• DocumentCode
    2936097
  • Title

    The potential use of zirconium-based alloys in fusion power plants

  • Author

    Forty, C.B.A. ; Karditsas, P.J.

  • Author_Institution
    Culham Lab., UKAEA, Abingdon, UK
  • Volume
    2
  • fYear
    1997
  • fDate
    6-10 Oct 1997
  • Firstpage
    849
  • Abstract
    Zirconium and zirconium based alloys have been used for many decades in the fission industry. Their main advantages over several other common engineering materials include: excellent corrosion resistance in aqueous environments; acceptable high-temperature mechanical properties and low thermal neutron absorption cross section. However, it would appear that the fusion community has given little consideration to this very well characterised and useful material. Whatever the reasons for the neglect, this paper is intended as a reassessment of zirconium-alloys and of their potential application in fusion power plants. It is hoped that, as such, it will promote further discussion and, perhaps, reopen the case for zirconium
  • Keywords
    fusion reactor materials; zirconium alloys; Zr; Zr-based alloys; fusion power plants; Absorption; Corrosion; Inductors; Mechanical factors; Neutrons; Power generation; Temperature; Thermal resistance; Water; Zirconium;
  • 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.1997.687758
  • Filename
    687758