The goals of DIII-D advanced tokamak (AT) experiments are investigation and optimization of the upper limits of energy confinement and MHD stability in a tokamak plasma, and simultaneous maximization of the fraction of non-inductive current drive. Significant overall progresshas been made in the past two years, as the performance figure of merit βN H89P of 9 has beenachieved in ELMing H mode for over 16τE without sawteeth. The tokamak was also operated at βNH ≈ 7 for over 35 τE or 3τR, with the duration limited by the hardware. Real time feedback control of β (at 95% of the stability boundary), optimizing the plasma shape (e.g., δ, divertor strike and X points, double/single null balance) and particle control (ne/nGW ≈ 0.3, Zeff < 2.0) were necessary for thelong pulse results. A new quiescent double barrier (QDB) regime with simultaneous inner andedge transport barriers and no ELMs has been discovered with a βN H89P of 7. The QDB regime has been obtained to date only with counter NBI. Further modification andcontrol of internal transport barriers (ITBs) has also been demonstrated with impurity injection(broader barrier), pellets and ECH (strong electron barrier). The new Divertor-2000, a keyingredient in all these discharges, provides effective density, impurity and heat flux control in thehigh triangularity plasma shapes. Discharges at ne/nGW ≈ 1.4 have been obtained with gaspuffing by maintaining the edge pedestal pressure; this operation is easier with Divertor-2000.We are developing several other tools required for AT operation, including real time feedbackcontrol of resistive wall modes with external coils and control of neoclassical tearingmodes with ECCD.