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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

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