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.
- Operator
- CEA
- Type
- Fusion device
- Approach
- Tokamak
- Country
- FR
- Status
- Operating
- First plasma
- 2016
- Ownership
- public
Results
1,337 s Plasma duration claimed
measured 2025-02-12 · sustained · high confidence
Design values
What the machine was built to do, as published. Not results, and never ranked.
| Parameter | Value | Unit | Status | Source |
|---|---|---|---|---|
| Major radius medium confidence | 2.5 m | m | claimed | World Survey of Fusion Devices 2022 independent |
| Minor radius medium confidence | 0.5 m | m | claimed | World Survey of Fusion Devices 2022 independent |
| Plasma current medium confidence | 1 MA | MA | claimed | World Survey of Fusion Devices 2022 independent |
| On-axis magnetic field medium confidence | 3.7 T | T | claimed | World Survey of Fusion Devices 2022 independent |
| Plasma duration (nominal) medium confidence | 1,000 s | s | claimed | World Survey of Fusion Devices 2022 independent |