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
Link To Document :
بازگشت