Relevant bibliographies by topics / Tokamak

Academic literature on the topic 'Tokamak'

Author: Grafiati
Published: 4 June 2021
Last updated: 8 June 2024

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Contents

Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Tokamak.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Journal articles on the topic "Tokamak"

1

El-zmeter, Nour El-Houda, Benjamin Schmiga, Brendan Boyd-Weetman, and Alicia Murphy. "Analysis of Tokamak fusion device parameters affecting the efficiency of Tokamak operation." PAM Review Energy Science & Technology 4 (June 5, 2017): 87–102. http://dx.doi.org/10.5130/pamr.v4i0.1444.

Full text
Abstract:
Nuclear Power has been available as a relatively clean and reliable energy source for several decades. While tokamak engines have been in existence almost as long as successful fission-powered nuclear generators, they have not yet reached operational success for energy generation. This meta study collates key fusion device parameters and determines ideas on the applicability of fusion devices for energy. This paper supports the argument that toroidal tokamaks are not limited by volume whereas spherical designs have a potential volume limit, spherical tokamaks use a lower magnetic field current than toroidal tokamaks. Further scientific and engineering progress is required before tokamak devices can be a viable technology to be used for energy generation.
APA, Harvard, Vancouver, ISO, and other styles
2

Whyte, Dennis. "Small, modular and economically attractive fusion enabled by high temperature superconductors." Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 377, no. 2141 (February 4, 2019): 20180354. http://dx.doi.org/10.1098/rsta.2018.0354.

Full text
Abstract:
The advantages of high magnetic fields in tokamaks are reviewed, and why they are important in leading to more compact tokamaks. A brief explanation is given of what limits the magnetic field in a tokamak, and why high temperature superconductors (HTSs) are a game changer, not just because of their higher magnetic fields but also for reasons of higher current density and higher operating temperatures. An accelerated pathway to fusion energy is described, defined by the SPARC and ARC tokamak designs. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’.
APA, Harvard, Vancouver, ISO, and other styles
3

Windridge, Melanie. "Smaller and quicker with spherical tokamaks and high-temperature superconductors." Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 377, no. 2141 (February 4, 2019): 20170438. http://dx.doi.org/10.1098/rsta.2017.0438.

Full text
Abstract:
Research in the 1970s and 1980s by Sykes, Peng, Jassby and others showed the theoretical advantage of the spherical tokamak (ST) shape. Experiments on START and MAST at Culham throughout the 1990s and 2000s, alongside other international STs like NSTX at the Princeton Plasma Physics Laboratory, confirmed their increased efficiency (namely operation at higher beta) and tested the plasma physics in new regimes. However, while interesting devices for study, the perceived technological difficulties due to the compact shape initially prevented STs being seriously considered as viable power plants. Then, in the 2010s, high-temperature superconductor (HTS) materials became available as a reliable engineering material, fabricated into long tapes suitable for winding into magnets. Realizing the advantages of this material and its possibilities for fusion, Tokamak Energy proposed a new ST path to fusion power and began working on demonstrating the viability of HTS for fusion magnets. The company is now operating a compact tokamak with copper magnets, R 0 ∼ 0.4 m, R / a ∼ 1.8, and target I p = 2MA, B t0 = 3 T, while in parallel developing a 5 T HTS demonstrator tokamak magnet. Here we discuss why HTS can be a game-changer for tokamak fusion. We outline Tokamak Energy's solution for a faster way to fusion and discuss plans and progress, including benefits of smaller devices on the development path and advantages of modularity in power plants. We will indicate some of the key research areas in compact tokamaks and introduce the physics considerations behind the ST approach, to be further developed in the subsequent paper by Alan Costley. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’.
APA, Harvard, Vancouver, ISO, and other styles
4

Pankratov, Igor M., and Volodymyr Y. Bochko. "Nonlinear Cone Model for Investigation of Runaway Electron Synchrotron Radiation Spot Shape." 3, no. 3 (September 28, 2021): 18–24. http://dx.doi.org/10.26565/2312-4334-2021-3-02.

Full text
Abstract:
The runaway electron event is the fundamental physical phenomenon and tokamak is the most advanced conception of the plasma magnetic confinement. The energy of disruption generated runaway electrons can reach as high as tens of mega-electron-volt and they can cause a catastrophic damage of plasma-facing-component surfaces in large tokamaks and International Thermonuclear Experimental Reactor (ITER). Due to its importance, this phenomenon is being actively studied both theoretically and experimentally in leading thermonuclear fusion centers. Thus, effective monitoring of the runaway electrons is an important task. The synchrotron radiation diagnostic allows direct observation of such runaway electrons and an analysis of their parameters and promotes the safety operation of present-day large tokamaks and future ITER. In 1990 such diagnostic had demonstrated its effectiveness on the TEXTOR (Tokamak Experiment for Technology Oriented Research, Germany) tokamak for investigation of runaway electrons beam size, position, number, and maximum energy. Now this diagnostic is installed practically on all the present-day’s tokamaks. The parameter v┴/|v||| strongly influences on the runaway electron synchrotron radiation behavior (v|| is the longitudinal velocity, v┴ is the transverse velocity with respect to the magnetic field B). The paper is devoted to the theoretical investigation of runaway electron synchrotron radiation spot shape when this parameter is not small that corresponds to present-day tokamak experiments. The features of the relativistic electron motion in a tokamak are taken into account. The influence of the detector position on runaway electron synchrotron radiation data is discussed. Analysis carried out in the frame of the nonlinear cone model. In this model, the ultrarelativistic electrons emit radiation in the direction of their velocity v→ and the velocity vector runs along the surface of a cone whose axis is parallel to the magnetic field B. The case of the small parameter v┴/|v||| (v┴/|v|||<<1, linear cone model) was considered in the paper: Plasma Phys. Rep. 22, 535 (1996) and these theoretical results are used for experimental data analysis.
APA, Harvard, Vancouver, ISO, and other styles
5

Manheimer, Wallace. "Comment on ‘The advanced tokamak path to a compact net electric fusion pilot plant’." Nuclear Fusion 62, no. 12 (October 18, 2022): 128001. http://dx.doi.org/10.1088/1741-4326/ac88e4.

Full text
Abstract:
Abstract This comment (letter) examines a recent GA concept which they hope will lead to a tokamak fusion pilot plant. As tokamaks are now the closest configuration to practical magnetic fusion, if they cannot do a pilot plant, almost certainly no other device can either. The conclusion is that constructing a tokamak fusion pilot plant at this time is enormously risky, and is almost certainly tremendous waste of scarce fusion resources, which could be better used on other efforts in the fusion effort.
APA, Harvard, Vancouver, ISO, and other styles
6

Hirsch, Robert L., and Roger H. Bezdek. "Public Acceptance of ITER-Tokamak Fusion Power." European Journal of Energy Research 1, no. 4 (October 8, 2021): 8–12. http://dx.doi.org/10.24018/ejenergy.2021.1.4.18.

Full text
Abstract:
One of the U.S. Electric Power Research Institute’s criteria for practical fusion power is public acceptance. In this analysis we consider the potential public acceptance of ITER-tokamak fusion power. Because ITER-like reactors are not likely to be commercially ready before mid-century, a forecast of public acceptance is very difficult. We break “the public” down into four entities: 1) Rank and file consumers, 2) Governments [local, state, & federal including regulators], 3) NGOs including environmental groups, and 4) Electric utilities. We assert that ITER-tokamaks will be evaluated in the context of fission power because both are nuclear processes. We observe that ITER-tokamak fusion will present radioactive hazards and be extremely expensive. Three possible futures for fission nuclear mid-century are: 1) full acceptance, 2) middling acceptance, and 3) rejection. If fission power is accepted mid-century, then ITER-tokamak fusion stands the best chance of being publicly acceptable, its largest drawback being very high cost. If fission power is of middling acceptance, then ITER-tokamak fusion might be marginally more acceptable because of its much shorter life radioactive waste. If fission power is unacceptable, then ITER-tokamak fusion acceptance will be very difficult.
APA, Harvard, Vancouver, ISO, and other styles
7

KROETZ, T., CAROLINE G. L. MARTINS, M. ROBERTO, and I. L. CALDAS. "Set of wires to simulate tokamaks with poloidal divertor." Journal of Plasma Physics 79, no. 5 (April 12, 2013): 751–57. http://dx.doi.org/10.1017/s0022377813000391.

Full text
Abstract:
AbstractSimple wire models have been proposed to simulate magnetic configurations in tokamaks. Here we consider electric currents in five parallel infinite wires to obtain double-null magnetic surfaces with specific choices of magnetic axis positions, triangularity, and elongation. As an example, we choose the position and the electric current of each wire to obtain magnetic surfaces similar to those expected in the tokamak international thermonuclear experimental reactor. Moreover, we also integrate the perturbed field line differential equation to simulate chaotic layers near the hyperbolic points and deposition patterns at the divertor plate observed in tokamaks. To simulate that, we add to the model a perturbing error field, due to asymmetries in the tokamak coils, and introduce a random collisional term to the field line mapping to reproduce escape pattern alterations due to particle collisions.
APA, Harvard, Vancouver, ISO, and other styles
8

Podpaly, Y. A., J. E. Rice, P. Beiersdorfer, M. L. Reinke, J. Clementson, and H. S. Barnard. "Tungsten measurement on Alcator C-Mod and EBIT for future fusion reactors1This article is part of a Special Issue on the 10th International Colloquium on Atomic Spectra and Oscillator Strengths for Astrophysical and Laboratory Plasmas." Canadian Journal of Physics 89, no. 5 (May 2011): 591–97. http://dx.doi.org/10.1139/p11-038.

Full text
Abstract:
Tungsten will be an important element in nearly all future fusion reactors because of its presence in plasma facing components. This makes tungsten a good candidate for a diagnostic element for ion temperature and toroidal velocity measurement, and it makes understanding tungsten emissions important for tokamak power balance. The effect of tungsten on tokamak plasmas is investigated at the Alcator C-Mod tokamak using VUV, bolometry, and soft X-ray spectroscopy. Tungsten was present in Alcator C-Mod as a plasma facing component and through laser blow-off impurity injection. Quasi-continuum emission previously seen at other tokamaks has been identified. Theoretical predictions are presented of tungsten emission that could be expected in future Alcator C-Mod measurements. Furthermore, spectra of highly charged tungsten ions have been studied at the SuperEBIT electron beam ion trap. This emission could prove useful for spectroscopic diagnostics of future high-temperature fusion reactor plasmas.
APA, Harvard, Vancouver, ISO, and other styles
9

Garrido, Izaskun, Aitor J. Garrido, Jesús A. Romero, Edorta Carrascal, Goretti Sevillano-Berasategui, and Oscar Barambones. "Low EffortLiNuclear Fusion Plasma Control Using Model Predictive Control Laws." Mathematical Problems in Engineering 2015 (2015): 1–8. http://dx.doi.org/10.1155/2015/527420.

Full text
Abstract:
One of the main problems of fusion energy is to achieve longer pulse duration by avoiding the premature reaction decay due to plasma instabilities. The control of the plasma inductance arises as an essential tool for the successful operation of tokamak fusion reactors in order to overcome stability issues as well as the new challenges specific to advanced scenarios operation. In this sense, given that advanced tokamaks will suffer from limited power available from noninductive current drive actuators, the transformer primary coil could assist in reducing the power requirements of the noninductive current drive sources needed for current profile control. Therefore, tokamak operation may benefit from advanced control laws beyond the traditionally used PID schemes by reducing instabilities while guaranteeing the tokamak integrity. In this paper, a novel model predictive control (MPC) scheme has been developed and successfully employed to optimize both current and internal inductance of the plasma, which influences the L-H transition timing, the density peaking, and pedestal pressure. Results show that the internal inductance and current profiles can be adequately controlled while maintaining the minimal control action required in tokamak operation.
APA, Harvard, Vancouver, ISO, and other styles
10

Stepanenko, A. A. "Effect of electromagnetic wave reflection from conducting surfaces on blob dynamics in the tokamak scrape-off layer." Physics of Plasmas 30, no. 4 (April 2023): 042301. http://dx.doi.org/10.1063/5.0140097.

Full text
Abstract:
Electromagnetic dynamics of blobs in hot scrape-off-layer plasmas of the tokamak are affected by excitation of the Alfvén waves and their subsequent propagation to the machine first wall along open magnetic field lines. In this study, the interaction of electromagnetic perturbations with the conducting tokamak wall and the resulting impact of these perturbations on the motion of filaments at the tokamak edge are analyzed. The model describing blob dynamics is presented. To describe the reflection of the Alfvén waves from the tokamak wall, the new form of sheath boundary conditions for the parallel current and electrostatic potential at the plasma–sheath interface is proposed. It is demonstrated that depending on the wall resistivity, the waves can be either absorbed or reflected by the wall, influencing the excitation of electromagnetic fluctuations inside the filament plasma. The theoretical conclusions of the study are supported with the BOUT++ numerical modeling of blob dynamics at the edge of the DIII-D and NSTX tokamaks. It is shown that taking the reflective boundary conditions into account leads to the excitation of the standing Alfvén waves in the filament, periodically canceling the electrostatic currents inside the blob.
APA, Harvard, Vancouver, ISO, and other styles
More sources

Dissertations / Theses on the topic "Tokamak"

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/.

Full text
Abstract:
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.
APA, Harvard, Vancouver, ISO, and other styles
2

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

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

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

Full text
Abstract:
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
APA, Harvard, Vancouver, ISO, and other styles
4

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

Full text
Abstract:
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.
APA, Harvard, Vancouver, ISO, and other styles
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.

Full text
Abstract:
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
APA, Harvard, Vancouver, ISO, and other styles
6

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

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

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

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

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

Full text
Abstract:
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
APA, Harvard, Vancouver, ISO, and other styles
9

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

Full text
Abstract:
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
APA, Harvard, Vancouver, ISO, and other styles
10

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

Full text
APA, Harvard, Vancouver, ISO, and other styles
More sources

Books on the topic "Tokamak"

1

Grange, Jean-Christophe. Tokamak. Grenoble: Gle nat, 2009.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
2

Riedel, Kurt S. Advanced statistics for tokamak transport colinearity and tokamak to tokamak variation. New York: Courant Institute of Mathematical Sciences, New York University, 1989.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
3

Knoepfel, Heinz, ed. Tokamak Start-up. Boston, MA: Springer US, 1986. http://dx.doi.org/10.1007/978-1-4757-1889-8.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Song, Yuntao, Weiyue Wu, and Shijun Du. Tokamak Engineering Mechanics. Berlin, Heidelberg: Springer Berlin Heidelberg, 2014. http://dx.doi.org/10.1007/978-3-642-39575-8.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Tokamak Fusion Test Reactor. Princeton, N.J: Princeton University, Plasma Physics Laboratory, 1986.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
6

Theory of tokamak plasmas. Amsterdam: North-Holland, 1989.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
7

Alfredo, Pironti, ed. Magnetic control of tokamak plasmas. London: Springer, 2008.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
8

Pitcher, C. S. Tokamak plasma interaction with limiters. Mississauga, Ont: Ontario Hydro, 1987.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
9

Ariola, Marco, and Alfredo Pironti. Magnetic Control of Tokamak Plasmas. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-29890-0.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Pitcher, Charles Spencer. Tokamak plasma interaction with limiters. Downsview, Ont: Institute for Aerospace Studies, 1988.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
More sources

Book chapters on the topic "Tokamak"

1

Miyamoto, Kenro. "Tokamak." In Plasma Physics for Controlled Fusion, 337–88. Berlin, Heidelberg: Springer Berlin Heidelberg, 2016. http://dx.doi.org/10.1007/978-3-662-49781-4_15.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Palumbo, D. "The Start-up of Tokamaks and the Tokamak Start-up." In Tokamak Start-up, 181–88. Boston, MA: Springer US, 1986. http://dx.doi.org/10.1007/978-1-4757-1889-8_10.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Sheffield, J. "Tokamak Start-Up." In Tokamak Start-up, 7–43. Boston, MA: Springer US, 1986. http://dx.doi.org/10.1007/978-1-4757-1889-8_2.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Song, Yuntao, Weiyue Wu, Shijun Du, and Xiaojun Ni. "Introduction." In Tokamak Engineering Mechanics, 1–20. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-39575-8_1.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Wu, Weiyue, Yuntao Song, Shijun Du, and Zhongwei Wang. "Mechanical Basics." In Tokamak Engineering Mechanics, 21–45. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-39575-8_2.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Song, Yuntao, Weiyue Wu, Weiwei Xu, Xufeng Liu, and Sumei Liu. "Electromagnetic, Structural and Thermal Analyses of the Vacuum Vessel." In Tokamak Engineering Mechanics, 47–98. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-39575-8_3.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Song, Yuntao, Mingzhun Lei, Xuebing Peng, Weiwei Xu, Weiyue Wu, and Shijun Du. "In-vessel Components." In Tokamak Engineering Mechanics, 99–158. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-39575-8_4.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Du, Shijun, Weiyue Wu, Yuntao Song, Xufeng Liu, and Jinxing Zheng. "Superconducting Magnet." In Tokamak Engineering Mechanics, 159–201. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-39575-8_5.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Lei, Mingzhun, Yuntao Song, Sumei Liu, and Shijun Du. "Thermal Shield." In Tokamak Engineering Mechanics, 203–22. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-39575-8_6.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Wu, Weiyue, Yuntao Song, Shijun Du, Songke Wang, and Xiaojun Ni. "Cryostat." In Tokamak Engineering Mechanics, 223–41. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-39575-8_7.

Full text
APA, Harvard, Vancouver, ISO, and other styles

Conference papers on the topic "Tokamak"

1

Waldon, C., R. Morrell, D. Buckthorpe, M. Davies, and P. Sherlock. "Engineering Practices for Tokamak Window Assemblies." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75858.

Full text
Abstract:
For fusion tokamak reactors the diagnostics and RF heating systems require the use of components with parts made of non-metallic materials. These can form part of the vacuum boundary of the tokamak which is the primary safety boundary and have a function of containing tritium fuel or activated gases and particulate debris. The engineering practices for such components and non-metallic materials are in an early state of preparation and require development to enable systems to be used in a safety and licensing context. Such developments will have to reflect the brittle nature of the materials, and are likely to be based on established arguments developed within the nuclear industry, such as containment and defence in depth. Given these requirements this task is a major challenge. The window systems fall broadly into two categories: • Transmission windows for the input of high-power microwaves to drive and heat the plasma; • Diagnostic windows to monitor the plasma. Currently there are no established fusion design codes that can be used to assure nuclear safety and a consistent engineering approach for either application. This paper reviews the progress made in developing such practices for transmission and diagnostic windows made from ceramic materials. The investigations undertaken and the engineering practices addressed for the tokamak windows generally fall into the following areas: • reviews of potential candidate materials along with a summary of the available property data; • definition of the function of torus window assemblies and an outline of the complexity and variety of design considerations (including historical failures, and statutory requirements); • development of the design methodology for technical ceramics; • definition of the design routes considered and selected (rule, analysis, experiment); • consideration of the material data available (or lack of) for technical ceramics and their failure criteria; • qualification and design of metallic / ceramic joints; • definition of the requirements with regard to quality control, from manufacture to in-service inspection; • development and formation of a draft code procedure. The practices and procedures developed are considered to be an important contribution and significant step forward in the development of a fusion tokamak windows code. Important contributions have been made to the design, procurement and installation philosophies for windows, especially the development of design criteria and the application of pressure proof-testing. This paper provides a review of key requirements and issues, with recommendations to allow development of the code for acceptance by nuclear regulators for tokamaks such as the International Tokamak Experimental Reactor (ITER) and future fusion reactor power plants.
APA, Harvard, Vancouver, ISO, and other styles
2

Sykes, A. "Compact tokamak fusion." In 2015 IEEE 15th International Conference on Environment and Electrical Engineering (EEEIC). IEEE, 2015. http://dx.doi.org/10.1109/eeeic.2015.7165195.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Rowan, William L. "Spectroscopic diagnostics and atomic physics experiments in tokamak plasmas." In OSA Annual Meeting. Washington, D.C.: Optica Publishing Group, 1988. http://dx.doi.org/10.1364/oam.1988.thk2.

Full text
Abstract:
As for other tokamaks, spectroscopy of the plasma produced in the Texas Experimental Tokamak (TEXT) has resulted in significant contributions to both atomic and plasma physics. The identification of magnetic and electric dipole transitions in highly ionized species allowed the determination of energy levels while increasing the availability of emission lines for plasma experiments and for use as standards in other atomic physics studies. Collisional rate measurements provided benchmarks for atomic theory and the basic data for implementation of some plasma diagnostics. Complementing the usual plasma physics role as a tool in the study of impurity behavior or ion energy transport, spectroscopy is now also employed in the study of plasma turbulence, MHD stability, and the nonthermal effects of rf heating. As accuracy requirements for some of these measurements increase, active spectroscopic techniques are displacing the familiar passive ones. The experiments which illustrate this review were all conducted on TEXT and are the work of physicists from a number of laboratories. They are chosen to emphasize advances in physics and to describe the critical role of spectroscopy in plasma physics.
APA, Harvard, Vancouver, ISO, and other styles
4

Suckewer, S., L. Bromberg, and D. Cohn. "Small Scale Tokamak for X-Ray Lithography." In Soft X-Ray Projection Lithography. Washington, D.C.: Optica Publishing Group, 1992. http://dx.doi.org/10.1364/sxray.1992.wb3.

Full text
Abstract:
A toroidal plasma device (tokamak) with electron temperature in the range of 150-200 eV and density ~1013 particles/cm3 can be built as a very compact and relatively inexpensive machine (~3 M$). A tokamak with a major radius R ≈ 1m, minor radius r ≈ 0.1m, and confining magnetic field ~ 5k Gauss is not a very attractive for fusion research, however it can be an excellent source of soft X-ray radiation. In particular if operated in a steady state regime or at a high repetition rate it can provide several orders of magnitude more soft X-ray radiation than a small synchrotron with an undulator. This can be seen easily by comparing the total radiated power of a small tokamak and a small sychrotron, taking into account the spectral intensity distribution of line radiation from the tokamak plasma and of continuum radiation from synchrotron. We will present related calculations. Based on the calculations we will discuss the usefulness of a small tokamak for X-ray projection and proximity lithography and simple methods to change the dominant lines in the plasma radiation spectrum.
APA, Harvard, Vancouver, ISO, and other styles
5

Majeski, R., T. Gray, R. Kaita, H. Kugel, T. Kozub, D. Mansfield, J. Spaleta, et al. "THE LITHIUM TOKAMAK EXPERIMENT (LTX) AND LOW-RECYCLING SPHERICAL TOKAMAK REACTORS." In CURRENT TRENDS IN INTERNATIONAL FUSION RESEARCH: Proceedings of the 7th Symposium—Selected Presentations. AIP, 2009. http://dx.doi.org/10.1063/1.3204591.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Sevillano-Berasategui, M. G., I. Garrido, A. J. Garrido, and O. Barambones. "Review of tokamak codes." In 2008 5th International Conference on Electrical Engineering, Computing Science and Automatic Control (CCE). IEEE, 2008. http://dx.doi.org/10.1109/iceee.2008.4723430.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Kim, C. S., H. S. Lee, and M. Kwon. "KSTAR Tokamak Neutronic Analysis." In IEEE Conference Record - Abstracts. 2005 IEEE International Conference on Plasma Science. IEEE, 2005. http://dx.doi.org/10.1109/plasma.2005.359096.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

De Tommasi, G., D. Alves, T. Bellizio, R. Felton, A. Neto, F. Sartori, R. Vitelli, et al. "Real-time systems in tokamak devices. A case study: The JET tokamak." In 2010 17th Real-Time Conference - IEEE-NPSS Technical Committee on Computer Applications in Nuclear and Plasma Sciences (RT 2010). IEEE, 2010. http://dx.doi.org/10.1109/rtc.2010.5750334.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Garrido, Izaskun, Aitor J. Garrido, Oscar Barambones, Patxi Alkorta, and Francisco J. Maseda. "Tokamak state-space control modeling." In 2008 Canadian Conference on Electrical and Computer Engineering - CCECE. IEEE, 2008. http://dx.doi.org/10.1109/ccece.2008.4564779.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Duan, X. R., Y. Huang, D. Q. Liu, W. M. Xuan, L. Y. Chen, J. Rao, X. M. Song, et al. "Operation of HL-2A tokamak." In 2011 IEEE 24th Symposium on Fusion Engineering (SOFE). IEEE, 2011. http://dx.doi.org/10.1109/sofe.2011.6052199.

Full text
APA, Harvard, Vancouver, ISO, and other styles

Reports on the topic "Tokamak"

1

Riedel, K. S. Advanced statistics for tokamak transport colinearity and tokamak to tokamak variation. Office of Scientific and Technical Information (OSTI), March 1989. http://dx.doi.org/10.2172/6317119.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Firestone, M. A., T. K. Mau, and R. W. Conn. ECH tokamak. Office of Scientific and Technical Information (OSTI), April 1985. http://dx.doi.org/10.2172/5733530.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Reid, R. L., R. J. Barrett, T. G. Brown, G. E. Gorker, R. J. Hooper, S. S. Kalsi, D. H. Metzler, Y. K. M. Peng, K. E. Roth, and P. T. Spampinato. Tokamak Systems Code. Office of Scientific and Technical Information (OSTI), March 1985. http://dx.doi.org/10.2172/5918112.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Murray, J. G., and G. E. Gorker. Tokamak ARC damage. Office of Scientific and Technical Information (OSTI), January 1985. http://dx.doi.org/10.2172/6101616.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Wootton, A. J. Texas Experimental Tokamak. Office of Scientific and Technical Information (OSTI), April 1993. http://dx.doi.org/10.2172/6560795.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Wootton, A. Texas Experimental Tokamak. Office of Scientific and Technical Information (OSTI), April 1990. http://dx.doi.org/10.2172/7131470.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Ivers, T. H., M. E. Mauel, G. A. Navratil, M. K. Sankar Vijaya, E. Eisner, A. Garofalo, D. Gates, R. Kombargi, E. Nadle, and Qingjun Xiao. High beta tokamak research. Office of Scientific and Technical Information (OSTI), December 1992. http://dx.doi.org/10.2172/6720777.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Dabiri, A. E. Multiplex tokamak power plant. Office of Scientific and Technical Information (OSTI), July 1986. http://dx.doi.org/10.2172/5489184.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Candy, Jeff. AToM (Advanced Tokamak Modeling). Office of Scientific and Technical Information (OSTI), November 2017. http://dx.doi.org/10.2172/1412538.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Steiner, D. ARIES tokamak reactor study. Office of Scientific and Technical Information (OSTI), July 1993. http://dx.doi.org/10.2172/6071074.

Full text
APA, Harvard, Vancouver, ISO, and other styles
You might also be interested in the extended bibliographies on the topic 'Tokamak' for particular source types:
Journal articles Dissertations / Theses Books
We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!

To the bibliography