• Title of article

    DORT analyses of decay heat experiment on tungsten for ITER

  • Author/Authors

    Konno، نويسنده , , Chikara and Maekawa، نويسنده , , Fujio and Wada، نويسنده , , Masayuki and Ikeda، نويسنده , , Yujiro and Takeuchi، نويسنده , , Hiroshi، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2001
  • Pages
    5
  • From page
    961
  • To page
    965
  • Abstract
    The decay heat experiment on tungsten for ITER performed with an ITER-simulated neutron field at JAERI/FNS was analyzed by the DORT code in order to assess the accuracy of DORT calculations with and without self-shielding corrected multigroup libraries on the production of 186W, which is the main source of decay heat of tungsten in the ITER neutron environment. Neutron multigroup libraries (175 groups and 46 groups) with and without self-shielding correction were generated from FENDL/E-1.1 by the NJOY and TRANSX codes. The followings were found through the comparison among the present calculations, an MCNP calculation with FENDL/MC-1.1 and the measured data for 186W production:1. RT calculations with the self-shielding corrected libraries are almost the same as the MCNP one and underestimate the measured data by 20%. fference of 187W production between the DORT calculations with and without the self-shielding corrected libraries is seemingly small for neutron 175 group structure, while 187W production in the DORT calculation without the self-shielding corrected library of neutron 46 group structure is 40% smaller than that with the self-shielding corrected one. s concluded that DORT calculations have almost the same accuracy as MCNP ones for 187W production in the divertor and baffle regions in ITER if a self-shielding corrected multigroup library is used.
  • Keywords
    DORT analyses , ITER , Tungsten
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2001
  • Journal title
    Fusion Engineering and Design
  • Record number

    2367500