ANALYTIC STUDY ON HIGH-VOLTAGE CROWBAR SYSTEM

Crowbar switches are largely used in plasma devices, such as field-reversed configuration (FRC) machines and tokamaks, to avoid energy return from the discharge coil to the capacitor bank. A method of identification of all resistances, inductances and currents involved in capacitor bank discharges using a crowbar is proposed based on the derivation of the general analytical form of the coil current. This analysis can also be used for optimization of the discharge, reducing the ripple amplitude inherent in the crowbar-switched current. Fitting results of the TC-1 UNICAMP FRC device are also presented in this work.

Self-consistent equilibrium calculation through a direct variational technique in tokamak plasmas

A self-consistent equilibrium calculation, valid for arbitrary aspect ratio tokamaks, is obtained through a direct variational technique that reduces the equilibrium solution, in general obtained from the 2D Grad-Shafranov equation, to a 1D problem in the radial flux coordinate rho. The plasma current profile is supposed to have contributions of the diamagnetic, Pfirsch-Schluter and the neoclassical ohmic and bootstrap currents. An iterative procedure is introduced into our code until the flux surface averaged toroidal current density (J(T)), converges to within a specified tolerance for a given pressure profile and prescribed boundary conditions. The convergence criterion is applied between the (J(T)) profile used to calculate the equilibrium through the variational procedure and the one that results from the equilibrium and given by the sum of all current components. The ohmic contribution is calculated from the neoclassical conductivity and from the self-consistently determined loop voltage in order to give the prescribed value of the total plasma current. The bootstrap current is estimated through the full matrix Hirshman-Sigmar model with the viscosity coefficients as proposed by Shaing, which are valid in all plasma collisionality regimes and arbitrary aspect ratios. The results of the self-consistent calculation are presented for the low aspect ratio tokamak Experimento Tokamak Esferico. A comparison among different models for the bootstrap current estimate is also performed and their possible Limitations to the self-consistent calculation is analysed.

Controle de dinâmica caótica com toros robustos

Conselho Nacional de Desenvolvimento Científico e Tecnológico (CNPq)

Tokamak TCABR: Acquisition system, data analysis, and remote participation using MDSplus

Each plasma physics laboratory has a proprietary scheme to control and data acquisition system. Usually, it is different from one laboratory to another. It means that each laboratory has its own way to control the experiment and retrieving data from the database. Fusion research relies to a great extent on international collaboration and this private system makes it difficult to follow the work remotely. The TCABR data analysis and acquisition system has been upgraded to support a joint research programme using remote participation technologies. The choice of MDSplus (Model Driven System plus) is proved by the fact that it is widely utilized, and the scientists from different institutions may use the same system in different experiments in different tokamaks without the need to know how each system treats its acquisition system and data analysis. Another important point is the fact that the MDSplus has a library system that allows communication between different types of language (JAVA, Fortran, C, C++, Python) and programs such as MATLAB, IDL, OCTAVE. In the case of tokamak TCABR interfaces (object of this paper) between the system already in use and MDSplus were developed, instead of using the MDSplus at all stages, from the control, and data acquisition to the data analysis. This was done in the way to preserve a complex system already in operation and otherwise it would take a long time to migrate. This implementation also allows add new components using the MDSplus fully at all stages. (c) 2012 Elsevier B.V. All rights reserved.

Shearless transport barriers in magnetically confined plasmas

Shearless transport barriers appear in confined plasmas due to non-monotonic radial profiles and cause localized reduction of transport even after they have been broken. In this paper we summarize our recent theoretical and experimental research on shearless transport barriers in plasmas confined in toroidal devices. In particular, we discuss shearless barriers in Lagrangian magnetic field line transport caused by non-monotonic safety factor profiles. We also discuss evidence of particle transport barriers found in the TCABR Tokamak (University of Sao Paulo) and the Texas Helimak (University of Texas at Austin) in biased discharges with non-monotonic plasma flows.

Dynamical analysis of turbulence in fusion plasmas and nonlinear waves

Turbulence is one of the key problems of classical physics, and it has been the object of intense research in the last decades in a large spectrum of problems involving fluids, plasmas, and waves. In order to review some advances in theoretical and experimental investigations on turbulence a mini-symposium on this subject was organized in the Dynamics Days South America 2010 Conference. The main goal of this mini-symposium was to present recent developments in both fundamental aspects and dynamical analysis of turbulence in nonlinear waves and fusion plasmas. In this paper we present a summary of the works presented at this mini-symposium. Among the questions to be addressed were the onset and control of turbulence and spatio-temporal chaos. (C) 2011 Elsevier B. V. All rights reserved.

Secondary nontwist phenomena in area-preserving maps

Phenomena as reconnection scenarios, periodic-orbit collisions, and primary shearless tori have been recognized as features of nontwist maps. Recently, these phenomena and secondary shearless tori were analytically predicted for generic maps in the neighborhood of the tripling bifurcation of an elliptic fixed point. In this paper, we apply a numerical procedure to find internal rotation number profiles that highlight the creation of periodic orbits within islands of stability by a saddle-center bifurcation that emerges out a secondary shearless torus. In addition to the analytical predictions, our numerical procedure applied to the twist and nontwist standard maps reveals that the atypical secondary shearless torus occurs not only near a tripling bifurcation of the fixed point but also near a quadrupling bifurcation. (C) 2012 American Institute of Physics. [http://dx.doi.org/10.1063/1.4750040]

Long-distance correlations in TCABR biasing experiments

Long-distance correlations (LDCs) of plasma potential fluctuations in the plasma edge have been investigated in the TCABR tokamak in the regime of edge biasing H-mode using an array of multi-pin Langmuir probes. This activity was carried out as part of the scientific programme of the 4th IAEA Joint Experiment (2009). The experimental data confirm the effect of amplification of LDCs in potential fluctuations during biasing recently observed in stellarators and tokamaks. For long toroidal distances between probes, the cross-spectrum is concentrated at low frequencies f < 60 kHz with peaks at f < 5 kHz, f = 13-15 kHz and f similar to 40 kHz and low wave numbers with a maximum at k = 0. The effects of MHD activity on the LDCs in potential fluctuation are investigated.

Modelo no estacionario para determinar la estructura atómica en un plasma de fusión por confinamiento inercial

Durante los últimos años la física atómica ha vuelto a cobrar un papel fundamental en los planes de investigación, entre los que destacan aquellos dedicados al estudio teórico y experimental de la fusión nuclear. Concretamente, en el concepto de fusión por confinamiento inercial se pueden distinguir cuatro grandes áreas donde es básico el conocimiento de las propiedades atómicas de la materia. Estas son: 1. Modelado de la interacción entre haces de partículas o láser con la cápsula combustible 2. Simulación de blancos de irradiación indirecta mediante conversión a rayos X 3. Diagnosis de experimentos 4. Láseres de rayos X La modelación de los plasmas en fusión depende principalmente de la densidad electrónica. En fusión por confinamiento magnético (tokamaks), los plasmas tienen densidades bajas, por lo que, en general, es suficiente considerar un modelo corona, en el que la mayoría de los iones se encuentran en su estado fundamental o con un número pequeño de estados excitados, estableciéndose sus poblaciones mediante un balance entre la ionización colisional/recombinación radiativa y excitación/decaimiento espontáneo. Sin embargo, los plasmas característicos de la fusión por confinamiento inercial tienen densidades más altas, aunque, normalmente, no lo suficientes como para poder establecer condiciones de equilibrio local termodinámico (balance entre procesos colisionales). Estas densidades, que se podrían clasificar como intermedias, se caracterizan por la aparición de un mayor número de estados excitados por ión y por la importancia tanto de los procesos colisionales como radiativos. Además de lo expuesto anteriormente, en ciertos regímenes de plasma, las variables termodinámicas locales, fundamentalmente presión (densidad) y temperatura, varían fuertemente con el tiempo, de manera que cuando los tiempos característicos de esta variación son menores que los propios de relajación de los procesos atómicos, el sistema no puede tratarse en estado estacionario, siendo necesario resolver las ecuaciones de balance con dependencia temporal. Estas ecuaciones de tasa o de balance contienen una serie de términos que representan los distintos procesos mediante una serie de coeficientes cuyas expresiones dependen de las condiciones del plasma, por lo que el problema es fuertemente no lineal. Por otra parte, hay que añadir que si el medio es ópticamente grueso a la radiación, en las ecuaciones de tasa aparecen términos radiativos que incluyen el campo de radiación, por lo que es necesario resolver la ecuación de transferencia en cada línea o bien, utilizar otras aproximaciones, que sin resolver dicha ecuación, permitan tener en cuenta el campo de radiación en la línea. Por todo ello, el objetivo de esta Tesis se centra en el desarrollo de un modelo original para el cálculo de la distribución de los estados de ionización en un plasma de fusión por confinamiento inercial en condiciones de no-equilibrio termodinámico local, caracterizado por: 1. Resolución de las ecuaciones de balance en estado estacionario y con dependencia temporal, considerando a las distintas especies iónicas tanto en su estado fundamental como en posibles estados excitados. 2. Elección de especies iónicas y número de estados excitados en función de las condiciones de densidad y temperatura del plasma. En el caso de una evolución temporal el número de estados excitados y su distribución se adecúan en cada caso a las condiciones del plasma. 3. Tratamiento de medios ópticamente finos y gruesos, utilizándose para estos últimos una evaluación aproximada del campo de radiación en la línea. 4. Capacidad de acoplamiento a un modelo hidrodinámico a través de la temperatura electrónica, densidad y campo de radiación. Entre todas estas características, se debe hacer constar que las principales aportaciones originales se refieren, en primer lugar, a la forma original de resolver las ecuaciones de tasa con dependencia temporal, ya que se tiene en cuenta la evolución de todos los estados: fundamentales y excitados, frente a la hipótesis habitual de resolver las ecuaciones temporales sólo de los estados fundamentales, y suponer los excitados en estado estacionario, es decir, que siguen el comportamiento de su correspondiente fundamental. En segundo lugar, la elección del número de estados excitados por cada funda- X mental, que se realiza mediante un cálculo inicial donde se considera todos los iones del plasma en estado fundamental, para en función de las densidades de población obtenidas, elegir los estados fundamentales y sus correspondientes excitados que se deben considerar. Y por último, señalar que en el tratamiento de medios ópticamente gruesos se ha conseguido obtener una evaluación de la radiación absorbida por el plasma, independientemente de la geometría del mismo, sin necesidad de resolver la ecuación de transferencia en la línea, y sin acudir a otros métodos, que sin resolver dicha ecuación, necesitan la definición de una geometría para el plasma, por ejemplo, factores de escape. El modelo ha sido comparado y contrastado tanto con resultados teóricos como experimentales, observando unos resultados muy aceptables, de lo cual se deduce que el modelo es capaz de suministrar la evaluación de los parámetros atómicos en este tipo de plasmas. A partir de esta Tesis, el modelo se puede potenciar, a través de varias líneas de investigación que se han identificado: 1. Tratamiento de medios ópticamente gruesos con resolución de la ecuación de transferencia en las líneas. 2. Evaluación detallada de las secciones eficaces de los distintos procesos que tienen lugar en plasmas, y que aparecen en las ecuaciones de balance a través de los coeficientes de tasa.

Implementation of the disruption predictor APODIS in JET Real Time Network using the MARTe framework

Disruptions in tokamaks devices are unavoidable, and they can have a significant impact on machine integrity. So it is very important have mechanisms to predict this phenomenon. Disruption prediction is a very complex task, not only because it is a multi-dimensional problem, but also because in order to be effective, it has to detect well in advance the actual disruptive event, in order to be able to use successful mitigation strategies. With these constraints in mind a real-time disruption predictor has been developed to be used in JET tokamak. The predictor has been designed to run in the Multithreaded Application Real-Time executor (MARTe) framework. The predictor ?Advanced Predictor Of DISruptions? (APODIS) is based on Support Vector Machine (SVM).

Estudo de efeitos da polarização eletrostática periférica no Tokamak TCABR

Efeitos da polarização eletrostática de eletrodos na periferia de tokamaks têm sido investigados em pequenos tokamaks e mesmo em alguns tokamaks de grande porte. Em geral as experiências são realizadas em condições em que bifurcação do campo elétrico radial é obtida, processo este identificado como modo H de polarização. No Tokamak TCABR, as experiências indicam que o confinamento aumenta para tensões aplicadas até +300 volts, atingindo um máximo de duas vezes o tempo de confinamento do modo L, mas sem bifurcação. Indícios de bifurcação foram notados com +400 V de polarização, mas a descarga termina devido à excitação da atividade MHD, ainda sob investigação. No presente trabalho, a pesquisa é aprofundada com a utilização de uma sonda de Langmuir com 18 pinos dispostos em duas fileiras sob a forma de um ancinho (rake probe) o que permite a medição da temperatura, densidade e flutuação de potencial ao longo do raio menor na periferia do Tokamak. A resolução temporal desse sistema é de cerca de 0,5 ms, para a temperatura, e 5 microssegundos para densidade e potencial flutuante do plasma. Outra sonda eletrostática com 5-pinos na mesma posição radial, mas em diferentes posições poloidal e toroidal foi usada para medições de turbulência e transporte de partículas. Os efeitos da polarização foram investigados e indicam que os níveis de turbulência e transporte começam a diminuir entre +150 e +200 V e para +300 V chegam a atingir uma quase supressão. Nesse mesmo intervalo de tensão a densidade começa a aumentar e para +300 V chega a ser um fator de aproximadamente 2. Quanto ao perfil de temperatura a variação é pouco significativa, mas as incertezas das medidas são maiores. Esses dados são compatíveis com a criação de uma barreira de transporte na região entre o eletrodo em r = 17 cm e o limitador em a = 18 cm. Além disso, o campo elétrico radial mostra forte cisalhamento nessa região. Tomando o início da subida do potencial flutuante como origem de uma escala de tempo, o atraso temporal do início da subida da densidade de elétrons e o atraso do início do decréscimo do transporte de partículas foram medidos. Os resultados são 50 microssegundos para a densidade de elétrons e 60 microssegundos para o transporte de partículas. A questão dos limiares de potência é discutida no texto. Os dados desta experiência indicam que o campo elétrico radial desempenha o papel principal para a melhoria do confinamento.

Tokamak experimental power reactor conceptual design /

"August, 1976."

Feasibility study of a fission-suppressed Tokamak fusion breeder /

"UCID-20154"--Cover.

Tokamak experimental power reactor studies /

"Prepared for the U.S. Energy Research and Development Administration under Contract W-31-109-Eng-38"--Cover.

Insights into hydrogen atom adsorption on and the electrochemical properties of nitrogen-substituted carbon materials

The nitrogen substitution in carbon materials is investigated theoretically using the density functional theory method. Our calculations show that nitrogen substitution decreases the hydrogen adsorption energy if hydrogen atoms are adsorbed on both nitrogen atoms and the neighboring carbon atoms. On the contrary, the hydrogen adsorption energy can be increased if hydrogen atoms are adsorbed only on the neighboring carbon atoms. The reason can be explained by the electronic structures analysis of N-substituted graphene sheets. Nitrogen substitution reduces the pi electron conjugation and increases the HOMO energy of a graphene sheet, and the nitrogen atom is not stable due to its 3-valent character. This raises an interesting research topic on the optimization of the N-substitution degree, and is important to many applications such as hydrogen storage and the tokamaks device. The electronic structure studies also explain well why nitrogen substitution increases the capacitance but decreases the electron conductivity of carbon electrodes as was experimentally observed in our experiments on the supercapacitor.