Magnetic

Sites 16

• 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.
• Joint European Torus (JET) The world's largest magnetic confinement fusion experiment. News, fusion basics, and scientific information. Culham, United Kingdom.
• 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.
• IGNITOR A proposed next-step fusion experiment to study burning plasma physics in a relatively small device.
• 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.
• 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.
• PEGASUS Toroidal Experiment Extremely low-aspect-ratio tokamak experiment at the Department of Engineering Physics, University of Wisconsin-Madison.
• Fusion Plasma Physics at KTH (Sweden) Plasma physics program at The Royal Institute of Technology (Kungliga Tekniska Högskolan).
• 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.
• QPS Project A project to explore the quasi-poloidal approach to compact stellarators. Project reports and reviews.
• Magnetic Confinement Fusion Article from Wikipedia on the generation of energy using magnetic fields to confine the fusion fuel in the form of a plasma.
• KSTAR Korean superconducting tokamak advanced research project is a superconducting tokamak facility for controlled fusion research. First plasma was obtained in 2008. One of the main goals is long-pulse non-inductive plasma heating and current drive.
• ISTTOK Tokamak Tokamak plasma research experiment based at Instituto Superior Técnico (IST), Portugal. Website includes tokamak description, photos, objectives, and physics program.
• Spherical Stellarator Describes the concept and its development.
• MAST Mega Amp Spherical Tokamak experiment at Culham, UK, with information on MAST research, its history and planned upgrades, as well as links to other fusion research experiments in Europe.
• The SST-1 Tokamak Steady State Superconducting Tokamak at the Institute for Plasma Research, Gugarat, India, has an objective of a steady-state operation via the RF and NBI plasma heating and current drive.