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1. magnetic confinement - ENEA - Fusione

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66<br />

3. FUSION TECHNOLOGY<br />

3.2 First Wall and Divertor<br />

600°C leaves the mechanical properties at acceptable values, although better results<br />

can be expected from a manufacturing process that starts from an as-received<br />

condition, with the temperature kept below or equal to 650°C.<br />

3.2.2 Manufacturing of small-scale W monoblock mockups by hot<br />

radial pressing (ITER EFDA R&D Tasks)<br />

The aim of this activity is to develop an alternative technique for manufacturing the<br />

ITER PFCs, which have a monoblock geometry (i.e. the vertical target).<br />

The basic idea is to perform radial diffusion bonding between the cooling tube and<br />

the tungsten tile, with the process parameters such that degradation of the thermalmechanical<br />

properties remains limited.<br />

The feasibility of joining Cu//Cu and Cu//W by diffusion bonding was studied,<br />

and some small-scale W monoblock mockups were successfully manufactured by<br />

placing them inside a special stainless steel container that does not deform during<br />

HIP, and tested for thermal fatigue (20 MW/m 2 for 1000 cycles).<br />

Following the good results obtained in the tests, a canister was then designed to<br />

perform hot radial pressing (HRP) in a standard furnace in which only a section of<br />

the canister (fig. 3.1) is heated and just the internal tube is pressurised up to the<br />

bonding pressure. The main advantage of this technique compared to HIP is that<br />

neither a high temperature/pressure furnace nor machining of the sheath is<br />

required.<br />

A dummy component was first tested using the following process parameters:<br />

temperature 600°C and pressure 700 bar applied for 3 h. The tests confirmed the<br />

capability of the canister to withstand the load conditions required by HRP.<br />

3.2.3 Runaway electrons on ITER PFCs (EFDA Contract /00-520)<br />

In 2001, the assessment of the thermal effects of runaway electrons (RAEs) on the<br />

ITER-FEAT plasma-facing components was concluded [3.1, 3.2].<br />

The integrated, versatile, multi-particle Monte Carlo code FLUKA was used to get<br />

the energy deposited inside the PFCs by a 10- or 15-MeV RAE impinging on the firstwall<br />

structures with an incidence angle of 1°. The geometrical model is a 3-D layered<br />

structure divided into 24 unit regions centred on the cooling tubes. Starting from the<br />

plasma, the model consists of armour, heatsink, cooling tube and coolant. Constant<br />

conditions were assumed in the poloidal direction. Five different geometries were<br />

investigated: 1) primary first wall armoured with Be (with and w/o protecting<br />

carbon fibre composite (CFC) poloidal limiters); 2) two port limiter first-wall options;<br />

3) Be flat tile; 4) CFC monoblock; 5) divertor baffle first wall armoured with W. The<br />

deposited energy density, normalised to one electron, for the Be-armoured first wall,<br />

and a 10-MeV RAE is shown in figure 3.2.<br />

∅54<br />

∅26<br />

[3.1] G. Maddaluno, S.<br />

Rollet, G. Maruccia,<br />

Thermal effects of<br />

runaway electrons on<br />

ITER plasma facing<br />

components, EFDA<br />

Contract 00-520 - Final<br />

Report - September 2001<br />

[3.2] G. Maddaluno et al.,<br />

Energy deposition and<br />

thermal effects of<br />

runaway electrons in<br />

ITER-FEAT plasma<br />

facing components, in<br />

preparation<br />

115<br />

150<br />

Fig. 3.1 - Cross section of<br />

the canister.

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