Non-inductively driven tokamak plasmas at near-unity βt in the Pegasus toroidal experiment

A major goal of the spherical tokamak (ST) research program is accessing a state of low internal inductance li, high elongation κ, and high toroidal and normalized beta ( βt and βN) without solenoidal current drive. Local helicity injection (LHI) in the Pegasus ST [Garstka et al., Nucl. Fusion 46, S603 (2006)] provides non-solenoidally driven plasmas that exhibit these characteristics. LHI utilizes compact, edge-localized current sources for plasma startup and sustainment. It results in hollow current density profiles with low li. The low aspect ratio ( R0/a∼1.2) of Pegasus allows access to high κ and high normalized plasma currents ( IN=Ip/aBT>14). Magnetic reconnection during LHI provides auxiliary ion heating. Together, these features provide access to very high βt plasmas. Equilibrium analyses indicate that βt up to ∼100% is achieved. These high βt discharges disrupt at the ideal no-wall β limit at βN∼7.