A project to explore the quasi-poloidal approach to compact stellarators. Site includes project reports and reviews.

NCSX is a compact stellarator concept based on quasi-toroidal symmetry.

The world's largest magnetic confinement fusion experiment; it is based on the tokamak concept.

Korean Superconducting Tokamak Advanced Research. Fusion experiment based on the tokamak concept.

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.

The stellarator-spheromak is a fusion concept with elements of spherical stellarator and spheromak configurations.

Contains information about fusion experiments at the DIII-D National Fusion Facility in San Diego, California.

Device to expore the physics of plasma confinement in a magnetic dipole field.

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.

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.