QPS Project  
   A project to explore the quasi-poloidal approach to compact stellarators. Site includes project reports and reviews.
   http://qos.fed.ornl.gov/

JT-60 Project at JAERI Naka Fusion Research Establishment  
   JT-60 is the largest fusion tokamak experiment in Japan, and one of the largest in the world.
   http://www-jt60.naka.jaeri.go.jp/

National Compact Stellarator Experiment  
   NCSX is a compact stellarator concept based on quasi-toroidal symmetry.
   http://www.pppl.gov/ncsx

KSTAR  
   Korean Superconducting Tokamak Advanced Research. Fusion experiment based on the tokamak concept.
   http://www.knfp.net/

Consorzio RFX  
   A fusion energy experiment in Padova, Italy. RFX is a toroidal device where a ring of high temperature ionized gas (plasma) is confined by a magnetic field in the Reversed Field Pinch configuration.
   http://www.igi.pd.cnr.it/

Stellarator Spheromak  
   The stellarator-spheromak is a fusion concept with elements of spherical stellarator and spheromak configurations.
   http://www.highfactor.com/ssp

DIII-D Relational Database  
   Contains information about fusion experiments at the DIII-D National Fusion Facility in San Diego, California.
   http://d3dnff.gat.com/D3DRDB

Levitated Dipole Experiment  
   Device to expore the physics of plasma confinement in a magnetic dipole field.
   http://www.psfc.mit.edu/ldx

Large Helical Device (LHD)  
   The largest current fusion experiment based on the stellarator concept. Located at NIFS, Japan. The mission of the LHD project is to develop a scientific basis for stellarator fusion reactor. An important feature in the LHD design is a high magnetic field
   http://www.lhd.nifs.ac.jp/

ITER  
   A proposed international experimental fusion reactor based on the tokamak concept. ITER's mission is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes.
   http://www.iter.org

MAST  
   Mega Amp Spherical Tokamak experiment at Culham, UK.
   http://www.fusion.org.uk/mast/index.html

Spherical Stellarator  
   The SS is a low aspect ratio compact stellarator concept emphasizing effective use of the plasma (bootstrap) current to reach high plasma pressure operation and improved confinement. The concept is most advantageous at aspect ratios R/a < 3.5.
   http://www.highfactor.com/ss

TJII Flexible Heliac  
   Euratom-SIEMAT fusion experiment based on the heliac concept.
   http://www-fusion.ciemat.es/fusion/TJII/TJII.html

H-1NF  
   Australian fusion experiment based on the H-1 Heliac concept.
   http://wwwrsphysse.anu.edu.au/prl/H-1NF.html

START  
   Small Tight Aspect Ratio Tokamak fusion experiment at UKAEA Culham - it was a pioneering experiment based on the spherical tokamak concept. Operated 1991 - 1998. START's successor experiment is MAST.
   http://www.fusion.org.uk/culham/start.htm

Wendelstein 7-X  
   Large fusion experimental machine currently under construction in Greifswald, Germany; based on the large-aspect-ratio advanced stellarator concept.
   http://www.ipp.mpg.de/ipp/w7x.html

Helicity Injected Torus  
   HIT-II is the experiment to develop a method of coaxial helicity injection as a means of producing current drive. Built at the University of Washington.
   http://www.aa.washington.edu/AERP/HIT/hit.html

National Spherical Torus Experiment  
   NSTX is an experimental fusion device based on the spherical tokamak concept. Built at Princeton Plasma Physics Laboratory.
   http://www.pppl.gov/projects/pages/nstx.html

Madison Symmetric Torus  
   MST is a research device based on the reversed field pinch concept. Built at the University of Wisconsin-Madison. Operation began in 1988.
   http://sprott.physics.wisc.edu/mst.htm

IGNITOR  
   A proposed next-step fusion experiment to study burning plasma physics in a relatively small device. This approach is based on the concept of a tokamak with very strong magnetic field, and is under development by an international team of plasma and fusion
   http://www.frascati.enea.it/ignitor/

Sustained Spheromak Physics Experiment (SSPX)  
   Spheromak now operating at the Lawrence Livermore National Laboratory with a minor radius of 0.23m.
   http://www.mfescience.org/sspx

Compact Helical System (CHS)  
   Compact stellarator experiment with aspect ratio A ~ 5. Located at NIFS, Japan. Latest news and coming events.
   http://rd-w3server.nifs.ac.jp/chs/

HBT-EP Tokamak  
   Experiment at the Columbia University Plasma Physics Laboratory to demonstrate the feasibility of a high-beta tokamak stabilized by a combination of a close-fitting conducting wall, plasma rotation, and active feedback.
   http://www.seas.columbia.edu/apam/HBT-EP/

Fusion Ignition Research Experiment (FIRE)  
   A proposed next-step fusion experiment to study burning plasma physics based on the tokamak concept. It would require about $1.2B to build. The site includes information related to FIRE, its engineering design, related publications and meetings.
   http://fire.pppl.gov/fire_program.htm

Alcator C-Mod  
   A research fusion experiment utilizing the world's highest magnetic field tokamak plasma confinement concept.
   http://www.psfc.mit.edu/cmod

ASDEX Upgrade Fusion Experiment  
   Experimental tokamak facility at Max-Planck-Institut für Plasmaphysik, Germany.
   http://www.aug.ipp.mpg.de/aug.eng/

Compass-D  
   Highly flexible, medium-sized tokamak that has been specifically designed to address the key physics issues associated with magnetic confinement fusion. It plays a major role in the co-ordinated European fusion programme and is funded by the DTI and EURAT
   http://www.fusion.org.uk/culham/compass.htm

CASTOR  
   A fusion research facility (a tokamak) of the Academy of Sciences of The Czech Republic, Institute of Plasma Physics.
   http://www.ipp.cas.cz/WWW/

TFTR  
   The Tokamak Fusion Test Reactor experiment that was a large US fusion experiment directed by the Princeton Plasma Physics Lab. Stopped operation and decomissioned by 2000.
   http://www.pppl.gov/projects/pages/tftr.html

STX  
   Star Thrust Experiment at the University of Washington is an FRC (field reversed configuration) plasma startup experiment via application of a rotating magnetic field.
   http://www.aa.washington.edu/AERP/RPPL/programs/stx.html

TCS Experiment  
   The translation, confinement and sustainment FRC (field reversed configuration) experiment at the University of Washington.
   http://www.aa.washington.edu/AERP/RPPL/programs/tcs.html

FRC  
   An FRC (field reversed configuration) is a fusion concept where a toroidal plasma represents an elongated plasma ellipsoid conducting an azimuthal current which reverses the direction of an externally applied magnetic field.
   http://www.aa.washington.edu/AERP/RPPL/programs/frc_intro.html

Spheromak  
   The spheromak is a toroidal magnetic confinement concept where no toroidal magnetic field coils link the torus. The magnetic field is generated primarily by plasma currents.
   http://www-ferp.ucsd.edu/PUBLIC/AC-PANEL/REC-DOCS/W-PAPERS/spher.html

Tokamak ISTTOK  
   Tokamak plasma research experiment based at Instituto Superior Técnico (IST), Portugal.
   http://www.cfn.ist.utl.pt/Eng/index.html

Stellarator News  
   An international newsletter containing online publications on stellarators and links to some other stellarator web pages.
   http://www.ornl.gov/sci/fed/stelnews/

PEGASUS Toroidal Experiment  
   Extremely low-aspect-ratio tokamak experiment at the Department of Engineering Physics, University of Wisconsin-Madison.
   http://pegasus.ep.wisc.edu/