Recent experiments on DIII-D have demonstrated the ability to sustain plasma conditions that integrate and sustain the key ingredients of Advanced Tokamak (AT) operation: high beta with q(sub min) greater than 1, good energy confinement, and high current drive efficiency. Utilizing off-axis (p=0.4) electron cyclotron current drive (ECCD) to modify the current density profile in a plasma operating near the no-wall ideal stability limit with q(sub min) greater than 2, plasmas with beta approximately 2.9% and 90% of the plasma current driven non-inductively have been sustained for nearly 2 s limited only by the duration of the ECCD pulse. Separate experiments have demonstrated the ability to sustain a steady current density profile using ECCD for periods as long as 1 s with beta equals 3.3% and greater than 90% of the current driven non-inductively.