• Title of article

    Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling

  • Author/Authors

    Jaewoon Yoo، نويسنده , , Yuki Ishiwatari، نويسنده , , Yoshiaki Oka، نويسنده , , Jie Liu، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2006
  • Pages
    12
  • From page
    945
  • To page
    956
  • Abstract
    Fuel rod design for high power density supercritical water-cooled fast reactor was conducted with mixed-oxide (MOX) fuel and stainless steel (SUS304) cladding under the limiting cladding surface temperature of 650 °C. Fuel and cladding integrities, and flow-induced vibration were taken into account as design criteria. Designed fuel rod has the diameter of 7.6 mm and is arranged in the fuel assembly with pitch-to-diameter ratio of 1.14. New core arrangement for negative void reactivity is proposed by three-dimensional tri-z core calculation fully coupled with thermal hydraulic calculation, where ZrH layer concept is used for negative void reactivity. The core has high power density of 156 W/cm3 and its equivalent diameter is only 2.7 m for 1000 MWe class reactor core. High average core outlet temperature of 500 °C is achieved by introducing radial fuel enrichment zoning and downward flow in seed assembly. Small pressure vessel size and simplified direct steam cycle with higher thermal efficiency give an economical potential in aspect of capital and operating cost.
  • Journal title
    Annals of Nuclear Energy
  • Serial Year
    2006
  • Journal title
    Annals of Nuclear Energy
  • Record number

    406206