Literatura científica selecionada sobre o tema "Physique des tokamaks"
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Artigos de revistas sobre o assunto "Physique des tokamaks"
"Fusion nucléaire, panorama des programmes de recherche dans le monde". Revue Générale Nucléaire, n.º 6 (novembro de 2018): 32–33. http://dx.doi.org/10.1051/rgn/20186032.
Texto completo da fonteTeses / dissertações sobre o assunto "Physique des tokamaks"
Autricque, Adrien. "Dust transport in tokamaks". Electronic Thesis or Diss., Aix-Marseille, 2018. http://www.theses.fr/2018AIXM0315.
Texto completo da fonteThermonuclear 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
Duthoit, François-Xavier. "Physique néoclassique pour la génération de courant dans les plasmas de tokamaks". Phd thesis, Ecole Polytechnique X, 2012. http://pastel.archives-ouvertes.fr/pastel-00708795.
Texto completo da fonteAutricque, Adrien. "Dust transport in tokamaks". Thesis, Aix-Marseille, 2018. http://www.theses.fr/2018AIXM0315/document.
Texto completo da fonteThermonuclear 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
Pilipenko, Denis. "Influence of ion cyclotron resonance heating on tranport of seeded impurities in the tokamak plasmas". Doctoral thesis, Universite Libre de Bruxelles, 2005. http://hdl.handle.net/2013/ULB-DIPOT:oai:dipot.ulb.ac.be:2013/210947.
Texto completo da fontePlasma heating by radio-frequency (RF) waves has been proven to be a useful tool to control the behaviour of puffed impurities. In order to asses the prospective of impurity control by RF waves in larger devices and under reactor conditions, proper modelling approaches have been developed. One of the important parameters, which should be evaluated, is the averaged energy or temperature of heated impurity ions. The latter determines, in particular, the power transported to the main species, and, thus, the heating efficiency. Besides, the temperature of impurity ions characterizes the intensity of particle losses for heated impurities. An approach to compute the impurity temperature under such conditions is elaborated. It is based on the construction of a hierarchy of approximate solutions to the impurity heat balance equation and takes into account that the density and, thus, the heat conductivity of heated ion species can change by many orders of magnitude with the position in the plasma. The developed method has been incorporated into 1D transport code RITM. Coupled with the full wave code TORIC, the particle and heat balances for impurity and main plasma species provide a self-consistent approach to model the ion cyclotron resonance heating (ICRH) scenario. The modelling of various heating scenarios for several tokamaks displays the impacts of impurity heating on the heat and particles transport and heating efficiency. To investigate the possibility of impurity control at the large tokamak the experiment on selective impurity heating in the mode conversion H/D plasma was prepared and carried out in the tokamak JET.
Doctorat en sciences, Spécialisation physique
info:eu-repo/semantics/nonPublished
Sourd, Frédéric. "Etudes des électrons découplés accélérés lors des disruptions majeures dans les tokamaks". Aix-Marseille 1, 2004. http://www.theses.fr/2004AIX11049.
Texto completo da fonteThe aim of this thesis is a better comprehension of the runaway electrons creation and to qualify a disruption mitigation method. In first part, we use Tore Supra disruptions to simulate the runaway electrons creation. We calculate the electric field in plasma to work out the electrons number with Dreicer and “hot tail” model. The second part of this thesis consists to determinate the electron distribution function. We simulate interaction of these electrons with a wall element. Finally we create a high-pressure gas jet to injected helium in less 5ms to mitigate disruption. The opening command is based on disruption detection method. This should be useful to qualify the principle of this technique what is allowed to ITER
Azeroual, Abderrhaman (19. "Pompage des particules dans les tokamaks au moyen d'une structure à évents : le Divertor Ergodique de Tore Supra". Aix-Marseille 1, 2000. http://www.theses.fr/2000AIX11016.
Texto completo da fonteYang, Chang. "Analyse et mise en oeuvre des schémas numériques pour la physique des plasmas ionosphériques et de tokamaks". Thesis, Lille 1, 2011. http://www.theses.fr/2011LIL10183/document.
Texto completo da fonteThis thesis focuses on modeling and numerical simulation of ionospheric and Tokamak plasmas.The first part of this work concerns the modeling and simulation of ionospheric perturbations effects for earth-satellite communications. The starting point of this part is an asymptotic analysis of Euler-Maxwell model leading to Dynamo model, which results into a 3D coupling problem between an elliptic equation for the electric potential and a mass conservation equation for the plasma density. Because of the strong anisotropy of the diffusion matrix associated with the elliptic equation, we developed an asymptotic preserving numerical scheme thus allowing the well conditioned linear system. The simulation of the mass conservation equation is made by using high order conservation laws scheme. The validation of this model Dynamo is obtained by a comparison with the 2D Striation model. In the second part, we are interested in tokamak plasma. We extract from TOKAM3D model, a 2D nonlinear energy balance equation containing all the numerical difficulties. Standard numerical methods are very CPU consuming, thus we develop an implicit-explicit scheme shown efficient and stable for this type of problem. Finally, this scheme is combined with dimensional splitting method for the discretization and numerical experiments are then presented
Balbin, Arias Julio José. "Investigation of the dependency of separatrix density of tokamaks as a function of engineering parameters". Electronic Thesis or Diss., Aix-Marseille, 2022. http://www.theses.fr/2022AIXM0174.
Texto completo da fonteThe analysis of JET H-mode discharges considered for this work is detailed. A first analysis of the dataset shows that some engineering parameters cannot be considered as independent for our analysis because many discharges were performed considering the same typical values of these parameters, such as the toroidal magnetic field and the plasma current. Thus, two main engineering parameters are first identified and will be used for the scaling law on the ratio of the separatrix density to the top pedestal one, namely the plasma current IP and the total injected power PTOTAL. This first scaling law seems to predict the experimental data quite well for low and medium values of the separatrix density, while at high density a strong discrepancy appears. In order to get further insight on such behavior the discharges were analyzed in terms of divertor magnetic configuration. A clear difference is observed between experiments with a corner-corner divertor magnetic configuration compared to the horizontal-vertical ones or vertical-vertical ones. This result suggests the introduction a parameter taking into account the quality of confinement. In this way, a better agreement between predictions and experimental results is obtained for both low and high-density values. Finally, the same type of study is performed on TCV and a scaling law taking into account both devices is derived
Doré, Patrice. "Développement d'une technique de mesure d'érosion et de redéposition par interférométrie de speckle dans un tokamak". Aix-Marseille 1, 2006. http://www.theses.fr/2006AIX11029.
Texto completo da fonteSelig, Gaël. "Équilibre évolutif à frontière libre et diffusion résistive dans un plasma de tokamak". Nice, 2012. http://www.theses.fr/2012NICE4075.
Texto completo da fonteIn a Tokamak, in order to create the necessary conditions for nuclear fusion to occur, a plasma is maintained by applying magnetic fields. Under the hypothesis of an axial symmetry of the tokamak, the study of the magnetic configuration at equilibrium is done in two dimensions, and is deduced from the poloidal flux function ψ. This function is solution of a non linear partial differential equation system, known as equilibrium problem. This thesis presents the time dependent free boundary equilibrium problem, where the circuit equations in the tokamak’s coils and passive conductors are solved together with the Grad-Shafranov equation to produce a dynamic simulation of the plasma. In this framework, the Finite Element equilibrium code CEDRES++ has been improved in order to solve the aforementioned dynamic problem. Consistency tests and comparisons with the DINA-CH code on an ITER’s vertical instability case have validated the results. Then, the resistive diffusion of the plasma’s current density has been simulated using a coupling between CEDRES++ and the averaged one-dimensional diffusion equation, and it has been successfully compared with the integrated modeling code CRONOS