Strike point control for the National Spherical Torus Experiment (NSTX)
نویسندگان
چکیده
منابع مشابه
Strike point control for the National Spherical Torus Experiment
This paper presents the first control algorithm for the innerand outer-strike point position for a Spherical Torus (ST) fusion experiment and the performance analysis of the controller. A liquid lithium divertor (LLD) will be installed on NSTX which is believed to provide better pumping than lithium coatings on carbon PFCs. The shape of the plasma dictates the pumping rate of the lithium by cha...
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The mission of the National Spherical Torus Experiment (NSTX) is the demonstration of the physics basis required to extrapolate to the next steps for the spherical torus (ST), such as a plasma facing component test facility (NHTX) or an ST based component test facility (ST-CTF), and to support ITER. Key issues for the ST are transport, and steady state high β operation. To better understand ele...
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The understanding of power balance is an important aspect of magnetic confinement. It is particularly important to understand loss mechanisms and transport. The inherently low toroidal field of low aspect ratio machines means that much of the analysis of standard aspect ratio devices must be modified. Typically, analyses of confinement and transport in large aspect ratio devices use the approxi...
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We have designed and constructed a system for control of the normalized β in the National Spherical Torus Experiment [M. Ono, et al., Nuclear Fusion 40, 557 (2000)]. A PID operator is applied to the difference between the present value of βN (from realtime equilibrium reconstruction) and a time-dependent request, in order to calculate the required injected power. This injected power request is ...
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Recent NSTX high power divertor experiments have shown significant and recurring benefits of solid lithium coatings on PFC’s to the performance of divertor plasmas in both Land Hmode confinement regimes heated by high-power neutral beams. The next step in this work is installation of a liquid lithium divertor (LLD) to achieve density control for inductionless current drive capability (e.g., abo...
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ژورنال
عنوان ژورنال: Nuclear Fusion
سال: 2010
ISSN: 0029-5515,1741-4326
DOI: 10.1088/0029-5515/50/10/105010