This paper presents an overview of results of the 1994/95 experimental
campaign on JET with the new pumped divertor and draws implications f
or ITER in the areas of detached and radiative divertor plasmas, the u
se of beryllium as a divertor target tile material, the confinement pr
operties of discharges with the same dimensionless parameters (except
for the dimensionless Larmor radius) as ITER and the effect of varying
the toroidal magnetic field ripple in the ITER relevant range. Discha
rges with high fusion performance at high current, in steady-state wit
h ELMs and in the ELM-free hot-ion H-mode, are also reported. Limits t
o operations are discussed and projections to D-T performance are made
.