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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058<br />
progress report<br />
2010<br />
development and manufacturing of plasma facing compontens<br />
(PFCs) for the ITER tokamak and to the qualification of the<br />
manufacturing technologies for the ITER <strong>di</strong>vertor procurement.<br />
Figure 3.2 – Plane CFC–Cu joint sample<br />
Amplitude<br />
40<br />
30<br />
20<br />
10<br />
0 0 0 20<br />
C-scan 0<br />
C-scan 1<br />
C-scan<br />
REPORT<br />
100<br />
0<br />
-100<br />
Nome del file<br />
30 40 50 60<br />
13.39 17.39 22.00<br />
-19.28 43.75 0.00<br />
120<br />
80<br />
40<br />
0<br />
DX mm<br />
32.67<br />
DY mm<br />
26.36<br />
TXT<br />
OK<br />
D:\Lavoro\ULTRASUONI\CAMPIONE01ULTRAN\ultime provecd<br />
plane15.rf1<br />
One of the main issues in the manufacturing of the plasma facing<br />
units is the reliability of the non destructive controls that are<br />
necessarily performed during the manufacturing process. <strong>ENEA</strong> has<br />
developed a suitable ultrasonic technique (UT) for the control of all<br />
the joining interfaces of the ITER <strong>di</strong>vertor IVT plasma facing units,<br />
but the defect detection capability of the method has to be proved for<br />
both metal to metal and metal to CFC joints, since both types of<br />
joints are present. Within this activity, the UT results coming from<br />
the investigation being performed during the manufacturing, but also<br />
after the thermal fatigue testing (up to 20 MW/m 2 ) of mock–ups<br />
manufactured in <strong>ENEA</strong> labs by using the HRP technology were<br />
stu<strong>di</strong>ed and compared with the evidences coming from the final<br />
destructive examination in order to qualify the method. Regar<strong>di</strong>ng<br />
the Cu/CFC joint, the effectiveness of the ultrasonic test has been<br />
deeply stu<strong>di</strong>ed due to the high acoustic attenuation of CFC to<br />
ultrasonic waves. For these purpose an ‘ad hoc’ plane Cu/CFC joint<br />
sample, that reproduces the actual annular joint interfaces, was<br />
manufactured. This plane sample has the advantage of being easily<br />
tested by probes with <strong>di</strong>fferent geometry and ultrasonic<br />
characteristics. UT testing results were compared with x–ray and<br />
Eddy current of the same sample.<br />
The results confirmed that the evidences detected by UT can be<br />
easily correlated to lack of adhesion of the copper to CFC; in fact,<br />
the position of the defective zones coincides with the points where<br />
the brazing alloy deposition <strong>di</strong>d not succeed.<br />
Figure 3.2 shows the CFC–Cu sample being used for the testing and<br />
figure 3.3 compares the images obtained by the <strong>di</strong>fferent techniques:<br />
UT, x–ray, Eddy current.<br />
C-scan<br />
Height<br />
0<br />
10<br />
20<br />
30<br />
0 50 100 150<br />
Figure 3.3 – Images obtained by UT,<br />
x–ray, and Eddy current<br />
Analysis of the ITER <strong>di</strong>vertor cassettes<br />
<strong>ENEA</strong> completed the activities related to the performing of a new set<br />
of 3D electromagnetic (EM) and mechanical analyses of the revised<br />
design of the ITER <strong>di</strong>vertor cassettes to the purpose of checking the<br />
fulfillment of the requirements and better assessing the merits of<br />
each envisaged alternative during several off–normal events,<br />
inclu<strong>di</strong>ng category II and III events. These activities, in the frame of<br />
the European Fusion Development Agreement (EFDA) Contract 07–<br />
1702/1596 (TW6–TVD–DIAGAN) [3.1], were performed with the<br />
support of L.T. Calcoli, an Italian company specialized in<br />
electromagnetic and structural finite element analysis.<br />
The Divertor is one of the most challenging components of the ITER machine: it is designed to sustain the<br />
heat load and reduce the impurity in the plasma: it consists of the PFCs and a massive structure called the<br />
cassette body (CB) (fig. 3.4). The PFCs are actively cooled thermal shields required to sustain the heat and<br />
particle fluxes during normal and transient operations as well as during <strong>di</strong>sruption events. The CB is needed<br />
for supporting the PFCs, routing the water coolant into them and provi<strong>di</strong>ng neutron shiel<strong>di</strong>ng: it is mounted<br />
onto the vacuum vessel’s (VV) inboard and outboard rails via a mechanical locking system.<br />
The performed 3D EM numerical analysis allowed the EM loads to be calculated, inclu<strong>di</strong>ng integral forces<br />
and moments on the PFCs, CBs and components (pipes, manifolds and multilinks in figure 3.5) due to halo<br />
and Eddy currents by taking into account both the thermal and current quench. The EM loads thus obtained<br />
were then transferred for the correspon<strong>di</strong>ng dynamic mechanical analysis that allowed the stresses and