Engineering design of the National Spherical Torus Experiment
نویسندگان
چکیده
منابع مشابه
National Spherical Torus Experiment Liquid Lithium Divertor
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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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...
متن کاملImplementation of βN Control in the National Spherical Torus Experiment
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 ...
متن کاملStrike 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...
متن کاملThe confinement of dilute populations of beam ions in the national spherical torus experiment
Short ∼3 ms pulses of 80 keV deuterium neutrals are injected at three different tangency radii into the national spherical torus experiment. The confinement is studied as a function of tangency radius, plasma current (between 0.4 and 1.0 MA), and toroidal field (between 2.5 and 5.0 kG). The jump in neutron emission during the pulse is used to infer prompt losses of beam ions. In the absence of ...
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ژورنال
عنوان ژورنال: Fusion Engineering and Design
سال: 2001
ISSN: 0920-3796
DOI: 10.1016/s0920-3796(00)00469-5