Abstract. Results of studies towards steady state operation of an advanced tokamak accompanied by an internal transport barrier (ITB) concerning fusion relevant conditions on JT-60U are presented. The major results are; 1) High confinement improvement at high normalized density regime which is expected in the ITER steady state operational scenario was obtained in a reversed magnetic shear (RS) plasma under full non inductive current drive (CD). In the discharge, capability of active current profile control was also demonstrated. 2) Influence of dominant electron heating, or Te/Ti > 1 condition, on the ITB was investigated, and it was found that in RS plasmas the confinement improvement by the ITBs could be maintained. On the other hand, it was found that the Ti ITB could be degraded by dominant electron heating. These results have been obtained utilizing a variety of heating/CD systems, positive/negative-ion based (P/N-) NB, ECRF, LHRF, ICRF, equipped on JT-60U. They enable to explore reactor relevant regime in which electron heating by alpha particles is dominant.