Published March 2003 | Version v1
Journal article

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

  • 1. Department of Nuclear Engineering,Xi'an Jiaotong University, Xi'an, Shaanxi 710049 (China)

Description

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.

Availability note (English)

Available from http://dx.doi.org/10.1016/S0306-4549(02)00077-4

Additional details

Identifiers

DOI
10.1016/S0306-4549(02)00077-4;
arXiv
arXiv:hep-ph/9902390v1;
PII
S0306454902000774;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
30
Journal Issue
4
Journal Page Range
p. 405-412
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Copyright
Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.