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Littérature scientifique sur le sujet « Plasmi in tokamak »

Auteur : Grafiati
Publié le 9 mars 2023
Mis à jour le 31 juillet 2025

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Articles de revues sur le sujet "Plasmi in tokamak"

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Liang, Chen, Zhuang Ma, Zhen Sun, et al. "Demonstration of object location, classification, and characterization by developed deep learning dust ablation trail analysis code package using plasma jets." Review of Scientific Instruments 94, no. 2 (2023): 023506. http://dx.doi.org/10.1063/5.0123614.

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Based on deep learning, a Dust Ablation Trail Analysis (DATA) code package is developed to detect dust ablation trails in tokamaks, which is intended to analyze a large amount data of tokamak dusts. To validate and benchmark the DATA code package, 2440 plasma jet images are exploited for the training and test of the deep learning DATA code package, since plasma jets resemble the shape and size of dust ablation clouds in tokamaks. After being trained by 1920 plasma jet images, the DATA code package is able to locate 100% plasma jets, classify plasma jets with the accuracy of >99.9%, and outp
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Voronin A.V., Goryainov V. Yu., Zabrodsky V. V., et al. "Plasma electron temperature measurement by foil soft-X-Ray spectrometer installed on TUMAN-3M and Globus-M2 tokamaks." Technical Physics 67, no. 15 (2022): 2377. http://dx.doi.org/10.21883/tp.2022.15.55263.188-21.

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Technical solution were presented for a foil spectrometer installed on the Globus-M2 and TUMAN-3M tokamaks for measuring the electron plasma temperature. Measurements have been carried out of the time dependence of the plasma temperature in the central region of tokamaks. Using of integrated photodetectors and unique beryllium foils with a thickness of 14-80 μm made it possible to increase the sensitivity of the spectrometer. An important quality of the foils used were the increased values of strength, plasticity, homogeneity, and the absence of surface and internal defects. The combined use o
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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.

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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 i
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Crea, Francesco. "Tokamak, fusion reactor device: Welding and joining for plasma facing components." EPJ Web of Conferences 310 (2024): 00014. http://dx.doi.org/10.1051/epjconf/202431000014.

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Nuclear fusion might be an unlimited, everywhere available source of energy for electrical production. Among the various machines designed and prototyped to demonstrate electricity production from nuclear fusion the tokamak is certainly the most promising. Tokamaks are complex devices, consisting of various components, which in turn are composed of many parts. This contribution reports on the joining and welding techniques used and specifically developed for the elements of a tokamak, with a focus on plasma facing components as the divertor targets.
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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 (2019): 20170438. http://dx.doi.org/10.1098/rsta.2017.0438.

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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.
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Nguyen, van yen Romain, Nicolas Fedorczak, F. Brochard, et al. "Tomographic reconstruction of tokamak plasma light emission from single image using wavelet-vaguelette decomposition." Nuclear Fusion 52, no. 1 (2011): 013005. https://doi.org/10.1088/0029-5515/52/1/013005.

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Images acquired by cameras installed in tokamaks are difficult to interpret because the three-dimensional structure of the plasma is flattened in a non-trivial way. Nevertheless, taking advantage of the slow variation of the fluctuations along magnetic field lines, the optical transformation may be approximated by a generalized Abel transform, for which we propose an inversion technique based on the wavelet-vaguelette decomposition. After validation of the new method using an academic test case and numerical data obtained with the Tokam 2D code, we present an application to an experimental mov
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Garrido, I., A. J. Garrido, M. G. Sevillano, and J. A. Romero. "Robust Sliding Mode Control for Tokamaks." Mathematical Problems in Engineering 2012 (2012): 1–14. http://dx.doi.org/10.1155/2012/341405.

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Nuclear fusion has arisen as an alternative energy to avoid carbon dioxide emissions, being the tokamak a promising nuclear fusion reactor that uses a magnetic field to confine plasma in the shape of a torus. However, different kinds of magnetohydrodynamic instabilities may affect tokamak plasma equilibrium, causing severe reduction of particle confinement and leading to plasma disruptions. In this sense, numerous efforts and resources have been devoted to seeking solutions for the different plasma control problems so as to avoid energy confinement time decrements in these devices. In particul
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Saperstein, A. R., J. P. Levesque, M. E. Mauel, and G. A. Navratil. "Halo current rotation scaling in post-disruption plasmas." Nuclear Fusion 62, no. 2 (2022): 026044. http://dx.doi.org/10.1088/1741-4326/ac4186.

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Abstract Halo current (HC) rotation during disruptions can be potentially dangerous if resonant with the structures surrounding a tokamak plasma. We propose a drift-frequency-based scaling law for the rotation frequency of the asymmetric component of the HC as a function of toroidal field strength and plasma minor radius (f rot ∝ 1/B T a 2). This scaling law is consistent with results reported for many tokamaks and is motivated by the faster HC rotation observed in the HBT-EP tokamak. Projection of the rotation frequency to ITER and SPARC parameters suggest the asymmetric HC rotation will be o
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Sadakov, Sergey, Fabio Villone, Daniel Iglesias, et al. "Practical Model for the Calculation of Lateral Electromagnetic Loads in Tokamaks at Asymmetric Vertical Displacement Events (AVDEs)." Plasma 7, no. 1 (2024): 178–200. http://dx.doi.org/10.3390/plasma7010012.

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This paper describes a new practical numerical model for the calculation of lateral electromagnetic (EM) loads in tokamaks during asymmetric vertical displacement events (AVDEs). The model combines key features of two recently reported trial models while avoiding their drawbacks. Their common basic feature is the superposition of two patterns of halo current: one perfectly symmetric and another perfectly anti-symmetric. This model combines the following features that have not been combined before (a) a helically distorted halo layer wrapping around core plasma, and (b) halo-to-wall interceptio
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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.

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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 noninduct
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Thèses sur le sujet "Plasmi in tokamak"

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CASIRAGHI, IRENE. "First principle based integrated modelling in support of the Divertor Tokamak Test facility design." Doctoral thesis, Università degli Studi di Milano-Bicocca, 2023. https://hdl.handle.net/10281/402360.

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Nel programma di ricerca europeo per la fusione termonucleare controllata sono stati definiti otto differenti obiettivi a lungo termine. Una di queste sfide cruciali riguarda lo smaltimento (exhaust) di particelle ed energia provenienti da un reattore a fusione. Per sviluppare e testare delle strategie alternative atte a risolvere il problema dell'exhaust, una nuova macchina sperimentale è attualmente in costruzione in Italia a Frascati presso il centro di ricerca ENEA: il Divertor Tokamak Test facility (DTT). Per progettare un nuovo tokamak sono richiesti sforzi congiunti di fisici ed ingegne
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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 va
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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 (f
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Hornung, Grégoire. "Etude de la turbulence plasma par réflectrométrie à balayage ultra-rapide dans le tokamak Tore Supra." Thesis, Aix-Marseille, 2013. http://www.theses.fr/2013AIXM4741/document.

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La turbulence plasma engendre un transport anormal de la chaleur et des particules qui dégrade l’efficacité d’un réacteur de fusion. La mesure de la turbulence plasma dans un tokamak est donc essentielle à la compréhension et au contrôle de ce phénomène. Parmi les instruments de mesure à disposition, le réflectomètre à balayage installé sur le tokamak Tore Supra a accès à la densité du plasma et ses fluctuations depuis le bord jusqu’au centre des décharges, avec une excellente résolution spatiale (mm) et temporelle (µs), de l’ordre des échelles de la turbulence. Cette thèse est dédiée à la car
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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.
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Mercadier, Laurent. "Spectrocopie de plasma induit par laser pour l'analyse des composants face au plasma de tokamaks : étude paramétrique et mesures autocalibrées." Thesis, Aix-Marseille 2, 2011. http://www.theses.fr/2011AIX22071/document.

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Lors du fonctionnement d'un réacteur de fusion nucléaire par confinement magnétique comme ITER, une fraction de tritium est piégée par les composants face au plasma et doit être mesurée pour des raisons de sureté nucléaire. La spectroscopie de plasma induit par laser est proposée pour effectuer cette mesure. Le plasma laser produit sur des tuiles de Tore Supra en composite à fibre de carbone est analysé à l'aide d'une étude paramétrique : il doit avoir une température supérieure à 10000 K et une densité électronique supérieure à 10^17 cm^-3 pour optimiser l'application. Une méthode "autocalibr
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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 différent
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Lerche, Ernesto Augusto. "Aquecimento do plasma por ondas de Alfvén no tokamak TCABR." Universidade de São Paulo, 2003. http://www.teses.usp.br/teses/disponiveis/43/43134/tde-17072012-141903/.

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Os resultados de uma extensa campanha experimental, realizada no tokamak TCABR, para se investigar a física das ondas de Alfvén e suas aplicações para o aquecimento de plasmas em tokamaks são apresentados. Ao longo das investigações, foram testados dois tipos de antena, tendo sido observado aquecimento considerável do plasma com ambas, mesmo com valor moderado da potência RF injetada no plasma. Diversas configurações de excitação e diversas condições do plasma foram investigadas, e foi verificado que a escolha correta da helicidade da onda excitada PE crucial para se reduzir o acoplamento para
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Marx, Alain. "Deux étapes majeures pour le développement du code XTOR : parallélisation poussée et géométrie à frontière libre." Thesis, Université Paris-Saclay (ComUE), 2017. http://www.theses.fr/2017SACLX095/document.

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Le code XTOR-2F simule la dynamique 3D des instabilités MHD bi-fluides de plasmas de tokamaks.La première partie de la thèse a été consacrée à la parallélisation du code XTOR-2F. Le code a été parallélisé significativement malgré la représentation pseudo-spectrale pour les deux directions angulaires, la raideur des équations résolues et l’utilisation d’une décomposition LU exacte afin d’inverser le préconditionneur physique. Le temps d’exécution de la version parallèle est un ordre de grandeur plus petit que la version séquentielle sur un maillage basse résolution. L’accélération croît ensuite
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Kumar, Neeraj. "Analysis of turbulent transport in the central part of high-confinement tokamak plasmas." Electronic Thesis or Diss., Aix-Marseille, 2021. http://www.theses.fr/2021AIXM0038.

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Le transport turbulent dans la région centrale est exploré dans un plasma à haut β en mode H hybride du tokamak JET au moyen de simulations linéaires et non-linéaires effectuées avec le code gyrocinétique GKW dans la limite locale. Par rapport aux travaux précédents, l'analyse est étendue à la région ρ > 0.3 et révèle que les Kinetic Ballooning Modes (KBM) y sont linéairement instables, contrairement à la région ρ > 0.3 où les modes Ion Temperature Gradient dominent. Des simulations spécifiques à ρ=0.15 ont permis d'identifier le faible cisaillement magnétique et la haute pression normal
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Livres sur le sujet "Plasmi in tokamak"

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

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

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Kadomt͡sev, B. B. Tokamak plasma: A complex physical system. Institute of Physics Pub., 1992.

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Kloe, J. De. Pellet-plasma interaction in a tokamak. University of Eindhoven, 2000.

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Emaami-Khonsaari, Majid. Modelling and control of plasma position in the STOR-M Tokamak. Plasma Physics Laboratory, University of Saskatchewan, 1990.

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Zhang, Wei. Improved confinement and edge plasma fluctuations in the STOR-M tokamak. University of Saskatchewan, Plasma Physics Laboratory, 1991.

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Zhang, Wei. Plasma auto-biasing during Ohmic H-mode in the STOR-M tokamak. University of Saskatchewan, Plasma Physics Laboratory, 1993.

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Mitarai, Osamu. Alternating current plasma operation in the STOR-M tokamak. Plasma Physics Laboratory, University of Saskatchewan, 1995.

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Jain, K. K. Measurement of plasma rotation velocities with electrode biasing in the Saskatchewan Torus-Modified (STOR-M) Tokamak. Plasma Physics Laboratory, University of Saskatchewan, 1994.

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Matthews, G. F. Measurements of cross-field plasma transport to an object in a tokamak edge plasma. [s.n.], 1989.

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Chapitres de livres sur le sujet "Plasmi in tokamak"

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

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Coccorese, E., and F. Garofalo. "Plasma Position Control." In Tokamak Start-up. Springer US, 1986. http://dx.doi.org/10.1007/978-1-4757-1889-8_22.

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Seidel, U., K. Lackner, G. Lappus, H. Preis, and H. Woyke. "Plasma Position Control in ASDEX Upgrade." In Tokamak Start-up. Springer US, 1986. http://dx.doi.org/10.1007/978-1-4757-1889-8_21.

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Hastie, R. J. "Sawtooth Instability in Tokamak Plasmas." In Plasma Physics. Springer Netherlands, 1998. http://dx.doi.org/10.1007/978-94-011-4758-3_13.

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Ehst, David A., and Kenneth Evans. "Plasma Current Profile Shaping with RF-Current Drive." In Tokamak Start-up. Springer US, 1986. http://dx.doi.org/10.1007/978-1-4757-1889-8_17.

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Ariola, Marco, and Alfredo Pironti. "Plasma Vertical Stabilization." In Magnetic Control of Tokamak Plasmas. Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-29890-0_7.

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Kikuchi, Mitsuru, and Masafumi Azumi. "Plasma Equilibrium in Tokamak." In Frontiers in Fusion Research II. Springer International Publishing, 2015. http://dx.doi.org/10.1007/978-3-319-18905-5_2.

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Sharapov, Sergei. "Equilibrium of Tokamak Plasma." In Energetic Particles in Tokamak Plasmas. CRC Press, 2021. http://dx.doi.org/10.1201/9781351002820-4.

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Rozhansky, Vladimir. "Transport Phenomena in Tokamaks." In Plasma Theory. Springer Nature Switzerland, 2023. http://dx.doi.org/10.1007/978-3-031-44486-9_13.

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Ariola, Marco, and Alfredo Pironti. "Plasma Magnetic Control Problem." In Magnetic Control of Tokamak Plasmas. Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-29890-0_5.

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Actes de conférences sur le sujet "Plasmi in tokamak"

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Gaspar, Jonathan. "Fiber Sensors in Tokamak for Nuclear Fusion." In Bragg Gratings, Photosensitivity, and Poling in Glass Waveguides. Optica Publishing Group, 2024. https://doi.org/10.1364/bgpp.2024.bm4a.1.

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Temperature measurement and heat flux estimation of plasma facing component in Tokamak is mandatory for component protection and physics studies. Fiber Bragg diagnostics have been used in WEST Tokamak up to 800°C and 9 MW/m2. Full-text article not available; see video presentation
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Acres, Jack, and Chris Clements. "Fusion Energy and Future Fusion Power Plants." In ASME Turbo Expo 2024: Turbomachinery Technical Conference and Exposition. American Society of Mechanical Engineers, 2024. http://dx.doi.org/10.1115/gt2024-126730.

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Abstract Fusion energy offers clean, reliable power for future generations and is undeniably part of a fully sustainable energy mix. Fusion combines two light atomic nuclei to form a single heavier one while releasing massive amounts of energy. To fuse atoms requires extremely high temperatures and pressures, in a plasma, to overcome the nuclei’s mutual electrical repulsion — achieving these conditions on earth, which is typically achieved in stars, has a host of challenges. Within a magnetic confinement device (tokamak), plasma is heated using ohmic and a mixture of neutral beam and/or radio-
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Rowan, William L. "Spectroscopic diagnostics and atomic physics experiments in tokamak plasmas." In OSA Annual Meeting. Optica Publishing Group, 1988. http://dx.doi.org/10.1364/oam.1988.thk2.

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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
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Tarkeshian, R., M. Ghoranneviss, K. Salem, et al. "Different Methods for Measuring Plasma Displacement in Tokamaks, Construction & Compensation of Continuous Coils in IR-T1 Tokamak." In PLASMA 2007: International Conference on Research and Applications of Plasmas; 4th German-Polish Conference on Plasma Diagnostics for Fusion and Applications; 6th French-Polish Seminar on Thermal Plasma in Space and Laboratory. AIP, 2008. http://dx.doi.org/10.1063/1.2909116.

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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.

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

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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. Th
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Walker, Michael L., Peter De Vries, Federico Felici, and Eugenio Schuster. "Introduction to Tokamak Plasma Control." In 2020 American Control Conference (ACC). IEEE, 2020. http://dx.doi.org/10.23919/acc45564.2020.9147561.

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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.

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Cui, Zhiqiang. "Energy Calibration of Scintillator Detectors in Different Neutron Diagnostic System on Tokamak." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81190.

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The purpose of tokamak plasma diagnostics is to provide the necessary parameters for device protection, operation, and maintenance. It can also supply parameters for fusion physics research. As one of the main ways to diagnose nuclear fusion plasma, neutron diagnosis focuses on the detection of neutrons, produced by the D-D and D-T fusion reactions, to obtain the physical information of internal plasma. Neutron measurements are widely performed on tokamak to provide the essential information on the neutron yield rate of the plasma that is related to fusion power. Since neutron has no electric
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Diebold, D., N. Hershkowitz, and J. Sorensen. "Phaedrus-T tokamak probe measurements." In International Conference on Plasma Sciences (ICOPS). IEEE, 1993. http://dx.doi.org/10.1109/plasma.1993.593411.

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Rapports d'organisations sur le sujet "Plasmi in tokamak"

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R. Kaita, R. Majeski, R. Doerner, et al. Liquid Lithium Limiter Effects on Tokamak Plasmas and Plasma-Liquid Surface Interactions. Office of Scientific and Technical Information (OSTI), 2002. http://dx.doi.org/10.2172/809848.

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Hernandez, J. V., Z. Lin, W. Horton, A. Vannucci, and S. C. McCool. Neural net prediction of tokamak plasma disruptions. Office of Scientific and Technical Information (OSTI), 1994. http://dx.doi.org/10.2172/10193739.

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Author, Not Given. (High beta tokamak research and plasma theory). Office of Scientific and Technical Information (OSTI), 1990. http://dx.doi.org/10.2172/6156973.

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Medley, S. S., and K. M. Young. Plasma diagnostics for the compact ignition tokamak. Office of Scientific and Technical Information (OSTI), 1988. http://dx.doi.org/10.2172/7231452.

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Furth, H. P. Three novel tokamak plasma regimes in TFTR. Office of Scientific and Technical Information (OSTI), 1985. http://dx.doi.org/10.2172/5109719.

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Singer, C. E., L. P. Ku, and G. Bateman. Plasma transport in a compact ignition tokamak. Office of Scientific and Technical Information (OSTI), 1987. http://dx.doi.org/10.2172/6685807.

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L.E. Zakharov. Stabilization of tokamak plasma by lithium streams. Office of Scientific and Technical Information (OSTI), 2000. http://dx.doi.org/10.2172/759425.

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Ward, D. J., and S. C. Jardin. The effects of plasma deformability on the feedback stabilization of axisymmetric modes in tokamak plasmas. Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/5956297.

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Ward, D. J., and S. C. Jardin. The effects of plasma deformability on the feedback stabilization of axisymmetric modes in tokamak plasmas. Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/10115427.

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Hassanein, A., and I. Konkashbaev. Modeling plasma/material interactions during a tokamak disruption. Office of Scientific and Technical Information (OSTI), 1994. http://dx.doi.org/10.2172/10197014.

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