Physics design of the National Spherical Torus Experiment

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The mission of the National Spherical Torus Experiment (NSTX) is to prove the principles of spherical torus physics by producing high-beta(t) plasmas that are noninductively sustained and whose current profiles are in steady state. The NSTX will be one of the first ultralow-aspect-ratio tori (R/a less than or equal to 1.3) to operate at high power (P-input up to 11 MW) to produce high-beta(t) (25 to 40%), low-collisionality, high-bootstrap-fraction (less than or equal to 70%) dis charges. Both radio-frequency and neutral beam heating and current drive will be employed Built into the NSTX is sufficient configurational flexibility to study a range of operating space and the resulting dependences of the confinement, micro- and magnetohydrodynamic stability, and particle- and power-handing properties. NSTX research will be carried out by a nationally based science team.
Publisher
AMER NUCLEAR SOCIETY
Issue Date
1999-07
Language
English
Article Type
Article
Keywords

LOW-Q DISRUPTIONS; HIGH-BETA; CONFINEMENT; TOKAMAKS; PLASMAS; DISCHARGES; STABILITY; ITER; PBX

Citation

FUSION TECHNOLOGY, v.36, no.1, pp.16 - 37

ISSN
0748-1896
URI
http://hdl.handle.net/10203/74135
Appears in Collection
NE-Journal Papers(저널논문)
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