Published June 2008 | Version v1
Journal article

Development of a CFD model for the CANDU-6 moderator analysis using a coupled solver

  • 1. Korea Atomic Energy Research Institute, P.O. Box 105 Yusong, Daejon 305-600 (Korea, Republic of)

Description

A computational fluid dynamics (CFD) moderator analysis model by using a coupled solver has been developed for the moderator analysis of Canada deuterium uranium (CANDU) reactors. For Wolsong Units 2/3/4, a steady-state moderator circulation under operating conditions and the local moderator subcooling during a LOCA transient were evaluated using the CFD tool. When compared to a former study in the Final Safety Analysis Reports, the current analysis provided well-matched trends and reasonable results. This new CFD model based on a coupled solver shows a dramatic increase in the computing speed, when compared to that based on a segregated solver

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2007.11.013

Additional details

Identifiers

DOI
10.1016/j.anucene.2007.11.013;
PII
S0306-4549(07)00296-4;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
35
Journal Issue
6
Journal Page Range
p. 1041-1049
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.