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Journal ArticleDOI

Engineering Design of the National Spherical Tokamak Experiment

TLDR
The National Spherical Tokamak Experiment (NSTX) as mentioned in this paper is an ultra low aspect ratio device with a plasma current of 1 MA, which is designed for an experimental pulse length that will demonstrate quasi-steady state non-inductively driven advanced tokamak operation.
Abstract
The National Spherical Tokamak Experiment (NSTX) is an ultra low aspect ratio device with a plasma current of 1 MA. The tokamak features auxiliary heating and current drive with a close-fitting conducting shell to maximize the plasma pressure. NSTX is designed for an experimental pulse length that will demonstrate quasi-steady state non-inductively driven advanced tokamak operation. The design also takes maximum advantage of existing facilities and components from previous Princeton devices to reduce the overall program costs.

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Journal ArticleDOI

Bootstrap current and neoclassical transport in tokamaks of arbitrary collisionality and aspect ratio

TL;DR: In this article, a multi-species fluid model is described for the steady state parallel and radial force balance equations in axisymmetric tokamak plasmas, and the bootstrap current, electrical resistivity and particle and heat fluxes are evaluated in terms of the rotation velocities and friction and viscosity coefficients.
Journal ArticleDOI

Computation of three-dimensional tokamak and spherical torus equilibria

TL;DR: In this paper, the ideal perturbed equilibrium code (IPEC) is applied to the study of the plasma response in a spherical torus to such external perturbations, and the results show that the IPEC can be applied to any tokamak configuration.
Journal ArticleDOI

Control of Asymmetric Magnetic Perturbations in Tokamaks

TL;DR: DIII-D and NSTX experiments find that when the deleterious effects of asymmetries are mitigated, the external asymmetric field was often made stronger and had an increased interaction with the magnetic field of the unperturbed equilibrium.
Journal ArticleDOI

Scintillator based energetic ion loss diagnostic for the National Spherical Torus Experiment

TL;DR: A scintillator based energetic ion loss detector has been built and installed on the National Spherical Torus Experiment (NSTX) to measure the loss of neutral beam ions.
Journal ArticleDOI

The prospects for electron Bernstein wave heating of spherical tokamaks

TL;DR: Darke et al. as discussed by the authors used an inhomogeneous plane slab model of the plasma with a sheared magnetic field to calculate the linear conversion of the ordinary mode (O-mode) to the extraordinary mode (X-mode).
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