WEST
Key missions of WEST are the qualification of the high heat flux plasma facing components in integrating both technological and physics aspects in relevant heat and particle exhaust conditions (particularly for the tungsten monoblocks foreseen in ITER divertor), as well as the demonstration of integrated steady state operation, with a focus on power exhaust issues.
Quoted verbatim from the IAEA World Survey of Fusion Devices, not paraphrased.
- Operator
- CEA
- Type
- Fusion device
- Approach
- Tokamak
- Country
- FR
- Status
- Operating
- First plasma
- 2016
- Ownership
- public
Measurements
2.5 m Major radius claimed
0.5 m Minor radius claimed
1 MA Plasma current claimed
3.7 T On-axis magnetic field claimed
1000 s Plasma duration claimed
nominal