Published March 2008 | Version v1
Journal article

CFX simulation of a horizontal heater rods test

  • 1. Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

Description

In this study a CFD simulation of a horizontal heater rods test (CS28-2) has been performed with the CFX-10 code and it has been compared with an experiment in order to develop a post-blowdown modeling of a CANDU fuel channel during a large break loss of coolant accident (LBLOCA). The CS28-2 experiment is one of three series of experiments to simulate the fuel channel at a high temperature and a low steam flow rate which may occur in severe accident conditions such as a LBLOCA of CANDU reactors. Since radiation heat transfer is dominant in the CS28-2 experiment, a benchmark problem of radiation heat transfer for the same geometry as the CS28-2 is carried out first to assess the radiation model by CFX-10, to confirm whether CFX-10 can be applied to a complex fuel geometry or not. And, the CFD study of the CS28-2 has been performed with the aim to simulate the steady-state condition of the CS28-2. These steady-state calculation results will be used for the initial conditions of the transient simulation

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2007.02.045

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2007.02.045;
PII
S0029-5493(07)00341-X;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
238
Journal Issue
3
Journal Page Range
p. 522-529
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

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