Journal ArticleDOI
Reconstruction of current profile parameters and plasma shapes in tokamaks
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In this paper, an efficient method is given to reconstruct the current profile parameters, the plasma shape, and a current profile consistent with the magnetohydrodynamic equilibrium constraint from external magnetic measurements, based on a Picard iteration approach.Abstract:
An efficient method is given to reconstruct the current profile parameters, the plasma shape, and a current profile consistent with the magnetohydrodynamic equilibrium constraint from external magnetic measurements, based on a Picard iteration approach which approximately conserves the measurements. Computational efforts are reduced by parametrizing the current profile linearly in terms of a number of physical parameters. Results of detailed comparative calculations and a sensitivity study are described. Illustrative calculations to reconstruct the current profiles and plasma shapes in ohmically and auxiliarily heated Doublet III plasmas are given which show many interesting features of the current profiles.read more
Citations
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Journal ArticleDOI
Optimizations of CFETR steady state H-mode scenario with localized reversed shear enhanced internal transport barrier
TL;DR: In this paper , a localized reversed magnetic shear using radio frequency wave driven current was proposed to achieve the target fusion power and fusion gain for Chinese fusion engineering testing reactor steady state operation.
Journal ArticleDOI
An equilibrium model for helicity injector operation in the helicity injected tokamak (HIT) experiment
A K Martin,T R Jarboe +1 more
TL;DR: In this article, the authors present a model for the helicity injector that treats the open field lines as being in a force-free equilibrium determined by the field line length, the applied injector voltage, and an effective resistivity, which can have both resistive and dynamic components.
Journal ArticleDOI
Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years
Wang Linsen,G. S. Xu,Jin-Yong Hu,Kai Li,Q. P. Yuan,J. B. Liu,Fang Ding,Y. W. Yu,Z. P. Luo,Xu Jiawen,L. Y. Meng,K. Wu,Bin Zhang,M. W. Chen,G. Z. Deng,Xiaogang Liu,Zhongshi Yang,Xufeng Liu,S. C. Liu,R. Ding,Guizhong Zuo,Zhen Sun,Jiefeng Wu,B. Cao,Yange Zhang,Y. Duan,Lei Zhang,X. Y. Qian,A. Li,Longxi Chen,M. N. Jia,H. Si,T. Y. Xia,Y. W. Sun,Y. P. Chen,Q. Li,Guang-Nan Luo,Damao Yao,Bingjia Xiao,Xianzu Gong,Xudong Zhang,Baonian Wan,H. Q. Wang,Houyang Guo,David Eldon,A.M. Garofalo,Y. Liang,S. Xu,C. F. Sang,D. Z. Wang,S. Y. Dai,J. Z. Sun,Hongbin Ding,R. Maingi,K. F. Gan,X. L. Zou,H. L. Du +56 more
Abstract: Active control of the excessively high heat and particle fluxes on the divertor target plates is of fundamental importance to the steady state operation of tokamaks, especially for fusion reactors. A series of experiments have been carried out on this critical issue to relieve the plasma-wall interactions in the experimental advanced superconducting tokamak (EAST) in the last ten years, not only contributing to the long pulse operation of EAST itself, but also providing physical understandings and potential techniques to the next-generation devices like ITER. We have characterized the power deposition pattern and broadened the divertor footprint width effectively. The plasma-wetted area is actively handled using either 3-dimentional edge magnetic topology or advanced plasma equilibrium, thereby peak heat flux around the strike point is reduced. Active control of detachment or radiation compatible with core plasma performance has progressed significantly in very recent years, with a series of active feedback control modules developed and utilized successfully, based on the divertor physics advances with both experiments and simulation. The upper divertor of EAST was upgraded from graphite to active water-cooling ITER-like tungsten in 2014, exhibiting much enhanced heat removal capability. As for the particle exhaust including both fueling and impurity particles, in addition to wall conditioning and impurity source control, the efficiency of particle flux exhaust is optimized by making full use of the divertor closure and the plasma drifts in both scrape-off layer and divertor volume. These heat and particle exhaust advances contribute greatly to a series of EAST achievements like H-mode operation over 100 s. A brief near-term plan on the integrated control of divertor plasma-wall interactions in long-time scale will also be introduced, aiming to provide favorable divertor operation solution for ITER and CFETR.
Journal ArticleDOI
Three-wave interactions between fast-ion driven modes in the National Spherical Torus Experiment
Neal Crocker,E.D. Fredrickson,S. Kubota,W. A. Peebles,R.E. Bell,S.M. Kaye,B.P. LeBlanc,Jonathan Menard +7 more
TL;DR: Crocker et al. as mentioned in this paper showed that the interaction between CAEs and EPMs spatially redistributes the energy of CAEs, concentrating it into a toroidally localized wave packet.
Journal ArticleDOI
Optimized quasi-optical cross-polarization scattering system for the measurement of magnetic turbulence on the DIII-D tokamak.
TL;DR: The goal of the new quasi-optical design is to demonstrate the full spatial and wavenumber capabilities of the CPS diagnostic to address the contribution of magnetic turbulence to anomalous thermal transport in fusion research relevant plasmas.
References
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Journal ArticleDOI
Separation of β̄p and ℓi in tokamaks of non-circular cross-section
TL;DR: In this paper, integral relations for the average poloidal beta p and the plasma internal inductance li are derived from the magnetohydrodynamic (MHD) equilibrium equation for an axisymmetric torus.
Journal ArticleDOI
Computation of ideal MHD equilibria
TL;DR: In this paper, a review of two-and three-dimensional ideal MHD equilibrium codes, with particular emphasis on axisymmetric toroidal calculations, is presented. But this paper is restricted to the case of Tokyoamak geometry.
Journal ArticleDOI
An efficient technique for magnetic analysis of non-circular, high-beta tokamak equilibria
D.W. Swain,G.H. Neilson +1 more
TL;DR: In this paper, a method for determining plasma shape and global properties of high-beta non-circular tokamak equilibria (βp, β, q and li) from magnetic sensor data is described.
Journal ArticleDOI
Magnetic analysis of non-circular cross-section tokamaks
J.L. Luxon,B.B. Brown +1 more
TL;DR: In this paper, the MHD equilibrium configuration for circular and non-circular plasmas from measurements of the magnetic field and flux made outside the discharge was determined using least squares minimization techniques.
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