Dennis J Strickler

TL;DR: The spherical torus is a very small aspect ratio (A 2 ) characterized by high toroidal beta (βt > 0.2), low poloidal β (βp 1.5), and strong magnetic helical pitch (Θ comparable to F).

TL;DR: The National Compact Stellarator Experiment (NCSX) as discussed by the authors was designed to enhance the magnetohydrodynamic (MHD) stability without feedback or nearby conducting structures and provide drift-orbit confinement similar to tokamaks.

TL;DR: In this paper, the authors present a design concept that allows straight-line access via remote handling to all activated fusion core components and present a system code that combines the key required plasma and engineering science conditions of CTF.

TL;DR: In this paper, the magnetic field modulus |B| in magnetic co-ordinates is dominated by poloidally symmetric components and two distinct configuration types are considered: (1) those that achieve their drift optimization and rotational transform at low β and low bootstrap current by appropriate plasma shaping; and (2) those which have a greater reliance on plasma β and bootstrap currents for supplying the transform and obtaining quasi-poloidal symmetry.

TL;DR: The National Spherical Torus Experiment (NSTX) as discussed by the authors is one of the first ultra low a[P(input) up to 11 MW] in order to produce high-beta toroidal (25 to 40%), low collisionality, high bootstrap fraction (less than or equal to 70%) discharges.