2007
DOI: 10.1088/0029-5515/47/10/s05
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Development in the DIII-D tokamak of advanced operating scenarios and associated control techniques for ITER

Abstract: Abstract. Significant progress has been made on the DIII-D tokamak in the capability to control key plasma features and using such control to expand the operational limits of stationary and steady-state tokamak operation. Recent experiments have demonstrated the capability to suppress the key plasma instabilities of concern for ITER, including edge localized modes, neoclassical tearing modes, and resistive wall modes. In addition, the ability to regulate the rotation and current density profiles through feedba… Show more

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Cited by 33 publications
(29 citation statements)
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“…In these high performance plasmas, the pressure, rotation and current profiles play the critical roles in determining transport [1][2][3] and MHD stability [4][5][6][7] interacting with each other [8]. Therefore, the development of the real-time control system [9][10][11][12][13][14] for these parameters is essentially important in sustaining high performance plasmas. For example, it is generally accepted that the control of pressure and current profiles is useful to stabilize the neoclassical tearing mode (NTM) [4] and the edge localized mode (ELM) [15].…”
Section: Introductionmentioning
confidence: 99%
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“…In these high performance plasmas, the pressure, rotation and current profiles play the critical roles in determining transport [1][2][3] and MHD stability [4][5][6][7] interacting with each other [8]. Therefore, the development of the real-time control system [9][10][11][12][13][14] for these parameters is essentially important in sustaining high performance plasmas. For example, it is generally accepted that the control of pressure and current profiles is useful to stabilize the neoclassical tearing mode (NTM) [4] and the edge localized mode (ELM) [15].…”
Section: Introductionmentioning
confidence: 99%
“…However, because the response of current profile is about one order magnitude longer than that of pressure profile, the control of pressure is more useful for fast MHD feedback control. It is also reported that the toroidal rotation velocity (V t ) plays an important role for the NTM stabilization [13] and ELM behavior [16][17][18]. And V t profile can also be changed on a time scale comparable to the change in the pressure profile.…”
Section: Introductionmentioning
confidence: 99%
“…The need for time-frequency (t-f) analysis [1,2] in nuclear fusion research, when processing data coming from dedicated high-temperature plasma diagnostics, has always been strongly felt [3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18][19][20]. Indeed, fusion plasmas are an incredibly rich source of physical phenomenology whose spectral content changes in time, as often seen in plasma turbulence and MHD instabilities.…”
Section: Introductionmentioning
confidence: 99%
“…This gives rise to signals exhibiting, in general, time-varying spectra that can range from a few to hundreds of kHz, and can change as fast as in some hundredths of ms. The basic, almost universal approach to process and analyse such signals has been the short-time Fourier transform (STFT), from which the spectrogram (SPEC) has emerged as the ancestor of modern t-f distributions [1][2][3][4][5][6][7][8][9][10][11]13,[16][17][18][19][20]. Sometimes, more sophisticated versions of time-local Fourier spectra, like wavelets [12,17], or alternative yet equivalent techniques, such as complex demodulation [14], have been used, but always within a framework that can be called the STFT paradigm.…”
Section: Introductionmentioning
confidence: 99%
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