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Pegasus Toroidal Experiment
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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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Local Helicity Injection
Pegasus is used to study start up of spherical tokamaks using local helicity injection.[1][2]
URANIA
Pegasus 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
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