A. Sykes

TL;DR: The first six months of MAST operations have been remarkably successful as discussed by the authors, with a plasma current of over 1 MA with central plasma temperatures (ohmic) of order 1 keV.

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.

Abstract: Values of ${\ensuremath{\beta}}_{T}\ensuremath{\ge}30%$ have been achieved and sustained for several confinement times on the START spherical tokamak using additional heating provided by neutral beam injection. These values are more than twice the highest value previously obtained in a tokamak, and correspond to normalized $\ensuremath{\beta}$ values of ${\ensuremath{\beta}}_{N}\ensuremath{\ge}4$. In these shots values of ${I}_{p}g{I}_{\mathrm{rod}}$ (where ${I}_{\mathrm{rod}}$ is the current flowing in the central toroidal field rod) have been obtained, which are considered to be necessary for spherical tokamak power plant. The results are compared with ideal-MHD stability theory.

TL;DR: Tokamak Energy Ltd, UK, developed spherical tokamaks using high temperature superconductor magnets as a possible route to fusion power using relatively small devices as discussed by the authors, and presented an overview of the development programme including details of the enabling technologies, the key modelling methods and results, and the remaining challenges on the path to compact fusion.

TL;DR: In this article, a combination of state-of-the-art imaging and profile diagnostics, together with established plasma simulation codes, are providing for the first time on Mega Ampere Spherical Tokamak (MAST) the tools required for studying confinement and transport, from the core through to the plasma edge and scrape-off-layer (SOL).