• Title of article

    Performance of FCCI barrier foils for U–Zr–X metallic fuel

  • Author/Authors

    Ryu، نويسنده , , Ho Jin and Lee، نويسنده , , Byoung Oon and Oh، نويسنده , , Seok Jin and Kim، نويسنده , , Jun Hwan and Lee، نويسنده , , Chan Bock، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2009
  • Pages
    7
  • From page
    206
  • To page
    212
  • Abstract
    Diffusion couple tests of U–Zr or U–Zr–Ce alloys vs. ferritic martensitic steels such as HT9 or T91 were carried out in order to evaluate the performance of the diffusion barrier candidates. Elemental metal foils of Zr, Nb, Ti, Mo, Ta, V and Cr were very effective in inhibiting interdiffusion between these fuels and steels. Eutectic melting between the fuels and steels was not observed in any of the diffusion couples using these diffusion barrier foils at annealing temperatures up to 800 °C. Among the metallic foils evaluated in this study, V and Cr exhibited the most promising performances as a diffusion barrier material for eliminating the fuel cladding chemical interaction problem. However, Zr, Nb and Ti showed an active interaction with the fuel mainly due to the large U solubility.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2009
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1365013