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Latest ITER Newsline

  • IAEA and ITER | Even closer cooperation

    Under Practical Arrangements signed in June, the International Atomic Energy Agency and the ITER Organization will be expanding and deepening a long history of [...]

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  • Neutral Beam Test Facility | High voltage component for MITICA

    Creating reliable high-energy neutral beams at ITER parameters, from a negative ion source, requires such a large technological leap that the components of the [...]

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  • 24th ITER Council | En route to First Plasma, 63% of the work is done

    The ITER Council has met for the twenty-fourth time since the signature of the ITER Agreement. Representatives from China, the European Union, India, Japan, Kor [...]

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  • Upper ports | A very international effort

    The 18 upper ports of the ITER vacuum vessel are procured by Russia, manufactured in Germany, and mounted (in part) on the vessel sectors by contractors in Ital [...]

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  • Paint job | One level done, five to go

    The job is done and the effect is spectacular. At the deepest basement level (B2) of the Tokamak Building, the floors, walls, and ceilings are now perfectly whi [...]

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Of Interest

See archived entries

Design of ITER's in-vessel coils converging

Edward Daly, Mechanical Engineer, Vacuum Vessel Section

Two vertical stability coils (orange) provide fast vertical stabilization of the plasma. An array of 27 ELM coils (green and blue) provide a magnetic ''massage'' of the plasma exterior to suppress potentially harmful power deposition on plasma-facing components. (Click to view larger version...)
Two vertical stability coils (orange) provide fast vertical stabilization of the plasma. An array of 27 ELM coils (green and blue) provide a magnetic ''massage'' of the plasma exterior to suppress potentially harmful power deposition on plasma-facing components.
Last week, experts from around the world assembled virtually in Cadarache to conduct a preliminary design review of the ITER in-vessel coils and feeders. Their mission was to evaluate the results from the preliminary design work presented by the in-vessel coil design team. The hard work of the design team lead by the Princeton Plasma Physics Lab (PPPL) paid off with a successful review enabling design and R&D activities to proceed towards an interim review planned for March 2011.

The ITER in-vessel coil system is comprised of two systems: the vertical stability coils and the edge localized mode (ELM) coils. The vertical stability coils are two poloidal field coils located above and below the tokamak's mid-plane. They provide fast vertical stabilization of the plasma. The ELM coils, an array of 27 coils fixed to the wall of the vacuum vessel, provide resonant magnetic perturbations in order to control the plasma so that certain types of plasma instabilities called edge-localized modes are avoided. 

Each in-vessel coil is wound from about 50 metres of conductor consisting of a 59-mm outer diameter stainless steel jacket, an insulating layer of magnesium oxide and an inner copper conductor. Magnesium oxide is chosen for its ability to withstand the harsh radiation environment within the Tokamak. In total, the in-vessel coils require more than 4 km of mineral-insulated conductors. (Click to view larger version...)
Each in-vessel coil is wound from about 50 metres of conductor consisting of a 59-mm outer diameter stainless steel jacket, an insulating layer of magnesium oxide and an inner copper conductor. Magnesium oxide is chosen for its ability to withstand the harsh radiation environment within the Tokamak. In total, the in-vessel coils require more than 4 km of mineral-insulated conductors.
The control functions provided by these two coil systems are part of the overall plasma control system that ensures and maintains stable plasma operations. Two vertical stability coils (marked orange) provide fast vertical stabilization of the plasma. An array of 27 ELM coils (green & blue) provide a magnetic "massage" of the plasma exterior to suppress potentially harmful power deposition on plasma-facing components.

The masterminds behind the in-vessel coils at the Princeton Plasma Physics Lab. (Click to view larger version...)
The masterminds behind the in-vessel coils at the Princeton Plasma Physics Lab.
Each in-vessel coil is wound from about 50 metres of conductor consisting of a 59-mm outer diameter stainless steel jacket, an insulating layer of magnesium oxide and an inner copper conductor. Magnesium oxide is chosen for its ability to withstand the harsh radiation environment within the ITER Tokamak. Water will flow through the central hole to remove power deposited from resistive and neutron heating. In total, the in-vessel coils require more than four kilometres of mineral-insulated conductors.

 
Click here to learn more about ELMs and how to control them
 
Clikc here to find out why not all ELMs are trees.


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