Tokamak vs stellarator
Both confine plasma magnetically in a torus. The difference is where the twist in the magnetic field comes from — and everything else follows from that.
Tokamak
Doughnut-shaped magnetic confinement using a strong toroidal field plus a current driven through the plasma itself. The most-studied configuration, and the one ITER uses. Its main open problem is heat exhaust at the divertor, where the plasma edge concentrates power onto a small area, together with the risk of disruptions: sudden, uncontrolled losses of the plasma current.
54 devices · 13 organisations · 272 measurements
Stellarator
Confinement produced by external coils twisted into complex three-dimensional shapes, so no net current has to be driven through the plasma. That removes the disruptions a tokamak's plasma current can cause and allows continuous operation, at the price of coils that are far harder to design and build.
16 devices · 9 organisations · 46 measurements
Differences
| Tokamak | Stellarator | |
|---|---|---|
| Where the field twist comes from | A current driven through the plasma itself. | The shape of the external coils alone. |
| Consequence for operation | The plasma current must be sustained, which historically meant pulsed operation and makes long steady-state discharges hard. | No plasma current is needed, so steady-state operation is natural. This is the central advantage. |
| Disruptions | A sudden loss of plasma current can dump the stored energy into the wall. Disruption mitigation is a major engineering programme. | No large plasma current, so current-driven disruptions are largely absent. |
| Engineering difficulty | Coils are comparatively simple and axisymmetric. | Coils are three-dimensional and must be manufactured to very tight tolerance. This is why there are far fewer of them. |
| Maturity | By far the most-built approach, and the basis of ITER. | Fewer machines, but W7-X holds the stellarator record for triple product. |
Devices
Tokamak 54
- Joint European Torus · 14
- Experimental Advanced Superconducting Tokamak · 11
- JT-60U · 11
- KSTAR · 11
- ITER · 10
- DIII-D · 9
- ASDEX UPGRADE · 9
- SPARC · 9
- WEST · 6
- Tokamak Fusion Test Reactor · 6
- NOVA-FURG · 5
- TCABR · 5
- STOR-M · 5
- HL-2A · 5
- and 40 more
Stellarator 16
- Wendelstein 7-X · 9
- SCR-1 · 4
- CTH · 4
- CFQS · 3
- TJ-K · 3
- HELIOTRON J · 3
- TJ-II · 3
- URAGAN-2M · 3
- URAGAN-3M · 3
- HIDRA · 3
- HSX · 3
- Large Helical Device · 3
- Infinity Two · 2
- Infinity One
- and 2 more