• Title of article

    The coupled kinetic and thermal-hydraulic three dimensional code system NLSANMT/COBRA-IV for PWR core transient analysis

  • Author/Authors

    Chengkui Liao، نويسنده , , Zhongsheng Xie، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2003
  • Pages
    8
  • From page
    405
  • To page
    412
  • Abstract
    A three dimensional neutron kinetic nodal code NLSANMT has been developed based on the semi-analytical nodal expansion method and nonlinear iteration strategy, and it has been coupled with the subchannel thermal hydraulic core analysis code COBRA-IV to form the integrated code system NLSANMT/COBRA-IV for PWR core transient analysis. This paper describes the features and status of the integrated NLSANMT/COBRA-IV system. A demonstration application of the NLSANMT/COBRA-IV code to rod ejection accident analysis is presented using the OECD NEACRP PWR hot zero power full core rod ejection benchmark problem. The NLSANMT/COBRA-IV solution agrees well with the reference solution, even when one node per assembly and one channel per assembly are used.
  • Journal title
    Annals of Nuclear Energy
  • Serial Year
    2003
  • Journal title
    Annals of Nuclear Energy
  • Record number

    405770