Towards the ITER steady-state goal of Q=5, recent DIII-D/EAST joint experiments on high poloidal beta (βP) scenario development have demonstrated sustainment of excellent energy confinement quality (H98y2>1.5) via a large radius internal transport barrier (ITB) at high normalized beta (βN~3.5) and reactor-relevant q95~6.0 on DIII-D. This high normalized fusion performance ITB state with Greenwald density fraction near 100% and qmin≥3, is achieved with plasma toroidal rotation Vtor~0 at ρ≥0.6, a key result for a reactor where toroidal rotation is expected to be low. Experimental results also show that negative magnetic shear in the plasma core contributes to turbulence suppression and can compensate for reduced Shafranov shift to still access a large radius ITB and excellent confinement with low plasma rotation, consistent with results of gyrofluid transport simulations. In EAST, with the increased auxiliary heating and current drive capability, the operational regime has been extended (RF only: β_N ~1.5 and β_P~2.0; RF+NB : β_N ~2.0 and β_P~2.5). Using RF-only heating and current drive (lower hybrid LH, electron cyclotron EC, and ion cyclotron IC), EAST has achieved one hundred seconds steady state H-mode (H98y2~1.1) discharge at moderate βp~1.2 with actively cooled ITER-like mono-block tungsten divertor.