The capabilities of JET can advance experience and understanding in
many areas essential to ITER:
-
due to its unique tritium handling capability, JET can actually
study plasmas with a high rate of Deuterium-Tritium (D-T) fusion
reactions (commonly known as "burning plasmas")
-
due to the size of JET, it is the best suited facility to study
the confinement of the fusion products, the fast alpha particles.
The fast alpha particles have to be sufficiently confined in order
to transfer their kinetic energy to other plasma particles (and thus
maintain extreme plasma temperatures), but if they're too confined,
they hamper the fusion process by dissolving the D-T fuel and increasing
plasma radiation losses. At JET, we can produce fast alphas either
in D-T fusion, or by their acceleration in plasmas on special radiofrequency
waves.
-
JET provides key contributions to the material studies and plasma-wall
interaction studies due to JET's unique beryllium handling capability
(beryllium being the design choice for the ITER first wall, i.e.
the plasma facing material)
-
JET extends experience of in-vessel remote handling techniques,
based on its comprehensive Remote Handling facility (see Fig. 1 & 2).
Ongoing experimental studies on JET provide detailed groundwork for
ITER operations. These include further optimisation of the "basic" operating
scenario and development of "advanced" scenarios with a potential
for increased fusion performance and steady state operation. An important
part of this work is devoted to the development of extensive real-time
control and powerful heating
systems, and to the development of new plasma diagnostics and heating
schemes. JET plays a dominant role in the international tokamak database
that is used for
extrapolations to ITER (see scaling
laws), with data closest to the ITER working point. In addition, the JET
experimental programme allows continuous benchmarking in order to develop an
integrated set of modelling
tools for the preparation and analysis of ITER experiments.
In 2004/2005 JET underwent numerous enhancements;
notably a new JET divertor configuration has been set up, able to accommodate
plasmas of an ITER-like shape at high currents (3.5-4 MA), and new
neutron and alpha diagnostics tools as well as numerous devices for studies
of
plasma-wall
interactions
have been installed. A new high-power ITER-like Ion Cyclotron Resonant
Heating antenna is under construction.
As a part of the "JET programme in support of ITER" proposed
for 2005-2010,
three major projects for upgrading JET were recently approved and launched.
They are the "ITER-like wall", the "Neutral Beam Enhancement" and
the "High Frequency Pellet Injector". Design work has started
and calls for tenders are being made, with installation foreseen in
2008. |
Fig. 1 Controlling the Mascot Remote Handling Manipulator
Fig. 2 Inside the torus, showing the Mascot Remote Handling Manipulator on the end of the boom, during the Remote Tile Exchange phase in 1996
|