• Title of article

    Design study of plasma-facing components for JT-60SA

  • Author/Authors

    Sakurai، نويسنده , , S. and Masaki، نويسنده , , K. and Shibama، نويسنده , , Y.K. and Tamai، نويسنده , , H. and Matsukawa، نويسنده , , M.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2007
  • Pages
    7
  • From page
    1767
  • To page
    1773
  • Abstract
    The Japanese national project toward DEMO reactor and a satellite tokamak project for ITER in a Broader Approach with Japan and EU collaboration are combined as the JT-60SA (Super Advanced) project. Design of PFC for JT-60SA is widely modified from original national plan due to the increase of plasma heating power and annual neutron yield. Mono-block divertor target aiming at power handling of 15 MW/m2 should be adopted to an outer divertor, because expected heat flux will exceed 10 MW/m2. Since high coolant flow velocity of 10–12 m/s is required to enhance heat transfer and critical heat flux for swirl or screw tube, primary coolant water system is increased from 1300 to 4600 m3/h. Remote handling system similar with ITER blanket manipulator is adopted to maintain plasma-facing components. Divertor cassette has 10° width in toroidal direction and weight of 300 kg itself due to the limitation of port width and manipulator.
  • Keywords
    Divertor , Design , remote handling , First wall , JT-60SA
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2007
  • Journal title
    Fusion Engineering and Design
  • Record number

    2354090