DocumentCode
2938349
Title
Helium loops of an ITER HCPB test blanket module
Author
Albrecht, H. ; Hutter, E. ; Kleefeldt, K. ; Penzhorn, R.-D.
Author_Institution
Hauptabteilung Versuchstech., Forschungszentrum Karlsruhe, Germany
Volume
2
fYear
1997
fDate
6-10 Oct 1997
Firstpage
983
Abstract
The operation of a He cooled pebble bed (HCPB) test blanket module for ITER requires three helium loops which are being designed for (a) tritium extraction, (b) heat removal, and (c) coolant purification. The main design data as well as flow diagrams of the loops are presented. Although the concepts for tritium extraction and coolant purification have a good potential for reliable application they still need to be verified and tested with respect to process control and chemical analysis
Keywords
Tokamak devices; fusion reactor blankets; fusion reactor design; helium; He; He cooled pebble bed test blanket module; He loops; ITER; T extraction; flow diagrams; test blanket module; Coolants; Data mining; Filters; Helium; Neutrons; Plasma temperature; Process control; Purification; System testing; Valves;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location
San Diego, CA
Print_ISBN
0-7803-4226-7
Type
conf
DOI
10.1109/FUSION.1997.687789
Filename
687789
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