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Numerical Transport Codes

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TLDR
The relevant equations that are used in these codes are established, and on the basis of these equations, the necessary calculations needed to resolve them are pointed out.
Abstract
This paper gives a brief introduction on numerical transport codes. The relevant equations which are used in these codes are established, and on the basis of these equations, the necessary calculations needed to resolve them are pointed out. Finally, some examples are given, illustrating their application.

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Fusion nuclear science facilities and pilot plants based on the spherical tokamak

TL;DR: Menard et al. as mentioned in this paper developed a blanket system capable of tritium breeding ratio TBR ≈ 1, a poloidal field coil set supporting high elongation and triangularity for a range of internal inductance and normalized beta values consistent with NSTX/NSTX-U previous/planned operation, and a long-legged divertor analogous to the MAST-U divertor which substantially reduces projected peak divertor heat-flux and has all outboard field coils outside the vacuum chamber and superconducting to reduce power consumption.
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Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations

TL;DR: A new beamlet-based neutral beam ionization model called BBNBI, which takes into account the fine structure of the injector, follows the injected neutrals until ionization, and generates a source ensemble of ionized NBI test particles for slowing down calculations, is introduced.
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Orchestrating TRANSP Simulations for Interpretative and Predictive Tokamak Modeling with OMFIT

TL;DR: By using OMFIT to orchestrate the steps for experimental data preparation, selection of operating mode, submission, postprocessing, and visualization, the usage of TRANSP is streamlined and standardized.
References
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Journal ArticleDOI

Reconstruction of current profile parameters and plasma shapes in tokamaks

TL;DR: In this paper, an efficient method is given to reconstruct the current profile parameters, the plasma shape, and a current profile consistent with the magnetohydrodynamic equilibrium constraint from external magnetic measurements, based on a Picard iteration approach.
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Theory of plasma transport in toroidal confinement systems

TL;DR: A review of magnetized-plasma transport theory can be found in this paper, with a focus on the application to axisymmetric tokamak-type confinement systems.
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Equilibrium analysis of current profiles in tokamaks

TL;DR: In this paper, an efficient method is given for self-consistent reconstruction of the tokamak current profiles and their associated magnetic topology using the magnetohydrodynamic (MHD) equilibrium constraint from external magnetic measurements, kinetic profile measurements, internal poloidal magnetic field measurements, and topological information from soft X-ray (SXR) measurements.
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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.
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New techniques for calculating heat and particle source rates due to neutral beam injection in axisymmetric tokamaks

TL;DR: In this paper, a set of numerical techniques for calculating heat and particle source rates due to neutral beam injection in axisymmetric tokamaks is described, taking into account a number of significant, and normally neglected, effects.
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