Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT)
Joint Authors
Sánchez Espinoza, Victor Hugo
Imke, Uwe
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2012, Issue 2012 (31 Dec. 2012), pp.1-12, 12 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2012-08-28
Country of Publication
Egypt
No. of Pages
12
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
SUBCHANFLOW is a computer code to analyze thermal-hydraulic phenomena in the core of pressurized water reactors, boiling water reactors, and innovative reactors operated with gas or liquid metal as coolant.
As part of the ongoing assessment efforts, the code has been validated by using experimental data from the NUPEC PWR Subchannel and Bundle Tests (PSBT).
The database includes single-phase flow bundle outlet temperature distributions, steady state and transient void distributions and critical power measurements.
The performed validation work has demonstrated that the two-phase flow empirical knowledge base implemented in SUBCHANFLOW is appropriate to describe key mechanisms of the experimental investigations with acceptable accuracy.
American Psychological Association (APA)
Imke, Uwe& Sánchez Espinoza, Victor Hugo. 2012. Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT). Science and Technology of Nuclear Installations،Vol. 2012, no. 2012, pp.1-12.
https://search.emarefa.net/detail/BIM-473698
Modern Language Association (MLA)
Imke, Uwe& Sánchez Espinoza, Victor Hugo. Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT). Science and Technology of Nuclear Installations No. 2012 (2012), pp.1-12.
https://search.emarefa.net/detail/BIM-473698
American Medical Association (AMA)
Imke, Uwe& Sánchez Espinoza, Victor Hugo. Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT). Science and Technology of Nuclear Installations. 2012. Vol. 2012, no. 2012, pp.1-12.
https://search.emarefa.net/detail/BIM-473698
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-473698