• Title of article

    First neutronics analysis for ITER bio-shield equatorial port plug

  • Author/Authors

    Dang، نويسنده , , Tongqiang and Ying، نويسنده , , Dongchuan and Yang، نويسنده , , Qi and Loughlin، نويسنده , , Michael and Davis، نويسنده , , Andrew، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2012
  • Pages
    6
  • From page
    1447
  • To page
    1452
  • Abstract
    ITER equatorial port cell outside the bio-shield plug is a place to allow personnel access after shutdown that accommodates various sensitive equipment and pipes. Gamma dose rate after shutdown of 1 day in the port cell should be within 10 μSv/h for occupational safety which is one order of magnitude less than that in the port interspace by the shielding of bio-shield plug. To verify the shielding property of the bio-shield plug, the distributions of gamma dose rates in port cell were studied. Based on the ITER neutronics model Alite4 which is a three-dimensional ITER tokomak neutronics model for MCNP calculations with a 40 degree extent in the toroidal direction and vertical reflecting bounded planes on both sides, the equatorial port was updated according to a conceptual CAD model using Monte Carlo Automatic Modeling Program for Radiation Transport Simulation (MCAM). A 2-step method of gamma dose rate calculation was used for shutdown dose rates in CAD-based Multi-Functional 4D Neutronics Simulation System (VisualBUS). The result showed that gamma dose rates in the port cell were higher than the desired limit. Refinements to the bio-shield plug design were suggested to ensure that dose rates in the port cell were within the design value for maintenance access.
  • Keywords
    Gamma dose rate , CAD-based Multi-Functional 4D Neutronics Simulation System , ITER , Bio-shield plug , Port cell
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2012
  • Journal title
    Fusion Engineering and Design
  • Record number

    2360664