• Title of article

    Neutronic analysis of ITER neutral beam test bed

  • Author/Authors

    Loughlin، نويسنده , , M.J.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2005
  • Pages
    5
  • From page
    461
  • To page
    465
  • Abstract
    The neutron dose arising during the operation of the ITER neutral beam test bed was calculated using the Monte-Carlo code MCNP. The activation of the injector components was determined using the inventory code FISPACT and the resultant gamma ray doses at the end of the test programme were determined. It is found that there would be a neutron dose during beam operations sufficient to entail restricted and monitored access to areas outside the shield wall. A careful assessment of the shielding is needed. The individual components of the injector are generally not activated excessively, i.e. their activation levels fall below the hands on limit within 1 year. However, the total gamma dose close to the vessel is substantially higher than any individual contact dose. This must be taken into consideration in maintenance planning.
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2005
  • Journal title
    Fusion Engineering and Design
  • Record number

    2352194