Title :
Preliminary thermo-hydraulic analysis of the Breeder Zone for the EU helium cooled pebble bed test blanket module for ITER
Author :
Neuberger, H. ; Lux, M.
Author_Institution :
Forschungszentrum Karlsruhe (FZK), Karlsruhe, Germany
Abstract :
This paper summarizes the results of a preliminary thermo-hydraulic analysis in 2007 and 2008 of the HCPB-TBM Breeder Zone (BZ) after significant modifications have been implemented in the design. In the frame of this study the design of the BZ has been analyzed with regard to the pebble bed temperatures and heat flux extracted from the pebble beds by the surrounding TBM structural components.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor design; EU helium cooled pebble bed test blanket module; ITER; TBM structural component; breeder zone; heat flux; reactor design; thermo-hydraulic analysis; Boundary conditions; Ceramics; Design optimization; Fabrication; Helium; Inductors; Performance analysis; Performance evaluation; Temperature; Testing; BZ; Heilum Cooled Pebble Bed Test Blanket Modul (HCPB TBM)e; Pebble beds; Solid Breeder Concept;
Conference_Titel :
Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
978-1-4244-2635-5
Electronic_ISBN :
978-1-4244-2636-2
DOI :
10.1109/FUSION.2009.5226439
