1. magnetic confinement - ENEA - Fusione
1. magnetic confinement - ENEA - Fusione
1. magnetic confinement - ENEA - Fusione
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3. FUSION TECHNOLOGY<br />
3.9 Thermal-Fluidodynamics<br />
2001, the first experimental campaign started on four of the EDA mockups mounted<br />
inside EDA-BETA [3.44, 3.45].<br />
3.9.2 HE-FUS3 experimental cassette of lithium-beryllium pebble<br />
beds<br />
During 2001, a new thermal test campaign was started on the HELICHETTA solidbreeder<br />
mockup. The objective of the tests on a single prismatic cell filled with the<br />
reference breeder Li 4 SiO 4 and Li 2 TiO 3 pebble beds was to determine the influence<br />
of the filling factor on the thermal-mechanical parameters and the behaviour of the<br />
ceramic bed after mechanical pre-cycling and application of the spring-system lateral<br />
load. From July 2001 to the end of the year, 60 tests were carried out in air on the<br />
HEFUS-3 facility at <strong>ENEA</strong> Brasimone on both the reference materials. The measured<br />
Li 4 SiO 4 and Li 2 TiO 3 pebble packing factors were, respectively, 0.65 and 0.64. The<br />
results of the first HELICHETTA test campaigns are:<br />
i) the displacement of the beds is as large as 0.2 mm towards the cooling plates and<br />
ranges from 0.5 to 1 mm for L i 2TiO 3 and up to <strong>1.</strong>5 mm for Li 4 SiO 4 towards the<br />
sliding plug;<br />
ii) the washer springs and sliding plug systems prevent larger stresses on the<br />
containment structure;<br />
iii) the pebble bed thermal conductivities in air show good agreement with previous<br />
FZK experiments;<br />
iv) the pebble thermal mechanical hysteresis, well evident during the cyclic ramp<br />
up/down tests, affects the thermal-mechanical bed behaviour.<br />
The tender for construction of both HELICA and HEXCALIBER was launched in<br />
December 2001 and their fabrication will be finished, respectively, by June 2002 and<br />
December 2002 [3.46, 3.47].<br />
3.10 International Fusion Material<br />
Irradiation Facility (IFMIF)<br />
3.10.1 Design and mockup tests of lithium jet target<br />
One of the main tasks of the lithium target design is to guarantee the jet stability<br />
against overheating by the powerful deuteron beam. This is achieved with the use<br />
of a curved plate (backplate) on which lithium flows. A computer code (RIGEL)<br />
developed ad hoc by <strong>ENEA</strong> Bologna was used to determine the best working<br />
conditions (table 3.V) for the new IFMIF design parameters (Reduced Cost Design).<br />
[3.44] G. Dell’Orco et al.,<br />
Status of the Contracts<br />
EFDA 00/529 and<br />
00/533 for the thermal<br />
fatigue tests of Be<br />
protected EDA – PFW<br />
mock-ups, <strong>ENEA</strong>-EFDA<br />
Meeting (Brasimone<br />
2001)<br />
[3.45] G. Dell’Orco et al.,<br />
Report for the Task<br />
T216+, subtask E1, on the<br />
thermal fatigue tests of<br />
Be protected first wall<br />
mock-ups, <strong>ENEA</strong> Internal<br />
Report, SB-G-R-0051<br />
(2001)<br />
[3.46] G. Dell’Orco et al.,<br />
TAZZA mock-up pebble<br />
beds - Experimental and<br />
theoretical investigations,<br />
presented at the<br />
10th Int. Workshop on<br />
Ceramic Breeder Blanket<br />
Interactions (CCBI-10)<br />
(Karlsruhe 2001)<br />
[3.47] G. Dell’Orco et al.,<br />
Progress on pebble bed<br />
experimental activity for<br />
the HE-FUS3 mock-ups,<br />
presented at the 10th<br />
Int. Workshop on<br />
Ceramic Breeder Blanket<br />
Interactions (CCBI-10)<br />
(Karlsruhe 2001)<br />
Tab 3.V - IFMIF target input data and Li jet stability results<br />
Main input data<br />
r<br />
Main results<br />
Beam footprint 5×20 [cm×cm] Reynolds number 694417 [-]<br />
Jet thickness 0.025 [m] Max. pressure 12493 [Pa]<br />
Jet width 0.26 [m] Max. surface temperature 297 [°C]<br />
Jet velocity 15 [m/s] Max. temperature in the 441 [°C]<br />
bulk<br />
Backplate curvature 0.25 [m] Min. free surface boiling 35 [°C]<br />
radius<br />
margin<br />
Inlet temperature 250 [°C] Min. bulk boiling margin 403 [°C]<br />
Jet power deposition 10 [MW] Free surface evaporation 16 [g/year]