• Title of article

    ITER shielding blanket

  • Author/Authors

    Strebkov، نويسنده , , Yu and Avsjannikov، نويسنده , , A and Baryshev، نويسنده , , M and Blinov، نويسنده , , Yu and Shatalov، نويسنده , , G and Vasiliev، نويسنده , , A and Chernjagin، نويسنده , , A، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 1995
  • Pages
    9
  • From page
    363
  • To page
    371
  • Abstract
    A reference non-breeding blanket is under development now for the ITER Basic Performance Phase for the purpose of high reliability during the first stage of ITER operation. More severe operation modes are expected in this stage with first wall (FW) local heat loads up to 100–300 W cm−2. Integration of a blanket design with protective and start limiters requires new solutions to achieve high reliability, and possible use of beryllium as a protective material leads to technologies. The rigid shielding blanket concept was developed in Russia to satisfy the above-mentioned requirements. The concept is based on a copper alloy FW, austenitic stainless steel blanket structure, water cooling. Beryllium protection is integrated in the FW design. Fabrication technology and assembly procedure are described in parallel with the equipment used.
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    1995
  • Journal title
    Fusion Engineering and Design
  • Record number

    2363045