The Pegasus Toroidal Experiment is a plasma confinement experiment relevant to fusion power production, run by the Department of Engineering Physics of the University of Wisconsin–Madison. It is a spherical tokamak, a very low-aspect-ratio version of the tokamak configuration, i.e. the minor radius of the torus is comparable to the major radius.
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| Device type | Spherical tokamak |
|---|---|
| Location | Madison, Wisconsin, US |
| Affiliation | University of Wisconsin–Madison |
| Technical specifications | |
| Major radius | 45 cm (18 in) |
| Minor radius | 40 cm (16 in) |
| Links | |
| Website | Pegasus Toroidal Experiment webpage |
Local Helicity Injection
editPegasus is used to study start up of spherical tokamaks using local helicity injection.[1][2]
URANIA
editPegasus is being upgraded in 2019 (e.g. by removal of the central solenoid) to build the Unified Reduced Non-Inductive Assessment (URANIA) experiment. This will study plasma startup using transient coaxial helicity injection (CHI).[2][1]
The max toroidal field is being increased from 0.15 T to 0.6 T, and the pulse duration from 25 to 100 ms.[3]
References
edit- ^ a b Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup Bongard 2018
- ^ a b "URANIA: A Dedicated Spherical Tokamak Experiment for Developing Non-Solenoidal Plasma Startup Techniques" (PDF). Archived from the original (PDF) on 2019-05-04. Retrieved 2019-05-04.
- ^ "Research Directions on the Pegasus Toroidal Experiment Reusch 2018" (PDF). Archived from the original (PDF) on 2019-05-04. Retrieved 2019-05-04.
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