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NSTX-U

The objectives of NSTX-U are: (i) to study plasma control scenarios in a high-performance spherical tokamak; (ii) to investigate non-inductive plasma smart-up; and (iii) to study heat exhaust solutions.

Quoted verbatim from the IAEA World Survey of Fusion Devices, not paraphrased.
Type
Fusion device
Approach
Tokamak
Country
US
Status
Operating
Ownership
public

Measurements

0.934 m Major radius claimed

0.68 m Minor radius claimed

2 MA Plasma current claimed

1 T On-axis magnetic field claimed

5 s Plasma duration claimed

nominal