• DocumentCode
    2759537
  • Title

    Tritium analysis for the european HCPB TBM in ITER

  • Author

    Meyder, R. ; Boccaccini, L.V. ; Bekris, N.

  • Author_Institution
    Inst. fur Reaktorsicherheit, Assoc. Euratom-Forschungszentrum Karlsruche, Karlsruhe
  • fYear
    2005
  • fDate
    Sept. 2005
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    Tritium inventory and permeation are important data for a breeding blanket of a fusion reactor. For the HCPB TBM in ITER a first attempt has been done to calculate these data at the design stage using available analysis tools. The results are in the expected range but further validation work is needed
  • Keywords
    Tokamak devices; fusion reactor blankets; fusion reactor design; ITER; breeding blanket; design stage; european HCPB TBM; fusion reactor; test blanket module; tritium analysis; tritium inventory; tritium permeation; Ceramics; Coolants; Fusion reactor design; Fusion reactors; Helium; Steel; System testing; Temperature; Thermomechanical processes; Transient analysis; Fusion; analysis; inventory; pebble bed; permeation; tritium;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
  • Conference_Location
    Knoxville, TN
  • Print_ISBN
    0-4244-0150-X
  • Electronic_ISBN
    0-4244-0150-X
  • Type

    conf

  • DOI
    10.1109/FUSION.2005.252903
  • Filename
    4018937
    • Link To Document
    https://search.isc.ac/dl/search/defaultta.aspx?DTC=49&DC=2759537