Flow analysis in the HCLL-TBM ITER channels including MHD and heat transfer

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Document typeConference lecture
Defense date2010
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Abstract
One of the key components regarding heat transfer and tritium inventories in
deuterium-tritium nuclear fusion reactors is the (tritium) Breeding Blanket, called Test
Blanket Module or TBM in ITER experiment. Several designs are going to be tested in
ITER, one of those is the HCLL (Helium Cooled Lithium Lead) design. Before being
tested, it is of major interest to predict in detail several
ow parameters such as pressure
drop, tritium inventories and tritium permeation rates through walls.
The goal of the present study is to analyze the
ow near the gap region (close to the
rst wall) in the HCLL-TBM so as to quantify tritium inventories and permeation
uxes.
To do so, simpli ed C-shaped channels are simulated under ITER speci cations. The
ow appears to be very complex and, in order to get the origin of this complexity, the phe-
nomenon physics are decoupled. First, the pure hydrodynamic case is simulated; obtaining
that the critical Reynolds number is around TBM/ITER speci cations. Second, the MHD
ow with perfectly insulating walls is studied and, as expected due to the high Hartmann
number, hydrodynamic instabilities disappear. Finally, when heat transfer is introduced,
vorticity is generated due to Rayleigh-B enard instabilities at the channel inlet and, as the
ow travels through the channel, faster vortices appear in the gap region and in the outlet
channel. These vortices originate high tritium concentration zones. Hence, the existence
of vortices is of crucial interest for tritium inventories prediction and HCLL design.
CitationMas De Les Valls, E.; Fradera, J.; Batet, L. Flow analysis in the HCLL-TBM ITER channels including MHD and heat transfer. A: European Conference on Computational Fluid Dynamics (ECCOMAS - CFD). "Fifth European Conference on Computational Fluid Dynamics (CFD 2010)". Lisboa: 2010, p. 1-9.
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