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National Compact Stellarator Experiment

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The National Compact Stellarator Experiment (NCSX) is a plasma confinement experiment being conducted at the Princeton Plasma Physics Laboratory. First plasma is scheduled to take place in July 2009. It is a variation of the stellarator concept, with a much lower aspect ratio than a typical stellerator. NCSX is one of the first fusion experiments to use massively parallel computing to find the optimal shape for the reactor vessel; one of the advantages of correctly-designed stellerators is that the confined plasma is passively stable when a steady magnetic field is applied, whereas tokamaks require an array of active control strategies to stabilise the plasma, even under a constant magnetic field. Up to 12MW of auxiliary heating power will be available to the NCSX chamber, consisting of 6MW from tangential neutral-beam injection, and 6MW from radio-frequency (RF) heating. Up to 3MW of electron cyclotron heating may also be available in future iterations of the design.


Atomic nucleus | Nuclear fusion | Nuclear power | Nuclear reactor | Timeline of nuclear fusion
Plasma physics | Magnetohydrodynamics | Neutron flux | Fusion energy gain factor | Lawson criterion
Methods of fusing nuclei
Fusion experiments

Magnetic confinement devices
ITER (International) | JET (European) | JT-60 (Japan) | Large Helical Device (Japan) | EAST (China) | T-15 (Russia) | DIII-D (USA) | TFTR (USA) | NSTX (USA) | NCSX (USA) | Alcator C-Mod (USA) | LDX (USA) | PACER (USA) | H-1NF (Australia) | MAST (UK) | START (UK) | DEMO (Commercial)


Inertial confinement devices
NIF (USA) | Nova laser (USA) | OMEGA laser (USA) | Shiva laser (USA)
Z machine (USA)
See also: International Fusion Materials Irradiation Facility

External link

 


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