Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione

fusion advanced studies torus (cont’d.)
progress report
2010
051
Pressure
4.02×10 06
3.77×10 06
3.51×10 06
3.25×10 06
3.00×10 06
2.74×10 06
2.48×10 06
2.23×10 06
1.97×10 06
1.72×10 06
1.46×10 06
Pa
Figure 2.7 – Pressure in the divertor pipes
Figure 2.6 – FAST divertor design with ~20° outward strike
point angle
along the dump plate and the dome, continues through
the inner dump plate and vertical target and finally
returns into the cassette manifold through the back of
the inner vertical target. A preliminary 3D
thermo–hydraulic analysis has been carried out for the
divertor module by using the ANSYS CFX fluid
dynamics code. The total heat power on each individual
divertor module a single module (the total power on the
whole divertor is 22.7 MW) has been splitted between
the two vertical target surfaces (2/3 in the outer and 1/3
in the inner vertical target) and applied as heat flow into
the model. Assuming the water flowing with 10 Kgs –1
rate and 4 Mpa pressure, 120°C as inlet conditions, a
2.2 MPa pressure drop (fig. 2.7) and 11°C temperature
increase have been computed in a single divertor
module. The temperature distribution along a single
tiles row in the straight part of the outer vertical target
has been evaluated by assuming the same inlet condition
as before (1.67 Kg s –1 mass flow rate, 4 MPa inlet
pressure, 120°C inlet temperature). The model includes
the presence of the swirl tape as foreseen in the bottom
part of the vertical target. It was supposed that the W
monoblocks are bonded on the CuCrZr pipe by a Cu
OFHC interlayer. The heat load has been assumed to
vary exponentially with an energy decay length of 5 mm
at the outer midplane and a factor 5 for the expansion
at the target, thus resulting in ∼20 MWm –2 on the strike
point. The average heat transfer coefficient at the
interface between water and pipe has been computed as
∼110 kW m –2 K –1 . The maximum stationary
temperature reached is ∼1700°C on the W tile facing
the plasma and ∼490°C on the Cu OFHC layer
(fig. 2.8).
Temperature
1.7×10 03
1.6×10 03
1.4×10 03
1.3×10 03
1.1×10 03
9.3×10 02
7.7×10 02
6.1×10 02
4.4×10 02
2.8×10 02
1.2×10 02
[C]
Figure 2.8 – Temperature contour on the divertor outer
vertical target
Figure 2.9 – FW and divertor in the FAST CATIA5
model
First wall design
The first wall design advanced in the last year, based
upon a solution consisting in a bundle (fig. 2.9) of
poloidal coaxial pipes (fig. 2.10) armoured with 4 mm
thick plasma-sprayed W [2.10]. This configuration
Figure 2.10 – Section of the FW model showing the
poloidal coaxial pipes bundle