Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies

Adrian Tentrier; W. David Pointer; Tanju Sofu; David Weber; Simon Lo; Andrew Splawski

Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies

Adrian Tentrier, W. David Pointer, Tanju Sofu, David Weber, Simon Lo, Andrew Splawski

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

1 Scopus citations

Abstract

This paper presents recent advances in the development and integral validation of a two-phase Computational Fluid Dynamics (CFD) computer model (CFD-BWR) that allows the detailed analysis of the two-phase flow and heat transfer phenomena in Boiling Water Reactor (BWR) fuel bundles. The CFD-BWR code is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities.

Original language	English
Title of host publication	Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
Pages	2682-2691
Number of pages	10
State	Published - 2008
Externally published	Yes
Event	Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work" - Nice, France Duration: May 13 2007 → May 18 2007

Publication series

Name	Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
Volume	5

Conference

Conference	Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
Country/Territory	France
City	Nice
Period	05/13/07 → 05/18/07

Cite this

Tentrier, A., Pointer, W. D., Sofu, T., Weber, D., Lo, S., & Splawski, A. (2008). Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies. In Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work" (pp. 2682-2691). (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"; Vol. 5).

Tentrier, Adrian ; Pointer, W. David ; Sofu, Tanju et al. / Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies. Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". 2008. pp. 2682-2691 (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work").

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title = "Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies",

abstract = "This paper presents recent advances in the development and integral validation of a two-phase Computational Fluid Dynamics (CFD) computer model (CFD-BWR) that allows the detailed analysis of the two-phase flow and heat transfer phenomena in Boiling Water Reactor (BWR) fuel bundles. The CFD-BWR code is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities.",

author = "Adrian Tentrier and Pointer, {W. David} and Tanju Sofu and David Weber and Simon Lo and Andrew Splawski",

year = "2008",

language = "English",

isbn = "9781604238716",

series = "Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, {"}The Nuclear Renaissance at Work{"}",

pages = "2682--2691",

booktitle = "Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, {"}The Nuclear Renaissance at Work{"}",

note = "Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, {"}The Nuclear Renaissance at Work{"} ; Conference date: 13-05-2007 Through 18-05-2007",

}

Tentrier, A, Pointer, WD, Sofu, T, Weber, D, Lo, S & Splawski, A 2008, Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies. in Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", vol. 5, pp. 2682-2691, Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", Nice, France, 05/13/07.

Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies. / Tentrier, Adrian; Pointer, W. David; Sofu, Tanju et al.
Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". 2008. p. 2682-2691 (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"; Vol. 5).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies

AU - Tentrier, Adrian

AU - Pointer, W. David

AU - Sofu, Tanju

AU - Weber, David

AU - Lo, Simon

AU - Splawski, Andrew

PY - 2008

Y1 - 2008

N2 - This paper presents recent advances in the development and integral validation of a two-phase Computational Fluid Dynamics (CFD) computer model (CFD-BWR) that allows the detailed analysis of the two-phase flow and heat transfer phenomena in Boiling Water Reactor (BWR) fuel bundles. The CFD-BWR code is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities.

AB - This paper presents recent advances in the development and integral validation of a two-phase Computational Fluid Dynamics (CFD) computer model (CFD-BWR) that allows the detailed analysis of the two-phase flow and heat transfer phenomena in Boiling Water Reactor (BWR) fuel bundles. The CFD-BWR code is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities.

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M3 - Conference contribution

AN - SCOPUS:52249116759

SN - 9781604238716

T3 - Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"

SP - 2682

EP - 2691

BT - Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"

T2 - Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"

Y2 - 13 May 2007 through 18 May 2007

ER -

Tentrier A, Pointer WD, Sofu T, Weber D, Lo S, Splawski A. Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies. In Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". 2008. p. 2682-2691. (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work").

Development and validation ofan extended two-phase computational fluid dynamics model for the analysis of boiling flow in reactor fuel assemblies

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