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T-11M

The main purpose of T-11M is to conduct research on lithium plasma facing components protection and lithium injection into scrape-off-layer plasma.

Quoted verbatim from the IAEA World Survey of Fusion Devices, not paraphrased.
Type
Fusion device
Approach
Tokamak
Country
RU
Status
Operating
Built
1985
Ownership
public

Measurements

0.7 m Major radius claimed

0.2 m Minor radius claimed

0.1 MA Plasma current claimed

1 T On-axis magnetic field claimed

0.25 s Plasma duration claimed

nominal