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
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