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Articles de revues sur le sujet « Plasmi in tokamak »

Auteur : Grafiati

Publié le 9 mars 2023

Mis à jour le 31 juillet 2025

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1

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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2

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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3

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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7

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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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 (2011): 591–97. http://dx.doi.org/10.1139/p11-038.

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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 emis

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12

Federici, Fabio, Matthew L. Reinke, Bruce Lipschultz, et al. "Design and implementation of a prototype infrared video bolometer (IRVB) in MAST Upgrade." Review of Scientific Instruments 94, no. 3 (2023): 033502. http://dx.doi.org/10.1063/5.0128768.

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A prototype infrared video bolometer (IRVB) was successfully deployed in the Mega Ampere Spherical Tokamak Upgrade (MAST Upgrade or MAST-U), the first deployment of such a diagnostic in a spherical tokamak. The IRVB was designed to study the radiation around the lower x-point, another first in tokamaks, and has the potential to estimate emissivity profiles with spatial resolution beyond what is achievable with resistive bolometry. The system was fully characterized prior to installation on MAST-U, and the results are summarized here. After installation, it was verified that the actual measurem

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13

Dlougach, Eugenia, Alexander Panasenkov, Boris Kuteev, and Arkady Serikov. "Neutral Beam Coupling with Plasma in a Compact Fusion Neutron Source." Applied Sciences 12, no. 17 (2022): 8404. http://dx.doi.org/10.3390/app12178404.

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FNS-ST is a fusion neutron source project based on a spherical tokamak (R/a = 0.5 m/0.3 m) with a steady-state neutron generation of ~1018 n/s. Neutral beam injection (NBI) is supposed to maintain steady-state operation, non-inductive current drive and neutron production in FNS-ST plasma. In a low aspect ratio device, the toroidal magnetic field shape is not optimal for fast ions confinement in plasma, and the toroidal effects are more pronounced compared to the conventional tokamak design (with R/a > 2.5). The neutral beam production and the tokamak plasma response to NBI were efficiently

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Mitrishkin, Yuri V., Valerii I. Kruzhkov, and Pavel S. Korenev. "Methodology of Plasma Shape Reachability Area Estimation in D-Shaped Tokamaks." Mathematics 10, no. 23 (2022): 4605. http://dx.doi.org/10.3390/math10234605.

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This paper suggests and develops a new methodology of estimation for a multivariable reachability region of a plasma separatrix shape on the divertor phase of a plasma discharge in D-shaped tokamaks. The methodology is applied to a spherical Globus-M/M2 tokamak, including the estimation of a controllability region of a vertical unstable plasma position on the basis of the experimental data. An assessment of the controllability region and the reachability region of the plasma is important for the design of tokamak poloidal field coils and the synthesis of a plasma magnetic control system. When

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15

Shukla, Braj Kishore, Jatin Patel, Harshida Patel, Dharmesh Purohit, Hardik Mistry, and K. G. Parmar. "ECRH experiments on Tokamaks SST-1 & Aditya-U and ECRH upgradation plan for SST-1." EPJ Web of Conferences 277 (2023): 02005. http://dx.doi.org/10.1051/epjconf/202327702005.

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A 42GHz-500kW ECRH system [1-6] is used to carry out various experiments related to plasma breakdown and ECR heating on tokamaks SST-1 and Aditya-U. The system has been upgraded with new anode modulator power supply to launch two ECRH pulses to carry out breakdown and heating simultaneously. In SST-1, ECRH system is used routinely for plasma breakdown at fundamental harmonic, approximately 150kW power is launched for 70ms to 150ms duration and consistent plasma start-up is achieved in SST-1. In the recent experiments, second EC pulse is also launched at the plasma flat-top to heat the plasma,

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16

Bishop, Chris M., Paul S. Haynes, Mike E. U. Smith, Tom N. Todd, and David L. Trotman. "Real-Time Control of a Tokamak Plasma Using Neural Networks." Neural Computation 7, no. 1 (1995): 206–17. http://dx.doi.org/10.1162/neco.1995.7.1.206.

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In this paper we present results from the first use of neural networks for real-time control of the high-temperature plasma in a tokamak fusion experiment. The tokamak is currently the principal experimental device for research into the magnetic confinement approach to controlled fusion. In an effort to improve the energy confinement properties of the high-temperature plasma inside tokamaks, recent experiments have focused on the use of noncircular cross-sectional plasma shapes. However, the accurate generation of such plasmas represents a demanding problem involving simultaneous control of se

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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 (2023): 042301. http://dx.doi.org/10.1063/5.0140097.

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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 para

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18

Segura, Javier Lopez, Nicolas Urgoiti Moinot, and Enzo Lazzaro. "Simulation of a high proton temperature plasma toroidal magnetic trap to be used in proton-11B fusion." Journal of Technological and Space Plasmas 1, no. 1 (2019): 12–20. http://dx.doi.org/10.31281/jtsp.v1i1.6.

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Several tokamaks structures containing 500 keV protons to be used in P-B11 fusion were simulated. In order to find the optimal confinement configuration, the simulation was helped by an evolutionary algorithm running 145,000 simulations. The results are presented in this paper. According to the simulations the tokamak structure can be operated to reach ignition using the proposed plasma mode that includes the use of low electron temperature and high thermal energy protons in the plasma (500 keV).

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19

Sadakov, Sergey, Fabio Villone, Guglielmo Rubinacci, and Salvatore Ventre. "Simple Parametric Model for Calculation of Lateral Electromagnetic Loads in Tokamaks at Asymmetric Vertical Displacement Events (AVDE)." Plasma 5, no. 3 (2022): 306–23. http://dx.doi.org/10.3390/plasma5030024.

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This paper describes a family of relatively simple numerical models for calculation of asymmetric electromagnetic (EM) loads at all tokamak structures and coils at asymmetric vertical plasma displacement events (AVDE). Unlike currently known AVDE studies concentrated on plasma physics, these models have a practical purpose to calculate detailed time-dependent patterns of AVDE-induced EM loads everywhere in the tokamak. They are built to intrinsically assure good-enough EM load balance (opposite net forces and torques for the Vacuum Vessel and the Magnets with zero total for the entire tokamak)

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SAADAT, SH, M. SALEM, M. GHORANNEVISS, and P. KHORSHID. "Stochastic modeling of plasma mode forecasting in tokamak." Journal of Plasma Physics 78, no. 2 (2011): 99–104. http://dx.doi.org/10.1017/s0022377811000456.

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AbstractThe structure of magnetohydrodynamic (MHD) modes has always been an interesting study in tokamaks. The mode number of tokamak plasma is the most important parameter, which plays a vital role in MHD instabilities. If it could be predicted, then the time of exerting external fields, such as feedback fields and Resonance Helical Field, could be obtained. Autoregressive Integrated Moving Average (ARIMA) and Seasonal Autoregressive Integrated Moving Average are useful models to predict stochastic processes. In this paper, we suggest using ARIMA model to forecast mode number. The ARIMA model

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O’Shea, Finn H., Semin Joung, David R. Smith, and Ryan Coffee. "Automatic identification of edge localized modes in the DIII-D tokamak." APL Machine Learning 1, no. 2 (2023): 026102. http://dx.doi.org/10.1063/5.0134001.

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Fusion power production in tokamaks uses discharge configurations that risk producing strong type I edge localized modes. The largest of these modes will likely increase impurities in the plasma and potentially damage plasma facing components, such as the protective heat and particle divertor. Machine learning-based prediction and control may provide for the automatic detection and mitigation of these damaging modes before they grow too large to suppress. To that end, large labeled datasets are required for the supervised training of machine learning models. We present an algorithm that achiev

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Воронин, А. В., В. Ю. Горяинов, В. В. Забродский та ін. "Измерение электронной температуры плазмы фольговым рентгеновским спектрометром, установленным на токамаках ТУМАН-3М и Глобус-М2". Журнал технической физики 91, № 12 (2021): 1922. http://dx.doi.org/10.21883/jtf.2021.12.51758.188-21.

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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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Fenstermacher, M. E., L. R. Baylor, E. de la Luna, et al. "Progress in pedestal and edge physics: Chapter 3 of the special issue: on the path to tokamak burning plasma operation." Nuclear Fusion 65, no. 5 (2025): 053001. https://doi.org/10.1088/1741-4326/adb1f3.

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Abstract This paper describes the extensive progress that has been made in the understanding of tokamak pedestal physics since the 2007 publication of ‘Progress in the ITER Physics Basis’ (Ikeda 2007 Nucl. Fusion 47 E01–S500). It serves as Chapter 3 of the 2025 Nuclear Fusion Special Issue titled ‘On the Path to Tokamak Burning Plasma Operation’ (Campbell et al 2025 Nucl. Fusion). This review was compiled by the pedestal and edge physics (PEP) community affiliated with the International Tokamak Physics Activity organization. It attempts to collect in one place citations to the majority of publ

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Firpo, Marie-Christine. "Cross-Analysis of Magnetic and Current Density Field Topologies in a Quiescent High Confinement Mode Tokamak Discharge." Foundations 5, no. 2 (2025): 22. https://doi.org/10.3390/foundations5020022.

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In axisymmetric fusion devices like tokamaks, the winding of the magnetic field is characterized by its safety profile q=qB. Similarly, the winding of the current density field is characterized by qJ. Currently, the relationship between qB and qJ profiles and their effect on tokamak plasma confinement properties remains unexplored, as the qJ profile is neither computed nor considered. This study presents a reconstruction of the current density winding profile from experimental data in the quiescent H-mode. The topology analysis derived from (qB,qJ) was carried out using Hamada coordinates. It

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Riazifar, MR, S. Meshkani, H. Mahdavy - Moghaddam, and M. Ghoranneviss. "The toroidal magnetic field correction to reduce instabilities through current rise up phase in IR-T1 tokamak." Physics & Astronomy International Journal 3, no. 6 (2019): 251–55. http://dx.doi.org/10.15406/paij.2019.03.00190.

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Keeping the plasma stable throughout the plasma discharge is now considered a massive undertaking in today’s Tokamaks. In this study, the part that the current rise up phase plays in the total plasma stability was investigated, toroidal magnetic field on IR-T1 Tokamak was altered to reach the least amount of instabilities in current rise up phase. In this experiment, in order to provide rigorous and details affirmation, SVD, FFT and hard X-ray analyses were employed. The results state that with toroidal magnetic field increment to a specific amount (3.10 KV), the plasma experiences the least a

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Menard, J. E., B. A. Grierson, T. Brown, et al. "Fusion pilot plant performance and the role of a sustained high power density tokamak." Nuclear Fusion 62, no. 3 (2022): 036026. http://dx.doi.org/10.1088/1741-4326/ac49aa.

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Abstract Recent U.S. fusion development strategy reports all recommend that the U.S. should pursue innovative science and technology to enable construction of a fusion pilot plant (FPP) that produces net electricity from fusion at low capital cost. Compact tokamaks have been proposed as a means of potentially reducing the capital cost of a FPP. However, compact steady-state tokamak FPPs face the challenge of integrating a high fraction of self-driven current with high core confinement, plasma pressure, and high divertor parallel heat flux. This integration is sufficiently challenging that a de

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BATISHCHEV, O. V., M. M. SHOUCRI, A. A. BATISHCHEVA, and I. P. SHKAROFSKY. "Fully kinetic simulation of coupled plasma and neutral particles in scrape-off layer plasmas of fusion devices." Journal of Plasma Physics 61, no. 2 (1999): 347–64. http://dx.doi.org/10.1017/s0022377898007375.

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Fluid descriptions of plasmas, which are usually applied to a collisional plasma, can only be justified for very small Coulomb Knudsen numbers. However, the scrape-off layer (SOL) plasmas of experimental magnetic confinement fusion devices tend to have operational regimes characterized by a Coulomb Knudsen number around 0.1. In interesting detached regimes of an SOL plasma in a tokamak, when the plasma detaches from the limiters or divertors, this number may increase along with the local plasma gradients. Plasma gradients are also known to increase (and thus drive non-local effects) in inertia

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Konkov, A. E., P. S. Korenev, Yu V. Mitrishkin, I. M. Balachenkov, and E. O. Kiselev. "Real-Time Plasma Magnetic Control System with Equilibrium Reconstruction Algorithm in the Feedback for the Globus-M2 Tokamak." Физика плазмы 49, no. 12 (2023): 1348–56. http://dx.doi.org/10.31857/s0367292123600760.

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To control the plasma shape during a tokamak discharge, it is necessary to calculate the plasmashape in real-time. The rate requirements for the shape calculations are especially high for tokamaks with asmall radius, such as Globus-M2 (St. Petersburg, Russia). A real-time magnetic plasma control system forthe Globus-M2 tokamak with flux and current distribution identification (FCDI) algorithm for the plasmaequilibrium reconstruction in feedback is presented. The control system contains discrete one-dimensionaland matrix proportional-integral-derivative controllers synthesized by the matrix ine

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Binderbauer, M. W., and N. Rostoker. "Turbulent transport in magnetic confinement: how to avoid it." Journal of Plasma Physics 56, no. 3 (1996): 451–65. http://dx.doi.org/10.1017/s0022377800019413.

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From recent tokamak research, there is considerable experimental evidence that superthermal ions slow down and diffuse classically in the presence of turbulent fluctuations that cause anomalous transport of thermal ions. Further more, research on field-reversed configurations at Los Alamos is consistent with the view that kinetic effects suppress instability growth when the ratio of plasma radius to ion orbital radius is small; turbulence is enhanced and confinement degrades when this ratio increases. Motivated by these experiments, we consider a plasma consisting of large-orbit non-adiabatic

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Melnikov, Alexander. "Evolution of Heavy Ion Beam Probing from the Origins to Study of Symmetric Structures in Fusion Plasmas." Symmetry 13, no. 8 (2021): 1367. http://dx.doi.org/10.3390/sym13081367.

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The overview discusses development of the unique fusion plasma diagnostics—Heavy Ion Beam Probing (HIBP) in application to toroidal magnetic plasma devices. The basis of the HIBP measurements of the plasma electric potential and processing of experimental data are considered. Diagnostic systems for probing plasma in tokamaks TM-4, TJ-1, TUMAN-3M and T-10, stellarators WEGA, TJ-II and Uragan-2M are presented. Promising results of the HIBP projects for various existing modern machines, such as TCV, TCABR, MAST, COMPASS, GLOBUS-M2, T-15 MD and W7-X and the international fusion tokamak reactor ITE

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Sadakov, Sergey. "A Few Points of the Engineering Logic Discussed in ITER EDA on Evaluation of Halo- and AVDE-Induced Loads in Tokamaks." Plasma 4, no. 3 (2021): 366–75. http://dx.doi.org/10.3390/plasma4030025.

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All tokamaks are designed to withstand a certain number of energetic electromagnetic (EM) transients caused by uncontrolled terminations of plasma pulses, including symmetric and asymmetric plasma vertical displacement events: VDEs and AVDEs. These events generate significant pulsed EM loads in all conductive components and coils. Axially symmetric transient EM loads induced by VDEs without Halo current have been calculated well since the 1980s; however, Halo-related EM load components and lateral loads associated with AVDEs still cause discussions. The author worked on fast plasma and EM tran

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Donnelly, I. J., and B. E. Clancy. "Kinetic theory of Alfvén waves in plasmas with force-free currents." Journal of Plasma Physics 45, no. 2 (1991): 213–28. http://dx.doi.org/10.1017/s0022377800015658.

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Equations are derived for the kinetic-theory analysis of small-amplitude Alfvén waves in cylindrical plasmas carrying force-free currents. The equations, which include ion Larmor-radius effects to second order, are applicable to reversed-field pinches as well as to tokamaks. Fourier mode amplitudes are derived for model antennas with radial current feeds, and a quantitative analysis is made of the antenna resistance and the wave density fields in a small tokamak during Alfvén-wave heating. The effect of the plasma current on the wave thermal energy flux is discussed.

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Ravish Sharma, Rudraksh Tiwari, Kash Dev Sharma, Himmat Singh Mahor, and Khusvant Singh. "Evaluating the Viability and Optimization of Plasma Pilot Plants." International Research Journal on Advanced Engineering and Management (IRJAEM) 2, no. 09 (2024): 2903–10. http://dx.doi.org/10.47392/irjaem.2024.0428.

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Nuclear fusion stands as a promising avenue for achieving a sustainable and abundant energy source. Central to this endeavor is the development of effective pilot plants capable of demonstrating the feasibility of fusion power on a commercial scale. This paper provides a comprehensive evaluation of three leading magnetic confinement fusion configurations: the Advanced Tokamak (AT), Spherical Tokamak (ST), and Compact Stellarator (CS).The Tokamak, characterized by its toroidal shape and strong magnetic fields, has been the most researched and developed fusion device. The analysis focuses on the

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Montani, Giovanni, Nakia Carlevaro, and Brunello Tirozzi. "On the Turbulent Behavior of a Magnetically Confined Plasma near the X-Point." Fluids 7, no. 5 (2022): 157. http://dx.doi.org/10.3390/fluids7050157.

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We construct a model for the turbulence near the X-point of a Tokamak device and, under suitable assumptions, we arrive to a closed equation for the electric field potential fluctuations. The analytical and numerical analysis is focused on a reduced two-dimensional formulation of the dynamics, which allows a direct mapping to the incompressible Navier-Stokes equation. The main merit of this study is to outline how the turbulence near the X-point, in correspondence to typical operation conditions of medium and large size Tokamaks, is dominated by the enstrophy cascade from large to smaller spat

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Yashin, Alexander, Alexander Belokurov, Leonid Askinazi, Alexander Petrov, and Anna Ponomarenko. "The Influence of Fast Particles on Plasma Rotation in the TUMAN-3M Tokamak." Atoms 10, no. 4 (2022): 106. http://dx.doi.org/10.3390/atoms10040106.

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In most present-day tokamaks, the majority of the heating power comes from sources such as neutral-beam injection (NBI) and other types of auxiliary heating which allow for the transfer of energy to the plasma by a small population of externally introduced fast particles. The behavior of the fast ions is important for the overall plasma dynamics, and understanding their influence is vital for the success of any future magnetic confinement devices. In the TUMAN-3M tokamak, it has been noted that the loss of fast particles during NBI can lead to dramatic changes in the rotation velocity profiles

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Zhang, W., Z. W. Ma, H. W. Zhang, W. J. Chen, and X. Wang. "Influence of aspect ratio, plasma viscosity, and radial position of the resonant surfaces on the plasmoid formation in the low resistivity plasma in Tokamak." Nuclear Fusion 62, no. 3 (2022): 036007. http://dx.doi.org/10.1088/1741-4326/ac46f8.

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Abstract In the present paper, we systematically investigate the nonlinear evolution of the resistive kink mode in the low resistivity plasma in Tokamak geometry. We find that the aspect ratio of the initial equilibrium can significantly influence the critical resistivity for plasmoid formation. With the aspect ratio of 3/1, the critical resistivity can be one magnitude larger than that in cylindrical geometry due to the strong mode–mode coupling. We also find that the critical resistivity for plasmoid formation η crit decreases with increasing plasma viscosity in the moderately low resistivit

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Ondac, Peter, Jan Horacek, Jakub Seidl, et al. "COMPARISON BETWEEN 2D TURBULENCE MODEL ESEL AND EXPERIMENTAL DATA FROM AUG AND COMPASS TOKAMAKS." Acta Polytechnica 55, no. 2 (2015): 128–35. http://dx.doi.org/10.14311/ap.2015.55.0128.

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<p style="text-indent: 0px; margin: 0px;">In this article we have used the 2D fluid turbulence numerical model, ESEL, to simulate turbulent transport in edge tokamak plasma. Basic plasma parameters from the ASDEX Upgrade and COMPASS tokamaks are used as input for the model, and the output is compared with experimental observations obtained by reciprocating probe measurements from the two machines. Agreements were found in radial profiles of mean plasma potential and temperature, and in a level of density fluctuations. Disagreements, however,

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Буланин, В. В., В. К. Гусев, Г. С. Курскиев та ін. "Применение метода многочастотного допплеровского обратного рассеяния для исследования альфвеновских мод в токамаке". Письма в журнал технической физики 45, № 21 (2019): 44. http://dx.doi.org/10.21883/pjtf.2019.21.48474.17982.

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The results of the study of toroidal Alfven modes (TAE) using the multi-frequency Doppler backscattering (DBS) in the Globus-M tokamak are presented. The article is focused on the presentation of the Alfven mode registration method for multichannel probing. The possible causes of the observed oscillations of the poloidal plasma rotation velocity at the Alfvén oscillation frequencies are discussed in detail. The data on the spatial distribution of Alfvén modes revealed by multi-frequency DBS are given. The recommendations for the further development of the DBS with the aim of a more detailed st

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Sadowski, Marek J. "Selected methods of electron-and ion-diagnostics in tokamak scrape-off-layer." Nukleonika 60, no. 2 (2015): 199–206. http://dx.doi.org/10.1515/nuka-2015-0039.

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Abstract This invited paper considers reasons why exact measurements of fast electron and ion losses in tokamaks, and particularly i n a scrape-off-layer and near a divertor region, are necessary in order to master nuclear fusion energy production. Attention is also paid to direct measurements of escaping fusion products from D-D and D-T reactions, and in particular of fast alphas which might be used for plasma heating. The second part describes the generation of so-called runaway and ripple-born electrons which might induce high energy losses and cause severe damages of internal walls in fusi

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Escande, D. F., F. Sattin, and P. Zanca. "Plasma-wall self-organization in magnetic fusion." Nuclear Fusion 62, no. 2 (2021): 026001. http://dx.doi.org/10.1088/1741-4326/ac3c87.

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Abstract This paper introduces the concept of plasma-wall self-organization (PWSO) in magnetic fusion. The basic idea is the existence of a time delay in the feedback loop relating radiation and impurity production on divertor plates. Both a zero and a one-dimensional description of PWSO are provided. They lead to an iterative equation whose equilibrium fixed point is unstable above some threshold. This threshold corresponds to a radiative density limit, which can be reached for a ratio of total radiated power to total input power as low as 1/2. When detachment develops and physical sputtering

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Mitrishkin, Yuri V., Pavel S. Korenev, Artem E. Konkov, Valerii I. Kruzhkov, and Nicolai E. Ovsiannikov. "New Identification Approach and Methods for Plasma Equilibrium Reconstruction in D-Shaped Tokamaks." Mathematics 10, no. 1 (2021): 40. http://dx.doi.org/10.3390/math10010040.

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The paper deals with the identification of plasma equilibrium reconstruction in D-shaped tokamaks on the base of plasma external magnetic measurements. The methods of such identification are directed to increase their speed of response when plasma discharges are relatively short, like in the spherical Globus-M2 tokamak (Ioffe Inst., St. Petersburg, Russia). The new approach is first to apply to the plasma discharges data the off-line equilibrium reconstruction algorithm based on the Picard iterations, and obtain the gaps between the plasma boundary and the first wall, and the second is to appl

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Dong, Qilong, Jie Zhang, Tao Lan, et al. "Effects of vacuum magnetic field region on the compact torus trajectory in a tokamak plasma." Plasma Science and Technology, March 21, 2024. http://dx.doi.org/10.1088/2058-6272/ad36aa.

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Abstract The trajectory of the compact torus (CT) within a tokamak discharge is crucial to fueling. In this study, we developed a penetration model with a vacuum magnetic field region to accurately determine CT trajectories in tokamak discharges. This model was used to calculate the trajectory and penetration parameters of CT injections by applying both perpendicular and tangential injection schemes in both HL-2A and ITER tokamaks. For perpendicular injection along the tokamak's major radius direction from the outboard, CTs with the same injection parameters exhibited an 0.08 reduction in rela

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Hecko, Jan, Michael Komm, Miroslav Šos, et al. "Experimental evidence of very short power decay lengths in H-mode discharges in the COMPASS tokamak." Plasma Physics and Controlled Fusion, November 2, 2023. http://dx.doi.org/10.1088/1361-6587/ad08f0.

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Abstract Analysis of the heat ﬂuxes in the scrape-oﬀ layer (SOL) plasma is important for prediction of divertor tile heat loads in future reactor-sized tokamak machines. Typically, the radial heat ﬂux proﬁle can be accurately characterized by the decay length parameter λq. The predictions are then based on the dependence of λq on plasma and machine parameters. In the recent years, several empirical scaling models were derived from a collective database of decay lengths observed in several large tokamaks as well as two spherical tokamaks. Most recently, a report from the TCV tokamak showed a de

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Wang, Weixing, Min-Gu Yoo, Edward A. Startsev, Stanley M. Kaye, S. Ethier, and Jin Chen. "Plasma self-driven current in tokamaks with magnetic islands." Nuclear Fusion, November 6, 2024. http://dx.doi.org/10.1088/1741-4326/ad8f45.

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Abstract Magnetic island perturbations may cause a reduction in plasma self-driven current that is needed for tokamak operation.&#xD; A novel effect on tokamak self-driven current revealed by global gyrokinetic simulations is due to magnetic-island-induced&#xD;3D electric potential structures, which have the same dominant mode numbers as that of the magnetic island,&#xD;whereas centered at both the inner and outer edge of the island. The non-resonant potential islands&#xD;are shown to drive a current through an efficient nonlinear parallel acceleration of electrons.&#xD;In

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Pamela. "Extended Full-MHD Simulation of Non-linearInstabilities in Tokamak Plasmas." June 15, 2020. https://doi.org/10.5281/zenodo.3971940.

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Non-linear MHD simulations play an essential role in active research and understanding of tokamakplasmas for the realisation of a fusion power plant. The development of MHD codes like JOREK isa key aspect of this research effort. In this paper, we present a fully operational full-MHD modelin JOREK, a significant advancement from the reduced-MHD model used for previous studies.The model is presented in detail, and benchmarks are performed using both linear and non-linearsimulations, including comparisons between the new full-MHD model of JOREK and the previ-ously extensively studied reduced-MHD

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V., Weinzettl, Imrisek M., Havlicek J., et al. "On Use of Semiconductor Detector Arrays on COMPASS Tokamak." November 20, 2012. https://doi.org/10.5281/zenodo.1060521.

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Semiconductor detector arrays are widely used in high-temperature plasma diagnostics. They have a fast response, which allows observation of many processes and instabilities in tokamaks. In this paper, there are reviewed several diagnostics based on semiconductor arrays as cameras, AXUV photodiodes (referred often as fast "bolometers") and detectors of both soft X-rays and visible light installed on the COMPASS tokamak recently. Fresh results from both spring and summer campaigns in 2012 are introduced. Examples of the utilization of the detectors are shown on the plasma shape determination, f

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Yang, SeongMoo, Jong-Kyu Park, YoungMu Jeon, et al. "Tailoring tokamak error fields to control plasma instabilities and transport." Nature Communications 15, no. 1 (2024). http://dx.doi.org/10.1038/s41467-024-45454-1.

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AbstractA tokamak relies on the axisymmetric magnetic fields to confine fusion plasmas and aims to deliver sustainable and clean energy. However, misalignments arise inevitably in the tokamak construction, leading to small asymmetries in the magnetic field known as error fields (EFs). The EFs have been a major concern in the tokamak approaches because small EFs, even less than 0.1%, can drive a plasma disruption. Meanwhile, the EFs in the tokamak can be favorably used for controlling plasma instabilities, such as edge-localized modes (ELMs). Here we show an optimization that tailors the EFs to

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Parisi, Jason, W. Guttenfelder, Oak Nelson, et al. "Kinetic-ballooning-limited pedestals in spherical tokamak plasmas." Nuclear Fusion, April 3, 2024. http://dx.doi.org/10.1088/1741-4326/ad39fb.

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Abstract A theoretical model is presented that for the first time matches experimental measurements of the pedestal width-height Diallo scaling in the low-aspect-ratio high-$\beta$ tokamak NSTX. Combining linear gyrokinetics with self-consistent pedestal equilibrium variation, kinetic-ballooning, rather than ideal-ballooning plasma instability, is shown to limit achievable confinement in spherical tokamak pedestals. Simulations are used to find the novel Gyrokinetic Critical Pedestal constraint, which determines the steepest pressure profile a pedestal can sustain subject to gyrokinetic instab

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Mazzucato, Ernesto. "A Spitzer Model-C Stellarator fusion reactor." AIP Advances 14, no. 4 (2024). http://dx.doi.org/10.1063/5.0203015.

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Tokamaks are affected by two serious problems. The first problem is the radiation damage to the internal reactor structures by energetic neutrons carrying 80% of the total fusion energy that are generated by the deuterium–tritium fusion cycle that tokamaks are planning to use. The second problem is a loss of plasma control because of the onset of instabilities, causing the sudden shutdown of the tokamak itself. Certainly, no electric utility knowing about these disruptive events would dare to use a tokamak reactor for powering the turbines of its power plant! This paper describes a new fusion

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Barukčić, Ilija. "Exploring the Use of Tokamaks for Rocket Propulsion: A Novel Approach to Space Travel." Causation 21, no. 1 (2025). https://doi.org/10.5281/zenodo.14758159.

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<strong>Background:</strong>The development of efficient propulsion systems for space exploration remains a significant challenge,particularly for deep space missions. Tokamaks, known for their ability to generate high-energyplasma and sustain controlled fusion reactions, could theoretically provide the necessary thrust forinterplanetary and interstellar travel. This paper explores the concept of utilizing Tokamak reactors,typically designed for nuclear fusion research, as a propulsion system for spacecraft.<strong>Material and methods:</strong>The methodology involves analyzing the principles

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