Milestone
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Sunday, June 28, 2026
Vol. III · Edition · Web
Milestone · high impact
WEST tokamak, inside and out
The WEST tokamak in Cadarache, France, provides a critical testbed for ITER's tungsten divertor technology, leveraging the superconducting legacy of Tore Supra to explore long-pulse, high-heat-flux plasma scenarios.
Reported fusion metrics
Pulse Duration
1000 s
Design goal for the WEST tokamak.
Heat Flux
20 MW/m²
Maximum steady-state heat flux on the WEST divertor components.
Plasma Current
1 MA
Maximum plasma current in the WEST tokamak.
Injected Energy
1 GJ
Record set by the predecessor machine, Tore Supra, during a 6.5-minute pulse.
Cadarache, France – The WEST tokamak is actively pushing the boundaries of fusion energy research, serving as a vital testing ground for the advanced tungsten divertor technology destined for the international ITER project. This unique facility, built upon the foundation of the former Tore Supra superconducting tokamak, is meticulously designed to simulate the extreme conditions expected in future fusion power plants, particularly the immense heat loads on plasma-facing components.
At the heart of WEST's mission is the validation of tungsten as the primary material for the divertor, a critical component that manages the exhaust of heat and particles from the fusion plasma. Tungsten's high melting point and low sputtering yield make it an ideal candidate for withstanding the intense thermal fluxes, which can reach several megawatts per square meter, a key challenge for sustained fusion operations.
Significant progress has already been made, with WEST successfully completing its first experimental campaign.
The facility's design leverages the powerful superconducting magnets inherited from Tore Supra, enabling WEST to achieve long-pulse plasma discharges, a crucial requirement for demonstrating the viability of fusion power. This capability allows researchers to study the long-term performance and degradation of the tungsten divertor under realistic operational scenarios, providing invaluable data for ITER's construction and operation.
Significant progress has already been made, with WEST successfully completing its first experimental campaign. This initial phase focused on demonstrating the integrated performance of the tungsten divertor modules and the associated cooling systems under high-power plasma conditions. The data gathered is essential for confirming the design choices and operational parameters for ITER's own divertor.
The development and operation of WEST represent a substantial international collaboration, with contributions from numerous research institutions and funding bodies. While specific financial figures for the entire project are complex, the investment reflects the global commitment to advancing fusion technology and the recognition of WEST's pivotal role in de-risking ITER's divertor solution.
Challenges remain, including managing the accumulation of impurities within the plasma and ensuring the long-term structural integrity of the tungsten components under repeated thermal cycling. However, the ongoing experimental campaigns are designed to systematically address these issues, building confidence in the tungsten divertor's resilience.
Looking ahead, WEST will continue its rigorous testing program, aiming to achieve even higher plasma performance and longer pulse durations. The data from these future campaigns will directly inform decisions regarding the final design and operational strategies for ITER's divertor, a critical step towards realizing commercial fusion power.
The next major decision point will revolve around the results of ongoing and planned experiments, particularly concerning the thermal management and material endurance of the tungsten divertor. Successful validation will pave the way for the full implementation of this technology in ITER, with significant milestones expected in the coming years.
Reporting grounded in coverage from the original publisher — read the source .
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