Of all approaches to controlled thermonuclear fusion the tokamak exper
iments have been most successful. Over the last decade particularly th
ree large devices have achieved plasma density, n, temperature, T, and
energy confinement time, tau(E), in ranges necessary for a fusion rea
ctor plasma. Such maximum values have, however, been obtained not yet
simultaneously but only in separate pulses, although the crucial tripl
e product, nTtau(E), has also been improved by several orders of magni
tude. The high temperatures sufficient in a fusion reactor can be prod
uced by injection of neutral atoms or by absorption of radio frequency
waves in the ion cyclotron frequency range. The plasma confinement (t
au(E) almost-equal-to 1s) is still not understood and is handled throu
gh empirical ''scaling laws''. Particle densities have usually been on
the low side (n less-than-or-equal-to 5 x 10(19) m-3) because increas
ed fuelling rates can easily lead to violent current disruptions. Prog
ress in obtaining peaked density profiles with pellet injection has le
d to high density plasmas without disruptions. Serious unsolved proble
ms concern the spoiling of the fusion rates by (nonhydrogenic) impurit
ies, the plasma parameter control over longer periods of time and inde
ed the plasma heating by fusion alpha-particles (''ignition, burning''
). The most urgent technological question refers to the lifetime of th
e first wall which is in direct contact with the plasma. An important
step towards ignition has been made by the recent JET/DT experiments i
n which, for the first time, the actual reactor fuel component tritium
has been used to produce neutrons. The ''next generation'' tokamak IT
ER is, at present, being planned and designed in a world-wide collabor
ative effort. It should be operating before the year 2010 and is inten
ded to investigate an ignited plasma burning for several minutes.