FAST:

Fusion by Advanced Superconducting Tokamak

FAST is the world’s first project to extract fusion energy from burning plasma and to comprehensively demonstrate both plasma sustainment and the associated engineering challenges.

Our goal is to achieve the first demonstration of fusion power generation in the 2030s.

About Fusion Energy

Fusion energy is what gives the stars their seemingly limitless power.

A single fusion reaction between deuterium (D) and tritium (T) releases 17.6 MeV of energy, which is an enormous amount when added up over time.

Deuterium can be extracted from seawater, and tritium can be self-multiplied, giving it geopolitical advantages of securing fuel domestically. Because no greenhouse gas is contained in the fuel or exhaust, it also contributes to a carbon-neutral society.

Since fusion energy does not produce high concentrations of radioactive waste, there is optimism for its development as a permanent next-generation energy source.

Shaping the future of energy by surpassing technical frontiers

We’re accelerating development toward the commercialization of fusion energy by aiming for a demonstration of power generation in the 2030s and tackling the following technical challenges:

D-T burning demonstration

Achieving, sustaining, and controlling burning plasma with tritium—the core technology of fusion energy.

Breeding, extracting, recovering, and reusing tritium fuel to establish a sustainable cycle.

Developing and demonstrating plant technologies to safely and reliably integrate and operate a fusion energy system.

Uniting the latest engineering innovations in the Tokamak

FAST adopts the tokamak system, a proven approach backed by extensive experimental experience. This design offers high reliability while effectively managing costs and technical risks. We are integrating state-of-the-art reactor engineering technologies—such as high-temperature superconducting magnets and advanced blankets—to build an innovative, highly feasible, low-aspect-ratio tokamak reactor.

Specification of FAST

FAST is a low aspect-ratio tokamak with HTS coils, making it a compact, economical Fusion Pilot Plant. This design will have the following specifications, which will inform the development tests necessary for early deployment.​

50-100
MW
(D–T = deuterium–tritium)
300 – 1,000
kW/m²
Neutron wall loading
1000
seconds
Approx. discharge duration
1000
hours
Approx. cumulative full-power operation time
Major Radius
2.8m
Minor Radius
0.95 m
Elongation
1.8
Magnetic Field Strength
4.8 T
Magnet
HTS Coils
Fuel
Deuterium and Tritium
External heating systems
NBI, ECH
Ion Temperature
~ 20 keV (200 million ℃)
Line Average Density
0.5 x 1020m-3
Normalized Beta
2.6
Plasma Current
7 MA
Self-driven Current Fraction
0.25
Confiinement enhancement factor
1.2
Energy Confiinement Time
0.65 sec

Project Timeline

Join us in shaping the future of fusion

We are seeking companies and organizations interested in participating in and supporting our project.

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