of research. Firstly, a comparison of radiation environments found in both fusion reaction chambers will be presented. Then, wall materials, optical components, cables and electronics will be discussed, pointing to possible future areas of common research. Finally, a brief discussion of experimental techniques available to simulate the radiation effect on materials is included

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The aim of inertial confinement fusion is the production of energy by the fusion of thermonuclear fuel (deuterium-tritium) enclosed in a spherical target due to its implosion. In the direct-drive approach, the energy needed to spark fusion reactions is delivered by the irradiation of laser beams that leads to the ablation of the outer shell of the target (the so-called ablator). As a reaction to this ablation process, the target is accelerated inwards, and, provided that this implosion is sufficiently strong a symmetric, the requirements of temperature and pressure in the center of the target are achieved leading to the ignition of the target (fusion). One of the obstacles capable to prevent appropriate target implosions takes place in the ablation region where any perturbation can grow even causing the ablator shell break, due to the ablative Rayleigh-Taylor instability. The ablative Rayleigh-Taylor instability has been extensively studied throughout the last 40 years in the case where the density/temperature profiles in the ablation region present a single front (the ablation front). Single ablation fronts appear when the ablator material has a low atomic number (deuterium/tritium ice, plastic). In this case, the main mechanism of energy transport from the laser energy absorption region (low density plasma) to the ablation region is the electron thermal conduction. However, recently, the use of materials with a moderate atomic number (silica, doped plastic) as ablators, with the aim of reducing the target pre-heating caused by suprathermal electrons generated by the laser-plasma interaction, has demonstrated an ablation region composed of two ablation fronts. This fact appears due to increasing importance of radiative effects in the energy transport. The linear theory describing the Rayleigh-Taylor instability for single ablation fronts cannot be applied for the stability analysis of double ablation front structures. Therefore, the aim of this thesis is to develop, for the first time, a linear stability theory for this type of hydrodynamic structures.

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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.

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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.

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Systems inertial confinement fusion (ICF) need of a manufacturing process targets very accurate and efficient (Fig. A). Due to the frequency needed for energy production techniques are necessary to achieve high repetition rates, however it is also necessary to increase or maintain the quality and efficiency of these targets. In order to observe more resolution possible problems in the target manufacture (B), we propose the following theoretical methodology, by means of which analyze different phenomena present in the conditions which are fabrication and handled deuterium tritium target spheres (DT ice). Recent experiments show that addition of instabilities caused by the geometry of the solid layer of DT ice (C), and the cover (ablator), one can relate the loss of power delivery in the implosion due to different conformations of the solid layers with regarding handling conditions.

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Final lenses in laser fusion plants. Challenges for the protection of the final lenses. Plasmonic nanoparticles. Radiation resistance

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A numerical method providing the optimal laser intensity profiles for a direct-drive inertial confinement fusion scheme has been developed. The method provides an alternative approach to phase-space optimization studies, which can prove computationally expensive. The method applies to a generic irradiation configuration characterized by an arbitrary number NB of laser beams provided that they irradiate the whole target surface, and thus goes beyond previous analyses limited to symmetric configurations. The calculated laser intensity profiles optimize the illumination of a spherical target. This paper focuses on description of the method, which uses two steps: first, the target irradiation is calculated for initial trial laser intensities, and then in a second step the optimal laser intensities are obtained by correcting the trial intensities using the calculated illumination. A limited number of example applications to direct drive on the Laser MegaJoule (LMJ) are described.

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Designing the ignition and high-gain targets for inertial confinement fusion (ICF) requires a condensed uniform layer of the hydrogen fuel on the inner surface of a spherical polymer shell. The fuel layers have to be highly uniform in thickness and roughness.

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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

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After 10s the 90-99% of particles are released from the tungsten wall, mostly, towards the chamber. No element crosses the tungsten wall to the cooler. With 1x1022p/m2of He inside the W wall, He starts occasioning damages in the material. For case HiPER4a that is not a problem

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We will present calculations of opacities for matter under LTE conditions. Opacities are needed in radiation transport codes to study processes like Inertial Confinement Fusion and plasma amplifiers in X-ray secondary sources. For the calculations we use the code BiGBART, with either a hydrogenic approximation with j-splitting or self-consistent data generated with the atomic physics code FAC. We calculate the atomic structure, oscillator strengths, radiative transition energies, including UTA computations, and photoionization cross-sections. A DCA model determines the configurations considered in the computation of the opacities. The opacities obtained with these two models are compared with experimental measurements.

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The computation of dipole matrix elements plays an important role in the study of absorption or emission of radiation by atoms in several fields such as astrophysics or inertial confinement fusion. In this work we obtain closed formulas for the dipole matrix elements of multielectron ions suitable for using in the framework of a Relativistic Screened Hydrogenic Model.

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Desde el año 2004 el código ARWEN ha sido utilizado con éxito para simular y diseñar experimentos relacionados con blancos para fusión por confinamiento inercial [146], astrofísica de laboratorio [145], plasmas como amplificadores de láseres de rayos X [107] o plasmas creados por láser para la medición de espectros de transmisión. Para la realización de estas simulaciones es necesario, además de métodos de alto orden precisos y que presenten buenas propiedades conservativas, conocer ciertas propiedades de los plasmas. En el caso de la fluidodinámica y la conducción electrónica necesitaremos conocer la ecuación de estado [94, 49, 36], y para el transporte de la radiación será preciso disponer de los datos de absorción y emisión [104, 95, 40]. Hasta el año 2009 ARWEN dependía de códigos externos para la generación de estas tablas de opacidad, careciendo de control sobre los métodos empleados para su generación. Además estos códigos asumían equilibrio local termodinámico (LTE), limitando su validez a rangos de alta densidad y baja temperatura. En el marco de esta tesis se ha desarrollado el código BIGBART para la generación de tablas detalladas de opacidad y emisividad para su uso en el módulo de transporte de radiación. De esta forma el grupo dispondrá de su propia herramienta de generación de propiedades radiativas. El código desarrollado es capaz de tratar plasmas en estado fuera de equilibrio (non-LTE) mediante el modelo colisional-radiativo, extendiendo así el rango de validez de las tablas generadas. El trabajo desarrollado para implementar un código LTE/non-LTE estacionario es el siguiente Cálculo de estructura y datos atómicos. Se ha acoplado en código FAC a BIGBART, incorporando la capacidad para generar potenciales atómicos para una configuración y el cálculo de funciones de onda de electrones en orbitales ligados y libres. Aproximaciones y métodos para la obtención de tasas y secciones eficaces de procesos. Se han incluido y programado los modelos implementados en FAC para el cálculo de secciones eficaces de fotoionización, y tasas de decaimiento de emisión espontánea y autoionización. Además se ha incluido el modelo Plane-Wave Born (PWBA) para el cálculo de las secciones eficaces de ionización y excitación colisional. Modelos para la obtención de la distribución de estados iónicos dentro del plasma. Se ha programado un solver LTE basado en la ecuación de Saha-Boltzmann con efectos de ionización por presión debida a los iones adyacentes. También se ha implementado un modelo non-LTE colisionalradiativo para la resolución del sistema de ecuaciones que nos permite obtener la densidad de estados iónicos fuera de equilibrio. Modelo non-LTE RADIOM. Se ha implementado el modelo RADIOM para aproximar efectos de no-equilibrio mediante cálculos LTE a una temperatura equivalente, menor o igual que la temperatura electrónica real. Cálculo de las propiedades espectrales de absorción y emisión. Se han implementado los modelos para el cálculo de los perfiles espectrales de absorción y emisión para procesos entre niveles ligados, ligado-libre y librelibre. Aprovechando el trabajo realizado en este sentido, durante el transcurso de esta tesis se amplió el código BIGBART para tratar problemas con dependencia temporal. La extensión para tratar este tipo de problemas se orientó a la simulación numérica de la interacción de láseres ultra intensos en el rango XUV/rayos X. Para ello, además de adaptar el modelo non-LTE colisionalradiativo se incluyeron procesos adicionales asociados a la interacción de la materia con fotones altamente energéticos. También se han incluido modelos para el cálculo de las propiedades ópticas, y por ende las propiedades dieléctricas de la materia irradiada, de gran interés en algunas aplicaciones novedosas de estos láseres intensos. Debido a la naturaleza fuertemente fuera de equilibrio en la interacción de fotones de alta energía con la materia, se incluyó el tratamiento de la distribución de electrones libres fuera de equilibrio en la aproximación de Fokker-Planck, tanto para condiciones degeneradas como no degeneradas. El trabajo desarrollado en el código non-LTE con dependencia temporal es el siguiente Procesos asociados a láseres intensos XUV/rayos X. Se ha implementado el cálculo de procesos radiativos estimulados de absorción y emisión por el láser. También se han incluido procesos asociados a la creación de vacantes en capas internas electrónicas (Shake), además de doble autoionización y doble fotoionización. Cálculo de propiedades ópticas y dieléctricas en blancos sólidos. Se ha implementado un modelo para la absorción por bremsstrahlung inverso en blancos en estado sólido. Con el coeficiente de extinción debido a procesos de fotoabsorción resonante, fotoionización y bremsstrahlung inverso se obtiene el ´ındice de refracción mediante la relación de Kronig-Kramers. Electrones fuera de equilibrio. Se ha tratado la evolución de la distribución de electrones, cuando no está justificado asumir que es Maxwelliana o de Fermi-Dirac, mediante la aproximación de Fokker-Planck para la colisión entre electrones libres. En la resolución de la ecuación de Fokker-Planck se han incluido los procesos inelásticos por colisiones con iones y términos fuente por interacción con el láser y otros procesos. ABSTRACT Since 2004 the ARWEN code has been successfully used to simulate and design targets for inertial confinement fusion experiments [146], laboratory astrophysics [145], plasmas as X-ray lasers amplifiers [107] or laser created plasmas for measuring transmission spectra. To perform these simulations it is necessary, in addition to high order precise methods with good conservative properties, to know certain properties of plasmas. For fluid dynamic and electronic conduction we need to know the equation of state [94, 49, 36], and for radiation transport it will be necessary to have the data of the absorption and emission [104, 95, 40]. Until 2009 ARWEN depended on external codes to generate these opacity tables, lacking of control over the methods used for their generation. Besides, these codes assumed local thermodynamic equilibrium (LTE), limiting their validity ranges to high densities and low temperatures. As part of this thesis it has been developed the BIGBART code for generating detailed opacity and emissivity tables for use in the radiation transport module. This group will have its own tool for the generation of radiative properties. The developed code is capable of treating plasmas out of equilibrium (non-LTE) by means of a collisional-radiative model, extending the range of validity of the generated tables. The work to implement an LTE/non-LTE steady-state code is as follows Calculation of structure and atomic data. the FAC code was coupled to BIGBART, incorporating the ability to generate atomic potentials for calculating configuration wave functions for bound and free electrons. Approaches and methods for obtaining cross sections and processes rates. We have included and reprogrammed in Fortran the models implemented in FAC for calculation of photoionization cross sections and decay rates of spontaneous emission and autoionization. We also included the Plane- Wave Born (PWBA) model to calculate the cross sections of ionization and collisional excitation. Models for the obtention of the distribution of ionic states within the plasma. We programmed a LTE solver based on the Saha-Boltzmann equation with pressure ionization effects due to adjacent ions. It has also been implemented a non-LTE collisional-radiative model for solving the system of equations that allows us to obtain the density of ionic states out of equilibrium. Non-LTE RADIOM model. We have implemented the non-LTE RADIOM model to approximate non-equilibrium effects with LTE data at an equivalent temperature, lower or equal to the actual electronic temperature. Calculation of the spectral absorption and emission properties. Models have been implemented for the calculation of the spectral profiles of absorption and emission processes between bound levels, free-bound and free-free. Taking advantage of the work done in this direction throughout the course of this thesis the code BIGBART was extended to treat time-dependent problems. The extension to treat such problems is oriented to the numerical simulation of the interaction of ultra intense lasers in the XUV/X-ray range. For this range, in addition to adapting the non-LTE collisional-radiative model, additional processes associated with the interaction of matter with high energy photons. We also included models for calculation of the optical properties, and therefore the dielectric properties of the irradiated material, of great interest in some novel applications of these intense lasers. Due to the strong non-equilibrium nature of the interaction of high energy photons with matter, we included the treatment of the distribution of free electrons out of equilibrium in the Fokker-Planck approximation for both degenerate and non-degenerate conditions. The work in the non-LTE time-dependent code is as follows Processes associated with intense XUV/X-ray lasers. We have implemented the calculation of stimulated radiative processes in absorption and emission. Also we included processes associated with the creation of electronic vacancies in inner shells (Shake), double autoionization and double photoionization. Calculation of optical and dielectric properties in solid targets. We have implemented a model for inverse bremsstrahlung absorption in solid targets. With the extinction coefficient from resonant photoabsorption, photoionization and inverse bremsstrahlung the refractive index is obtained by the Kramers-Kronig relation. Electrons out of equilibrium. We treat the evolution of the electron distribution, when it is not justified to assume a Maxwellian or Fermi-Dirac distribution, by the Fokker-Planck approximation for collisions between electrons. When solving the Fokker-Planck equation we included inelastic collision processes with ions and source terms by interaction with the laser and other processes.

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The use of the Laser MegaJoule facility within the shock ignition scheme has been considered. In the first part of the study, one-dimensional hydrodynamic calculations were performed for an inertial confinement fusion capsule in the context of the shock ignition scheme providing the energy gain and an estimation of the increase of the peak power due to the reduction of the photon penetration expected during the high-intensity spike pulse. In the second part, we considered a Laser MegaJoule configuration consisting of 176 laser beams that have been grouped providing two different irradiation schemes. In this configuration the maximum available energy and power are 1.3 MJ and 440 TW. Optimization of the laser?capsule parameters that minimize the irradiation non-uniformity during the first few ns of the foot pulse has been performed. The calculations take into account the specific elliptical laser intensity profile provided at the Laser MegaJoule and the expected beam uncertainties. A significant improvement of the illumination uniformity provided by the polar direct drive technique has been demonstrated. Three-dimensional hydrodynamic calculations have been performed in order to analyse the magnitude of the azimuthal component of the irradiation that is neglected in twodimensional hydrodynamic simulations.

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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.