Main research experiences:

·        MagnetoHydroDynamics (MHD) Instabilities in magnetized plasmas

1) Edge Localized Mode control with external perturbation fields

Type-I edge localized modes (ELMs) have been mitigated at the JET tokamak using a static external n = 1 perturbation field generated by four error field correction coils (EFCCs) located far from the plasma. During the application of the n = 1 field the ELM frequency increased by a factor of 4 and the amplitude of the Da signal decreased. The normalised energy loss per ELM DW/W dropped to values below 2%. Furthermore, the temperature at the outer limiters was also reduced. Transport analyses shows no or only a moderate (up to 20%) degradation of energy confinement time during the ELM mitigation phase. [ref. “Active control of type-I edge localized modes with n = 1 perturbation fields on JET”, Y. Liang, et al., Phys. Rev. Lett. 98, 265004 (2007)]

2) Error field and tearing mode physics

The dynamic ergodic divertor (DED) on the TEXTOR tokamak allows for the creation of static and rotating helical magnetic perturbation fields. In the 3/1 configuration the strong m/n = 2/1 sideband excites a locked 2/1 tearing mode above a critical perturbation field strength. The mode onset threshold depends strongly on the plasma fluid rotation with respect to the mode. Rotation in plasma current direction destabilizes the mode in a certain range of rotation frequencies, whereas counter-rotation has a stabilizing influence. The threshold shows a minimum when the frequency of the external perturbation equals the MHD frequency of the mode. [ref. “Dependence of the threshold for perturbation field generated m/n = 2/1 tearing modes on the plasma fluid rotation”, H.R. Koslowski, Y. Liang, et al., Nucl. Fusion 46 No 8 (August 2006) L1-L5]

 3) Mode locking and unlocking

Experimental studies of the locking and unlocking of the m/n = 2/1 tearing modes using beta and plasma rotation scans have been performed on TEXTOR. A large 2=1 island (width ~ 8 cm; ~ 17% of plasma minor radius) near half plasma radius is seeded by application of a static (dc) or rotating (ac) perturbation field with the Dynamic Ergodic Divertor (DED) in 3/1 configuration on TEXTOR. The 2/1 island is phase locked to the external perturbation field, i.e. it has zero frequency in dc case. The sawteeth are found to become stabilized after the 2/1 island has been excited. Stabilizing of the 2/1 tearing mode by increasing of beta has been observed in low beta plasmas. A significant influence of anisotropic pressure induced by tangential neutral beam injection (NBI) on the locking of the 2/1 tearing modes has been observed. In the dc case, the island stays locked for a few hundred ms after switch off of the DED, starting to spin up after co-NBI (PNBI > 300kW) is switched off. In the 1 kHz case, the frequency of the 2/1 islands exponential decay towards zero after switch off of the DED, and stay locked up to switch off of the co-NBI. The persistent locking of the 2/1 island even without the external perturbation field can be attributed to coupling with an m/n = 1/1 internal kink mode enhanced by a large anisotropic pressure in the NBI heated plasmas. [ref. “Influence of anisotropic pressure on the locking of 2/1 tearing modes in TEXTOR”, Y. Liang, et al., 32nd EPS Conference on Plasma Phys. Tarragona, 27 June - 1 July 2005 ECA Vol.29C, P-4.060 (2005)]

 4) Plasma minor disruption

Collapse events at the q = 2 surface occurring during the mode locking process of an m/n = 2/1 tearing mode have been observed on TEXTOR. The plasma confinement within the q = 2 surface collapses without much influence on the width of the island (O-point). With an external rotating Resonant Magnetic Perturbation (RMP) field induced by the Dynamic Ergodic Divertor (DED), secondary islands moving near the separatix of the primary large 2/1 island with the same frequency as the RMP have been observed after the collapse events. The plasma confinement recovers when the secondary islands vanish. [ref. “Observations of secondary islands after collapse events occurring at the q=2 magnetic surface in the TEXTOR tokamak”, Y. Liang, et al., Nuclear Fusion 47, (2007) L21-L25]

5) Density limit and Marfe

A significant influence of the dynamic ergodic divertor (DED) on the density limit in TEXTOR has been found. In Ohmic discharges, where without DED detachment normally arises at the density limit, a MARFE (multifaceted asymmetric radiation from the edge) develops when the DED is operated in a static regime. The threshold of the MARFE onset in the neutral beam heated plasmas is increased by applying 1 kHz ac DED at the high-field side. The theoretical predictions based on the parallel energy balance taking poloidal asymmetries into account agree well with the experimental observation. [ref. “Influence of the Dynamic Ergodic Divertor on the Density Limit in TEXTOR”, Y. Liang, et al., Physical Review Letters 94, 105003 (2005)]

6) Measurement of Shafranov shift in the high beta plasma in Helical Devices.

The Shafranov shift is derived from the two-dimensional profile of x-ray intensity measured with a soft x-ray CCD camera in LHD. The accuracy of the measurement of the magnetic axis is 3% of the Shafranov shift at high beta. The measured Shafranov shift increases linearly up to 280 ± 3 mm, which is 47% of the minor radius as the volume averaged beta <bdia> measured with a diamagnetic loop is increased up to 2.6%. The Shafranov shift measured with a soft x-ray CCD camera agrees with that calculated with the three dimensional equilibrium code VMEC. [ref. “Measurement of Shafranov shift with soft x-ray CCD camera on LHD” Y. Liang, et al., Plasma Phys. Control. Fusion, Vol. 44, 1383 (2002)]

 7) Shafranov shift due to beam pressure in Helical devices

The radius of the plasma magnetic axis has been measured with soft X-ray CCD camera in its imaging mode. The Shafranov shift of plasma magnetic axis measured from the x-ray images was found to be larger than that estimated from diamagnetic loop in the low-density NBI heated plasmas in CHS. This discrepancy is considered to be due to the beam pressure driven by a tangentially-injected neutral beam. [ref. “Imaging of soft x-ray by using soft x-ray CCD camera”, Y. Liang, et al., Proc. of the 2nd IAEA TCM on Steady State Operation of Magnetic Fusion Device – Plasma Facing Component, Fukuoka, Japan, 25-29th Oct. 1999, FURKU Report 99-05(67), Vol. III, pp. 736-751”]

·        Energy and particle transport of magnetized plasmas

8) Internal transport barrier in electron heat transport in Helical Devices

The internal transport barriers triggered by neoclassical bifurcation are observed with electron cyclotron heating (ECH) in low-density plasmas. The two-dimensional profiles electron temperature measured with the soft x-ray CCD camera in CHS ITB plasma show a sharp temperature gradient appeared at the layer in between the electron root and ion root of neoclassical transport where a large radial electric field shear (Er shear) exists. [ref. Photon counting CCD detector as a tool of x-ray imaging”, Y. Liang, et al., Review of Scientific Instruments, Vol. 72, 717 (2001)]

9) Internal transport barrier in particle transport in Helical Devices

The radial profiles of titanium Ka spectra are measured with photon counting x-ray CCD cameras for plasmas with a neoclassical ITB in CHS. The impurity transport analysis based on the radial profiles of emission and averaged energy of titanium Ka lines indicates that the diffusion coefficient inside the neoclassical ITB is one order of magnitude lower than that of the plasma without neoclassical ITB. [ref. “Observation of Low Impurity Diffusivity inside the Neoclassical Internal Transport Barrier (ITB) in CHS”, Y. Liang, et al., Physics of Plasmas, Vol. 9, 4179 (2002)]

 ·        Devolvement of high temperature plasma diagnostics:

1) X-ray Pin-diodes Arrays

 “Observation of mode structure and mode locking using the Dynamic Ergodic Divertor on TEXTOR”, Y. Liang, et al., 31st EPS Conference on Plasma Phys. London, 28 June - 2 July 2004 ECA Vol.28G, P-1.126 (2004)

 2) Bolometer

 “Radiation power profiles in the plasma with the Dynamic Ergodic Divertor on TEXTOR”, Y. Liang et al., 31st EPS Conference on Plasma Phys. London, 28 June - 2 July 2004 ECA Vol.28G, P-1.125 (2004)

3). X-ray CCD camera system

 Energy and spatial resolved measurement of soft x-ray emission with photon counting x-ray CCD camera in CHS”, Y. Liang, et al., Review of Scientific Instruments, Vol. 71, 3711 (2000).

 “Photon counting CCD detector as a tool of x-ray imaging”, Y. Liang, et al., Review of Scientific Instruments, Vol. 72, 717 (2001)

Measurement of soft x-ray image by using CCD camera for long pulse discharge“, Y. Liang, et al., Journal of Plasma and Fusion Research SERIES, Vol. 3, 427  (2000).

 ”Measurement of the Shape of Magnetic Flux Surfaces in a High Temperature Plasma Using a Soft X-ray CCD Imaging Camera”, Y. Liang, et al., IEEE Transactions on Plasma Science, Vol. 30, 84 (2002)].

4). Charge Exchange Spectroscopy (CXS)

 “Measurements of poloidal rotation velocity using charge exchange spectroscopy in a large helical device”, K. Ida, S. Kado, and Y. Liang, Rev. Sci. Instrum. 71, 2360 (2000)

5). Soft X-ray Pulse Height Analysis (PHA)

 “Diagnostics of high temperature plasma with soft x-ray spectrometer under high count rates”, Y. Liang, Nuclear Fusion and Plasma Physics (in Chinese), Vol. 17, 57, (1997).

 “Soft x-ray spectrometer on HT-7 Tokamak”, Y. Liang, et al., Fusion Engineering and Design, Vol. 34 and 35, 201, (1997).