• DocumentCode
    3168808
  • Title

    Organic cooled first wall and shield design for the ARIES-III D 3He reactor

  • Author

    ARIES Team

  • fYear
    1991
  • fDate
    30 Sep-3 Oct 1991
  • Firstpage
    1110
  • Abstract
    An efficient organic cooled low activation ferritic steel first wall and shield were designed for the D-3He power reactor ARIES-III. The design allows removal of the large surface heat load without exceeding temperature and stress design limits. The structure is expected to last for the whole reactor life. The major concerns regarding using the organic coolant in fusion reactors were greatly alleviated. Organic coolant at a pressure of 2.6 MPa and inlet and outlet temperatures of 350 and 425°C are used. The low activation modified HT-9 alloy is used as structural and shielding material, allowing the radwaste to qualify as Class A waste. The total inboard first wall and shield thickness required for protecting the toroidal field coils is 65 cm. The first wall is coated by a 1.5-mm layer of beryllium, which is separated from the steel wall by a 100 μm layer of tungsten. The first wall is subjected to a high surface heat flux with a peak of 1.86 MW/m2. The steel front layer of the first wall is 1 mm thick, resulting in a maximum temperature of 531°C and acceptable thermal stresses. The end-of-life peak damage is only 63 dpa, implying that no change-out is required
  • Keywords
    deuterium; fusion reactor fuel; fusion reactor materials; fusion reactor theory and design; helium; shielding; thermal stresses; ARIES-III; Class A waste; D-3He reactor; HT-9 alloy; change-out; end-of-life peak damage; first wall; front layer; low activation ferritic steel; maximum temperature; organic cooled; outlet temperatures; power reactor; radwaste; shield design; stress design limits; surface heat load; thermal stresses; toroidal field coils; Coolants; Fusion reactor design; Fusion reactors; Helium; Inductors; Protection; Steel; Temperature; Thermal stresses; Waste materials;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-0132-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1991.218677
  • Filename
    218677