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FusionBenchmark

ITER

The purpose of ITER is to demonstrate the scientific and technological feasibility of fusion energy production.

Quoted verbatim from the IAEA World Survey of Fusion Devices, not paraphrased.
Type
Fusion device
Approach
Tokamak
Fuel
D-T
Country
FR
Status
Under construction
Ownership
public

Measurements

10 Plasma gain (Q_plasma) planned

Denominator: External heating power coupled into the plasma

6.2 m Major radius planned

2 m Minor radius planned

15 MA Plasma current planned

5.3 T On-axis magnetic field planned

3000 s Plasma duration planned

nominal

7.4 × 10²¹ m⁻³·keV·s Fusion triple product (nTτ_E) planned

shot Projected

20 keV Ion temperature planned

shot Projected

10²⁰ m⁻³ Plasma density planned

shot Projected

3.7 s Energy confinement time (τ_E) planned

shot Projected