J-TEXT

The main purpose of J-TEXT is proving fundamental physics and control mechanisms of fusion plasma confinement and stability in support of ITER’s successful operation and the design of CFETR (see p.
Quoted verbatim from the IAEA World Survey of Fusion Devices, not paraphrased.

Operator: Huazhong University of Science and Technology
Type: Fusion device
Approach: Tokamak
Country: CN
Status: Operating
Ownership: public

Measurements

1.05 m Major radius claimed

0.25 m Minor radius claimed

0.2 MA Plasma current claimed

2 T On-axis magnetic field claimed

0.8 s Plasma duration claimed

nominal