Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes
Joint Authors
Petrov, Victor
Manera, Annalisa
Kim, Taewan
Lo, Simon
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2012, Issue 2012 (31 Dec. 2012), pp.1-20, 20 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2012-10-11
Country of Publication
Egypt
No. of Pages
20
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
In order to assess the accuracy and validity of subchannel, system, and computational fluid dynamics codes, the Paul Scherrer Institut has participated in the OECD/NRC PSBT benchmark with the thermal-hydraulic system code TRACE5.0 developed by US NRC, the subchannel code FLICA4 developed by CEA, and the computational fluid dynamic code STAR-CD developed by CD-adapco.
The PSBT benchmark consists of a series of void distribution exercises and departure from nucleate boiling exercises.
The results reveal that the prediction by the subchannel code FLICA4 agrees with the experimental data reasonably well in both steady-state and transient conditions.
The analyses of single-subchannel experiments by means of the computational fluid dynamic code STAR-CD with the CD-adapco boiling model indicate that the prediction of the void fraction has no significant discrepancy from the experiments.
The analyses with TRACE point out the necessity to perform additional assessment of the subcooled boiling model and bulk condensation model of TRACE.
American Psychological Association (APA)
Kim, Taewan& Petrov, Victor& Manera, Annalisa& Lo, Simon. 2012. Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes. Science and Technology of Nuclear Installations،Vol. 2012, no. 2012, pp.1-20.
https://search.emarefa.net/detail/BIM-495418
Modern Language Association (MLA)
Kim, Taewan…[et al.]. Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes. Science and Technology of Nuclear Installations No. 2012 (2012), pp.1-20.
https://search.emarefa.net/detail/BIM-495418
American Medical Association (AMA)
Kim, Taewan& Petrov, Victor& Manera, Annalisa& Lo, Simon. Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes. Science and Technology of Nuclear Installations. 2012. Vol. 2012, no. 2012, pp.1-20.
https://search.emarefa.net/detail/BIM-495418
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-495418