Yinxian Jie

Plasma density behavior with new graphite limiters in the Hefei Tokamak-7

A new set of actively cooled toroidal double-ring graphite limiters has been developed in the Hefei Tokamak-7 (HT-7) [X. Gao et al., Phys. Plasmas 7, 2933 (2000)] for long pulse operation. The extension of operational region and density behavior with graphite (C) limiters have been studied in this paper. Extended high-density region at the high plasma current low-qa was obtained. The density profile with the C limiter was studied to compare with the previous molybdenum (Mo) limiter. The critical density of multifaceted asymmetric radiation from the edge (MARFE) onset is observed in the region of Zeff1∕2fGW=0.9∼1.2, where fGW=n¯e∕nGW. (Here n¯e is the maximum line average electron density and nGW is the Greenwald density.) Under the same injected power, the critical density of MARFE onset with the new C limiter is much higher than the previous Mo limiter.

Multi-Channel FIR HCN Laser Interferometer on HT-7 Tokamak

A Five-channel far-infrared (FIR) hydrogen cyanide (HCN) laser interferometer was developed to measure plasma electron density profile on the HT-7 superconducting tokamak. The structure of the five-channel FIR laser interferometer is described. The laser source used in the interferometer was a continuous wave glow discharge HCN laser with 3.4 m cavity length and 100 mW power output at 337 μm wavelength. The temporal resolution was 0.1 ms and the detection sensitivity was 1/12 fringe. Preliminary experimental results measured by the interferometer on HT-7 tokamak are reported.

Lower hybrid current drive experiments and improved performance on the HT-7 superconducting tokamak

The feedback control system to control plasma current and position on the HT-7 superconducting tokamak was greatly improved in early 1998. Lower hybrid current drive (LHCD) experiments with the improved control system were performed to sustain long pulse discharges and to improve plasma confinement. Partial non-inductive current drive and full non-inductive current drive for several seconds by means of LHCD were demonstrated. It was observed that plasma confinement could be considerably improved by LHCD. Experimental evidence suggests that this improvement during the LHCD phase could be due to the modification of the current profile in the outer region of the plasma. MHD modes (especially m = 2) seem unstable with such a current profile. The EFIT code was modified for the reconstruction of the magnetic surfaces in HT-7 and a test computation was performed.

Plasma density behavior in the Hefei tokamak-7

The density profiles were measured in the Hefei tokamak-7 (HT-7) [World Survey of Activities in Controlled Fusion Research, Nuclear Fusion Special Supplement (International Atomic Energy Agency, Vienna, 1997), p. 61] ohmic discharges by means of a new multichannel far-infrared (FIR) laser interferometer. The progress on the extension of the HT-7 ohmic discharge operation region was introduced. The experiment results at the density limit, the multifaceted asymmetric radiation from the edge (MARFE) phenomena, the rf (radio frequency) boronization experiments, and the fueling efficiency studies were reported. The plasma physics in the molecular beam injection (MBI), the pellet injection (PI), and the gas puffing (GP) fueling experiments was studied and discussed.

Faraday-effect polarimeter-interferometer system for current density measurement on EAST.

A multichannel far-infrared laser-based POlarimeter-INTerferometer (POINT) system utilizing the three-wave technique is under development for current density and electron density profile measurements in the EAST tokamak. Novel molybdenum retro-reflectors are mounted in the inside wall for the double-pass optical arrangement. A Digital Phase Detector with 250 kHz bandwidth, which will provide real-time Faraday rotation angle and density phase shift output, have been developed for use on the POINT system. Initial calibration indicates the electron line-integrated density resolution is less than 5 × 10(16) m(-2) (∼2°), and the Faraday rotation angle rms phase noise is <0.1°.

High density operation on the HT-7 superconducting tokamak

The structure of the operation region has been studied in the HT-7 superconducting tokamak, and progress on the extension of the HT-7 ohmic discharge operation region is reported. A density corresponding to 1.2 times the Greenwald limit was achieved by RF boronization. The density limit appears to be connected to the impurity content and the edge parameters, so the best results are obtained with very clean plasmas and peaked electron density profiles. The peaking factors of electron density profiles for different current and line averaged densities were observed. The density behaviour and the fuelling efficiency for gas puffing (20-30%), pellet injection (70-80%) and molecular beam injection (40-50%) were studied. The core crash sawteeth and MHD behaviour, which were induced by an injected pellet, were observed and the events correlated with the change of current profile and reversed magnetic shear. The MARFE phenomena on HT-7 are summarized. The best correlation has been found between the total input ohmic power and the product of the edge line averaged density and Zeff. HT-7 could be easily operated in the high density region MARFE-free using RF boronization.

ELMy H-mode confinement and threshold power by low hybrid wave on the EAST tokamak

Stationary type-III ELMy H-mode plasmas were achieved on Experimental Advanced Superconducting Tokamak (EAST) by low hybrid wave in 2010. The threshold power increases with plasma density, and a significant reduction in the H-mode occurs by decreasing the distance between the X-point and the strike point at the outside lower divertor on EAST. A series of statistics for the H-mode confinement such as the dependence of energy confinement time (τE) on plasma density and loss power is experimentally studied in detail.

Electron heating by ion Bernstein wave in the HT-7 tokamak

Ion Bernstein wave (IBW) heating has been investigated in the HT-7 superconducting tokamak. Electron heating mode was concentrated on deuterium plasma with an injecting power to 320?kW. The bulk electron temperature showed a significant rise with a heating factor, ?Te?ne/PRF, up to 9.4?eV?1013?cm-3?kW-1. The direct electron heating via electron Landau damping from IBW has been demonstrated after intensive RF wall conditioning. Both on-axis and off-axis electron heating were obtained. Electron temperature profile was modified by IBW under different plasma conditions. Edge density showed no sharp drop during IBW heating. Plasma density and temperature remained almost unchanged in front of antenna. But edge temperature and density inside of plasma visibly increased and their profiles became steeper. Particle confinement improvement was observed by IBW.

Design of far-infrared polarimeter/interferometer system for EAST tokamak

A double-pass, radially-viewing, multichannel far-infrared (FIR) polarimeter/interferometer system is under development for current density profile and electron density profile measurements in the EAST tokamak. The system utilizes three 432.5 μm CW formic acid FIR lasers pumped by three CO2 lasers. Each of the three FIR lasers can generate high output power of more than 30 mW per cavity. Two lasers, with slight frequency offset ( ~ 1 MHz), will be made collinear with counter-rotating circular polarization in order to determine the Faraday effect by measuring their phase difference. The third laser also frequency offset, will be used as a reference providing local oscillator (LO) power to each mixer so that one can obtain the phase shift caused by the plasma electron density. Novel molybdenic retro-reflectors with shutter protection have been designed and will be mounted on the inner vessel wall in EAST. The retro-reflectors can withstand baking temperature up to 350°C and discharge duration more than 1000 s. Vibrations and path length changes due to thermal expansion will be compensated using a He-Ne interferometer as the second color. VDI planar-diode Integrated Conical Horn Fundamental Mixers optimized for high sensitivity, typical 750 V/W, will be used. Initially a five-chord system will be installed in 2013 and an eleven-chord system will be implemented on the core region of EAST plasmas. MHz frequency response allows system to resolve fast MHD events such as tearing/neoclassical tearing, disruptions and fast-particle modes. Preliminary design will be presented.

Modulated toroidal current suppression of MHD activity on the HT-7 superconducting tokamak

Modulation of the plasma current has been used successfully to suppress MHD activity. This was achieved in discharges near the density limit where large MHD m = 2 tearing modes were suppressed by sufficiently large plasma current oscillations. The modulation of the plasma current must be large enough to move the resonance q = 2 surface outside the island width on a timescale faster than the growth time of the instability. These observations resemble those predicted in a previous study of non-linear effects on the m = 1 mode.