Magnetic Fusion Nuclear

Magnetic

This category includes web pages related to magnetic confinement fusion.

• - Tokamak plasma research experiment based at Instituto Superior Técnico (IST), Portugal.
  
• - 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
  
• - Device to expore the physics of plasma confinement in a magnetic dipole field.
  
• - The translation, confinement and sustainment FRC (field reversed configuration) experiment at the University of Washington.
  
• - JT-60 is the largest fusion tokamak experiment in Japan, and one of the largest in the world.
  
• - Mega Amp Spherical Tokamak experiment at Culham, UK.
  
• - 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
  
• - MST is a research device based on the reversed field pinch concept. Built at the University of Wisconsin-Madison. Operation began in 1988.
  
• - 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
  
• - Korean Superconducting Tokamak Advanced Research. Fusion experiment based on the tokamak concept.
  
• - 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.
  
• - Compact stellarator experiment with aspect ratio A ~ 5. Located at NIFS, Japan. Latest news and coming events.
  
• - Australian fusion experiment based on the H-1 Heliac concept.
  
• - Spheromak now operating at the Lawrence Livermore National Laboratory with a minor radius of 0.23m.
  
• - 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.
  
• - 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.
  
• - Star Thrust Experiment at the University of Washington is an FRC (field reversed configuration) plasma startup experiment via application of a rotating magnetic field.
  
• - NCSX is a compact stellarator concept based on quasi-toroidal symmetry.
  
• - 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.
  
• - Euratom-SIEMAT fusion experiment based on the heliac concept.
  
• - 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.
  
• - An international newsletter containing online publications on stellarators and links to some other stellarator web pages.
  
• - Experimental tokamak facility at Max-Planck-Institut für Plasmaphysik, Germany.
  
• - 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.
  
• - Large fusion experimental machine currently under construction in Greifswald, Germany; based on the large-aspect-ratio advanced stellarator concept.
  
• - 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.
  
• - A fusion research facility (a tokamak) of the Academy of Sciences of The Czech Republic, Institute of Plasma Physics.
  
• - The stellarator-spheromak is a fusion concept with elements of spherical stellarator and spheromak configurations.
  
• - NSTX is an experimental fusion device based on the spherical tokamak concept. Built at Princeton Plasma Physics Laboratory.
  
• - The Steady State Tokamak (SST-1) is under fabrication at the Institute for Plasma Research in India.
  
• - Contains information about fusion experiments at the DIII-D National Fusion Facility in San Diego, California.
  
• - 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.
  
• - A research fusion experiment utilizing the world's highest magnetic field tokamak plasma confinement concept.
  
• - 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.
  
• - A project to explore the quasi-poloidal approach to compact stellarators. Site includes project reports and reviews.
  
• - Extremely low-aspect-ratio tokamak experiment at the Department of Engineering Physics, University of Wisconsin-Madison.
  
• - The first spherical tokamak in China. Built at the Department of Engineering Physics, Tsinghua University, Beijing.
  
• - 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.
  
  

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