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research article

Single-phase mixing studies by means of a directly coupled CFD/system-code tool

Bertolotto, D.  
•
Manera, A.
•
Frey, S.
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2009
Annals of Nuclear Energy

The present paper describes the coupling of the 3D computational fluid dynamics (CFD) code CFX with the best estimate thermal-hydraulic code TRACE. Two different coupling schemes - one explicit and the other semi-implicit - have been tested. Verification of the coupled CFX-TRACE code has first been carried out on the basis of a simple test case consisting of a straight pipe filled with liquid subject to a sudden acceleration. As a second validation step, measurements using advanced instrumentation (wire-mesh sensors) have been performed in a simple, specially constructed test facility consisting of two loops connected by a double T-junction. Comparisons of the measurements are made with calculation results obtained using the coupled codes, as well as the individual codes in stand-alone mode, thereby clearly bringing out the effectiveness of the achieved coupling for simulating situations in which three-dimensional mixing phenomena are important. [All rights reserved Elsevier].

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Type
research article
DOI
10.1016/j.anucene.2008.11.027
Web of Science ID

WOS:000264744500011

Author(s)
Bertolotto, D.  
Manera, A.
Frey, S.
Prasser, H. M.
Chawla, R.  
Date Issued

2009

Publisher

Elsevier Science Ltd.

Published in
Annals of Nuclear Energy
Volume

36

Issue

3

Start page

310

End page

16

Subjects

computational fluid dynamics

•

fission reactor cooling

•

fission reactor safety

•

fission reactor theory

•

light water reactors

•

nuclear engineering computing

•

nuclear facility regulation

Note

Paul Scherrer Inst. (PSI), Villigen, Switzerland

Editorial or Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
LRS  
Available on Infoscience
September 17, 2010
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/53908
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