W (tungsten) Environment in Steady-state Tokamak
WEST validates and fatigue-tests the ITER actively-cooled tungsten divertor components
during the ITER construction phase and prepare their safe operation.
The mastery of nuclear Fusion and the construction of the ITER tokamak will inevitably involve a number of challenges. The WEST tokamak is dealing with one of them already: the divertor.
WEST (acronym derived from W Environment in Steady-state Tokamak, where W is the chemical symbol for tungsten) is the transformation of the Tore Supra tokamak from a limiter to a divertor configuration.
Remote participation to fusion experiments will be used in the next years by scientists all over the world. On November 28th, for the first time, the Remote Experimentation Center (REC) in Rokkasho (Japan) took control of the WEST IRFM tokamak in Cadarache, located 9486 km away.
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A new infrared thermography system has been installed in the WEST tokamak to observe the thermal scene of the first wall and components in a wide-angle tangential view of the poloidal cross-section.
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On the 18th of December 2017 current was raised in the divertor coils and the very first X-point plasma was obtained in the WEST tokamak.
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