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HT-7U Superconducting Tokamak
EAST(HT-7U Superconducting Tokamak), a non-circular advanced steady-state plasma experimental device, was rectified by the Leading Team of Science and Technology, the State Council on June 3, 1997 as a National Mega-Project of Science Research. Its scientific mission is to realize stable operation and carry out experiments on heating and confinement improvement under the tokamak advanced operation and finally realize the tokamak advanced operational mode. |
HT-7U will have a long pulse (60-1000s) capability, a flexible PF system, and auxiliary heating and current drive systems, and will be able to accommodate divertor heat loads that make it an attractive test facility for the development of advanced tokamak operating modes. HT-7U consists of nine sub-systems, namely superconducting tokamak device, cryogenic and refrigerator system, power supply system, control and data acquisition system, lower hybrid current drive (LHCD) system, ion cyclotron resonance heating (ICRH) system, vacuum pumping and gas puffing system, diagnostic system, and water cooling system. The main parameters are:
Table I. Main Parameters of HT-7U Device
| Toroidal Field, Bo |
3.5 T |
| Plasma Current, IP |
0.5 MA |
| Major Radius, Ro |
1.7 m |
| Minor Radius, a |
0.4 m |
| Aspect Ratio, R/a |
4.25 |
| Elongation, Kx |
1.6 - 2 |
| Triangularity, dx |
0.6 - 0.8 |
| Heating and Driving: |
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| ICRH |
3 MW |
| LHCD |
4 MW |
| ECRH |
0.5 MW |
| NBI |
Non(maybe will has) |
| Pulse length |
1-1000 s |
| Configuration |
- Double-null divertor
- Pump limiter
- Single null divertor
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