• Title of article

    Accident analyses and passive measures reducing the consequences of a core-melt in CAPRA/CADRA reactor cores Original Research Article

  • Author/Authors

    W Maschek، نويسنده , , D Struwe، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2000
  • Pages
    14
  • From page
    311
  • To page
    324
  • Abstract
    As part of the Combustion Améliorée du Plutonium dans les Réacteurs Avancés/Consommation DʹActinides et de Déchets dans les Réacteurs Avancés (CAPRA/CADRA) program the feasibility of reactor systems with different neutron spectra and coolants is investigated to burn plutonium and also to destruct minor actinides and long lived fission products. In this paper, we deal with reactor cores with fast spectrum and metal cooling. The design of this type of CAPRA/CADRA cores shows significant differences compared e.g. to conventional fast reactor cores. The high Pu-enrichment and the high minor actinide load have an important influence on the core meltdown behavior and the associated recriticality risk. To cope with this risk, inherent design features and special measures/devices are investigated for their potential of early fuel discharge to reduce the criticality of the reactor core. An assessment of such measures/devices, which could provide an additional line of defense against severe accident development, is given. Within the CAPRA/CADRA program, also accelerator driven subcritical systems are investigated for performing the task of transmutation and incineration. In these fast neutron systems with a strong external neutron source, the kinetic behavior is different to a critical core and new strategies and measures for accident prevention have to be investigated.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2000
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    889241