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1

Severo, José Helder Facundo. "Estudo da rotação de plasma no tokamak TCABR." Universidade de São Paulo, 2003. http://www.teses.usp.br/teses/disponiveis/43/43134/tde-06092012-125249/.

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Este trabalho, que pode ser dividido em duas partes, teórica e experimental, trata da rotação residual de plasma no TCABR. No que se refere à parte teórica, foi obtida uma expressão geral para a velocidade poloidal e o fluxo de calor, para tokamaks com seção transversal arbitrária, em um plasma que está sujeito a um fluxo subsônico toroidal. Foram estudadas em detalhe as dependências da velocidade poloidal com o número de Mach sigma e o fluxo de calor iônico e foi verificado que a velocidade poloidal troca de sentido para um certo valor sigma=sigma IND.0. Também foi verificado que existe um valor sigma=sigma IND.K, a velocidade poloidal começa a diminuir. Quanto ao fluxo de calor, foi observado que ele é fortemente afetado pela geometria e é proporcional a q POT.2, onde q é o fator de segurança. Para q=1, o fluxo de calor tem um máximo para um fator de elongação k=1, correspondente a uma seção transversal circular, diminui com o aumento de k e apresenta um mínimo em k=2. No que se refere à parte experimental,foram obtidos pela primeira vez, no tokamak TCABR, os perfis radiais das velocidade de rotação poloidal e toroidal para um regime colisional, usando o deslocamento Doppler das linhas espectrais das impurezas de CIII (646,74nm) e CVI (529,02nm), medidas com um espectrômetro TH1000 de distância focal 1000mm e dispersão linear de 8 A/mm. Os resultados experimentais mostram que a velocidade poloidal tem um máximo de (4,5 + OU -1,0).10 POT.5cm/s, cujo sentido de deriva diamagnética dos elétrons. Estes resultados mostram uma boa concordância com a teoria neoclássica para a região da coluna r=5-14 cm, enquanto que para r>14 cm os resultados experimentais estão de desacordo com a teoria. No que diz respeito à velocidade de rotação toroidal, ela é oposta à corrente de plasma e tem um valor máximo de (20 + OU -1).10 POT.5cm/s, o que está em razoável concordância com o modelo proposto por ) Kim e Diamond. Foi observado que a velocidade de rotação toroidal troca de sentido em r>16 cm, indicando haver um forte cisalhamento da rotação na borda da coluna de plasma. A partir dos resultados das velocidades poloidal e toroidal e do gradiente de temperatura iônica, foi calculada a componente radial do campo elétrico que resultou negativo em toda a coluna de plasma. Finalmente, estes resultados estão em boa concordância com os resultados obtidos em tokamaks semelhantes ao TCABR. Os resultados experimentais para a velocidade poloidal podem ser bem descritos pela teoria neoclássica de rotação em tokamaks, exceto nas regiões próximas ao limitador. No entanto, ainda não existe uma teoria geral satisfatória para explicar os resultados da rotação toroidal do plasma em tokamaks. Existem teorias interessantes, porém não são aplicáveis ao tokamak TCABR
In the present work we investigated theorically and experimentally the plasma residual rotation in the tokamak TCABR. Using the neoelassical theory, general expressions for the poloidal velocity and heat flux were obtained for tokamaks with arbitrary plasma cross-sections, and subsonic toroidal flows. The dependency of the poloidal velocity and the heat flow with Mach number a were analyzed. It was found that the poloidal velocity changes sign for a ccrtain valuc alpfa = alpha 0, a critical value ak of a exists corresponding to a maximum value of ion poloidal velocity, and that for alpha > alpha k the poloidal velocity is a decreasing function of alpha.
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2

Kelly, Frederick Alan. "Tokamak density limits." Diss., Georgia Institute of Technology, 2000. http://hdl.handle.net/1853/16628.

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3

AMROLLAHI, REZA. "Iran et tokamak." Paris 6, 1994. http://www.theses.fr/1994PA066779.

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Cette these est divisee en six chapitres et deux appendices. Au cours d'une breve introduction, l'auteur rappelle que les pays en voie de developpement se doivent de construire des petites machines a fusion thermonucleaire controlee du filiere dite tokamak pour former les physiciens locaux specialises en physique des plasmas et dans d'autres disciplines mais aussi pour developper les industries locales. Le premier chapitre, apres un rapide rappel de l'etat des recherches sur les grands tokamaks mondiaux, indique les tendances des recherches a moyen terme et les projets de tres gros tokamaks a l'horizon du 3#e#m#e millenaire. Enfin l'auteur situe l'effort de l'iran en la matiere, a savoir un petit tokamak operationnel alvand et un projet deja bien avance de tokamak a section droite allongee damavand. Ce petit tokamak de recherches alvand est tres abondamment decrit dans le deuxieme chapitre ainsi que les nombreux diagnostics qui entourent la machine. Le chapitre 3 decrit le principe de la mesure de densite electronique dans un plasma de tokamak par l'interferometrie micro-onde ainsi que la mise en uvre sur la machine alvand. Le morceau de choix de l'ouvrage est le chapitre 5 etaye par une abondante bibliographique. En effet dans ce chapitre l'auteur expose les considerations theoriques et les principes physiques mis a contribution pour concevoir un nouveau tokamak iranien damavand dont la particularite est de creer un plasma toroidal a section droite allongee et l'allongement prevu ici est consequent puisqu'il est prevu d'atteindre une ellipticile de 4. Des etudes theoriques de stabilite du plasma sont decrites. Le court chapitre 6 est plutot un resume des resultats d'alvand et des perspectives sur damavand. Enfin deux appendices donnent l'un les notations utilisees et l'autre le listing du code numerique ainsi que des resultats numeriques
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4

Weening, Richard Henry. "Completely bootstrapped tokamak." W&M ScholarWorks, 1991. https://scholarworks.wm.edu/etd/1539623812.

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A fundamental requirement for the successful operation of a tokamak is the maintenance of a toroidal electric current within the tokamak plasma itself. Maintaining this internal plasma current can be a very difficult technological problem. In this work, a well-known but non-standard method for maintaining the tokamak current called the bootstrap effect is discussed. The bootstrap effect occurs when a fusion plasma is near thermonuclear conditions, and allows the tokamak to greatly amplify its electric current.;Because the bootstrap effect amplifies but does not create a plasma current, it has long been argued that a completely bootstrapped tokamak is not possible. That is, it has been argued that some fraction of the tokamak current must be created externally and injected into the plasma for a bootstrap amplification to occur. This injection of current is not desirable, however, since current-drive schemes are difficult to implement and are only marginally efficient.;An important but largely unexplored implification of the bootstrap effect is that the effect, by itself, creates hollow (outwardly peaked) tokamak current profiles. Hollow tokamak current profiles are known to lead to tearing modes, which are resistive (non-ideal) magnetohydrodynamic (MHD) plasma instabilities. Although usually characterized as harmful for plasma confinement, it turns out that tearing modes may actually be beneficial for the tokamak bootstrap effect.;In this work, a new theoretical approach based on a helicity conserving mean-field Ohm's law is used to examine the interaction between the bootstrap effect and tearing modes. Magnetic helicity is a topological quantity which is conserved even in turbulent plasma. Computer simulation results of the mean-field Ohm's law are presented which suggest that a completely bootstrapped tokamak may indeed be possible. In a completely bootstrapped tokamak, the tokamak self-maintains its electric current by amplifying an intrinsic internal plasma current due to the tearing modes.
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5

Naiim, Habib Marie. "Caractérisation d'une source de particules de carbone créée par ablation laser pour calibrer les mesures d'érosion par spectrosamakcopie dans un tok." Thesis, Aix-Marseille 2, 2011. http://www.theses.fr/2011AIX22122/document.

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Dans un tokamak, les interactions entre le plasma et la paroi conduisent à l'érosion des composants face au plasma. Celle-ci peut nuire au fonctionnement et à la sûreté du tokamak. Afin de respecter les limites imposées pour la sûreté du projet ITER, il est donc nécessaire de contrôler la quantité de matière érodée. La spectroscopie optique d’émission dans le domaine visible est traditionnellement utilisée pour mesurer des flux de particules de la paroi vers le plasma. Ces mesures sont permises grâce à un modèle collisionnel-radiatif s’appuyant sur des données de physique atomique. Cependant, ces données ne prennent pas en compte la géométrie d’observation du diagnostic de spectroscopie, et présentent des incertitudes relativement importantes. D'autre part, les phénomènes de transport, de déposition et de ré-érosion, ainsi que la modification de la transmission ou de la réflexion des optiques peuvent conduire à une mesure erronée de la quantité de matière effectivement érodée. Une méthode de calibration in situ, qui consiste à injecter par laser une source connue de particules de carbone dans la ligne de visée du diagnostic de spectroscopie pendant les décharges plasma, est proposée. L’étude expérimentale de l’ablation laser du carbone a permis de déterminer les conditions optimales à la constitution de cette source, et de caractériser les espèces ablatées. Ces expériences sont complétées par une modélisation du spectre d’émission du plasma induit par laser, afin d’obtenir des informations sur son degré d’ionisation. Enfin, les résultats des premières expériences de validation réalisées sur le tokamak allemand TEXTOR sont présentés et discutés
In a tokamak, plasma-wall interactions lead to the erosion of plasma facing components, which can be detrimental to plasma operation and to the safety of the tokamak. In order to fulfil the safety requirements imposed to the ITER project, it is necessary to monitor the amount of eroded material. Optical emission spectroscopy in the visible range is traditionally used to measure particle fluxes from the wall to the plasma. These measurements are done thanks to a collisionnal-radiative model based on atomic physics data. However, these data don’t take into account the observation geometry of the spectroscopic diagnostic, and suffer from relatively large uncertainties. Furthermore, transport, deposition and re-erosion phenomena, as well as the evolution of the transmission or the reflection of optical components can lead to an incorrect estimation of the amount of effectively eroded material. An in situ calibration technique, which consists in injecting by laser a known carbon particle source in the line of sight of the spectroscopic diagnostic during plasma operation, is proposed. The experimental study of laser ablation of carbon allowed to determine the optimal conditions for the constitution of this source, and to characterise the ablated species. These experiments are completed by a modelling of the emission spectrum of the laser induced plasma, in order to obtain information on its ionisation degree. Finally, results of the first validation experiments realised in the German TEXTOR tokamak are presented and discussed
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6

Hoffman, Edward A. "Low activation tokamak reactors." Thesis, Georgia Institute of Technology, 1995. http://hdl.handle.net/1853/16679.

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7

Sharma, Atul Stefan. "Tokamak modelling & control." Thesis, Imperial College London, 2002. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.270120.

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8

Mavkov, Bojan. "Control of coupled transport in Tokamak plasmas." Thesis, Université Grenoble Alpes (ComUE), 2017. http://www.theses.fr/2017GREAT004/document.

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L'objectif de cette thèse est le développement de nouvelles méthodes d'analyse et de commande pour une classe d'équations aux dérivées partielles couplées permettant de modéliser le transport combiné du flux magnétique et de la pression (produit de la densité et de la température) dans les plasmas tokamak. Le système couplé est représenté par deux équations 1D de diffusion résistive. Dans cette thèse, on a obtenu deux types de modèles: le premier repose sur des principes physiques et le second exploite les données obtenues en utilisant des techniques d'identification des systèmes. La conception de commande est basée sur l'etude en dimension infinie en utilisant l'analyse de Lyapunov. Le contrôle composite est synthétisé en utilisant la théorie des perturbations singulières pour isoler la composante rapide de la composante lente. Tout le travail théorique est implémenté et testé dans des simulations basées sur la physique avancée en utilisant le simulateur de plasma pour les tokamaks DIII-D, ITER et TCV
The objective of this thesis is to propose new methods for analysis and control of partial differential equations that describe the coupling between the transport models of the electron pressure (density multiplied by the temperature) and the magnetic flux in the tokamak plasma. The coupled system is presented by two1D resistive diffusion equations. In this thesis two kinds of control models are obtained. The first is a first-principle driven model and the second one is the data-driven model obtained using system identification techniques. The control design is based on an infinite dimensional setting using Lyapunov analysis. Composite control is designed using singular perturbation theory to divide the fast from the slow component. All the theoretical work is implemented and benchmarked in advanced physics based on simulations using plasma simulator dor DIII-D, ITER and TCV tokamaks
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9

Autricque, Adrien. "Dust transport in tokamaks." Thesis, Aix-Marseille, 2018. http://www.theses.fr/2018AIXM0315/document.

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Les nombreux avantages que présenteraient la fusion thermonucléaire, en particulier la configuration tokamak, en font un candidat idéal en vue de la transition énergétique. Cependant, un certain nombre de difficultés technologiques et physiques restent à résoudre avant que l'étape d'une centrale électrique à fusion puisse voir le jour. La production de poussières est l'une des principales difficultés rencontrées dans les tokamaks. Ces petites particules composées de matériaux présents dans les parois de la machine sont créées par l'érosion de ces parois par le plasma dans lequel les réactions de fusion doivent avoir lieu. Les poussières peuvent être transportées dans le plasma et y libérer de grandes quantités d'impuretés, ce qui a pour conséquence de baisser les performances de la machine (en augmentant les pertes radiatives et en créant des instabilités), et qui peut mettre en danger les composants face au plasma. Dans le but de comprendre le transport de ces poussières, des expériences d'injection sont réalisées sur le tokamak coréen \KSTAR. Les trajectoires des poussières dans le plasma sont observées par des caméras rapides et sont extraites des films à l'aide de routines de traitement d'images. Un code numérique implémentant les derniers modèles d'interactions plasma-poussières est développé, et des comparaisons avec les données expérimentales sont faites, confirmant la tendance générale de ces modèles à la sous-estimation de la longueur des trajectoires des poussières. Des pistes d'amélioration sont présentées. Concernant les sources et puits de poussières, l'accent est porté sur l'adhésion et remise en suspension de particules sur les parois de la machine
Thermonuclear fusion could play an important role amongst the numerous alternative energy sources, especially though the tokamak configuration. It could be a prime candidate for the energy transition, owing to its significant advantages (fuel abundance, low amount of wastes generated, low risks of accidents). However, a certain amount of technological and physical challenges require solving before any fusion power plant can be built. Dust production is one of the major difficulties encountered in tokamaks. These small particles, made out of wall material, are created by erosion of the plasma-facing components by the plasma, where the fusion reactions occur. Dust particles can be transported in the plasma, thereby unleashing large amounts of impurities, which in turn reduces the plasma performances (by raising radiative losses and generating instabilities) and can even jeopardize plasma-facing components. Aiming to understand dust transport, injection experiments are performed on the Korean tokamak \KSTAR. Trajectories are recorded on film via fast cameras and are extracted by image processing routines. A numerical tool implementing the latest models for dust-plasma interactions is developed, and comparisons with experimental data is made, confirming the overall tendency of these models to underestimate the trajectory lengths. Leads of improvements are presented. Concerning dust sources and sinks, the focus is made on dust adhesion and resuspension of dust on the machine walls
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10

Pierre, Ralf. "Lokale Einschlusszeiten eines Tokamak-Plasmas." [S.l. : s.n.], 2003. http://deposit.ddb.de/cgi-bin/dokserv?idn=966424131.

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11

Moradi, Sara. "Transport analysis in tokamak plasmas." Doctoral thesis, Universite Libre de Bruxelles, 2010. http://hdl.handle.net/2013/ULB-DIPOT:oai:dipot.ulb.ac.be:2013/210097.

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In this thesis we mainly focus on the study of the turbulent transport of impurity particles in the plasma due to the electrostatic drift wave microinstabilities. In a fusion reactor, the helium produced as a result of the fusion process is an internal source of impurity. Moreover, impurities are released from the material surfaces surrounding the plasma by a variety of processes: by radiation from plasma, or as a result of sputtering, arcing and evaporation. Impurities in tokamak plasmas introduce a variety of problems. The most immediate effect is the radiated power loss (radiative cooling). Another effect is that the impurity ions produce many electrons and in view of the operating limits on density and pressure, this has the effect of replacing fuel ions. For example, at a given electron density, $n_{e}$, each fully ionized carbon ion (used in the wall materials in the form of graphite) replaces six fuel ions, so that a 7\\% concentration of fully ionized carbon in the plasma core, would reduce the fusion power to one half of the value in a pure plasma. Therefore, for all tokamaks it become an immediate and continuing task to reduce impurities to acceptably low concentrations. However, the presence of impurities, with control, can be beneficial for the plasma performance and reduction of strong plasma heat loads on the plasma facing walls. The radiative cooling effect which was mentioned above can be used at the edge of the plasma in order to distribute the plasma heat more evenly on the whole surface of the vessel walls and therefore, reduce significantly plasma heat bursts on the small regions on the divertor or limiter tiles. The experiments at TEXTOR show that the presence of the impurities at the plasma edge can also improve the performance and reduce the turbulent transport across the magnetic field lines. The observed behavior was explained trough the proposed mechanism of suppression of the most important plasma drift wave microinstability in this region, namely, the Ion Temperature Gradient mode (ITG mode) by the impurities. The impurity's positive impact on the plasma performance offered a possibility to better harness the fusion power, however, it is vital for a fusion reactor to have feedback controls in order to keep impurities at the plasma edge and limit their accumulation in the plasma core where the fusion reactions are happening. In order to have control over the impurity transport we first need to understand different mechanisms responsible for its transport.

One of the least understood areas of the impurity transport and indeed any plasma particle or heat transport in general, is the turbulent transport. Extensive efforts of the fusion plasma community are focused on the subject of turbulent transport. Motivated by the fact that impurity transport is an important issue for the whole community and it is an area which needs fundamental research, we focused our attention on the development of turbulent transport models for impurities and their examination against experiments. In a collaboration effort together with colleagues (theoreticians as well as experimentalist) from different research institutes, we tried to find, through our models, physical mechanisms responsible for experimental observations. Although our main focus in this thesis has been on the impurity transport, we also tried a fresh challenge, and started looking at the problem of drift wave turbulent transport in a different framework all together. Experimental observation of the edge turbulence in the fusion devices show that in the Scrape of Layer (SOL: the layer between last closed magnetic surface and machine walls) plasma is characterized with non-Gaussian statistics and non-Maxwellian Probability Distribution Function (PDF). It has been recognized that the nature of cross-field transport trough the SOL is dominated by turbulence with a significant ballistic or non-local component and it is not simply a diffusive process. There are studies of the SOL turbulent transport using the 2-D fluid descriptions or based on probabilistic models using the Levy statistics (fractional derivatives in space). However, these models are base on the fluid assumptions which is in contradiction with the non-Maxwellian plasmas observed. Therefore, we tried to make a more fundamental study by looking at the effect of the non-Maxwellian plasma on the turbulent transport using a gyro-kinetic formalism. We considered the application of fractional kinetics to plasma physics. This approach, classical indeed, is new in its application. Our aim was to study the effects of a non-Gaussian statistics on the characteristic of the drift waves in fusion plasmas.

Ce travail de thèse porte sur le transport turbulent d'impuretés dans les plasmas de fusion

par confinement magnétique. C'est une question de la plus haute importance pour le développement

de la fusion comme source d'énergie. En effet, une accumulation d'impuretés au coeur

du plasma impliquerait des pertes d'énergie par radiation, conduisant par refroidissement à

l'extinction des réactions de fusion. Il est par contre prévu d'injecter des impuretés dans le

bord du plasma, afin d'extraire la chaleur par rayonnement sans endommager les éléments de

la première paroi. Ces contraintes contradictoires nécessitent un contrôle précis du transport

d'impuretés, afin de minimiser la concentration d'impuretés au coeur du plasma tout en la

maximisant au bord. Une très bonne connaissance de la physique sous-jacente au transport

est donc indispensable. L'effet de la turbulence, principal mécanisme de transport, sur les impuretés

est alors une question centrale. Dans cette thèse, un code numérique, AFC-FL, a été développé sur la base d'une approche ``fluide' linéaire pour la turbulence d'ondes de dérive. Il calcule les taux de croissance qui caractérisent la rapidité de l'amorçage des instabilités. L'analyse de stabilité est complétée par l'évaluation des taux de croissance en présence d'un gradient de densité, un cisaillement magnétique ou un nombre arbitraire de différentes espèces d'impureté. Les formules complètes du flux turbulent d'impuretés pour ces taux de croissance calculés des instabilités des ondes de dérive ont été dérivées. Un modèle de transport anormal qui nous permet d'étudier la dépendence du transport en fonction de la charge d'impureté a été développé. Ce modèle prend en compte les effets collisionnels entre les ions, l'impureté et les particules principales de plasma. Une telle dépendence du transport anormal en fonction de la charge de l'impureté est observée dans les expériences et il a été montré que les résultats obtenus sont en bon accord avec les observations expérimentales. Nous avons également étudié l'effet des impuretés sur le confinement de l'énergie dans les plasmas du tokamak JET. La modélisation de transport a été exécutée pour des plasmas avec injection de néon dans la périphérie du tokamak. Cette technique est utilisée afin d'extraire la chaleur par rayonnement sans endommager la paroi et pour réduire certaines instabilités (ELM). Des simulations du code RITM ont été comparées à des mesures effectuées lors d'expériences au JET. Il a été montré que l'injection de néon mène toujours à une dégradation du confinement par rapport aux décharges sans néon. Cependant, l'augmentation de la charge effective, en raison du presence du néon peut diminuer le taux de croissance d'autres instabilité (ITG) et amèliorer le confinement du coeur du plasma. Ce confinement amélioré du coeur peut alors compenser la dégradation au bord et le confinement global du plasma peut s'améliorer.


Doctorat en sciences, Spécialisation physique
info:eu-repo/semantics/nonPublished

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12

Fernandes, Tiago. "Instabilidades MHD no Tokamak TCABR." Universidade de São Paulo, 2016. http://www.teses.usp.br/teses/disponiveis/43/43134/tde-03062016-155509/.

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Este trabalho descreve o estudo das instabilidades magneto-hidro-dinâmicas (MHD) comumente observadas nas descargas elétricas de plasma no tokamak TCABR, do Instituto de Física da USP. Dois diagnósticos principais foram empregados para observar essas instabilidades: um conjunto poloidal de 24 bobinas magnéticas (bobinas de Mirnov) colocadas próximas à borda do plasma e um medidor de emissões na faixa do Ultra Violeta e de raios X moles com 20 canais (sistema SXR), cujo circuito de condicionamento de sinais foi aprimorado como parte deste trabalho. Esses diagnósticos foram escolhidos porque fornecem informações complementares, uma vez que o sistema SXR observa a parte central da coluna de plasma, enquanto as bobinas de Mirnov detectam as instabilidades MHD na região mais externa da coluna. As informações coletadas por esses diagnósticos foram submetidas à análise espectral com resolução temporal e espacial, possibilitando determinar a evolução das características espectrais e espaciais das instabilidades MHD observadas. Essas análises revelaram que durante a etapa inicial da formação do plasma (quando a corrente de plasma ainda está aumentando) ilhas magnéticas com números de onda decrescente, identificadas como sendo modos kink de borda, são detectadas nas bobinas de Mirnov. Após a formação do plasma, quando os parâmetros de equilíbrio estão relativamente estáveis (platô), oscilações são detectadas tanto nas bobinas de Mirnov quanto no sistema de SXR, indicando a presença de instabilidades MHD em toda a coluna de plasma. Em geral as oscilações medidas nas bobinas de Mirnov tem baixa amplitude e correspondem a pequenas ilhas magnéticas que foram identificadas como sendo modos de ruptura (modos tearing). Por outro lado, as instabilidades na região central foram identificadas como dentes de serra, que correspondem a relaxações periódicas da região interna à superfície magnética com fator de segurança q=1 e que são acompanhadas de oscilações precursoras, cuja amplitude depende da fase do ciclo de relaxação. Devido à essa modulação de amplitude, aparecem picos de frequência satélite nos espectrogramas dos sinais do SXR. Além disso, devido ao fato dos ciclos de relaxação não serem sinusoidais, os harmônicos da frequência de relaxação também aparecem nesses espectrogramas. No entanto, em muitas descargas do TCABR, a intensidade das oscilações medidas nas bobinas de Mirnov aumentam significativamente durante o platô, com efeitos sobre a frequência de todas as instabilidades MHD, até mesmo sobre os dentes de serra localizados na região central da coluna. Em todos os casos, observou-se que durante o platô a frequência das ilhas magnéticas coincide com a frequência das oscilações precursoras do dente de serra, apesar de serem duas instabilidades distintas, localizadas em posições radiais muito diferentes. Essa coincidência de frequências possibilitou descrever a evolução em frequência de todas as oscilações detectadas em diversos diagnósticos com base em apenas duas frequências básicas: a dos ciclos de relaxação dente de serra e a das ilhas magnéticas.
This work describes the study of magneto-hydro-dynamic instabilities (MHD) commonly observed in plasma discharges in tokamak TCABR (at Instituto de Física da USP). Two main diagnostics were employed to observe these instabilities: a poloidal set of 24 magnetic coils (Mirnov coils) placed near the plasma border and a detector of emissions in the Ultra Violet and soft X-ray range with 20 channels (SXR system) which improvement of the signal conditioning circuit was done as part of this work. These diagnostics were chosen because they provide complementary information, since the SXR system measures the central part of the plasma column, while the Mirnov coils detect the MHD instabilities in the outer part of the column. The information collected by these diagnoses was submitted to spectral analysis with temporal and spatial resolution, making it possible to determine the evolution of the spectral and spatial characteristics of the observed MHD instabilities. These analyzes revealed that during the initial stage of the plasma formation (when the plasma current is still increasing) magnetic islands with decreasing wave numbers, identified as edge kink modes, are detected in the Mirnov coils. After the plasma formation, when the equilibrium parameters are relatively flat (plateau), oscillations are detected in both Mirnov coils and SXR system, indicating the presence of MHD instability in the whole plasma column. In general, the fluctuations measured by the Mirnov coils have low amplitude corresponding to small magnetic islands, which were identified as tearing modes. On the other hand, the instabilities at the central region were identified as sawteeth oscillations that correspond to periodic relaxations in the internal region of the magnetic surface with safety factor q = 1 and that are accompanied by precursor oscillations which amplitude depends on the phase of the relaxation cycles. Due to this amplitude modulation, frequency satellite peaks appear in the spectrograms of the SXR signals. Furthermore, due to the fact that relaxation cycles are not sinusoidal, harmonics of the relaxation frequency also appear in the spectrograms. However, in many TCABR discharges, the intensity of the oscillations measured by the Mirnov coils increase significantly during the plateau, with affects the frequency of all MHD instabilities, even over the sawteeth in the central region of the column. In all cases, it was observed that during the plateau the frequency of the magnetic islands coincides with the frequency of the sawtooth precursors, although they are two different instabilities located in separated radial positions. This coincidence of frequencies allowed describing the frequency evolution of all measured oscillations by considering only two basic frequencies: the cycles of sawtooth relaxation and the magnetic islands.
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13

Oliveira, Alexandre Machado de. "Emissivity Profiles at TCABR Tokamak." Universidade de São Paulo, 2017. http://www.teses.usp.br/teses/disponiveis/43/43134/tde-05092017-154738/.

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The determination of plasma equilibrium profiles is necessary to evaluate the properties of the confinement and to investigate perturbation effects. Optical diagnostics can be used to determine some of these profiles. However, these diagnostics measure all emitted radiation at a solid angle that illuminate each diagnostic channel through a slit. Therefore, the real measured quantity is the emissivity integrated along the line-of-sight and some unfolding procedure, like Abels inversion, is commonly used to recover the emissivity profile. In TCABR tokamak, at the Physics Institute of the University of São Paulo, a 24-channel bolometer and a 20-channel soft X-ray optical diagnostics are used to measure the plasma emissivity in wavelength range from 1.0 to 1000 nm, depending on the used filters. In this work, a numerical simulation is used to compute the signal measured by the diagnostics for a given emissivity profile, allowing direct comparison with the experimental data and avoiding the use of the Abel\'s inversion directly and the numerical difficulties associated with unfolding procedures. By considering TCABR tokamak geometry, spatial coordinates can be related to the normalized linear coordinates of the plasma by imposing a plasma emissivity model that depends on some free parameters, allowing the emissivity resulting in each point can be calculated. Thus, the luminosity of each channel is calculated by the integral of the emissivity modeled in each line-of-sight (Radon Transformation). Emissivity model free parameters are determined by fitting calculated luminosity to measured one. We considered three types of emissivity profiles: a parabolic model in law of power, a Gaussian model and a model based on Bessel functions. We observed that the parabolic profile fits well the bolometer data, while the Gaussian profile is adequate to describe the data obtained with the soft X-ray detector.
A determinação dos perfis de equilíbrio do plasma é necessária para avaliar as propriedades do confinamento e para investigar os efeitos de perturbações. Diagnósticos ópticos podem ser usados para determinar alguns desses perfis. No entanto, esses diagnósticos medem toda a radiação luminosa emitida em um ângulo sólido que ilumina cada canal do detector através de uma fenda. Assim, a verdadeira grandeza física medida é a emissividade integrada ao longo da linha de visada. Com isso, algum procedimento de deconvolução, como a inversão de Abel, se faz necessário para obter o perfil de emissividade. No tokamak TCABR do Instituto de Física da USP, um bolômetro de 24 canais e um detector de raios-X moles de 20 canais são utilizados para medir a emissividade do plasma no intervalo de comprimento de onda de 1 a 1.000 nm, dependendo dos filtros utilizados. Neste trabalho, uma simulação numérica é usada para calcular o sinal medido pelos diagnósticos para um dado perfil de emissividade, possibilitando a comparação direta com os dados experimentais, evitando a realização da inversão de Abel e os problemas numéricos associados aos procedimentos de deconvolução. Pela consideração da geometria do tokamak TCABR, as coordenadas espaciais podem ser relacionadas com as coordenadas lineares normalizadas do plasma por meio da imposição de um modelo de emissividade para o plasma que dependa de alguns parâmetros livres, permitindo que a emissividade resultante em cada ponto possa ser calculada. Assim, a luminosidade de cada canal é calculada pela integral da emissividade modelada em cada linha de visada (Transformada de Radon). Os parâmetros livres dos perfis de emissividade são determinados ajustando-se as luminosidades calculadas em termos das luminosidades medidas. Nós consideramos três modelos de perfis de emissividade: um modelo parabólico em lei de potência, um modelo gaussiano e um modelo baseado em funções de Bessel. Observamos que o perfil parabólico ajusta-se bem aos dados do bolômetro, ao passo que o perfil gaussiano é adequado para descrever os dados obtidos com o detector de raios-X moles.
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14

Abiteboul, Jérémie. "Transport turbulent et néoclassique de quantité de mouvement toroïdale dans les plasmas de tokamak." Thesis, Aix-Marseille, 2012. http://www.theses.fr/2012AIXM4062/document.

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L'objectif de la fusion par confinement magnétique, et notamment du tokamak, est de produire de l'énergie à partir des réactions de fusion nucléaire, dans un plasma à faible densité et haute température. Expérimentalement, une amélioration de la performance des tokamaks a été observée en présence de rotation toroïdale. Or, les sources extérieurs de quantité de mouvement seront très limitées dans les futurs tokamaks, et notamment ITER. Une compréhension de la physique de la génération intrinsèque de rotation toroïdale permettrait donc de prédire les profils de rotation dans les expériences futures. Parmi les mécanismes envisagés, on s'intéresse ici à la génération de rotation par la turbulence, qui domine le transport de la chaleur dans les tokamaks. Les plasmas de fusion étant faiblement collisionnels, la modélisation de cette turbulence suppose un modèle cinétique décrivant la fonction de distribution des particules dans l'espace des phases à six dimensions (position et vitesse). Cependant, ce modèle peut être réduit à cinq dimensions pour des fréquences inférieures à la fréquence cyclotronique des particules. Le modèle gyrocinétique qui découle de cette approximation est alors accessible avec les ressources numériques actuelles. Les travaux présentés portent sur l'étude du transport de quantité de mouvement toroïdale dans les plasmas de tokamak, dans le cadre du modèle gyrocinétique. Dans un premier temps, nous montrons que ce modèle réduit permet une description précise du transport de quantité de mouvement en dérivant une équation locale de conservation. Cette équation est vérifiée numériquement à l'aide du code gyrocinétique GYSELA
The goal of magnetic confinement devices such as tokamaks is to produce energy from nuclear fusion reactions in plasmas at low densities and high temperatures. Experimentally, toroidal flows have been found to significantly improve the energy confinement, and therefore the performance of the machine. As extrinsic momentum sources will be limited in future fusion devices such as ITER, an understanding of the physics of toroidal momentum transport and the generation of intrinsic toroidal rotation in tokamaks would be an important step in order to predict the rotation profile in experiments. Among the mechanisms expected to contribute to the generation of toroidal rotation is the transport of momentum by electrostatic turbulence, which governs heat transport in tokamaks. Due to the low collisionality of the plasma, kinetic modeling is mandatory for the study of tokamak turbulence. In principle, this implies the modeling of a six-dimensional distribution function representing the density of particles in position and velocity phase-space, which can be reduced to five dimensions when considering only frequencies below the particle cyclotron frequency. This approximation, relevant for the study of turbulence in tokamaks, leads to the so-called gyrokinetic model and brings the computational cost of the model within the presently available numerical resources. In this work, we study the transport of toroidal momentum in tokamaks in the framework of the gyrokinetic model
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15

Vayakis, George. "Anomalous transport in the tokamak edge." Thesis, University of Oxford, 1991. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.291539.

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16

Casson, Francis James. "Turbulent transport in rotating tokamak plasmas." Thesis, University of Warwick, 2011. http://wrap.warwick.ac.uk/36765/.

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Small scale turbulence in a magnetically confined fusion plasma drives energy and particle transport which determine the confinement. The plasma in a tokamak experiment has a toroidal rotation which may be driven externally, but can also arise spontaneously from turbulent momentum transport. This thesis investigates the interaction between turbulence and rotation via nonlinear numerical simulations, which use the gyrokinetic description in the frame that corotates with the plasma. A local gyrokinetic code is extended to include both the centrifugal force, and the stabilising effect of sheared equilibrium flow. Sheared flow perpendicular to the magnetic field suppresses the turbulence, and also breaks a symmetry of the local model. The resulting asymmetry creates a turbulent residual stress which can counteract diffusive momentum transport and contribute to spontaneous rotation. The competition between symmetry breaking and turbulence suppression results in a maximum in the nondiffusive momentum flux at intermediate shearing rates. Whilst this component of the momentum transport is driven by the sheared flow, it is also found to be suppressed by the shearing more strongly than the thermal transport. The direction of the residual stress reverses for negative magnetic shear, but also persists at zero magnetic shear. The parallel component of the centrifugal force traps particles on the outboard side of the plasma, which destabilises trapped particle driven modes. The perpendicular component of the centrifugal force appears as a centrifugal drift which modifies the phase relation between density and electric field perturbations, and is stabilising for both electron and ion driven instabilities. For ion temperature gradient dominated turbulence, an increased fraction of slow trapped electrons enhances the convective particle pinch, suggesting increased density peaking for strongly rotating plasmas. Heavy impurities feel the centrifugal force more strongly, therefore the effects of rotation are significant for impurities even when the bulk ion Mach number is low. For ion driven modes, rotation results in a strong impurity convection inward, whilst a more moderate convection outward is found for electron driven modes.
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17

Hernández, Manuel S. (Manuel Segundo). "Meta-analysis of Tokamak reactor designs." Thesis, Massachusetts Institute of Technology, 2016. http://hdl.handle.net/1721.1/106768.

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Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2016.
Cataloged from PDF version of thesis.
Includes bibliographical references (pages 55-60).
The long-term interest in nuclear fusion using tokamaks has yielded many published reactor designs. This study performs the first meta-analysis of tokamak reactor designs in an attempt to unveil new understanding not available in the traditional bottom-up method of looking at each design individually. Forty tokamak designs intended to produce significant fusion power at gains above one were identified in the published literature. Thirty-three important parameters describing a tokamak design were compiled by examining the set. The parameters from each design were extracted and placed into a database and plotted against each other to identify trends and outliers. Major outliers include two low aspect ratio designs and two He-3 reactor designs. Two classes are apparent in the database indicating two design philosophies: large major radius (~7 m), high power (~1.8 GW), and low density (~1 * 1020 m-3) designs utilizing superconducting magnets; and small major radius (~2.5 m), low power (~0.2 GW), and high density (~4* 1020 m-3 designs utilizing copper magnets. The former class has longer confinement times, higher plasma current, and lower magnetic field while the latter class tends to have lower gain, higher power per surface area, higher power per volume, and much smaller stored magnetic energies. Between the two sets, the non-dimensional plasma physics parameters are similar. These two basic design strategies have been in practice for the last 40 years. Since tokamak designs were first published, there has been little appreciable change in the mean and design envelope of the major parameters such as major radius, fusion power, magnetic field, and plasma current and of the plasma physics parameters such as beta, safety factor, temperature, density, and confinement time. The lack of significant change suggests that no major technological or physics breakthrough that could radically affect design philosophy has been discovered, and neither design philosophy has dominated. Trade-offs in triple product are apparent as all designs are at similar plasma temperature except He-3 reactors, while confinement time and density vary inversely among designs. The major dependencies on plasma current and size in the experimental confinement time scaling are also apparent. The conservatism inherent in reactor designs can be inferred from plasma physics parameters such as the confinement enhancement factor, normalized beta, and safety factor. The database indicates designers push all plasma physics limits simultaneously instead of individually.
by Manuel S. Hernandez.
S.B.
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18

Abel, Ian G. "Multiscale gyrokinetics for rotating tokamak plasmas." Thesis, University of Oxford, 2013. http://ora.ox.ac.uk/objects/uuid:254aa8c8-a68f-401a-8a32-432d26717b25.

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This thesis presents a complete theoretical framework for turbulence and transport in tokamak plasmas. The fundamental scale separations present in plasma turbulence are codified as an asymptotic expansion in the ratio of the gyroradius to the equilibrium scale length. Proceeding order-by- order in this expansion, a framework for plasma turbulence is developed. It comprises an instantaneous equilibrium, the fluctuations driven by gra- dients in the equilibrium quantities, and the transport-timescale evolu- tion of mean profiles of these quantities driven by the fluctuations. The equilibrium distribution functions are local Maxwellians with each flux surface rotating toroidally as a rigid body. Large-scale deviations of the distribution function from a Maxwellian are given by neoclassical theory. The fluctuations are determined by the high-flow gyrokinetic equation, from which we derive the governing principle for gyrokinetic turbulence in tokamaks: the conservation and local cascade of free energy. Transport equations for the evolution of the mean density, temperature and flow ve- locity profiles are derived. These transport equations show how the neo- classical corrections and the fluctuations act back upon the mean profiles through fluxes and heating. This framework is further developed by exploiting the scale separation between ions and the electrons. The gyrokinetic equation is expanded in powers of the electron to ion mass ratio, which provides a rigorous method for deriving the electron response to ion-scale turbulence. We prove that such turbulence cannot change the magnetic topology, and ar- gue that, therefore, the magnetic field lies on fluctuating flux surfaces. These flux surfaces are used to construct magnetic coordinates, and in these coordinates a closed system of equations for the electron response is derived. All fast electron timescales have been eliminated from these equations. Simplified transport equations for electrons in this limit are also derived.
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19

Kloe, Joost de. "Pellet-plasma interaction in a tokamak /." [S.l. : s.n], 2000. http://catalogue.bnf.fr/ark:/12148/cb37725261x.

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20

Song, Shaodong. "Etude du transport de la chaleur et des particules dans les tokamaks Tore Supra et HL-2A." Thesis, Aix-Marseille 1, 2011. http://www.theses.fr/2011AIX10142/document.

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Le transport de la chaleur et des particules est un des sujets de recherche fondamentaux de la physique des plasmas chauds confinés par des champs magnétiques, systèmes physiques qui sont étudiés dans le cadre des recherches sur la fusion thermonucléaire contrôlée. Ces phénomènes de transport sont essentiellement liés à la turbulence électromagnétique et ils sont donc extrêmement difficiles à modéliser par la théorie. Des expériences spécifiques sont alors réalisées sur des machines expérimentales, telles que les tokamaks ou les stellarators, afin d'améliorer la connaissance de ces phénomènes. Cette thèse décrit des études expérimentales de ce type réalisées sur deux tokamaks de grande dimension: Tore Supra (machine basée au CEA/Cadarache) et HL-2A (basée au South-Western Institute of Physics, Chengdu, Chine). La technique utilisée consiste à injecter, de façon modulée dans le temps, des ondes de forte puissance afin de perturber la température électronique du plasma, et des faisceaux supersoniques de particules pour en perturber la densité. La température est mesurée par l'Emission Cyclotronique Electronique et la densité par Réflectométrie micro-onde. Ces expériences on mis en évidence une convection de la chaleur vers l'intérieur du plasma (un phénomène dont l'existence est toujours controversée), et des effets dus aux termes non-diagonaux de la matrice de transport. Ces résultats ont été comparés aux modèles de transport existants
Heat and particle transport is one of the fundamental subjects of research in the physics of hot plasmas confined by magnetic fields, a class of physical systems that are studied in the framework of research on controlled thermonuclear fusion. These transport phenomena are mainly related to electromagnetic turbulence and are therefore extremely difficult to model at a first-principle level. Specific experiments in this area, on plasma devices such as tokamaks or stellarators, are widely used to improve understanding of these phenomena. This thesis reports on experimental studies performed on two large tokamaks : Tore Supra (based at CEA/Cadarache, France) and HL-2A (based at the South-Western Institute of Physics, Chengdu, China). The technique used consists in modulated injection of wave power to perturb the electron temperature and/or of Supersonic Molecular Beams to perturb the plasma density. Temperature is then measured by Electron Cyclotron Emission and density by Reflectometry, and Fourier analysis is used to determine the transport properties. Evidence has been found of inward heat convection (a phenomenon whose existence is still controversial) as well as of peculiar effects due to the non-diagonal terms of the transport matrix. Comparison with transport models has been carried out
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21

Hamed, Myriam. "Electron heat transport in tokamak H-mode pedestals." Electronic Thesis or Diss., Aix-Marseille, 2019. http://theses.univ-amu.fr.lama.univ-amu.fr/191128_HAMED_534gjvrc761ijwn176jbu525de_TH.pdf.

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Dans les plasmas en mode H, la modélisation de la dynamique du piédestal est une question importante pour prédire les profils de température et de densité dans le bord et le cœur des tokamaks. Le modèle EPED , basé sur la stabilité de modes Magnetohydrodynamiques, est le plus souvent utilisé pour caractériser la région du piédestal. Ce modèle EPED ne prend pas en compte les microinstabilités pouvant se développer dans la région du piédestal. Ainsi, la prédiction des caractéristiques du piédestal est toujours une question ouverte. De plus, certaines analyses récentes des plasmas JET suggèrent qu’une autre classe d’instabilités, appelée modes de microdéchirement, peut être responsable du transport de chaleur des électrons et jouer ainsi un certain rôle dans la détermination des caractéristiques du piédestal. Les modes de microdéchirement appartiennent à une classe d’instabilités où une modification de la topologie des lignes de champ magnétique. Cela conduit à la formation d’îlots magnétiques qui peuvent augmenter le transport de chaleur électronique. La stabilité des MTMs a été théoriquement étudiée dans le passé, montrant qu’une couche de courant est stable en l’absence de collisions. En revanche, des simulations gyrocinétiques récentes ont révélé que les MTMs étaient instables, même à faible collisionalité. Le but de cette thèse est d'améliorer la compréhension de la stabilité des modes de microdéchirement en comparant une théorie analytique avec des simulations gyrocinétique. Plus précisément, différents mécanismes physiques (dérive magnétique..) ont été ajouté progressivement au modèle dans le but de réconcilier les résultats numériques avec la théorie analytique
In H-mode plasmas, the modeling of the pedestal dynamics is an important issue to predict temperature and density profiles in the tokamak edge and therefore in the core. The EPED model, based on the stability of large scales MagnetoHydroDynamic (MHD) modes, is most commonly used to characterize the pedestal region. The EPED model has been successful until now. However, EPED model does not take into account small scales instabilities linked the the sharp pressure gradient and the pedestal characteristics prediction in terms of width and height is still open. Moreover, some recent analysis of JET plasmas suggest that another class of instabilities, called microtearing modes, may be responsible for electron heat transport in the pedestal, and thereby play some role in determining the pedestal characteristics. Microtearing modes belong to a class of instabilities where a modification of the magnetic field line topology is induced at the ion Larmor radius scale. This leads to the formation of magnetic islands, which can enhance the electron heat transport. The stability of MTMs has been theoretically studied in the past showing that a slab current sheet is stable in the absence of collisions. In contrast, recent gyrokinetic simulations in toroidal geometry found unstable MTMs, even at low collisionality. The purpose of our work is to improve the MTM stability understanding by comparing new analytical theory to linear gyrokinetic simulations. More precisely, physical mechanisms (magnetic drift, electric potential) are progressively included in the analytical description to recover the numerical simulations results and to "reconcile" numerical MTM investigations with theory
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22

Savčenko, Fedir. "Mitigation of disruptions in a tokamak by means of large gas injection." [S.l.] : [s.n.], 2003. http://deposit.ddb.de/cgi-bin/dokserv?idn=971442193.

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Marchuk, Oleksandr. "Modeling of He-like spectra measured at the tokamaks TEXTOR and TORE SUPRA." [S.l.] : [s.n.], 2004. http://deposit.ddb.de/cgi-bin/dokserv?idn=971969884.

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Tardini, Giovanni. "Validation of theory based transport models in tokamak plasmas." [S.l.] : [s.n.], 2003. http://deposit.ddb.de/cgi-bin/dokserv?idn=969342926.

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Thomsen, Henning. "A Dynamics investigation into edge plasma turbulence." [S.l.] : [s.n.], 2002. http://deposit.ddb.de/cgi-bin/dokserv?idn=96493230X.

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Savtchkov, Alexei. "Mitigation of disruptions in a tokamak by means of large gas injection." [S.l. : s.n.], 2003. http://deposit.ddb.de/cgi-bin/dokserv?idn=971442193.

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Merkl, Doris. "Current holes and other structures in motional Stark effect measurements." [S.l. : s.n.], 2004. http://deposit.ddb.de/cgi-bin/dokserv?idn=971921830.

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Lauber, Philipp. "Linear gyrokinetic description of fast particle effects on the MHD stability in tokamaks." [S.l. : s.n.], 2003. http://deposit.ddb.de/cgi-bin/dokserv?idn=969890222.

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Na, Yong-Su. "Modelling of current profile control in tokamak plasmas." [S.l. : s.n.], 2003. http://deposit.ddb.de/cgi-bin/dokserv?idn=970018460.

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30

Daviot, Ronan. "Etude des champs de flux thermique sur les composants faisant face au plasma dans un tokamak à partir de mesures de température par thermographie infrarouge." Phd thesis, Ecole Centrale Paris, 2010. http://tel.archives-ouvertes.fr/tel-00534809.

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La connaissance des champs de flux thermique sur les composants d'un tokamak estun élément important de la conception de ce type de machines. L'objectif de cette thèse est dedévelopper et mettre en œuvre une méthode de calcul de ces flux à partir des mesures detempérature par thermographie infrarouge. Ce travail repose sur trois objectifs qui concernentles tokamaks actuels et futurs (ITER) : mesurer un champ de température d'une paroiréfléchissante par pyrométrie photothermique (pré-étude), caractériser les propriétésthermiques des dépôts sur les surfaces des composants et développer un calcultridimensionnel et non-linéaire du flux.Une comparaison de différentes techniques de pyrométries monochromatique,bichromatique et photothermique est effectuée sur une expérience de laboratoire de mesure detempérature. Une sensibilité importante de la technique de pyrométrie photothermique auxgradients de température sur la zone observée a été mise en évidence.Les dépôts en surface des composants exposés au plasma, sans inertie thermique, sontmodélisés par des champs de résistance thermique équivalente transverse. Ce champ derésistance est déterminé, en tout point de mesure, par confrontation du champ de températurede paroi issu de la thermographie avec le résultat d'une simulation par un modèlemonodimensionnel linéaire du composant. Une information sur la répartition spatiale du dépôtà la surface d'un composant est alors obtenue.Un calcul tridimensionnel et non-linéaire du champ de flux pariétal sur un composantest développé, par une méthode d'éléments finis, à partir de maillages de composants issus deCAO. La sensibilité du flux calculé à la précision des mesures de températures est discutée.Cette méthode est appliquée à des campagnes de mesures de températurebidimensionnelles par thermographie infrarouge sur des composants du tokamak JET. Leschamps de flux sur les tuiles du divertor, la protection supérieure et les protections poloïdalesinternes et externes sont déterminés et étudiés dans les deux directions, poloïdale ettoroïdale, du tokamak. La symétrie toroïdale du flux, d'une tuile à l'autre, est établie.L'influence de la résolution spatiale des mesures sur les flux calculés est discutée, à partir decomparaisons de résultats obtenus à partir de deux systèmes de thermographie de résolutionsdifférentes.
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31

Bae, Cheonho. "Extension of neoclassical rotation theory for tokamaks to account for geometric expansion/compression of magnetic flux surfaces." Diss., Georgia Institute of Technology, 2012. http://hdl.handle.net/1853/45839.

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An extended neoclassical rotation theory (poloidal and toroidal) is developed from the fluid moment equations, using the Braginskii decomposition of the viscosity tensor extended to generalized curvilinear geometry and a neoclassical calculation of the parallel viscosity coefficient interpolated over collision regimes. Important poloidal dependences of density and velocity are calculated using the Miller equilibrium flux surface geometry representation, which takes into account elongation, triangularity, flux surface compression/expansion and the Shafranov shift. The resulting set of eight (for a two-ion-species plasma model) coupled nonlinear equations for the flux surface averaged poloidal and toroidal rotation velocities and for the up-down and in-out density asymmetries for both ion species are solved numerically. The numerical solution methodology, a combination of nonlinear Successive Over-Relaxation(SOR) and Simulated Annealing(SA), is also discussed. Comparison of prediction with measured carbon poloidal and toroidal rotation velocities in a co-injected and a counter-injected H-mode discharges in DIII-D [J. Luxon, Nucl. Fusion 42, 614 (2002)] indicates agreement to within <10% except in the very edge in the co-injected discharge.
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32

Asp, Elina. "Drift-Type Waves in Rotating Tokamak Plasma." Doctoral thesis, Uppsala University, Department of Astronomy and Space Physics, 2003. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-3400.

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The concept of energy production through the fusion of two light nuclei has been studied since the 1950’s. One of the major problems that fusion scientists have encountered is the confinement of the hot ionised gas, i.e. the plasma, in which the fusion process takes place. The most common way to contain the plasma is by using at magnetic field configuration, in which the plasma takes a doughnut-like shape. Experimental devices of this kind are referred to as tokamaks. For the fusion process to proceed at an adequate rate, the temperature of the plasma must exceed 100,000,000C. Such a high temperature forces the plasma out of thermodynamical equilibrium which plasma tries to regain by exciting a number of turbulent processes. After successfully quenching the lager scale magnetohydrodynamic turbulence that may instantly disrupt the plasma, a smaller scale turbulence revealed itself. As this smaller scale turbulence behaved contrary to the common theory at the time, it was referred to as anomalous. This kind of turbulence does not directly threaten existents of the plasma, but it allows for a leakage of heat and particles which inhibits the fusion reactions. It is thus essential to understand the origin of anomalous turbulence, the transport it generates and most importantly, how to reduce it. Today it is believed that anomalous transport is due to drift-type waves driven by temperature and density inhomogeneities and the theoretical treatment of these waves is the topic of this thesis.

The first part of the thesis contains a rigorous analytical two-fluid treatment of drift waves driven solely by density inhomogeneities. Effects of the toroidal magnetic field configuration, the Landau resonance, a peaked diamagnetic frequency and a sheared rotation of the plasma have been taken into account. These effects either stabilise or destabilise the drift waves and to determine the net result on the drift waves requires careful analysis. To this end, dispersion relations have been obtained in various limits to determine when to expect the different effects to be dominant. The main result of this part is that with a large enough rotational shear, the drift waves will be quenched.

In the second part we focus on temperature effects and thus treat reactive drift waves, specifically ion temperature gradient and trapped electron modes. In fusion plasmas the α-particles, created as a by-product of the fusion process, transfer the better part of their energy to the electrons and hence the electron temperature is expected to exceed the ion temperature. In most experiments until today, the ion temperature is greater than the electron temperature and this have been proven to improve the plasma confinement. To predict the performance of future fusion plasmas, where the fusion process is ongoing, a comprehensive study of hot-electron plasmas and external heating effects have been carried out. Especially the stiffness (heat flux vs. inverse temperature length scale) of the plasma has been examined. This work was performed by simulations done with the JETTO code utilising the Weiland model. The outcome of these simulations shows that the plasma response to strong heating is very stiff and that the plasma energy confinement time seems to vary little in the hot-electron mode.

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33

Seto, Haruki. "Two-Dimensional Transport Modeling of Tokamak Plasmas." 京都大学 (Kyoto University), 2014. http://hdl.handle.net/2433/188588.

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34

You, Setthivoine. "Computational and experimental studies of tokamak refuelling." Thesis, Imperial College London, 2002. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.396290.

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35

Ford, Oliver P. "Tokamak Plasma Analysis through Bayesian Diagnostic Modelling." Thesis, Imperial College London, 2010. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.526369.

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36

Podpaly, Yuri Anatoly. "Rotation generation and transport in tokamak plasmas." Thesis, Massachusetts Institute of Technology, 2012. http://hdl.handle.net/1721.1/77061.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012.
Cataloged from PDF version of thesis.
Includes bibliographical references (p. 187-201).
Plasma toroidal rotation is a factor important for plasma stability and transport, but it is still a fairly poorly understood area of physics. This thesis focuses on three aspects of rotation: momentum transport, Ohmic rotation reversals, and LHCD induced rotation. Momentum transport is approached in a semi-empirical method through the development of the "Toy Model." The "Toy Model" assumes that the toroidal momentum is transported via diffusive and convective profiles, and, using assumptions about the diffusive and convective terms, it can generate the profiles of the residual stress or source as a function of space and time. Several resultant source profile calculations are shown for SSEP sweeps, rotation reversals, H-modes, and I-modes. Generally, it is observed that the convective profiles do not greatly improve the fits to the data, and that source profiles have peaks around the steep core rotation gradient region of the plasma. Rotation reversals, spontaneous reversals of the rotation direction during the Ohmic phase, are also described in this work. It is seen that they are related to the Linear Ohmic Confinement (LOC) to Saturated Ohmic Confinement (SOC) regime changeover. This relation is supported through linear gyrokinetic simulations that show that the co- to counter- reversal coincides with a change from marginally electron to ion diamagnetic direction most unstable modes which is believed to play a role in the LOC to SOC explanation as well. Lower Hybrid Current Drive (LHCD) induced rotation is also described, including the first experimental observations of bi-directional rotation on a single tokamak. These observations help to explain differences in rotation seen among the various devices running lower hybrid. The LHCD rotation reverses direction as a function of plasma current, and this occurs in a similar parameter space as the Ohmic rotation reversal; it also has turbulence changes that are reminiscent of the Ohmic reversal as well. This suggests that LHCD is, in fact, causing the plasma to transition from the ITG dominated regime to the TEM dominated regime, which explains the rotation differences. These experiments and models provide new tools to understand rotation transport and generation in tokamaks.
by Yuri Anatoly Podpaly.
Ph.D.
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37

Monteiro, Marcelo de Jesus Rangel. "Espalhamento Thomson multipassagem no Tokamak Nova-UNICAMP." [s.n.], 2003. http://repositorio.unicamp.br/jspui/handle/REPOSIP/278476.

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Orientador: Munemasa Machida
Tese (doutorado) - Universidade Estadual de Campinas, Instituto de Fisica Gleb Wataghin
Made available in DSpace on 2018-08-03T17:00:15Z (GMT). No. of bitstreams: 1 Monteiro_MarcelodeJesusRangel_D.pdf: 3635325 bytes, checksum: 206622522804a8aa49d97c248dffa665 (MD5) Previous issue date: 2003
Resumo: Foram executados no tokamak NOVA-UNICAMP os trabalhos da tese que consistiram em duas partes distintas: a primeira ligada à implementação de programas e operação da máquina, e a segunda compreendeu a realização do diagnóstico de espalhamento Thomson utilizado para a medida direta da temperatura eletrônica, e indireta, via espalhamento Rayleigh, da densidade eletrônica do plasma. Com relação à primeira parte, foram desenvolvidos os programas para a aquisição e tratamento dos principais dados provenientes do tokamak e estudado (e determinado) durante os trabalhos as melhores condições de operação da máquina. Já com relação à segunda parte, foi implantado o sistema de multipassagem para o feixe do laser de rubi, que permitiu o aumento da potência incidente em torno de seis vezes, e foi utilizado um novo detector multicanal, o XP 1752 da Philips, que é uma matriz de 8 x 8, totalizando 64 fotomultiplicadoras independentes, e que ainda não havia sido testado na realização do espalhamento Thomson multipassagem e multiespacial. Devido ao número limitado de canais para a aquisição dos dados, via conversores analógico / digital (ADC) , foi possível trabalhar com um total de 20 dos 64 canais do detector multicanal, permitindo se fazer pela primeira vez desde que o tokamak chegou ao laboratório, medidas simultâneas de temperatura e densidade eletrônicas em quatro posições espaciais distintas ao longo do raio do plasma e do tempo de descarga do tokamak
Abstract: In this thesis we present two distinct works implemented on the NOVA-UNICAMP tokamak. The first one involved the determination of the best machine operation conditions with the development of software¿s for machine control, data acquisition and analysis which were not available up to the moment. The second part is the development, set up and use of the Thomson scattering diagnostic with multi-pass, multi-channel, and multi-space capability. This diagnostic permitted us to carry out direct measurements of electron temperature and indirect measurements of electron density using Rayleigh scattering, along a full tokamak discharge time in four different radial position inside the plasma. For the multipass set up, the initial ruby laser power has been increased by a factor of six, which permitted good precision electron temperature and density measurements. The multichannel detection capability has been possible due to the newly available 8 x 8 matrix multi-channel detector XP 1752 from Philips, which, up to our knowledge was used for the first time. Due to the limited numbers of ADC modules available at the time of the measurements, in our Lab., we could use only 20 of the 64 channels which permitted us to perform four spatial temperature measurements during one tokamak discharge. Nevertheless the capability of full spatial electron temperature and density measurements along the tokamak discharges, with good precision, has been demonstrated.
Doutorado
Física
Doutor em Ciências
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38

Sa, Wanderley Pires de. "Reconstrução do equilíbrio no tokamak TCA/BR." Universidade de São Paulo, 1996. http://www.teses.usp.br/teses/disponiveis/43/43131/tde-12122013-162240/.

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A determinação precisa e rápida das configurações de equilíbrio Magnetohidrodinâmico (MHD) em tokamaks é de fundamental importância para o confinamento magnético do plasma. Através do conhecimento dos parâmetros que caracterizam este equilíbrio MHD é possível controlar o plasma durante a sua formação por processos de realimentação. Uma análise mais detalhada destes parâmetros é necessária, também, entre um disparo e outro, para a estruturação do experimento. Neste trabalho é investigada a reconstrução das configurações de equilíbrio MHD no tokamak TCA/BR a partir de medidas magnéticas externas, utilizando um método que permite uma rápida determinação dos parâmetros principais da descarga. A tese divide-se em duas partes. Na primeira, é apresentada a construção de um código de equilíbrio que resolve a equação de Grad-Shafranov para a configuração geométrica que caracteriza o tokamak TCA/BR. Na segunda, é descrito o processo de reconstrução do equilíbrio MHD através de medidas de campos e fluxos magnéticos externos ao plasma no TCA/BR, e utilizando o método de Função de Parametrização FP. Este método baseia-se no tratamento estatístico de um banco de dados simulados de configurações de equilíbrio, com o objetivo de obter uma expressão simples relacionando os parâmetros que caracterizam o equilíbrio e as medidas realizadas. Os resultados obtidos através da FP são comparados com os obtidos através de outros métodos convencionais.
The accurate and rapid determination of the Magnetohydrodynamic (MHD) equilibrium configuration in tokamaks is a fundamental subject for the magnetic confinement of the plasma. With the knowledge of characteristic plasma MHD equilibrium parameters it is possible to control the plasma position during its formation using feed-back techniques. It is also necessary an on-line analysis between successive discharges to program external parameters for the subsequent discharges. In this work it is investigated the MHD equilibrium configuration reconstruction of the TCA/BR tokamak from external magnetic measurements, using a method that is able to determine fastly the main parameters of discharge. The thesis has two parts. Firstly it is presented the development of an equilibrium co de that solves de Grad-Shafranov equation for the TCA/BR tokamak geometry. Secondly it is presented the MHD equilibrium reconstruction process from external magnetic field and flux measurements using the Function Parametrization FP method. This method is based on the statistical analysis of a database of simulated equilibrium configurations, with the goal of obtaining a simple relationship between the parameters that characterize the equilibrium and the measurements. The results from FP are compared with conventional methods.
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39

Baquero, Wilson Andres Hernandez. "Flutuações turbulentas de temperatura no Tokamak TCABR." Universidade de São Paulo, 2017. http://www.teses.usp.br/teses/disponiveis/43/43134/tde-30012018-100934/.

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A contribuição dos eventos extremos, chamados \\emph{bursts}, relacionados com estruturas coerentes que se propagam na turbulência, parece ser parte da explicação para o transporte anômalo que acontece em plasmas confinados. Porém, ainda não existe um modelo adequado no quadro da teoria neoclássica de transporte, para explicar adequadamente a contribuição destes eventos extremos. Assim, a caracterização do transporte de partículas e energia, devido a esses eventos extremos, e a sua estrutura interna, são questões relevantes no estudo do plasma de fusão. Para isso, medições locais da temperatura dos elétrons são necessárias, pois o transporte de partículas e energia sofre correções devido à temperatura. Por terem boa resolução espacial e serem relativamente fáceis de construir, as sondas eletrostáticas são comumente utilizadas em tokamaks para medir a temperatura local na região da borda de plasmas confinados magneticamente. Os métodos de varredura de tensão e a configuração de sonda tripla estão dentre os métodos mais usados para medir a temperatura local na borda do plasma com sondas eletrostáticas. Neste trabalho, é apresentada uma comparação entre as medições de temperatura usando esses dois métodos no tokamak TCABR. Para esse fim, foram utilizadas descargas de plasma em condições padrão, onde a corrente de plasma e a densidade são mantidas praticamente estáveis e há baixa atividade MHD, isto é, a fase estacionária da descarga, com os parâmetros macroscópicos de equilíbrio aproximadamente constantes. As medições da temperatura pelos dois métodos têm boa correspondência na região da sombra do limitador, mas existem discrepâncias quando as medidas são feitas dentro da coluna de plasma. Verificou-se que esta discrepância se deve ao efeito de expansão da região de transição entre o plasma e a superfície da sonda, conhecida como bainha de plasma. Portanto, foram modificadas as equações do método da sonda tripla a fim de considerar, de maneira adequada, este efeito. Esta modificação conduz a medições de temperatura compatíveis entre os dois métodos. Também se estudou as estruturas coerentes que se propagam na turbulência da borda (bursts), que são detectados como picos no sinal de corrente de saturação iônica. Para esse fim, foi usada a técnica da análise condicional. Os resultados obtidos parecem ser compatíveis com estruturas que apresentam uma inclinação no plano radial-poloidal. Esta inclinação implica que o método comumente usado para medir a velocidade de propagação das estruturas, baseado no atraso entre a detecção do pico entre dois pinos próximos, pode levar a resultados completamente errados. Os resultados para a evolução média da temperatura durante os bursts são incompatíveis entre os dois métodos. De fato, os resultados fornecidos pelo método de sonda tripla aparentam estar fisicamente errados, uma vez que indicam um alto gradiente de temperatura dentro dos bursts. Constatou-se que este problema é devido aos altos gradientes de potencial dentro dos bursts que inviabilizam a hipótese de potencial uniforme na região entre os pinos da sonda tripla.
The contribution of the extreme events related to propagating structures in the turbulence, the so-called bursts, seems to be part of the explanation to anomalous transport in confined plasma. But, up to now, there is not an adequate model in the frame of neoclassical transport theory to properly account the contribution of these extreme events. Therefore, the characterization of the particle and energy transport due to the extreme events and the burst internal structure are an important issue in fusion plasma research. However, local electron temperature measurements are necessary to investigate those topics, because particles and energy transport have temperature corrections. Due to their good spatial resolution and relatively easy construction, electrostatic probes are often used to measure temperature in the plasma edge of tokamak. The triple probe configuration and voltage sweep technique are among the most common techniques used with electrostatic probes to measure local temperature in the plasma edge. We present a comparison between the temperature measurement using these two techniques in the tokamak TCABR. For this purpose, it was used stationary standard plasma discharges (it is, discharges with almost stable plasma current and density and with low MHD activity). For temperature measurement, the two methods have good correlation in the Scrape-Off-Layer region but there are discrepancies between their values inside the plasma column. We found that this discrepancy is due to the sheath expansion effect. Therefore, the triple probe equations were modified to properly consider this effect. The modification leads to compatible average temperature measurements between the two methods. We also studied coherent structures propagating in the edge turbulence (detected as bursts in the saturation current) by using the conditional analysis technique. The results seem to be compatibles with structures tilted in the radial-poloidal plane. This tilt implies that the common method to measure the propagation velocity using the delay time of detection between two probes, could produce wrong values. The results for the average temporal behavior of temperature during the bursts are inconsistent between the two methods. Indeed, the triple probe results seems to be physically wrong, once it indicates a strong temperature gradient inside the bursts. We found that this problem is due to the strong potential gradients inside the burst, breaking the assumption that the pins used in the triple probe configuration are in a homogeneous plasma.
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40

Kroetz, Tiago. "Linhas de campo magnético caóticas em tokamak." Instituto Tecnológico de Aeronáutica, 2006. http://www.bd.bibl.ita.br/tde_busca/arquivo.php?codArquivo=339.

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Investigamos nesta dissertação o comportamento das linhas de campo magnético caóticas em tokamaks. Estas linhas surgem devido à perturbações ressonantes com os campos magnéticos de equilíbrio, que podem aparecer naturalmente no plasma ou serem produzidas devido à ação externa. Produzimos numericamente esta perturbação simulando a ação de um dispositivo chamado limitador magnético ergódico (LME). A motivação para esta investigação de linhas caóticas é um possível melhoramento no confinamento do plasma em tokamaks e um maior controle da interação plasma-borda. Tratamos, primeiramente neste trabalho, a configuração de equilíbrio dos campos magnéticos. Em seguida aplicamos o formalismo hamiltoniano para descrevermos o traçado das linhas de campo na configuração de equilíbrio. Obtivemos também a hamiltoniana total do sistema sob a perturbação gerada pelo LME. Através das equações de Hamilton para o sistema perturbado escrevemos as equações de um mapa estroboscópico que fornecem as coordenadas canônicas da linha de campo na posição de cada anel do LME. A partir do mapa estroboscópico traçamos diversos mapas de Poincaré para diferentes modos ressonantes perturbados e intensidades de perturbação. Explicamos a formação das cadeias de ilhas, os fenômenos de reconexão e bifurcação e identificamos e caracterizamos a existência de linhas de campo caóticas no tokamak devido à perturbação. O escape destas linhas de campo magnético para a borda do tokamak também foi estudado. Para isso, foram obtidos os mapas de conexão, bacias de escape e os "footprints". Estes fornecem, respectivamente, o número de voltas que uma dada linha de campo magnético percorre no toróide até alcançar a parede, a localização das linhas ao chegarem na parede, assim como as impressões deixadas pelas linhas nas paredes. Estas impressões consistem numa distribuição de manchas nas paredes do toróide, fornecendo um padrão de escape não uniforme com uma estrutura complexa.
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41

Morris, Robert Christian. "Neoclassical poloidal flow damping in a tokamak." Thesis, Imperial College London, 1996. http://hdl.handle.net/10044/1/59970.

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The damping rate of the poloidal flow in a tokamak is determined in the banana regime as an initial value problem. The bounce averaged drift kinetic equation is solved analytically for early times, and on longer time scales (of the order To) a numerical solution is performed. Initial conditions are chosen for the ion distribution function t = 0) describing states with similar flows ug(t = 0), but differing structure in the pitch angle variable A = 2/x/t;^. At early times an analytical treatment shows that the damping characteristics of ug{t) depend sensitively on whether the ions responsible for the flow be close to the trapped-passing boundary. Initial decay is shown to be of the form ^ ~ A numerical treatment then confirms this early time result and extends the solution to the long term aymptotic decay, which is found to be independent of the initial preparation of the system. A spread of characteristic times are estimated for differing initial conditions and in terms of the ion-ion collision frequency tu can be written Tp % 0.2 — O.Grf,-. The previous attempts at such a calculation are criticised and, as far as possible, explained in terms of the present work. The paper by Shaing and Hirshman (1989) claims an inverse aspect ratio dependence of Tp DC and this result is found to be most compatible with the asymptotic result of the present work.
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42

BREMOND, SYLVAIN. "Modelisation et commande des plasmas de tokamak." Paris 11, 1995. http://www.theses.fr/1995PA112320.

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Les plasmas de tokamaks a section elliptique, avantageux vis-a-vis du critere de lawson, sont verticalement instable. Nous avons obtenu une expression analytique des poles et zeros du systeme couple complet plasma-enceinte conductrice-bobines, qui permet de caracteriser la dynamique de l'instabilite en boucle ouverte a partir de la definition de deux parametres sans dimensions: le coefficient de couplage inductif entre les bobines et l'enceinte, et le rapport de l'efficacite stabilisante des bobines a celle de l'enceinte. On montre que l'effet passif des bobines permet d'elargir le domaine de stabilite a l'echelle du temps d'alfven, et de reduire le taux de croissance de l'instabilite, de facon d'autant plus ample que les deux parametres sont distincts. Des applications a tore supra -ou l'instabilite est due a l'attraction du noyau de fer- et a diii-d sont donnees. En revanche, on met en evidence un contre-effet de l'enceinte, qui entraine une inversion temporaire de l'effet de la commande des bobines sur le deplacement du plasma, lorsque le couplage inductif est superieur au rapport d'efficacite stabilisante. Cette situation, qui correspond en particulier au cas present d'iter, reduit significativement la marge de manuvre de la retroaction. Une precision du controle de la frontiere du plasma est necessaire afin d'avoir une meilleure maitrise de l'interaction avec la paroi et/ou du couplage avec les antennes de chauffage. La derive positionnelle de quelques mm/s observee sur le tokamak tore supra est expliquee et corrigee. Une identification parametrique de la reponse lineaire de la forme du plasma, a partir de calculs d'equilibres magnetohydrodynamiques perturbes, est effectuee et validee en comparaison avec l'experience. Une loi de commande optimale, basee sur la minimisation d'un critere integral quadratique ponderant l'erreur de suivi et la consommation, qui permet d'eviter l'apparition de doublets de courants dans les bobines, est mise en uvre. La realisation de deformations locales du plasma s'en trouve facilitee
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43

Nicolas, Timothée. "Sawtooth driven particle transport in tokamak plasmas." Palaiseau, Ecole polytechnique, 2013. http://pastel.archives-ouvertes.fr/docs/00/92/64/28/PDF/SawtoothDrivenParticleTransportInTokamakPlasmas_09_01_2014.pdf.

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Le transport radial des particules dans les tokamaks constitue une des questions les plus cruciales pour la communauté de la fusion par con finement magnétique. En eff et, d'une part la puissance de fusion est proportionnelle au carré de la pression, d'autre part l'accumulation d'impuretés lourdes dans le coeur du plasma conduit à d'importantes pertes par rayonnement qui peuvent fi nir par causer un e ffondrement radiatif du plasma. Les dent de scie et la redistribution périodique de la température et de la densité de coeur qui lui est associée peuvent a ffecter signifi cativement le transport radial des électrons et des impuretés. Dans cette thèse, nous présentons des simulations numériques de dents de scie utilisant un code tridimensionnel non linéaire de magnétohydrodynamique appelé XTOR-2F, a n d'étudier le transport de particules pendant les dents de scie. Nous montrons que le code est capable de reproduire les structures fines de densité observées après le crash de la dent de scie avec le diagnostic de réfl ectométrie à balayage rapide sur les tokamaks Tore Supra et JET. La présence de ces structures implique la possibilité que le crash de dent de scie ne soit pas aussi effi cace que prévu pour évacuer les impuretés du coeur du plasma. Cependant, en appliquant le code aux impuretés, nous montrons que finalement le taux de redistribution est quantitativement similaire à ce qui est prévu par le modèle de Kadomtsev, un résultat inattendu a priori. Nous concluons que la dent de scie est e fficace pour évacuer les impuretés du coeur du plasma
The radial transport of particles in tokamaks is one of the most stringent issues faced by the magnetic confinement fusion community, because the fusion power is proportional to the square of the pressure, and also because accumulation of heavy impurities in the core leads to important power losses which can lead to a "radiative collapse". Sawteeth and the associated periodic redistribution of the core quantities can significantly impact the radial transport of electrons and impurities. In this thesis, we perform numerical simulations of sawteeth using a nonlinear tridimensional magnetohydrodynamic code called XTOR-2F to study the particle transport induced by sawtooth crashes. We show that the code recovers, after the crash, the fine structures of electron density that are observed with fast-sweeping reflectometry on the JET and TS tokamaks. The presence of these structure may indicate a low efficiency of the sawtooth in expelling the impurities from the core. However, applying the same code to impurity profiles, we show that the redistribution is quantitatively similar to that predicted by Kadomtsev's model, which could not be predicted a priori. Hence finally the sawtooth flushing is efficient in expelling impurities from the core
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44

Grandgirard, Virginie. "Modelisation de l'equilibre d'un plasma de tokamak." Besançon, 1999. http://www.theses.fr/1999BESA2039.

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Cette these traite de la modelisation, de la simulation numerique et du controle optimal de l'equilibre du plasma dans un tokamak. Dans le premier chapitre, les equations aux derivees partielles, regissant l'equilibre d'un plasma axisymetrique, sont presentees. Il s'agit d'un probleme elliptique, non-lineaire, a frontiere libre, avec conditions limites a l'infini. Le probleme faible associe est linearise par un algorithme de newton et resolu par elements finis sur un domaine suffisamment grand pour y appliquer une condition de dirichlet sur la frontiere. Dans le second chapitre, un traitement rigoureux des conditions a l'infini est presente. Le domaine est divise en une partie interieure, comprenant toutes les non-linearites et en la partie exterieure complementaire. En choisissant une frontiere semi-circulaire entre ces deux domaines, les problemes interieurs et exterieurs sont decouples. Dans le troisieme chapitre, deux methodes iteratives (gmres et bigradient conjugue preconditionnes) sont comparees a une methode directe (woodbury associe a une decomposition de cholesky) en termes de taille memoire et temps de calcul. Le probleme inverse est formule, dans le quatrieme chapitre, en terme de controle optimal. Le lagrangien associe et le systeme d'optimalite de premier ordre sont alors definis. Une methode d'optimisation quadratique, utilisant l'algorithme du gradient conjugue, est introduite. Des exemples d'applications pour les projets de tokamaks futurs, sont presentes. Enfin, dans le dernier chapitre, est decrite une methode iterative d'approximations successives, associee a une application de point fixe croissante-decroissante. Il est demontre que cette methode permet, a partir d'un couple de sur et sous-solutions, de construire des suites monotones convergeant vers un encadrement de la solution.
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45

Bourdelle, Clarisse. "Analyse de stabilité de plasmas de Tokamak." Université Joseph Fourier (Grenoble), 2000. http://www.theses.fr/2000GRE10101.

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Dans un plasma de tokamak, le transport de l'energie est principalement de nature turbulente. Afin d'augmenter le nombre de reactions de fusion, il est necessaire d'ameliorer le confinement de l'energie. L'objet de cette these est d'identifier les parametres permettant l'obtention de plasmas dont l'energie est mieux confinee afin de guider les experiences a venir. Pour ce faire, un code numerique a ete developpe. Il calcule les taux de croissance qui caracterisent la rapidite de l'amorcage des instabilites. L'analyse de stabilite est completee par l'evaluation du taux de cisaillement de la vitesse de rotation due au champ electrique radial. Lorsque ce taux est superieur au taux de croissance local maximal, la turbulence ionique est stabilisee. Le taux de cisaillement de rotation et le taux de croissance sont determines a partir des profils radiaux de densite, de temperature et du facteur de securite d'un plasma donne. En particulier, trois familles de plasmas sont analysees. Dans les plasmas radiatifs de textor (modes ri), l'injection d'ions de nombre de charge eleve entraine la diminution des taux de croissance. Dans les plasmas a forte densite de tore supra, un fort cisaillement magnetique et/ou un chauffage des ions plus efficace associe a une bifurcation de la direction de rotation toroidale (par ailleurs non-expliquee) declenchent l'amelioration du confinement. Dans tore supra, des gradients de pression electronique localement tres raides (appeles barrieres internes de transport) sont obtenus suite a une inversion du cisaillement magnetique. Ce cisaillement magnetique localement negatif a un effet stabilisant. Dans ces trois types de plasmas, les taux de croissance diminuent, le confinement s'ameliore, les profils de densite et de temperature se piquent. Ces piquages entrainent une augmentation du taux de cisaillement de rotation qui permet de maintenir la qualite du confinement.
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46

Bodi, Vasudeva Raghavendra Kowsik. "Anomalous radial transport in tokamak edge plasma." Diss., [La Jolla] : University of California, San Diego, 2010. http://wwwlib.umi.com/cr/ucsd/fullcit?p3390465.

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Thesis (Ph. D.)--University of California, San Diego, 2010.
Title from first page of PDF file (viewed February 18, 2010). Available via ProQuest Digital Dissertations. Vita. Includes bibliographical references (p. 67-72).
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47

Najera, Omar Cipriano Usuriaga. "Tomografia de emissão H-alfa no tokamak TCABR." Universidade de São Paulo, 2006. http://www.teses.usp.br/teses/disponiveis/43/43134/tde-27022008-133846/.

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Neste trabalho foi feito um estudo do perfil tomográfico da emissão da linha do átomo de hidrogênio, H-alfa (?=656,28 nm) no plasma do TCABR, um tokamak de porte médio em operação no Laboratório de Física de Plasmas do Instituto de Física da Universidade de São Paulo. Nosso trabalho centrou-se no estudo dos efeitos da introdução de um eletrodo polarizado na borda do plasma no tokamak TCABR. O eletrodo pode ser introduzido até 1,5 cm para dentro da coluna do plasma, sem causar disrupturas para polarização positiva de 0 até +350V, e situado no plano equatorial do tokamak. Perfis tomográficos de H-alfa com e sem polarização foram medidos. A comparação dos perfis mostra um aumento da densidade de linha na posição central, quando a emissividade H-alfa diminui. A análise dos perfis tomográficos de H-alfa, tempo de confinamento das partículas e também do estudo de reciclagem das partículas neutras, indica que o plasma entra no regime de alto confinamento (modo-H). Cálculos de turbulência e de transporte na borda do plasma (SOL), feitos medindo o potencial flutuante e a corrente de saturação de íons, mostram uma diminuição forte no espectro de potência e de transporte. Também foram feitos estudos do novo regime de descargas com elétrons fugitivos (\"runaway electron\"), descoberto no tokamak TCABR. As características distintivas deste regime são um plasma de baixa temperatura fracamente ionizado, destacado do limitador devido a processos de recombinação, e instabilidade de relaxação com fortes picos de emissão H-alfa correlacionados com instabilidade dente de serra da densidade eletrônica de linha. No presente trabalho fazemos a descrição das condições experimentais para a geração destas descargas. A produção dos elétrons fugitivos é analisada; mostrando que a geração de elétrons fugitivos somente pode ser explicada pelo mecanismo de avalanche. A confirmação de baixa temperatura do plasma é obtida de uma análise do perfil tomográfico da emissão H-alfa. Esta emissão não pode ser explicada por excitação de elétrons no plasma. A recombinação, de outro lado, dá uma explicação plausível para a dependência temporal da emissão, em particular para alta densidade de partículas neutras.
A study of the tomography profile of the emission of the line of Hydrogen, atomic H-alpha line (?=656.28 nm), was carried out in TCABR, a medium-size tokamak in operation at the Laboratory of Plasma Physics of the Institute of Physics of the University of São Paulo. Our work focuses on the study of the effects of due to the introduction of a biased electrode in the plasma edge of the TCABR tokamak. The electrode could be introduced up to 1.5 cm inside the plasma, without plasma disruptions for positive voltages from 0 to +350V, and was located on the equatorial plane of the plasma column. Tomography profiles of H-alpha with and without bias were measured. Comparison of the profiles shows an increase of the central line-averaged density, while the emissivity of the line H-alpha decreases. The analysis of the tomography profiles of H-alpha, time of confinement of particles and also the study of recycling of the neutral particles, indicate that the confined plasma enters the H-mode regime. Calculations of turbulence and transport at the Scrape-Off-Layer, using measured floating potentials and ion saturation currents, show a strong decrease in the power spectra and transport. The H-alpha tomography was also employed to study the new regime of runaway discharges that has been discovered in the TCABR tokamak. The distinctive features of this regime are weakly ionized low-temperature plasma detached from the limiter due to the recombination process, and a relaxation instability with strong spikes of H-alpha emission correlated with sawtooth relaxation of the line density. In the present thesis we report experimental data on conditions for generation of these discharges. The runaway electron production is analyzed; show that generation of runaway electrons can only be explained by the runaway avalanche mechanism. The confirmation of low plasma temperature is a obtained from an analysis of the tomography profile of H-alpha emission. This emission cannot be explained by excitation by plasma electrons. Recombination, on the other hand, gives a rather plausible explanation for the time dependency of the emission, in particular at high neutral densities.
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48

Breton, Sarah. "Tungsten transport in a tokamak : a first-principle based integrated modeling approach." Thesis, Aix-Marseille, 2018. http://www.theses.fr/2018AIXM0007.

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La fusion par confinement magnétique est actuellement la voie la plus avancée pour produire de l’énergie grâce à la réaction de fusion. L’un des défis à relever concerne la contamination du plasma par le Tungstène (W), un matériau capable de résister aux hauts flux de chaleur. A cause de son grand nombre atomique, le W rayonne dans les plasmas de tokamak. S’il s’accumule au cœur du tokamak, il refroidit le plasma. Il est donc crucial de comprendre les mécanismes du transport du W et d’identifier les paramètres favorisant son accumulation. Le W interagit de façon non-linéaire avec les différents paramètres du plasma. La simulation intégrée est le seul outil permettant à tous ces paramètres d’être simulés de façon auto-consistante durant plusieurs temps de confinement. Pour la première fois, l’outil de simulation intégrée est couplé à des codes de transport premiers principes modélisant de façon auto-consistante les transports turbulent et collisionnel du W, les profils de densité, température, rotation, radiation, et l’évolution du chauffage. Pour des raisons numériques, certains phénomènes ne sont pas modélisés et l'interaction plasma/paroi interne est simplifiée. A chaque pas de temps, cette simulation reproduit avec succès les signaux expérimentaux et le comportement du W. De plus, des acteurs responsables de l’accumulation du W (la rotation et la source centrale de particules) sont identifiés. Enfin, la simulation intégrée a permis de mettre en lumière l’effet stabilisant du W sur la turbulence. Le travail accompli montre que la simulation intégrée premiers principes permet désormais d'optimiser à l'avance les scénarios de plasma afin d'y limiter l'accumulation de W
Magnetic confinement fusion is currently the most advanced way to produce energy thanks to Deuterium/Tritium reaction. One of the challenges is the limitation of the reaction contamination because of Tungsten (W), a material capable of resisting high heat fluxes. W large atomic number causes W to radiate inside tokamak plasmas. If W accumulates in the central part, it cools down the plasma. It is therefore crucial to understand the mechanisms of W transport and identify the actuators of the accumulation process. W transport is involved in complex interplays with the plasma parameters (density, temperature, rotation). Therefore the use of integrated modeling is mandatory in order to evolve self-consistently all those parameters for several confinement times. For the first time, an integrated modeling tool is coupled to first-principle transport codes to self-consistently simulate the time evolution of the W behavior, as well as the evolution of density, temperature, rotation profiles, radiation and external heating. For numerical reasons, several phenomena are not modeled, and the physics of the interaction with the inner wall is simplified. At each time step, this simulation successfully reproduces experimental profiles and the W central accumulation. Moreover, actuators of the central W accumulation (rotation and central particle fueling) were identified. Finally, integrated modeling simulation allowed bringing out a very interesting non-linear mechanism: the stabilizing effect of W on turbulence. This work demonstrates that first-principles integrated modeling now allows to design and optimize in advance plasma scenarios with limited W central accumulation
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49

Sridhar, Sundaresan. "Study of tokamak plasma disruptions and runaway electrons in a metallic environment." Electronic Thesis or Diss., Aix-Marseille, 2020. http://www.theses.fr/2020AIXM0313.

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Les dispositifs de fusion de type tokamaks ont atteint des performances proches de celles nécessaires à réacteur industriel de fusion et les disruptions sont des événements majeurs dans lesquels l'énergie du plasma est perdue en un très court instant. Electrons découplés (RE), de par leur énergie (quelques 10ème\,MeV), peuvent endommager des composants internes du tokamak. La stratégie actuelle consiste à éviter la génération de RE à l’aide d’une injection massive de matière (MMI). Si leur génération ne peut pas être évitée, une 2ème MMI sera utilisée pour atténuer le faisceau d’électrons découplés. Après la 1ère MMI, un plasma de fond dense et froid d'impuretés MMI est formé et le 2ème MMI visant à atténuer l'emballement du faisceau d'électrons peut être inefficace dans ce plasma de fond, comme observé dans le tokamak JET. Comprendre la physique de l'interaction entre le faisceau d'électrons découplés et le 2ème MMI en présence du plasma de fond froid sera au centre de cette thèse
Tokamaks are the devices currently closest to achieve nuclear fusion power and disruptions are unfavorable events in which the plasma energy is lost in a very short timescale causing damage to tokamak structures. RE beams are one of the consequence of disruptions and they carry the risk of in-vessel component damage. Thus, the prevention and control of the RE are of prime importance. The current strategy for runaway electrons is to avoid their generation by a massive material injection (MMI). If their generation cannot be avoided, a 2nd MMI will be used to mitigate the generated RE beam. After the 1st MMI to prevent RE generation, a background plasma of 1st MMI impurities is formed which make the second MMI inefficient to mitigate RE beams inefficient, as observed in the JET tokamak. In this thesis, the physics of the interaction between the RE beam and the mitigation MMI in the presence of a cold background plasma is studied
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50

Liang, Anshu. "Understanding the low to high confinement transition in tokamak plasmas." Electronic Thesis or Diss., Aix-Marseille, 2023. http://theses.univ-amu.fr.lama.univ-amu.fr/230112_LIANG_826zuy182lisgpn946fzpk544n_TH.pdf.

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Les travaux présentés dans cette thèse sont consacrés à la compréhension du mécanisme physique de la transition L-H. Le mécanisme d'entraînement du cisaillement de vitesse dans le bord du plasma a été étudié à l'aide d'une injection de puissance d'entraînement à courant hybride inférieur (LHCD) sur le tokamak HL-2A en Chine. Il a été montré que l'augmentation du cisaillement de vitesse est principalement entraînée par le terme diamagnétique ionique du champ électrique radial Er. Au cours de la transition L-H, on observe que le terme diamagnétique ionique du champ électrique radial Er joue un rôle dominant dans l'augmentation du cisaillement de vitesse, tandis que les contributions des termes de vitesse poloïdal et toroïdal sont négligeables. Le cisaillement de vitesse doit atteindre une valeur critique pour permettre à la transition L-H de se produire. Cela signifie que la valeur critique joue un rôle de seuil de cisaillement de vitesse pour la transition L-H. De plus, l'effet stimulé de l'injection de faisceaux moléculaires supersoniques (SMBI) sur la transition L-H a également été étudié sur HL-2A. Les résultats suggèrent que le SMBI pourrait être une méthode fiable pour réduire le seuil de puissance de transition L-H et contrôler la transition L-H dans les futurs réacteurs de fusion. Enfin, des efforts ont été faits sur l'optimisation du couplage LHCD sur le tokamak WEST en France et une analyse du couplage de l'onde LH dans les plasmas WEST a été réalisée. L'analyse montre que le remodelage toroïdal du lanceur multijonction entièrement actif effectué avant son installation à WEST a été un succès
The works presented in this thesis are devoted to understand the physical mechanism of the L-H transition. The driving mechanism of the velocity shear in the plasma edge has been studied using lower hybrid current drive (LHCD) power injection on the HL-2A tokamak in China. It has been shown that the increase of the velocity shear is mainly driven by the ion diamagnetic term of the radial electric field Er. During the L-H transition, it is observed that the ion diamagnetic term of the radial electric field Er plays a dominant role in the increase of velocity shear, while the contributions of the poloidal and toroidal velocity terms are negligible. The velocity shear must reach a critical value to allow the L-H transition to occur. This means that the critical value plays a role as a velocity shear threshold for the L-H transition. In addition, the stimulated effect of supersonic molecular beam injection (SMBI) on the L-H transition has also been investigated on HL-2A. The results suggest that SMBI could be a reliable method for reducing the L-H transition power threshold and controlling the L-H transition in future fusion reactors. Finally, efforts have been made on the optimization of LHCD coupling on the WEST tokamak in France and an analysis of the LH wave coupling in WEST plasmas has been carried out. The analysis shows that the toroidal reshaping of the fully-active-multijunction launcher carried out before its installation in WEST was successful. The experiments have also shown that the reshaping of the passive-active-multijunction launcher is necessary in order to avoid overheating on the launcher front in long pulses
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