1. magnetic confinement - ENEA - Fusione
1. magnetic confinement - ENEA - Fusione
1. magnetic confinement - ENEA - Fusione
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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.