Abstract
The superconducting tokamak project HT-7U, aiming at steady-state advanced operation mode, will make a contribution to future steady-state tokamak reactors. The scientific and the engineering missions of the project are to study physics issues of the steady-state tokamak operation and to establish technology basis of full superconducting tokamaks. It features: superconducting toroidal field system and poloidal field system, non-inductive current drive and plasma heating systems, flexibility and reliability of plasma shaping control, J(r) and P(r) control, replaceability of plasma facing components and divertors for power and particle handling study in steady-state operation and advanced diagnostic measurements. The physics design and the engineering design have been completed essentially. The key R&D programs of the tokamak device have been successful. The assembly of the device has begun. It is planned to obtain the first plasma in 2005.
| Original language | English |
|---|---|
| Pages | 646-651 |
| Number of pages | 6 |
| State | Published - 2003 |
| Event | 20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03 - San Diego, CA, United States Duration: 14 Oct 2003 → 17 Oct 2003 |
Conference
| Conference | 20th IEEE/NPSS Symposium on Fusion Engineering, SOFE 03 |
|---|---|
| Country/Territory | United States |
| City | San Diego, CA |
| Period | 14/10/03 → 17/10/03 |
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