Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione
Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione
Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione
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technology programme (cont’d.)<br />
progress report<br />
2010<br />
057<br />
3.1 Divertor, First Wall, Vacuum Vessel and Shield<br />
Manufacturing technology for the ITER inner vertical target<br />
<strong>ENEA</strong> has been deeply involved in the ITER R&D activities for the manufacturing of high heat flux<br />
plasma–facing components, and in particular for the inner vertical target (IVT) of the ITER <strong>di</strong>vertor.<br />
This component has to be manufactured by using both armour and structural materials whose properties are<br />
defined by ITER. Their physical properties prevent standard joining techniques from being applied. The<br />
reference armour materials are tungsten and carbon/carbon fibre composite (CFC), and, for the cooling pipe,<br />
a copper alloy (CuCrZr).<br />
During the last years <strong>ENEA</strong>, in collaboration with Ansaldo, has been manufacturing several actively cooled<br />
mock–ups and prototypical components of <strong>di</strong>fferent length, geometry and materials, by using innovative<br />
processes: hot ra<strong>di</strong>al pressing (HRP) and pre–brazed casting (PBC).<br />
The optimization of the processes started from the successful manufacturing of both W and CFC small scale<br />
mockups and successful testing in the worst ITER operating con<strong>di</strong>tion (20 MW/m 2 ) through the achievement<br />
of record performances obtained from a me<strong>di</strong>um scale IVT CFC and W armoured mockup: after ITER<br />
relevant heat flux fatigue testing (20 MW/m 2 for 2000 cycles CFC part, 15 MW/m 2 for 2000 cycles W part)<br />
it reached a critical heat flux of 35 MW/m 2 at ITER relevant thermal–hydraulic con<strong>di</strong>tions.<br />
On the basis of these results, <strong>ENEA</strong>–ANSALDO participated in the European program for the qualification<br />
and manufacturing of the <strong>di</strong>vertor IVT, accor<strong>di</strong>ng to the Fusion For Energy (F4E) specifications. A <strong>di</strong>vertor<br />
IVT prototype (400 mm total length) with three plasma facing component units (fig 3.1) was successfully tested<br />
at ITER relevant thermal heat fluxes (20 MW/m 2 for 3000 cycles CFC part, 15 MW/m 2 for 3000 cycles W<br />
part).<br />
Now, this technology is ready to face the challenge of the ITER<br />
IVT production, thus transferring the experience gained in the<br />
development, optimization and qualification of the PBC and<br />
HRP processes to an industrial production line.<br />
Qualification of ultrasonic non–destructrive testing method<br />
for plasma facing components<br />
Under the “EURATOM Training Network for Plasma–facing<br />
Materials” (ETN_PFM) (Contract No. 042314 (FU 06)), <strong>ENEA</strong><br />
was assigned with a trainee to be prepared in the area of<br />
“Design, manufacturing and acceptance procedures of PFC”.<br />
This area is strictly linked to the activities related to the<br />
Figure 3.1 – ITER <strong>di</strong>vertor IVT qualification<br />
prototype manufactured by <strong>ENEA</strong>–Ansaldo