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.
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 (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
Advancing Local Helicity Injection for Non-Solenoidal Tokamak Startup Bongard 2018
URANIA: A Dedicated Spherical Tokamak Experiment for Developing Non-Solenoidal Plasma Startup Techniques
Research Directions on the Pegasus Toroidal Experiment Reusch 2018
vte
Fusion power, processes and devices
Core topics
Nuclear fusion
Timeline List of experiments Nuclear power Nuclear reactor Atomic nucleus Fusion energy gain factor Lawson criterion Magnetohydrodynamics Neutron Plasma
Processes,
methods
Confinement
type
Gravitational
Alpha process Triple-alpha process CNO cycle Fusor Helium flash Nova
remnants Proton-proton chain Carbon-burning Lithium burning Neon-burning Oxygen-burning Silicon-burning R-process S-process
Dense plasma focus Field-reversed configuration Levitated dipole Magnetic mirror
Bumpy torus Reversed field pinch Spheromak Stellarator Tokamak
Spherical Z-pinch
Inertial
Bubble (acoustic) Laser-driven Magnetized Liner Inertial Fusion
Fusor Polywell
Other forms
Colliding beam Magnetized target Migma Muon-catalyzed Pyroelectric
Devices, experiments
Magnetic confinement
Tokamak
International
Americas
Canada STOR-M United States Alcator C-Mod ARC
SPARC DIII-D Electric Tokamak LTX NSTX
PLT TFTR Pegasus Brazil ETE Mexico Novillo [es]
Asia,
Oceania
China CFETR EAST
HT-7 SUNIST India ADITYA SST-1 Japan JT-60 QUEST [ja] Pakistan GLAST South Korea KSTAR
Europe
European Union JET Czech Republic COMPASS GOLEM [cs] France TFR WEST Germany ASDEX Upgrade TEXTOR Italy FTU IGNITOR Portugal ISTTOK Russia T-15 Switzerland TCV United Kingdom MAST-U START STEP
Stellarator
Americas
United States CNT CTH HIDRA HSX Model C NCSX Costa Rica SCR-1
Asia,
Oceania
Australia H-1NF Japan Heliotron J LHD
Europe
Germany WEGA Wendelstein 7-AS Wendelstein 7-X Spain TJ-II Ukraine Uragan-2M
Uragan-3M [uk]
Magnetized target
Canada SPECTOR United States LINUS FRX-L – FRCHX Fusion Engine
Other
Russia GDT United States Astron LDX Lockheed Martin CFR MFTF
TMX Perhapsatron PFRC Riggatron SSPX United Kingdom Sceptre Trisops ZETA
Inertial confinement
Laser
Americas
United States Argus Cyclops Janus LIFE Long path NIF Nike Nova OMEGA Shiva
Asia
Japan GEKKO XII
Europe
European Union HiPER Czech Republic Asterix IV (PALS) France LMJ LULI2000 Russia ISKRA United Kingdom Vulcan
Non-laser
Applications
Thermonuclear weapon
Pure fusion weapon
International Fusion Materials Irradiation Facility ITER Neutral Beam Test Facility
Hellenica World - Scientific Library
Retrieved from "http://en.wikipedia.org/"
All text is available under the terms of the GNU Free Documentation License