VEST
The main objectives of VEST are to study spherical tokamak plasmas, wave heating and high beta operations, as well as divertor concepts, including Super-X divertor configuration.
- Operator
- Seoul National University
- Type
- Fusion device
- Approach
- Spherical tokamak
- Country
- KR
- Status
- Operating
- Built
- 2013
- Ownership
- public
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 | 0.45 m | m | claimed | World Survey of Fusion Devices 2022 independent |
| Minor radius medium confidence | 0.33 m | m | claimed | World Survey of Fusion Devices 2022 independent |
| Plasma current medium confidence | 0.1 MA | MA | claimed | World Survey of Fusion Devices 2022 independent |
| On-axis magnetic field medium confidence | 0.1 T | T | claimed | World Survey of Fusion Devices 2022 independent |