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Studies the properties of a reference quasi-axisymmetric plasma configuration. Features of stellarators and advanced tokamaks; Evaluation of quasi-omnigeneous plasma configurations stable to ballooning modes; Economic benefits of steady-state magnetic confinement systems for magnetic fusion energy power plants.

Describes a multi-species fluid model for the steady state parallel and radial force balance equations in axisymmetric tokamak plasmas. Steady state force balance model; Reduced charge state solution; Current and resistivity; Particle and heat fluxes; Local flow velocities.

This paper reviews the status of methods used to analyze local transport of particles, energy, and angular momentum in plasmas contained in toroidal fusion devices. The standard technique at present is based on determination of particle, energy, and momentum fluxes through analysis based on measured profiles of density, temperature and angular rotation speed and on calculation of all sources of particles, energy, and momentum. Recent experiments have also been done using perturbations of local density, temperature, or angular rotation speed caused by modulating the input sources. The local transport information is then extracted from the time history of the perturbations. These two techniques are contrasted and the strengths of each are discussed in this paper. Recommendations for further work needed to make progress in understanding transport are also given. [ABSTRACT FROM AUTHOR]

This paper describes the between shots data analysis on TFTR using the one-dimensional equilibrium kinetic analysis code SNAP. SNAP accepts as input data: the measured plasma size and current, toroidal field, surface voltage, plasma composition (total Z[sub eff] and Z[sub eff] contribution from metallic impurities), edge neutral density, auxiliary heating power data (neutral beam power, energy, injection geometry and/or rf power and frequency), and measured profiles of T[sub e](R), n[sub e](R), T[sub i](R), V[sub φ](R), and P[sub rad](R). SNAP iteratively calculates: (1) the mapping of profile data to a minor radius grid, (2) the magnetic topology including Shafranov shifted circular flux surfaces, (3) neutral beam attenuation and deposition profiles, (4) unthermalized beam ion density and beam power density delivered to thermal plasma species from a numerical solution to the Fokker-Planck equation, (5) the neutral density profile, (6) local heat and particle transport coefficients consistent with the measured profiles and calculated source terms, (7) ICRF power profiles from a reduced order full wave analysis and isotropic Stix quasilinear model, and (8) total neutron emissivity and plasma stored energy. Several ion heat transport models (including neoclassical χ[sub i] and χ[sub i] ∝ χ[sub e]) are available to calculate an expected T[sub i](r) profile in the absence of measurements. [ABSTRACT FROM AUTHOR]