Pegasus Toroidal Experiment

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.

Pegasus Toroidal Experiment
Device TypeSpherical tokamak
LocationMadison, Wisconsin, US
AffiliationUniversity of Wisconsin–Madison
Technical specifications
Major Radius45 cm (18 in)
Minor Radius40 cm (16 in)
Links
WebsitePegasus Toroidal Experiment webpage

URANIA

Pegasus is being upgraded in 2019 (eg. 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


This article is issued from Wikipedia. The text is licensed under Creative Commons - Attribution - Sharealike. Additional terms may apply for the media files.