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- National_Spherical_Torus_Experiment abstract "The National Spherical Torus Experiment (NSTX) is an innovative magnetic fusion device based on the spherical tokamak concept. It was constructed by the Princeton Plasma Physics Laboratory (PPPL) in collaboration with the Oak Ridge National Laboratory, Columbia University, and the University of Washington at Seattle.The spherical tokamak is an offshoot of the conventional tokamak design. Proponents claim that it has a number of practical advantages over these devices, some of them dramatic. For this reason the ST has seen considerable interest since it was introduced in the late 1980s. However, development remains effectively one generation behind mainline efforts like JET. Other major experiments in the field include the pioneering START and MAST at Culham in the UK.First plasma was obtained on NSTX on Friday, February 12, 1999 at 6:06 p.m. NSTX is being used to study the physics principles of spherically shaped plasmas—hot ionized gases in which nuclear fusion will occur under the appropriate conditions of temperature and density, which are produced by confinement in a magnetic field.Magnetic fusion experiments use plasmas composed of one or more of the isotopes of hydrogen. For example, in 1994, PPPL's Tokamak Fusion Test Reactor (TFTR) produced a world-record 10.7 megawatts of fusion power from a plasma composed of equal parts of deuterium and tritium, the fuel mix likely to be used in commercial fusion power reactors. NSTX is a "proof of principle" experiment and therefore employs deuterium plasmas only. If successful it will be followed by similar devices, eventually including a demonstration power reactor, burning deuterium-tritium fuel.NSTX produces a plasma that is shaped like a sphere with a hole through its center (a "cored apple" profile; see MAST), different from the doughnut-shaped (toroidal) plasmas of conventional tokamaks. The low aspect ratio A (that is, an R/a of 1.31, with the major radius R of 0.85 m and the minor radius a of 0.65 m) experimental NSTX device has several advantages including plasma stability through improved confinement, but requires a very careful design of the toroidal and poloidal field coils, vacuum vessels and plasma-facing components. Moreover, this innovative plasma configuration has the advantage of being able to confine a higher pressure plasma than a doughnut tokamak of high aspect ratio for a given, confinement magnetic field strength. Since the amount of fusion power produced is proportional to the square of the plasma pressure, the use of spherically shaped plasmas could allow the development of smaller, more economical and more stable fusion reactors. NSTX's attractiveness may be further enhanced by its ability to trap in a high "bootstrap" electric current. This self-driven internal plasma current would reduce the power requirements of externally driven plasma currents required to heat and confine the plasma.".
- National_Spherical_Torus_Experiment thumbnail NSTX.jpg?width=300.
- National_Spherical_Torus_Experiment wikiPageExternalLink nstxschem.gif.
- National_Spherical_Torus_Experiment wikiPageExternalLink nstx.pppl.gov.
- National_Spherical_Torus_Experiment wikiPageExternalLink nstx.
- National_Spherical_Torus_Experiment wikiPageID "4365438".
- National_Spherical_Torus_Experiment wikiPageLength "4234".
- National_Spherical_Torus_Experiment wikiPageOutDegree "21".
- National_Spherical_Torus_Experiment wikiPageRevisionID "606280502".
- National_Spherical_Torus_Experiment wikiPageWikiLink Ampere.
- National_Spherical_Torus_Experiment wikiPageWikiLink Category:Plasma_physics.
- National_Spherical_Torus_Experiment wikiPageWikiLink Category:Tokamaks.
- National_Spherical_Torus_Experiment wikiPageWikiLink Columbia_University.
- National_Spherical_Torus_Experiment wikiPageWikiLink Deuterium.
- National_Spherical_Torus_Experiment wikiPageWikiLink Joint_European_Torus.
- National_Spherical_Torus_Experiment wikiPageWikiLink Magnetic_confinement_fusion.
- National_Spherical_Torus_Experiment wikiPageWikiLink Magnetic_fusion_energy.
- National_Spherical_Torus_Experiment wikiPageWikiLink Mega_Ampere_Spherical_Tokamak.
- National_Spherical_Torus_Experiment wikiPageWikiLink Megaampere.
- National_Spherical_Torus_Experiment wikiPageWikiLink Megawatt.
- National_Spherical_Torus_Experiment wikiPageWikiLink Oak_Ridge_National_Laboratory.
- National_Spherical_Torus_Experiment wikiPageWikiLink Plasma_(physics).
- National_Spherical_Torus_Experiment wikiPageWikiLink Princeton_Plasma_Physics_Laboratory.
- National_Spherical_Torus_Experiment wikiPageWikiLink Small_Tight_Aspect_Ratio_Tokamak.
- National_Spherical_Torus_Experiment wikiPageWikiLink Spherical_tokamak.
- National_Spherical_Torus_Experiment wikiPageWikiLink TFTR.
- National_Spherical_Torus_Experiment wikiPageWikiLink Tesla_(unit).
- National_Spherical_Torus_Experiment wikiPageWikiLink Tokamak.
- National_Spherical_Torus_Experiment wikiPageWikiLink Tokamak_Fusion_Test_Reactor.
- National_Spherical_Torus_Experiment wikiPageWikiLink Tritium.
- National_Spherical_Torus_Experiment wikiPageWikiLink University_of_Washington.
- National_Spherical_Torus_Experiment wikiPageWikiLink Watt.
- National_Spherical_Torus_Experiment wikiPageWikiLinkText "NSTX".
- National_Spherical_Torus_Experiment wikiPageWikiLinkText "National Spherical Torus Experiment".
- National_Spherical_Torus_Experiment current "1.4".
- National_Spherical_Torus_Experiment field "0.3".
- National_Spherical_Torus_Experiment hasPhotoCollection National_Spherical_Torus_Experiment.
- National_Spherical_Torus_Experiment heating "11.0".
- National_Spherical_Torus_Experiment imagetitle "NSTX".
- National_Spherical_Torus_Experiment majorRadius "0.85 m".
- National_Spherical_Torus_Experiment minorRadius "0.68 m".
- National_Spherical_Torus_Experiment name "NSTX".
- National_Spherical_Torus_Experiment operation "1999".
- National_Spherical_Torus_Experiment type Spherical_tokamak.
- National_Spherical_Torus_Experiment wikiPageUsesTemplate Template:Cite_web.
- National_Spherical_Torus_Experiment wikiPageUsesTemplate Template:Fusion_devices.
- National_Spherical_Torus_Experiment wikiPageUsesTemplate Template:Fusion_experiments.
- National_Spherical_Torus_Experiment subject Category:Plasma_physics.
- National_Spherical_Torus_Experiment subject Category:Tokamaks.
- National_Spherical_Torus_Experiment hypernym Device.
- National_Spherical_Torus_Experiment type Device.
- National_Spherical_Torus_Experiment type Astrophysic.
- National_Spherical_Torus_Experiment type Physic.
- National_Spherical_Torus_Experiment type Reactor.
- National_Spherical_Torus_Experiment comment "The National Spherical Torus Experiment (NSTX) is an innovative magnetic fusion device based on the spherical tokamak concept. It was constructed by the Princeton Plasma Physics Laboratory (PPPL) in collaboration with the Oak Ridge National Laboratory, Columbia University, and the University of Washington at Seattle.The spherical tokamak is an offshoot of the conventional tokamak design. Proponents claim that it has a number of practical advantages over these devices, some of them dramatic.".
- National_Spherical_Torus_Experiment label "National Spherical Torus Experiment".
- National_Spherical_Torus_Experiment sameAs آزمایش_ملی_چنبره_کروی.
- National_Spherical_Torus_Experiment sameAs National_Spherical_Torus_Experiment.
- National_Spherical_Torus_Experiment sameAs NSTX.
- National_Spherical_Torus_Experiment sameAs m.0bzck6.
- National_Spherical_Torus_Experiment sameAs Q3873195.
- National_Spherical_Torus_Experiment sameAs Q3873195.
- National_Spherical_Torus_Experiment wasDerivedFrom National_Spherical_Torus_Experiment?oldid=606280502.
- National_Spherical_Torus_Experiment depiction NSTX.jpg.
- National_Spherical_Torus_Experiment homepage nstx.pppl.gov.
- National_Spherical_Torus_Experiment isPrimaryTopicOf National_Spherical_Torus_Experiment.