Abstract
By the end of September 2006, the engineering commissioning of the Experimental Advanced Superconducting Tokamak (EAST) was completed and the first H2 plasma was achieved with stainless steel as the plasma-facing material (PFM). In the following phases, with gradual increase in the heating power, the EAST divertor targets have to handle expected heat loads up to ∼10 MW m-2. The PFMs to be employed include doped graphite and W coatings. The former will be used to cover the whole plasma-facing surface in the first phase, and then the latter applied to replace the graphite tiles gradually in the second phase, and finally a whole W plasma-facing surface will be expected. Graphite has been studied for many years and contributed greatly to the HT-7 to achieve long pulses of some 100 s. The W coatings are being developed and the latest R&D development is reported in the paper.
| Original language | English |
|---|---|
| Pages (from-to) | 1-5 |
| Number of pages | 5 |
| Journal | Physica Scripta T |
| Volume | T128 |
| DOIs | |
| State | Published - 2007 |
| Event | 11th International Workshop on Plasma-Facing Materials and Components for Fusion Applications - Greifswald, Germany Duration: 10 Oct 2006 → 12 Oct 2006 |
Fingerprint
Dive into the research topics of 'Overview of plasma-facing materials and components for EAST'. Together they form a unique fingerprint.Cite this
- APA
- Author
- BIBTEX
- Harvard
- Standard
- RIS
- Vancouver