High-performance experiments with the aim of establishing a physics ba
sis for advanced steady-state tokamak reactors have been carried out i
n JT-60U using two approaches; high-beta(p) H-mode and reversed-shear
mode. In the high-beta(p) H-mode, where an internal transport barrier
(ITB) formed in the positive-shear region is combined with an edge-tra
nsport barrier (H-mode), a quasi-steady state with the ELMy H-mode edg
e has been obtained through pressure profile control and its beta limi
t has been improved by increasing the plasma triangularity, delta. In
the reversed-shear mode, a radially localized ITB including a clear el
ectron-temperature pedestal is formed in the negative-shear region and
very high confinement is obtained; H factors up to 3.3 have been achi
eved with an L-mode edge. The location of the ITB was well correlated
to the location of q(min). Clear electron-and ion-temperature pedestal
s were sustained with a small density gradient in the combined heating
experiments with ICRF + NBI. Large confinement improvement resulted f
rom the large radius of the ITB and that of q(min) in the low q(min) r
egion (q(min) similar to 2). The performance was limited by disruptive
beta collapses with B-N similar to 2 and q(min) similar to 2 and no s
teady-state was attained. The fusion performance was enhanced with the
plasma current and the highest performance was achieved at 2.8 MA (q(
95) = 3.1); Q(DT)(eq) = 1.05, tau(E) =0.97 s, n(D)(0) = 4.9 x 10(19) m
(-3) and T-i(0) = 16.5 keV. Optimization of both regimes will be conti
nued, especially on the non-inductive current drive fraction and parti
cle and heat control in the radiative divertor, using the negative-ion
-based NBI and a newly installed W-shaped divertor.