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Artykuły w czasopismach na temat "Fusion thermonucléaire par confinement magnétique"
Bonhomme, Gérard. "La fusion nucléaire par confinement magnétique : avancées, défis et perspectives". Reflets de la physique, nr 77 (luty 2024): 104–11. http://dx.doi.org/10.1051/refdp/202477104.
Pełny tekst źródłaJacquinot, Jean. "ITER et les recherches sur la fusion par confinement magnétique". Reflets de la physique, nr 32 (styczeń 2013): 19–25. http://dx.doi.org/10.1051/refdp/201332019.
Pełny tekst źródłaSarazin, Yanick. "Physique des plasmas - 9e Festival de Théorie à Aix-en-Provence". Reflets de la physique, nr 56 (styczeń 2018): 40–41. http://dx.doi.org/10.1051/refdp/201856040.
Pełny tekst źródłaGingras, Yves, i Michel Trépanier. "Le Tokamak de Varennes et le programme canadien de fusion nucléaire: anatomie d'une décision". Politique et interventions 30, nr 3 (12.04.2005): 421–46. http://dx.doi.org/10.7202/056472ar.
Pełny tekst źródłaRozprawy doktorskie na temat "Fusion thermonucléaire par confinement magnétique"
Dachicourt, Remi. "Contrôle du rayonnement dans les plasmas de fusion par confinement magnétique". Thesis, Aix-Marseille, 2012. http://www.theses.fr/2012AIXM4097.
Pełny tekst źródłaThe route presently envisaged towards the development of a commercial fusion power plant includes that a few remaining physics issues are solved. The present work addresses two of them: plasma radiation control, as a part of the more general power handling issue, and high density tokamak operation. These two issues will be most critical in the demonstration reactor, called DEMO, intermediate step between ITER and a future commercial reactor. For DEMO, the need to radiate a large fraction of the power so as to limit the peak power load on the divertor will be a key constraint. High confinement will have to be combined with high radiated power fraction, and the required level of plasma purity. A fractional radiated power, including bremsstrahlung radiation, of 80-90% of the total power loss will be required. Present studies suggest that this level of radiation could be achieved with acceptable levels of plasma contamination, but improvements are required in models of plasma radiation, and compatibility with the edge transport barrier of the H-mode has to be further assessed. Correlatively, high plasma density (typically with a Greenwald fraction above unity) is required, both because it allows efficient radiation of exhaust power to the reactor walls, and because the final cost of electricity is directly influenced by the achieved Greenwald value
Geulin, Eléonore. "Contribution to the modeling of pellet injection : from the injector to ablation in the plasma". Electronic Thesis or Diss., Aix-Marseille, 2023. http://www.theses.fr/2023AIXM0066.
Pełny tekst źródłaThe preferred method of fueling fusion device is the use of D and/or T pellets injected into the plasma. They are currently used, but the results cannot be extrapolated to future larger reactors where the design of the injection system and the construction of scenarios will be mainly based on simulations. It is therefore important to fill in the gaps in the existing models from the manufacture of pellets to the deposition of material in the plasma. Two lacks of knowledge appear: the modeling of the pellet transport in the injection pipe and the validation of the ablation process. This work aims to fill these gaps and consists of 3 parts.- Describe the physics of material deposition, then the state of the art of the main results and finally the description of the pellet injection systems planned for the next machines.- Model the transport of the pellet in the injection pipe. The effects taken into account in the model are the weakening of the ice during rebounds, the increase in its temperature and its erosion. The model gives in particular the slowing down and the loss of mass of the pellet during the journey, as well as the stored elastic energy linked to its integrity on leaving the tube.- Contribute to the validation of the HPI2 ablation code, by comparing its predictions to data measured in ablation clouds. The method used is a calculation of synthetic data sets from simulations and comparing them to measurements. This method made it possible to validate the assumptions and approximations of the ablation model
Ialovega, Mykola. "Influence des conditions de surface sur le piégeage de l'hydrogène dans le tungstène". Electronic Thesis or Diss., Aix-Marseille, 2021. http://www.theses.fr/2021AIXM0058.
Pełny tekst źródłaInvestigations of hydrogen isotopes and helium retention in plasma facing components (PFC) that are exposed to various plasma conditions are important for future fusion devices such as ITER and DEMO. Due to its favorable physical properties, tungsten (W) has been chosen as the plasma-facing material of the ITER divetor. In the deuterium/tritium (D/T) phase of ITER, W PFC will experience incident particles flux composed of hydrogen isotopes (HI), helium (He), impurities and neutrons. In particular, it has been found that He significantly affects W PFC near surface, with the formation of dislocation loops, bubbles, or even W-fuzz. Furthermore, since oxygen is a typical main impurity in tokamak vacuum vessels, W PFC can get oxidized due to the high surface temperatures during ITER operation. Such surface and bulk modifications of W PFC may significantly affect the retention and other physical properties of W leading to an increase of the T inventory in the tokamak. Also, the modification of retention properties of PFC may impact plasma edge physics due to the outgassing of cold HI molecules or He atoms.\\In this PHD thesis, laboratory experiments involving ion implantation and thermal desorption spectrometry (TDS) technique were used to investigate the fundamental retention properties of HI in W PFC due to: - The presence of an oxide layer grown on the polycrystalline W surfaces in ITER relevant conditions, - An impact of ITER relevant He irradiation on the W surface and near-surface layer. TDS measurements were coupled with observations of modification occurring on the surface, in the bulk and in the structure of various PCW samples
Walraet, François. "Propagation et rétrodiffusion d'un faisceau laser lissé dans un plasma de fusion thermonucléaire". Palaiseau, Ecole polytechnique, 2003. http://www.theses.fr/2003EPXX0011.
Pełny tekst źródłaBardin, Sébastien. "Etude des interactions plasma-paroi par imagerie rapide : application aux plasmas de laboratoire et de tokamak". Thesis, Université de Lorraine, 2012. http://www.theses.fr/2012LORR0012/document.
Pełny tekst źródłaThe necessity to find a new energy source has lead scientists to explore the way of thermonuclear fusion by magnetic confinement considered as one of the most promising possibility. However the production of such plasmas in the current tokamaks lies to several challenges like the interactions between the plasma and the first wall which spark off the creation of a lot of dust in the plasma which could be problematic for the operation of the next fusion reactors. The knowledge of dust production rates, localisation and transport through the vacuum vessel during plasma phases is of primary importance and must be investigated in preparation of ITER. A time and resource efficient algorithm named TRACE, validated thanks to a dedicated laboratory experiment, is used to detect and track dust particles in ASDEX Upgrade during plasma phase. It allows for automatically analyzing videos originating from fast framing cameras. A statistic about micron sized dust detection rate as a function of cumulated discharge duration is made on a large number of discharges (1470). First analyses covering five last campaigns clearly confirm that the amount of dust is significantly low in most of discharges realized in ASDEX Upgrade, excepted for specific conditions corresponding to off-normal plasma phases (disruptions, strong plasma fluctuations including ELMs, plasma displacement toward PFCs and inefficient absorption of heating power). These observations allow to identify the risky plasma discharges and choose the most efficient plasmas scenarios for ITER. It seems to also confirm the applicability of an all tungsten first wall for future fusion reactors as ITER
Coulette, David. "Simulation numérique de modèles cinétiques réduits pour l'étude de la dynamique des plasmas de fusion par confinement magnétique". Thesis, Université de Lorraine, 2013. http://www.theses.fr/2013LORR0159/document.
Pełny tekst źródłaThe research exposed therein is developed in the context of the study of turbulent energy and particle transport phenomena occuring in magnetically confined fusion plasmas. A study of the ion temperature gradient instability, one of the main sources of such turbulent transport, is carried out using a gyrokinetic model. The main originality of this work lies in the use of a reduced model, the so-called Multi-Water-Bag model, which allows to reduce the problem dimension while preserving kinetic effects. The model is developed in two types of confinement field geometries. In cylindrical geometry, the growth of the instability is analysed by the mean of three dynamical models : linear, quasi-linear and non-linear. Starting from a given unstable stationary state, linear stability analysis allows one to obtain spectral and geometrical characteristics of the instability. In a second phase, comparing results of numerical simulations implementing the three dynamical models, the growth of turbulence is analysed as well as the first stages of non-linear saturation of the instability. In toroidal geometry, a linear stability analysis is performed. Two different methods, time-based and spectral, were implemented in order to obtain the spectral and geometrical characteristics of the most unstable modes. In both field geometries encompassed by this research, the numerical methods used to obtain the results are described and their performances analyzed. Throughout the work, particular care is given to the balance between the benefits and costs of the Multi-Water-Bag reduction
Isoardi, Livia. "Modelisation du transport dans le plasma de bord d'un tokamak". Aix-Marseille 3, 2010. http://www.theses.fr/2010AIX30066.
Pełny tekst źródłaHelou, Walid. "Design and operation of antennas at the ion cyclotron and lower hybrid range of frequencies for nuclear fusion reactors". Electronic Thesis or Diss., Aix-Marseille, 2017. http://www.theses.fr/2017AIXM0395.
Pełny tekst źródłaThe thesis provides at first a brief introduction to magnetic nuclear fusion and tokamaks. It explains the need for auxiliary plasma heating and current-drive electromagnetic systems at the Ion Cyclotron and Lower Hybrid Range of Frequencies (ICRF and LHRF). The thesis then sets antenna specifications that allow satisfying proper plasma wave propagation and proper wave-particle resonance. The Radio Frequency (RF) network solver SIDON developed for this thesis is then presented. The thesis then discusses the different types of ICRF antennas and details the challenges of the impedance matching in ICRF arrays of straps. WEST ICRF launchers are discussed in great detail and simulations of impedance matching scenarios for these launchers using SIDON are reported. The thesis reports on the low-power (milliwatt range) testbed that has been developed for WEST ICRF launchers, as well as the low-power tests of the first one among them. Furthermore, high power (megawatt range) experiments on plasma with the JET ICRF ITER-Like Antenna are reported. The thesis then provides an overview about existing LHRF antennas and discusses the numerical modeling of the coupling of waveguide phased arrays to the plasma. The RF design of ASTARTE-LP and its feeding circuit is discussed. ASTARTE-LP is a low-power (milliwatt range) prototype LHRF antenna based on the Slotted Waveguide Antenna concept that has been designed and built to perform proof of principle experiments on the COMPASS tokamak. The experimental validation of ASTARTE-LP and its feeding circuit before the experiments on COMPASS, as well as the experiments performed on COMPASS plasmas are reported
Helou, Walid. "Design and operation of antennas at the ion cyclotron and lower hybrid range of frequencies for nuclear fusion reactors". Thesis, Aix-Marseille, 2017. http://www.theses.fr/2017AIXM0395/document.
Pełny tekst źródłaThe thesis provides at first a brief introduction to magnetic nuclear fusion and tokamaks. It explains the need for auxiliary plasma heating and current-drive electromagnetic systems at the Ion Cyclotron and Lower Hybrid Range of Frequencies (ICRF and LHRF). The thesis then sets antenna specifications that allow satisfying proper plasma wave propagation and proper wave-particle resonance. The Radio Frequency (RF) network solver SIDON developed for this thesis is then presented. The thesis then discusses the different types of ICRF antennas and details the challenges of the impedance matching in ICRF arrays of straps. WEST ICRF launchers are discussed in great detail and simulations of impedance matching scenarios for these launchers using SIDON are reported. The thesis reports on the low-power (milliwatt range) testbed that has been developed for WEST ICRF launchers, as well as the low-power tests of the first one among them. Furthermore, high power (megawatt range) experiments on plasma with the JET ICRF ITER-Like Antenna are reported. The thesis then provides an overview about existing LHRF antennas and discusses the numerical modeling of the coupling of waveguide phased arrays to the plasma. The RF design of ASTARTE-LP and its feeding circuit is discussed. ASTARTE-LP is a low-power (milliwatt range) prototype LHRF antenna based on the Slotted Waveguide Antenna concept that has been designed and built to perform proof of principle experiments on the COMPASS tokamak. The experimental validation of ASTARTE-LP and its feeding circuit before the experiments on COMPASS, as well as the experiments performed on COMPASS plasmas are reported
Salazar, Luigui. "Data-driven discovery approach to tackle turbulence in fusion plasmas". Electronic Thesis or Diss., Université de Lorraine, 2023. http://www.theses.fr/2023LORR0327.
Pełny tekst źródłaOne way to achieve fusion on Earth is through toroidal magnetic confinement, in which the main devices are tokamaks and stellarators. One of the main limiting phenomena is turbulence. This is the result of a mixture of instabilities on different temporal and spatial scales. The aim of this thesis was to contribute to the understanding of turbulent transport, which is the interaction of this turbulence with the plasma properties, in magnetically confined plasmas, focusing on the characterisation of density fluctuations and their dynamics using reflectometry. From the signal spectrum provided by reflectometry, each spectral component was extracted using an algorithm developed in this thesis. It performs this spectral decomposition(Low frequency component, Broadband component, QC modes and noise) in an intelligent way (without ad hoc constraints), preserving its statistical and physical information. Particular attention has been paid to a spectral component, the so-called QC modes because of its link with TEM, an instability acting in turbulent transport. Thanks to the algorithm, the properties and dynamics of the QC modes have been studied, allowing a statistical study and a detailed analysis of the interaction with other spectral components in different magnetic configurations: ToreSupra(limiter), WEST(divertor) and W7X(island divertor). This work is qualified as exploratory because there were no methods to access these QC mode properties and dynamicsThe statistical studies carried out with the ToreSupra and WEST database provided a probability map of the occurrence of the QC modes in the ohmic confinement regime, confirming their link with the TEM,but also 2 more classes, one at low current and another at high current were found. The broadband component was also analysed as it is believed to be related to the microturbulence. Since the spectral amplitude of the BB component is found with the AGG, mainly μ and β, which correspond to the assymetry and shape of the spectrum, show a variation during the transition. On the other hand, the analysis of the dynamics of the QC modes by means of an algorithm developed in this thesis showed a recurrent interaction between the QC modes and the modes in the LF component. Finally, in order to better discriminate the QC modes, the concept of transfer entropy is used to analyse the causality in this interaction. Some cases shows the interaction between the LF component corresponding to the sawtooth instability and the QC modes. All this analysis of dynamics and also causality is then applied to ToreSupra, WEST and W7X, where there is a similar dynamic for signals with bi-directional causality, i.e. not only from the LF component to the QC modes, but also from the QC modes to the BB component. In addition, the ECRH is also examined for the TS database, which shows a decrease in the probability of QC modes as the PECRH increases. Since these QC modes appear in different magnetic configurations, the ultimate objective is to discover if all these QC modes are produced by the same mechanism, since it is believed that there must be a universal mechanism underlying the physics in fusion plasmas, this is still under investigation
Części książek na temat "Fusion thermonucléaire par confinement magnétique"
"4 Quelques aspects du confinement magnétique". W La fusion thermonucléaire contrôlée, 59–76. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-1217-2-008.
Pełny tekst źródła"4 Quelques aspects du confinement magnétique". W La fusion thermonucléaire contrôlée, 59–76. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-1217-2.c008.
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