Results 21 to 30 of about 91,764 (228)
Initial analytical theory of plasma disruption and experimental evidence
Scientific Reports, 2023 It is a great physical challenge to achieve controlled nuclear fusion in magnetic confinement tokamak and solve energy shortage problem for decades. In tokamak plasma, large-scale plasma instability called disruption will halt power production of reactor
Huibin Qiu +13 more
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Compact steady-state tokamak performance dependence on magnet and core physics limits
Philosophical Transactions of the Royal Society A, 2019 Compact tokamak fusion reactors using advanced high-temperature superconducting magnets for the toroidal field coils have received considerable recent attention due to the promise of more compact devices and more economical fusion energy development ...
J. Menard
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Towards a compact spherical tokamak fusion pilot plant
Philosophical Transactions of the Royal Society A, 2019 The question of size of a tokamak fusion reactor is central to current fusion research especially with the large device, ITER, under construction and even larger DEMO reactors under initial engineering design.
A. Costley
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A model of multi-pass absorption of external EC radiation at initial stage of discharge in ITER
EPJ Web of Conferences, 2015 A model is developed for multi-pass absorption of external electron cyclotron radiation (ECR) in tokamaks, which is used at initial stage of discharge to overcome the impurity radiation barrier (burn-through). Model is based on a semi-analytical solution
Minashin P.V. +3 more
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Development of a plasma shape and position display system for damavand tokamak control room [PDF]
مجله علوم و فنون هستهای, 2023 Determining the magnetic field profile is very important for studying flux surfaces, elongation, plasma boundaries, and real-time control in tokamaks. In this research, a system for calculating and displaying the shape, position, and boundary of plasma ...
D. Iraji +3 more
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Modelling the capacitance of the elongated plasma in tokamak
Scientific Reports, 2023 The capacitance model suitable for the non-circular cross-section plasma is studied based on the capacitance model of the circular cross-section plasma.
Pengcheng Miao +5 more
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Fusion Technology, 2000 An overview is given of recent results obtained in tokamak devices. We introduce basic confinement scenarios as L-mode, H-mode and plasmas with an internal transport barrier and discuss methods for profile control. Important findings in DT- experiments at JET as α- particle heating are described.
Unterberg, B., Samm, U.
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Plasma Magnetic Control in Tokamak Devices
, 2019 In tokamak experimental reactors, the magnetic control system is one of the main plasma control systems that is required, together with the density control, since the very beginning, even before first operations.
G. Tommasi
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On The Confinement of a Tokamak Plasma [PDF]
SIAM Journal on Mathematical Analysis, 2010 The goal of this paper is to understand from a mathematical point of view the magnetic confinement of plasmas for fusion. Following Fr nod and Sonnendr cker \cite{FS2}, we first use two-scale convergence tools to derive a gyrokinetic system for a plasma submitted to a large magnetic field with a slowly spatially varying intensity.
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EPJ Web of Conferences, 2015 A method of spectroscopic diagnostics of the average perpendicular-to-magnetic-field momentum of the superthermal component of the electron velocity distribution (EVD), based on the high-number-harmonic electron cyclotron (EC) radiation, is suggested for
Minashin P.V., Kukushkin A.B.
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