ITER-like Wall Project |
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One of the main challenges for fusion reactors is the compatibility
between a reactor-grade plasma and the materials facing the plasma
(the "First Wall"). Most current tokamaks (including JET) use carbon
composite (CFC) tiles for the First Wall, as does the Space Shuttle, which use
it on the wings to withstand extreme heat fluxes. However, from JET's D-T experiments
it is obvious that carbon composites are not suitable for the tritium operation
due to high carbon migration, leading to tritium deposition in walls. Therefore
the ITER design comprises a beryllium-clad First Wall in the main chamber, while
use of carbon tiles is limited to the region where the edge plasma is deflected
on to the wall
("divertor strike points") and tungsten tiles are to be used elsewhere
on the divertor (see areas marked Be, C and W in Fig. 1). Tungsten
is very resistant to high temperatures (melting only at 3695 degrees Celsius)
but it is a heavy element (proton number 74) that can pollute plasmas considerably:
it gets highly ionised in extreme plasma temperatures which causes immense energy
losses due to plasma radiation, and dilutes the D-T fuel. Beryllium is a light
element with a proton number just 4. However it melts at just 1284 degree Celsius.
The combination of beryllium and tungsten has never been tested in a tokamak,
let alone in one with ITER-relevant geometry and plasma parameters like JET.
During the one year installation period in 2008, extensive use of Remote
Handling technology will be made in implementing the beryllium first
wall and tungsten divertor. Following installation, the JET experimental
programme will focus on optimising operating scenarios compatible with
the ITER-like wall. The level of retained tritium and its dependence
on plasma parameters will be determined. Plasma performance will be tested
to show that the level of tungsten reaching the core is acceptably low.
The lifetime of the wall will be studied with ITER-relevant power loading
provided by increased heating due to Neutral Beam Enhancement Project.
Also notice the synergy in the pan-European fusion research: while ASDEX
Upgrade tokamak (Association Euratom-IPP Garching, Germany) is exploring
the viability of an all-Tungsten first wall (tungsten is considered the
long-term front runner as a material for fusion reactors), JET will be
looking at more immediate ITER needs. |
Fig. 1 ITER wall and two options for
JET's ITER-like Wall Project (to scale)
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