• Title of article

    Multiscale simulation of neutron induced damage in tritium breeding blankets with different spectral shifters

  • Author/Authors

    Choi، نويسنده , , Yong Hee and Joo، نويسنده , , Han Gyu، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2013
  • Pages
    5
  • From page
    2471
  • To page
    2475
  • Abstract
    A multiscale material defect simulation established to evaluate neutron induced damages on metals is applied to an estimation of material degradation in helium cooled molten lithium blankets in which four different spectral shifter materials are examined as a means of maximizing the tritium breeding ratio through proper shaping of the neutron spectrum. The multiscale system consists of a Monte Carlo neutron transport code, a recoil spectrum generation code, a molecular dynamics code, a high energy cascade breakup model, an object kinetic Monte Carlo code, and a simple formula as the shear stress estimator. The average recoil energy of the primary knock-on atoms, the total concentration of the defects, average defect sizes, and the increase in shear stress after a certain irradiation time are calculated for each spectral shifter. Among the four proposed materials of B4C, Be, Graphite and TiC, B4C reveals the best shielding performance in terms of neutron radiation hardening. The result for the increase in shear stress after 100 days of irradiation indicates that the increased shear stress is 1.5 GPa for B4C which is about 40% less than that of the worst one, the graphite spectral shifter. The other damage indicators show consistent trends.
  • Keywords
    Multiscale simulation , Neutron induced damage , Radiation defect , Spectral shifter , Fusion blanket
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2013
  • Journal title
    Fusion Engineering and Design
  • Record number

    2362000