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  • ITER Design Handbook | Preserving the vital legacy of ITER

    The contributions that ITER is making to fusion physics and engineering—through decades of decisions and implementation—are delivering insights to the fusion co [...]

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  • Electron cyclotron heating | Aligning technology and physics

    ITER, like other fusion devices, will rely on a mix of external heating technologies to bring the plasma to the temperature necessary for fusion. At a five-day [...]

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  • Poloidal field magnets | The last ring

    As the massive ring-shaped coil inched its way from the Poloidal Field Coils Winding Facility, where it was manufactured, to the storage facility nearby where i [...]

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  • Heat rejection | White "smoke" brings good news

    Like a plume of white smoke rising from a cardinals' conclave to announce the election of a new pope, the tenuous vapour coming from one of the ITER cooling cel [...]

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  • WEC 2024 | Energy on centre stage

    The global players in the energy sector convened in Rotterdam last week for the 26th edition of the World Energy Congress (WEC). The venue was well chosen, wit [...]

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Of Interest

See archived entries

Merry plasmas!

On 14 December, at 6:03 p.m., a flash of light illuminated the vacuum vessel of WEST, the rejuvenated Tore Supra tokamak designed to serve as a test bench for ITER.

Operational since 1988, the CEA-Euratom tokamak Tore Supra underwent a major transformation and became WEST (W Environment in Steady-state Tokamak), a test bench for ITER. The machine produced its first plasma on 14 December. (Click to view larger version...)
Operational since 1988, the CEA-Euratom tokamak Tore Supra underwent a major transformation and became WEST (W Environment in Steady-state Tokamak), a test bench for ITER. The machine produced its first plasma on 14 December.
This first plasma rewarded four years of hard work that involved stripping out the 30-year-old machine, adding magnetic coils to confine the originally circular plasma into a "D shape," and trading its carbon-carbon fibre (CFC) "limiter" for an ITER-like tungsten divertor.

Operators at the French Institute for Magnetic Fusion Research (IRFM) are now confident that they can move forward to the first experimental campaign, set to be launched in March 2017. The first phase of the campaign will explore heat load patterns and H mode transition; the second in October-December 2017 will focus on testing plasma-facing components under the high heat loads of ITER-grade plasmas.

On that very same day, Korea's National Fusion Research Institute (NFRI) announced that the KSTAR tokamak had achieved a record 70-second H-mode plasma. (Click to view larger version...)
On that very same day, Korea's National Fusion Research Institute (NFRI) announced that the KSTAR tokamak had achieved a record 70-second H-mode plasma.
On the very same day that the IRFM team was (discreetly) celebrating WEST's first plasma, another team, at the other end of the world, also had an achievement to announce: a record 70-second H-mode plasma had just been recorded by the Korean superconducting tokamak KSTAR.

One month earlier, in mid-November, the Chinese tokamak EAST had achieved a similar but slightly shorter 60-second steady-state high energy plasma.

Read more about WEST here.


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