TEXTOR

Figure 1:Forschungszentrum Jülich (Germany)

Introduction to TEXTOR
TEXTOR Parameters
TEXTOR Milestones
TEXTOR Objectives and Achievements
Operation schedule

Introduction to TEXTOR

Figure 2:TEXTOR outside

The programme of the Association EURATOM-IPP (Institute of Plasma Physics) in Jülich (Germany) concentrates on the interaction of the magnetically confined high-temperature plasma with the surrounding walls and on methods of influencing it as well as on linking these issues with the transport of particles and energy in the plasma core.
The EURATOM-associated fusion laboratories from three countries in the region (ERM/KMS Brussels - Belgium, FOM Nieuwegein - The Netherlands and Research Centre Jülich - Germany) have joined forces as a joint research team forming the Trilateral Euregio Cluster (TEC) to jointly handle this comprehensive programme.
The TEC partners' central experimental facility is the TEXTOR long-pulse tokamak. Further apparatus oriented to the programme goal is under construction or at the planning stage. At the Research Centre at Jülich this is primarily the Dynamic Ergodic Divertor (DED), which represents a novel technique for influencing the particle and energy transport in the plasma boundary layer by "magnetic edge layer vortexing". The installation of the DED in the TEXTOR vessel was completed in Autumn 2002. Extensive new installations in TEXTOR are also provided by the Dutch TEC partner. They comprise new diagnostics and an electron cyclotron resonance heating (ECRH) system with a 1 MW gyrotron.
A co-operation agreement on the joint use of TEXTOR with the International Energy Agency (IEA) regulates the participation of scientists from Japan, the USA and Canada, the provision of equipment from these countries and the implementation of self-contained programme elements of the partner countries.

Figure 3:TEXTOR inside

Figure 4:TEXTOR inside

TEXTOR Parameters

Pulse duration	12 s
Plasma current	800 kA
Magnetic field	2.8 T
Auxiliary heating	4 MW NBI, 4 MW ICRH, 500kW ECRH
Major radius	1.75 m
Minor radius	0.50 m
Plasma shape	circular

Figure 4:TEXTOR Plasma

TEXTOR Milestones

1983	first plasma experiments.
1984	auxiliary heating with 4 MW ICRH.
1984	wall coating by carbonisation.
1985	poloidal limiters made of graphite.
1986	limiter lock system for test limiters.
1987	toroidal belt pumped limiter ALT-II (graphite).
1988 1988	wall coating by boronisation. auxiliary heating with 4 MW neutral beams.
1991	radiation cooling with seeded impurities (neon).
1994	new transformer, major pulse prolongation (12 sec pulse duration, 800 kA max. plasma current).
1996	foundation of the Trilateral Euregio Cluster (TEC).
1999	Electron Cyclotron Heating (ECRH).
2002	Dynamic Ergodic Divertor (DED).

Figure 5:TEXTOR Machine in November 2001

TEXTOR Objectives and Achievements

The joint research programme of the TEC partners aims at developing a coherent concept for energy and particle transport as well as exhaust under quasi-stationary conditions. The tokamak TEXTOR is equipped with a toroidal pump limiter (ALT-II) and, with a heating power of - up to now - 4.0 MW NBI, 4.0 MW ICRH (provided by the Belgian TEC partner) and 500 kW ECRH (provided by the Dutch TEC partner). This achieves a power flux density through the boundary of up to 25 W/cm2. Reactor relevant plasmas can be produced and maintained for a duration of up to about 12 seconds. The experiments are accompanied by related modelling activities. Plasma facing materials and components are developed and tested using specific facilities for applying extremely high heat loads.
The scientific programme of TEXTOR is currently divided into seven general issues: plasma-wall interaction, impurity transport, energy confinement, magnetohydrodynamics, advanced tokamak scenarios, new concepts and special components as well as modelling and theory. R&D projects at Forschungszentrum Jülich, as well as research by the TEC partners ERM/KMS and FOM, contribute towards dealing with these issues. Analogously, the instrumental and diagnostic equipment of TEXTOR is jointly provided and coordinated by the TEC partners.
The research team is involved in the Joint European Torus (JET) by planning, implementing (partially heading) and scientifically evaluating experimental campaigns on selected issues. Mutual enrichment plays an important part in the research on JET and TEXTOR. Participation in the stellarator programme of the Max Planck Institute of Plasma Physics (Garching, Berlin, Greifswald) covers work on specific physical problems, intensive cooperation in the conceptual design of selected boundary layer and core diagnostics for the Wendelstein 7-X project as well as the further development of equally TEXTOR- and stellarator-relevant numerical models.
Scientific highlights of the TEXTOR programme are: Investigation of the Dynamic Ergodic Divertor concept, wall conditioning (boronisation/siliconisation), erosion and deposition, recycling, helium exhaust, confinement physics (especially RI-mode, edge-core relations), energy and particle transport, magnetohydrodynamics, runaway electrons, diagnostics development, development and validation of codes (erosion-deposition, edge physics, strongly radiating plasmas).

Operation schedule

The DED installation is completed now, operation has begun in 2003. You can follow topic events at TEXTOR on: