180 research outputs found
Plasma tomographic reconstruction from tangentially viewing camera with background subtraction
Formation of convective cells in the scrape-off layer of the CASTOR tokamak
Understanding of the scrape-off layer (SOL) physics in tokamaks requires
diagnostics with sufficient temporal and spatial resolution. This contribution
describes results of experiments performed in the SOL of the CASTOR tokamak
(R=40 cm, a = 6 cm) by means of a ring of 124 Langmuir probes surrounding the
whole poloidal cross section. The individual probes measure either the ion
saturation current of the floating potential with the spatial resolution up to
3 mm. Experiments are performed in a particular magnetic configuration,
characterized by a long parallel connection length in the SOL, L_par ~q2piR. We
report on measurements in discharges, where the edge electric field is modified
by inserting a biased electrode into the edge plasma. In particular, a complex
picture is observed, if the biased electrode is located inside the SOL. The
poloidal distribution of the floating potential appears to be strongly
non-uniform at biasing. The peaks of potential are observed at particular
poloidal angles. This is interpreted as formation of a biased flux tube, which
emanates from the electrode along the magnetic field lines and snakes q times
around the torus. The resulting electric field in the SOL is 2-dimensional,
having the radial as well as the poloidal component. It is demonstrated that
the poloidal electric field E_pol convects the edge plasma radially due to the
E_pol x B_T drift either inward or outward depending on its sign. The
convective particle flux is by two orders of magnitude larger than the
fluctuation-induced one and consequently dominates.Comment: 12th International Congress on Plasma Physics, 25-29 October 2004,
Nice (France
Installation of the room temperature solid state pellet injector for investigation of runaway electrons at the COMPASS tokamak
Plasma tomographic reconstruction from tangentially viewing camera with background subtraction
Overview of power exhaust experiments in the COMPASS divertor with liquid metals
Power handling experiments with a special liquid metal divertor module based on the capillary porous system technology were performed in the tokamak COMPASS. The performance of two metals (Li and LiSn alloy) were tested for the first time in a divertor under ELMy H-mode conditions. No damage of the capillary mesh and a good exhaust capability were observed for both metals in two separate experiments with up to 12 MW/m(2) of deposited perpendicular, inter-ELM steady-state heat flux and with ELMs of relative energy similar to 3% and a local peak energy fluence at the module similar to 15 kJ.m(-2). No droplets were directly ejected from the mesh top surface and for the LiSn experiment, no contamination of the core and SOL plasmas by Sn was observed. The elemental depth profile analysis of 14 stainless-steel samples located around the vacuum vessel for each experiment provides information about the migration of evaporated/redeposited liquid elements
Quantification of locked mode instability triggered by a change in confinement
This work presents the first analysis of the disruptive locked mode (LM)
triggered by the dynamics of a confinement change. It shows that, under certain
conditions, the LM threshold during the transient is significantly lower than
expected from steady states. We investigate the sensitivity to a controlled error field (EF) activated prior to the L-H transition in the COMPASS
tokamak, at , , and using EF coils on the
high-field side of the vessel. A threshold for EF penetration subsequent to the
L-H transition is identified, which shows no significant trend with density or
applied torque, and is an apparent consequence of the reduced intrinsic
rotation of the 2/1 mode during this transient phase. This finding challenges
the assumption made in theoretical and empirical works that natural mode
rotation can be predicted by global plasma parameters and urges against using
any parametric EF penetration scaling derived from steady-state experiments to
define the error field correction strategy in the entire discharge.
Furthermore, even at EFs below the identified penetration threshold, disruptive
locking of sawtooth-seeded 2/1 tearing modes is observed after about 30% of L-H
transitions without external torque.Comment: 15 pages, 13 figures, submitted to Nuclear Fusio
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