Abstract
The Chinese Experimental Advanced Superconducting Tokamak (EAST) has been successfully constructed and has produced a discharge of plasma in ×2006. It aims to achieve static-state operation of high performance D-D plasma with a long pulse of up to 1000 s and may be severed as a valuable pre-testing platform for Test Blanket Module (TBM) prior to International Thermonuclear Experimental Reactor (ITER). Based on the Chinese Dual Function Lithium Lead TBM (DFLL-TBM) design and its testing plan for ITER and EAST, a lithium lead test blanket module concept for the EAST (EAST-TBM) has been proposed as an important R&D activity and is expected to be tested in EAST focusing on electro-magnetics and thermo-mechanics performances of the TBM, including the influence of TBM made of ferromagnetic steel on tokamak plasma. This paper presents the status of EAST-TBM design, including design guideline, main features, instrumentation configuration, and installation in EAST port. The feasibility of the EAST-TBM has been validated with the preliminary performance analyses.
| Original language | English |
|---|---|
| Pages (from-to) | 2347-2352 |
| Number of pages | 6 |
| Journal | Fusion Engineering and Design |
| Volume | 82 |
| Issue number | 15-24 |
| DOIs | |
| State | Published - Oct 2007 |
Keywords
- Breeding blanket
- EAST device
- EAST-TBM
- ITER
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