• Title of article

    Integrated experiment of blanket in-pile mockup with Li2TiO3 pebbles

  • Author/Authors

    Tsuchiya، نويسنده , , K and Nakamichi، نويسنده , , M and Nagao، نويسنده , , Y and Fujita، نويسنده , , J and Sagawa، نويسنده , , H and Tanaka، نويسنده , , S and Kawamura، نويسنده , , H، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2000
  • Pages
    6
  • From page
    887
  • To page
    892
  • Abstract
    Lithium titanate (Li2TiO3) is one of the candidate tritium breeding materials for breeding blanket of the fusion reactor. Therefore, tritium release experiments from Li2TiO3 packing region were carried out to evaluate the effects of various parameters, i.e. sweep gas flow rate, irradiation temperature, and hydrogen content in sweep gas, etc. on tritium release. As for the shape of the Li2TiO3, a small spherical form (pebbles) is preferred to reduce the induced thermal stress in the breeding material. The diameter and total weight of Li2TiO3 pebbles were 1 mm and ∼135 g, respectively. And the integrated experiment of blanket in-pile mockup with Li2TiO3 pebble bed was carried out at the Japan Materials Testing Reactor (JMTR). The tritium released from Li2TiO3 pebble bed was swept by the helium gas with hydrogen. The total tritium concentration (HT+HTO) and gaseous tritium concentration (HT) of tritium released from Li2TiO3 pebbles were measured, and HT/(HT+HTO) ratio was evaluated under various conditions.
  • Keywords
    Lithium titanate , Integrated experiment , Tritium breeding materials , Blanket in-pile mockup
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2000
  • Journal title
    Fusion Engineering and Design
  • Record number

    2366435