Confinement in START beam heated discharges

摘要

Plasma profile data, from a number of neutral beam heated discharges in the START spherical tokamak, have been exploited for transport analysis over a wide range of β(where β = 2μop/B~2, μo is the permeability of free space, P is plasma pressure, and B is toroidal magnetic field strength). Magnetic equilibrium reconstructions, and Monte Carlo calculations of the neutral beam heat and particle sources, are incorporated in a particle and power balance code to extract the thermal diffusivities.