Phy.org - Science: Physics: Nuclear: Fusion: Magnetic

DescriptionThis category includes web pages related to magnetic confinement fusion.

Joint European Torus (JET) - The world's largest magnetic confinement fusion experiment; it is based on the tokamak concept.
Alcator C-Mod - A research fusion experiment utilizing the world's highest magnetic field tokamak plasma confinement concept.
ASDEX Upgrade Fusion Experiment - Experimental tokamak facility at Max-Planck-Institut für Plasmaphysik, Germany.
CASTOR - A fusion research facility (a tokamak) of the Academy of Sciences of The Czech Republic, Institute of Plasma Physics.
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 EURATOM, with additional support from EPSRC and various schemes for student grants.
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.
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.
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. Includes information related to FIRE, its engineering design, related publications and meetings.
Fusion Plasma Physics at KTH (Sweden) - Plasma physics program at The Royal Institute of Technology (Kungliga Tekniska Högskolan).
H-1NF - Australian fusion experiment based on the H-1 Heliac concept.
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.
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.
HSX - Helically Symmetric eXperiment is a university scale plasma experiment based on the large-aspect-ratio helically-symmetric stellarator approach. University of Wisconsin-Madison, USA.
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 physicists.
ISTTOK Tokamak - Tokamak plasma research experiment based at Instituto Superior Técnico (IST), Portugal.
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.
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.
KSTAR - Korean Superconducting Tokamak Advanced Research. Fusion experiment based on the tokamak concept.
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 of 3-4 Tesla produced by superconducting magnets.
Levitated Dipole Experiment - Device to expore the physics of plasma confinement in a magnetic dipole field.
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.
MAST - Mega Amp Spherical Tokamak experiment at Culham, UK.
National Compact Stellarator Experiment - NCSX is a compact stellarator concept based on quasi-toroidal symmetry.
National Spherical Torus Experiment - NSTX is an experimental fusion device based on the spherical tokamak concept. Built at Princeton Plasma Physics Laboratory.
PEGASUS Toroidal Experiment - Extremely low-aspect-ratio tokamak experiment at the Department of Engineering Physics, University of Wisconsin-Madison.
QPS Project - A project to explore the quasi-poloidal approach to compact stellarators. Project reports and reviews.
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.
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.
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.
Stellarator News - An international newsletter containing online publications on stellarators and links to some other stellarator web pages.
Stellarator Spheromak - The stellarator-spheromak is a fusion concept with elements of spherical stellarator and spheromak configurations.
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.
SUNIST - The first spherical tokamak in China. Built at the Department of Engineering Physics, Tsinghua University, Beijing.
Sustained Spheromak Physics Experiment (SSPX) - Spheromak now operating at the Lawrence Livermore National Laboratory with a minor radius of 0.23m.
TCS Experiment - The translation, confinement and sustainment FRC (field reversed configuration) experiment at the University of Washington.
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.
The SST-1 Tokamak - The Steady State Tokamak (SST-1) is under fabrication at the Institute for Plasma Research in India. SST-1 has superconducting TF and PF coils capable of producing a toroidal magnetic field of up to 3T. The goals include reaching the plasma pulse duration of up to 1000 seconds. Plasma heating and current drive will be provided by ICRH, NBI and LHCD. The project started in 1994.
TJII Flexible Heliac - Euratom-SIEMAT fusion experiment based on the heliac concept.
Unofficial ITER Fan Club - A community of people interested in International Thermonuclear Experimental Reactor. We keep track of news, links and publications about ITER and fusion energy in general.
Wendelstein 7-X - Large fusion experimental machine currently under construction in Greifswald, Germany; based on the large-aspect-ratio advanced stellarator concept.

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