RF power experiments in WEST to prepare for next-step fusion device operation
Abstract
The WEST superconducting tokamak, featuring a full tungsten environment and equipped with an actively cooled ITER-grade divertor, provides valuable inputs for future ITER operation. One of its distinctive features is that auxiliary plasma heating and current drive is exclusively supplied by radiofrequency (RF) systems. Scenario development supported by integrated modelling has allowed pulses exceeding 1300 s and 2.6 GJ of energy to be performed, based on feedback-controlled plasma current sustained by LHCD power in order to achieve a zero-loop voltage target. In this contribution, we review recent progress and near-term plans related to plasma scenario performance improvement using RF waves in WEST, directly relevant to the operation of future fusion devices in full metal environments.
Fields of Study & Subjects
Magnetic confinement fusion research
Fusion materials and technologies
Superconducting Materials and Applications
Publication details
- Journal / source
- Springer Link (Chiba Institute of Technology)
- Publication date
- 7 January 2026
- Language
- EN