[en] Recent JT-60U experimental results towards development of steady-state advanced tokamak scenario are presented with emphasis on extension of the operation regimes and improvement of physics understandings for the strong parameter linkage. Reduction of toroidal magnetic field ripple by installing ferritic steel tiles decreases the fast ion loss, and consequently enables to access the new regimes due to increase in net heating power and confinement improvement attributed to the reduction of counter toroidal rotation. High β_N (∼ 4.2) exceeding no wall ideal limit is achieved at l_i = 0.8-1 in the high β_p ELMy H-mode plasmas with a weak positive shear at the large volume configuration close to the wall, which had so far suffered from the large toroidal field ripple. The value of β_N reaches ideal wall limit, where RWM is suppressed by the plasma rotation. Small critical rotation velocity about 0.3% of Alfven velocity is found for suppressing RWM. High β_N·HH_98(y,2) of 2.2 with β_N ∼ 2.3 and HH_98(y,2) ∼ 1 is sustained for 23.1 s significantly longer than the current diffusion time (∼ 12 τ_R) in the high β_p ELMy H-mode plasmas. This duration is extended to the time scale for enhancement of recycling owing to the decrease in wall-pumping rate. Successful recycling and density control is demonstrated for ∼ 30 s in the enhanced recycling regime even with outgas from the wall by maximizing the divertor pumping in the high-density ELMy H-mode plasmas. With small effects of the toroidal field ripple reduction, parameter linkage is investigated in the reversed shear (RS) plasmas with high bootstrap current fraction (f_BS) of ∼ 0.7-1. In these plasmas, the duration is determined by ideal limit or slow ITB degradation in the linkage of current and pressure profiles. Real time q_min control is demonstrated with MSE diagnostics and LHCD at f_BS=0.46 among the strong parameter linkage. Physics studies also progress towards burning plasma control. The semi-global nature is observed in the ITB region both for high β_p mode and RS plasmas. Complete NTM suppression is demonstrated with misalignment of ECCD position less than about half of the island width. Fast ELM propagation to the main chamber wall is observed, and significant hydrogen retention in the main chamber wall is found. In the plasma-shadowed area underneath the divertor region, the averaged carbon deposition rate is significantly low, however, (H+D)/C retention rate is high (∼ 0.8). (author)